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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MONTHYEARML20217A2421999-09-30030 September 1999 Proposed Tech Specs Removing Parameters No Longer Applicable & Adding Tdf Value for Model 94 SGs in Place of Reactor Coolant Sys Flow ML20211Q8071999-09-0808 September 1999 Proposed Tech Specs & Associated Bases for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] |
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ST-NOC-AE-000205 Annotated Technical Specifications and Bases Page1 I
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Annotated Technical Specification and Bases Pages i
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9907140172 990706 PDR ADOCK 05000499 P
PDRy E__--__---___-__-_-__--------____-----
-- A
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVElltANCE RE0VIREMENTS SECTION P.!LGE 3/4.2 POWER DISTRIBUTION LIMITS -
3/4.2.1 AXIAL FL X DIFFERENCE..'.................................... 3/4 2-1 FIGURE 3.2.1 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER......................................... Del e t ed 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - F,(Z)....................... 3/4 2-5 FIGURE 3.2-2 K(Z) - NORMALIZED F,(Z) AS A FUNCTION OF CORE HEIGHT.... Deleted 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR................... 3/4 2-9 3/4.2.4 QUADRANT POW 2R TILT RATIO.................................. 3/4 2-10 3/4.2.5 DNB PARAMETERS............................................. 3/4 2-11 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION........................ 3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION..................... 3/4 3-2 TABLE 3.3-2 (Thi s tabl e number not used)............................ 3/4 3-9 l
TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................................... 3/4 3-11 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION............................................ 3/4 3-16
~
TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION............................................ 3/4 3-18 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS............................. 3/4 3-29 TABLE 3.3-5 (Th i s t abl e number not used)............................ 3/4 3-37 TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS.................. 3/4 3-42 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring for Pl ant Operations................... 3/4 3-50 TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS....................................... 3/4 3-51 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS....................... 3/4 3-53 Movabl e Incore Detectors................................... 3/4 3-54
'......[.......~..........................................
- l' : ::
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..,...................,.. ~.... -.,......
SOUTH TEXAS - UNITS 1 & 2 v
Unit 1 - Amendment No. N, 50 Unit 2 - Amendment No. H, 39 l
~
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION PAGE
~ ~.:." : '.:
- 2."': "^":T^^ "
'"""""E"" 0" C'""' :' ' "?T :
N.........
3/4 3-57 Meteorological Instrumentation 3/4 3-58 TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION 3/4 3-59 TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION 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................
3/4 3-66 Accident Monitoring Instrumentation...........
3/4 3-67 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTS 10N.........
3/4 3-68 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-73 Chemical Detection Systems
^
3/4 3-75 TABLE 3.3-11 (This table number is not used)...........
3/4 3-77 Radioactive Liquid Effluent Monitoring Instrumentation DELETED TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTAT TABLE 4.3-8 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DELETED Explosive Gas Monitoring Instrumentation 3/4 3-79 TABLE 3.3-13 EXPLOSIVE GAS MONITORING INSTRUMENTATION 3/4 3-80 TABLE 4.3-9 EXPLOSIVE GAS MONITORING INSTRUMENTATION i
SURVEILLANCE REQUIREMENTS................
3/4 3-82 3/4.3.4 TURBINE OVERSPEED PROTECTION...............
3/4 3-84, SOUTH TEXAS - UNITS I & 2 vi Unit I - Amen'...it No. 47 Unit 2 - An..ndment No. 36 L_
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3.3.3.3 ": --i -?: : rit-T,..:. ;. ; 7
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APPLICABILITY: At all times.
, ACTION:
a.
With one or more of the above required seismic monitoring instrume inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within e
next 10 days outlining the cause of the malfunction and the p s
for restoring the instrument (s) to OPERABLE status. This AC ON may be applicable to both units simultaneously.
b.
The provisions of Specification 3.0.3 are not applicab SURVEILLANCE REQUIREMENTS 4.3.3.3.1 Each of the above required seismic monitori instruments shall be demonstrated OPERABLE by the performance of the CHAN CHECK, CHANNEL CALI-BRATION, and ANALOG CHANNEL OPERATIONAL TEST at th.
requencies shown in l
Table 4.3-4.
1 4.3.3.3.2 Each of the above required seismi onitoring instruments actuated during a seismic event shall be restored to PERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CHANNEL CALIBRATION performed within 1 ays following the seismic event.
Data shall be retrieved from actuated truments and analyzed to determine the magnitude of the vibratory ground mo on. A Special Report shall be prepared and submitted to the Commission pu uatt to Specification 6.9.2 within 14 days l
describing the magnitude, frequ y spectrum, and resultant effect upon facility features important to safety.
)
e instrumentation may be shared with additional units at a common site
^
provided seismic instrumentation and corresponding Technical Specifications meet the recommendations of Regulatory Guide 1.12, Revision 1, April 1974.
50llTH TEXAS - UNITS 1 & 2 3/4 3-55 Unit I - Amendment No. 4 u----------------------------------------
J TABLE 3.3-7 7
SEISMIC MONITORING INSTRUMENTATION MINIMUM INSTRUMENTS AND SENSOR LOCATIONS MEASUREMENT INSTRUMENTS (Unit 1 only)
RANGE OPERABLE l
^
- 1. Triaxial Time-History Accelerometers ***
- a. Free Field 13g 1
- b. Containment Bldg. Foundation 13g 1
)
(Tendon Gallery E1. -36'9")
i
- c. Outside Face Containment Shell 13g 1
(Reactor Containment Building El. 68'0")
- d. Steam Generator Upper Lateral Support 13g 1
(Reactor Containment Building El. 66'7 ")
- e. Fuel Handling Building Foundation i3g 1
(Fuel Handling Building El. -29'0")
- f. Mechanical Electrical Auxiliary Building 13g 1
(Mechanical Electrical Auxiliary Building El. 35'0")
- 2. Triaxial Peak Accelerographs
- a. Spent Fuel Pool Heat Exchanger 3g 1
(Inlet Line Fuel Handling Building E1. 64'5k")
- b. Reactor Vessel 13g 1
(Reactor Containment Building Eli 68'0")
- c. Cold Leg of RC Piping 3g 1
(Reactor Containment Building E1. 34'3")
- 3. Self-Contained Triaxial Accelerograph 13g 1
(At Reactor Containment Building Foundation Tendon Gallery El. -36'9")
- 4. Triaxial Seismic Switch * ** #
0.03 to 3g 1
- 5. Triaxial Seismic Trigger * ** ##
0.003 to 0.3g 1
- 6. Response Spectrum Analyzer * **
1 to 32 Hz 1
- 7. Magnetic Tape Recorders **
0.1 to 33 Hz 6
- 8. Playback System **
N.A.
1
- With reactor control room indication and alarm in Unit 1 (Alarm only in Unit 2)
I
- At seismic monitoring panel in Control Room, Unit 1
- Accelerometer data is gathered and analyzed by the Response Spectrum Analyzer (Item 6).
- Triaxial seismic switch is set at the OBE acceleration level of 0.05g horizontal and 0.033g vertical.
- Triaxial seismic trigger is set at 0.02g all axes.
SOUTH TEXAS - UNITS 1 & 2 3/4 3-56 Unit.1 - Amendment No. 4
~
Tn415 PA4F tWTENTISNALLY BLMK TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG CHANNEL INSTRUMENTS AND SENSOR LOCATIONS CHANNEL CHANNEL OPERATIONAL (Unit 1 only)
CHECK CALIBRATION TEST
{
- 1. Triaxial Time-History Accelerometers ***
- a. Free Field M
R SA
- b. Containment Bldg. Foundation M
R SA (Tendon Gallery El. -36'9")
- c. Outside Face Containment Shell M
R SA (Reactor Containment Building E1, 68'0")
- d. Steam Generator Upper Lateral Support M
R SA (Reactor Containment Building El. 66'7 ")
- e. Fuel Handling Building Foundation M
R SA (Fuel Handling Building E1. -29'0")
- f. Mechanica) Electrical Auxiliary M
R SA Building (Mechanical Electrical Auxiliary Build!ng El. 35'0")
- 2. Triaxial Peak Accelerographs
- a. Spent Fuel Pool Heat Exchanger N.A.
R N.A.
(Inlet Line Fuel Handling Building E1. 64'5k")
- b. Reactor Vessel N.A.
R N.A.
(Reactor CMitainment Building E1. 68'0")
- c. Cold Leg of RC Piping N.A.
R N.A.
(Reactor Containment Building El. 34'3")
- 3. Self-Contained Triaxial Accelerograph M
R SA (At Reactor Containment Building Foundation Tendon Gallery E1. -36'9")
- 4. Triaxial Seismic SwitcS* **
M R
SA
- 5. Triaxial Seismic Trigger * **
M R
SA
- 6. Response Spectrum Analyzer * **
M R
SA
- 7. Magnetic Tape Recorders **
M R
SA
- 8. Playback System **
M R
N.A.
I i
- With reactor control room indication and alarm in Unit 1 (Alarm only in I
Unit 2)
- At seismic monitoring panel in Control Room, Unit 1
- Accelerometer data is gathered and analyzed by the Response Spectrum Analyzer (Item 6).
l SOUTH TEXAS - UNITS 1 & 2 3/4 3-57 Unit 1 - Amendment No. 4 I
i
_o
l INSTRUMENTATION IlaS.ES_
3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the core. The OPERABILITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve.
l ForthepurposeofmeasuringF(Z)orFfHafullincorefluxmapisused.
q Quarter-core flux maps, as defined in WCAP-8648, June 1976, may be used in recalibration of the Excore Neutron Flux Detection System, and full incore flux ma~ or symmetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range channel is inoperabic.
3/4.3.3.3 6EMWNMNGEiniWiiNEHGE (MQT @
f The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.
This capa-bility is required to permit comparison of the measured response to that used in the design basis for the facility to determine if plant shutdown is required pursuant to Appendix A of 10 CFR Part 100.
The instrumentation is consistent l
with the recommendations of Regulatory Guide 1.12, " Instrumentation for Earth-quakes," April 1974.
j 3/4.3.3.4 HETEOR0 LOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data are available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite meteorological Programs," Februar.v 1972.
l 3/4.3.3.5 REMOTE SHUTDOWN SYSTEM l
The OPERABILITY of the Remote Shutdewn System ensures that sufficient capability is available to permit safe shutdown of the facility from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR Part 50.
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SOUTH TEXAS - UNITS 1 & 2 8 3/4 3-4 7
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