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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217A2421999-09-30030 September 1999 Proposed Tech Specs Removing Parameters No Longer Applicable & Adding Tdf Value for Model 94 SGs in Place of Reactor Coolant Sys Flow ML20211Q8071999-09-0808 September 1999 Proposed Tech Specs & Associated Bases for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 ML20211Q2361999-09-0808 September 1999 Proposed Tech Specs 3/4.8.1,revised by Relocating 18-month Surveillance to Subject Sdg to Insps IAW Procedures Prepared in Conjunction with Mfg Recommendations to Section 3.8.1.1.4.8 of UFSAR ML20211G2281999-08-24024 August 1999 Proposed Tech Specs Pages,Relocating Cycle Specific Operating Parameters from TSs to Colr,Including Moving Location of Insert 6 from Page 6-21 to Page 6-22 of Administrative Control Section & Renumbering Methods List ML20211C0371999-08-18018 August 1999 Proposed Tech Specs 3.4.9.3 Re Cold Overpressure Mitigation Curve Associated with Replacement SGs ML20209G9351999-07-15015 July 1999 Proposed Tech Specs 3.7.1.6 Re Atmospheric Steam Relief Valves ML20209G4461999-07-13013 July 1999 Proposed Tech Specs,Modifying 3.6.3 Action B,Clarifyin Use of Check Valve with Flow Through Valve Secured as Means to Isolated Affected Containment Penetrations ML20209C1511999-07-0101 July 1999 Proposed Tech Specs Pages Re Amend to License NPF-80, Changing TSs 3.3.2 & 3.7.8 Allowing All Fuel Handling Bldg Exhaust Air Sys Components to Be Inoperable for Period of 8 Hours to Facilitate Repair of Train B Exhaust Booster Fan ML20209B5341999-06-24024 June 1999 Proposed Tech Specs Section 6.9.1.6.a,adding Min Measured RCS Flow,Which Lists Parameters Included in COLR ML20195E4701999-06-0707 June 1999 Proposed Tech Specs Pages Re Proposed Amend to Licenses NPF-76 & NPF-80,deleting Total Allowance,Sensor Error & Z Terms from ESFAS & RTS Instrumentation Trip Setpoint Tables of TS 2.2.1 & 3.3.2 ML20195E4211999-06-0707 June 1999 Proposed Tech Specs,Relocating cycle-specific RCS-related TS Parameter Limits to COLR ML20205S3511999-04-19019 April 1999 Proposed Tech Specs Bases Page 3/4 8-3 Removing Reference to Fast Transfer Capability That Is Inconsistent with STP Design Bases as Described in UFSAR Chapters 8.2 & 8.3 ML20205G8081999-03-30030 March 1999 Proposed Tech Specs,Relocating Section 3/4.3.3.4, Meteorological Instrumentation & Associated Bases Description to STP Trm,Per NUREG-1431 ML20204J9681999-03-22022 March 1999 Proposed Tech Specs Incorporating New TS for Atmospheric Steam Relief Valve Instrumentation & Revising TS 3.7.1.6 Re Atmospheric Steam Relief Valves ML20204D1581999-03-15015 March 1999 Proposed Tech Specs 3/4.7.9 for Snubbers to TRM ML20207L9441999-03-0909 March 1999 Proposed Tech Specs,Removing Ref to Independent Safety Engineering Group from Requirements ML20207D9651999-03-0202 March 1999 Proposed Tech Specs Change Clarifies Use of Check Valve with Flow Through Valve Secured as Means to Isolate Containment Penetration in TS 3.6.3 Action B ML20207C4721999-02-24024 February 1999 Proposed Tech Specs Bases 3/4.2.5,clarifying That Averaging of Only Three Channels Is Min Expected When Verifying DNB Parameter Compliance ML20202G6871999-01-26026 January 1999 Proposed Tech Spec Page 3/4 4-39,revising TS 4.4.10 for Alternate ISI of RCP Flywheels ML20199K5681999-01-20020 January 1999 Proposed Tech Specs Surveillance Requirement 4.7.1.2.1.a Re AFW Pump Performance Testing ML20198A2181998-12-10010 December 1998 Revised TS Pages,Adding Ref to TS Figure 2.1-2 to Bases Section 2.1.1 as Figure Provides DNBR Curves Appropriate to Alternate DNB Operating Criteria ML20198A1951998-12-0909 December 1998 Corrected TS Bases Pages B 3/4 8-15,-16 & -17,as Discussed During 981103 Telcon ML20196B8121998-11-23023 November 1998 Proposed Tech Specs Pages for Proposed Amends to Licenses NPF-76 & NPF-80,relocating 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 ML20155J9031998-11-0303 November 1998 Proposed Corrected Tech Specs Bases 3/4 9-3 Re Water level- Refueling Cavity & Storage Pools ML20155D5441998-10-29029 October 1998 Proposed Tech Specs Pages for Proposed Amend to Relocate Turbine Overspeed Protection TS 3/4.3.4 to TRM ML20155D5801998-10-29029 October 1998 Proposed Tech Specs Pages for Amends to Relocate Portion of TS Surveillance Requirement for DG Fuel Oil Storage Tank to TRM ML20155D5561998-10-29029 October 1998 Proposed Tech Specs Pages for Proposed Amends to Relocate Snubber TS 3/4.7.9 to TRM ML20154M1621998-10-12012 October 1998 Revised Tech Specs Bases Pages B3/4 8-14 Through -17 ML20154C0051998-09-30030 September 1998 Proposed Tech Specs Reflecting Replacement SG Tube Insp Surveillance Differences & Deleting Provision Allowing Use of F* Alternate Repair Criteria ML20154C5071998-09-30030 September 1998 Proposed Tech Specs Bases Page B 3/4 9-2,removing Wording Re 10% Value for Clad Gap Iodine Isotopics ML20154A4281998-09-28028 September 1998 Proposed Tech Specs Re Requirements Associated with Control Room & Fuel Handling Bldg Ventilation Sys ML20151T1621998-08-31031 August 1998 Proposed Tech Specs 3.4.9.3 Re Cold Overpressure Mitigation Curve Associated W/Replacement SGs ML20238F0841998-08-28028 August 1998 Proposed Tech Specs Section 4.0.5,excluding Specified Containment Isolation Valves from ISI & Testing Requirements as Stated in Section XI of ASME Boiler & Pressure Vessel Code ML20236T5141998-07-22022 July 1998 Proposed Tech Specs Re Replacement SG Water Level Setpoint Differences ML20236R1461998-07-15015 July 1998 Proposed Changes to Current Tech Specs Bases ML20236L6311998-07-0707 July 1998 Proposed Tech Specs,Reflecting Rev of Criticality Analyses & Rack Utilization Schemes for Regions 1 & 2 of Spent Fuel Racks as Described in STP UFSAR & TSs ML20236N0001998-07-0606 July 1998 Proposed Tech Specs,Relocating RCS Design Features from TS Section 5.4 to UFSAR ML20236K3481998-07-0606 July 1998 Proposed Tech Specs,Relocating 3/4.7.13 Requirements for Area Temp Monitoring Sys to Technical Requirements Manual ML20236M6381998-07-0606 July 1998 Proposed Tech Specs,Relocating 3/4.3.3.3 Requirements for Seismic Instrumentation to Technical Requirements Manual ML20247F3321998-05-0707 May 1998 Proposed Tech Specs Pages,Reflecting Replacement SG Reactor Coolant Flow Differences ML20217P1441998-04-0202 April 1998 Proposed Tech Specs 3.4.5 Re voltage-based Repair Criteria ML20202H9771998-02-16016 February 1998 Proposed Tech Specs Pages,Implementing 1-volt voltage-based Repair Criteria for SG Tube Support plate-to-tube Intersections ML20198C3741997-12-31031 December 1997 Proposed Tech Specs 2.1,2.2 & 3/4.2.5 for Alternate Operation W/Reduced Measured RCS Flow ML20197A7211997-12-17017 December 1997 Proposed Tech Specs Pages,Revising TS 4.6.2.1 to Extend Surveillance Interval of Containment Spray Sys Nozzle Air Flow Test from Five Years to Ten Years ML20199H2081997-11-20020 November 1997 Revised TS Bases Page B 3/4 4-15 ML20199A6101997-11-0505 November 1997 Proposed Tech Specs Pages,Updating TS Bases Section 3/4.4.9, to Reflect Results of Revised Analysis That Was Reviewed & Accepted by NRC as Part of License Amends 55 & 44.Analysis Results Not Incorporated Into TS Bases Due to Oversight ML20210T7401997-09-0404 September 1997 Proposed Tech Specs,Revising TS to Allow Use of Elbow Tap Differential Pressure Measurements Instead of Precision Heat Balance Measurements to Determine RCS Total Flow Rate ML20217M8351997-08-18018 August 1997 Proposed Tech Specs Incorporating Revs to TS 3.7.1.6, Atomospheric Steam Relief Valves, to Ensure Automatic Feature of SG Power Operated Relief Valve Remains Operable During Mode 1 & 2 ML20210L5801997-08-14014 August 1997 Proposed Tech Specs Allowing Tolerance of RCS Volume Provided in Specification 5.4.2 to Account for SG Tube Plugging ML20198F2211997-08-0505 August 1997 Proposed Tech Specs,Providing Suppl Info Re Amends to Licenses to Convert STP TS to Improved STS Format 1999-09-08
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARNOC-AE-000661, Rev 4 to Severe Weather Plan, Including Summary of Changes.With1999-10-0404 October 1999 Rev 4 to Severe Weather Plan, Including Summary of Changes.With ML20217A2421999-09-30030 September 1999 Proposed Tech Specs Removing Parameters No Longer Applicable & Adding Tdf Value for Model 94 SGs in Place of Reactor Coolant Sys Flow ML20211Q8071999-09-0808 September 1999 Proposed 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 ML20211Q2361999-09-0808 September 1999 Proposed Tech Specs 3/4.8.1,revised by Relocating 18-month Surveillance to Subject Sdg to Insps IAW Procedures Prepared in Conjunction with Mfg Recommendations to Section 3.8.1.1.4.8 of UFSAR ML20211G2281999-08-24024 August 1999 Proposed Tech Specs Pages,Relocating Cycle Specific Operating Parameters from TSs to Colr,Including Moving Location of Insert 6 from Page 6-21 to Page 6-22 of Administrative Control Section & Renumbering Methods List ML20211C0371999-08-18018 August 1999 Proposed Tech Specs 3.4.9.3 Re Cold Overpressure Mitigation Curve Associated with Replacement SGs ML20210J0481999-07-28028 July 1999 STP Unit 1,Cycle 9 Startup Testing Summary Rept ML20209G9351999-07-15015 July 1999 Proposed Tech Specs 3.7.1.6 Re Atmospheric Steam Relief Valves ML20209H3371999-07-13013 July 1999 Rev 0 to 0PGP02-ZA-0004, Station Performance Data Collection,Categorization & Reporting ML20209H2131999-07-13013 July 1999 Rev 4,revised Pages 29 & 30 of 102 to Procedure 0ERP01-ZV-IN01, Emergency Classification ML20209G4461999-07-13013 July 1999 Proposed Tech Specs,Modifying 3.6.3 Action B,Clarifyin Use of Check Valve with Flow Through Valve Secured as Means to Isolated Affected Containment Penetrations ML20209C1511999-07-0101 July 1999 Proposed Tech Specs Pages Re Amend to License NPF-80, Changing TSs 3.3.2 & 3.7.8 Allowing All Fuel Handling Bldg Exhaust Air Sys Components to Be Inoperable for Period of 8 Hours to Facilitate Repair of Train B Exhaust Booster Fan ML20209B5341999-06-24024 June 1999 Proposed Tech Specs Section 6.9.1.6.a,adding Min Measured RCS Flow,Which Lists Parameters Included in COLR ML20209H3151999-06-23023 June 1999 Rev 4 to 0PGP02-ZA-0003, Comprehensive Risk Management ML20195E4701999-06-0707 June 1999 Proposed Tech Specs Pages Re Proposed Amend to Licenses NPF-76 & NPF-80,deleting Total Allowance,Sensor Error & Z Terms from ESFAS & RTS Instrumentation Trip Setpoint Tables of TS 2.2.1 & 3.3.2 ML20195E4211999-06-0707 June 1999 Proposed Tech Specs,Relocating cycle-specific RCS-related TS Parameter Limits to COLR ML20209H3081999-06-0101 June 1999 Rev 3 to 0PGP04-ZA-0604, Probabilistic Risk Assessment Program ML20205S3511999-04-19019 April 1999 Proposed Tech Specs Bases Page 3/4 8-3 Removing Reference to Fast Transfer Capability That Is Inconsistent with STP Design Bases as Described in UFSAR Chapters 8.2 & 8.3 ML20205G8081999-03-30030 March 1999 Proposed Tech Specs,Relocating Section 3/4.3.3.4, Meteorological Instrumentation & Associated Bases Description to STP Trm,Per NUREG-1431 ML20204J9681999-03-22022 March 1999 Proposed Tech Specs Incorporating New TS for Atmospheric Steam Relief Valve Instrumentation & Revising TS 3.7.1.6 Re Atmospheric Steam Relief Valves ML20204D1581999-03-15015 March 1999 Proposed Tech Specs 3/4.7.9 for Snubbers to TRM ML20207L9441999-03-0909 March 1999 Proposed Tech Specs,Removing Ref to Independent Safety Engineering Group from Requirements ML20207D9651999-03-0202 March 1999 Proposed Tech Specs Change Clarifies Use of Check Valve with Flow Through Valve Secured as Means to Isolate Containment Penetration in TS 3.6.3 Action B ML20207C4721999-02-24024 February 1999 Proposed Tech Specs Bases 3/4.2.5,clarifying That Averaging of Only Three Channels Is Min Expected When Verifying DNB Parameter Compliance ML20202G6871999-01-26026 January 1999 Proposed Tech Spec Page 3/4 4-39,revising TS 4.4.10 for Alternate ISI of RCP Flywheels ML20199K5681999-01-20020 January 1999 Proposed Tech Specs Surveillance Requirement 4.7.1.2.1.a Re AFW Pump Performance Testing ML20198A2181998-12-10010 December 1998 Revised TS Pages,Adding Ref to TS Figure 2.1-2 to Bases Section 2.1.1 as Figure Provides DNBR Curves Appropriate to Alternate DNB Operating Criteria ML20198A1951998-12-0909 December 1998 Corrected TS Bases Pages B 3/4 8-15,-16 & -17,as Discussed During 981103 Telcon ML20196B8121998-11-23023 November 1998 Proposed Tech Specs Pages for Proposed Amends to Licenses NPF-76 & NPF-80,relocating 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 ML20155J9031998-11-0303 November 1998 Proposed Corrected Tech Specs Bases 3/4 9-3 Re Water level- Refueling Cavity & Storage Pools ML20155D5801998-10-29029 October 1998 Proposed Tech Specs Pages for Amends to Relocate Portion of TS Surveillance Requirement for DG Fuel Oil Storage Tank to TRM ML20155D5561998-10-29029 October 1998 Proposed Tech Specs Pages for Proposed Amends to Relocate Snubber TS 3/4.7.9 to TRM ML20155D5441998-10-29029 October 1998 Proposed Tech Specs Pages for Proposed Amend to Relocate Turbine Overspeed Protection TS 3/4.3.4 to TRM ML20154M1621998-10-12012 October 1998 Revised Tech Specs Bases Pages B3/4 8-14 Through -17 ML20154C0051998-09-30030 September 1998 Proposed Tech Specs Reflecting Replacement SG Tube Insp Surveillance Differences & Deleting Provision Allowing Use of F* Alternate Repair Criteria ML20154C5071998-09-30030 September 1998 Proposed Tech Specs Bases Page B 3/4 9-2,removing Wording Re 10% Value for Clad Gap Iodine Isotopics ML20154A4281998-09-28028 September 1998 Proposed Tech Specs Re Requirements Associated with Control Room & Fuel Handling Bldg Ventilation Sys ML20151T1621998-08-31031 August 1998 Proposed Tech Specs 3.4.9.3 Re Cold Overpressure Mitigation Curve Associated W/Replacement SGs ML20238F0841998-08-28028 August 1998 Proposed Tech Specs Section 4.0.5,excluding Specified Containment Isolation Valves from ISI & Testing Requirements as Stated in Section XI of ASME Boiler & Pressure Vessel Code ML20236T5141998-07-22022 July 1998 Proposed Tech Specs Re Replacement SG Water Level Setpoint Differences ML20236R1461998-07-15015 July 1998 Proposed Changes to Current Tech Specs Bases ML20236L6311998-07-0707 July 1998 Proposed Tech Specs,Reflecting Rev of Criticality Analyses & Rack Utilization Schemes for Regions 1 & 2 of Spent Fuel Racks as Described in STP UFSAR & TSs ML20236M6381998-07-0606 July 1998 Proposed Tech Specs,Relocating 3/4.3.3.3 Requirements for Seismic Instrumentation to Technical Requirements Manual ML20236N0001998-07-0606 July 1998 Proposed Tech Specs,Relocating RCS Design Features from TS Section 5.4 to UFSAR ML20236K3481998-07-0606 July 1998 Proposed Tech Specs,Relocating 3/4.7.13 Requirements for Area Temp Monitoring Sys to Technical Requirements Manual ML20247F3321998-05-0707 May 1998 Proposed Tech Specs Pages,Reflecting Replacement SG Reactor Coolant Flow Differences ML20217P1441998-04-0202 April 1998 Proposed Tech Specs 3.4.5 Re voltage-based Repair Criteria ML20202H9771998-02-16016 February 1998 Proposed Tech Specs Pages,Implementing 1-volt voltage-based Repair Criteria for SG Tube Support plate-to-tube Intersections ML20198C3741997-12-31031 December 1997 Proposed Tech Specs 2.1,2.2 & 3/4.2.5 for Alternate Operation W/Reduced Measured RCS Flow ML20197A7211997-12-17017 December 1997 Proposed Tech Specs Pages,Revising TS 4.6.2.1 to Extend Surveillance Interval of Containment Spray Sys Nozzle Air Flow Test from Five Years to Ten Years 1999-09-08
[Table view] |
Text
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NOC-AE-00G462 Page 1 of 14 1
ATTACHMENT 5 TECHNICAL SPECIFICATION PROPOSED NEW PAGE OR MARKED-UP PAGE CHANGES 4
PJ 28s!" M888?J e=J e
NOC-AE-000462 Page 2 of 14 PROPOSED CH ANGES TO TECHNICAL SPECIFICATIONS The Technical Specification and Technical Specification Bases pages listed below are proposed as new pages or as marked-up pages to identify the proposed changes associated with this. submittal and are enclosed in this attachment.
Pages:
Marked up index page vi Marked up index page xiii New page 3/4 3-85 New page 3/4 3-86 New page 3/4 3-87 Marked up page 3/4 7-10 Marked up page B 3/4 3-6 Marked up page B 3/4 7-3 o
0 INDEX LIMinNG CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE Meteorological Instmmentation.............................
3/4 3-58 TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATIGN......
3/4 3-59 TABLE 4.3-5 METEOROLOGICALMONITORINGINSTRUMENTATION SURVEILLANCE REQUIREMENTS.........................
3/4 3-60 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.........................
3/4366 Accident Monitoring Instrumentation.........................
3/4 3-67 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION............
3/4 3-68
{
TABLE 4.3-7 ACCIDENTMONITORINGINSTRUMENTATION SURVEILLANCE REQUIREMENTS.........................
3/43-73 Chemical Detection Systems..............................
3/4 3-75 TABLE 3.3-11 (This table number is not used)...........................
3/4 3-77 Radioactive Liquid Effluent Monitor instumentation DELETED TABLE 3.3-12 RADIOACTIVE LlOUlD EFFLUENT MONITORING INSTRUMENTATION DELETED TABLE 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DELETED Explosive Gas MonitorRn9 Instmmentation...................
3/4 3-79 TABLE 3.3-13 EXPLOStVE GAS MONITORING INSTRUMENTATION.......
3/4 3-80 TABLE 4.3-9 EXPLOSIVE GAS MONITbRING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.........................
3/4 3-82 3/4.3.4 (This specification number is not used)
{
hNSU*T D 1
SOUTH TEXAS -UNITS 1 & 2 vi Unit 1 - Amendment No. 47;99.101 Unit 2 - Amendment No. 06;06,88
i l
Proposed Insert to index Page vi 1
lasert 1 3/4.3.5 ATMOSPHERIC STEAM RELIEF VALVE I N STR U M ENTATION.............................................
3/4385 TABLE 3.3-14 ATMOSPHERIC STEAM RELIEF VALVE I NSTR UM ENTATION............................................
3/4386 I-l 1
l 1
l 1
4 1
INDEX BASES P.Agig SECTION 8 3/4 0-1 3/4.0 APPLICABILITY............................................
3/4.1 REACTIVITY CONTROL. SYSTEMS S3/41-1 3/4.1.1 BORATION CONTROL.....................................
B 3/412 3/4.1.2 BORATION SYSTEMS......................................
83/41-3 3/4.1.3 MOVABLE CONTROL ASSEMBLIES...........................
B 3/4 2-1 3/4.2 POWER DISTRIBUTION LIMITS................................
B 3/4 2-1 3/4.2.1 AXIAL FLUX DIFFERENCE..................................
3/4.22 and3/4.2.3 HEATFLUXHOTCHANNELFACTORand B 3/4 2-2 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR............
FIGURE B 3/42-1 TYPICAL INDICATED AXIAL FLUX DIFFERENCE VERSUS
,B 3/4 2-3 THERMAL POWER........................................
B 3/4 2-5 3/42.4 QUADRANT POWER TILT RATIO.............................
l B 3/4 2 5 3/4.2.5 DNB PARAMETERS.......................................
3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.32 REACTOR TRIP SYSTEM and ENGINEERED SAFETY B 3/4 3 1 FEATURES ACTUATION SYSTEM INSTRUMENTATION..........
B 3/4 3 3 3/4.3.3 MONITORING INSTRUMEUATION...........................
l 3/4.3.4 (This specification number is not used)
QtuoT "lj 3/4.4 REACTOR OOOLANT SYSTEM B 3/4 4-1 3/4.4.1 REACTOR COOUWT LOOPS AND COOLANT CIRCULATION......
8 3/4 4-1 3/4.42 SAFETY VALVES..........................................
B 3/4 4-2 3/4:4.3 PRESSURIZER...........................................
83/44-2 3/4.4.4 RELIEF VALVES..........................................
B 3/4 4-2 3/4.4.5 STEAM GENERATORS.....................................
B 3/4 4-3 3/4A.6 REACTOR COOLANT SYSTEM LEAKAGE......................
B 3/4 4-4 3/4.4.7 CHEMISTRY.............................................
B3/4.4-5 3/4A.8 SPECIFIC ACTIVITY.......................................
SOUTHTEXAS-UNITS 1 & 2 wil Unit 1 - Amendment No.- 101 Unit 2-Amendment No. 88
F j
Proposed Insert to index Page xiii 4
Insert 2 4
3/4.3.5 ATMOSPHERIC STEAM RELIEF VALVE l
INSTR UMENTATION............................................. B 3/4 3 6
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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 SURVEILLANCE REQUIREMENTS:
e 4.3.5.1 Perform a CHANNEL CAllBRATION on each atmospheric steam relief valve automatic actuation channel at a setpoint of 1225 psig at least once every 18 months.
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SOUTH TEXAS - UNITS 1 &2 3/4 3-85 I
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2BLE 3.3-14 (Continued)
)
TABLE NOTATIONS I
When steain 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 indicah.d steam generator pressure of 1225 psig.
1 ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channe;s less than the required number of channels, declare the affected valve (s) inoperable and I
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 j
next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
1 SOUTH TEXAS - UNITS 1 &2 3/4 3-87
PLANT SYSTEMS l
ATMOSPHERIC STEAM RELIEF VALVES l
LIMITING CONDITION FOR OPERATION
)
3.7.
6 At,least four atmospheric steam relief valves (and associated marida controls shall be OPERABLE.
APPLICABILITY: H0 DES 1, 2, 3, and 4.*
j i
ACTION:
a.
With one less than the required atmospheric steam relief valves OPERABLE, j
restora the required atmospheric steam relief valves 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 /> 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/
i RHR loops in operation for decay heat removal.
b.
With two less than the required atmospheric relief valves OPERABLE, re-store 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 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 folicwing 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 RESUIREMENTS 4.7.1.6 Each atmospheric relief valvd(iind associated manual control 11 be demonstrated OPERABLE prior to startup following anytreruelina shutdown _ orf T by verifying that all valves will open and l
COLD SHUTOOWN of 30 day @s or longe:
close f,ully by operatio f manual controls.
(o.wbo mb. %Q ko\\\\ow q ug nbhg sb%c
SOUTH TEXAS - UNITS 1 & 2 3/4 7-10 Unit 1 - Amendment No. 4 L
'}
INSTRUMENTATI'ON I
BASES 3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION (Continued) 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 falbre 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,U_ggil 3/4.3.3.10 DELETED j
3/4.3.3.11 EXPLOSIVE GAS MONITO' RING 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) 1 SOUTH TEXAS - UNITS 1 & 2 B 3/4 3-6 Unit 1 - Amendment No. 47,70.77,101 Unit 2 - Amendment No. 66;65;66,88
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Proposed insert to Technical Specification Bases Page B 3/4 3-6 Insert 3 3/4.3.5 ATMOSPHERIC STEAM RELIEF VALVE INSTRUMENTATION 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 an indicated setpoint of 1225 psig in Modes 1 and 2 because the safety analysis assumes automatic operation of the atmospheric steam relief valves 1
with an indicated 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 1225 psig setpoint, every 18 months.
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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, c g
3 /4.7.1.7 FEEDWATER ISOLATION VALVES hMN N 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 r.1se 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.
i 3 /4.7.2 S(EAM 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 m
to prevent brittle fracture.
3 /4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the Component Cooling Water System ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions. The redundant cooli.ng capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.
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-I related equipment during normal and ac.cident conditions. The redundant cooling cap.acity 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 tak'e'n out of service, it is important to assure that the tm' pact on plant risk of this and other equipment simultaneously taken out of service can a assessed. The Configuration Risk Management Program evaluates the impact SOUTH TEXAS - UNITS 1 & 2 B 3/4 7-3 Unit 1 - Amendment No. M,85
' Unit 2 - Amendment No. 9,72
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Proposed insert to Technical Specification Bases Page B 3/4 7-3, Section 3/4.7.1.6, Atmospheric Steam Relief Valves Insert 4 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 an indicated setpoint of 1225 psig in Modes 1 and 2 because the safety analysis assumes automatic operation of the atmospheric steam relief valves with an indicated setpoint of 1225 psig with uncertainties for mitigation of the small break LOCA. In order to support startup and shutdown activities
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(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, i
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