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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
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ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SON-TS-94-07, SUPPLEMENTAL)
LIST OF AFFECTED PAGES I Unit 1 3/4 7-1 Unit 2 I
3/4 7-1 I i.
9502140346 950210 POR ADOCK 05000327 P. PDR
3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE pFETYVALVES LIll! TING CONDITION FOR OPERATION (stssVd 3.7.1.1 AH g+ein steam linc x 2 safety valves ::::ict s ith och 5tes-
-g:ra ctor shall be OPERABLE wi 'ft settings as specified in Table 3.7-APPLICABILITY: V00E5 1, 2 a M ACTION: ,
- a. Wi 4 teactorholant loops hd associate teamgenethrsin ope tici and wi one or more in steam lin code safety alves e,e inope b 4 , operat n in MODES 1, 2 and 3 may p ceed provi , that within hours, eith r the inopera e valve is re tored to OPERABLE Mfe"p g status 0; the Power R ge Neutron F1 High Setpoi trip is re ed per T:. ole 7-1; otherw e, be in at I ast HOT STAND within the next 6 haur and in COLD UTDOWN withi the following 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.
W h 3 reactor colant loops nd associate in g.d
- b. team generato op ation and wi one or more main steam lin code safety v ves K
. asso 'ated with an perating lo inop,erabl e , eration in MOD 3 Rll "
may pr eed provide that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, eithe the inoperable valve is restored to ERABLE stat or the Power nge Neutron F1 High Trip etpoint trip is reduced p Table 3.7-2; therwise,bein\ ,
t least H STANDBY wit 'n the next hours and in C D SHUTDOWN t
" thin the f lowing 30 ho s.
- c. The rovisions Specificati 3.0.4 are n t applicable. ,
i.
SURVEILLANCE RE0VIREMENTS ;
4.7.1.1 No additional Surveillance Requirements other than those required by Specification 4.0.
With +he. r 4ch>r e + rip sp+e m brakes k the dosed '
p:Fo.s, kk l SMUOYAH - UNIT 1 3/4 7-1 Amancments No.114 May 5, 1959 l
r*-
3/4.7 PLANT SYSTEMS I 3/4.7.1 TURBINE CYCLE
. SAFETY VALVES Ll.ilTING CONDITION FOR OPERATION
"' g::in steam linc adc safety valves (M SS %)
3.7.1.1 ;;;icted itF och ; team gener:te shall be OPERABLE with lif t settings as specified in Table 3.7-/
2.
APPLICABILITY: Modes 1, 2 an 3N ACTION:
_ _-w ctor co lant loops and a ociated stea enerators in eration and with e or more main eam line code afety valves g& i erable, operation 'n Modes 1, 2 an 3 may procee rovided, that 5 wit 'n 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either e inoperable va e is restore o OPERABLE
,sd statu or the Power Range eutron Flux Hig Trip Setpoint 's reduced
\ per Tab next 6 hou 3.7-1; otherwise, e in at least H STANDBY with and in COLD SHUT WN within the fo lowing 30 hou the
- b. ith 3 reactor colant loops and sociated steam g erators in op ation and wi one or more main team line code s ety valves
) asso lated with an perating loop inop rable, operation 'n MODE 3 may p eed provide , that within 4 hou either tM ino rable valve i estored to O RABLE status or th Power Rar.p Neu on R I.
Flux High ip Setpoint ' reduced per Table 3.7-2; otnerwise, be in at le HOT STANDB ithin the next 6 h rs and in COLD cHUT00WN with1 the followin 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
I
- c. The rovisions of ecification 0.4 are not applic le.
\- _
SURVEILLAhqEREQUIREMENTS 4.7.1.1 No additional Surveillance Requirements other than those required by Specification 4.0.5.
q M N u^
% yu +ke reaek Wp sySh bel (en in +he dwed ,
p osn;m.
^
U
}
SEQUOYAH - UNIT 2 3/4 7-1 Amendment No. 104 May 5, 1989 l l
-i t
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ENCLOSURE 2 t i
PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE -
SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2 - l DOCKET NOS. 50-327 AND 50-328 i
(TVA-SON-TS-94-07, SUPPLEMENTAL) !
DESCRIPTION AND JUSTIFICATION FOR .
i LIMITING MODE 3 APPLICABILITY .
i e
t 9
6 l
i i
l l
-- . --,:-- .m__._. -- -. _- . .---- - - . ..)
P Descriotion of Chanae TVA proposes to modify the Sequoyah Nuclear Plant (SON) Units 1 and 2 technical specifications (TSs) as originally proposed by TS 94-07. Specifically, ,
TS 94-07 is supplemented by modifying the mode of applicability such that Mode 3 is constrained to require the reactor trip breakers to be closed. The supplementalinformation provided is to add an asterisk to the Mode 3 [
applicability, which is annotated as follows: >
"*With the reactor trip system breakers in the closed position." !
Reason for Chance TS 3.7.1.1 requires the Nuclear Instrumentation System (NIS) high-neutron flux trip setpoint to be lowered if one or more main steam safety valves is determined to be inoperable. This TS is applicable in Modes 1, 2, and 3. >
However, reduction of the NIS trip setpoint with the reactor trip breakers (RTBs) open is an administrative burden, which provides no added safety benefit. ,
Justification for Chanaes [
The intended function for the NIS high-trip setpoint is to open the RTB upon detection of a neutron flux corresponding to certain required analytical limits.
With the RTBs open, the intended function is already complete. In this ;
configuration, adjustment of the NIS trip setpoint provides no added safety benefit. ,
Environmental Impact Evaluation The proposed change does not involve an unreviewed environmental question because operation of SON 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 EnvironmentaljStatement (FES) as modified by NRC's testimony to tha Atomic Sakty and Licensing Board, supplements to the FES, environmental impact appraisals, or decisions of -
the Atomic Safety and Licensing Board.
- 2. Result in a significant change in effluents or power levels.
- 3. Result in matters not previously reviewed in the licensing basis for SON that may have a significant environmentalimpact.
i I
i ENCLOSURE 3 I PROPOSED TECHNICAL SPECIFICATION CHANGE l 4
SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2 l DOCKET NOS. 50-327 AND 50-328 (TVA-SON-TS-94-07, SUPPLEMENTAL)
DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION ' -l l
1 l
l 4
l I
, Significant Hazards Evaluation l TVA has evaluated the proposed technical specification (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 Sequoyah Nuclear Plant (SON) in accordance with the proposed amendment will not:
- 1. Involve a significant increase in the probability or consequences'of an accident previously evaluated.
This change reduces the power level at which the reactor may be operated :
with one or more main steam safety valves (MSSVs) inoperable, to ensure '!
that the secondary system is not overpressurized during the most severe l pressurization transient of the secondary side. Additionally, this change ;
will combine the TS action statements for 3- and 4-loop operation with one ;
or more MSSVs inoperable, revise the mode requirements and times of 7 Action Statement 3.7.1.1.a, and correct a reference in the bases section E to Table 3.7-1. Reduction of the high neutron flux (HNF) trip setpoint will ;
continue to be used as the means to ensure that the required reactor I power level reductions are met. Mode 3 will be limited to application j whan the reactor trip breakers (RTB) are closed. Lack of NIS trip setpoint !
adjustments with the RTB open has no effect on the accident analysis. l There is no change to the function of the MSSVs by the proposed change. !
This change will not alter any accident analysis assumptions or results for SON. The proposed change will reduce the amount of relief capacity I required to mitigate the consequences of the transient by reducing the i total amount of energy in the primary system. Therefore, this change will not increase the probability of an accident.
1 This change is consistent with current SON accident analysis assumptions i for the MSSVs and does not change the containment response for any )
design basis event. Therefore, no change in the mitigation of an accident- 1 will result from this proposed change and no change will occur in the ;
consequences of any accident currently analyzed. j
- 2. Create the possibility of a new or different kind of accident from any !
previously analyzed. I I
Inadvertent opening of a MSSV is currently analyzed es an initiating event for accidental depressurization of the main steam system. The proposed
- b. ,
& +
i change does not alter the valves or any other plant component. The l valves will continue to perform as analyzed in current accident analyses. ]
The proposed change will not create the possibility for any new or different kind of accident. . !
i By retaining the use of the HNF trip setpoint reduction, no change is being !
proposed in the methodology used to ensure that power reductions are carried'out; therefore, this will not create the possibility of placing the :
plant into any new unanalyzed condition. Not adjusting the Nuclear Instrumentation System trip setpoint with the RTBs open will not create an !
accident. The existing accident analysis is still bounding. l Combining the separate action statements for 3- and 4-loop operation into !
I a single action does not create the possibility for a new or different kind of accident. Operation with 4 loops will continue to be required in Modes 1 .
and 2 by TS 3.4.1.1. Operation with less than 4 loops will continue to be governed by TS 3.4.1.2 in Mode 3 and TS 3.4.1.3 in Mode 4. This change will not place the plant in a configuration not currently bounded by :
existing acciaent analysis. i Revising the roode requirements and their associated times, consistent ' !
with the requirements in NUREG-1431, will continue to ensure that if the i unit is unable to comply with the limiting condition for operation, the unit !
will begin an orderly shutdown until a mode is reached where the I specification is not applicable. !
i
- 3. Involve a significant reduction in a margin of safety. ;
i The proposed change reduces the total energy of the reactor coolant _
]
system that will ensure the ability of the MSSVs to perform their intended function as assumed in current accident analyses. This change has been .
g evaluated on a generic basis for Westinghouse Electric Corporation :
designed 4-loop nuclear steam supply systems. SON plant specific .
j features have been evaluated including power limit calculations and the j interaction of the reactor protection system trip time delay and the - ;
anticipated transient without scram mitigating system actuation circuitry. . 'l Correcting this nonconservatism restores the margin of safety to what was -l originally envisioned. Therefore, the margin of safety assumed in the !
accident analysis is not reduced by this ghange. !
l
.(
7 5
. Combining the separate' action statements for 3- and 4-loop operation into a single action has no effect on the margin of safety for 4-loop operation .
with one or more MSSVs inoperable. Under the revised TS, 3-loop operation with one or more MSSVs inoperable would only be allowed in .
Mode 3, and 4-loop operation will be required in Modes 1 and 2 in ,
accordance with current TSs 3.4.1.1 and 3.4.1.2.
Revising the mode requirements and their associated times, consistent with the requirements in NUREG-1431, will not reduce the safety margin since the new requirements will continue to place the unit in a mode where the TS is no longer applicable. The new completion times for mode changes are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner without challenging unit systems. :
The margin of safety is unaffected by modifying the limits of Mode 3 applicability to require the RTBs to be closed as the intended safety function is already completed when they are open.
i
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