Proposed Tech Spec Changes Re Requirement That Containment Sump Level Instrumentation Be Operable for Automatic Switchover from Refueling Water Storage Tank to Containment Sump & Accident MonitoringML20054J581 |
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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: |
06/18/1982 |
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From: |
TENNESSEE VALLEY AUTHORITY |
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To: |
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Shared Package |
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ML20054J578 |
List: |
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References |
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NUDOCS 8206290290 |
Download: ML20054J581 (15) |
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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. 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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] |
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PROPOSED TECHNICAL. SPECIFICATIONS'
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s SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 Y '#""
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k 7-v, TABLE 3.3-3 (Continued) ~
'15 Ei ' ENGit:EERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION
, ~
x '
HINIMUM Si TOTAL NO. CHANNELS CHANNELS APPLICABLE
- FilNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION'
- 7. LOSS OF POWER ,
- a. 6.9 kv Shutdown Board
- 1. toss of Voltage 2/ shutdown 1 loss of 2/ shutdown 1, 2, 3, 4 20*
board voltage on board any shutdown np board
- 2. Load Shedding -2/ shutdown 1/ shutdown 2/ shutdown 1, 2, 3, 4 20*
board board board ;
R 8. ENGINEERED SAFETY FEATURE
- ACTUATION SYSTEM INTERLOCKS
- a. Pressurizer Pressure - 3 .2 2 1,2,3 22a Hot P-11 *
- b. T avg
- P-12 4 2 3 1,2,3 22b
- c. Steam Generator _3/ loop 2/ loop 3/ loop 1, 2 22c j Level P-14 .any loop Note: ' Manual switchover of RHR pump suction from the RWST to containment sump will be employed-until containment sump level' indicators are returned OPERABLE. Automatic switchover is
^ '
not required'0PERABLE during the interim.
yg TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRuttENTATION TRIP SETPOINTS s
x i FUNCTIONAL UNIT- TRIP SETPOINT. ALLOWABLE VALUES C
E3 8. ENGINEERED SAFETY FEATURE ACTUATION
(( SYSTEM INTERLOCES (Continued)
- b. T avg -
Prevents Mancal Block of Safety
. Injection P-12' < 540*F
< 542 F
- c. T,yg Hanual-Block of Safety Injection,
-Steam Line Isolation, Block Steam Dump 1 540*F 1 538 F -
GJ P
30 d. Steam Generator Level us Turbine Trip, Feedwater Isolation j P-14 (See 5. above)
. . _ - . . _ . - ._ _ - - _ _ - . . . . . . - - ..~ . . . - . .
TABLE 4.3-2 (Continued) .
M E ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS
{
=
' CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E TEST REQUIRED Q FUNCTIONAL UNIT CHECK CALIBRATION w 1, '
3 Main Steam Generator. Water R M
- c. S Level-Lca-Low 4 d. S. I. See 1 above (all SI surveillance requirements)~
- e. Station Blackout N.A. R N.A. 1, 2, 3 N.A. N.A. R 1, 2
- f. . Trip of Main Feedwater Pumps N.A. M 1, 2,.3
- g. Auxiliary Feedwater Suction R _ . _
~~
i
- 7. LOSS OF POWER .
w a. 6.9 kv Shutdown Board
, g Undervoltage Loss of. Voltage .S R M 1,2,3,4 1.
- 2. Load Shedding a 5- . R N.A. 1, 2, 3, 4
- 8. ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS
- a. Pressurizer Pressure, N.A. R (4) N.A. 1, 2, 3 P-11 .
R (4) N. A. 1, 2, 3'
- b. N.A.
T,yg, P-12
- c. Steam Generator -
N.A. R (4) N.A. 1, 2 Level, P-14
==
.4.-.
m TABLE 3.3-10 5
g ACCIDENT NONITORING INSTRUMENTATION
^
MINItt' JM REQUIRED NO CHANNELS
[ OF CHANNELS OPERABLE 5
w INSTRUMENT
- 2. 2 1 Reactor Coolant TCold (Wide Range) ,
- 3. Containment Pressure 2 1
- 4. Refueling Water Storage Tank Level 2 1
- 5. Reactor Coolant Pressure 2 1 w 6. Pressurizer Level (Wide Range) 2 1 .
s
^ 1/ steam line
- 7. Steam Line Pressure 2/ steam line m
- 8. Steat Generator Level - Wide 1/ steam generator 1/ steam generator
- 9. Steam Generator Level - Narrow. . 1/ steam generator 1/ steam generator
- 10. Auxiliary Feedwater Flow Rate 1/ pump 1/purp
- 11. Reactor Coolant System Subcooling Margin Monitor 1 0
- 12. Pressurizer PORV Position Indicator $ 2/ valve 1/ valve
- 13. Pressurizer PORV Block Valve Position Indicator ** 2/ valve 1/ valve
- 14. Safety Valve Position Indicator. 2/ valve 1/ valve
- 16. In Core Thermocouples 4/ core quadrant 2/ core quadrant "Not applicable if the associated block valve is in the closed position.
- Not applicable if the block valve is verified in.the closed position with power to the valve operator removed.
TABLE 4.3-7 .
1 iE . ACCIDENT MONITORIN3 INSTRUMENTATION SURVEILLANCE REQUIREMENTS S!
E CHANNEL CHANNEL CHECK CALIBRATION c: INSTRUMENT i'i R
.l . Reactor Coolant THot (Wide Range) M
-]
- 2. Reactor Coolant TCold (Wide Range)
M R
- 3. Containment Pressure ,
Refueling Water Storage Tank Level M R
- 4. .
M R
- 5. Reactor Coolant Pressure M R
- 6. Pressurizer Level .
w R 3; 7. Steam Line Pressure M .
M R
- 8. Steam Generator Level - Wide
- 9. Steam Generator Level - Narrow Ji R R
- 10. Auxiliary Feedwater Flowrate M Reactor Coolant Systam Subcooling M R 11.
Margin Monitor R
- 12. Pressurizer PORV Position Indicator li M R
- 13. Pressurizer PORV Block Valve .
Position Indicator R ,
____ .__14. . Safety Valve Position Indicator M In Core Thermocouples M R _
16.
.TAllLE 3.3-3 (Continued)
X Et: Git.!ERED SAFETY FEATilRE ACTU.iTI0tl SYSTEt1 It3STRUr-tErlTAT10t1
= I4111111HM CllAtif3ELS CilArillELS APPLICAllLE TOTAL t10. ACTIOri g OF CilArirJELS 10 ll!IP OPE RAllt E t100ES g FUNCTIONAL UtilT 7 LOSS OF POLKR 4
- d. 6.9 kV Shutdown Board 1, 2, 3, 4 20"
- 1. ' Loss of Voltage 2/ shutdown 1 loss of 2/ shutdown -
board voltage on board -d any shutdown board 20*
2/ shutdown 1, 2, 3, 4
- 2. Load-Shedding 2/ shutdown 1/ shutdown board board board g 6 D Ef1 git 4EEllET) SAFETY FEATURE g 8.
- ACTUAT10t1 SYSTEtt Itif ERLOCKS 4
~ 22a 2 1, 2, 3 Pressurizer Pressure, 3 2
a.
P-11 3 1,2,3 22b
, P-12 4 2
- b. T 3/ loop 1, 2 22c 3/ loop 2/ loop
- c. Steam Generator
. Level, P-14 any loop
~
Note: Manual switchover of RHR pump suction from the RWST to containment sump will be employed until containment sump level indicators are-returned OPERABLE.
Automatic switchover is not required OPERABLE'during the interim.
i1 . . .. .._ ._. . . _ _ . . .
M o
g liiBLE 3.3-4 (Continued}
5 E!Gir4EERfD SAFETY FE ATURE ACitlATICit SYSIUt lil5lRt!Mf fiTAlI0ft TRIP SETP0ltlTS
'.E SE ALLOWABLE VALUES TulP SEfP0ltiT 5 Fut4CT10t1AL titill
- 8. EllGINELRLD AFElY FEATilRE ACTUAT10t1 SYSTEl1 littli:t OCKS (Continued)
- b. E d'T. vents !!anual Block of Safety in jection P-12 5 540 F $ 542 F
- c. T d v,)
hanual Blu % of Safety Injection, Stewa Line Isolation, Block Steam
> 540 F > 538 F Du:ap l i 4 d. Steam Generator Level (f lurbine Trip, Feedsater Isolation ,
y P-14 (See 5. above) 5 4
. . . .. . .. . . - .--.. ..... -- ,.-_--- . .- -. ...- ._ ... - . -- -.-. -.- - . ~- . . . - . . . - -- - . . .
4 f1l':. f. -
- z. 9 .
!. m TABLE 4.3-2 (Continued) ,
1 m j ENGI!1EERED SAFETY FEATURE ACTUATIO!! SYSTEtt Ill5TRUf4ENTATION
, g SURVEILLAtlCE REQUIREf:ENTS .
i =
4 c CHANNEL H0 DES FOR M11CH
- 5. . CHANNEL CHANNEL FUNCTIONAL SURVE!LLANCE IS FUNCTIONAL UNIT CilECK ' CAllBRATION TEST REQUIRED-
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5
- ACCIDLili MONITORiflG INSTRUMilll A110N SURVElll AtiCE REQUIREMENTS
'E CllANNEL CHANi4EL Q CllECK CALIBRMION m INSTRUMENT M R
- 1. Reactor Coolant Tilot ( de Range) l H R
- 2. Reactor Coolant-TCold (We Range) .
H R
- 3. Containment Pressure
, l M R
- 4. Refueling Water Storage Tank Level H R S. Reactor Ccolant Pressure M R w 6. Pressurizer Level ';
2 .M R
- 7. Steam Line Pressure
- o. R
$ M j
- 8. Steam Generator Level - (Wide)
M R
- 9. Steam Generator Level - (Narrow) 11 R
- 10. Auxiliary Feedwater Fiowrate M R
- 11. Reactor Coolant System Subcooling Margin Monitor
!! R
- 12. Pressurizer PORV: Position Indicator M R
- 13. Pressurizer PORV Block Valve
- 14. Safety Valve Position Indicator '
I M R
.16. In Core thermocouples
ENCLOSURE 2 JUSTIFICATION FOR PROPOSED TECHNICAL SPECIFICATIONS SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 A problem has been identified concerning containment sump wide range level instrumentation at Sequoyah units 1 and 2. The instrumentation has been evaluated, and it has been determined that the instrumentation will fail in harsh environments. Failure modes include: (1) off-scale high, (2) indication higher than true level, and (3) indication lower than true level.
The estimated time required to modify the instrumentation is approximately 30 days.
The containment level instrumentation is designed to perform two different functions: (1) input to the logic which controls automatic switchover of emergency core cooling systems' suction from the RWST to the sump, and (2) r postaccident monitoring, including accident diagnosis. The safety implications of losing each of these functions are addressed below.
Automatic Switchover The logic for automatic switchover from RWST to the containment sump requirca all of the following: (1) Safety Injection (SI) signal, (2) two out of four RWST level channels indicating below 130" level, and (3) two out of four containment sump level channels indicating at least 30" above elevation 680'. ,
The reason for the sump level input to this logic is to prevent early switchover due to spurious RWST level signals or due to a break in the RWST (postulated to be caused by a MSLB close to the RWST). However, the 2/4 logic of the RWST level inputs provides assurance that a spurious signal will not cause premature switchover (i.e., a single instrument failure would not cause early switchover). Many other Westinghouse Electric Corporation plants do not have containment sump level input to their switchover logic; this input was designed to provide an extra mergin of safety against early switchover at Sequoyah. Although it is beneficial Lo-have, we believe the plant can be safely operated, and accidents safely mitigated without this extra margin.
The postulated accident which causes an RWST rupture is a steam line break" in the vicinity of the tank, with subsequent violent pipe whip. If automatic switchover relief on low RWST level alone, then the arction would switch to the empty sump almost inmediately, rather than continuing to pull water from the moat around the RWST. The sump level logic input was designed to prevent this.
9
. e ENCLOSURE 2 JUSTIFICATION FOR PROPOSED TECHNICAL SPECIFICATIONS SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2
Therefore, in the interim, we recommend that the automatic switchover logic be defeated in favor of manual switchover. Based on worst case accident conditions, RWST volume of 370,000 gallons, full ECCS system flow, and switching at 29 percent level, the switchover will not be necessary until approximately 14 minutes into the accident. Therefore, the operator will have sufficient time to perform the manual action in a timely fashion.
Further, even with inoperable containment sump level indication, containment sump inventory can be verified by the presence of adverse containment conditions .(i.e., pressure, radiation, and~ temperature).
Postaccident Monitoring The containment sump level instrumentation is presently used by the operator to help diagnose what accident is in progress and to help monitor the automatic switchover to the sump. After accident diagnosis and
- switchover, the only foreseeable use of the sump level instrumentation is to verify a leak in a component of the emergency core cooling systems during recirculation mode operation.
The diagnostic function which the sump level instrumentation serves is to aid in determining whether or.not a line break exists inside containment.
It in used in conjunction with containment pressure and radiation for this function; it is by no means the sole parameter upon which the diagnosis is based. The containment pressure and radiation parameters alone provide the operator sufficient information to make the diagnosis. Therefore there is no safety problem, with regards to accident diagnosis, caused by the inoperability of the containment sump level instrumentation.
The automatic switchover function is addressed in the preceding section.
According to present emergency operating instructions, the sump level ,
indication, in conjunction with RWST level, merely shows the operator when automatic switchover should be taking place. If manual actions are to be taken, the operator can rely on RWST level alone.
According to the Sequoyah FSAR (section 6.3.2.11), containment sump level Indication in not needed to verify an ECCS leak. Three independent means are available to provido information to the operator for use in identifying ECCS leakage. These include the auxiliary building flood detection system, the instrumentation and alarms associated with the drainage and waste processing system, and the auxiliary building passive sump level alarm instrumentation. Therefore we see no safety problem, concerning ECCS leak detection, caused by the inoperability of the sump level instrumentation.
Operational Limitations or Actions
- The following actions should be taken to ensure safe operation until the l containment sump level instrumentation is modified, t
- 1. The logic for automatic switchover of ECCS suction from the RWST to the containment sump shall be defeated such that the switch can only be l performed manually.
l l
(
f
- 2. The E0Is should be revised to reflect the change from automatic to manual switchover. Manual switchover should not be performed until there is positive indication of abnormal containment conditions in conjunction with low RWST level. This will preclude the possibility of early switchover in the event of RWST rupture (as postulated above).
The E0Is should also be evaluated for any changes necessary to preclude reliance on containment sump level instrumentation in the event of adverse containment conditions.
Conclusions Dased on the above safety evaluation, continued operation of Sequoyah Nuclear Plant units 1 and 2 is justified provided the above operational limitations and actions are implemented. This change is being reviewed by the Nuclear Safety Review Board.
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