|
---|
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
_ _ _ _ _ _ _ _
3901000402..
TABLE 3.6.3-1 (Continued) -
PART A - PRIMARY CONTAIMENT ISOLATION VALVES M INBOARO OUTBOARD ISOL.
5 PENETRATION FUNCTION ISOLATION ISOLATION . MAX.ISOL. SIGNAL (5), NOTES P&ID R NUPBER BARRIER BARRIER TIME.IF APP. IF APP.
'$$ i (SEC)(26) (20)
T@ c o 5 H
SV57-191 5 B ,H,R ,5 , 11
@$ (X-220A) .
Oo 116 STANDBY LIQUID CONTROL 48-IF007(CK) NA 48 (X-42) HV48-1F0068 60 29
$$ 1178-1 DRYWELL RADIATION SV26-190A 5 B ,II, R ,5 11 26 8S MONITORING SUPPLY . SV26-1908 5 B,H R.S 11 50S 117B-2 DRYWELL RADIATION SV26-190C 5 B,H,R,5 11 26 "fj MONITORING RETURN SV26-1900 5 B,ll,R,5 11 -
201A SUPPRESSION POOL PURGE IIV57-124 5** B II,5,U,W,R T 3,11,14 57 t' SUPPLY lfV57-131(X-25) 5** B,H,5,U,W,R,T 3,11,14 HV57-109(X-25) 6** B,ll,5,U,W,R,T 11
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HV57-147 6** B.H,5,U,W,R,T 11 M ^
HV57-121(X-25) 5** B,II,5,U,W,R,T 11 HYDROGEN REC 00BINER "B" IIV57-164 9 -
. B H,R,5 3,11,14
$ EXilAUST HV57-169
~
9 B,ll,R,5 11
" 202 SUPPRESSION POOL PURGE HV57-104 5** B,H.S",U,W R.T 3,11,14,33 57 EXHAUST HV57-105 15** B,H,S,U,R,T 11 8 HV57-112 6** B,H,5,U,W,R,T 11, 33
, HV57-118 5** 8,H,5,U,R,T 11 SV57-185 5 B,ll,R,5 'll g HYDROGEN REcopelNER "A" 11V57-162 9 B,H,R,5 3,11,14
, EXHAUST HV57-166 9 B,H,R,5 11
$ 203A(B,C,D) RHR PUMP SUCTION HV51-1F004A(8,240 -47227 51
,o C,D) 29,3 Y PSV51-1F030A NA lhM 3Y d "
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TABLE 3.6.3-1 (Continued) .
C '
PARI A - PRIMARY CONTAINNENT ISOLATION VALVES 5 INBOARD OUIBOARO R PENEIRAil0N 150L.
FUNCTION ISOLATION ISOLATION
. MAX.150L. SIGNAL (5), noiES P8.10 NUMBER ~ BARRIER BARRIER e
TIME.lF APP. IF APP.
z (SEC)(26) (20)
- 204A(B) RilR PUMP TEST LINE ANO llV51-125A(B) 180 -+cet,29 3/ 51 CONIAltmEHi C00LlHG '
205A(8) SUPPRESSION P0OL SPRAY IfV51-1F027A(B) 45 C.G 11 51l 206A(8,C,0) CS PUMP SUCTION llV52-IF001A (8,C,0) 160 -tfe 29,3il 52 207A(B) CS PUMP TEST AND FLU 511 ifv52-1F015A(B) 23 C.G 3r ff,8f 52 y 2088 CSPUMPMINIItUMRECIRC llV52-1F0318 45 LICil +;fiF,29,3/ 52 l ] 209 HPCI PUMP SUCTION llV55-IF042 160 . L,LA -+;inf 34 55
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210 llPCI TURBINE EXilAUST . itV55-1F072 120 , . 400,29,35 55 j 212 IIPCI PUMP TEST AND FLU 5tl llV55-1F071 40 B,Il - hB2 S/ 55 ;
214 RCIC PUMP SUCTION HV49-1F031 60 h 42,29,J / 49 ,
215 RCICTUR8tNdEXHAUST llV49-1F060 80 h44,29,M.49 216 RCIC MINIMUM FLOW liv 49-lF019 8 LFRC -hef M 49
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TABLE 3.6.3-1 ,
' PRIMARY CONIAINMENT ISOLATION VALVE 5
, NOTATION JAlf
~/ .
NOTES (Continued)- l
- 21. Automatic isolation signal causes TIP to retract; ball valve closes when probe is fully retracted. ,
- 22. Isolation barrier remains water filled or a water seal remains in the
. line post-LOCA. Isolation valve may be tested with water. Isolation valve leakage is not included in 0.60 La total Type B & C tests.
- 23. Valve does not receive an'isolati,on signal. Valves will be open during Type A test. Type C test not required.
- 24. Both isolation signals required for valve closure.
2,5. Deleted -
- 26. Valve stroke times listed are maximum times verified by testing per Speci-fication 4.0.5 acceptance criteria. The closure times for isolation valves in lines in which high-energy line breaks could occur are identified with a single asterisk. The closure times for isolation valves in lines which provide an open path from the containment to the environs are ioentified with a double asterisk.
- 27. The reactor vessel head seal leak tietection line (penetration 29A) excess flow check valve is not subject to OPERABILITY testing. This valve will not be exposed to primary system pressure except under the unlikely con-ditions of a seal failure where it could be partially pressurized to reactor pressure. Any leakage path is restricted at the source; therefore, this valve need not be OPERABILITY tested.
'd s 28. (DELETED)
- 29. Valve may be open during normal operation; capable of manual isolation from. control room. Position will be controlled procedurally.
- 30. Valve normally open, closes on scram signal.
- 31. Valve 41-1016 is an outboard isolation barrier for penetrations X-9A, B and X-44 Leakage through valve 41-1016 is included in the total for penetration X-44 only.
- 32. Feedwater long path recirculation valves are sealed closed whenever the reactor is critical and reactor pressure is greater than 600 psig. The valves are expected to be opened only in the following instances:
a Flushing of 'the condensate and feedwater systems during plant startup.
- b. Reactor pressure vessel hydrostatic testing, which is conducted follow-ing each refueling outage prior to commencing plant startup.
Therefore, valve stroke timing in accordance with Specification 4.0.5 is not required.
- 33. Valve also constitutes a Unit 2 Reactor Enclosure Secondary Containment Automatic Isolation Valve and a Refueling Area Secondary Containment Automatic Isolation Valve as shown in Table 3.6.5.2.1-1 and Table 3.6.5.2.2-1 respectively.
Q kc Y A Ar] * *
,-- LIMERICK - UNIT 1 3/4 6-43 Amendment No. 23 W JH 2 213ll
TABL'i 3,6.3-1 PRIMARY CONTAINPENT ISOLATION VALVES NOTATION NOTES (Continued) Al L 34. These valves are in lines that are below the minimum water level in the suppression I
/ pool, are part of closed systems outside primary containment, and are in portions of lines which a water seal will be present following an accident. Therefore, 10CFR50, Appendix J, Type C testing is not required. l Add L n 3/V6-f2 l
e N
4 - -
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n.
3 TABLE 3.6.3-1.(Continued) .'
g PART A - PRIMARY CONTAL NI ISOLATION VALVES .
N 5 INBOARD OUTBOARD ISOL.
p PENETRATION FUNCTION i$ ISOLATION ISOLATION MAX.ISOL. SIGNAL (S), NOTES P&ID NUMER e
}
BARRIER 3ARRIER TIME.IF APP.
(SEC)(26)
IF APP.
,, (20) i
$ !$ SV57-291 5 B,H,R,5 11 y ff (X-220A) 116 STANDBYLIQUIDiCONTROL 48-2F007(CK) NA 48 p (X-42) HV48-2F0068 60 29 1178-1 DRWELL RADIATION SV26-290A , 5 B,H R.S 11 26 MDNITORING SUPPLY SV26-2908 ,5 B,H,R,5 11
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201A SUPPRESSION POOL PURGE HV57-224 ,
5** B,H,S,U,W,R,T 3.11,14 57
{ SUPPLY }t HV57-231(X-25) . 5** B,H,S,U,W,R,T 3,11,14 m HV57-209(X-25)~6** B,H,5,U,W,R,T 11 4 ~h' HV57-247 6** B,H S U,W,R,T 11
B,H,5,U,W,R,T 11 HYDROGEN RECOMINER HV57-264 '9 -
8,H,R,5 3,11,14 "B" EXHAUST Si '
,$ HV57-269 9 B,H,'R,5 11 202 SUPPRESSIONPOOkPURGEHV57-204 5** B,H,S,U,W,R,T 3,11,14,3357[
EXHAUST ?. HV57-205 15** B,H,S,U R.T 11 e
p HV57-212 6** B,H,5,U,W,R,T 11, 33 f HV57-218 5** B,H,S,U,R,T 11
- g. SV57-285 5 B,H,R,5 11 HYDROGEN RECOMINER HV57-262 9 B,H,R,5 3,11,14 "A" EXHAUST v
.g ,
HV57-266 9 B,H.R,5 11 203A(B,C,0) RHRPUMPSUCTIdN 004A 240 51 E # '
PSV51-2F030A NA 49T e&3f' e $ (B,C.D) -
3cv -
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e-. TABLE 3.6.3-1 (Continued) -
c ,
{ PART A - PRIMRY CONTAllOENT' ISOLATION VALVES -
k N INBOARD OUT80ARD . .
ISOL.
PENETRATION FUNCTION 84 ISOLATION ISOLATION N4X.ISOL. SIGNAL (S), NOTES P&ID g NUMBER ,.. BARRIER BARRIER TIIE.IF APP. IF APP.
p + '. -(SEC)(26) (20) 204A(8) RHRPtwTESThMEAND HV51-225A(B) 1 4;;ft.29)f51 C0dTAllOENT COOLING
- g. .
205A(8) SUPPRESSION POOL SPRAY
.HV51-2F027A(8) 45. C.G 11 51 E
206A(B,C,5) CS Ptw SUCTION 1 HV52-2F001A 160 k - 434,29)f52 f (8,C,8) 3 u -
, k ab -
207A(B) CS PUW TEST Am FLUSH . MV52-2F015A(8) 23' C.G %222f 52 k*.
5 -
2088 CS PtMP NININIMjRECIRC HV52-2F0318 45 LFCH 4r32.29,Y52 i M t$ 209 HPCI PUW SUCTION HV55-2F042 ~160 L.LA h 23-35 55 y _ . +. : .: e ,
210 HPCI TUR8INE EXHAUST HV55-2F072~ ,120 .. . 4728,29,655 212 HPCI PUW TESTfAle FLUSH g.
HV55-2F&7.1 l40 I' 8,H -
432.J'i 55 r.: .o 214 RCIC PUW SUCTION . IN49-2F031 60 ' 4y34,29,649 sy; s ;e .-
215 RCIC TUR8INE EXHAUST NV49-2F060 80 - 4r32,29,I49 W '
! 216 RCIC NINIMM FLOW XV49-2F019 * '8 LFRC 5A3T 49 '
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C W TABLE 3.6.3-1 (Continued) x % .
@ .), PART A - PRIMARY CONTAINMENT ISOLATION VALVES R 'P:
% INBOARD OUTBOARD ISOL.
3 ISOLATION ISOLATION MAX.ISOL. SIGNAL (S), NOTES P & ID h PENETRATION FUNCTION BARRIER BARRIER . TIME.IF APP. IF APP.
3
-4 NUMBER 41 a (SEC)(26) (20) I ro .
n 226A RilR MINIMUM RECIRC IIV51-205A 40 +;tt,29,5I 51 226B RilR MINIMUM RECIRC llV51-205B 40 he2,29 3I 51 j
60 227 ILRTDATAACQUISITION60-2073 NA '
SYSTEM . . .
60-2074 NA 3 4,11.24 228D llPCI VACUUM RELIEF llV55-2F095 40 ll,LA 55 w 40 H,LA 11,24 llV5c-2F093 2 ..(
'e m -- SVL :1 5 10 57 A, 229A INSTRUMENTATION -1
= SUPPRESSION P00la' PRESSURE '
SUPPRESSIONPOOLCLEVEL
. y HV61-212 45 23,29 61 230B INSTRUMENTATIONJ!DRYWELL --
j HV61-232 45 23,29 SUMP LEVEL a
llV61-210 30 B,H 11,22 61 23IA DRYWELL FLOOR DRAIN y
to f;;
i SUMP DISCHARGE IIV61-211 30 B,H 11,22 Um a ,
kw DRYWELL EQUIPMENT 0 RAIN llV61-230 30 B,H ' 11,22 61 231B 8,H 11,22 HV61-231 30 3-- TANK DIScilARGE ,
m -- Svea,29 llV52-2F03IA 45 LFCH j 3f 52
?$ 235 CSPUMPMINIMUMikECIRC IIPCI PUMP MINIMUM RECIRC IIV55-2F012 15 LFHP -erb 4 3r 55 236
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TABLE 3.6.3;1 s PRIMARY CONTAINMENT ISOLATION VALVE 5 NOTATION
~
NOTES (Continued)
- 21. Automatic isolation signal causes TIP to retract; ball valve closes when probe is fully retracted. .
- 22. Isolation barrier remains water filled or a water seal remains in the line post-LOCA. Isolation valve may be tested with water. Isolation valve leakage is not included in 0.60 La total Type B & C tests. -
- 23. ' Valve does not receive an isolation signal. Valves will be open during Type A test. Type C test not required.*
- 24. Both isolation signals required for valve closure.
25,; Deleted 26.WValve . stroke times listed are maximum times verified tiy' testing per Speci-i - 4 ification'4.0.5 acceptance criteria. The closure times for isolation valves
- in:. lines .in which high-energy. line breaks could occur are identified with a
~s ingle asterisk. The closure times for isolation valves in lines which
.w. provide .an open path'from the containment to the environs are identified b with'a double asterisk.'
' 27. The reactor' vessel head seal leak detection line (penetration 29A) excess flow check valve is not subject to OPERABILITY testing. - This valve will not be exposed to primary system pressure except under the unlikely con-ditions of a seal fhilure where it could be partially pressurized to I reactor pressure. Any leakage path is restricted at the source; therefore, l y this valve need not be OPERABILITY tested.
I 28. (DELETED)
I
- 29. Valve say be open during normal operation; capable of manual' isolation from control room. Position will be controlled procedurally. j
- 30. Valve normally open, closes on scram signal.
- 31. Valve 41-2016 'is an outboard isolation barrier for penetrations X-9A, B l and X-44. Leakage through valve 41-2016 is included in the total for !
penetration X-44 only.
. ~
$$ffh 32. qFeedwater lonrpath e recirculationFeactorvalves are sealed. closed 600 whenever.the y,^:.m 2
wn:nrwFgiggy:isMitica1 and f pves'sure"islriker"tfaW psig." The' -
valves are expected to be opened only in the following instances:
- a. Flushing of the condensate and feedwater systees during plant startup.
- b. Reactor pressure vessel hydrostatic testing, which is conducted follow-ing each refueling outage prior to commencing plant startup.
Therefore, valve stroke timing in accordance with Specification 4.0.5 is not required.
- 33. Valve also constitutes a Unit 1 Reactor Enclosure Secondary containment Automatic Isolation Valve and a Refueling Area Secondary Containment Automatic.
Isolation Valve as shown in Table 3.6.5.2.1-1 and Table 3.6.5.2.2-1, '
respectively. -
- 34. Isolation signal causes recombiner to trip; valve closes when recombiner l C..) j r E- Id Abchad AUS251911 LIMERI - 3/4 6-43
TABLE 3.6.3-1 PRIMARY CONTAIIMENT ISOLATION VALVES NOTATION NOTES (Continued)
- 35. These valves are in lines that are below the minimum water level in the suppression pool,ines of l which a water seal will be present following an accident. Therefore,are part of 10CFR50, Appendix J, Type C testing is not required.
/Jdd 43 m 2//6-%?
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