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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MONTHYEARML20217A2421999-09-30030 September 1999 Proposed Tech Specs Removing Parameters No Longer Applicable & Adding Tdf Value for Model 94 SGs in Place of Reactor Coolant Sys Flow ML20211Q2361999-09-0808 September 1999 Proposed Tech Specs 3/4.8.1,revised by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 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 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 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 ML20155D5561998-10-29029 October 1998 Proposed Tech Specs Pages for Proposed Amends to Relocate Snubber TS 3/4.7.9 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 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 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 ML20154C0051998-09-30030 September 1998 Proposed Tech Specs Reflecting Replacement SG Tube Insp Surveillance Differences & Deleting Provision Allowing Use of F* Alternate Repair Criteria 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 ML20236M6381998-07-0606 July 1998 Proposed Tech Specs,Relocating 3/4.3.3.3 Requirements for Seismic Instrumentation to Technical Requirements Manual 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 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 ML20148G1531997-05-29029 May 1997 Proposed Tech Specs Providing Administrative Changes to Affected Page Re Removal of Surveillance Requirement 4.7.7.e.5 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 ML20209H2131999-07-13013 July 1999 Rev 4,revised Pages 29 & 30 of 102 to Procedure 0ERP01-ZV-IN01, Emergency Classification ML20209H3371999-07-13013 July 1999 Rev 0 to 0PGP02-ZA-0004, Station Performance Data Collection,Categorization & Reporting 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 ML20195E4211999-06-0707 June 1999 Proposed Tech Specs,Relocating cycle-specific RCS-related TS Parameter Limits to 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 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 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 ML20155D5561998-10-29029 October 1998 Proposed Tech Specs Pages for Proposed Amends to Relocate Snubber TS 3/4.7.9 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 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 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 ML20236N0001998-07-0606 July 1998 Proposed Tech Specs,Relocating RCS Design Features from TS Section 5.4 to UFSAR 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 1999-09-08
[Table view] |
Text
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/WCCUM ~1 E T ill- AE-3M PAGE_.1._.0F S _ . . -
INDt'X LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION .P. AGE FIGURE 3.4-3 REACTOR COOLANT SYSTEM C00LDOWN LIMITATIONS -
APPLICABLE UP TO 32 EFPY................................. 3/4 4-33 '
TABLE 4.4-544E+C-TOR VES$[L liATE"d AL 5""VTliiANCC- PROGRA!!
ncRAWAL Scn[ m t .................................... 3/4 4-34 (Tw+
w osd) w % g - @ Pressurizer............................................., 3/4 4-35 l Overpressure Protection Systems.......................... 3/4 4-36 FIGURE 3.4-4 NOMINAL MAXIMUM ALLOWABLE PORV SETPOINT FOR THE COLD OVERPRESSURE SYSTEM ........................ 3/4 4-38 3/4.4.10 STRUCTURAL INTEGRITY..................................... 3/4 4-39 3/4.4.11 RF. ACTOR VESSEL HEAD VENTS........ ........... ........... 3/4 4-40 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS ............................................ 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T F.... 3/4 5-3 3yg GREATER THAN OR EQUAL TO 350 3/4.5.3 ECCS SUBSYSTEMS - T avg LESS THAN 350 F................... 3/4 5-6 ECSS SUBSYSTEMS - T avg LESS THAN OR EQUAL TO 200 F....... 3/4 5-8 3/4.5.4 (This specification number is not used).................. 3/4 5-9 3/4.5.5 REFUELING WATER STORAGE TANK.................. ... . .... 3/4 5-10 3/4.5.6 RESIDUAL HEAT REMOVAL (RHR) SYSTEM . .................... 3/4 5-11 3/4.6 CONTAINMENT SYSTEMS 3/A.6.1 PRIMARY CONTAINMENT Containment Integrity. ............................. . .. 3/4 6-1 Containment Leakage......... ... ....................... 3/4 6-2 Containment Air Locks.. ........ .. ... ............ .... 3/4 6-5 Internal Pressure............ . ... .................... 3/4 6-7 Air Temperature................................... . . .. 3/4 6-8 Containment Structural Integrity......................... 3/4 6-9 Containment Ventilation System........ . ............ ... 3/4 6-12 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System....... ... ........ . . ....... 3/4 6-14 Spray Additive System....... .. ... . .. .. ... .... 3/4 6-15 Containment Cooling System... .. . ...... .. .... 3/4 6-17 yluezvoziB ylv043 PDR ADOCR 05000498 P PDR SOUTH TEXAS - UNITS 1 & 2 viii
! b v$$f553 sT.HL AE 3E 4 9 REACTOR COOLANT SYSTEM PAGE __Il-_ 0F i 3/4.4.9 PRESSURE / TEMPERATURE LIMITS REAC10R COOLANT SYSTEM L111LIK_COND11101LE01L0ELRA110N _
3.4.9.1 The Reactor Coolant System (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figures 3.4-2 and 3 4-3 during heatup, cooldown, criticality, and inservice leak and hydrostatic testing with:
- a. A maximum heatup of 100 F in any 1-hour period,
- b. A maximum cooldown of 100 F in any 1-hour period, ano
- c. A maximum temperature change of less than or equal to 10 F in any 1-hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.
APPLICABILITY: At all times.
ACTION:
With any of the above limits exceeded, restore the temperature and/or pressure to within the limit within 30 minutes; perform an engineering evaluation to determine the ef fects of the out of-limit condition on the structural integrity of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operation or be in at least HOT STAN0BY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce the RCS T avg and pressure to less than 200 F and 500 psig, respectively, within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
EURVEILLMCLREQUIREMBLS &
4.4.9.1.1 The Reactor Coolant c tem temperature and pressure shall be determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations.
4.4.9.1.2 The reactor vessel material irradiation surveillance specimens shall be removed and examined, to determine changes in material properties, i as required by 10 CFR Part 50, Appendix H, -4n accordeme with the schedah--
in Idule 4.4 5.- The results of these examinations shall be used to update Figures 3.4-2 and 3.4-3.
SOUTH TEXAS - UNITS 1 & 2 3/4 4-31
.-.. \
ATTACHMENT A l SbHL AE.38 Ljtf (Ws hkh now.kr m,t us,,a) PAGE_ 3___ 0F 5 TABLE 4.4-5
\ .
RE ET5R VESSEL MATERTAI3URVEILTANCE PROTIRAM - WITHDRAWAE'5CHEDULL f' CAPSULE VESSEL LEAD j NUMBER 4CbT10N FACTOR
/'WHtt01fAWAL TIME (Ef PY)
U 58.5* 4# first Refueling V 3 9 X 238'$ 4.00 15 W 121.5" 4.00 t.qdby Z 301.5 4.00 Standby SOUTH TEXAS - UNITS 1 & 2 3/4 4-34
7T1 ACHMENT &
REACTOR COOLANT SYSTEM ST-HL AE - 0FMW '$
PA .- . 4
__.GE.
fB515 PRESSURE / TEMPERATURE LIMITS (Continued) can cause an increase in the RT NDT. Therefore, an adjusted reference tempera-ture, based upon the fluence, copper content, and phosphorus content of the material in question, can be predicted using Figure B 3/4.4-1 and the value of ART NDT computed by Regulatory Guide 1.99, Revision 1, " Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessel Materials." The heat-up and cooldown limit curves of Figures 3.4-2 and 3.4-3 include predicted adjustments for this shift in RT NDT at the end of 32 EFPY as well as adjustments for possible errors in the pressure and temperature sensing instruments. l j Values of ART NDT determined in this manner may be used until the results i from the material surveillance program, evaluated according to ASTM E185, are , ,
available. Capsules will be removed in accordance with the requirements of i ASTM E185-73 and 10 CFR Part 50, Appendix H. The surveillance speci= n with-
= drewal schedule is shown in Tabic 4.4-5. The lesd facter represents the rela-
--tion; hip between tk fast neutron flux-dea-ity at the ' cation of the capsule
-end-the inner wall of th^ reactor vessel Therefererheresultsobtainedfrom the surveillance specimens can be used to predict future radiation damage to the reactor vessel material by using the lead factor and the withdrawal time of the capsule. The heatup and cooldown curves must be recalculated when the ART NDT determined from the surveillance capsule exceeds the calculated ART NDT for the equivalent capsule radiation exposure.
Allowable pressure-temperature relationships for various heatup and cool-down rates are calculated using methods derived from Appendix G in Se: tion III of the ASME Boiler and Pressure Vessel Code as required by Appendix G to 10 CFR Part 50, and these methods are discussed in detail in WCAP-7924-A.
The general method for calculating heatup and cooldown limit curves is based upon the principles of the linear elastic fracture mechanics (LEFM) technology.
In the calculation procedures a semielliptical surface defect with a depth of one quarter of the wall thickness, T, and a length of 3/2T is assumed to exist at the inside of the vessel wall as well as at the outside of the vessel wall.
The dimensions of this postulated crack, referred to in Appendix G of ASME Sec-tion III as the ieference flaw, amply exceed the current capabilities of inser-vice inspection techniques. Therefore, the reactor operation limit curves de-veloped for this reference crack are conservative and provide suf ficient safety margins for protertion against nonductile failure. To assure that the radiation embrittlement effects are accounted for in the calculation of the limit curves, the most limiting value of the nil-ductility reference temperature, RTNDT, is used and this includes the radiation-induced shift, ARTNDT, corresponding to the end of the period for which heatup and cooldown curves are generated.
The ASME approach for calculating the allowable limit curves for various heatup and cooldown rates specifies that the total stress intensity factor, j Kg , for the combined thermal and pressure stresses at any time during heatup l or cooldown cannot be greater than the reference stress intensity factor, K IR' for the metal temperature at that time. K IR is b'ained from the reference SOUTH TEXAS - UNITS 1 & 2 B 3/4 4-8
WiTACHMENT 2 ST-HL-AE-3 WV i REAbTORCOOLANTSYSTEM PAGE 3 - 0F S l
1
- -BASES ,
l LOW TEMPERATURE OVERPRESSURE PROTECTION (Continued) overshoot beyond the PORV Setpoint_which can occur as a result of time delays ,
in signal processing and valve opening, instrument uncertainties, and single "
failure. To ensure that mass and heat input transients more severe than those assumed cannot occur Technical Specifications require lockout of all high head safety injection pumps while in. MODE 5 and MODE 6 with the reactor-vessel head
-on. All but one high head safety injection pump are required to be locked out -
in MODE-4. . Technical Specifications also require lockout of the positive displacement pump and all but one charging pump while-in MODES 4, 5, and 6 with the reactor vessel head installed and-disallow start of an RCP if secondary
-temperature is more than 50*F above primary temperature. -
The Maximum Allowed PORV Setpoint for the COMS will be updated based on the results of examinations of reactor vessel- material irradiation surveillance specimens performed as required by 10 CFR Part 50, Appendix H, and in accordance-
-with the schedule in Tcble 1.'-5.
3/4.4.10--STRUCTURAL INTEGRITY The i_nservice inspection and testing programs for ASME Code Class 1, 2, and 3 components ensure that the structural integrity and operational readiness
-of these components will be maintained at an acceptable level throughout the life of the plant. These programs are in accordance with Section_XI of the ASME-Boiler and Pressure Vessel Code and applicable Addenda as required by
- l. 10 CFR 50.55a(g) except where specific written relief has_been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i),
Components of the Reactor Coolant System:were designed to-provide access to permit inservice inspections in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition and Addenda through Winter 1975.
3/4.4.11 REACTOR VESSEL HEAD VENTS
, Reactor _ vessel head vents are provided to exhaust noncondensible gases -
- and/or steam'from the Reactor Coolant System that could_ inhibit natural circulation core cooling... The OPERABILITY of at least two reactor vessel head l- . vent. paths ensures that the capability exists to perform this function.
The.' valve redundancy of the reactor vessel head vent paths serves to mini-mize the probability of inadvertent or irreversible actuation while ensuring
- that a single- failure of _a vent valve, power supply,- or control system does not prevent isolation of.the-vent path.
The function, capabilities, and testing requirements of the reactor vessel
, head' vents:are consistent with the requirements of Item II.B.1 of'NUREG-0737,
" Clarification of THI_ Action Plan Requirements," November 1980, i=
. SOUTH TEXAS - UNITS 1 & 2 B 3/4 4-15 Unit 1 - Arr,andment No. 4
..a- - - - _
+
ATTACllMENT 3 PROPOSED UFSAR CllANGES T3C \ 91- 169. 001
__A TACHMENT 3 STPEGS UFSAR SI-HL AE-37 y4 PAGE I -- O F A
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IbBLE OF CONTENTS CHAPTER 16 TECHNICAL SPECIFICATIONS LIST OF TABLES fatt Iahl.t 11.tl.t Containment Isolation Valves 16.1 2 16.1 1 llo.1 Seuchtr Nes:(( Mderini Sorye,glqnce _
h(ogro,m- WMk& tad Scheiolt TC 16 1 Revision 0
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. ATTACHMENT 3 - '
b I-' g ST HL AE 384 tl PAGE 3 0F L ,
TABLE REACTOR VESSEL MATCRIAL SURVEILLANCE PROGRAM - WITH0RAWAL SCHEDULE CAPSULE . VESSEL LEAD NUMBER LOCATION FACTOR WITH0RAWAL TIME (EFPY) l V 58.5' 4.00 First Refueling i Y 241 3.69 5 i V 61' 3.69 9 i X 238.5 4.00 15 -l W 121.5' 4.00 Standby t Z 301,5' 4.00 5tandby 3 I
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-500T!!-TEXA; UNITS 1 & 2-- -3/4 4 34 -
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