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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20247M6891998-05-14014 May 1998 Amend 128 to License NPF-39,documenting NRC Staff Approval of Implementation of Plant Mod to Support Installation of Replacement Suction Strainers for ECCS at Plant,Unit 1 ML20217Q5001998-05-0404 May 1998 Amend 127 to License NPF-39,revising Minimal Critical Power Ratio Safety Limits for Operation Cycle 8 ML20217M0731998-03-31031 March 1998 Amends 125 & 89 to Licenses NPF-39 & NPF-85,respectively, Revising LGS Units 1 & 2 TS Section 4.0.5 & Bases Sections B 3/4.4.8 Re Surveillance Requirements Associated W/Isi & IST ML20246G2071989-08-25025 August 1989 License NPF-85,authorizing Operation of Limerick Generating Station at Reactor Power Levels of 3,293 Mwt (100% Rated Power) ML20245F1561989-06-22022 June 1989 License NPF-83,authorizing Fuel Loading & Precriticality Testing of Plant ML20151T5141988-08-0303 August 1988 Amend 9 to License NPF-39,modifying Paragraph 2.E to Require Compliance W/Amended Physical Security Plan 1998-05-04
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217F0941999-10-14014 October 1999 Application for Amends to Licenses DPR-39 & DPR-85,to Revise TS Sections 2.2 & 3.0/4.0 to Support Mod P000224 Which Will Install New Power Range Neutron Monitoring Sys & Incorporate long-term thermal-hydraulic Stability Solution Hardware ML20216J3341999-09-27027 September 1999 Supplements Application for Amends to Licenses NPF-39 & NPF-45,to Modify Appearance of TS Page 3/4 4-8 as Typo Was Identified in Section 3.4.3.1 of Ts.Corrected TS Page,Encl ML20212H5521999-09-27027 September 1999 Application for Amends to Licenses NPF-39 & NPF-85,revising TS to Clarify Several Administrative Requirements,Deleting Redundant Requirements & Correcting Typos ML20212F9521999-09-20020 September 1999 Application for Amend to License NFP-39,requesting Issuance of TS Change Request 98-08-0 Re Increase in Allowable as- Found Main Steam SRV Setpoint Tolerance.Util Had Originally Requested That Subject TS Change Be Deferred in ML20196F5471999-06-22022 June 1999 Application for Amends to Licenses NPF-39 & NPF-85,change Request 99-01-0,to Revise TS to Delete Surveillance Requirement 4.4.1.1.2 & Associated TS Administrative Controls Section 6.9.1.9.h ML20195E7521999-06-0707 June 1999 TS Change Request 91-08-01 to License NPF-39,reflecting Permanently Deactivated Instrument Reference Leg Isolation Valve HV-61-102 in TS Table 3.6.3-1, Primary Containment Isolation Valves & Associated Notations ML20195G0421999-06-0707 June 1999 TS Change Request 98-09-0 for Licenses NPF-39 & NPF-85, Revising TS Section 3/4.4.3, RCS Leakage,Leakage Detection Systems, by Clarifying Action Statement Re Inoperative Reactor Coolant Leakage Detection Systems ML20195B8361999-05-26026 May 1999 TS Change Request 99-02-0 for Licenses NPF-39 & NPF-85, Revising TS Section 4.1.3.5.b by Removing & Relocating Control Rod Scram Accumulators Alarm Instrumentation to UFSAR & Revising TS Section 3.1.3.5 ML20207L6561999-03-11011 March 1999 TS Change Request 98-07-2 for License NPF-85,revising MCPR Safety Limit Contained in TS Section 2.1, Safety Limits. Proprietary & non-proprietary Info Re Cycle Specific SLMCPR for Lgs,Unit 2 Cycle 6,encl.Proprietary Info Withheld ML20199G1651999-01-12012 January 1999 TS Change Request 98-08-0 to Licenses NPF-39 & NPF-85, Proposing Rev to TS Section 3/4.4.2 & TS Bases Sections B 3/4.4.2,B 3/4.5.1 & B 3/4.5.2.Supporting TSs & Proprietary & non-proprietary Trs,Encl.Proprietary Info Withheld ML20199A6861999-01-0404 January 1999 TS Change Request 97-01-01 to Licenses NPF-39 & NPF-85, Revising Administrative Section on Controlled Access to High Radiation Areas & Rept Dates for Listed Repts ML20155H6311998-10-30030 October 1998 Application for Amends to Licenses NPF-39 & NPF-85, Respectively,Revising TS Surveillance Requirements 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 ML20154Q8781998-10-15015 October 1998 TS Change Request 97-04-0 to Licenses NPF-39 to NPF-85, Adding New TS Section & TS Bases Section to Incorporate Special Test Exception to Allow Rc Temp Greater than 200 F During IST & Hydrostatic Testing ML20151Z4541998-09-14014 September 1998 TS Change Request 98-04-2 to License NPF-85,revising TS Table 4.4.6.1.3-1 Re Withdrawal Schedule for Reactor Pressure Vessel Matl Surveillance Program Capsules.Ge Rept GE-NE-B1100786,encl ML20151V0731998-09-0404 September 1998 TS Change Request 96-23-0 to Licenses NPF-39 & NPF-85, Revising TS Pages to Ensure Fidelity Between TS Pages & 970324 Submittal ML20236L5151998-07-0202 July 1998 Supplemental Application for Amend to Licenses NPF-39 & NPF-85,consisting of TS Change Request 96-06-0,modifying Appearance of Unit 1,FOL Page 8 ML20247M6891998-05-14014 May 1998 Amend 128 to License NPF-39,documenting NRC Staff Approval of Implementation of Plant Mod to Support Installation of Replacement Suction Strainers for ECCS at Plant,Unit 1 ML20217Q5001998-05-0404 May 1998 Amend 127 to License NPF-39,revising Minimal Critical Power Ratio Safety Limits for Operation Cycle 8 ML20217M0731998-03-31031 March 1998 Amends 125 & 89 to Licenses NPF-39 & NPF-85,respectively, Revising LGS Units 1 & 2 TS Section 4.0.5 & Bases Sections B 3/4.4.8 Re Surveillance Requirements Associated W/Isi & IST ML20202G7591998-02-0909 February 1998 Application for Amend to License NPF-39,revising TS Section 2.1, Safety Limits, to Revise Minimum Critical Power Ratio Safety Limit.Proprietary Supporting Info Withheld (Ref 10CFR2.790) ML20199G7701998-01-27027 January 1998 Application for Amends to Licenses NPF-39 & NPF-89,removing Maximum Isolation Time for HPCI Turbine Exhaust Containment Isolation Valve HV-055-1(2)F072 from Ts.Change Request 98-01-0 & marked-up TS Encl ML20198M7551998-01-12012 January 1998 TS Change Request 97-02-1 to License NPF-39,revising TS Table 4.4.6.1.3-1 to Change Withdrawal Schedule for First Capsule to Be Withdrawn from 10 Effective Full Power Yrs to 15 Efpy.Ge Rept GE-NE-B1100786-01,Rev 1 Encl ML20212D1761997-10-24024 October 1997 Application for Amend to License NPF-39,revising TS Section 3/4.1.3.6,to Exempt Control Rod 50-27 from Coupling Test for Remainder of Cycle 7,provided Certain Conditions Are Met ML20216H0931997-09-0808 September 1997 Application for Amends to Licenses NPF-39 & NPF-85, Supplementing Changes Request 96-06-0 by Adding Three Addl TS Pages Containing Typo Errors Discovered Since 970225 Submittal ML20210T9141997-09-0202 September 1997 TS Change Request 96-20-0 to Licenses NPF-39 & NPF-85, Revising TS Section 4.0.5 & Bases Sections B 4.0.5 & B 3/4.4.8,re SRs Associated W/Isi & Inservice Testing of ASME Code Class 1,2 & 3 Components ML20137X7931997-04-0909 April 1997 TS Change Request 96-24-0 to Licenses NPF-39 & NPF-85, Deleting Requirement to Correct Specific Gravity Values Based on Electrolyte Battery State of Charge ML20137G6611997-03-24024 March 1997 Application for Amends to Licenses NPF-39 & NPF-85,deleting Drywell & Suppression Chamber Purge Sys Operational Time Limit & Adding SR to Ensure Purge Sys Large Supply & Exhaust Valves Are Closed as Required ML20135D0861997-02-25025 February 1997 Application for Amends to Licenses NPF-39 & NPF-85, Reflecting Name Change from PA Electric Co to PECO Energy Co ML20135F0911996-12-0606 December 1996 Application for Amend to License NPF-85,revising TS 2.1 to Change Minimum Critical Power Ratio Safety Limit ML20135A3841996-11-25025 November 1996 Application for Amends to Licenses NPF-39 & NPF-85,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 ML20128N7551996-09-27027 September 1996 Application for Amends to Licenses NPF-39 & NPF-85, Requesting Rev to Increase Reactor Enclosure Secondary Containment Maximum Inleakage Rate ML20116L2551996-08-0808 August 1996 Application for Amends to Licenses NPF-39 & NPF-85,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 ML20116H6161996-08-0505 August 1996 Application for Amend to License NPF-85,revising TS Section 2.1, Safety Limits, to Revise Min Critical Power Ratio Safety Limit ML20116E5981996-08-0101 August 1996 Application for Amend to License NPF-85,revising TS Section 3/4.4.4.6 to Reflect Addition of Two Hydroset Curves Effective for 6.5 & 8.5 Effective Full Power Years,To Existing Pressure-Temp Operating Limit for LGS Unit 2 ML20115A9071996-06-28028 June 1996 Application for Amend to Licenses NPF-39 & NPF-85 to Perform Containment leakage-rate Testing Per 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors, Option B ML20117H2441996-05-20020 May 1996 TS Change Request 96-12-0 to Licenses NPF-39 & NPF-85, Revising TS 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 Describe,Rhr Sys Shutdown Cooling Mode of Operation ML20117D7451996-05-0303 May 1996 Application for Amends to Licenses NPF-39 & NPF-85,revising TS SRs to Change Surveillance Test Frequency for Performing Flow Testing of SGTS & RERS from Monthly to Quarterly ML20107M5061996-04-25025 April 1996 TS Change Request 95-08-0 to Licenses NPF-39 & NPF-85, Relocating TS 3/4.7.7 Re Traversing in-core Probe LCO ML20101L9111996-03-29029 March 1996 Application for Amends to Licenses NPF-39 & NPF-85, Respectively,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 ML20095K4801995-12-22022 December 1995 Application for Amend to Licenses NPF-39 & NPF-85,increasing Drywell & Suppression Chamber Purge Sys Operating Time Limit from 90 H Each 365 Days to 180 H Each 365 Days ML20092J3941995-09-18018 September 1995 TS Change Request 95-01-0 to Licenses NPF-39 & NPF-85, Revising TS Table 4.3.1.1-1, RPS Instrumentation SRs to Reflect Change in Calibr Frequency for LPRM Signal from Every 1,000 EFPH to Every 2,000 Megawatt Days Per Std Ton ML20092J3181995-09-14014 September 1995 Application for Amends to Licenses NPF-39 & NPF-85,revising TS to Remove Secondary Containment Isolation Valve Tables ML20087C9451995-08-0101 August 1995 TS Change Request 95-12-0 Revising TS Section 3/4.9.1, to Provide Alternate Actions to Allow Continuation of Core Alterations in Event Certain RMCS & Refueling Interlocks Are Inoperable ML20086S5981995-07-28028 July 1995 Application for Amends to Licenses NPF-39 & NPF-85,revising TS Table 4.3.1.1-1,to Reflect Changes to Surveillance Test Frequency Requirements for Various RPS Instrumentation ML20086U4821995-07-28028 July 1995 TS Change Request 94-28-0 to Licenses NPF-39 & NPF-85, Revising TS SR & Deleting Specific Requirements to Perform Surveillances Prior to Beginning or Resuming Core Alterations or CR Withdrawal Assoc W/Refueling Activities ML20086U4361995-07-28028 July 1995 TS Change Request 95-09-0 to Licenses NPF-39 & NPF-8, Revising Ts,By Deleting Operability & SR Involving Secondary Containment Diffrential Pressure Instrumentation ML20086T6061995-07-28028 July 1995 TS Change Request 95-13-0 of License NPF-39 & NPF-85, Requesting Change to Ts,To Eliminate TS Requirement to Perform 10CFR50,App J,Type C,Hydrostatic Testing on Certain Valves ML20086A1631995-06-23023 June 1995 Application for Amend to License NPF-85,consisting of Change Request 95-07-2,extending AOT to Allow Adequate Time to Install Isolation Valves & cross-ties on ESW & RHRSW Sys to Facilitate Future Insps or Maint ML20085M8811995-06-20020 June 1995 Application for Amend to Licenses NPF-39 & NPF-85,consisting of Change Request 95-06,requesting one-time Schedular Exemption from 10CFR50,App J, Primary Containment Leakage Testing for Water-Cooled Power Reactors ML20085M9171995-06-19019 June 1995 Application for Amend to License NPF-39,consisting of Change Request 95-03,revising TS Section 2.1, Safety Limits, to Change MCPR Safety Limit,Due to Use of GE13 Fuel Product Line 1999-09-27
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Text
- M84 p 1 UNITED STATES j
, i NUCLEAR RECULATCRY COMMISSION WAsNINGToN, D.C. 30006 4001 s.,.....J l
PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-352 4 LIMERICK GENERATING STATION. UNIT 1 l AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No.128 License No. NPF-3g -l l
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- 1. The Nuclear Regulatory Commission (the Commission) has found that:
l A. The application for amendment by Philadelphia Electric Company (the licensee) 'l dated October 6,1997, as supplemented Fetruary 2 and May 13,1998, complies 1 with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 .
CFR ChapterI; B. The facility will operate in conformity witn the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment :
can be conducted without endangering the health and safety of the public, and (ii) !
that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9805260335 990514 "
PDR ADOCK 05000352 P PDR_ m
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- 2. Accordingly, the license is amended to add paragraph 2.C.(16) to Facility Operating Ucense No. NPF-39 as follows:
(16) AdditionalConditions t The Additional Conditions contained in Appendix C, as revised through Amendment No.
128 are hereby incorporated Ir to this license. Philadelphia Electric Company shall operate the facility in accordance with the Additional Condnions.
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! 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY i- COMMISSION T s L . J a .. C e r e J Robert A. Capra, Director Project Directorate 1-2 1 Division of Reactor Projects - t/11 Office of Nuclear Reactor Regulation
Attachment:
- 1. Pages 7 and 9 of Ucense* No. NPF-39
- 2. Page 1 of Appendix C Date of lasuance: May 14, 1998
- Pages 7 and 9 of the license and page 1 of Appendix C are attached, for convenience, for the composite license to reflect this change.
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7 (14) ftefuelina Floor Volume Connection to Standby Gas Treatment System (Section 6.2.3. SSER-2 and SSER-11 Prior to any roovement of irradia%d fuel within the refueling floor volume the licensee shall complete and test all modifications required to connect the refueling floor volume to standby gas treatment system. During the interim period, the !!cens6e shall not remove the reactor pressure vessel head prior to the NRC staff review and approval.
(15) Ememency Plannino Procedures Subiect to 44 CFR Par 1350 in the event the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, !s an indication that a major substantive problem ex!sts in achieving or ma'ntaining an adequate state of emergency properedness, the provisions of 10 CFR Section 50.54(s)(2) will apply.
l l' (16) Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No.128 are hereby incorporated into this licer.se.
Philadelphia Electric Company shall operate the facility !n accordance with the Additional Conditions.
I D. The facility requires exemptions from certain requirements of 10 CFR Part 50.
l These include (a) exemption from General Design Critoria (GDC) 61 of Appendix A, operation of that portion of the standby gas treatment system (SGTS) that serves the refueling area until the first refueling (Section 6.2.3 of SSER-2 and SSER 3) , (b) exemption from GDC 56 of Appendix A, the requirement for additional automatic containment isolation valves for the hydrogen recombiner lines and the requirement for automatic isolation of existing isolation valves in the Drywell Chilled Water (DCW) and the Reactor Enclosure Cooling Water (RECW) systems until prior to startup following the first refueling outage (Section 6.2.4.2 of the SER, SSER-1 and SSER-3), (c) exemption from GDC-1g of Aopendix A, as related to the requirement for redundant remote shutdown capability (Section 7.4.2.3 of SSER-3 and SSER-5),
(d) exemption from the requirement of Appendix J, the testing of containment mir locks at times when the containment integrity is not required (Section 6.2.6.1 of the SER and SSER-3), (e) exemption from the requirements of Appendix J, the l leak rate testing of the Main Steam isolation Valves (MSIVs) at the peak calculated containment pressure, Pa, and exemphon from the roouirements of Appendix J that the measured MSIV lesk rates be included in the summation for
- l. the local leak rate test (Section 6.2.6 of SSER-3), (f) exemption from the l requirement of Appendix .1, the local leak rate testing of the Traveming incore Probe Shear Valves (Sochon 6.2.6 of the SER and SSER-3), (g) a one time I exemption from the recluiratoent of Appendix J to perform local leak Amendment No. 446: 128 l
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H. This license is effective es of the date of issuance and shall expire at midnight .
on October 26,2024.
1 FOR THE NUCEAR REGUt.ATORY COMMISSION original signed by Darrell Eisenhut for i
Harold R. Denton, Director i Office of Nuclear Reactor Regulation !
Attachments / Appendices:
- 1. Attachments 1-2
- 2. Appendix A - Technical Specifications (NUREG-1149)
- 3. Appendix B - Environmental Protection Plan
- 4. Appendix C - Additional Conditions l
Date ofissuance: August 8,1985 i
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t Amendment No.128 !
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APPENDIX C ADDITIONAL CONDITIONS OPERATING LICENSE NO, NPF-39 Philadelphia Electric Company shall comply with the following conditions on the schedules noted below:
Amendmsr:t Additional Conditions implementaSon Number Date 128 This amendment authorizes the licensees to incorporate 30 days from i in the Updated Final Safety Analysis Report (UFSAR) May 14, 1998 I
certain changes to the description of the facility.
- implementation of this amendment is the incorporation of these changes as described in the licensee's application dated October 6,1997, as supplemented by letter dated i February 2,1998, and evaluated in the safety evaluation dated .
128 The suppression pool floor und the low pressure ECCS 1 (RHR and Cors Spray) suction strainers shall be visually l inspected for sludge accumulation and foreign material.
The visualinspection allows use of a remote camera in lieu of divers. The interval of these inspections shall be every other refueling outage. The inspection interval l
may be increased based on findings of two consecutive inspections. Should the licensee choose to increase the inspection interval, data supporting this increase shall be submitted to the NRC for review l
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i i Amendment No.128 l