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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217F1041999-10-14014 October 1999 Proposed Tech Specs Pages,Revising TS Sections 2.2 & 3.0/4.0,necessary to Support Mod P000224 Which Will Install New Power Range Neutron Monitoring Sys & Incorporate long- Term thermal-hydraulic Stability Solution Hardware ML20216J3471999-09-27027 September 1999 Corrected Tech Specs Page,Modifying Appearance of TS Page 3/4 4-8 as Typo Identified in Section 3.4.3.1 ML20212H5681999-09-27027 September 1999 Proposed Tech Specs Pages,Revising TS to Clarify Several Administrative Requirements,Delete Redundant Requirements & Correct Typos ML20196F5551999-06-22022 June 1999 Proposed Tech Specs Pages to Delete Surveillance Requirement 4.4.1.1.2 & Associated TS Administrative Controls Section 6.9.1.9.h,removing Recirculation Sys MG Set Stop ML20195H0651999-06-0909 June 1999 Revised Bases Pages B 3/4 10-2 & B 3/4 2-4 for LGS Units 1 & 2,in Order to Clarify That Requirements for Reactor Enclosure Secondary Containment Apply to Extended Area Encompassing Both Reactor Enclosure & Refueling Area ML20195E7611999-06-0707 June 1999 Proposed Tech Specs Table 3.6.3-1 & Associated Notations, Reflecting Permanently Deactivated Instrument Reference Leg Isolation Valve HV-61-102 ML20195G0481999-06-0707 June 1999 Proposed Tech Specs Section 3/4.4.3, RCS Leakage,Leakage Detection Systems, Clarifying Action Statement Re Inoperative Reactor Coolant Leakage Detection Systems ML20195B8431999-05-26026 May 1999 Proposed Tech Specs Section 4.1.3.5.b,removing & Relocating Control Rod Scram Accumulators Alarm Instrumentation to UFSAR & TS Section 3.1.3.5,allowing Alternate Method for Determining Whether Control Rod Drive Pump Is Operating ML20207L6591999-03-11011 March 1999 Proposed Tech Specs Section 2.1, Safety Limits, Revising MCPR Safety Limit ML20199G2021999-01-12012 January 1999 Proposed Tech Specs Section 3/4.4.2 & TS Bases Sections B 3/4.4.2,B 3/4.5.1 & B 3/4.5.2 to Increase Allowable as-found Main Steam SRV Code Safety Function Lift Setpoint Tolerance from +1% to +3% ML20199A7271999-01-0404 January 1999 Proposed Tech Specs Revising Administrative Section of TS Re Controlled Access to High Radiation Areas & Rept Dates for Annual Ore Rept & Annual Rer Rept ML20155H6401998-10-30030 October 1998 Proposed Tech Specs Pages Revising TS SRs 4.8.4.3.b.1, 4.8.4.3.b.2 & 4.8.4.3.b.3 in Order to Reflect Relay Setpoint Calculation Methodology ML20154Q8941998-10-15015 October 1998 Proposed Tech Specs Re Addition of Special Test Exception for IST & Hydrostatic Testing ML20154L3971998-10-13013 October 1998 Revised Tech Spec Bases Pages,Clarifying Thermal Overload Operation for Motor Operated Valves with Maintained Contact Control Switches ML20151Z4721998-09-14014 September 1998 Proposed Tech Specs Revising Table 4.4.6.1.3-1,re Withdrawal Schedule for Reactor Pressure Vessel Matl Surveillance Program Capsules ML20151V0951998-09-0404 September 1998 Proposed Tech Specs Ensuring Fidelity Between TS Pages & 970324 Submittal ML20236M1221998-07-0202 July 1998 Proposed Tech Specs Change Request 96-06-0,modifying FOL Page 8 ML20217K5291998-04-24024 April 1998 Proposed Tech Specs Page 6-18a Revising MCPR Safety Limit for Lgs,Unit 1,cycle 8 ML20202G7871998-02-0909 February 1998 Proposed TS Section 2.1, Safety Limits, Revising MCPR Safety Limit.Nonproprietary Supporting Info Encl ML20199G7771998-01-27027 January 1998 Proposed Tech Specs Pages,Removing Maximum Isolation Time for HPCI Turbine Exhaust Containment Isolation Valve HV-055-1(2)F072 from TS ML20198M7861998-01-12012 January 1998 Proposed Tech Specs Table 4.4.6.1.3-1 Re Surveillance Specimen Program Evaluation for Limerick Generating Station, Unit 1 ML20199H5971997-11-18018 November 1997 Proposed Tech Specs Re Affected Unit 1 FOL Page 8 ML20212D1851997-10-24024 October 1997 Proposed Tech Specs Revising Section 3/4.1.3.6 to Exempt Control Rod 50-27 from Coupling Test for Remainder for Cycle 7 at LGS Unit 1,provided Certain Conditions Are Met ML20216H1101997-09-0808 September 1997 Proposed Tech Specs,Supplementing Change Request 96-06-0 by Adding Three Addl TS Pages Containing Typos Discovered Since 970225 Submittal ML20210T9231997-09-0202 September 1997 Proposed Tech Specs,Revising TS Section 4.0.5 & Bases Sections B 4.0.5 & B 3/4.4.8 Re SRs Associated W/Isi & IST of ASME Code Class 1,2 & 3 Components ML20138A2311997-04-21021 April 1997 Proposed Tech Specs,Providing New Pp B 3/4 8-2a to Accomodate Overflow of Text from TS Bases Pp B 3/4 8-2 ML20137X8101997-04-0909 April 1997 Proposed Tech Specs Re Battery Specific Gravity Changes ML20137G6751997-03-24024 March 1997 Proposed Tech Specs Deleting Drywell & Suppression Chamber Purge Sys Operational Time Limit & Add SR to Ensure Purge Sys Large Supply & Exhaust Valves Are Closed as Required ML20135D0961997-02-25025 February 1997 Proposed Tech Specs Changing Corporate Name from PA Electric Co to PECO Energy Co & Removing Obsolete Info & Correcting Typos ML20133L2141997-01-15015 January 1997 Proposed Tech Specs Pp 3/4 5-5 mark-up Rev for Unit 1 Revising TS by Eliminating in-situ Functional Testing of ADS Valves Requirement as Part of start-up Testing Activities ML20135F0961996-12-0606 December 1996 Proposed Tech Specs 2.1 Re Safety Limits ML20135A4491996-11-25025 November 1996 Proposed Tech Specs Change Request 96-22-0,revising TS SR 4.8.1.1.2.e.2 & Supporting TS Bases Section 3/4.8,to Clarify Requirements Associated W/Single Load Rejection Testing of EDGs ML20134L7571996-11-0505 November 1996 Proposed Tech Specs Revising Same Pp Contained in TS Change Request 95-14-0 Re Adoption of Performance Based 10CFR50, App J,Option B Testing ML20128N7761996-09-27027 September 1996 Proposed Tech Specs 3/4.6.5 Re Secondary Containment & 4.6.5.1.1 Re Surveillance Requirements ML20116L2701996-08-0808 August 1996 Proposed Tech Specs,Revising TS Sections 3/4.3.1,3/4.3.2, 3/4.3.3 & Associated TS Bases Sections 3/4.3.1 & 3/4.3.2 to Eliminate Selected Response Time Testing Requirements ML20116H6511996-08-0505 August 1996 Proposed Tech Specs Section 2.1, Safety Limits, to Revise Min Critical Power Ratio Safety Limit ML20116E6191996-08-0101 August 1996 Proposed Tech Specs 3/4.4.6 Re Addition of Two Hydroset Curves,Effective for 6.5 & 8.5 Efpy,To Existing Ptol Curves ML20115A9111996-06-28028 June 1996 Proposed Tech Specs,Performing Containment leakage-rate Testing Per 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors, Option B ML20117H2621996-05-20020 May 1996 Proposed Tech Specs Sections 3/4.4.9.2,3/4.9.11.1,3/4.9.11.2 & Associated TS Bases 3/4.4.9 & 3/4.9.11 to More Clearly Described RHR Sys Shutdown Cooling Mode Operation ML20117D7801996-05-0303 May 1996 Proposed Tech Specs,Revising TS SRs to Change Surveillance Test Frequency for Performing Flow Testing of SGTS & RERS from Monthly to Quarterly ML20107M5141996-04-25025 April 1996 Proposed Tech Specs 3/4.3.7.7 Re Relocation of Traversing in-core Probe LCO ML20101L9211996-03-29029 March 1996 Proposed Tech Specs,Revising TS SR 4.5.1.d.2.b to Delete Requirement to Perform Functional Testing of ADS Valves as Part of start-up Testing Activities ML20095K5681995-12-22022 December 1995 Proposed Tech Specs Re Increase of Drywell & Suppression Chamber Purge Sys Operating Time Limit from 90 H Each 365 Days to 180 H Each 365 Days ML20094D2381995-10-27027 October 1995 Proposed TS Pages 1-6 & 1-7,revising Definitions 1.33, Reactor Enclosure Secondary Containment Integrity & 1.35, Refueling Floor Secondary Containment Integrity.' ML20093E5711995-10-10010 October 1995 Revised TS Page Re Primary Containment Isolation Valves ML20092J3961995-09-18018 September 1995 Proposed TS Table 4.3.1.1-1, RPS Instrumentation SRs & TS Bases 3/4.3.1,changing Calibr Frequency for LPRM Signal from Every 1,000 EFPH to Every 2,000 Megawatt Days Per Std Ton ML20092J3281995-09-14014 September 1995 Proposed Tech Specs,Removing Secondary Containment Isolation Valve Tables ML20087F9611995-08-10010 August 1995 Revised TS Pages 6-6 & 6-7 ML20087C9531995-08-0101 August 1995 Proposed Tech Specs in Order to Provide Alternate Actions to Allow Continuation of Core Alterations in Event Certain RMCS & Refueling Interlocks Are Inoperable ML20086S6131995-07-28028 July 1995 Proposed Tech Specs Reflecting Changes to Surveillance Test Frequency Requirements for Various RPS Instrumentation 1999-09-27
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F1041999-10-14014 October 1999 Proposed Tech Specs Pages,Revising TS Sections 2.2 & 3.0/4.0,necessary to Support Mod P000224 Which Will Install New Power Range Neutron Monitoring Sys & Incorporate long- Term thermal-hydraulic Stability Solution Hardware ML20212H5681999-09-27027 September 1999 Proposed Tech Specs Pages,Revising TS to Clarify Several Administrative Requirements,Delete Redundant Requirements & Correct Typos ML20216J3471999-09-27027 September 1999 Corrected Tech Specs Page,Modifying Appearance of TS Page 3/4 4-8 as Typo Identified in Section 3.4.3.1 ML20196F5551999-06-22022 June 1999 Proposed Tech Specs Pages to Delete Surveillance Requirement 4.4.1.1.2 & Associated TS Administrative Controls Section 6.9.1.9.h,removing Recirculation Sys MG Set Stop ML20195H0651999-06-0909 June 1999 Revised Bases Pages B 3/4 10-2 & B 3/4 2-4 for LGS Units 1 & 2,in Order to Clarify That Requirements for Reactor Enclosure Secondary Containment Apply to Extended Area Encompassing Both Reactor Enclosure & Refueling Area ML20195E7611999-06-0707 June 1999 Proposed Tech Specs Table 3.6.3-1 & Associated Notations, Reflecting Permanently Deactivated Instrument Reference Leg Isolation Valve HV-61-102 ML20195G0481999-06-0707 June 1999 Proposed Tech Specs Section 3/4.4.3, RCS Leakage,Leakage Detection Systems, Clarifying Action Statement Re Inoperative Reactor Coolant Leakage Detection Systems ML20195B8431999-05-26026 May 1999 Proposed Tech Specs Section 4.1.3.5.b,removing & Relocating Control Rod Scram Accumulators Alarm Instrumentation to UFSAR & TS Section 3.1.3.5,allowing Alternate Method for Determining Whether Control Rod Drive Pump Is Operating ML20207L6591999-03-11011 March 1999 Proposed Tech Specs Section 2.1, Safety Limits, Revising MCPR Safety Limit ML20199G2021999-01-12012 January 1999 Proposed Tech Specs Section 3/4.4.2 & TS Bases Sections B 3/4.4.2,B 3/4.5.1 & B 3/4.5.2 to Increase Allowable as-found Main Steam SRV Code Safety Function Lift Setpoint Tolerance from +1% to +3% ML20199A7271999-01-0404 January 1999 Proposed Tech Specs Revising Administrative Section of TS Re Controlled Access to High Radiation Areas & Rept Dates for Annual Ore Rept & Annual Rer Rept ML20195J1651998-11-16016 November 1998 Rev D to LGS Emergency Preparedness NUMARC Eals ML20155H6401998-10-30030 October 1998 Proposed Tech Specs Pages Revising TS SRs 4.8.4.3.b.1, 4.8.4.3.b.2 & 4.8.4.3.b.3 in Order to Reflect Relay Setpoint Calculation Methodology ML20154Q8941998-10-15015 October 1998 Proposed Tech Specs Re Addition of Special Test Exception for IST & Hydrostatic Testing ML20154L3971998-10-13013 October 1998 Revised Tech Spec Bases Pages,Clarifying Thermal Overload Operation for Motor Operated Valves with Maintained Contact Control Switches ML20151Z4721998-09-14014 September 1998 Proposed Tech Specs Revising Table 4.4.6.1.3-1,re Withdrawal Schedule for Reactor Pressure Vessel Matl Surveillance Program Capsules ML20151V0951998-09-0404 September 1998 Proposed Tech Specs Ensuring Fidelity Between TS Pages & 970324 Submittal ML20236M1221998-07-0202 July 1998 Proposed Tech Specs Change Request 96-06-0,modifying FOL Page 8 ML20217K5291998-04-24024 April 1998 Proposed Tech Specs Page 6-18a Revising MCPR Safety Limit for Lgs,Unit 1,cycle 8 ML20202G7871998-02-0909 February 1998 Proposed TS Section 2.1, Safety Limits, Revising MCPR Safety Limit.Nonproprietary Supporting Info Encl ML20199G7771998-01-27027 January 1998 Proposed Tech Specs Pages,Removing Maximum Isolation Time for HPCI Turbine Exhaust Containment Isolation Valve HV-055-1(2)F072 from TS ML20198M7861998-01-12012 January 1998 Proposed Tech Specs Table 4.4.6.1.3-1 Re Surveillance Specimen Program Evaluation for Limerick Generating Station, Unit 1 ML20203H2501997-12-31031 December 1997 Rev 19 to Odcm ML20198N8061997-12-31031 December 1997 NPDES Permit PA-0052221 Study Plan for Fecal Coliform Bacteria in Pont Pleasant Water Diversion Sys During May- Sept 1998 ML20199H5971997-11-18018 November 1997 Proposed Tech Specs Re Affected Unit 1 FOL Page 8 ML20212D1851997-10-24024 October 1997 Proposed Tech Specs Revising Section 3/4.1.3.6 to Exempt Control Rod 50-27 from Coupling Test for Remainder for Cycle 7 at LGS Unit 1,provided Certain Conditions Are Met ML20211P9471997-10-15015 October 1997 Revised MSRV Tailpipe Temp Action Plan ML20216H1101997-09-0808 September 1997 Proposed Tech Specs,Supplementing Change Request 96-06-0 by Adding Three Addl TS Pages Containing Typos Discovered Since 970225 Submittal ML20210T9231997-09-0202 September 1997 Proposed Tech Specs,Revising TS Section 4.0.5 & Bases Sections B 4.0.5 & B 3/4.4.8 Re SRs Associated W/Isi & IST of ASME Code Class 1,2 & 3 Components ML20141K9461997-05-27027 May 1997 PECO Nuclear Limerick Generating Station Unit 2 Startup Test Rept Cycle 5 ML20203H2701997-04-30030 April 1997 Rev 18 to Odcm ML20138A2311997-04-21021 April 1997 Proposed Tech Specs,Providing New Pp B 3/4 8-2a to Accomodate Overflow of Text from TS Bases Pp B 3/4 8-2 ML20137X8101997-04-0909 April 1997 Proposed Tech Specs Re Battery Specific Gravity Changes ML20137G6751997-03-24024 March 1997 Proposed Tech Specs Deleting Drywell & Suppression Chamber Purge Sys Operational Time Limit & Add SR to Ensure Purge Sys Large Supply & Exhaust Valves Are Closed as Required ML20135D0961997-02-25025 February 1997 Proposed Tech Specs Changing Corporate Name from PA Electric Co to PECO Energy Co & Removing Obsolete Info & Correcting Typos ML20133L2141997-01-15015 January 1997 Proposed Tech Specs Pp 3/4 5-5 mark-up Rev for Unit 1 Revising TS by Eliminating in-situ Functional Testing of ADS Valves Requirement as Part of start-up Testing Activities ML20135F0961996-12-0606 December 1996 Proposed Tech Specs 2.1 Re Safety Limits ML20135A4491996-11-25025 November 1996 Proposed Tech Specs Change Request 96-22-0,revising TS SR 4.8.1.1.2.e.2 & Supporting TS Bases Section 3/4.8,to Clarify Requirements Associated W/Single Load Rejection Testing of EDGs ML20134L7571996-11-0505 November 1996 Proposed Tech Specs Revising Same Pp Contained in TS Change Request 95-14-0 Re Adoption of Performance Based 10CFR50, App J,Option B Testing ML20128N7761996-09-27027 September 1996 Proposed Tech Specs 3/4.6.5 Re Secondary Containment & 4.6.5.1.1 Re Surveillance Requirements ML20116L2701996-08-0808 August 1996 Proposed Tech Specs,Revising TS Sections 3/4.3.1,3/4.3.2, 3/4.3.3 & Associated TS Bases Sections 3/4.3.1 & 3/4.3.2 to Eliminate Selected Response Time Testing Requirements ML20116H6511996-08-0505 August 1996 Proposed Tech Specs Section 2.1, Safety Limits, to Revise Min Critical Power Ratio Safety Limit ML20116E6191996-08-0101 August 1996 Proposed Tech Specs 3/4.4.6 Re Addition of Two Hydroset Curves,Effective for 6.5 & 8.5 Efpy,To Existing Ptol Curves ML20113E0491996-06-28028 June 1996 Technical Basis & Description of Approach for Review Method Selection ML20115A9111996-06-28028 June 1996 Proposed Tech Specs,Performing Containment leakage-rate Testing Per 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors, Option B ML20117H2621996-05-20020 May 1996 Proposed Tech Specs Sections 3/4.4.9.2,3/4.9.11.1,3/4.9.11.2 & Associated TS Bases 3/4.4.9 & 3/4.9.11 to More Clearly Described RHR Sys Shutdown Cooling Mode Operation ML20112C1691996-05-17017 May 1996 Startup Rept Cycle 7 ML20117D7801996-05-0303 May 1996 Proposed Tech Specs,Revising TS SRs to Change Surveillance Test Frequency for Performing Flow Testing of SGTS & RERS from Monthly to Quarterly ML20107M5141996-04-25025 April 1996 Proposed Tech Specs 3/4.3.7.7 Re Relocation of Traversing in-core Probe LCO ML20101L9211996-03-29029 March 1996 Proposed Tech Specs,Revising TS SR 4.5.1.d.2.b to Delete Requirement to Perform Functional Testing of ADS Valves as Part of start-up Testing Activities 1999-09-27
[Table view] |
Text
.,
a 4 e a ATTACHMENT 2 LIMERICK GENERATING STATION UNITS 1 AND 2 LICENSE CHANGE REQUEST NO. 96-23-0 AFFECTED PAGES UNIT 1 UNIT 2 3/4 6-11 3/4 6-11 B 3/4 6-2 B 3/4 6-2 9704010463 970324 PDR ADOCK 05000352 P PDR ,
L
CONTAINMENT SYSTENS
.
- ORYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM LIMITING CONDITION FOR OPEPATION 3'J.1.8 The drywell and suppression chamber purge system may be in operation
,.-- @,4p ya @ Vurs/eacV 36'VdaA]with the supply and exhaust isolation valves C [
in one supply line and one exhaust line open for inerting, deinerting b pressure control f; 4Lg4 e air gWiN cmudersher s fe, je s.%.le,dep eiro,,cyergLw, b ed nah /e rezaset the valJes k be eters. ,
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2,.and 3. '
ACTION:
- a. With a drywell and/or suppression chamber purge supply and/or exhaust isolation valve open, except as permitted above, close the valve (s) i within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, i
SURVEILLANCE RE0VIREMENTS 4.6.1.8Se ore /ein opey'ed, de dr ell 4nd sup'pressfon chjtsber,$' urge,tuppi nyex us bu trf1 issatio valv s s i be M or m e an 0hurs/nt pre ous 65 day s /yeriffed not/to Mve bepn op l
1 Al lud *nce, pr 38 k
- each frS<r4 conlasn'n,en) j bg , valsc[le%21"] is ver Ne,,W. -*y* **
furje ; l l
l 1
i I
l l
thh LW
- Valves open for pressure control are not subject to [VI80/our pM65J6) f l
@ provided the 1-inch /2-inch bypass line is being utilized.
n 0,y regos edr 40 be Hef in OfERhir0%'- CMDtTl0MS I,2 *nd 3.
4+fr Nd regshd 40 k me+ % he rmsy c*hin~ce d proc **I*n *'c cf*n fo<
snsehng, Ae-inerfin3,frecare cen4rel, ALAgA ee air quahh coualersfieru for fsrsonne]
e6+ey or L e m il.nce3 + Q r , g et g ,g y,jg,3 4, be open .
M295 LIMERICX - UNIT 1 3/4 6-11 Amendment No.115
. - . . . . . . .. . . .. . . : .. : = ~. :
.- I BASES .
~
3/4.6.1.5 PRIMARY CONTAlh&ENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment I will be maintained comparable o the original design standards for the life of the unit. Structural integri+.y !s required to ensure that the containment will withstand the maximum calculated pressure in the event of a LOCA. A visual inspection in accordance with the Primary Containment Leakage Rate Testing Program is sufficient to demonstrat? this capability.
1 3/4.6.1.6 ORYWELL AND SUPPRESSION CHAMBER INTERNAL PRESSURE 1
The limitations on drywell and suppression chamber internal pressure ensure that the calculated containment peak pressure does not exceed the design pressure of 55 psig during LOCA conditions or that the external pressure differ-ential does not exceed the design maximum external pressure differential of 5.0 psid. The limit of - 1.0 to + 2.0 psig for initial containment pressure ,
i will limit the total pressure to s 44 psig which is less than the design !
pressure and is consistent with the safety analysis. >
i
]!4.6.1.7 DRYWELL AVERAGE AIR TEMPERATURE The limitation on drywell average air temperature ensures that the con-tainment peak air temperature does not exceed the design temperature of 340*F during steam line break conditions and is consistent with the safety analysis.
g c* *Md3 !
3/4.6.1.8 ORYWELL AND SUPPRESSION CHAMBER pVRGE SYSTEM WA ' fd The drywell and suppression chamber pu
$.Ne hdf.{d.pR h) i ply and exhaust isolattor l
valves are required to be closed during pla nneration except as reouired for :
inertino, deinertina,dii$ pressure control '
(EurceMalw'oneratJcW if imposed to prote/'D#e 180 h6urs/per ct the integrity of the SGi5 265 #ay Kat1/b3 tilters.
Analysis indicates t at should a LOCA occur while this pathway is being utilized, the associated pres ure surge through the (18 or 24") purge lines will adversely affect the integri y of SGTS. This limit is not imposed, however, on the subject {
valves when press e control is being performed through the 2-inch bypass line, since a pressure urge through this line does not threaten the OPERABILITY of SGIS.
4 M)
} LQ %. ne of de' dit'll "^d sapec 'a.m **A'f%c'3'h
(
o spefL cd fc-rk l _
I Surveillance requirement 4.6.1.8 ensures that the pnmary containment purge valves are closed as I l required or, if open, open for an allowable reason. If a purge valve is open in violation of this SR, the l
v:lve is considered inoperable. The SR is modified by a Note stating that primary containment purge i vrives are only required to be closed in OPERATIONAL CONDITIONS 1,2 and 3. The SR is also i
modified by a Note stating that the SR is not required to be met when the purge valves are open for the '
stated reasons. The Note states that these valves may be opened for inerting, de-inerting, pressure
{
control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to /
l be open. The 18 or 24 inch purge valves are capable of closing in the environment following a LOCA. !
Th:refore, these valves are allowed to be open for limited periods of time. The 31 day Frequency is consistent with other PCIV requirements. g 7 4 7-1 LIMERICK - UNIT 1 B 3/4 6-2 AmendmentNo, 2g,.106, 115, 118
CONTAINMENT SYSTEMS
, . DRYWELL AND SUPTRESSION CHAMBER PURGE SYSTEM l LIMITING CONDITION FOR OPERATION 3 A 1.8 !
bdC The drywell and sunnression chamber purge system may be in operation I
' Tfo/ uVto )10 hpdrs adh M5 dds) with the supply and exhaust isolation valves in one supply line
- and one exhaust line open for inerting, deinerting,@ Deleb {
pressure cont ,
j wk A LARA%e reteira or misss N Wh kc****dershen.s be orm. 40' P*'2***l enfry or S.orse,I%s t%) '
- APPLICABILITY
- OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION: ;
- a. With a drywell and/or suppression chamber purge supply and/or exhaust isolation valve open, except as permitted above, close the valve (s) !
l within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> !
and in COLD S14UTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. l SURVEILLANCE REOUIREMENTS 4.6.1.8]Beorebei opened the dr ell and uppre ion chap 6er p sup i nd e aus butterf isola on valv shall veri ed nota o hav een en Delek for re an 180 ours in he prev ous 365 ays.*f (
AN hi leM) ence per- 3 \ d<ys , vers each p,[ conlaunmd .e.vslag[gg**,,g is c!med.* ,g 14'o LCo
- V lves ocen for pressure control are not subject to be idhourIr 365[] l
'i provided the 1-inch /2-inch bypass line is being utilized.
+w Ong required h h Mef In MWW C30mW5 8,2, and 3.
- %F rego,' red to be me$ den % fenry coEnmen$ PGC Wives are ofen bt'
\ssrEn erdr(ee 3,(dt -inerfiny vrveill.rre3 tM refutetf'twre Cmlro) flese valves b,hAlbPs open . or ai- qual,Q g 2 9 1996 cons <der LIMERICA - UNIT 2 3/4 6-11 Amendment No. 77 0 ^ ^ '
....a . . . . . . - . . ~ . - - ~ . . ~ ~ - - - ~ ~ . - ~ . . - ~ ~ ~ . -.. - --- X
BASES -
. 3/4.6'1.5 PRIMARY CONTAVNMENT STRUCTURAL !NTEGRfTV This limitation ensures that the structural integrity of the containment ci1l be ' maintained comparable to the original design standards for the life of the unit. Structural integrity is required to ensure that the containment will cithstand the maximum calculated pressure in the event of a LOCA. A visual inspection in accordance with the Primary Containment Leakage Rate Testing Program is sufficient to demonstrate this capability.
3/4.6.1.6 DRYWELL AND SUPPRESSION CHAM 8ER INTERNAL PRESSURE i I
The limitations on drywell and suppression chamber internal pressure ensure '
that the calculated containment peak pressure does not exceed the design pressure of 55 psig during LOCA conditions or that the external pressure differ-ential does not exceed the design maximum external pressure differential of 5.0 psid. The limit of - 1.0 to + 2.0 psig for initial containment pressure will limit the total pressure to s 44 psig which is less than the design pressure and is consistent wi*h the safety analysis.
3/4.6.1.7 ORYWELL AVERAGE AIR TEMPERATURE The limitation on drywell average air temperature ensures that the con-tainment peak air temperature does not exceed the design temperature or 340 r, during steam line break conditions and is consistent with the " M y anf l AJ,!
htMA or a e ku*hk-i '*Mder*k. s for 3 i s 3/4,6.1.8 DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM fyQ%* * M te The drywell and suppression chamber pur supply and exhaust isolation valves are required to be closed during pla _ceeration except_as recuired for j
inerting, deinerting M pressure control, Thel 80 be'urs/per/3654ay Pf'mitAin)
Cource vilve,dpergio3 is imposed to protect the integrity of the SGTS filters. ,
Analysis indicat~es t t should a LOCA occur while this pathway is being utilized, the associated press' re surge through the (18 or 24") purge lines will adversely affect the integrit of the SGTS. This limit is not imposed, however, on the subject valves when pressur control is being performed through the 2-inch bypass line, since a pressure s ge through this line does not threaten the OPERABILITY or SGTS.
i t
Q the Oce ch he kryeb QN Pfffudon c&
M to Efec8hc criferiq / ~
t
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\ Surveillance requirement 4.6.1.8 ensures that the primary containment purge valves ar equired or, if open, open for an allowable reason. If a purge valve is open in violation of this Md vahre is e nsidered in perable. The SR is modified by a Note stating that primary conta valves are only required to be closed in OPERATIONAL CONDITIONS 1,2 and 3. The SR is also i modified by a Note stating that the SR is not required to be met when the purge valves are o stated reasons. The Note states that these valves may be opened for inerting, de.inerting, pres control, ALARA or air quality considerations for personnel entry, or Surveillances that require the t
be open. The 18 or 24 inch purge valves are capable of closing in the environment followi Therefore, consistent with otherthese valves PCIV are allowed to be open for limited periods of time. The 31 day requirements.
p4g LIMERICK - UNIT 2 B 3/4 6-2 ,,
Amendment No. .97-*** 31 I
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