Corrected Amend 4 to License NPF-76,combining Units 1 & 2 Tech Specs to Add Requirement Which Places Positive Displacement Pump in lock-out Condition During Modes 4,5 & 6 to Prevent Cold OverpressurizationML20235M550 |
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South Texas |
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Issue date: |
02/17/1989 |
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NRC |
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Shared Package |
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ML20235M548 |
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NUDOCS 8902280311 |
Download: ML20235M550 (14) |
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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20235M5501989-02-17017 February 1989 Corrected Amend 4 to License NPF-76,combining Units 1 & 2 Tech Specs to Add Requirement Which Places Positive Displacement Pump in lock-out Condition During Modes 4,5 & 6 to Prevent Cold Overpressurization 1989-02-17
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARNOC-AE-000672, Suppl 1 to 990930 Application for Amend to Licenses NPF-60 & NPF-80,reflecting Replacement SG Rc Flow Differences.Encl Notarized Affidavit Page Replaces Affidavit Page Originally Transmitted in1999-10-20020 October 1999 Suppl 1 to 990930 Application for Amend to Licenses NPF-60 & NPF-80,reflecting Replacement SG Rc Flow Differences.Encl Notarized Affidavit Page Replaces Affidavit Page Originally Transmitted in NOC-AE-000651, Suppl to 980507 Application for Amends to Licenses NPF-76 & NPF-80,to Remove Parameters No Longer Applicable & Adding Tdf Value for Model 94 SGs in Place of Reactor Coolant Sys Flow. Ts,With Changes,To Demonstrate Intended Affect,Encl1999-09-30030 September 1999 Suppl to 980507 Application for Amends to Licenses NPF-76 & NPF-80,to Remove Parameters No Longer Applicable & Adding Tdf Value for Model 94 SGs in Place of Reactor Coolant Sys Flow. Ts,With Changes,To Demonstrate Intended Affect,Encl NOC-AE-000630, Application for Amends to Licenses NPF-76 & NPF-80,revising TS 3/4.8.1,by Relocating 18-month Surveillance to Subject Sdg to Insps IAW Procedures Prepared in Conjunction with Mfg Recommendations to Section 8.3.1.1.4.8 of UFSAR1999-09-0808 September 1999 Application for Amends to Licenses NPF-76 & NPF-80,revising TS 3/4.8.1,by Relocating 18-month Surveillance to Subject Sdg to Insps IAW Procedures Prepared in Conjunction with Mfg Recommendations to Section 8.3.1.1.4.8 of UFSAR NOC-AE-000629, Application for Amends to Licenses NPF-76 & NPF-80,revising Tech Specs & Associated Bases for Specification 3/4.8.1, AC Sources, to Eliminate Requirement for Accelerated Testing of Standby DGs & Associated NRC Reporting Requirements1999-09-0808 September 1999 Application for Amends to Licenses NPF-76 & NPF-80,revising Tech Specs & Associated Bases for Specification 3/4.8.1, AC Sources, to Eliminate Requirement for Accelerated Testing of Standby DGs & Associated NRC Reporting Requirements NOC-AE-000601, Suppl 2 to Application for Amends to Licenses NPF-76 & NPF-80,relocating Cycle Specific Operating Parameters from TSs to COLR1999-08-24024 August 1999 Suppl 2 to Application for Amends to Licenses NPF-76 & NPF-80,relocating Cycle Specific Operating Parameters from TSs to COLR NOC-AE-000521, Revised Application for Amends to Licenses NPF-76 & NPF-80,to Incorporate Administrative Word Change,Add Two Surveillances to Cold Overpressure Mitigation Sys (COMS) TS & Incorporate Two Functions Into Methodology1999-08-18018 August 1999 Revised Application for Amends to Licenses NPF-76 & NPF-80,to Incorporate Administrative Word Change,Add Two Surveillances to Cold Overpressure Mitigation Sys (COMS) TS & Incorporate Two Functions Into Methodology NOC-AE-000564, Suppl to 990322 Amends to Licenses NPF-76 & NPF-80,revising TS 3.7.1.6, Atmospheric Steam Relief Valves. Replacement Proposed TS Encl1999-07-15015 July 1999 Suppl to 990322 Amends to Licenses NPF-76 & NPF-80,revising TS 3.7.1.6, Atmospheric Steam Relief Valves. Replacement Proposed TS Encl NOC-AE-000551, Suppl to Proposed Amend to Licenses NPF-76 & NPF-80, Clarifying Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration in TS 3.6.3 Action B1999-07-13013 July 1999 Suppl to Proposed Amend to Licenses NPF-76 & NPF-80, Clarifying Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration in TS 3.6.3 Action B NOC-AE-000578, Application for Amend to License NPF-80 to Change TSs 3.3.2 & 3.7.8 to Allow All Fuel Handling Bldg Exhaust Air Sys Components to Be Inoperable for Period Not to Exceed 8 Hours to Facilitate Repair of Train B Exhaust Booster Fan1999-07-0101 July 1999 Application for Amend to License NPF-80 to Change TSs 3.3.2 & 3.7.8 to Allow All Fuel Handling Bldg Exhaust Air Sys Components to Be Inoperable for Period Not to Exceed 8 Hours to Facilitate Repair of Train B Exhaust Booster Fan NOC-AE-000569, Suppl to 990607 Application for Amends to Licenses NPF-56 & NPF-80,relocating cycle-specific Operating Parameters from TS to Colr.Suppl Adds Min Measured RCS Flow to TS Section 6.9.1.9.a Which Lists Parameters Included in COLR1999-06-24024 June 1999 Suppl to 990607 Application for Amends to Licenses NPF-56 & NPF-80,relocating cycle-specific Operating Parameters from TS to Colr.Suppl Adds Min Measured RCS Flow to TS Section 6.9.1.9.a Which Lists Parameters Included in COLR NOC-AE-000465, Application for Amends to Licenses NPF-76 & NPF-80,changing TS 2.2.1 & 3.3.2 & Associated Bases.Amend Would Delete Total Allowance,Sensor Error & Z Terms from ESFAS & Reactor Trip Sys Instrumentation Trip Setpoints Tables1999-06-0707 June 1999 Application for Amends to Licenses NPF-76 & NPF-80,changing TS 2.2.1 & 3.3.2 & Associated Bases.Amend Would Delete Total Allowance,Sensor Error & Z Terms from ESFAS & Reactor Trip Sys Instrumentation Trip Setpoints Tables NOC-AE-000471, Application for Amends to Licenses NPF-76 & NPF-80, Relocating cycle-specific RCS-related TS Parameter Limits to COLR1999-06-0707 June 1999 Application for Amends to Licenses NPF-76 & NPF-80, Relocating cycle-specific RCS-related TS Parameter Limits to COLR NOC-AE-000513, Suppl to Application for Amends to Licenses NPF-76 & NPF-80, Changing Tech Specs to Modify Requirements Associated with CR & Fuel Handling Bldg Ventilation Sys1999-04-22022 April 1999 Suppl to Application for Amends to Licenses NPF-76 & NPF-80, Changing Tech Specs to Modify Requirements Associated with CR & Fuel Handling Bldg Ventilation Sys NOC-AE-000367, Application for Amends to Licenses NPF-76 & NPF-80, Relocating TS 3/4.3.3.4, Meteorological Instrumentation & Associated Bases Description to STP Trm,Per NUREG-14311999-03-30030 March 1999 Application for Amends to Licenses NPF-76 & NPF-80, Relocating TS 3/4.3.3.4, Meteorological Instrumentation & Associated Bases Description to STP Trm,Per NUREG-1431 NOC-AE-000462, Application for Amends to Licenses NPF-76 & NPF-80, Incorporating New TS for Atmospheric Steam Relief Valve Instrumentation & Revising TS 3.7.1.6 Re Atmospheric Steam Relief Valves1999-03-22022 March 1999 Application for Amends to Licenses NPF-76 & NPF-80, Incorporating New TS for Atmospheric Steam Relief Valve Instrumentation & Revising TS 3.7.1.6 Re Atmospheric Steam Relief Valves NOC-AE-000396, Supplemental Application for Amends to Licenses NPF-76 & NPF-80,relocating TS 3/4.7.9 for Snubbers to TRM1999-03-15015 March 1999 Supplemental Application for Amends to Licenses NPF-76 & NPF-80,relocating TS 3/4.7.9 for Snubbers to TRM NOC-AE-000450, Application for Amends to Licenses NPF-76 & NPF-80,proposing to Clarify Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration in TS 3.6.3 Action B1999-03-0202 March 1999 Application for Amends to Licenses NPF-76 & NPF-80,proposing to Clarify Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration in TS 3.6.3 Action B NOC-AE-000241, Application for Amends to Licenses NPF-76 & NPF-80,proposing Rev to TS 4.4.10 for Alternate ISI of RCP Flywheels.Se,Nshc Determination & TS Page 3/4 4-39,included1999-01-26026 January 1999 Application for Amends to Licenses NPF-76 & NPF-80,proposing Rev to TS 4.4.10 for Alternate ISI of RCP Flywheels.Se,Nshc Determination & TS Page 3/4 4-39,included NOC-AE-000264, Application for Amends to Licenses NPF-76 & NPF-80,revising Descriptive Details of TS Surveillance Requirement 4.7.1.2.1.a Re Performance Testing of AFW Pumps to More Closely Adhere to NUREG-1431,ISTS for W Plants1999-01-20020 January 1999 Application for Amends to Licenses NPF-76 & NPF-80,revising Descriptive Details of TS Surveillance Requirement 4.7.1.2.1.a Re Performance Testing of AFW Pumps to More Closely Adhere to NUREG-1431,ISTS for W Plants NOC-AE-000335, Application for Amends to Licenses NPF-76 & NPF-80,to Relocate Descriptive Design Info from TS 3/4.7.1.1 (Table 3.7-2) Re Orifice Sizes for Main Steam Line Code Safety Valves,To Bases Section,Per NUREG-14311998-11-23023 November 1998 Application for Amends to Licenses NPF-76 & NPF-80,to Relocate Descriptive Design Info from TS 3/4.7.1.1 (Table 3.7-2) Re Orifice Sizes for Main Steam Line Code Safety Valves,To Bases Section,Per NUREG-1431 NOC-AE-000262, Application for Amends to Licenses NPF-76 & NPF-80, Respectively.Proposed Amends Would Relocate Snubber TS 3/4.7.9 to TRM1998-10-29029 October 1998 Application for Amends to Licenses NPF-76 & NPF-80, Respectively.Proposed Amends Would Relocate Snubber TS 3/4.7.9 to TRM NOC-AE-000261, Application for Amends to Licenses NPF-76 & NPF-80, Respectively.Proposed Amend Would Relocate Portions of TS Surveillance Requirement for DG Fuel Oil Storage Tank to TRM1998-10-29029 October 1998 Application for Amends to Licenses NPF-76 & NPF-80, Respectively.Proposed Amend Would Relocate Portions of TS Surveillance Requirement for DG Fuel Oil Storage Tank to TRM NOC-AE-000263, Application for Amends to Licenses NPF-76 & NPF-80, Respectively.Amend Would Relocate Turbine Overspeed Protective TS 3/4.3.4 to TRM1998-10-29029 October 1998 Application for Amends to Licenses NPF-76 & NPF-80, Respectively.Amend Would Relocate Turbine Overspeed Protective TS 3/4.3.4 to TRM NOC-AE-0140, Application for Amend to Licenses NPF-76 & NPF-80, Incorporating Revised Radiological Aspects of Operation at Reduced Feedwater Temp & Operation with Replacement SGs Into Encl Pages of STP Usfar1998-09-30030 September 1998 Application for Amend to Licenses NPF-76 & NPF-80, Incorporating Revised Radiological Aspects of Operation at Reduced Feedwater Temp & Operation with Replacement SGs Into Encl Pages of STP Usfar NOC-AE-0162, Application for Amends to Licenses NPF-76 & NPF-80, Reflecting Replacement SG Tube Insp Surveillance Differences & Deleting Provision Allowing Use of F* Alternate Repair Criteria1998-09-30030 September 1998 Application for Amends to Licenses NPF-76 & NPF-80, Reflecting Replacement SG Tube Insp Surveillance Differences & Deleting Provision Allowing Use of F* Alternate Repair Criteria NOC-AE-0231, Application for Amends to Licenses NPF-76 & NPF-80,allowing Use of Revised Methodology to Calculate Mass & Energy Release Following Postulated Large Loca.Proposed Changes to Units 1 & 2 UFSAR Attached1998-09-29029 September 1998 Application for Amends to Licenses NPF-76 & NPF-80,allowing Use of Revised Methodology to Calculate Mass & Energy Release Following Postulated Large Loca.Proposed Changes to Units 1 & 2 UFSAR Attached ML20154A4121998-09-28028 September 1998 Application for Amends to Licenses NPF-76 & NPF-80,changing TS to Mod Requirements Associated with Control Room & Fuel Handling Building Ventilation Sys.Proposed TS Pages Encl NOC-AE-00203, Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Changes to Reflect Revised Cold Overpressure Mitigation Curve Associated W/Replacement SGs Into TS 3.4.9.3, Overpressure Protection Sys1998-08-31031 August 1998 Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Changes to Reflect Revised Cold Overpressure Mitigation Curve Associated W/Replacement SGs Into TS 3.4.9.3, Overpressure Protection Sys NOC-AE-000280, Application for Exigent Amends to Licenses NPF-76 & NPF-80, Excluding Specified Containment Isolation Valves from ISI & Testing Requirements as Stated in Section XI of ASME Boiler & Pressure Vessel Code1998-08-28028 August 1998 Application for Exigent Amends to Licenses NPF-76 & NPF-80, Excluding Specified Containment Isolation Valves from ISI & Testing Requirements as Stated in Section XI of ASME Boiler & Pressure Vessel Code NOC-AE-00151, Application for Amends to Licenses NPF-76 & NPF-80, Addressing Operator Action to Be Used in Event of Small Break Loca.W/Affidavit,Safety Evaluation,No Significant Hazards Determination & Revised Updated FSAR1998-07-28028 July 1998 Application for Amends to Licenses NPF-76 & NPF-80, Addressing Operator Action to Be Used in Event of Small Break Loca.W/Affidavit,Safety Evaluation,No Significant Hazards Determination & Revised Updated FSAR NOC-AE-0163, Application for Amends to Licenses NPF-76 & NPF-80, Replacing SG Water Level Trip Setpoint Differences1998-07-22022 July 1998 Application for Amends to Licenses NPF-76 & NPF-80, Replacing SG Water Level Trip Setpoint Differences NOC-AE-000178, Application for Amends to Licenses NPF-76 & NPF-80, Reflecting Rev of Criticality Analyses & Rack Utilization Schemes for Regions 1 & 2 of Spent Fuel Racks as Described in STP UFSAR & TSs1998-07-0707 July 1998 Application for Amends to Licenses NPF-76 & NPF-80, Reflecting Rev of Criticality Analyses & Rack Utilization Schemes for Regions 1 & 2 of Spent Fuel Racks as Described in STP UFSAR & TSs ML20236K3441998-07-0606 July 1998 Application for Amends to Licenses NPF-76 & NPF-80,to Relocate TS 3/4.7.13 Requirements for Area Temperature Monitoring Sys to Technical Requirements Manual.Affidavit, SE & Determination of NSHC & marked-up TS Pages Encl NOC-AE-00020, Application for Amends to Licenses NPF-76 & NPF-80, Relocating TS 3/4.3.3.3 Requirements for Seismic Instrumentation to Technical Requirements Manual1998-07-0606 July 1998 Application for Amends to Licenses NPF-76 & NPF-80, Relocating TS 3/4.3.3.3 Requirements for Seismic Instrumentation to Technical Requirements Manual NOC-AE-00187, Application for Amends to Licenses NPF-76 & NPF-80, Relocating RCS Design Features from TS 5.4 to UFSAR1998-07-0606 July 1998 Application for Amends to Licenses NPF-76 & NPF-80, Relocating RCS Design Features from TS 5.4 to UFSAR ML20249B5411998-06-16016 June 1998 Application for Transfers of Control Re OLs NPF-76 & NPF-80, Requesting Consent of NRC to Indirect Transfers of Control of Interests That Will Occur Under Proposed Merger of Aep & Central & Southwest Corp NOC-AE-0080, Application for Amends to Licenses NPF-76 & NPF-80 to Reflect Replacement SG Reactor Coolant Flow Differences1998-05-0707 May 1998 Application for Amends to Licenses NPF-76 & NPF-80 to Reflect Replacement SG Reactor Coolant Flow Differences NOC-AE-000097, Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Tech Specs 3.4.5 Re 1-volt voltage-based Repair Criteria for SG Tube Support plate-to-tube Intersections,Per GL 95-051998-04-0202 April 1998 Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Tech Specs 3.4.5 Re 1-volt voltage-based Repair Criteria for SG Tube Support plate-to-tube Intersections,Per GL 95-05 NOC-AE-0074, Application for Amend to License NPF-80,incorporating Attached Amend to TS 3.4.5.Amend Will Implement 1-volt voltage-based Repair Criteria for SG Tube Support plate-to- Tube Intersections1998-02-16016 February 1998 Application for Amend to License NPF-80,incorporating Attached Amend to TS 3.4.5.Amend Will Implement 1-volt voltage-based Repair Criteria for SG Tube Support plate-to- Tube Intersections NOC-AE-000050, Application for Amends to Licenses NPF-76 & NPF-80,revising TS Sections 2.1,2.2 & 3/4.2.5 by Including Alternate Operating Criteria to Allow Continued Plant Operation W/ Reduced Measured RCS Flow Rate If Necessary1997-12-31031 December 1997 Application for Amends to Licenses NPF-76 & NPF-80,revising TS Sections 2.1,2.2 & 3/4.2.5 by Including Alternate Operating Criteria to Allow Continued Plant Operation W/ Reduced Measured RCS Flow Rate If Necessary NOC-AE-000042, Application for Amends to Licenses NPF-76 & NPF-80,revising TS 4.6.2.1 to Extend Surveillance Interval of Containment Spray Sys Nozzle Air Flow Test from Five Years to Ten Years. W/Ser & Proposed TS Changes1997-12-17017 December 1997 Application for Amends to Licenses NPF-76 & NPF-80,revising TS 4.6.2.1 to Extend Surveillance Interval of Containment Spray Sys Nozzle Air Flow Test from Five Years to Ten Years. W/Ser & Proposed TS Changes ST-HL-AE-5743, Application for Amends to Licenses NPF-76 & NPF-80,revising TS to Allow Elbow Tap Differential Pressure Measurements to Be Used Instead of Precision Heat Balance Measurements to Determine RCS Total Flow Rate1997-09-0404 September 1997 Application for Amends to Licenses NPF-76 & NPF-80,revising TS to Allow Elbow Tap Differential Pressure Measurements to Be Used Instead of Precision Heat Balance Measurements to Determine RCS Total Flow Rate ST-HL-AE-5689, Application for Amend to License NPF-76,incorporating Revs to TS 3.7.1.6, Atmospheric Steam Relief Valves, to Ensure Automatic Feature of SG Power Operated Relief Valve Remains Operable During Modes 1 & 21997-08-18018 August 1997 Application for Amend to License NPF-76,incorporating Revs to TS 3.7.1.6, Atmospheric Steam Relief Valves, to Ensure Automatic Feature of SG Power Operated Relief Valve Remains Operable During Modes 1 & 2 ST-HL-AE-5623, Application for Amends to Licenses NPF-76 & NPF-80,revising Allowed Tolerance of RCS Volume Provided in TS 5.4.2 to Account for SG Tube Plugging1997-08-14014 August 1997 Application for Amends to Licenses NPF-76 & NPF-80,revising Allowed Tolerance of RCS Volume Provided in TS 5.4.2 to Account for SG Tube Plugging ST-HL-AE-5675, Supplement to Application for Amends to Licenses NPF-76 & NPF-80,dtd 960604,requesting Conversion to Improved Std Tss, Per NUREG-14311997-07-22022 July 1997 Supplement to Application for Amends to Licenses NPF-76 & NPF-80,dtd 960604,requesting Conversion to Improved Std Tss, Per NUREG-1431 ST-HL-AE-5640, Submits Supplemental Info in Support of 960815 License Amend Request Re Removal of Surveillance Requirement 4.7.7.e.5. Supplement Provides Administrative Changes to Affected Page of TSs to Ensure Consistent Punctuation & Organization1997-05-29029 May 1997 Submits Supplemental Info in Support of 960815 License Amend Request Re Removal of Surveillance Requirement 4.7.7.e.5. Supplement Provides Administrative Changes to Affected Page of TSs to Ensure Consistent Punctuation & Organization ST-HL-AE-5622, Application for Amends to Licenses NPF-76 & NPF-80,revising Tech Specs 5.3.1, Fuel Assemblies & 6.9.1.6, COLR, to Allow Use of Alternate zirconium-based Fuel Cladding,Zirlo & Limited Substitution of Fuel Rods by ZIRLO Filter Rods1997-04-22022 April 1997 Application for Amends to Licenses NPF-76 & NPF-80,revising Tech Specs 5.3.1, Fuel Assemblies & 6.9.1.6, COLR, to Allow Use of Alternate zirconium-based Fuel Cladding,Zirlo & Limited Substitution of Fuel Rods by ZIRLO Filter Rods ST-HL-AE-5550, Application for Amends to Licenses NPF-76 & NPF-80,amending Tech Specs 3/4.4.5 & 3.4.6.2 to Allow Installation of Laser Welded Tube Sleeves as Alternative to Plugging Defective SG Tubes1997-03-17017 March 1997 Application for Amends to Licenses NPF-76 & NPF-80,amending Tech Specs 3/4.4.5 & 3.4.6.2 to Allow Installation of Laser Welded Tube Sleeves as Alternative to Plugging Defective SG Tubes ST-HL-AE-5547, Application for Amends to Licenses NPF-76 & NPF-80,revising TS 6.2.3 to Remove Reference to Independent Safety Engineering Group (Iseg) & Relocate All Details and Functions of Iseg to UFSAR1997-01-28028 January 1997 Application for Amends to Licenses NPF-76 & NPF-80,revising TS 6.2.3 to Remove Reference to Independent Safety Engineering Group (Iseg) & Relocate All Details and Functions of Iseg to UFSAR ST-HL-AE-5491, Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Proposed Change to TS 3.4.6.1, Reactor Coolant Leakage Detection Sys1996-10-23023 October 1996 Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Proposed Change to TS 3.4.6.1, Reactor Coolant Leakage Detection Sys 1999-09-08
[Table view] |
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- e 2.0 SdFETYLIMITSANDLIMITINGSAFETYSYSTEMSETTINGS _
2.1 SAFETY LIMITS REACTOR CORE 2.1.1 The combination of THERMAL POWER, pressurizer pressure, and the h'ghest operating Figure loop coolant temperature (T,y9) shall not exceed the limits shown in 2.1-1.
APPLICABILITY: MODES 1 and 2.
ACTION:
Whenever the point defined t'y the combination of the highest operating loop average temperature and THERMAL POWER t.as exceeded the appropriate pressurizer pressure line, be in HOT STANDBY within I hour, and comply with the require-ments of Specification 6.7.1.
REACTOR COOLANT SYSTEM PRES $URE 2.1.2 The Reactor Coolant System pressure shall not exceed 2735 psig.
APPLICABILITY: MODES 1, 2, 3, 4, and 5.
ACTION.
. MODES 1 and 2:
Whenever the Reactor Coolant System pressure has exceeded 2735 psig, be in HOT STANDBY with the Reactor Coolant System pressure within its limit within I hour, and comply with the requirements of Specification 6.7.1.
MODES 3, 4 and 5:
Whenever the Reactor Coolant System pressure has exceeded 2735 psig, reduce the Reactor Coolant System pressure to within its limit within 5 minutes, and comply with the regt.f rements of Specification 6.7.1.
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REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION SOUTH TEXAS - UNITS 1 & 2 2-2 Unit I Amendment No. 4 u
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REACTIVITY CONTROL SYSTEMS CONTROL R00 INSERTION LIMITS LIMITING CONDITION FOR OPiRATION 3.1.3.6 The control banks shall be limited in physical insertion as shown in Figure 3.1-3.
APPLICABILITY: MODES 1* and 2* **.
ACTION:
With the control banks itserted beyond the above insertion limits, except for surveillance, testing persuant to Specification 4.1.3.1.2:
a.
Restore the control banks to within the limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or
- b. l Reduce THERMAL POWER withir. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to less than or equal to that i
fraction of RATED THERMAL POWER which is allowed by the bank posi-tion using the above figure, or
- c. Se.,in at least' HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.3.6 The position of each control bank shall be determined to be within the insertion limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals !
when the rod insertion limit monitor.is inoperable, then verify the individual rod positions at Itast once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. .
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- See Special 1est Exceptions Specifications 3.10.2 and 3.10.3.
- With K,ff greater than or equal to 1.
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FIGURE 3.1-3 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER FOUR-LOOP OPERATION SOUTH' TEXAS - UNITS 1 & 2 3/4 1-24 Unit 1 Amendment No. 4 1
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FIGURE 3.2-1 AXIAL FLUX DIFFERENCE LIMITS A5 A FUNCTION OF RATED THERMAL POWER l
S0llTH TEXAS - UNITS 1 & 2 3/4 2-4 Unit 1 Amendment No. 4
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d ELECTRICAL POWER SYSTEMS A.C. SOURCES .
SHUTDOWN LIMiliNG CONDITION FOR OPERATION 3.8.1.2 As a minious, the following A.C. electrical power sources shall be OPERABLE:
- a. One circuit between the offsite transmission network and the Onsite I Class IE Distribution System, and f
- b. Two' standby diesel generators each with a separate fuel tank contain-ing a minimum volume of 60,500 gallons of fuel.
APPLICABILITY: MODES 5 and 6.
ACTION:
With less than the above minimum required A.C. electrical power sources OPERABLE, imediately suspend all operations involving CORE ALTERATIONS, posi-tive reactivity changes, movement of irradiated fuel, or crane operation with loads over the spent fuel pool, and within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, depressurize and vent the Reactor Coolant System through a greater than or equal to 2.0 square inch vent.
- In addition, when in MODE 5 with the reactor coolant loops not filled, or in MODE 6 with the water level less than 23 feet above the reactor vessel flange, imediately initiate corrective action to restore the required sources to OPERABLE status as soon as possible. !
SURVEILLANCE REQUIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be dee,onstrated OPERABLE by the performance of each of the requirements of Specifications 4.8.1.1.1, 4.8.1.1.2 (except for Specification 4.8.1.1.2a.3)), and 4.8.1.1.3.
i SOUTH TEXAS - UNITS 1 & 2 3/4 8-9 1
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A ELECTRICAL POWER SYSTEMS. ,
3/4.8.2 0.C. SOURCES OPERATING I LIMITING CONDITION FOR OPERATION 3.8.2.1 As a minimum, the following D.C. electrical sources shall be OPERABLE:
- a. Channel I 125-volt 84ttery Bank EIA11 (Unit 1), E2A11 (Unit 2) and its two associated chargers, (
- b. Channel II 125-volt Battery Bank E1D11 (Unit 1), E2D11 (Unit 2) and its associated full capacity charger, (
- c. Channel III 125-volt Battery Bank E1811 (Unit 1), E2811 (Unit 2) and l its associated full capacity charger, and ,
- d. Channel IV 125-volt Battery Bank E1C11 (Unit 1), E2C11 (Unit 2) and its two associated chargers. l APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
a.* With one of the required battery banks, and/or one of the required chargers for the Channels II or III inoperable, restore the inoperable battery bank and/or charger to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT STANDBY within the next.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- b. With only one charger on Channel I or IV OPERABLE, demonstrate the OPERABILITY of-the associated battery bank by performing Surveillance Requirement 4.8.2.1.a.1) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. If any Category A limit in Table 4.8-2 is not met, declare -
the battery inoperable. Restore the inoperable charger to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 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 /> and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
7
- S11RVEILLAN.CE REQUIREMENTS 4.8.2.1 Each 175-volt battery bank and charger shall be demonstrated OPERABLE:
- a. At least once per 7 days by verifying that:
- 1) The parameters in Table 4.8-2 meet the Category A limits, and
- 2) The total battery terminal voltage is greater than or equa) to 129 volts on float charge.
SOUTH TEXAS - UNITS 1 & 2 3/4 8-10 Unit 1 Amendment No. 4
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- __ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
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4-ELECTRICAL POWER SYSTEMS D.C. SOURCES SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.2.2 As a minimum, Channel I 125-volt Battery Bank EIA11 (Unit 1), E2A11 (Unit 2), and Channel IV 125-volt battery bank E1C11 (Unit 1), E2C11 (Unit 2),
and their two associated chargers shall be OPERABLE.
APPLICABILITY: MODES 5 and 6.
ACTION:
With the required battery banks and/or charger (s) inoperable, immediately sus-pend all operations involving CORE ALTERATIONS, positive reactivity changes, or movement of irradiated fuel; initiate corrective action to restore the required battery banks and/or chargers to OPERABLE status as soon as possible, and within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, depressurize and vent the Reactor Coolant System through a 2.0 square inch vent. ..
SURVEILLANCE REQUIREMENTS 4.8.2.2 The above required 125-volt batte banks and chargers shall be 4 demonstrated OPERABLE in accordance with S cification 4.8.2.1.
l SOUTH TEXAS - UNITS 1 & 2 3/4 8-13 Unit 1 Amendment No. 4 i
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ELECTRICAL POWER' SYSTEMS 3/4.8.3 ONSITE POWER DISTRIBUTION OPERATIE LIMITING CONDITION FOR OPERATION 3.8.3.1 The following electrical busses shall be energized in the specified manner:-
- a. Train A A.C.' ESF Busses consisting of:
- 1) 4160-Volt ESF Bus # E1A (Unit 1), E2A (Unit 2), and
- 2) 480-Volt ESF Busses # EIA1 and EIA2 (Unit 1), E2A1 and E2A2 (Unit 2) from respective load center transformers.
- b. Train B' A.C. ESF Busses consisting of:
- 1) 4160-Volt ESF Bus # ElB (Unit 1), E2B (Unit 2), and
- 2) 480-Volt ESF Busses # E181 and E182 (Unit 1), E281 and E282 (Unit 2) from respective load center transformers.
- c. Train C A.C. ESF Busses consisting of:
- 1) 4160-Volt ESF Bus # Elc (Unit 1), E2C (Unit 2), and
- 2) 480-Volt ESF Busses # E1C1 and E1C2 (Unit 1), E2C1 and E2C2 (Unit 2) from respective load center transformers.
- d. 120-Volt A.C. Vital Distribution Panels DP1201 and D9001 energized from their associated inverters connected to D.C. Bus # EIA11*
(Unit 1), E2A11* (Unit 2), '
- e. 120-Volt A.C. Vital Distribution Panel DP1202 energized from its associated inverter connected to D.C. Bus # E1011* (Unit 1), E2D11*
(Unit 2),
- f. 120-Volt A.C. Vital Distribution Panel DP1203 energized from its associated inverter connected to D.C. Bus # E1811* (Unit 1), E2B11*
(Unit 2),
g.
120-Volta.C.VitalDistributior,PanelsDP1204andDP002 energized from their associated inverters connected to D.C. Bus # E1C11 (Unit 1), E2C11* (Unit 2), ;
'O' *
- h. 125-Volt D.C. Bus EIA11 (Unit 1) E2A11 (Unit 2) energized from Battery Bank E1A11 (Unit 1), E2A11 (Unit 2),
- 1. 125-Volt D.C. Bus E1D11 (UnP. 1) E2D11 (Unit 2) energized from Battery Bank E1011 (Unit 1), E2D11 (Unit 2),
- j. 125-Volt D.C. Bus E1811 (Unit 1) E2B11 (Unit 2) energized from Battery Bank E1811 (Unit 1), E2811 (Unit 2), and k.
L 125-Volt D.C. Bus E1C11 (Unit 1) E2C11 (Unit 2) energized from )
Battery Bank E1C11 (Unit 1), E2C11 (Unit 2). -
i
- The inverter (s) associated with one channel may be disconnected from its D.C.
- bus for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> as necessary, for the purpose of performing an equaliz-ing charge on its associated battery bank provided: (1) its vital distribu-tion panels are energized, and (2) the vital distribution panels associated 3 with the other battery banks are energized from their associated inverters and connected to their associated D.C. busses.
SOUTH TEXAS - UNITS 1 & 2 3/4 8-14 Unit 1 Amendment No. 4 .
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5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA 5.1.I' The Exclusion sea shall be as shown in Figure 5.1-1.
LOW POPULATION ZONE-5.1.2 The Low Population Zone shall be as shown in Figure 5.1-2.
MAP DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS 5.1.3 Information regarding radioactive gaseous and liquid eff1 tents, which will. allow identification of structures and release points as well as defini-tion of UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to MEMBERS OF THE PUBLIC, shall be as shown in Figures 5.1-3 and 5.1-4.
4 The definition of UNRESTRICTED AREA used in implementing these Technical Speci-fications has been expanded over that in 10 CFR 20.3(a)(17). The UNRESTRICTED AREA boundary may coincide with the Exclusion (fenced) Area boundary, as defined in 10 CFR 100.3(a), but the UNRESTRICTED AREA does not include areas over water bodies. The concept of UNRESTRICTED AREAS, established at or beyond the SITE BOUNDAP.Y, is utilized in the Limiting Conditions for Operation to keep levels of radioactive materials in liquid and gaseous effluents as low as is reason-ably achievable, pursuant to 10 CFR 50.35a.
5.2 CONTAINMENT CONFIGURATION 5.2.1 The reactor containment building is a steel-lined, reinforced concrete building of cylindrical shape, with a dome roof and having the following design features:
- a. Nominal inside diameter = 150 feet.
- b. Nominal inside height = 241.25 feet.
- - c. Minimum thickness of concrete walls = 4 feet.
- d. Minimum thickness of concrete roof = 3 feet.
- e. Minimum thickness of concrete floor sat = 18 feet.
- f. Nominal thickness of steel liner = 3/8 inches.
- g. Net free volume = 3.56 x los cubic feet.
DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of 56.5 psig and a temperature of 286'F.
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