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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
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PROPOSED TECHNICAL SPECIFICATION. CHANGE- a r; ~
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01/05/1990 10 53 SCN SITE DIRNSITE LIC' 613 843 7139 P.04 i
- C 314.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
a.
Two physically independent circuits between the offsite transmission network and the onsite Class IE distribution system, and
- b. ,
Four separate and independent diesel generator sets each with:
1.
Two diesels driving a common generator 2.
Twogallons 250 engine of mounted fuel, perfuel tanktanks containing a minimum volume of
- 3. A separate fuel storage 62,000 gallons of fuel, system containing a minimum volume of
- 4. A separate fuel transfer pump, and
( 5.
A separate 125-volt 0.C. distribution panel,125-volt D.C.
battery bank and associated charger.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
34M W" ~
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Wth either an offsite circuit or diesel generatorb of the above
' required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillanc Requirements 4.8.1.1.1.a within one hour and at least once per 8 R10, hou thereaf ter, and Surveillance Requirement 4.8.1.1.2.a.4 within 24 h restore at least two offsite circuits and four diesel generator sets i to OPERABLE status within 72 hours or be in at least HOT S within the next 6 hours and in COLD SHUTDOWN within the followi i
30 hours.
b.
With one offsite circuit and one diesel generator set of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveilla Requirements 4.8.1.1.1.a within one. hour and at least once per R104 B ho!
(
thereaf ter, and Surveillance Requirement 4.8.1.1.2.a.4 within 8 hj restore at least one of the inoperable sources to OPERABLE status -
within'12 hours or within and in COLD SHUTDOWN be intheatfollowing least30HOT hours. STAN0BY within the ;
Restore at leas,t !
within 72 hours from the time of initial loss or be in STANOBY 30 hours. within the next 6 hours and in COLO SHUIDOWN wi SEQUDYAH - UNIT 1 3/4 8-1 Amendment No.100 January 31, 1989
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, .i 314.8.1 A.C. SOURCES OPERATING
.a ~ s LIMITING CONDITION FOR OPERATION . . .
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. . , . 3. 8.1.1 OPERABLE: As' a minimum,' the following A.C. electrical power sources shall b 4.
b.
network and the onsite Class IE distribution sys Four separate and independent diesel generator sets each with:
1.
Two diesels driving a common generator 2.
250 gallons of fuel, per tankTwo engine-mounted fuel tan
( 3 A separate 62,000 gallons fuel storage system containing a minimum volume of of fuel,
,; 4.
A separate fuel transfer pump, and 5.
battery bank and associated charger.A separate 125 l APPLICABILITY: MODES 1, 2, 3 and 4.
f ACTION: .
.5db M A Mn #M S
- a. -
' /v With either an offsite circuit or diesel generatorb'etr o of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surv Requirem nts 4.8.1.1.1.s within one hour and at least once per 8 h thereafter, and Surveillance Requirement 4.8.1.1.2.a.4 within g, 2 restore at least two offsite circuits and four diesel generator sets to OPERABLE status within 72 hours or be in at least HO 4
'30, hours.within the next 6 hours and in COLD SHUTDOWN with i
- b. Wi
' th one offsite circuit and one diesel generator set, of the abo required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surve
. Requirements 4.8.1.1.1.a within one hour and at least once per 8 .
thereafter, and Surveillance Requirement 4.8.1.1.2.a.4 within R89 restore at least one of the inoperable sources to OPERABLE status within and in C0LD 12SHUTDOWNhours orwithin be the in following at least HOT STANDBY with 30 hours.
Restore at least within 72 hours from the time of initial loss or b -
STANDBY 30 hours. within the next 6 hours and in COLD SHUTDOW '
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SEQUOYAH - UNIT 2 -7., ,,o
, , 3/4 8-1 Amendment No. ..-
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PROPOSED TECHNICAL SPECIFICATION CHANGE 3 J. -
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LL .SEQUOYAH-NUCLEAR PLANT UNITS ILAND.2:
DOCKET NOS,l50-327 AND'$0-328- :
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F , DESCRIPTION:AND' JUSTIFICATION FOR "
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Description of Change-Tennessee' Valley Authority proposes to modify the Sequoyah Nuclear Plant (SQN) Units 1 and 2 technical specifications (TSs) to revise Action Statement a of Limiting Condition'for Operation (LCO) 3.8.1.1 to allow operation to continue with diesel generator Set (s) 1A-A and/or 2A-A or IB-B and/or 2B-B-inoperable provided all four diesel generator sets are
_ returned,to operable status within 72 hours. This change provides consistency with otner action-statements for loss of a train of safety equipment.
o Reason for Change _
The action st:w nts of LC0 3.8.1.1 are laterna11y inconsistent in that
, Action a alloa antinued operation for 72 hours with a single diesel-generator set inoperable, whereas Action d allows operation to continue-for the same period of time with two diesel generator sets inoperable provided both diesel generator sets are on the same train (i.e., IA-A and 2A-A or.IB-B and 2B-B). The requested change to Action a of LCO 3.8.1.1 provides consistency within the LCO as well as consistency with similar LCOs that have actions writi)n with regard to " equipment train" availability.
Justification for Change The operability of the alternating current (ac) power sources during operation ensures that sufficient power will be available to supply the safety-related equipment required for the safe shutdown of the facility and the mitigation-and control of accident conditions within the facility. The requirements of General Design Criterion 17 of Appendix A
- to 10 CFR 50, which specify the minimum independent and redundant ac power sources, continue to be met with the proposed change to LCO 3.8.1.1 Action a.
The action requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation commensurate with the level of degradation. The operability of the power sources is consistent with the initial condition assumptions of the safety analyses ar.d power source operable during accident conditions coincident with an assumed loss of offsite' power and single failure of the other onsite at source.
The proposed change provides clarification as to the combinations of diesel generators that can be Inoperable simultaneously for 72 hours. The combinations are trained to provide consistency within LCO 3.8.1.1 as well as with other LCOs that are based on trained equipment. This TS change will make the diesel generator LCO consistent with LCO 3.7.4, " Essential Raw Cooling Water System (ERCH)" for Unit 1. LCO 3.7.4 provides a 72-hour period for recovery from a loss of one train of ERCW. The Unit 1 ERCH
~=.. ...
t.x u e iL. ' headers provide the primary cooling water supply for both the Unit 1 and Unit 2 diesel generators (the 1A'ERCH header supplies the IA-A and 2A-A
. diesel generators and the 1B ERCH header suppl'?s the IB-B and 2B-B diesel '
generators) as can be'seen,on final Safety Analysis Report' figure 9.2,2-1. 'Therefore, under the.present SQN TS, the action time for a LUnit 1 ERCH header outage would be limited by LCOs 3,8,1.1 and 3.0,3
- .because of the. operability requirements for the diesel generators.
' Environmental' impact Eval'uat1on The pro'posid change request does not involve an unreviewed environmental l question because operation of SQN Units 1 and 2 in accordance with this change would not:
- 1. Result in a significant increase in any adverse environmental impact previously evaluated in the final Environmental Statement (fES) as modified by the Staff's testimony to the Atomic Safety and Licensing Board,' supplements to the FES, environmental impact appralgals, or
," -decisions of the Atomic Safety and Licensing Board, 2, Result in a-significant change in effluents or power levels,
- 3. Result'tr matters not previously reviewed in the licensing basis for
=SQN that may have a significant environmental impact.
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f DETERMIN TIO.N~0F NO SIGNIFICANT -HAZARDS CONSIDERATIONSI Rj
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e ENCLOStJRE 3 Significant Hazards Evaluation
- TVA has evaluated the proposed TS change and has determined that it does
..not represent a significant hazards consideration based on criteria established in 10 CFR 50.92(c). 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 revision to LCO 3.8.1.1 Action a provides an action for ;
diesel generator inoperability based on power trains rather than !
individual diesel generator sets. The requirements of General Design li Criteria 17 of' Appendix A to 10 CFR 50, which specifies the minimum independent and redundant ac power sources, continue to be met by the proposed revision. The action requirements specified for the levels-of degradation of the power sources provide restriction upon continued facility operation commensurate with the level of degradation. The operability of the power sources is consistent with the initial condition assumptions of the safety analyses and is based ,
upon maintaining at least one onsite ac power source operable during j accident conditions with an assumed loss of offsite power and single :
failure of the other onsite ac source. This change has no impact on 1 the probability or consequences of any accident previously evaluated. l (2) Create the possibility of a new or different kind of accident from any previously analyzed, j The proposed revision to LCO 3.8.1.1 Action a provides an action for 1 diesel generator inoperability based on power trains rather than individual diesel generator sets. No physical plant modification is l being made, and no analyses are being changed. Therefore, the I proposed change does not create the possibility of a new or different l' kind of accident from any previously analyzed.
(3) Involve a significant reduction in a margin of safety.
The proposed revision to LCO 3.8.1.1 Action a provides an action for diesel generator inoperability based on power trains rather than individual diesel generator sets. No physical plant modification is '
being made, and no analyses are being changed. The action requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation commensurate with the level of degradation. The operaillity of the power sources is consistent with the initial condition assumptions of the safety analyses and is based upon maintaining at least one onsite ac power source operable during accident conditions coincident with ;
an assumed loss of offsite power and single failure of the other onsite at source. Therefore, the proposed change does not involve a reduction in any margin of safety. j l
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