ML20211F348
| ML20211F348 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 08/19/1999 |
| From: | Gramm R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20211F353 | List: |
| References | |
| NUDOCS 9908300309 | |
| Download: ML20211F348 (15) | |
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t UNITED STATES ye j Y NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.c. :9555e1 do STP NUCLEAR OPERATING COMPANY DOCKET NO. 50-498 SOUTH TEXAS PROJECT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE j
Amendment No.114 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 the City of Austin, Texas (COA) (the licensees), dated March 22, 1999, as supplemented by letter dated July 1C,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; j
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 regulptions 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 the City of Austin, Texas, and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.
9908300309 990819 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 ;o this license amer.dment and Paragraph 2.C.(2) of Facility Operating License No. NPF-76 is hereby amended to read as follows:
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2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.114, 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.
I 3.
The license amendment is effective as of its date of issuance and shall be implemented f
within 30 days from the date of issuance.
4 FOR THE NUCLEAR REGULATORY COMMISSION ha A A1-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: August 19, 1999 P
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UNITED STtTi S
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.j NUCLEAR REGULATORY COMMISSION
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WASHINGTON. D.C. 20555-0001
,o STP NUCLEAR OPERATING COMPANY DOCKET NO. 50-499 SOUTH TEXAS PROJECT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.102 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 the City of Austin, Texas (COA) (the licensees), dated March 22, 1999, as supplemented by letter dated July 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 the City of Austin, Texas, and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.
s 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 Specifications i
The Technical Specifications contained in Appendix A, as revised through Amendment No.102, 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 from the date 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: ' August 19, 1999 l
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ATTACHMENT TO LICENSE AMENDMENT NOS.114 AND 102 FACILITY OPERATING LICENSE NOS. NPF-76 AND NPF-80 DOCKET NOS. 50-493 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 vi vi xiii xiii 3/4 3-85 3/4 3-86 3/4 3-87 3/4 7-9 3/4 7-9*
3/4 7-10 3/4 7-10 B 3/4 3-6 B 3/4 3-6 B 3/4 7-3 9 3/4 7-3 B 3/4 7-3a
.B 3/4 7-3a I
- Overleaf page provided to maintain document completeness. No changes on these page.
3
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE Remote Shutdown System...............................
3/4 3-61 TABLE 3.3-9 REMOTE SHUTDOWN SYSTEM.........................
3/4 3-62 TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION 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 INSTRUMENTATION SURVEILLANCE REQUIREMENTS.................
3/4 3-73 Chemical Detection Systems..............................
3/4 3-75 TABLE 1.3-11 (This table number is not used) 3/4 3-77 Radioactive Liquid Effluent Monitor Instrumentation DELETED TABLE 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION DELETED TABLE 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DELETED Explosive Gas Monitoring Instrumentation....................
3/4 3-79 TABLE 3.3-13 ' EXPLOSIVE GAS MONITORING INSTRUMENTATION 3/4 3-80 TABLE 4.3-9 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.........................
3/4 3-82 3/4.3.4 (This specification number is not used) 3/4.3.5 ATMOSPHERIC STEAM RELIEF VALVE IN STR U M ENTATION..................................
3/4 3-85 TABL2 3.3-14 ATMOSPHERIC STEAM RELIEF VALVE I N STR U M ENTATI ON..............................
3/4 3-86 1
i SOUTH TEXAS - UNITS 1 & 2 vi Unit 1 - Amendment No. +M.114 Unit 2 - Amendment No. 98, 102
l i.
INDEX BASES SECTION PAGE 3/4.0 A P PLI CA BI LITY......................................
B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 B O R ATI O N C ONTR O L...................................
83/41-1 3/4.1.2 BO RATIO N S YSTEM S......................................
B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES.........................
B 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS..........
B 3/4 2-1 3/4.2.1 AXI AL FLUX DIFFERENCE................................
B 3/4 2-1 3/4.2.2 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 AXlAL FLUX DIFFERENCE VERSUS TH ERMAL POW ER...........................
B 3/4 2-3 3/4.2.4 QUADRANT POWER TILT RATIO............................
B 3/4 2-5 3/4.2.5 DNB PARAMETERS......................
B 3/4 2-5 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 specnication number is not used) 3/4.3.5 ATMOSPHERIC STEAM RELIEF VALVE INSTRUMENTATION...
B 3/4 3-6 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION..
B 3/4 4-1 3/4.4.2 S AF ETY VALV E S..........................................
B 3/4 4-1 3/4.4.3 PR ESSU RIZER...........................................
B 3/4 4-2 3/4.4.4 R E LI E F VALVE S...............................
B 3/4 4-2 3/4.4.5 STEAM G EN E RATO R S.....................................
B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE...................
B 3/4 4-3 l
3/4.4.7 C H E M I ST R Y...........................................
B 3/4 4-4
'3/4.4.8 SPECIFIC ACTIVITY.....................
8 3/4 4-5 SOUTH TEXAS - UNITS 1 & 2 xiii Unit 1 - Amendment No. Mt,114 Unit 2 - Amendment No. 66,102
INSTRUMENTATION 3/4.3.5 ATMOSPHERIC STEAM RELIEF VALVE INSTRUMENTATION LIMITING CONDITION FOR OPERATION:
3.3.5.1 The atmospheric steam relief valve instrumentation shown in Table 3.3-14 shall be OPERABLE.
APPLICABILITY: As shown in Table 3.3-14 ACTION: As shown in Table 3.3-14 SURVEILLANCE REOUIREMENTS:
4.3.5.1 Perform a CHANNEL CHECK on each atmospheric steam relief valve automatic actuation channel at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.3.5.2 Perform a CHANNEL CAllBRATION on each atmospheric steam relief valve automatic actuation channel at a nominal setpoint of 1225 psig 7 psi at least once every 18 months.
4.3.5.3 Perform an ANALOG CHANNEL OPERATIONAL TEST on each atmospheric steam relief valve automatic actuation channel at a nominal setpoint of 1225 psig _7 psi at least once every 18 months.
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TABLE 3.314 (Continued)
TABLE NOTATIONS When steam generators are being used for decay heat removal.
- Atmospheric steam relief valve (s) may be in manual operation and open to maintain secondary side pressure at or below an indicated steam generator pressure of 1225 psig.
ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels less than the required number of channels, declare the affected valve (s) inoperable and apply Technical Specification 3.7.1.6.
ACTION 2 - a.
With one less than the required number of OPERABLE channels, restore the inoperable channel to OPERABLE status within 7 days; or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With two less than the required number of OPERABLE channels, restore at least three channels to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SOUTH TEXAS - UNITS 1 &2 3/4 3-87 thit 1 - /muhent tb.114 thit 2 - hextent No.102
PLANT SYSTEMS MAIN STEAM LINE ISOLATION VALVES
. LIMITING CONDITION FOR OPERATION 3.7.1.5 Each main steam line isolation valve (MSIV) shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.
ACTION:
MODE 1:
With one MSIV inoperable but open, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
MODES 2 and 3:
With one MSIV inoperable, subsequent operation in MODE 2 or 3 may proceed
.provided the isolation valve is maintained closed.
Otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE RE0VIREMENTS 4.7.1.5 Each MSIV shall be demonstrated OPERABLE by verifying full closure within 5 seconds when tested pursuant to Specification 4.0.5.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.
SOUTH TEXAS - UNITS 1 & 2 3/4 7-9
PLANT SYSTEMS ATMOSPHERIC STEAM RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.7.1.6 At least four atmospheric steam relief valves shall be OPERABLE.
1 APPLICABILITY: MODES 1,2,3, and 4.*
ACTION:
With one less than the required atmospheric steam relief valves OPERABLE, restore the a.
required atmospheric steam relief valves to OPERABLE status within 7 days; or be in at least HOT STANDBY with the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and place the required RCS/RHR loops in operation for decay heat removal.
b.
With two less than the required atmospheric relief valves OPERABLE, restore at least three atmospheric relief valves to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY with the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and place the required RCS/RHR loops in operation for decay heat removal.
SURVEILLANCE REQUIREMENTS 4.7.1.6 Each atmospheric relief valve shall be demonstrated OPERABLE prior to startup following any COLD SHUTDOWN of 30 days or longer or following any refueling shutdown, by verifying that all valves will open and close fully by operation of automatic and manual controls.
I i
- When steam generators are being used for decay heat removal.
SOUTH TEXAS - UNITS 1 & 2 3/4 7-10 Unit 1 - Amendment No. 4,114 Unit 2 - Amendment No.102 i
INSTRUMENTATION BASES 3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION (Continued) quadrant. The unit specific response to item II.F.2 of NUREG-0737 furtner 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 four operable thermocouples in any quadrant (e.g., A Train has four operable thermocouples in one of the quadrants, and C Train has four operable thermocouples in the same quadrant or any other quadrant.). This preserves the ability to withstand a single failure.
3/4.3.3.7 (Not Used) 3/4.3.3.8 (Not Used) 3/4.3.3.9 (Not Used) 3/4.3.3.10 DELETED 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 SYSTEM.
3/4.3.4 (Not Used) 3/4.3.5 ATMOSPHERIC STEAM RELIEF VALVE INSTRUMENTATION The atmospheric steam relief valve manual controls must be OPERABLE in Modes 1,2, i
3, and 4 (Mode 4 when steam generators are being used for decay heat removal) to allow operator action needed for decay heat removal and safe cooldown in accordance with Branch Technical Position RSB 5-1.
The atmospheric steam relief valve automatic controls must be OPERABLE with a nominal setpoint of 1225 psig in Modes 1 and 2 because the safety analysis assumes i
automatic operation of the atmospheric steam relief valves with a nominal setpoint of 1225 psig with uncertainties for mitigation of the small break LOCA. In order to support startup and shutdown activities (including post-refueling low power physics testing), the atmospheric steam relief valves may be operated in manual and open in Mode 2 to maintain the secondary side pressure at or below an indicated steam generator pressure of 1225 psig.
The uncertainties in the safety analysis assume a channel calibration on each atmospheric steam relief valve automatic actuation channel, including verification of automatic actuation at the nominal 1225 psig setpoint, every 18 months.
SOUTH TEXAS - UNITS 1 & 2 B 3/4 3-6 Unit 1 - Amendment No. Wt,114 Unit 2 - Amendment No. 66, 102 4
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PLANT SYSTEMS BASES 3/4.7.1.6 ATMOSPHERIC STEAM RELIEF VALVES The atmospheric steam relief valves are required for decay heat removal and safe cooldown in accordance with Branch Technical Position RSB 5-1. In the safety analyses, operation of the atmospheric steam relief valves is assumed in accident analyses for mitigation of small break LOCA, feedwater line break, loss of normal feedwater and loss-of-offsite power.
The atmospheric steam relief valve manual controls must be OPERABLE in Modes 1,2, 3, and 4 (Mode 4 when steam generators are being used for decay heat removal) to allow operator action needed for decay heat removal and safe cooldown in accordance with Branch Technical Position RSB 5-1.
The atmospheric steam relief valve automatic controls must be OPERABLE with a nominal setpoint of 1225 psig in Modes 1 and 2 because the safety analysis assumes automatic operation of the atmosphenc steam relief valves with a nominal setpoint of 1225 psig with uncertainties for mitigation of the small break LOCA. In order to support startup and shutdown activities (including post-refueling low power physics testing), the atmospheric steam relief valves may be operated in manual and open in Mode 2 to maintain the secondary side pressure at or below an indicated steam generator pressure of 1225 psig.
The verification that all atmospheric steam relief valves will open and close fully prior to startup following a COLD SHUTDOWN of 30 days or longer, or following any refueling shutdown, allows for operation using either manual or automatic controls.
3/4.7.1.7 FEEDWATER ISOLATION VALVES The OPERABILITY of the feedwater isolation valves ensures that no more than one steam generator will blow down in the event of a steam line or feedwater line rupture. The operability of the Feedwater Isolation valves will minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and limit the pressure rise within containment. The OPERABILITY of the feedwater isolation valves within the closure times of the Surveillance Requirements are consistent with the assumptions used in the safety analysis.
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure-induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 70 F and 200 psig are based on a steam generator RT., of 10*F and are sufficient to prevent brittle fracture.
3/4.7.3 COMPONENT COOLING WATER SYSTEM L
l The OPERABILITY of the Component Cooling Water System ensures that sufficient I
cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.
SOUTH TEXAS - UNITS 1 & 2 B 3/4 7-3 Unit 1 - Amendment No. 65,114 Unit 2 - Amendment No. 72, 102
PLANT SYSTEMS BASES I
3/4.7.4 ESSENTIAL COOLING WATER SYSTEM The OPERABILITY of the Essential Cooling Water System ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.
When a risk-important system or component (for example Essential Cooling Water)is taken out of service, it is important to assure that the impact on plant risk of this and other equipment simultaneously taken out of service can be assessed. The Configuration Risk Management Program evaluates the impact on plant risk of equipment out of service. A brief description of the Configuration Risk Management Program is in Section 6.8.3 (administration section) of the Technical Specification.
3/4.7.5 ULTIMATE HEAT SINK The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available either: (1) provide normal cooldown of the facility or (2) mitigate the effects of accident conditions within acceptable limits.
4 I
SOUTH TEXAS - UNITS 1 & 2 B 3/4 7-3a Unit 1 - Amendment No. 65,114 Unit 2 - Amendment No. 72,102