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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217G6571999-10-13013 October 1999 Proposed Tech Specs Pages,Revising TS to Permit Relaxation of Allowed Bypass Test Times & Completion Times for LCOs 3.3.1 & 3.3.2 ML20217B1221999-10-0404 October 1999 Proposed Tech Specs Pages,Revising TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 Re Prestressed Concrete Containment Tendon Surveillance Program ML20212F4891999-09-22022 September 1999 Proposed Rev to TS SR 3.8.1.13,to Include Upper Limit for DG Loading for 2 H Portion of SR ML20211J5511999-08-30030 August 1999 Proposed Tech Specs,Raising Level of Approval Authority for Deviations from Guidelines Provided to Minimize Unit Staff Overtime Specified in TS 5.2.2 ML20211J7281999-08-26026 August 1999 Proposed Tech Specs Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be in IAW with Versions of LCO 3.0.4 & SR 3.0.4 as Noted in Rev 1 to NUREG-1431 ML20211E9111999-08-24024 August 1999 Proposed Tech Specs,Relaxing Slave Relay Test Frequency from Quarterly to Refueling Frequency ML20196L3181999-05-18018 May 1999 Proposed Tech Specs SRs 3.8.1.3 & 3.8.1.13 Reducing Loading Requirements for DGs ML20205S3791999-04-19019 April 1999 Proposed Tech Specs Revising SR 3.3.5.2 & Associated Bases to Allow Loss of Voltage & Degraded Voltage Trip Setpoints to Be Treated as Nominal Values in Same Manner as Trip Setpoints for RTS & ESFAS Instrumentation ML20205Q7901999-04-13013 April 1999 Proposed Tech Specs,Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be Consistent with Versions of LCO 3.0.4 & SR 3.0.4 as Appear in Rev 1 to NUREG-1431 ML20154M9961998-10-15015 October 1998 Proposed Tech Specs,Deleting & Modifing Conditions Which Were Issued with Licenses That Are Now Obsolete ML20151U2011998-09-0303 September 1998 Proposed Tech Specs Pages for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys Source Range & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236R4661998-07-13013 July 1998 Proposed Tech Specs Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Selected Protected Channels ML20154Q8611998-06-30030 June 1998 Proposed Tech Specs Bases Since Implementation of Improved TS on 970123 Through Aug 1998 ML20206N3131998-06-30030 June 1998 Proposed Tech Specs Re Replacement of Nuclear Instrumentation Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236F1631998-06-26026 June 1998 Proposed Tech Specs Revising LCO 3.3.6 Re CVI Instrumentation & LCO 3.9.4 Re Containment Penetrations to Facilitate Outage Planning ML20247K5041998-05-15015 May 1998 Proposed Tech Specs Pages Revising New Program 5.5.18 to Extent That Items B,C & D. Refer to LCO Action Statement & Bases Insert for New Required Actions B.5.1 & B.5.2 ML20247G9471998-05-0808 May 1998 Proposed Tech Specs Section 5.5.7, RCP Flywheel Insp Program, Specifying Alternate Flywheel Insp Once Every Ten Years ML20216J4971998-04-16016 April 1998 Proposed Tech Specs 3.3.1 & 3.3.2 Re Reactor Trip Sys & ESFAS Instrumentation ML20199E5351998-01-27027 January 1998 Complete Replacement of All Typed Pages of TS Changes Submitted in Ltr LCV-0849-E ML20199A4131998-01-22022 January 1998 Proposed Tech Specs Adding Conditions for DG for Extended DG Completion Time of Fourteen Days ML20199J6651997-11-20020 November 1997 Proposed Tech Specs Pages Changing Capacity of Unit 1 Spent Fuel Storage Pool from 288 to 1476 Assemblies & Revising Design Features Description to Reflect Criticality Analyses & Storage Cell Spacing ML20199G3901997-11-20020 November 1997 Proposed Tech Specs Facilitating Treatment of Trip Setpoints as Nominal Values & Correct Certain Typos ML20211N2451997-10-10010 October 1997 Proposed Typed Tech Specs Pages,Revising Credit for Boron & Enrichment Increase for Fuel Storage ML20217H9051997-08-0808 August 1997 Proposed Tech Specs Pages Re Credit for Boron & Enrichment Increase for Fuel storage.W/marked-up Pages ML20141A8541997-06-13013 June 1997 Proposed Tech Specs Revising LCO 3.4.10 to Reduce Nominal Set Pressure by 1% to 2460 & Increase Tolerance to +2% ML20133L3081997-01-10010 January 1997 Proposed Tech Specs Table 3.3.1-1 Re Amends 96 & 74 ML20132C4711996-12-12012 December 1996 Proposed Tech Specs Re Physical Security & Contingency Plan ML20117N5851996-09-13013 September 1996 Proposed Tech Specs 3.8.1 Re AC Electrical Sources ML20129A6461996-09-11011 September 1996 Proposed Tech Specs,Providing Updated Documentation for License Amends Application for Southern Nuclear to Become Licensed Operator ML20117C4151996-08-23023 August 1996 Proposed Tech Specs to Convert Units 1 & 2 Based on NUREG 1431 ML20117N6471996-06-17017 June 1996 Proposed Tech Specs Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo ML20117N6361996-06-17017 June 1996 Proposed Tech Specs,Clarifying Requirements of TS SR 4.8.1.1.2.j (2) That Prescribes Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code ML20111A5501996-05-0606 May 1996 Proposed Tech Specs,Incorporating Extended DG AOT to 14 Days from Discovery of Failure to Meet Lco,Provided Standby Auxiliary Transformer Available ML20101D4151996-03-0505 March 1996 Proposed Tech Specs Re Conversion Based on NUREG-1431 ML20100G0371996-02-19019 February 1996 Proposed Tech Specs Based on NUREG-1431 ML20097A3171996-01-30030 January 1996 Proposed Improved TS Based on NUREG-1431 ML20095J2501995-12-22022 December 1995 Proposed Tech Specs,Allowing Use of Option B of 10CFR50,App J for Type B & C Testing ML20094N4071995-11-20020 November 1995 Proposed Tech Specs,Converting Existing TS to Format & Content of NUREG-1431 ML20093K2281995-10-16016 October 1995 Proposed Tech Specs,Adding Footnote to Spec 4.6.1.2.d Stating That Type B & C Tests Scheduled for Refueling Outage 1R6 Will Be Conducted Per Option B of 10CFR50 App J & Using Guidance of RG 1.163,Rev 0 ML20098C1471995-10-0202 October 1995 Proposed Tech Specs,Allowing Next Type a Test to Be Rescheduled ML20098A4861995-09-22022 September 1995 Proposed Tech Specs,Converting Existing VEGP TS Requirements to Format & Content of NUREG-1431 ML20086G5691995-07-0606 July 1995 Proposed Tech Specs Section 3.8.3.1,Page 3/4 8-15 Re Footnote & Bases & Expansion ML20085G7171995-06-14014 June 1995 Proposed Tech Specs,Clarifying in Revised Bases of 3/4 Chapter 8,that Alignment of Standby Auxiliary Transformer Intended to Be Temporary Alignment & Will Be Utilized When Normal Preferred Offsite Power Source,Rat Unavailable ML20083M0731995-05-12012 May 1995 Proposed Tech Specs Revising SR 4.1.6.2 to Support Exemption from 10CFR50,App J Type a Test Schedule ML20083A1391995-05-0202 May 1995 Proposed Tech Specs,Adding Automatic Load Sequencer to Plant TS ML20082D9881995-04-0404 April 1995 Proposed Tech Spec Page 6-7 Reflecting Corrected Terminology Re Composition of Plant Review Board ML20081J5031995-03-17017 March 1995 Proposed TS 3.9.4 Re Containment Airlock Doors to Be Open During Fuel Movement ML20081D1591995-03-17017 March 1995 Proposed TS Table 3.3-8, Accident Monitoring Instrumentation, Deleting Loop Numbers 551,552,553 & 554 ML20082E7731995-03-0404 March 1995 Proposed Tech Specs Re Plant Review Board Composition ML20080N2451995-02-28028 February 1995 Proposed Tech Specs Pages Re Accident Montoring Instrumentation 1999-09-22
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217G6571999-10-13013 October 1999 Proposed Tech Specs Pages,Revising TS to Permit Relaxation of Allowed Bypass Test Times & Completion Times for LCOs 3.3.1 & 3.3.2 ML20217B1221999-10-0404 October 1999 Proposed Tech Specs Pages,Revising TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 Re Prestressed Concrete Containment Tendon Surveillance Program ML20212F4891999-09-22022 September 1999 Proposed Rev to TS SR 3.8.1.13,to Include Upper Limit for DG Loading for 2 H Portion of SR ML20211J5511999-08-30030 August 1999 Proposed Tech Specs,Raising Level of Approval Authority for Deviations from Guidelines Provided to Minimize Unit Staff Overtime Specified in TS 5.2.2 ML20211J7281999-08-26026 August 1999 Proposed Tech Specs Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be in IAW with Versions of LCO 3.0.4 & SR 3.0.4 as Noted in Rev 1 to NUREG-1431 ML20211E9111999-08-24024 August 1999 Proposed Tech Specs,Relaxing Slave Relay Test Frequency from Quarterly to Refueling Frequency ML20196L3181999-05-18018 May 1999 Proposed Tech Specs SRs 3.8.1.3 & 3.8.1.13 Reducing Loading Requirements for DGs ML20205S3791999-04-19019 April 1999 Proposed Tech Specs Revising SR 3.3.5.2 & Associated Bases to Allow Loss of Voltage & Degraded Voltage Trip Setpoints to Be Treated as Nominal Values in Same Manner as Trip Setpoints for RTS & ESFAS Instrumentation ML20205Q7901999-04-13013 April 1999 Proposed Tech Specs,Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be Consistent with Versions of LCO 3.0.4 & SR 3.0.4 as Appear in Rev 1 to NUREG-1431 ML20154M9961998-10-15015 October 1998 Proposed Tech Specs,Deleting & Modifing Conditions Which Were Issued with Licenses That Are Now Obsolete ML20151U2011998-09-0303 September 1998 Proposed Tech Specs Pages for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys Source Range & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236R4661998-07-13013 July 1998 Proposed Tech Specs Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Selected Protected Channels ML20154Q8611998-06-30030 June 1998 Proposed Tech Specs Bases Since Implementation of Improved TS on 970123 Through Aug 1998 ML20206N3131998-06-30030 June 1998 Proposed Tech Specs Re Replacement of Nuclear Instrumentation Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236F1631998-06-26026 June 1998 Proposed Tech Specs Revising LCO 3.3.6 Re CVI Instrumentation & LCO 3.9.4 Re Containment Penetrations to Facilitate Outage Planning ML20248K5801998-05-25025 May 1998 Rev 1 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20247K5041998-05-15015 May 1998 Proposed Tech Specs Pages Revising New Program 5.5.18 to Extent That Items B,C & D. Refer to LCO Action Statement & Bases Insert for New Required Actions B.5.1 & B.5.2 ML20247G9471998-05-0808 May 1998 Proposed Tech Specs Section 5.5.7, RCP Flywheel Insp Program, Specifying Alternate Flywheel Insp Once Every Ten Years ML20216J4971998-04-16016 April 1998 Proposed Tech Specs 3.3.1 & 3.3.2 Re Reactor Trip Sys & ESFAS Instrumentation ML20199E5351998-01-27027 January 1998 Complete Replacement of All Typed Pages of TS Changes Submitted in Ltr LCV-0849-E ML20199A4131998-01-22022 January 1998 Proposed Tech Specs Adding Conditions for DG for Extended DG Completion Time of Fourteen Days ML20198P6961998-01-16016 January 1998 Revised Spent Fuel Pool Boron Dilution Analysis ML20216B2621997-12-11011 December 1997 Rev 14 to ODCM, for Vogtle Electric Generating Plant ML20199G3901997-11-20020 November 1997 Proposed Tech Specs Facilitating Treatment of Trip Setpoints as Nominal Values & Correct Certain Typos ML20199J6651997-11-20020 November 1997 Proposed Tech Specs Pages Changing Capacity of Unit 1 Spent Fuel Storage Pool from 288 to 1476 Assemblies & Revising Design Features Description to Reflect Criticality Analyses & Storage Cell Spacing ML20211N2451997-10-10010 October 1997 Proposed Typed Tech Specs Pages,Revising Credit for Boron & Enrichment Increase for Fuel Storage ML20217H9051997-08-0808 August 1997 Proposed Tech Specs Pages Re Credit for Boron & Enrichment Increase for Fuel storage.W/marked-up Pages ML20141A8541997-06-13013 June 1997 Proposed Tech Specs Revising LCO 3.4.10 to Reduce Nominal Set Pressure by 1% to 2460 & Increase Tolerance to +2% ML20148E6481997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Pump IST Program ML20148E6611997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20133L3081997-01-10010 January 1997 Proposed Tech Specs Table 3.3.1-1 Re Amends 96 & 74 ML20140J4591996-12-13013 December 1996 Rev 11 to ODCM for Vogtle Electric Generating Plant, ML20138F1001996-12-13013 December 1996 Revs 10 & 11 to ODCM, Part 2 ML20132C4711996-12-12012 December 1996 Proposed Tech Specs Re Physical Security & Contingency Plan ML20134J9841996-10-0808 October 1996 /Unit 2 Fuel Assembly Insp Program ML20117N5851996-09-13013 September 1996 Proposed Tech Specs 3.8.1 Re AC Electrical Sources ML20129A6461996-09-11011 September 1996 Proposed Tech Specs,Providing Updated Documentation for License Amends Application for Southern Nuclear to Become Licensed Operator ML20117C4151996-08-23023 August 1996 Proposed Tech Specs to Convert Units 1 & 2 Based on NUREG 1431 ML20117N6361996-06-17017 June 1996 Proposed Tech Specs,Clarifying Requirements of TS SR 4.8.1.1.2.j (2) That Prescribes Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code ML20117N6471996-06-17017 June 1996 Proposed Tech Specs Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo ML20111A5501996-05-0606 May 1996 Proposed Tech Specs,Incorporating Extended DG AOT to 14 Days from Discovery of Failure to Meet Lco,Provided Standby Auxiliary Transformer Available ML20106H2391996-03-31031 March 1996 Rev 10 to Gap Security Dept Vogtle Electric Generating Plant Nuclear Security Training & Qualification Plan ML20101D4151996-03-0505 March 1996 Proposed Tech Specs Re Conversion Based on NUREG-1431 ML20100G0371996-02-19019 February 1996 Proposed Tech Specs Based on NUREG-1431 ML20097A3171996-01-30030 January 1996 Proposed Improved TS Based on NUREG-1431 ML20096G8241996-01-22022 January 1996 Inservice Insp Program, for VEGP-2 ML20095J2501995-12-22022 December 1995 Proposed Tech Specs,Allowing Use of Option B of 10CFR50,App J for Type B & C Testing ML20094N4071995-11-20020 November 1995 Proposed Tech Specs,Converting Existing TS to Format & Content of NUREG-1431 ML20093K2281995-10-16016 October 1995 Proposed Tech Specs,Adding Footnote to Spec 4.6.1.2.d Stating That Type B & C Tests Scheduled for Refueling Outage 1R6 Will Be Conducted Per Option B of 10CFR50 App J & Using Guidance of RG 1.163,Rev 0 ML20098C1471995-10-0202 October 1995 Proposed Tech Specs,Allowing Next Type a Test to Be Rescheduled 1999-09-22
[Table view] |
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ENCLOSURE 3 VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECHNICAL SPECIFICATIONS RELATED TO AREA TEMPERATURE MONITORING INSTRUCTIONS FOR CHANGE AND REVISED PAGES The proposed change to the Vogtle Electric Generating Plant Technical Specifications would be incorporated t.s follows.
Bemove Pagg Insert Page IX' and X IX* and X ,
3/4 7-27 and 3/4 7-28 3/4 7-27 and 3/4 7-28 B 3/4 7-6 B 3/4 7-6 l
?
- Overleaf page containing no change. t E3-1 9402090050 940203 I*
PDR ADDCK 05000424 I .
. P PDR 11 ,
l
-+- !
INDEX i
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS '
l SECTION- PAGE 1 l
3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Va1ves............................................ 3/4 7-1 TABLE 3.1-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STE/J4 LINE SAFETY VALVES........ 3/4 7-2 TABLE 3.7-2 STEAM LINE SAFETY VALVES PER L00P..................... 3/4 7-3 Auxiliary Feedwater System............................... 3/4 7-4 condensate Storage Tank.................................. 3/4 7-6 Specific Activity........................................ 3/4 7-7 i TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE :
AND ANALYSIS PROGRAM............. ..................... 3/4 7-8 Main Steam Line Isolation Valves.. .................. ... 3/4 7-9 3/4.7.2 STEAM GENERATOR PRESSURE / TEM 9ERATURE LIMITATION.......... 3/4 7-10 3/4.7.3 COH QNENT C00LadG WATER SYSTEM........................... 3/4 7-11 3/4.7.4 NUCLEAR SERVICE COOLING WATER (NSCW) SYSTEM. . . . . . . . . . . . . . 3/4 7-12 3/4.7.5 ULTIMATE HEAT SINK......................'................. 3/4 7-13 3/4.7.6 CONTROL ROOM EMERGENCY FILTRATION SYSTEM (Common System). 3/4 7-14 3/4.7.7 PIPING PENETRATION AREA FILTRATION AND EXHAUST SYSTEM.... 3/4 7-17 3/4.7.8 SNUBBERS................................................. 3/4 7-19 FIGURE 4.7-1 SAMPLE PLAN 2 FOR SNUBBER FUNCTIONAL TEST. . . . . . . . . . . . 3/4 7-24 TABLE 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL..................... 3/4 7-24a i 3/4.7.9 SEALED SOURCE CONTAMINATION.............................. 3/4 7-25 i
4.7.10 AREATEMPERATUREMONITORING.h6M.M.4:)................. 3/4 7-27 3.7-3 AREA TEMPERATURE MONITORING.(.Of.4.f. d ............. 3/4 7-28 l in. 7.1I ENGINEERED SAFETY FEATURES (ESF) ROOM COOLER AND SAFETY- i RELATED CHILLER SYSTEM................................... 3/4 7-29 I 3/4.7.12 REACTOR COOLANT PUMP THERMAL BARRIER COOLING WATER ISOLATION.................. ............................. 3/4 7-30 3/4.7.13 DIESEL GENERATOR BUILDING AND AUXILIARY FEEDWATER I PUMPHOUSE ESF HVAC SYSTEMS . .... ... . .... . .. 3/4 7-31 l
)
I V0GTLE UNITS - 1 & 2 X Amendment No. 41 (Unit 1)
Amencment No. 21 (Unit 2)
1 PLANT SYSTEMS 3/4.7.10 AREA TEMPERATURE MONITORING INITING CONDITION FOR OPERATION ,/
3.7. e Maximum Normal Temperature of each area shown in Table . -3 shall not be exc ed for more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and the Maximum Abnormal Te erature of Table 3.7-3 911 not be exceeded.
APPLICABILITY:
N never the equipment in an affected area 's required _to be OPERABLE.
ACTION:
- a. With one or more a as exceeding the JMximum Nonnal Temperature limit (s) shown in Table 3.7-3 for mpre than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, prepare and submit to the Commissio within 37 days, pursuant to Specifica-tion 6.8.2, a Special Rep tt { provides a record of the cumulativt.
time and the amount by whic e temperature in the affected area (s) exceeded the limit (s) and .alysis to demonstrate the continued OPERABILITY of the affe d equi .ent. The provisions of Specifi-l cation 3.0.3 are not plicable.
- b. With one or morej eas exceeding the M imum Abnormal Temperature limit (s) shown th Table 3.7-3 prepare an ubmit a Special Report as required by ION a. Above and within 4 ho s either restore the area (s) to ithin the temperature limit (s) or eclare the equipment in the a 'ected area (s) inoperable.
SURVEILLANC, EOUIREMENTS x
/
4.7 It The temperature in each of the areas shown in Table 3.7-3 shall e d ermined to be within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Sfa~c t F/CM/oM 3/+. 7. /O DELE TED I
I V0 GILE UNITS - 1 & 2 3/4 7-27 Amendment No.59 (Unit 1)
Amendment No.38 (Unit 2) ;
___----______'I
l* '
TABLE 3.7-3 ARE: TEFERATURE McNiTORING 72BLE 3. l-3 DELETEb U":T 1
\ MAXIMUM MAXIM IUILDING ROOM NO NORMAL TEMP ABNORMAL EMP FU B008 104 120 AUX 1 IARY 110 1(0 / 104 AUXI ARY 202 100 107 AUXIL RY 203 100 107 AUXILIARY A017 100 112 AUXILIAR A047 100 107 AUXILIARY B017 100 100 AUXILIARY Cll3 100 109 :
AUXILIARY C120 100 106 AUXILIARY 0053 100 110 i AUXILIARY D067 100 106 AUXILIARY D072 100 105 AUXILIARY D075 100 106 AUXILIARY 0119 100 105 AUXILIARY 121 100 103 CONTROL 47 8 87 CONTROL 14 0 87 CONTROL A05 00 114 CONTROL A062 100 103-CONTROL B065 100 106 CONTROL B074 100 107 CONTROL B078 100 104 UNIT 2 MAXIMUM MAXIMUM BUILDING ROOM NO N RMAL TEMP ABNORMAL TEMP AUXILIARY 159 15 126 AUXILIARY 22s 1 ;120 AUXILIARY AQ61 100 112 AUXILIARY $704 115 126 AUXILIARY A105 115 126 AUXILIARY A107 115 126 AUXILIAR" Bil3 100 117 AUXILIARf 0006 200 106 AUXILIARY 0011 100 120 ,
CONTROL 131 100 120 CONTROL 264 80 87 CONTROL A002 100 107-CONTROL A010 100 106 CONTROL A014 100 120 ,
CONTROL B019 100 106 CONTR0f B033 100 124 EQUIP, MENT A008 115 26 E0VI/ MENT A009 115 116 E0tf1PMENT 122 115 12 '
EpIPMENT 123 115 126 V0GTLE UNITS - 1 & 2 3/4 7-28
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, e. .
PLANT SYSTEMS BASE 5 SNUBBERS (Continued) 1 The service life of a snubber is. established via manufacturer input and information through consideration of the snubber service conditions and 4 associated installation and maintenance records (newly installed snubbers.. seal. ;
replaced, spring replaced, in high radiation area, in high temperature area, etc.). The requirement to monitor the snubber service life is included to' l f
ensure that the snubbers periodically undergo a perforssace evaluation in view !
of their age and operating conditions. These records will provide statistical .
bases for future consideration of snubber service life. t 3/4.7.9 SEALED SOURCE CONTAMINATION s
The limitations on removable contamination for sources reoviring leak '
testing, i ncluding alpha emitters, is based on 10 CFR 70.39(a)(3) limits for-plutonism. !
This limitation will ensure that leakage from Byproduct, Source, and Special Nuclear Material sources will not exceed allowable intake values' ,
Sealed sources are c)assified into three gro es according to their use, l with Surveillance Requirements commensurate with the precability of damage to a i source in that group. Those sources which are frequently handled are required to be tested more often than thost. *tich are not. Sealed sources which are continuously enclosed within a su'oded mechanism (i.e., sealed sources within ..
radiation monitoring or baron measuring devices) are considered to be stored and need not.be tested unless they are removed from the shielded mechanism. !
t 3/4.7.10 AREA TEMPERATURE MONITORING i (DEt.ETED) 'i '
Th; ;rn 0;n:reter; li;;it; tin; :;ni'i:0 :- T2h ??-? :--"-" ""t ""'"*Y~ ';
thi:0
- r u"'
- i: x^ ni nrvin; ty !T ""i ;y;;;c ;.: ;Gan/ f7 Of: Ch:1-
- t t: ;;;j;;;; t; t r-; return in 2,c;;; ;f th;i ; = '7:Zn^d cu:!'" :tir t;;;;r; .;rn. :.,;.;;;;; :: ;;n;;is; i;;n r; turn 227 f:--^I ,
- b : t :n: ::n nun ; 1;;; ef it; OP:"A"ILI"!. '
3/4.7.11 ENGINEERED SAFETY FEATURES (ESF)-ROOM COOLER AND SAFE' -RELATED ;
CHILLER SYSTEM -
The operation of the ESF Room Cooler and Safety-Related Chiller System ensures that the ambient air temperature does not exceed the allowable ;
temocrature for continuous duty rating for the equipment cooled by the-system.
3/4.7.12 REACTOR COOLANT PUMP THERMAL BARRIER COOLING WATER ISOLATION t
This isolation function is designed to prevent a Spill of.the reactor j
ecolant f rom a postulatea breacnec tnermal barrier snould a creat occur in the' :
nonsafety-related ACCW Diping cownstream of the isolation valve. I i
V0GTLE UN]TS - 1 & 2 B 3/a 7-6 !
,- l
- ENCLOSURE 4 VOGTLE ELECTRIC GENERATING PLANT ,
REQUEST TO REVISS TECHNICAL SPECIFICATIONS RELATED TO AREA TEMPERATURE MONITORING i a
PROPOSED CHANGES TO THE FSAR Add to section 3.11.B.1 as item "D" prior to section 3.11.B.1.1 (Page 3.11.B.1-6)
D. Rooms with safety related equipment necessary for safe shutdown were evaluated to !
assure that the temperatures would be within acceptable values in order to determine the necessity for temperature surveillance. Rooms that met any of the following criteria do not require surveillance:
. Rooms with safety related HVAC systems i
. Rooms with a high temperature alarm that annunciates in the main control room when the normal design temperature is exceededt
. Rooms classified as mild environment where the calculated room temperature with l a loss of normal HVAC for seven days is less than 150 F
. Rooms with natural ventilation and designed for ambient conditions (e.g. NSCW Pumphouse)
Rooms that contain safety related equipment necessary for safe shutdown that do not meet any of the above criteria were also evaluated based on historical records of temperatures.
These records indicated that the temperatures remain within their environmental qualification limits with the normally provided HVAC in operation, but that upcn failure of the HVAC it is possible for the room temperature to exceed the values assumed for ,
equipment environmental qualification. Therefore, surveillance of these rooms is conducted in accordance with section 16.3, Area Temperature Monitoring, in the event of a loss of the normal HVAC. -
The qualified life of environmentally qualified equipment is based on the emironmental conditions indicated in table 3.11.B.1-1. Area temperature monitoring in conjunction with the evaluation described above provides reasonable assurance that the normal temperature -
used for emironmental qualification of safety related equipment necessary for safe l shutdown is not exceeded without an evaluatien of equipment operability.
E4-1 l 1 IIigh temperature alanns require the samc level of action for exceeding the design temperature limits as those described in section 16.3, Area Temperature Monitoring. !
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P 1, . .
ENCLOSURE 4 (CONTINUED) 1 i
REQUEST TO REVISE TECHNICAL SPECIFICATIONS l
RELATED TO AREA TEMPERATURE MONITORING PROPOSED CHANGES TO THE FSAR Add to FSAR Section 16.3 Requirement 7 - Area Temperature Monitoring The temperature limitatic for each areat specified in table 16.3-6 shall not be exceeded for more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and a maximum temperature of 150 F shall not be exceeded.
Whenever the above temperature limitations are exceeded, perform the following:
- 1. With one or more area (s) exceeding the temperature limit (s) shown in table 16.3-6 for more the 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, prepare an analysis within 30 days to determine the effect on !
equipment operability and qualified life. !
- 2. With one or more areas exceeding 150 F, within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> either:
. Restore the area (s) temperature to less than the limit (s) shown in table 16.3-6, and prepare an evaluation as stated in 1 above to demonstrate equipment operability, or !
. Declare the equipment in the affected area (s) inoperable.
The temperature in each of the affected areas shown in table 16.3-6 shall be determined to be within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the associated area normal 2 IIVAC ,
system is not in service.
E4-2 [
l The basis for exclusion of areas from this table is given in section 3.11.B.I. .
2 For purposes of Area Temperature Monitoring, normal ventilation is defined as the following HVAC components or, the minimum amount of ventilation which can be shown, either through analysis or empirical data, to be sufficient to maintain the area temperature below the values shown in table 16.3-6.
A stable temperature must be achieved if using empirical data tojustify discontinuing or exempting an area from temperature monitoring.
Auxiliary Buildinc 5 Unit 1: 1-1551-A7-001/002,1-1553-N7-001/002/003 Unit 2: 2-1551-A7-001/002,2-1553-N7-001/002/003 Control Buildine Eauipment Building t Unit 1: 1-1533-A7 001/002 Unit 1: 1-1526-B7 001/002 -!
Unit 2: 2-1533-A7-001/002 Unit 2: 2-1526-B7-001/002 Fuel Handline Buildinc Unit I A 2: A-1541-A7-00I/002, A-1541-N74101/002 L
TABLE 16.3-6 (SHEET 1 OF 2)
AREA TEMPERATl'RE MONITORING t
UNIT 1 BUILDING ROOM NO. TEMPERATURE LIMIT PF) l AUX 212 100 AUX A047 100 AUX B017 100 AUX B023 100 AUX C064 100 ;
AUX C065 100 AUX C066 100 AUX C067 100 AUX C083 100 AUX Cll3 100 .
AUX D052 100 AUX D053 100 AUX D067 100 AUX D072 100 AUX D073 100 AUX D119 100 AUX D121 100 CONTROL A055 100 CONTROL B065 100 CONTROL B074 100 CONTROL B078 100 EQUIPMENT 117 120 EQUIPMEhTT 125 120 FHB B008 104 E4-3 I
VEGP-FSAR-16 TABLE 16.3-6 (SHEET 2 OF 2)~
UNIT 2 py[LQING ROOM NO. TEMPERATURE LIMIT (*F) ,
i' AUX 221 100 AUX A082 100 AUX Bil3 100 1 AUX C010 100 (
AUX C041 100 AUX D106 100 >
AUX D107 100 :
AUX D113 100 '
AUX D123 100 CONTROL A002 100 !
CONTROL A010 100 t
CONTROL B002 100 CONTROL B010 100 i CONTROL B019 100 EQUIPMENT 117 120 EQUIPMENT 125 120 FHB B006 104 E4-4