Proposed Tech Specs,Consisting of Tech Spec Change 88-08, Adding Addl Fire Detection Instrumentation to Table 3.3-11ML20151S795 |
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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: |
08/10/1988 |
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From: |
TENNESSEE VALLEY AUTHORITY |
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To: |
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Shared Package |
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ML20151S794 |
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References |
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NUDOCS 8808160112 |
Download: ML20151S795 (11) |
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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
_ _ _ _ _ _ _ _ _ _ _ _ .-.
1 o
ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAR NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS, 50-327 AND 50-328
, (TVA-SQN-TS-88-08)
LIST OF AFFECTED PAGES These pages also indicate the changes made under TVA-SQN-TS-87-45 Unit 1 3/4 3-61 3/4 3-65 3/4 3-67 Unit 2 3/4 3-65 3/4 3-67 h!k ADOC h7 P
a . d TABLE 3.3-11 (Continued)
FIRE DETECTION INSTRUMENTS Fire Zone Instrument Location Minimum Instruments Ooerable Ionization Photoelectric Themal Infrared 66 Communications Rm. El.
~~ ^ ~ 669,___.__4_ _- --
r ~~~
67'ConunIcationsRm.Ei,609 4 '
68 Mech. Ecuio. Rm. E1. 669 2 69 Mech. Equip. Rm. E1 669 70 2 Aux. Bldg. AS-All, Col. W-X. E1. 669 5 71 Aux. Bldg. A5-A11, Col. W-X, E1. 669 5 72 Aux. FW Pump Turbine 1A-5, El. 669 1 73 Aux. FW Pump Turbine 1A-5, Ei, 669 76 1 S.I. & Charging Pump Rms. E1.'669 77 5 S.I. Pump Rm. lA, E1. 669 1
78 S. I. Pump Rm. 1B, El. 669 1
79 Charging Pump Rm. 1C, E1, 669 1 80 ,
Charging Pump Rm. 1B, E1. 669 1
81 Charging Pump Rm. 1A, E1. 669 1
SS Aux. Bldg. Corridor Al-A8, E1. 669 8 E9 Aux. Bldg. Corridor Al AB,. E1. 669 8 90 Aux. Bldg. Corridor A8-A15. El. 669 8 91 Aux. Bldg. Corridor A8-A15, El. 669 8 i
92 Aux. Bldg. Corridor Col. U-W, E1. 669 4 93 Aux. Bldg. Corrioor Col. U-W, El. 669 4 94 Valve Galley, E1. 669 2
95 Valve Galley, E1. 669 2 -
98 Cntmt Purge Air Fitt., Ei, 690 2 E 99 Cntmt Purge Air Fitt., E1. 690 y ,,,,,g 2 2-102 Pipe Gallery, E1, 690 '
103 Pipe Gallery, El. 690 4 106 Aux. Building, El. 690 8 107 Aux. Building, El. 690 8 103 Radio Chemical Lab. Area, E1. 690 3 (
109 Racio Chemical Lab. Area, E1. 690 3 SEQUOYAH - UNI 7 1 Ryle.- J p' ww 3f 3.g1 gMd 4 ptywd T5 37-45
1
\
I
/ i TABLE 3.3-11 (Continued) \
FIRE DETECTION INSTRUMENTS Fire
!. Zone Minimum Instruments Ooerable Instr _ument location _____--_-- Ionization -Photoelectric
" ' ~ , _ . _ . _ _ _ _ - -
E06 Aux. CR Inst. Rm lA E1, 734 '
Infrared
( 207 1
Aux. CR Inst. Rm. 1A El. 734' 1 203 Aux. CR Inst. Rm. 18 E1. 734 1 209 Aux. CR Inst. Rm. IB E1. 734 1
-1/o Ale. M I,ul R~ .24 ft 7.W I 2// Y 2N kax. CA Imf Am. 2A AL 7J Y l ht g'i'l Aiav.
M .rauf den. 2d 24 7)Y +
2/J Aux.
a I,,1 ,g . an is< 73 y I
Oh j
214 Mech. Eqpt. Rm. E1. 732 215 5 f Hech. Eent Q E1. 732 5 216 CRFitr./El.732 I .
217 CR Fitt.0/ E1. 7S2 I I
218 CRFitt.4/ E1. 732 1 y 7S' M C8 219 CRFitr.4/E1.732 1
? 220 Mai I s
w n cR E1, 732.4-
- ..I .r-ap-r c, 25 221 ed. Stn '!Mt Ei, 732 4- f
. i.m 22., T t.. '.iO.. T,1. f. W.
n . '5.1. . 2 ,i
_~
-2 ": ?:: Oc.;c. She :1. 7 : -
1
-2 ^ *
?:0 :c.;;. ~ha :1. 7:2 225 Reiay Bd. Rm. El. 732 .
j 225 13 Electric Cont. Eds. El. 732 11 227 Oper. Living Area El. 732 22B 7 Oper. Living Area Ei, 732 /
22? Main Cont. Eds. ,
8 230 9 Aux. CR Eds. L-4A, 4C,11A & 10 E1. -M2 73 Y '
.2 D 9 23Y CM ded A E,,4 f . El psp
{ CM fod t.h. sy f /m, ad 7.rp it q
i 235 i
Ctri. Rod Dr. Eq;t. Rm. E1. 759 4 236 Ctr1. Rod Dr. Eqpt. Em. Ei, 759 4 237 Meen. Eqpt. Rm. El. 749 238 He:n Eqpt. Rm. Ei, 749 1 - g ofh cb 4)Y g
1, h T1 D ~ S SEQUOYAH - UNIT 1 3/4 3-65 /?,p /u M /df' JN # '
]
r TABLE 3.3-11 (Continued 1 FIRE DETECTION INSTRUMENTS y17, Minimum Instruments Doerable lene- Instrument - Locati en ~~~~~~~ Ioni:stien Photoelectric ~ Themal . In.frared - ....- ,
273 Computer Rm. Corridor 3 27g te.p e - ,u,. c.,.
r3 coo g gyn e ,c Q EACW i.-me J d. 21. ? U *r a i) 8
- h...u./ i , l TJ 87-2 9 296 Aux. CR Bds 734 L-48, 40, & 11B E1. 45+ 6 U? Obn &i $4. 9 295 C:=en Main CR Bds. EL 732 9 3M_deasAv B.. ld., 4,,,,,, /,,
3 0 ]I Aras6 05a A'~a/as 352 Lwr. Comet. Coolers , E1. 693 ff 35gg.cg 354 ^4 - '
Upr. Comet. Coolers, E1. 778 '
4 356 RCP 2, E1, 693 357 RCP 2, El. 693 2\ l 2
360 RCP 1. El. 693 361 RCP 1. El, 693 2\ l 2
364 RCP 3 El. 693 365 RCP 3, E1. 693 2\ l 2
368 RCP 4, E1. 693 369 RCP 4, E1. 693 , 2\ l 9 -
372 Reactor 51dg. Annulus 373 Reactor Bldg. Annulus )(J2 TS88-00 1
/3 /
357 Turoine Cent. Eidg. Wall, E1. 706 18 .
h ;// e/be c a nyes Mn fo@se' ySWW "5 .-e :rge : ":::< .: _ ;- : ;n 3 2- :<
- ::::::..g ;_:<.:.g._
fepbumed fa*e -V4' )O SEQUOYAH - UNIT 1 3/A 2'07
0 r I Allt E 3.3-11 (Continued) j g I o '
O FIRE DEI [Cil0fl lilSIRilflf flls l E l flRE filfilfftill INS 1Rl#1[Ill5 OPERABLE Infrared 10flE IriSIRilflElli l0 CATI 0tl lonization PhotoelectFIc Ihermal
- n. 196 125-V Ilatt. Bd. Rm. I, El. 734 1 j 197 125-V Ilatt. Ild. Rm. I, El. 734 1 !
198 12's-V llat t. Bd. Rs. II, El. 734 1 I l 199 125-V Ilatt. Bd. Hm. 11. El. 734 I l l 200 125-V Batt. Bd. Re. III, El. 134 1 201 125-V IlaLt. Bd. Rm. III, EI. 734 1
{
3 '
202 125-V ilatt. Bd. Rm. IV, El. 734 1 :
203 125-V Itatt. Bd. Rm. IV, El. 734 1 {
g,/ g]goS 204 Aux. CR El. 734 2 l f [ l R 210 Aux. CR El. 734 Aux. CR inst. Rs. 2A, El. 734 2
1 i
! y e
[,A
- Aux. CR Inst. Rs. 2A, El. 734 I 211 1
';' 212 Aux. CR Inst. Rs. 28. El. 734 I .
l 714 t 3; 213 Augu !::d R=. 2a ,ri 1 CR Iilter /,0El. 732 Iw / BJ Ifs 217 CR filtpr 8El. 732 I
1 I
[ilI 3 @~d 218 CR filter 8 El. 732 . {s 219 - CR Iiiter 8El.732 1 ls 240 flain CH, L1. /3 fr.4..~../ Afy. # (ab 25 2 221 hi--S tor-Vatel t- E l . 732 7 ,,g,,.,,f 4g f 4 -2 6~ ;
222 .Hnt-MotwVaul@ LI. 732 I 2-123 P50-Engr-SitoprH--732 I 1
-224 P50- E ngn--Shopr El---732 ;l 225 Ilelay tid. Rm. El. 732 13 ;
226 Llec. Cont. Ilits. El. 732 11 j 227 Operator Living Area, El. 732 7 ji l
228 operator Living Area, El. 732 73Y i8 I" "' ' 230 Aux. CR Ilds. L-4A, 4C,11 A & 10, El. -732- 9 l 233 CRDil Eqpt. Hm. El. 759 4 ,
2 Citilf f t yp t. Rm. El. 759 4 1 Id>" [ 31 240 39 fleth. t ilp t . Rm. , E l . 749 liet h. Iqpt. !!m., El. 749 2
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s ENCLOSURE 2 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1 Aht 2 DOCKET Nos. 50-327 AND 50-328 (TVA-SQN-TS-88-08)
DESCRIPTION AND JUSTIFICATION FOR TABLE 3.3-11. "FIRE DETECTION INSTRUMENTS" l
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ENCLOSURE 2' '
i Description of Change '
Tennessee Valley Authority proposes to modify the Sequoyah Nuclear Plant ?
Units 1 and 2 Technical Specifications to revise table 3.3-11 to include additional fire detectors as a result of plant modifications _and to correct identified deficiencies.
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Reason-for Change Table 3.3-11 "Fire Detection Instruments," contained in the SQN technical' specifications is being revised to reflect the current plant configuration l as follows:
- 1. Fire zones 98 and 99, unit I containment purge air filter, elevation 690, were modified to have two photoelectric and two thermal detectors in each of the two fire zones.
- 2. Fire zone 331, unit i reactor building annulus, was modified to have four photoelectric detectors.
- 3. Fire zone 372, unit I reactor building annulus, was modified to have !
22 photoelectric detectors. I
- 4. Fire zone 373, unit I reactor building annulits, was modified to have {
21 photoelectric detectors. ,
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- 5. Fire zone 333, unit 2 reactor building annulus, was modified to have '
four photoelect.rie detectors.
- 6. Fire zone 374, unit 2' reactor building annulus, was modified to have i 20 photoelectric detectors.
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- 7. Fire zene 375, unit 2 reactor building annulus, was modified to have l 19 photoelectric detectors.
S. Fire zones 216 and 217, control room filter, were incorrectly identified as train A and should have been train 3.
- 9. Fire zones 218 and 219, control room filter, were incorrectly identified as train B and should have been train A.
Justification for Change The addition of twa thermal fire detectors to each fire zone 98 and 99 uni
- 1 e ntainment purge air filter was made to ensure an effective dete u n methodology. The thermal detectors were added to supplement the smoke detectors in the containment purge filter assembliest which are ,
ineffective when there is no air flow or when the unit is out of service. I i
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The addition of photoelectric detectors to fire zones 331, 372, and 373, unit i reactor building annulus, and fire zones 333, 374, and 375, unit 2 reactor building annulus, was necessary to ensure compliance with 10 CFR 50, Appendix R. As identified in Inspection Report Nos. 50-327/88-24 and 50-328/88-24, the unit 2 reactor building annulus failed to meet the requirements of Appendix R.Section III.G.2. NRC concluded that the fire
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protection-improvements being -added -to -the annulus would provide- adequate - - - - - - -
protection. Therefore, this technical specification change is needed to reflect the addition of the Appendix R fire detectors to the units 1 and unit 2 annuluses.
The discrepancy associated with fire zones 216, 217, 218, and 219 is a result of the technical specification not agreeing with the as-constructed condition of the plant. It was determined in reviewing drawing 47W600-246 that the drawing did not reflect the present plank configuration; therefore, the drawing was changed. This drawing change shows that fire zones 216 and 217 are for the control room train B filter and fire zones 218 and 219 are for the control room train A filter. Therefore, this technical specification change is needed to reflect the as-constructed condition of the plant.
r ENCLOSURE 3 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-88-08)
DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATICNS
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4 ENCLOSURE 3 r
Significant Hazards Evaluation TVA bas evaluated the proposed technical specification change and has determined that it does not represent a significant hazards consideration based on criteria established -in--10 CFR 50.92(e). - Operation- of SQN in - - - - ~ ~ - -
accordance with the proposed stendment will nott (1) involve a significant increase in the probability or consequences of an accident previously evaluated. The fire detection instruments are elements of the early warning fire detection system whose mission is to notify personnel of a fire, actuate automatic suppression systems, and control auxiliary equipment. The addition of fire detection instrumentation will provide increased coverage of the areas monitored by the fire detection warning system, enabling a potential fire to be located and appropriate responses to bs initiated in a more timely fashion than without the instrumentation. The proposed technical specification change amends table 3.3-11 to add fire detection instruments installed as a result of plant modifications and correct a discrepancy to reflect the as-constructed condition of the plant. Thus, the proposed change improves overall plant safety ,
and does not increase either the probability or consequencas of an accident previously evaluated.
(2) create the possibility of a new or different kind of accident from any previously analyzed. The additional fire detection instrumentation increases the ability of plant personnel to identify and take appropriate corrective action in the unlikely event that a fire should occur. Thus, the proposed technical specification change improves the plant's ability to respond to previously evaluated accidents and events and does not create the possibility of a new or different kind of accident from any accident previously evaluated.
(3) involve a significant reduction in a margin of safety. The proposed technical specification change amends table 3.3-11 to add instrumentation installed as a result of plant modifications and I corrects a discrepancy to reflect the as-constructed condition of the plant. Addition of recently installed instrumentation provides for increased surveillance capabilities within the plant, thereby again improving plant safety. Thus the preposed technical specification <
change improves overall plant safety and results in no reduction in I margin of safety.
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