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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] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20195J1651998-11-16016 November 1998 Rev D to LGS Emergency Preparedness NUMARC Eals 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 ML20203H2501997-12-31031 December 1997 Rev 19 to Odcm ML20211P9471997-10-15015 October 1997 Revised MSRV Tailpipe Temp Action Plan ML20203H2701997-04-30030 April 1997 Rev 18 to Odcm ML20113E0491996-06-28028 June 1996 Technical Basis & Description of Approach for Review Method Selection ML20100L9131995-11-30030 November 1995 Rev 17 to LGS Units 1 & 2 Odcm ML20094B5391995-10-24024 October 1995 Scenario Manual for Limerick Generating Station Emergency Preparedness Annual Exercise (Radiological Scenario) ML20094B5041995-10-24024 October 1995 Scenario Manual for Limerick Generating Station Emergency Preparedness Annual Exercise (General Scenario) ML20100L9051995-05-0808 May 1995 Rev 16 to LGS Units 1 & 2 Odcm ML20100L9001995-01-19019 January 1995 Rev 1 to RW-C-100, Solid Radwaste Sys Pcp ML20080N1461994-12-31031 December 1994 Rev 15 to LGS Units 1 & 2 Odcm ML20073S9471994-06-21021 June 1994 Non-proprietary Revised Emergency Response Procedures, Including Revs 43 & 44 to Index,Rev 10 to ERP-300 & Rev 9 to & ERP-500 ML20080N1401994-06-0909 June 1994 Rev 14 to LGS Units 1 & 2 Odcm ML20080N1291994-06-0606 June 1994 Rev 13 to LGS Units 1 & 2 Odcm ML20080N1171994-04-30030 April 1994 Rev 12 to LGS Units 1 & 2 Odcm ML20056G0981992-12-28028 December 1992 Rev 0 to Procedure RW-C-100, Solid Radwaste Sys Pcp. Procedure Supersedes RW-800 at LGS & RW-120 & RW-121 at PBAPS ML20098D9641992-05-20020 May 1992 Rev 57 to Limerick Generating Station Off-Normal (on) (Bases) Procedures Index,Reflecting Rev 0 to ON-123 Bases, Mispositioned Control Rod ML20098D9501992-05-18018 May 1992 Rev 0 to Off-Normal (on) Procedure ON-123 Bases, Mispositioned Control Rod ML20098D9451992-05-18018 May 1992 Rev 0 to Off-Normal (on) Procedure ON-123, Mispositioned Control Rod ML20113G9421992-05-0101 May 1992 Rev 2 to Spec ML-008, Limerick Generating Station,Units 1 & 2 First Ten Yr Interval Pump & Valve IST Program ML20094S5671992-04-0303 April 1992 Rev 54 to Operational Transient Procedures Index ML20094S5881992-04-0303 April 1992 Rev 54 to Operational Transient Bases Procedures Index ML20094S5931992-04-0101 April 1992 Rev 9 to OT-100 Reactor Low Level ML20094S5751992-04-0101 April 1992 Rev 9 to OT-100 Bases, Reactor Low Level - Bases ML20091N2791991-10-0404 October 1991 Inservice Insp Program, First 10-Yr Interval ML20065S1171990-12-0606 December 1990 Procedures Index to Rev 2 to ON-120 Bases, Fuel Handling Problems ML20065S1151990-12-0606 December 1990 Rev 2 to ON-120 Bases, Fuel Handling Problems ML20065M6731990-11-26026 November 1990 Rev 19 to Limerick Generating Station Trip Bases Procedures Index ML20059E6501990-04-0303 April 1990 Rev 8 to Odcm ML20246E1601989-07-27027 July 1989 Samda Estimate Process & Cost Estimate Breakdown ML20246K5581989-03-0303 March 1989 Rev 8 to Solid Radwaste Sys Process Control Program ML20206M1671988-11-18018 November 1988 Rev 0 to Pump & Valve Inservice Testing (IST) Program,First 10 Yr Interval ML20205K8301988-08-31031 August 1988 Rev 1 to, Limerick Generating Station Unit 2 Reactor Pressure Vessel Preservice Insp Exam Plan ML20154B9361988-08-29029 August 1988 Rev 0 to Readiness Verification Program (Rvp) Description ML20150C9531988-07-0606 July 1988 Rev 1 to Program for Independent Design & Const Assessment of Limerick - Unit 2 ML20155A0081988-05-27027 May 1988 Rev 0 to Program for Independent Design & Const Assessment ML20151W2701988-04-26026 April 1988 Rev 5 to 8031-P-505, Preservice Insp Exam Plan for Nuclear Piping Sys ML20150E7971988-03-30030 March 1988 Rev 5 to Offsite Dose Calculation Manual ML20151W3551987-11-19019 November 1987 Suppl 2 to Rev 2 to UT-AUSTENITIC-M, Suppl for Manual Ultrasonic Exam of Dissimilar Metal Welds ML20151W3501987-11-18018 November 1987 Suppl 2 to Rev 1 to UT-AUSTENITIC-A, Suppl for Automatic Ultrasonic Exam of Dissimilar Metal Welds ML20151W2831987-10-15015 October 1987 Rev 1 to Field Quality Procedure FQP-01, Procedure for Qualification & Certification of Insp & Testing Personnel in Accordance W/Asme/Ansi N45.2.6 - 1978 & Asme/Ansi NQA-1 ML20151W2971987-10-13013 October 1987 Rev 01 to Field Quality Procedure FQP-03, Procedure for Qualification & Certification of NDE Personnel in Accordance W/Asnt SNT-Tc-1A & Section XI ML20151W3451987-08-28028 August 1987 Suppl 1 to Rev 1 to UT-AUSTENITIC-A, Suppl for Ultrasonic Exam of Weld Overlayed Austenitic Piping ML20151W3391987-08-28028 August 1987 Rev 4 to UT-AUSTENITIC-A, Automatic Ultrasonic Exam of Similar & Dissimilar Metal Welds in Piping Sys ML20236Y2751987-08-28028 August 1987 Rev 1 to 8031-P-504, Preservice Insp Program ML20237J9901987-07-31031 July 1987 Rev 3 to First 10-yr Interval Augmented Inservice Insp Program ML20237J8401987-07-31031 July 1987 Rev 3 to First 10-yr Interval Inservice Insp Program ML20238C8121987-07-27027 July 1987 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 5 to App 1 to EP-102, Unusual Event Notification Message & Rev 8 to EP-110, Personnel Assembly & Accountability. W/Revised Index ML20236A7231987-07-21021 July 1987 Rev 6 to 80A2972, Pump & Valve Inservice Testing Program Plan for Limerick Generating Station Unit 1 1998-11-16
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2 1 Attachment - .
Docket Hos. 50 352 and 50-353 October 15,1997
- Page _1 Limerick Generatina Station. 'Inits 1 and 2 Revised Main Steam Relief Valve (MSRV5 Tailoice Temperature Action Plan For any MSRV > 235 degrees F (Alert Level)
Operations shall log the affected MSRV tailpipe temperature every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> while operating at power (and every six hours rturing startup). i A determination shall be made if the leakage is a main valve or a pilot valve lerk by the next day based on pilot temperature changes or other behavior of the leakage. Pilot
- valve leakage will be assumed if the cause is indeterminate.
>240 degrees F_(Action Level):
Engineering shall perform an assessment of the cause of leakage and evaluate setpoint operability by the next day (if pilot leakage or indeterminate).
Engineering shall begin trend;ng plant parameters to determine MSRV input to the suppression pool. Leakage shall be neitored and trended. Plant management shall -
be updated on status weekly.
At 200 lbnihr, the MSRV will be considered inoperable for setpoint actuated function
- at the required 1% setpoint tolerance.
Engineering shall project when the affected MSRV leakage will increase to 200, 500, ^
and 1000 lbm/hr based on current and previous temperaare trends or other exponence.-
. At 500 lbm/hr leakage rate, Outage Management shall schedule an outage to replace
' the affected MSRV prior to a leakage of 1000 lbm/hr.
Technical Basis and Discussion of Margins 235 degrees F - Leakage is above expected value but very low relative to operability concems.
240 degrees F - Leakage is below 100 lbm/hr design value and margin exists relative to
. operability concems.
200 lbm/hr- 1% Setpoint tolerance confidence is reduced and setpoint operability cannot be assured. Remote actuation is assured. Margin exists to an inadvertent opening concem.
500 lbm/hr- Leakage is abnormally high. Outage scheduling is warranted to avoid a
- forced shutdown. Remote actuation is assured. Margin exists to prevent inadvertent opening.
1000 lbm/hr- Margin to inadvertent opening is reduced such that continued operation is not justified.
9710220035 971015 PDR ADOCK 05000352 P. PDR; ,
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