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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2101999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20217M6631999-10-19019 October 1999 Forwards Insp Rept 50-277/99-07 & 50-278/99-07 on 990920.No Violations Noted ML18107A5601999-10-18018 October 1999 Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses ML20217K9241999-10-14014 October 1999 Forwards Amend 234 to License DPR-56 & Se.Amend Consists of Changes to TS in Response to Application & Suppls ,1001 & 06,which Will Support PBAPS Mod P00507,which Will Install Digital Pr Neutron Mining Sys ML20217F7391999-10-14014 October 1999 Requests Addl Info Re Peach Bottom Atomic Power Station Units 2 & 3 Appendix R Exemption Requests ML20217F6841999-10-13013 October 1999 Forwards Senior Reactor Operator Initial Exam Repts 50-277/99-302(OL) & 50-278/99-302(OL) Conducted on 990913- 16.All Applicants Passed All Portions of Exam ML20217F3021999-10-12012 October 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at PBAPS Have Been Completed.Ltr Also Confirms Completion of Actions Required by Confirmatory Order Modifying Licenses, ML20217E7451999-10-0808 October 1999 Forwards Response to NRC 990820 RAI Concerning Proposed Alternatives Associated with Third ten-yr Interval ISI Program for Pbaps,Units 2 & 3 ML18107A5531999-10-0808 October 1999 Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1 ML18107A5561999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML20217C4141999-10-0606 October 1999 Forwards Response to NRC 981109 RAI Re Resolution of USI A-46 for Pbaps.Proprietary Excerpts from GIP-2,Ref 25 Results of BWR Trial Plant Review Section 8 Also Encl. Proprietary Excerpts Withheld ML20217B9151999-10-0606 October 1999 Provides Clarifying Info to Enable NRC to Complete Review of License Change Request ECR 98-01802,re Changes Necessary to Support Installation of Digital Pr Neutron Monitoring & Incorporate long-term T/H Stability Solution Hardware ML20217B7701999-10-0606 October 1999 Submits Corrected Info to NRC 980528 RAI Re Util Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20217B4051999-10-0505 October 1999 Forwards Amend 233 to License DPR-56 & Safety Evaluation. Amend Changes Minimum Critical Power Ratio Safety Limit & Approved Methodologies Referenced in Core Operating Limits Report ML20217B3181999-10-0505 October 1999 Advises That Info Submitted in 990712 Application,Which Contained Attachment Entitled, Addl Info Re Cycle Spec SLMCPR for Peach Bottom 3 Cycle 13,dtd 990609, with Affidavit,Will Be Withheld from Public Disclosure ML18107A5501999-10-0505 October 1999 Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station ML18107A5521999-10-0505 October 1999 Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys ML18107A5591999-10-0505 October 1999 Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 ML20217B8891999-10-0101 October 1999 Forwards Response to RAI Re Request to Install Digital Power Range Neutron Monitoring Sys & Incorporate long-term,thermal-hydraulic Stability Solution Hardware. Revised TS Table 3.3.2.1-1 Encl 05000278/LER-1999-004, Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv)1999-10-0101 October 1999 Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv) ML20217D5211999-09-30030 September 1999 Informs That Remediating 3D Monicore Sys at Pbaps,Units 2 & 3 & 3D Monicore/Plant Monitoring Sys at Lgs,Unit 2 Has Been Completed Ahead of Schedule ML20212J6851999-09-29029 September 1999 Informs of Completion of mid-cycle PPR of Peach Bottom Atomic Power Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl New Insps Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20216J3981999-09-29029 September 1999 Submits Comments for Lgs,Unit 1 & Pbaps,Units 2 & 3 Rvid,Rev 2,based on Review as Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20212J6561999-09-29029 September 1999 Informs of Completion of mid-cycle PPR of Limerick Generating Station on 990913.Identified No Areas in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20212J5751999-09-28028 September 1999 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 990913-16 at Licensee Facility.Without Encls IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML20216J0191999-09-27027 September 1999 Forwards Request for Addl Info Re Util 990301 Request to Support Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware,For Plant ML20212H6171999-09-24024 September 1999 Forwards Rev 2 to COLR for Pbaps,Unit 2,Reload 12,Cycle 13, IAW TS Section 5.6.5.d.Rept Incorporates Revised Single Loop Operation MAPLHGR Flow Multiplier ML20212H5431999-09-24024 September 1999 Informs of Decision to Inspect H-3 & H-4 Shroud Welds During Upcoming 3R12 Outage Scheduled to Begin Late Sept 1999 ML20216H6751999-09-24024 September 1999 Forwards Amends 229 & 232 to Licenses DPR-44 & DPR-56, Respectively & Ser.Amends Will Delete SR Associated Only with Refueling Platform Fuel Grapple Fully Retracted Position Interlock Input,Currently Required by SR 3.9.1.1 ML20216H6451999-09-24024 September 1999 Forwards Notice of Withdrawal of Util 990806 Application for Amends to Fols DPR-44 & DPR-56.Proposed Change Would Have Involved Temporary Change to Increase Limit for Average Water Temp of Normal Heat Sink ML20212H6401999-09-24024 September 1999 Forwards Revised Epips,Including Rev 11 to ERP-101 & Rev 18 to ERP-800.Copy of Computer Generated Rept Index Identifying Latest Revs of LGS Erps,Encl ML20216F8811999-09-23023 September 1999 Withdraws 990806 Exigent License Change Application.Tech Spec Change to Allow Continued Power Operation with Elevated Cooling Water Temps During Potentially Extreme Weather Conditions No Longer Needed Due to Favorable Weather ML20212E8661999-09-22022 September 1999 Discusses GL 98-01 Y2K Readiness of Computer Sys at NPPs & Supplement 1 & PECO Response for PBAPS Dtd 990630. Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient During Y2K Transition ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML18107A5421999-09-22022 September 1999 Forwards Discharge Monitoring Rept for Salem Generating Station for Aug 1999.Rept Is Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML20212E7941999-09-22022 September 1999 Requests Authorization for Listed Licensed Operators to Temporarily Suspend Participation in Licensed Operator Requalification Program at LGS ML20212E8081999-09-22022 September 1999 Provides Notification That Listed Operators Have Been Permanently Reassigned to Duties That Do Not Require Maintaining Licensed Operator Status,Per 10CFR50.74 ML20212F5481999-09-20020 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing, for Pbaps,Units 2 & 3 & Lgs,Units 1 & 2 ML20212D1191999-09-17017 September 1999 Forwards SE Re Proposed Alternatives to ASME Section XI Requirements for Containment Inservice Insp Program at Plant,Units 2 & 3 ML20212F8991999-09-17017 September 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at Lgs,Units 1 & 2 Have Been Completed 05000353/LER-1999-010, Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl1999-09-16016 September 1999 Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl ML20216F7821999-09-16016 September 1999 Forwards Insp Repts 50-352/99-05 & 50-353/99-05 on 990713-0816.One Violation Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy.Violation Re Inoperability of Automatic Depression Sys During Maint ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML20212A8751999-09-13013 September 1999 Forwards Safety Evaluation of First & Second 10-year Interval Inservice Insp Plan Request for Relief ML18107A5331999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 ML18107A5321999-09-13013 September 1999 Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources. ML18107A5351999-09-13013 September 1999 Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments ML20212A0091999-09-0909 September 1999 Provides Notification That Licenses SOP-11172 & SOP-11321, for SO Muntzenberger & Rh Wright,Respectively,Are No Longer Necessary as Result of Permanent Reassignment ML20211N5061999-09-0909 September 1999 Forwards TSs Bases Pages B 3/4 10-2 & B 3/4 2-4 for LGS, Units 1 & 2,being Issued to Assure Distribution of Revised Bases Pages to All Holders of TSs 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18107A5601999-10-18018 October 1999 Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses ML20217F3021999-10-12012 October 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at PBAPS Have Been Completed.Ltr Also Confirms Completion of Actions Required by Confirmatory Order Modifying Licenses, ML20217E7451999-10-0808 October 1999 Forwards Response to NRC 990820 RAI Concerning Proposed Alternatives Associated with Third ten-yr Interval ISI Program for Pbaps,Units 2 & 3 ML18107A5531999-10-0808 October 1999 Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1 ML18107A5561999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML20217C4141999-10-0606 October 1999 Forwards Response to NRC 981109 RAI Re Resolution of USI A-46 for Pbaps.Proprietary Excerpts from GIP-2,Ref 25 Results of BWR Trial Plant Review Section 8 Also Encl. Proprietary Excerpts Withheld ML20217B9151999-10-0606 October 1999 Provides Clarifying Info to Enable NRC to Complete Review of License Change Request ECR 98-01802,re Changes Necessary to Support Installation of Digital Pr Neutron Monitoring & Incorporate long-term T/H Stability Solution Hardware ML20217B7701999-10-0606 October 1999 Submits Corrected Info to NRC 980528 RAI Re Util Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML18107A5501999-10-0505 October 1999 Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station ML18107A5521999-10-0505 October 1999 Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys ML18107A5591999-10-0505 October 1999 Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 ML20217B8891999-10-0101 October 1999 Forwards Response to RAI Re Request to Install Digital Power Range Neutron Monitoring Sys & Incorporate long-term,thermal-hydraulic Stability Solution Hardware. Revised TS Table 3.3.2.1-1 Encl 05000278/LER-1999-004, Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv)1999-10-0101 October 1999 Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv) ML20217D5211999-09-30030 September 1999 Informs That Remediating 3D Monicore Sys at Pbaps,Units 2 & 3 & 3D Monicore/Plant Monitoring Sys at Lgs,Unit 2 Has Been Completed Ahead of Schedule ML20216J3981999-09-29029 September 1999 Submits Comments for Lgs,Unit 1 & Pbaps,Units 2 & 3 Rvid,Rev 2,based on Review as Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20212H6171999-09-24024 September 1999 Forwards Rev 2 to COLR for Pbaps,Unit 2,Reload 12,Cycle 13, IAW TS Section 5.6.5.d.Rept Incorporates Revised Single Loop Operation MAPLHGR Flow Multiplier ML20212H5431999-09-24024 September 1999 Informs of Decision to Inspect H-3 & H-4 Shroud Welds During Upcoming 3R12 Outage Scheduled to Begin Late Sept 1999 ML20212H6401999-09-24024 September 1999 Forwards Revised Epips,Including Rev 11 to ERP-101 & Rev 18 to ERP-800.Copy of Computer Generated Rept Index Identifying Latest Revs of LGS Erps,Encl ML20216F8811999-09-23023 September 1999 Withdraws 990806 Exigent License Change Application.Tech Spec Change to Allow Continued Power Operation with Elevated Cooling Water Temps During Potentially Extreme Weather Conditions No Longer Needed Due to Favorable Weather ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML20212E7941999-09-22022 September 1999 Requests Authorization for Listed Licensed Operators to Temporarily Suspend Participation in Licensed Operator Requalification Program at LGS ML20212E8081999-09-22022 September 1999 Provides Notification That Listed Operators Have Been Permanently Reassigned to Duties That Do Not Require Maintaining Licensed Operator Status,Per 10CFR50.74 ML20212F5481999-09-20020 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing, for Pbaps,Units 2 & 3 & Lgs,Units 1 & 2 ML20212F8991999-09-17017 September 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at Lgs,Units 1 & 2 Have Been Completed 05000353/LER-1999-010, Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl1999-09-16016 September 1999 Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML18107A5321999-09-13013 September 1999 Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources. ML18107A5331999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 ML18107A5351999-09-13013 September 1999 Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments ML20212A0091999-09-0909 September 1999 Provides Notification That Licenses SOP-11172 & SOP-11321, for SO Muntzenberger & Rh Wright,Respectively,Are No Longer Necessary as Result of Permanent Reassignment ML18107A5231999-09-0808 September 1999 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999 ML18107A5221999-09-0808 September 1999 Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations 05000352/LER-1999-009, Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed1999-09-0101 September 1999 Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed ML20211K7031999-08-30030 August 1999 Forwards Response to NRC 990826 RAI Re License Change Application ECR 99-01255,revising TSs 2.1.1.2 & 5.6.5 ML18107A5181999-08-26026 August 1999 Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided ML18107A5061999-08-26026 August 1999 Provides First Feedback from Observation of NRC Insp Under Pilot Nuclear Power Plant Insp Program.Attached Are Completed Insp Feedback Forms for Procedure 71111, Attachment 21 & Procedure 71151 ML18107A4981999-08-26026 August 1999 Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues ML20211E9191999-08-24024 August 1999 Forwards fitness-for-duty Program Performance Data for Jan-June 1999 for PBAPS & LGS IAW 10CFR26.71(d).Data Includes Listed Info ML18107A5051999-08-24024 August 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves ML18107A4921999-08-23023 August 1999 Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02 ML20211E9731999-08-23023 August 1999 Forwards LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5, Per TS SRs 4.0.5 & 10CFR50.55a(g) ML20211D6761999-08-20020 August 1999 Forwards non-proprietary Revised Emergency Response Procedures (Erps),Including Rev 29 to ERP-110, Emergency Notification & Rev 17 to ERP-800, Maint Team & Proprietary App ERP-110-1.App Withheld Per 10CFR2.790(a)(6) ML18107A4911999-08-20020 August 1999 Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars ML18107A4831999-08-18018 August 1999 Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1 ML18107A4801999-08-13013 August 1999 Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed ML20210P8151999-08-11011 August 1999 Forwards Final Pages for Pbaps,Unit 2 & 3 OLs Re License Change Application ECR 99-01497,which Reflects Change in Corporate Structure at Pse&G ML20210P8321999-08-11011 August 1999 Responds to NRC 990715 Telcon Re Util 990217 Submittal of Proposed Alternatives to Requirements of 10CFR50.55a(g)(6)(ii)(B)(1) Re Containment Inservice Insp Program ML20211B6521999-08-10010 August 1999 Informs That Dp Lewis,License SOP-11247,has Been Permanently Reassigned & No Longer Requires License,Per 10CFR50.74.Util Requests That Subject Individual Be Removed from List of License Holders 05000353/LER-1999-005, Forwards LER 99-005-00,re Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Esf.Fuse Failed Due to Mechanical Failure of Cold Solder Joint1999-08-10010 August 1999 Forwards LER 99-005-00,re Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Esf.Fuse Failed Due to Mechanical Failure of Cold Solder Joint ML18107A4751999-08-0505 August 1999 Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630 1999-09-09
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PECO NUCLEAR- ecco e"e'av comae"v 965 Chesterbrook Boulevard A Unit of PECO Energy wayne. PA 90er.sc91 August 4,1999 Docket Nos. 50-352 50-353 50-171 50-277 50-278 50-272 50-311 License Nos. NPF-39 NPF-85 DPR-12 DPR-44 DPR-56 DPR-70 DPR 75 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Subject:
LimerirA Generating Station, Units 1 and 2 Peach Bottom Atomic Power Station, Units 1,2 and 3 Salem Generating Station, Units 1 and 2 Response to Request for Additional Information Regarding Status of Decommissioning Funding
Reference:
Letter from Bartholomew C. Buckley, USNRC, to Garrett D. Edwards, PECO Energy Company (PECO Energy) dated July 1,1999
Dear Sir / Madam:
The reference letter requested additional information regarding the status of decommissioning funding for Limerick Generating Station, Units 1 and 2, Peach Bottom Atomic Power Station, Units 1,2, end 3, and Salem Nuclear Generating Station, Units 1 and 2. Attachment 1 provides a restatement of the questions followed by our response. If you have any questions, please do not hesitate to contact us.
Very truly yours, mes A. Hutton, Jr.
irector- Licensing i Enclosure cc H. J. Miller, Administrator, Region I, USNRC ,oh A. L. Burritt, USNRC Senior Resident inspector, LGS A. C. McMurtray, USNRC Senior Resident inspector, PBAPS S. A. Morris, USNRC Senior Resident Inspector, SGS 9968500169 990804 PDR ADOCK 05000171 P PDR 1.
Ib .
i ATTACHMENTI Limerick Generating Station, Units 1 and 2 Peach Bottom Atomic Power Station, Units 1,2 and 3 i
Salem Generating Station, Units 1 and 2 Docket Nos. 50-352 4 1
50-353 50-171 50-277 50-278 50-272 50-311 License Nos. NPF-39 NPF-85 DPR-12 DPR-44 DPR-56 DPR-70 DPR-75 i
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Response to Request for Additional Information Limerick Generating Station, Units 1 and 2 Peach Bottom Atomic Power Station, Units 1,2 and 3 Salem Generating Station, Units 1 and 2
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j Decommissioning Funding i l
Question 1' As stipulated in 10 CFR 57.75 (e)(1)(ii), the regulations allow an annual Rate of Retum (interest samed) of 2 percent. Please explain why a 4 percent annual Rate of Retum was assumed in the Decommissioning Cost Estimate Calculations in your March 31,1999, submittal and confirm that this rate was approved by the State Public Utility Commission.
Response 1 in our recently settled restructuring case before the Pennsylvania Public Utility Commission (Pa PUC), the basis for the agreed upon decommissioning amount was an inflation factor of 3.5% and an eamings rate on our investments of 7.5%, assuming favorable tax treatment by the intamal Revenue Service The net of these two assumptions yield a real annual rate of retum of 4%.
Additionally, our actual experience for the last two years has been as follows:
1997 - Eamings Rate = 12.3% Inflation Rate = 2.1% Real Rate of Retum = 10.2% ,
1998 - Eamings Rate = 11.9% Inflation Rate = 2.3% Real Rate of Retum = 9.6% l l
Given the above information, we felt it was reasonable to assume a 4% Real Annual Rate of ;
Retum.
t Question 2 Please explain the shortfall between the " Average Calculated Deposit Per Year" and the
" Current projected annual deposit"in pages 2 and 3 of Exhibit 2 of your submittal.
Response 2 Based on the 1998 funding allowances, combined with a 4% real rate of retum, both Limerick Generating Station, Unit 2, and Peach Bottom Atomic Power Station, Unit 1, show annual shortfalls. However, use of the current funding effective January 1,1999, results in all the units (with the exception of Peach Bottom Atomic Power Station, Unit 2) having a " Current '
Projected Annual Deposit"in excess of the " Average Calculated Deposit Per Year" on a recalculated basis. A revised Exhibit 2 is attached to highlight this information.
In the case of Peach Bottom Atomic Power Station, Unit 2, the shortfall is less than $42,000 per year. In this regard, the Pa PUC order approving the collection of decommissioning funds gives us the right to seek additional funds for decommissioning if assumptions used in
. establishing required decommissioning amounts change.
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EXHIBIT 2 Decommissioning Cost Estimate Calculations Schedule of Payments Limerick Generating Station, Units 1 and 2 Peach Bottom Atomic Power Station, Units 1,2, and 3 Salem Generating Station, Units 1 and 2
Limerick Generating Station, Unit 1 Revised 1999 Fundina NRC Minimum Amount 367,949,698 ,
Balance in Trust- December 31,1998 92,504,353 Remainder to be funded 275,445,345 Remaining years for collection of Decommissioning Costs 1999-2024 26 Average Calculated Deposit per Year 10,594,052 Current Sources of Funding:
Annual Funding 5,822,000 4,403,000 Effective annual retum of 6.8% on balance in Trust") 6,290,296 Current projected annual deposit 12,112,296 10,693,296 I
- 0) Based on a projected real Rate of Retum of 4% per year
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Limerick Generating Station, Unit 2 l
Revised 1999 Fundina NRC Minimum Amount 367,949,698 Balance in Trust - December 31,1998 54,819,839 Remainderto be funded 313,129,859 Remaining years for collection of -
Decommissioning Costs 1999-2029 31 AveraQe Calculated Deposit per Year 10,100,963 Current Sources of Funding:
Annual Funding 4,763,000 8,043,000 Effective annual retum of 7.7% on balance in TrustW 4,221,128 Current projected annual deposit 8,984,128 12,264.128 I
N Based on a projected real Rate of Retum of 4% per year I
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Peach Bottom Atomic Power Station, Unit 1 Revised 1999 Fundina NRC Minimum Amount 48,852,963 Balance in Trust - December 31,1998 11,392,599 Remainder to be funded 37,460,364 Remaining years for collection of Decommissioning Costs 1999-2013 15 Average Calculated Deposit per Year 2,497,358 Current Sources of Funding:
Annual Funding 740,000 2,992,000 Effective annual retum of 5.3% on balance in Trust (" 603,808 Current projected annual deposit 1,343,808 3,595,808 l (U Based on a projected real Rate of Retum of 4% per year i
Peach Bottom Atomic Power Station, Unit 2 Revised 1999 Fundina NRC Minimum Amount 156,341,827 2 Balance in Trust - December 31,1998 65,121,824 Remainder to be funded 91,220,003 Remaining years for collection of Decommissioning Costs 1999-2013 15 Average Calculated Deposit per Year 6,081,334 Current Sources of Funding:
Annual Funding 2,775,000 2,588,000 Effective annual retum of 5.3% on balance in Trust") 3,451,457 Current projected annual deposit 6,226,457 6,039,457
") Based on a projected Real Retum of 4% per year
- Reflects funds available to decommission Peach Bottom Unit 2 and 50% of Common Plant. PECO share of decommissioning costs - 42.49% ownership
Peach Bottom Atomic Power Station, Unit 3 Revised 1999 Fundina ,
1 NRC Minimum Amount 156,341,827 A i l
Balance in Trust - December 31,1998 65,345,228 l j Remainder to be funded 90,996,599 l
Remaining years for collection of l Decommissioning Costs 1999-2013 15 !
Average Calculated Deposit per Year 6,066,440 Current Sources of Funding:
Annual Funding 2,775,000 5,976,000 Effective annual retum of 5.3% on balance in Trust") 3,463,297 l
Current projected annual deposit 6,238,297 9,439,297 l
U) Based on a projected real Rate of Retum of 4% per year A Reflects funds available to decommission Peach Bottom Unit 3 and 50% of Common Piant. PECO
, share of decommissioning costs 42.49% ownership
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Salem Generating Station, Unit 1 Revised l 1999 Fundina l NRC Minimum Amount 124,040,287m Balance in Trust - December 31,1998 49,147,619 Remainder to be funded 74,892,668 Remaining years for collection of Decommissioning Costs 1999-2010 18 Average Calculated Deposit per Year 4,160,704 Current Sources of Funding:
Annual Funding 1,962,000 2,651,000 Effective annual retum of 5.7% on balance in TrustW 2,801,414 Current projected annual deposit 4,763,414 5,452,414 l N Based on a projected real Rate of Retum of 4% per year A Reflects funds available to decommission Salem Unit 1 and 50% of Common Plant.
PECO share of decommissioning costs - 42.59% ownership.
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Salem Generating Station, Unit 2 Revised 1999 Fundino NRC Minimum Amount 124,040,287*
Balance in Trust - December 31,1998 41,613,435 Remainder to be funded 82,426,852 Remaining years for collection of Decommissioning Costs 1999-2020 22 Average Calculated Deposit per Year 3,746,675 Current Sources of Funding:
Annual Funding 1,851,000 2,509.000 Effective annual retum of 6.2% on balance in Trust") 2,580,033 Current projected annual deposit 4,431,033 5,089,033 "I
Based on a projected Real Retum of 4% per year
- Reflects funds available to decommission Salem Unit 1 and 50% of Common Plant.
PECO share of decommissioning costs - 42.59% ownership.
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