|
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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
-. _ - _ _ . _ _ _ _ ..__
i CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION
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APPLICABILITY: MODES 1, 2, 3 and 4+.
1 ACTIOM:
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j g With one4 containment spray p W inoperable, rest re the inoperable spray i %., p'n to OPERABLE status within 72 hoyrs or be in 07 STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the inoperable spray ?.M^= to OP RABLE status within the gi i next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD S}lVT00WN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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SURVEILLANCE REQUIREMENTS i c, s 1.n e.u
- 4.6.2.1 Each /ontainment Jrpray .pt= shall be demonstrated OPERABLE
- a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked,
] sealed, or otherwise secured in position, is in its correct position.
- b. By verifying, that on recirculation flow, each pump develops a discharge pressure of greater than or equal to 140 psig when tested i !
pursuant to Specification 4.0.5.
- c. At least onco per 18 months during shutdown, by
- 1. Verifying that each automatic valve in the flow path actuates to its correct positinn on a Containment Pressurr -- ligh-liigh test signal,
- 2. Verifying that each spray pump starts automatically on a Containment Pressur #->81gh liigh test signal.
Eddc h 4%W s A towr er spast
- d. At least once per 5 years by performing an air or smoke flow test thrnuyh each spray header and verifying each spray nottle is M1 c b unobstructed.
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n.e p, Md I m MDC N g epenceurv of T2.62. hn's %' "(MAR 2 5 1982 l
SEQUOYAll UNIT 1 3/4 6-16 Amendment No. 1' 8704140328 B70405 PDR ADOCK 05000327 p PDM
. i
l CONTAINMENT SYSTEMS i
3/4.6.2 OEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM t L
i LIMITING CONDITION FOR OPERATION r
'9.t1NJ w 4b 3.6.2.1 1: ' /:;;rt:-t : :nt:' :--t :;r:-j ,:t:r: : :!' :: ? !MSL! -!th :::n !
o M 'g :; :, ;,:t;r ::;;:4 ;' :: 'ng :. ti:r '.r:r th: '" U : d tr;::';r ' ; :::1!:n 1; in; c::::t ::nt ;.
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4 APPLICABILITY: MODES 1, 2, 3 and 4 d yk s&) St"'T I
i ACT!0N:
u ne'. ~
with oneA:onta19 ment spray 4W inoperable, restore the inoperable spray j M*4 :,:::m to CPERABLE status within 72 nours or be in at least NOT STANDBY witnin the next 6 nours; restore tre inopersole spray @s to OPERABLE status 41 thin the nest 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTOChN ilthin the following 30 nours, SURVE!LLANCE 4E00!9E4!4TS 1
l C 5 An..u 4.6,/.1 Eich /ontalsment / pray a shall ce demonstrated CPERABLE:
- o At least once per 31 days by verifying that eacn valve (msnual, power operated or tutomatic) in tno ficw patn that is not locked sealed, or otnerwise secured in position, is in its correct positon.
D By serif / ing, that on recirculation flow, eacn pumo develoos a 1 Jischarge pressure of .ireater than or equal to 140 psig wnen tested ;
l pursuant ta icectficat*cq 4.0.5. I
- c. At least once per 18 montns during shutdown, by:
i
). Verifying that enen nutomatic valve in the flow patn actuates to its carrect position on a Containment Pressure Hign-Hign I i test signal.
l 2, Verifying tnat eacn soray pump starts lutamatically on i Canttinment Pressure Hign Hign test signal.
At least ance per 5 ,oirs Dy performinij an at e or smone f t:w test 2,
through elan lorly helder and verifying dach spr3y noz:le it A M a.%Ld unon s t e t.c t d >J.
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SEGUCVAH UNII J 3/4 0'10
\.
3.6.2.1 Two independent trains of both the containment spray and residual heat removal spray shall be OPERAdLE with each train comprised of:
- a. A Containment Spray train with:
- 1. One OPERABLE Containment Spray pump, !
- 2. One OPERABLE Containment Spray heat exchanger,
- 3. An OPERABLE flow path capable of taking suction from the refueling water storage tank and transferring suction to the containment sump, and
- b. A RHR Spray train with:
l
- 1. One OFERABLE residual heat removal pump, .
- 2. One OPERABLE residual heat removat heat exchanger, and
- 3. An OPERABLE flow path capable of taking suction from the containment sump.
1 1
1
_________________________J
! 4.6.2.2 Each RHR spray train shall t'e demonstrated OPERABLE:
1 i
- a. Per surveillance requirements 4.5.2.b.2 and 4.5.2.f.3;
- b. At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unolstructed.
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ENCLOSURE 2 PROPOSED TECHNICAL SPECIFICATION CHANGE I
SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 i
i DOCKET NOS. 50-327, -328
] (TVA SQN TS 87-03)
DESCRIPTION AND JUSTIFICATION FOR PROPOSED ADDITION OF RHR SPRAY REQUIREMENTS I TO SECTION 3/4 6.2 J
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DESCRIPTION OF CHANGE
- This change revises section 3/4.6.2 on page 3/4 6-16 of units 1 and 2 technical specifications. Limiting Condition for Operation (LCO) 3.6.2.1 is revised to specifically require the operability of both trains of Residual 4
Heat Removal (RHR) spray. The associated action statement and surveillance requirements are revised accordingly. The applicability statement is revised i to exempt the operability requirements for the RHR Spray in Mode 4. The j existing surveillance requirement (SR) is expanded to clearly identify SRs for
- both the RHR spray and containment spray (CS) trains. Additionally, two editorial changes are made to the action statement and SR 4.6.2.1.c of only i the unit 1 technical specifications.
REASON FOR CHANGE.
The Sequoyah Design Criteria and the Sequoyah FSAR state that one train of RHR spray is needed if a design basis LOCA has occurred and only one train of ,
J containment spray is available (assuming a single failure had disabled the other train of containment spray). While operability of both RHR trains during Modes 1, 2, and 3 is currently ensured by LCO 3.5.2, the applicable
^
operability requirements for the RHR spray train should also be stated in 1 LCO 3.6.2 to establish consistency between the containment spray system
! requirements in the technical specifications and the requirements discussed in the Sequoyah Design Celteria and FSAR. The two editorial changes made in the unit 1 technical specifications will make the technical specifications consistent with the unit 2 technical specifications and the St'andard Technical _
- Specifications for Westinghouse Pressurized Water Reactors, NUREG-0452, ~*
, Revision 5, (Draft). :
JUSTIFICATION FOR CHANGE The proposed change does not compromise nuclear safety. The operation of the
, plant is not altered. The containment spray system for each unit at Sequoyah
! includes four spray headers. Two of these headers belong to redundant trains
]'
of containment spray. Each containment spray train has a dedicated pump and heat exchanger, and each train is capable of delivering 4,750 spa of spray.
Containment spray is automatically initiated upon the hi-hi containment
! pressure signal. The other two headers belong to redundant trairis of RHR j spray. A total of 2,000 gpm of RHR spray can be provided by either train of
! the RHR system. RHR spray can only be' initiated by manual valve
{ manipulations. The proposed revision will make the containment spray system
, requirements explicitly consistent with the plant's Design Criteria and FSAR.
j While the necessary operability requirements do exist cumulatively in the current technical specifications under LCOs 3.5.2 and 3.6.2.1, this change l will enhance the technical specifications by placing all of the containment spray system requirements in one LCo.
]
l In Mode 4, the RHR system's primary function changes from emergency core
- cooling to shutdown decay heat removal, and the RHR system technical j specification requirements and alignment change accordingly. The following
- evaluation concludes that use of RHR spray will not be necessary in Mode 4.
i 1
l t
4 Assuming a cooldown rate of 500 F per hour, which is stipulated in the General Operating Instruction (COI) -3, " Plant Shutdown from Minimum Load to Cold Shutdown," it would take at least four hours to get from initial 0 0 shutdown (assume tave=550 F) to Mode 4 (maximum tave=350 F).
Per the Function Restoration Guideline, FR-Z, use of RHR spray is prohibited for at least an hour after the initiation of a LOCA. Based on the above, the earliest time for RHR spray initiation following a LOCA occurring in Mode 1 and Mode 4 is one hour and five hours af ter shutdown, respectively. A comparison of the decay heat rates given in the Sequoyah FSAR table 6.2.1-8 for one hour and five hours after shutdown shows that the decay heat rate at five hours is approximately 61 percent of the decay heat rate at one hour. Similarly, the operation of one train of containment spray alone provides 70 percent of the flow rate of one train of containment spray supplemented by one train of RHR spray. Since the decrease in the decay heat rate is greater than the reduction in the containment spray system's capacity, it is concluded that the spray provided by the RHR spray will not be necessary following a LOCA which is initiated in Mode 4. In addition, the amount of initial blowdown energy released in Mode 4 will be significantly less than a design basis event due to the lower prinary coolant temperature.
6 e
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i ENCLOSURE 3 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2
, DOCKET NOS. 50-327, -328 (TVA SQN TS 87-03) :
DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATIONS FOR PROPOSED ADDITION OF RHR SPRAY REQUIREMENTS TO SECTION 3/4 6.2 e
d
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SIGNIFICANT HAZARDS EVALUATION
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
No. The proposed amendment makes the Limiting condition for Operation 3.6.2.1 regarding the containment spray system's requirements explicitly consistent with the Sequoyah Design Criteria and the FSAR design basis LOCA analysis. The Design Criteria and the FSAR state that one train of RHR spray is needed if a design basis LOCA has occurred and one train of containment spray is lost (single failure criterion). While the operability of the RHR spray has been assured by existing surveillance requirements in the technical specifications, these requirements will now be appropriately listed or referenced in the containment spray system section.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
a No. The proposed amendment does not change the plant's design, procedures, or testing. Therefore, it will not create any new accidents.
- 3. Does the proposed amendment involve a significant reduction in a
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margin of safety? . _
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No. The proposed amendment can only enhance safety since it will make the technical specifications clearer in regard to the design requirements for the containment spray system. The margin of safety regarding containment integrity as provided for by the containment spray system is not affected.
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