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Line 329: |
Line 329: |
| Reason for Change The revised trip setpoints and allowable values reflect the improved accuracy of the modified Barton steam generator level transmitters being installed in Unit 1 during the upcoming Unit i Cycle 5 refueling outage. | | Reason for Change The revised trip setpoints and allowable values reflect the improved accuracy of the modified Barton steam generator level transmitters being installed in Unit 1 during the upcoming Unit i Cycle 5 refueling outage. |
| The modification to these transmitters is performed by the manufacturer and eliminates errors associated with thermal nonrepeatability (environmental heatup and subsequent cooling) of the transmitter. The present steam generator setpoints in the TS are for unmodified Barton transmitters. This change will also make the Unit 1 TS agree with the Unit 2 TS. | | The modification to these transmitters is performed by the manufacturer and eliminates errors associated with thermal nonrepeatability (environmental heatup and subsequent cooling) of the transmitter. The present steam generator setpoints in the TS are for unmodified Barton transmitters. This change will also make the Unit 1 TS agree with the Unit 2 TS. |
| Justification for Change The original setpoints in the Westinghouse Electric Corporation Setpoint Methodology. WCAP-11239 (transmitted to NRC by letter dated April 23, 1990, "Sequoyah Nuclear Plant (SQN} - Eagle 21 Setpoint Methodolexy Westinghouse Electric Corporation WCAPs 11239 and 11626"), provided values for both unmodified and modified Barton level transmitters to accommodate the installed steam generator level transmitters and to provide values for , | | Justification for Change The original setpoints in the Westinghouse Electric Corporation Setpoint Methodology. WCAP-11239 (transmitted to NRC by {{letter dated|date=April 23, 1990|text=letter dated April 23, 1990}}, "Sequoyah Nuclear Plant (SQN} - Eagle 21 Setpoint Methodolexy Westinghouse Electric Corporation WCAPs 11239 and 11626"), provided values for both unmodified and modified Barton level transmitters to accommodate the installed steam generator level transmitters and to provide values for , |
| the modified Earton transmitters TVA planned to install when available. | | the modified Earton transmitters TVA planned to install when available. |
| As documented in the letter from Westinghouse, TVA 00-792 dated May 13, . | | As documented in the letter from Westinghouse, TVA 00-792 dated May 13, . |
|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217F9701999-10-14014 October 1999 Proposed Tech Specs,Incorporating ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plate Intersections ML20217E4301999-10-12012 October 1999 Proposed Tech Specs,Revising Requirements for Containment Penetrations During Refueling Operations ML20211M7341999-08-30030 August 1999 Marked-up & Revised TS Pages,Providing Alternative to Requirement of Actually Measuring Response Times ML20211K1721999-08-30030 August 1999 Proposed Tech Specs,Providing Clarification to Current TS Requirements for Containment Isolation Valves ML20209B7731999-06-30030 June 1999 Proposed Tech Specs Updating Requirmements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196F2211999-06-24024 June 1999 Proposed Tech Specs Pages for Amend to Licenses DPR-77 & DPR-79,allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20196G4701999-06-24024 June 1999 Proposed Tech Specs Pages Re Amends to Licenses DPR-77 & DPR-79,revising TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196G7961999-06-22022 June 1999 Proposed Tech Specs Bases,Clarifying Proper Application of TS Requirements for Power Distribution Systems & Functions That Inverters Provide to Maintain Operability & Providing Updated Info on Cold Leg Injection Accumulators ML20195E9841999-06-0707 June 1999 Proposed Tech Specs,Increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core ML20206E1391999-04-29029 April 1999 Proposed Tech Spec Change 99-03, Main Control Room Emergency Ventilation Sys Versus Radiation Monitors. Changes Add LCOs 3.3.3.1 & 3.7.7 to Address Inoperability of Radiation Monitoring CREVS & NUREG-1431 Recommendations ML20206E1611999-04-29029 April 1999 Proposed Tech Spec Change 99-04, Auxiliary Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20204H4081999-03-19019 March 1999 Proposed Tech Specs,Relocating TS 3.8.3.1,3.8.3.2,3.8.3.3 & Associated Bases Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207D6011999-02-26026 February 1999 Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20207D6331999-02-26026 February 1999 Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets ML20206S0131999-01-15015 January 1999 Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual ML20199K6001999-01-15015 January 1999 Proposed Tech Specs Adding New Action Statement to 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Appropriate Overall Level of Protection ML20195H6111998-11-16016 November 1998 Proposed Tech Specs Revising EDG SRs by Adding Note That Allows SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Certain Lockout Features Prevent EDG Starting ML20154H7251998-10-0808 October 1998 Proposed Tech Specs Pages,Supplementing Proposed TS Change 96-08,rev 1 to Add CRMP to Administrative Controls Section & Bases of TS ML20238F1091998-08-27027 August 1998 Proposed Tech Specs Providing for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20238F3001998-08-27027 August 1998 Proposed Tech Specs Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of EDGs ML20236G5961998-06-29029 June 1998 Proposed Tech Specs Typed Pages for TS Change 95-19, Section 6 - Administrative Controls Deletions ML20249C6371998-06-26026 June 1998 Proposed Tech Specs Lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05 ML20248F0051998-05-28028 May 1998 Proposed Tech Specs for Section 6, Administrative Controls Deletions ML20217N3511998-04-30030 April 1998 Proposed Tech Specs Pages,Modifying Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4 ML20203J1681998-02-25025 February 1998 Proposed Tech Specs Pages,Revising EDG Surveillance Requirements to Delete Requirement for 18-month Insp IAW Procedures Prepared in Conjunction W/Vendor Recommendations & Modify SRs Associated W/Verifying Capability of DGs ML20202J7601998-02-13013 February 1998 Proposed Tech Specs Section 3.7.9 Re Relocation of Snubber Requirements ML20202J7141998-02-13013 February 1998 Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20202J6961998-02-13013 February 1998 Proposed Tech Specs Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20198T4311998-01-21021 January 1998 Proposed Tech Specs Re New Position Title & Update of Description of Nuclear Organization ML20199K4571997-11-21021 November 1997 Proposed Tech Specs Adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required ML20211A3191997-09-17017 September 1997 Proposed Tech Specs Re Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20137T0871997-04-0909 April 1997 Proposed Tech Specs Re Elimination of Cycle 8 Limitation for SG Alternate Plugging Criteria ML20137M8581997-04-0101 April 1997 Proposed Tech Specs 2.1 Re Safety Limits & TS 3/4.2 Re Power Distribution Limits ML20137C8421997-03-19019 March 1997 Proposed Tech Specs Re Conversion from Westinghouse Electric Corp Fuel to Framatome Cogema Fuel ML20136J0381997-03-13013 March 1997 Proposed Tech Specs Section 5.6.1.2,revising Enrichment of Fuel for New Fuel Pit Storage Racks ML20134P8631997-02-14014 February 1997 Proposed Tech Specs Requesting Discretionary Enforcement for 48 Hours Which Is in Addition to 72 Hours Allowed Outage Time Provided by TS Action 3.8.1.1.b ML20134K9981997-02-0707 February 1997 Proposed Tech Specs Revising TS Change Request 96-01, Conversion from W Electric Corp Fuel to Framatome Cogema Fuel (MARK-BW-17), to Ensure That Core Analysis Computer Code Output Actions Are Consistent W/Hot Channel Factor SRs ML20134L9261996-11-0808 November 1996 Proposed Tech Specs Re Placing of Channel in Trip for Reactor Trip & Engineered Safety Feature Instrumentation Sys Solely to Perform Testing as Not Requiring Channel to Be Declared Inoperable ML20129D2661996-10-18018 October 1996 Proposed Tech Specs,Removing Existing Footnotes That Limit Application of Apc for Plant S/G Tubes to Cycle 8 Operation for Both Units ML20129G7301996-09-26026 September 1996 Proposed Tech Specs 3/4.3.3 Re Fire Detection instrumentation,3/4.7.11 Re Fire Suppression Systems & 3/4.7.12 Re Fire Protection Penetrations ML20113G2691996-09-20020 September 1996 Proposed Tech Specs Change 96-09, Clarification of Work Shift Durations for Overtime Limits ML20117J3391996-08-28028 August 1996 Proposed Tech Specs Revising Psv & MSSV Setpoint Tolerance from Plus or Minus 1% to Plus or Minus 3% ML20117D1651996-08-22022 August 1996 Proposed Tech Specs of SQN Units 1 & 2,deleting Table 4.8.1, DG Reliability, & Revising Section 3.8.1 to Allow Once Per 18 month,7 Day AOT for EDGs ML20117D3121996-08-22022 August 1996 Proposed Tech Specs,Lowering Minimum TS ice-basket Weight of 1,155 Lbs to 1,071 Lbs.Reduced Overall Ice Weight from 2,245,320 Lbs to 2,082,024 Lbs ML20117D3141996-08-21021 August 1996 Proposed TS 3.7.1.3 Re Condensate Storage Tank ML20117D3341996-08-21021 August 1996 Proposed Tech Specs Re Deletion of Surveillance Requirement 4.8.1.1.1.b ML20112H0431996-06-0707 June 1996 Proposed Tech Specs,Revising Section 6, Administrative Controls, to Be More Closely Aligned W/Requirements of STSs ML20101N7071996-04-0404 April 1996 Proposed Tech Specs,Allowing Conversion from Westinghouse Fuel to Fuel Provided by Framatome Cogema Fuels ML20096B3761996-01-0404 January 1996 Proposed Tech Specs Extending Radiation Monitoring Instrumentation Surveillance Period Per GL 93-05 ML20096C2481996-01-0303 January 1996 Proposed Tech Specs,Revising Bases Section 3/4.7.1.2 to Indicate Current Operational Functions of turbine-driven AFW Level Control Valves Modified During Unit 1 Cycle 7 Refueling Outage 1999-08-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F9701999-10-14014 October 1999 Proposed Tech Specs,Incorporating ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plate Intersections ML20217E4301999-10-12012 October 1999 Proposed Tech Specs,Revising Requirements for Containment Penetrations During Refueling Operations ML20211M7341999-08-30030 August 1999 Marked-up & Revised TS Pages,Providing Alternative to Requirement of Actually Measuring Response Times ML20211K1721999-08-30030 August 1999 Proposed Tech Specs,Providing Clarification to Current TS Requirements for Containment Isolation Valves ML20209B7731999-06-30030 June 1999 Proposed Tech Specs Updating Requirmements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196F2211999-06-24024 June 1999 Proposed Tech Specs Pages for Amend to Licenses DPR-77 & DPR-79,allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20196G4701999-06-24024 June 1999 Proposed Tech Specs Pages Re Amends to Licenses DPR-77 & DPR-79,revising TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196G7961999-06-22022 June 1999 Proposed Tech Specs Bases,Clarifying Proper Application of TS Requirements for Power Distribution Systems & Functions That Inverters Provide to Maintain Operability & Providing Updated Info on Cold Leg Injection Accumulators ML20196G8071999-06-22022 June 1999 Revs to Technical Requirements Manual ML20195E9841999-06-0707 June 1999 Proposed Tech Specs,Increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core ML20206E1611999-04-29029 April 1999 Proposed Tech Spec Change 99-04, Auxiliary Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20206E1391999-04-29029 April 1999 Proposed Tech Spec Change 99-03, Main Control Room Emergency Ventilation Sys Versus Radiation Monitors. Changes Add LCOs 3.3.3.1 & 3.7.7 to Address Inoperability of Radiation Monitoring CREVS & NUREG-1431 Recommendations ML20204E8501999-03-21021 March 1999 Plant,Four Yr Simulator Test Rept for Period Ending 990321 ML20204H4081999-03-19019 March 1999 Proposed Tech Specs,Relocating TS 3.8.3.1,3.8.3.2,3.8.3.3 & Associated Bases Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207D6331999-02-26026 February 1999 Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets ML20207D6011999-02-26026 February 1999 Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20206S0131999-01-15015 January 1999 Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual ML20199K6001999-01-15015 January 1999 Proposed Tech Specs Adding New Action Statement to 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Appropriate Overall Level of Protection ML20195H6111998-11-16016 November 1998 Proposed Tech Specs Revising EDG SRs by Adding Note That Allows SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Certain Lockout Features Prevent EDG Starting ML20154H7251998-10-0808 October 1998 Proposed Tech Specs Pages,Supplementing Proposed TS Change 96-08,rev 1 to Add CRMP to Administrative Controls Section & Bases of TS ML20238F1091998-08-27027 August 1998 Proposed Tech Specs Providing for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20238F3001998-08-27027 August 1998 Proposed Tech Specs Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of EDGs ML20209J1631998-08-0707 August 1998 Rev 41 to Sequoyah Nuclear Plant Odcm ML20236G5961998-06-29029 June 1998 Proposed Tech Specs Typed Pages for TS Change 95-19, Section 6 - Administrative Controls Deletions ML20249C6371998-06-26026 June 1998 Proposed Tech Specs Lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05 ML20248F0051998-05-28028 May 1998 Proposed Tech Specs for Section 6, Administrative Controls Deletions ML20217N3511998-04-30030 April 1998 Proposed Tech Specs Pages,Modifying Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4 ML20203J1681998-02-25025 February 1998 Proposed Tech Specs Pages,Revising EDG Surveillance Requirements to Delete Requirement for 18-month Insp IAW Procedures Prepared in Conjunction W/Vendor Recommendations & Modify SRs Associated W/Verifying Capability of DGs ML20202J7651998-02-13013 February 1998 Technical Requirements Manual ML20202J7141998-02-13013 February 1998 Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20202J6961998-02-13013 February 1998 Proposed Tech Specs Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20202J7601998-02-13013 February 1998 Proposed Tech Specs Section 3.7.9 Re Relocation of Snubber Requirements ML20198T4311998-01-21021 January 1998 Proposed Tech Specs Re New Position Title & Update of Description of Nuclear Organization ML20199F8231997-11-30030 November 1997 Cycle 9 Restart Physics Test Summary, for 971011-971130 ML20199K4571997-11-21021 November 1997 Proposed Tech Specs Adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required ML20211A3191997-09-17017 September 1997 Proposed Tech Specs Re Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20203B9731997-08-0505 August 1997 Rev 1 to RD-466, Test & Calculated Results Pressure Locking ML20217J5581997-07-31031 July 1997 Cycle Restart Physics Test Summary, for Jul 1997 ML20210J1671997-04-30030 April 1997 Snp Unit 1 Cycle 8 Refueling Outage Mar-Apr 1997,Results of SG Tube ISI as Required by TS Section 4.4.5.5.b & Results of Alternate Plugging Criteria Implementation as Required by Commitment from TS License Condition 2C(9)(d) ML20137T0871997-04-0909 April 1997 Proposed Tech Specs Re Elimination of Cycle 8 Limitation for SG Alternate Plugging Criteria ML20137M8581997-04-0101 April 1997 Proposed Tech Specs 2.1 Re Safety Limits & TS 3/4.2 Re Power Distribution Limits ML20137C8421997-03-19019 March 1997 Proposed Tech Specs Re Conversion from Westinghouse Electric Corp Fuel to Framatome Cogema Fuel ML20136J0381997-03-13013 March 1997 Proposed Tech Specs Section 5.6.1.2,revising Enrichment of Fuel for New Fuel Pit Storage Racks ML20134P8631997-02-14014 February 1997 Proposed Tech Specs Requesting Discretionary Enforcement for 48 Hours Which Is in Addition to 72 Hours Allowed Outage Time Provided by TS Action 3.8.1.1.b ML20134K9981997-02-0707 February 1997 Proposed Tech Specs Revising TS Change Request 96-01, Conversion from W Electric Corp Fuel to Framatome Cogema Fuel (MARK-BW-17), to Ensure That Core Analysis Computer Code Output Actions Are Consistent W/Hot Channel Factor SRs ML20138F2581997-01-17017 January 1997 Rev 39 to Sequoyah Nuclear Plant Odcm ML20134L9261996-11-0808 November 1996 Proposed Tech Specs Re Placing of Channel in Trip for Reactor Trip & Engineered Safety Feature Instrumentation Sys Solely to Perform Testing as Not Requiring Channel to Be Declared Inoperable ML20129D2661996-10-18018 October 1996 Proposed Tech Specs,Removing Existing Footnotes That Limit Application of Apc for Plant S/G Tubes to Cycle 8 Operation for Both Units ML20129G7301996-09-26026 September 1996 Proposed Tech Specs 3/4.3.3 Re Fire Detection instrumentation,3/4.7.11 Re Fire Suppression Systems & 3/4.7.12 Re Fire Protection Penetrations ML20134J9991996-09-23023 September 1996 Fuel Assembly Insp Program 1999-08-30
[Table view] |
Text
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ENCLOSURE 1 PROPOSED TECilNICAL SPECIFICATION CHANGE SEQUOYAll NUCLEAR PLANT UNIT 1 DOCKET NO. 50-327 (TVh-SQN-TS-91-04)
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TABLE 3.3-4 (Continued)
N ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 8
i M E FUNCTIONAL UNIT TRIP SETPOINT Att0VABLE VALUES
.I .
I g fi. RCS Loop AT Equivalent to
~
Coincident with (5.0 I4M Steam Generator Water 1 %#E 4 of narrow range 144-4% of narrow range tevel - Low-Low (Adverse) instrument span instrursent span R145 and A-- ^ ~ /
l Containment Pressure (EAM) $ 0.5 psig < 0.6 psig i G.'7 l
Steam Generator Water > H-9% of narrow range 144L-4% of narrow range f level -- Low-low (EAH) instrument span instromant span d w n f A > d D d. S.I. See 1 above (all SI Setpoints)
- e. Station Blackout 0 volts with a 5.0 second 0 volts with a 5.0 1.0 second a time delay time delay
- f. Trip of Main feedwater N.A. N.A.
Pu:ps
- g. Auxiliary Feedwater Suction 1 2 psig (rnotor driven punp) 1 I psig (trotor driven ptrp)
, Pressure-Low 113.9 psig (turbine driven 1 12 psig (turbine driven g EC pump) pump) a d k<
- ) -
- h. Auxiliary Feedwater Suction Transfer Time Delays 4 seconds (motor driven puep) 4 seconds t 0.4 seconds (motor driven pump)
C 5.5 seconds (turbine driven 5.5 seconds i 0.55 secends 6 g; ptsp) (turbine driven pump)
M y-
.o
,*e
~ a JD
ENCLOSURE 2 PROPOSED TEClISICAL SPECIFICATION CllAfiGE SEQUOYAll NUCLEAR PLANT UNIT 1 DOCKET No. 50-327 (TVA-SQN-TS-91-04)
DESCRIPTION A'iD JUSTIFICATION FOR REVISION TO STEAM GENERATOR LO-LO LEVEL TRIP SETPOINY 4
E5 CLOSURE 2 Qescription_of Change TVA proposes to modif y the Sequoyah Nuclear Plant (SQN) Unit I technical specifications (TSs) to revise the steam generator wate. level trip setpoints (Table 2.2-1, Reactor Trip System Instrumaatation Trip Setpoints, Items 13.a and b, and Table 3.3-4, Engineered Safety Feature Actuation System Trip setpoints, item 6.c) to account for the installation of modified International Telephone and Telegraph Corporation (ITT) Barton Model 764 steam generator level transn:itters for Unit 1 only. This change to the TS was previously implemented for SQN Unit 2 by NRC Amendment 132.
Reason for Change The revised trip setpoints and allowable values reflect the improved accuracy of the modified Barton steam generator level transmitters being installed in Unit 1 during the upcoming Unit i Cycle 5 refueling outage.
The modification to these transmitters is performed by the manufacturer and eliminates errors associated with thermal nonrepeatability (environmental heatup and subsequent cooling) of the transmitter. The present steam generator setpoints in the TS are for unmodified Barton transmitters. This change will also make the Unit 1 TS agree with the Unit 2 TS.
Justification for Change The original setpoints in the Westinghouse Electric Corporation Setpoint Methodology. WCAP-11239 (transmitted to NRC by letter dated April 23, 1990, "Sequoyah Nuclear Plant (SQN} - Eagle 21 Setpoint Methodolexy Westinghouse Electric Corporation WCAPs 11239 and 11626"), provided values for both unmodified and modified Barton level transmitters to accommodate the installed steam generator level transmitters and to provide values for ,
the modified Earton transmitters TVA planned to install when available.
As documented in the letter from Westinghouse, TVA 00-792 dated May 13, .
I 1990, adjustments to steam generator level setpoints (adverse) for reference leg heatup were issued for unmodified Barton transmitters.
TVA's letter to Westinghouse, Letter No. NB212, dated June 27, 1990, and Westinghouse letter to TVA, TVA-90-1071, dated October 12, 1990, documented the applicability of this correction to the modified Barton Model 764 steam generator transmitters, and because of the increased accuracy over Barton 764 unmodified level transmitters, supports the icwer setpoints for environmental allowance modifier (EAM) and adverse steam generator lo-lo level.
The installation of the modified steam generator level transmitter is being performed for Unit I during the upcoming Cycle 5 refueling outage.
With the modified Earton level transmitters, the revised setpoints in this revision will still meet the requirements assumed in the SQN safety analysis. The lower setpoints will also provide additional margin for steam generator lo-lo level trips, within the safety analysis, to decrease j the occurrences of challenging SQN safety systems during startup and
~
normal operation feedwater transients. When this TS cnange is !
implemented, both units will have the same setpoints for steam generator lo-lo level trips, thus eliminating any possible confusion between the units.
ENCLOSURE 3 PROPOSED TECHNICAL SPECIFICATION Cl!ANGE SEQUOYAll NUCLEAR PLANT UNIT 1 DOCKET NO. 50-327 (TVA-SQN-IS-91-04)
DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION r
/
. . . ~ - - - - - - .
ENCLOSURE 3 1 Significant flazards Evaluation TVA has evaluated the proposed technical specification (TS) change and has determined that it does not tepresent a significant hazards consideration based on criteria established in 10 CFR 50.92(c). Operation of Sequoyah Nuclear Plant in accordance with the proposed amendment will nott
- 1. Involve a significant increa'e s in the probability or consequences of an accident previously evaluated.
The modified transmitters are the same model as the existing transmitters but have been modified to provide increased accuracy l under thermal heatup and cooldown evolutions to improve repeatability. They perform the same function in the same manner with only the accuracy being improved to ensure identification of an ,
accident condition with the revised setpoints. This will provide accident mitigation initiations at the appropriate time to limit the consequences of the event _as assumed in the safety analysis. These transmitters are'not a device that could create an accident. but instead identify conditions associated with an accident to initiate logic for accident mitigation. Therefore. the installation of the
- modified steam generator level transmitters and revision of the steam generator lo-lo level trip setpoints will not increase the probability or consequences of an accident.
I
- 2. Create the possibility of a new or different kind of accident from any previously analyzed. ,
The steam generator level transmitters and associated trip setpoints are not a source for any accident. They provide actuation of mitigation logic for specific accident parameters. Therefore, this .
change cannot create any new or different kind of accident.
- 3. Involve a significant reduction in a margin of safety.
The reduction in the steam generator 1o-10 level trip setpoints is the result of the-improved accuracy of the modifled steam generator level transmitters. This improved ace,uracy allows the use of a lower setpoint and still maintains the same level of confidence of accident ;
condition identification without reducing the existing margin of safety. This is accomplished by only reducing the instrument inaccuracy values and not the margin of safety limits to allow the ,
lower setpoints. Therefore, there is no reduction in the margin of !
safety.
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