Proposed Tech Specs Changing Table 3.3-11 Allowing Use of Thermal Fire Detectors Instead of Infrared DetectorsML20096C336 |
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Site: |
Sequoyah |
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Issue date: |
08/27/1984 |
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From: |
TENNESSEE VALLEY AUTHORITY |
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To: |
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Shared Package |
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ML20096C323 |
List: |
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References |
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NUDOCS 8409050233 |
Download: ML20096C336 (5) |
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Category:TECHNICAL SPECIFICATIONS
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[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 SPECIFICATIONS SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 t
TVA-SQN-TS-58 1 B409030233 840827
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PDR ADOCK 05000327 i P PDR
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TABLE 3.3-11 (Continued)
FIRE DETECTION INSTRUMENTS [
Fire Minimum Instruments Operable Zone Instrument location Ionization Photoelectric Thermal Infrared 267 Aux. Instr. Rm. El. 685 8 268 -Aux. Instr. Rs. El. 685 9 269 Computer Rm. El. 685 4 270 Computer Rm. El. 685 4
276 ~ Intk.~ Pumping Sta. El. 690 & 670.5 15 354 Upr. Compt. Coolers, El. 778 4
352 Lwr. Compt. Coolers, El. 693 4 356- RCP 2, El. 693 2*
357 RCP 2, El. 693 2
360 'RCP 1, El. 693 2*
361 RCP 1, El. 693 2
364 RCP 3. El. 693- 2*
365 RCI 4 il. 693 2
368 RCP 4, El. 693 2*
369 RCP 4, El. 693
'2 372 Reactor-Bldg. Annulus 18
.373. Reactor Bldg. Annulus 18 1 Diesel Gen. Rm. 2B B, El. 722 5 2 Diesel Gen. Rm. 28-8, El. 722 5 3 ' Diesel Gen.-Rm. 18-8, El. 722 ,
5 4 Diesel Gen. Rm. IB-8, El. 722 5 5 . Diesel Gen. Rm. 2A-A, El. 722 .
~ 5-6 Diesel Gen. Rm. 2A-A, El. 722 5 7 Diesel Gen. Rm. lA-A, El. 722 5
.8 Diesel Gen. Rm. 1A-A, El. 722 5
- This change is effective upon completion of the associated modification.
SEQUOYAH - UNIT 1 3/4 3-66 ,
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INSlRilHfNI 10CA110N loninit. ion ~ Photoelectric. lhei W l'a i ra rett 5
1 296 Aux. CR this. 1-4H,~4tl, & 11B L1 732 6 N 297 Main CR Bds. El. 732 9 l 298 - Conanon MCR Bds. El 732 9 l 387~ lurbine Cont. Bldg. Wall, El. 706 18 353 Iwe.-Compt.' Coolers, L1. 693 4 355 Upr. Cuiupt. Coolers ,- f. l . 7/8 -
4 3/4 Reactor Huiltling Annulus 18 3/S Reactor fluilding Annulus- 18 362 RCP 1 L1. 69.1 2*
363 RCP 1 11. 693 2 m -358 RCP 2 11. 693- 2*
}_ 359 RCP 2 Ll. 693 2 RLP 3 L1. 693 2, m 366_ ,
j, 367 RCP 3 El. 693 2 ,
N 370 RCP 4 ll. 693 2*
371 RCP 4 Ll. 693 2 l
- This change is effective upon completion of the modification.
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ENCLOSURE 2 JdSTIFICATION FOR PROPOSED TECHNICAL SPECIFICATIONS TVA-SQN-TS-58
. Description of Change Table 3.3-11 for units 1 and 2 lists the fire detection instruments. This proposed technical specification change revises the type of detectors used in fire zones 356, 360, 364, 368 for unit 1 and fire zones 362, 358, 366, and 370 for unit 2. The new detectors will be thermal detectors. The technical specification is requested to be approved for implementation following completion.of the associated modifications.
Justification The infrared detectors have experienced a high failure rate which has been attributed to the high temperature and high radiation environment surrounding the' infrared detectors. The infrared detectors are also subject to spurious alarms caused by flashlight beams. Suitable infrared detector replacements are not available. Thermal detectors are available
- that have not adversely responded to the high radiation and high tempera-ture environment. This change in detectors will increase the fire detection system availability and reliability. Also, based on the attached significant hazards consideration determination, we have concluded that:
(1) the proposed change does not constitute a significant hazards consideration as defined by 10 CFR 50.92; and (2) there is reasonable assurance that the health and safety of the public will not be endangered
.by the proposed change; and (3) this action will not result in a condition which significantly alters the impact of the station on the environment as described in the NRC Environmental Statement.
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SIGNIFICANT HAZARDS CONSIDERATIONS 1.
Is the probability of an occurrence or the consequences of an accident c .-
increased?, evaluated in the safety analysis report significantly previously '
No. .
v Replacing the infrared flame detectors with thermal detectors
'will increase the fire detectio'n systems availability and reliability.
' Thermal detectors presently located in the same environment have not responded adversely. .
- 2. , Is the possibility for an accident of a new or different type than evaluated 'previously in the safety analysis report created?
No.
'The fire detection system will perform the identical function as it did prior to the modification.
- 3. _ Is the margin of safety significantly reduced?
I No.
d This modification and reliability. is necessary to increase the system's availability The margin of safety will not be reduced.
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