Proposed Tech Specs,Requiring Response Time Testing for Containment Ventilation Isolation Function When Initiated by High Containment or Low Pressurizer Pressure SignalsML20234F079 |
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Site: |
Sequoyah ![Tennessee Valley Authority icon.png](/w/images/c/ce/Tennessee_Valley_Authority_icon.png) |
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Issue date: |
09/14/1987 |
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From: |
TENNESSEE VALLEY AUTHORITY |
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To: |
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Shared Package |
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ML20234F047 |
List: |
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References |
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NUDOCS 8709230020 |
Download: ML20234F079 (13) |
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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
{{#Wiki_filter:-- - - - - - - - - - - - - - - -
ENCLOSURE 1 4
PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-87-38)
LIST OF AFFECTED PAGES Unit 1 3/4 3-29 3/4 3-30 3/4 3-33a Unit 2 3/4 3-29 3/4 3-30 3/4 3-33a 8709230020 070914 7 j DR ADOCK 0500
' - TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS
~ ~ ~ ~ ~
- 1. Manual
- a. Safety Injection (ECCS) Not Applicable Feedwater Isolation Not Applicable Reactor Trip (SI) Not Applicable Containment Isolation-Phase "A" Not Apolicable Containment Ventilation Isolation Not Applicable Auxiliary Feedwater Pumps
.Not Applicable Essential Raw Cooling Water System Not Applicable-Emergency Gas Treatment System Not Applicable.
- b. Containment Spray Not Applicable Containment Isolation-Phase "B" Not Applicable Containment Ventilation Isolation Not Applicable es Containment Air Return Fan Not Applicable
- e. u) 1<,3 4 c. Containment Isolation-Phase "A" Not Applicable Emergency Gas Treatment System Not Applicable Containment Ventilation Isolation Not Applicable
- d. Steam Line Isolation Not Applicable
- 2. Containment Pressure-Hich R59
- a. Safety Injection (ECCS) $ 32.0( ) '
- b. Reactor Trip (from SI) 1 3.0 ' '
< 8.0(2)
- c. Feedwater Isolation
- d. Containment Isolation-Phase " A"(3) 18.0(0)/28.0( )
- e. Containment Ventilation Isolation ht--Appliccbic 4 5,.5-(9)OQ
- f. Auxiliary Feecwater Pumps 1 60
- g. Essential Raw Cooling Water System 1 65.0(6)/75.0(9)
- h. Emergency Gas Treatment System 5 38.0(9) l-
.Wh.
- .)
-J
May 12, 1987 SEQUOYAH - UNIT 1 3/4 3-29 Amendment No. 55
"-' ---------___m _ _ _ _ , _ _ _
TABLE 1.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS
- 3. Pressurizer Pressure-Low
- a. Safety Injection (ECCS) 1 32.0(1)/28.0(7) R59
- b. Reactor Trip (from SI) < 3.0
- c. Feedwater Isolation < 8.0(2)
- d. Containment Isolation-Phase "A"(3) 18.0(8).
ceXn)
- e. Containment Ventilation Isolation Net ^p;:!ic2M $ f,5
- f. Auxiliary Feedwater Pumps < 60
- g. Essential Raw Cooling Water System 65.0(8)/75.0(9)
- h. Emergency Gas Treatment System 5 28.0(8)
- 4. Differential Pressure Between Steam Lines-High
- a. Safety Injection (ECCS)
- b. Reactor Trip (from SI) < 3.0
- c. Feedwater Isolation < 8.0(2)
- d. Containment Isolation-Phase "A"(3) 18.0(8)/28.0(9)
- e. Containment Ventilation Isolation Not Applicable
- f. Auxiliary Feedwater Pumps 1 60
- g. Essential Paw Cooling Water System s 65.0(8)/75.0(9)
- h. Emergency Gas Treatment System 1 38.0(9) l l
- 5. . Steam Flow in Two Steam Lines - High Coincident with T --Low-Low
- a. Saf ty Injection (ECCS) < 30.0(7)/30.0(1) R59
- b. Reactor Trip (from SI) < 5.0 .
- c. Feedwater Isolation 10.0(2) -
- d. Containment Isolation-Phase "A"I ) 20.0(9)/30.0(9)
- e. Containment Ventilation Isolation Not Applicable
- f. Auxiliary Feedwater Pumps 1 60
- g. Essential Raw Cooling Water System 1 67.0(9)/77.0(9)
- h. Steam Line Isolation < 10.0
- i. Emergency Gas Treatment System 1 40.0(9) l l
May 12, 1987 SEQUOYAH - UNIT 1 3/4 3-30 Amendment No. 55
(- .
l . .
,. INSTRUMENTATION l
TABLE 3.3-5 (Continued) l TABLE NOTATION (10) The response time for loss of voltage is measured from the time voltage
.is lost until the time full voltage is restored by the diesel. The response time for degraded voltage is measured from the time the load R33 shedding signal is generated, either from the degraded voltage or the SI enable timer, to the time full voltage is restored by the diesel. The response time of the timers is covered by the requirements on their setpoints.
(11) (c.,-{ainmed fae9e vn b't> 0"lt Y"'"'" b # " "
A,,4 a responn -h%s o / 6.5 sero d o' lug *
- NOTE: This tech'nical specification to be implemented at the startup following the second refueling outage or following completion of the modification, whichever is earlier. R33 I
l' SEQUOYAH - UNIT 1 3/4 3-33a
- Amendment No. 29 May 5, 1983
r .
----= - - - - ~ ~ - - ~ - - - - -
TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES-1
-INITIATING' SIGNAL AND FUNCTION RESPONSE TIME IN SECONOS
- i. 1. Manual
- a. Safety Injection (ECCS) Not Applicable Feedwater Isolation Not Applicable
~
Reactor Trip (SI) Not Applicable
. Containment Isolation-Phase "A" Not Applicable Containment' Ventilation Isolation Not Applicable Auxiliary Feedwater Pumps Not Applicable
-Essential Raw Cooling Water System Not Applicable Emergency Gas Treatment System Not Applicable-
- b. Containment Spray Not Applicable Containment Isolation-Phase "B" Not Applicable Containment Ventilation Isolation Not Applicable Containment Air Return Fan Not Applicable
- c. Containment Isolation-Phase "A" Not Applicable Emergency Gas Treatment System Not Applicable Containment Ventilation Isolation Not Applicable
- d. Steam Line Isolation Not Applicable
- 2. Containment Pressure-High-
- a. Safety Injection (ECCS) $ 32.0(I) .
- b. Reactor Trip (from SI) 13.0
- c. Feedwater Isolation < 8. 0( 2
- d. Containment Isolation-Phase "A"I ) 118.0(8)/28.0( )
- e. Containment Ventilation Isolation '!;t ^.pp l i c able- f S,5-(9X'd
- f. Auxiliary Feedwater Pumps $06
- g. Essential Raw Cooling Water System 16 5.0(8)/75.0(9)
- h. Emergency Gas Treatment System 138.0(9) l l
I 4
May 12, 1987 SEQUOYAH - UNIT 2 3/4 3-29 Amendment No.47
' TABLE 3.3-5 (Con'tinued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES ._,
INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONOS
- 3. Pressurizer Pressure-Low :6
- a. Safety Injection (ECCS) R47 1 32.0(1)/28.0(7)
- b. Reactor Trip (from SI) < 3.0 -
- c. Feedwater Isolation 8.0(2) i
- d. Containment Isolation-Phase "A"( ) 18.0(8)
- e. Containment Ventilation Isolation Net ipp!!c2 P 55f an>
- f. Auxiliary Feedwater Pumps < #'
_60
- g. Essential Raw Cooling Water System 1 65.0(8)/75.0(9) 3 h.
Emergency Gas Treatment System <
_28.0(8)
- 4. Differential Pressure Between Steam Lines-High i
- a. Safety injection (ECCS)
R'7
- b. Reactor Trip (from SI) 13.0 y
- c. Feedwater Isolation <8.0(2)
- d. Containment Isolation-Phase "A"( ) 18.0(8)/28.059)
- e. Containment Ventilation Isolation Not Applicable
- f. Auxiliary Feedwater Pumps <60
- g. Essential Raw Cooling Water System 65.0(9)/75.0(9)
- h. Emergency Gas Treatment System <
_38.0(9)
- 5. Steam Flow in Two Steam Lines - High Coincident with T --Low-Low
- a. S ty Injection (ECCS) 1 30.0(7)/30.0(1) R47
- b. Reactor Trip (from SI) <
_. 5. 0
- c. Feedwater Isolation <10.0(2) ~
- d. Containment Isolation-Phase "A"( ) 20.0(8)/30.0(9)
- e. Containment Ventilation Isolation Not Applicable
- f. Auxiliary Feedwater Pumps <
_.60
- g. Essential Raw Cooling Water System 1 67.0(8)/77.0(9)
- h. Steam Line Isolation 110.0
- i. Emergency Gas Treatment System 14 0,0(9)
May 12, 1987 SEQUOYAH - UNIT 2 3/4 3-30 Amendment No. 47 i
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; [_.; y Y i'z\f (
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MSTRUMENTATION ) ~
l i
,T,ABLE 3.3-5 (Continued)
, i TAf1!E NOTATION
./
I
') ., c {>^
; (
A (10) The response. time <for loss'of voltage is measured from the time voltage d i is lost untW the time full voltage is restored by the diesel. The' '
response, tirar fdr' degraded voltage is measured f rom.th'e time. the loadf gtg shedding signal is generated, either from the degraded voltage or the 51 enable timer, to the time full voltage is restored by the diesel. The response time of the timers:is covered by the requirements on their setpoints; (II) $ hl;,,,,,,.,a} a p ey, ya/va, only , bf ja,m.J rsd,/an so w L ys /vas I.
k^ n ' A keyo st s du ofdJ sn o.,df o a leis, l i l
l l
f i
. 1 I
I
(*fl0TE: This technical specification is to be-implemented during the startup R18
'4 following the first refueling outage.,
i SEQUOYAH - UNIT 2 3/4 3 33a Amendment No.18 MAY 5 1933 4
ENC'LOSUR'E 2-f '
h PROPOSED. TECHNICAL SPECIFICATION CHANGE SEQUOYAH' NUCLEAR PLANT UNITS.1 AND-2.
DOCKET NOS, 50-327 AND 50-328
.(TVA-SQN-TS-87-38)
DESCRIPTION, AND JUSTIFICATION FOR THE ADDITION OF RESPONSE TIME TESTING FOR THE CONTAINMENT VENTILATION ISOLATION FUNCTION l
~
W s'
- 1. .
ENCLOSUR'E 2 Description of Change The proposed change to table 3.3-5 of the TSs will add requirements to response time test of the containment ventilation isolation function when initiated by a high containment pressure signal or a low pressurizer pressure signal.
Reason for Change Section 15.4.1.1.5 of the SQN Final Safety Analysis Report-(FSAR) describes the effects of containment purging on the Loss of Coolant Accident (LOCA) analysis. This analysis assumes that containment purge is isolated 5.5 seconds after the postulated break. The analysis also assumes 6.5 seconds for the isolation of the upper and lower containment air radiation monitors. These assumptions are currently verified by response time testing, but not as a requirement of specification 3.3.2.1.
dustificationforChange The containment ventilation isolation function is currently response time L tested by the performance of Surveillance Instruction SI-247.900,
" Engineered Safety Features Response Time Verification," and Instrument Maintenance Instructions (IMIs)-99 RT-622A and RT-6228, " Response Time Testing Engineered Safety Feature Actuation Slave Relay K622." The proposed change to the TSs adds a requirement to perform the response time testing, which is currently being performed. This is done to ensure that the assumptions made in the FSAR accident analysis are verified by response time testing pursuant to specification 3.3.2.1.
The response times for the containment ventilation isolation function that are added to table 3.3-5 of the TSs are derived from data in the FSAR.
Section 15.4.1.1.5 of the FSAR assumes a value of 1.5 seconds for the j generation of a safety injection (SI) signal and containment ventilation i isolation signal. This includes allowances for the initiating parameter i to reach its SI setpoint. Table 6.2.4-1 in turn indicates that the j accident analysis assumes the containment purge isolation valves require j 4.0 seconds to close, and the isolation valves for the upper and lower j compartment air radiation monitors, which also close on the CVI signal, i require 5.0 seconds to close. Table 6.2.4-1 indicates that these valves I isolate on the phase B isolation signal. This discrepancy will be corrected in the 1988 FSAR epdate. These values yield the response time test values of 5.5 seconds and 6.5 seconds for the containment purge isolation valves and the containment air radiation monitor isolation valves, respectively.
The response time test for the containment ventilation isolation function l 1s performed only for the high containment pressure and the low I pressurizer pressure initiating signals. This is appropriate since these are the only two automatic SI initiating signals indicative of a LOCA.
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A g ,i ENCLOSUR$3 PROPOSED TECHNICAL SPECIFICATION CHANGES SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-87-38)
DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATIONS 4
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4 ENCLOSURL 3 Significant Hazards Evaluation TVA has evaluated the proposed TS change and determined that it does not represent a significant hazards consideration based on the criteria established in 10 CFR 50.9Ec. Operation of SQN in accordance with the proposed amendment will not:
- 1. Involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed change adds requirements for response time testing of the containment ventilation isolation function. This testing is currently performed, but not as a requirement of TS 3.3.2.1. By requiring the response time testing of the isolation function, the plant is ensured of being bounded by the accident analysis.
- 2. Create the possibility of a new or.different kind of accident from any accident previously evaluated. The addition of the requirement for response time testing of the containment ventilation isolation ensures that SQN is bounded by its FSAR accident analysis. Since the response time testing is presently performed, the requirement does not change the function or operation of the equipment.
- 3. Involve a significant reduction in a margin of safety. The proposed testing requirement will be used to ensure that the testing presently performed continues to be conducted. By performing the response time l test of the contatament ventilation isolation function, the current margins of safety for the plant are verified.
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e ENCL.05URE 4 PROPOSED TECHNICAL SPECIFICATION CHANGES SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-87-38)
LIST OF COMMITMENTS IDENTIFIED IN ENCLOSURE 2 I
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ENC'LOSURE4 List of Commitments
- 1. FSAR table 6.2.4-1 indicates that the upper and lower containment air radiation monitor isolation valves isolate on the phase B isolation signal. These valves actually isolate on the containment ventilation isolation signal. This discrepancy will be corrected in the 1988 FSAR update.
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