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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M6631999-10-19019 October 1999 Forwards Insp Rept 50-277/99-07 & 50-278/99-07 on 990920.No Violations Noted 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 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 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 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 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 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 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 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 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 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 ML20212A8751999-09-13013 September 1999 Forwards Safety Evaluation of First & Second 10-year Interval Inservice Insp Plan Request for Relief 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 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 ML20211P8571999-09-0808 September 1999 Forwards Reactor Operator Retake Exams 50-352/99-303OL & 50-353/99-303OL Conducted on 990812 ML20211P2961999-09-0707 September 1999 Provides Authorization to Administer NRC Approved Initial Written Exams to Listed Applicants on 990913 at Peach Bottom Npp,Delta,Pennsylvania ML20211P3891999-09-0303 September 1999 Informs That During 990902 Telcon Between J Williams & B Tracy,Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant.Insp Planned for Wk of 991018 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 ML20211E6941999-08-26026 August 1999 Forwards Request for Addl Info Re Min Critical Power Ratio. Response Should Be Submitted within 30 Days of Ltr Receipt ML20211H2571999-08-26026 August 1999 Informs of Individual Exam Result on Initial Retake Exam on 990812.One Individual Was Administered Exam & Passed ML20211Q4491999-08-25025 August 1999 Responds to Re Changes to PBAPS Physical Security Plan,Safeguards Contingency Plan & Guard Training & Qualification Plan Identified as Revs 13,11 & 9, Respectively.No NRC Approval Is Required,Per 10CFR50.54(p) 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 ML20211D5421999-08-23023 August 1999 Forwards Amends 228 & 231 to Licenses DPR-44 & DPR-56, Respectively & Se.Amends Revise TSs to Correct Typographical & Editorial Errors Introduced in TSs by Previous Amends 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) ML20211A9721999-08-20020 August 1999 Forwards Request for Addl Info Re Third 10-year Interval Inservice (ISI) Insp Program Plan for Plant,Units 2 & 3 ML20210T4271999-08-13013 August 1999 Informs That NRC Revised Info in Rvid & Releasing Rvid Version 2 as Result of Review of 980830 Responses to GL 92-01 Rev 1,GL 92-01 Rev 1 Suppl 1 & Suppl Rai.Tacs MA1197 & MA1198 Closed 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062G4531990-11-20020 November 1990 Forwards SE Supporting Util Actions to Address Indication in Reactor Vessel Recirculation Riser nozzle-to-safe End Weld ML20062G4021990-11-19019 November 1990 Forwards Safety Insp Repts 50-352/90-21 & 50-353/90-20 on 900827-31.No Violations Noted ML20062F1771990-11-13013 November 1990 Confirms Dates of 901126-30 for NRC Equipment Qualification Insp of Facility ML20062F2241990-11-0909 November 1990 Forwards SSFI Repts 50-277/90-80 & 50-278/90-80 on 900917- 1003 Conducted by Corrective Action Review Team.Corrective Actions Generally Acceptable W/Some Weaknesses Noted IR 05000277/19900191990-11-0707 November 1990 Forwards Exam Repts 50-277/90-19OL & 50-278/90-19OL Administered During Wk of 900924 ML20062D5381990-11-0606 November 1990 Forwards List of Unimplemented Generic Safety Issues at Facilities,Per Generic Ltr 90-04 ML20058F1981990-11-0505 November 1990 Advises That 901002 Response to Generic Ltr (GL) 90-03, Relaxation of Staff Position in GL 83-28,Item 2.2 Part 2, 'Vendor Interface for Safety-Related Components,' Acceptable ML20058G1541990-10-31031 October 1990 Requests That Util Furnish Ref Matl Listed in Encl 1, Ref Matl Requirements, for Administration of Licensing Exams & Evaluation of Requalification Program Scheduled for Wk of 910304 ML20058E6121990-10-29029 October 1990 Forwards Radiological Safety Insp Repts 50-352/90-24 & 50-353/90-23 on 901001-05.No Violations Noted ML20058D2371990-10-26026 October 1990 Informs of Impending fitness-for-duty Program Insp & Requests 10CFR26.20 Required Policies & Procedures ML20062C7451990-10-26026 October 1990 Forwards Safety Evaluation Accepting Response to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow ML20058C1331990-10-23023 October 1990 Advises That Reactor Operator & Senior Reactor Operator Licensing Exams Scheduled for Wk of 910121 & Requalification Program Evaluation Scheduled for Wks of 910114 & 21.Ref Matl Listed on Encl Should Be Provided by 901029 ML20058A6241990-10-18018 October 1990 Forwards Insp Repts 50-352/90-22 &50-353/90-21 on 900912-19. No Violations Noted ML20062B7891990-10-12012 October 1990 Forwards Safety Insp Repts 50-352/90-20 & 50-353/90-19 on 900813-0916.No Violations Noted ML20062B8211990-10-11011 October 1990 Forwards Final SALP Repts 50-277/89-99 & 50-278/89-99 for Jul 1989 to May 1990.Improvements Noted ML20062A0651990-10-0505 October 1990 Forwards Safety Insp Repts 50-277/90-17 & 50-278/90-17 on 900814-0924.One Violation Noted ML20059N5841990-10-0303 October 1990 Informs That Issuance of Senior Reactor Operator Licenses, for Fuel Handling Only,For More than One Facility Conditionally Acceptable IR 05000352/19900801990-09-28028 September 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/90-80 & 50-353/90-80.Requests Status of Planned Revs to Procedures & Expected Completion Dates in 910130 Response ML20059M6561990-09-22022 September 1990 Ack Receipt of Util Re Corrective Actions Taken in Response to Insp Repts 50-277/90-13 & 50-278/90-13 ML20059J1971990-09-13013 September 1990 Ack Receipt of & Payment for Civil Penalty Proposed by NRC in in Amount of $75,000 ML20059H0701990-09-11011 September 1990 Requests Addl Info Re Audit Rept Distribution,Per 890711 & 900420 Application Request for Removal of Organization Charts from Tech Spec Per Guidance Provided in Generic Ltr 88-06 & Miscellaneous Administrative Changes ML20059K7211990-09-0606 September 1990 Forwards Safety Insp Repts 50-277/90-15 & 50-278/90-15 on 900723-27 & Notice of Violation ML20059F6561990-08-29029 August 1990 Forwards Notice of Withdrawal of 900516 Application for Amend to License NPF-39,revising Tech Specs to Allow one- Time Extension of Visual Insp Period for Three Small Inaccessible Snubbers in Drywell ML20056B2691990-08-23023 August 1990 Forwards Request for Addl Info Re 880126 Application for Amends to Licenses,Revising Tech Specs to Provide More Restrictive Limits on Emergency Svc Water Sys.Response Should Be Provided within 60 Days of Ltr Receipt ML20059A6581990-08-16016 August 1990 Requests Discussion of Measures Considered &/Or Taken to Reduce Amount of Time Needed to Obtain Effluent Sample Analyses Results,Per 870121 Application for License Amends to Licenses DPR-44 & DPR-56 ML20058N0531990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Encourages Initiation of Initiative Similar to Region V Licensees Establishment of Engineering Managers Forum ML20058M5981990-08-0303 August 1990 Forwards Safety Insp Repts 50-352/90-17 & 50-353/90-16 on 900522-0701 & Notice of Violation.Inspectors Continued to Note Problems W/Procedure Compliance & in Technical Adequacy & Implementation of Procedures ML20058M3311990-08-0303 August 1990 Forwards Radiological Safety Insp Repts 50-352/90-19 & 50-353/90-18 on 900709-13.No Violations Noted.Weakness Observed in Maint of Station Health Physics Procedures ML20056A5011990-07-30030 July 1990 Forwards Safety Insp Repts 50-277/90-13 & 50-278/90-13 on 900516-0702 & Notice of Violation ML20055E8641990-07-10010 July 1990 Comments on Util 891228 Response to Generic Ltr (GL) 89-10, Safety-Related Motor-Operated Valve (MOV) Testing & Surveillance. Requests Proposed Schedule for Completion of GL Program Along W/Justification for Alternative Schedule ML20055E1711990-07-0606 July 1990 Requests That Licensee Provide Data on Channel Box Bow Vs Exposure Associated W/Methods Used to Account for Effects of Channel Box Bow During Second Bundle Lifetime Channel Boxes, Per 900425 Response to Bulletin 90-002,within 30 Days ML20055E9611990-07-0505 July 1990 Requests Addl Info Re Util 891228 Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance ML20055F5591990-07-0303 July 1990 Forwards Safety Insp Repts 50-352/90-80 & 50-353/90-80 on 900521-25.Plant Transient Response Implementing Plan (Trip) Technically Acceptable.Unresolved Items Noted.Impact of Insp Findings on Peach Bottom Trip Procedures Should Be Reviewed ML20055D0721990-06-27027 June 1990 Advises That Reactor Operator & Senior Reactor Operator Licensing Exams Scheduled for Wks of 900924 & 1001.Ref Matls,Listed on Encl,Should Be Provided by 900724 ML20055C8761990-06-15015 June 1990 Forwards Safety Insp Repts 50-277/90-10 & 50-278/90-10 on 900403-0515.No Violations Noted.Increased Mgt Attention Warranted to Ensure That Instances of Failure to Complete Surveillance Testing Identified & Corrected ML20059M8671990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20058K1961990-05-31031 May 1990 Forwards Results & Conclusions of Regulatory Effectiveness Review on 900507-11.Encl Withheld (Ref 10CFR73.21) ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) ML20055C3091990-02-14014 February 1990 Forwards Safety Insp Repts 50-352/90-03 & 50-353/90-03 on 900116-19.No Violations Noted ML20248H8041989-10-0505 October 1989 Grants Termination of Requirements Set Forth in Section VA of Order to Permit Operation of Both Units at Full Power ML20248H1361989-10-0303 October 1989 Forwards Unexecuted Amend 22 to Indemnity Agreement B-28, Reflecting Changes to 10CFR140 Re Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu ML20248G2291989-09-29029 September 1989 Forwards Safety Insp Repts 50-277/89-21 & 50-278/89-21 on 890901.No Violations Noted.Insp Concluded That Improvements in Radiological Controls Program Have Been Slow.Addl Mgt Attention to Program Warranted ML20248G6601989-09-27027 September 1989 Forwards Operational Readiness Insp Rept 50-353/89-81 on 890730-0804 & Notice of Violation ML20248E2351989-09-27027 September 1989 Forwards Summary of Issues Re Verification of Quality of Certain Types of Activities Performed for Mods at Facility. Mods Cover Automatic Depressurization Sys/Msiv Instrument Nitrogen Accumulator & Svc Water Pipe Replacement ML20248E7421989-09-27027 September 1989 Forwards Exam Repts 50-352/89-13OL & 50-353/89-22OL Administered on 890612-16 & 19.NRC Concerned About Effectiveness of Util Candidate Screening & Evaluation Process That Permitted Marginal Individual for NRC Exam ML20248A4111989-09-25025 September 1989 Forwards Restart Team Safety Insp Repts 50-277/89-20 & 50-278/89-20 on 890730-0902.No Violations Noted 1990-09-06
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M6631999-10-19019 October 1999 Forwards Insp Rept 50-277/99-07 & 50-278/99-07 on 990920.No Violations Noted ML20217F7391999-10-14014 October 1999 Requests Addl Info Re Peach Bottom Atomic Power Station Units 2 & 3 Appendix R Exemption Requests 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 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 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 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 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 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 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 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 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 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 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 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 ML20212A8751999-09-13013 September 1999 Forwards Safety Evaluation of First & Second 10-year Interval Inservice Insp Plan Request for Relief 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 ML20211P8571999-09-0808 September 1999 Forwards Reactor Operator Retake Exams 50-352/99-303OL & 50-353/99-303OL Conducted on 990812 ML20211P2961999-09-0707 September 1999 Provides Authorization to Administer NRC Approved Initial Written Exams to Listed Applicants on 990913 at Peach Bottom Npp,Delta,Pennsylvania ML20211P3891999-09-0303 September 1999 Informs That During 990902 Telcon Between J Williams & B Tracy,Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant.Insp Planned for Wk of 991018 ML20211E6941999-08-26026 August 1999 Forwards Request for Addl Info Re Min Critical Power Ratio. Response Should Be Submitted within 30 Days of Ltr Receipt ML20211H2571999-08-26026 August 1999 Informs of Individual Exam Result on Initial Retake Exam on 990812.One Individual Was Administered Exam & Passed ML20211Q4491999-08-25025 August 1999 Responds to Re Changes to PBAPS Physical Security Plan,Safeguards Contingency Plan & Guard Training & Qualification Plan Identified as Revs 13,11 & 9, Respectively.No NRC Approval Is Required,Per 10CFR50.54(p) ML20211D5421999-08-23023 August 1999 Forwards Amends 228 & 231 to Licenses DPR-44 & DPR-56, Respectively & Se.Amends Revise TSs to Correct Typographical & Editorial Errors Introduced in TSs by Previous Amends ML20211A9721999-08-20020 August 1999 Forwards Request for Addl Info Re Third 10-year Interval Inservice (ISI) Insp Program Plan for Plant,Units 2 & 3 ML20210T4271999-08-13013 August 1999 Informs That NRC Revised Info in Rvid & Releasing Rvid Version 2 as Result of Review of 980830 Responses to GL 92-01 Rev 1,GL 92-01 Rev 1 Suppl 1 & Suppl Rai.Tacs MA1197 & MA1198 Closed ML20210T5451999-08-12012 August 1999 Forwards Copy of Environ Assessment & Findings of No Significant Impact Re Licensee Request for Amends to Plant. Amends Consist of Changes to TS to Correct Typos & Editorial Errors Introduced in TS by Previous Amends ML20210P1561999-08-10010 August 1999 Submits Response to Requests for Addl Info Re GL 92-01,rev 1,Suppl 1, Rv Structural Integrity, for Pbap,Units 1 & 2. NRC Will Assume That Data Entered Into Rvid Are Acceptable for Plants,If Staff Does Not Receive Comments by 990901 ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210U2211999-08-10010 August 1999 Forwards Insp Repts 50-352/99-04 & 50-353/99-04 on 990525-0712.One Violation Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy.Violation Re Late Performance of off-gas Grab Sample Surveillance ML20210N7831999-08-0909 August 1999 Forwards Copy of Notice of Consideration of Issuance of Amends to Fols,Proposed NSHC Determination & Opportunity for Hearing, Re 990806 Request for License Amends.Amends Incorporate Note Into PBAPS TS to Permit One Time Exemption ML20210P0801999-08-0404 August 1999 Forwards Initial Exam Repts 50-277/99-301 & 50-278/99-301 on 990702-14 (Administration) & 990715-22 (Grading).Six of Limited SRO Applicants Passed All Portion of Exam ML20210P4191999-08-0404 August 1999 Forwards Initial Exam Repts 50-352/99-302 & 50-353/99-302 on 990702-04 (Administration) & 990715-22 (Grading).Six of Limited SRO Applicants Passed All Portion of Exam NUREG-1092, Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls1999-08-0303 August 1999 Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls ML20210J0161999-07-30030 July 1999 Forwards Copy of Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amends Re 990723 Application ML20210H5341999-07-27027 July 1999 Forwards Insp Repts 50-277/99-05 & 50-278/99-05 on 990518- 0628.NRC Determined That Two Severity Level IV Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20209F2461999-07-15015 July 1999 Request Addl Info Re Relief Request CRR-01 Through CRR-11 for Plant,Units 2 & 3.RAI Undtd ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 ML20212J5401999-06-28028 June 1999 Discusses Completion of Licensing Action for NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs. Bulletin Closed for Unit 2 by NRC ML20196G7041999-06-24024 June 1999 Forwards Insp Repts 50-352/99-03 & 50-353/99-03 on 990413- 0524.No Violations Noted.Nrc Concluded That Licensee Staff Continued to Operate Both Units Safely ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195K2251999-06-11011 June 1999 Forwards Insp Repts 50-277/99-04 & 50-278/99-04 on 990405- 0517.One Severity Level IV Violation of NRC Requirements Identified & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20207G2051999-06-0707 June 1999 Informs of Reorganization in NRR Ofc,Effective 990328. Reorganization Chart Encl ML20207B8381999-05-24024 May 1999 Forwards FEMA Final Exercise Rept for Peach Bottom Atomic Power Station Plume Exposure Pathway Exercise Conducted on 981117.One Deficiency & 27 Areas Requiring Corrective Actions Identified ML20207A0541999-05-17017 May 1999 Acks 990512 & 14 Telcons with Licensee Re Util Request That Rev 8 of NUREG-1021, OL Exam Stds for Power Reactors Be Followed Rather than Interim Rev 8 for Exams in Sept 1999. Request Acceptable ML20206Q5871999-05-14014 May 1999 Advises That Info Contained in ,Which Submitted Revised Procedures for Plant EP Response Procedures Will Be Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20206R3031999-05-11011 May 1999 Informs That on 990407,NRC Administered GFE Section of Written Operator Licensing Exam to Employees of Facility. Forwards Copies of Both Forms of Exam,Including Answer Keys & Grading Results of Facility ML20206N1111999-05-0707 May 1999 Forwards Insp Repts 50-352/99-02 & 50-353/99-02 on 990302-0412.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20206H2651999-05-0606 May 1999 Informs That on 990112 Licensee Submitted to NRC Core Shroud Insp Plan for Plant,Unit 2,in Response to GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors ML20206K2231999-05-0606 May 1999 Informs That Author Authorized to Exercise Discretion & Not Issue NOV or Civil Penalty Re Violation Util Identified Involving Unit 2 Rod Block Monitoring Sys Being Inoperable for 29 of 185 Control Rods 1999-09-09
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September 23, 1988 Docket Nos. 50-277/278 50-352/353 Mr. William Alden Director-Licensing Philadelphia Electric Con'pany Correspondence Control Desk P.O. Box 7520 Philadelphia, Pennsylvania 19101
Dear Mr. Alden:
SUBJECT:
NRC LETTER ACKNOWLEDGING RECEIPT OF 2.206 PETITION REGARDING BWR STABILITY RE: PEACH BOTTOM ATOMIC POWER STATION, UNITS 283 LIMERICK GENERATING STATION, UNITS 1&2 Enclosed for your information is a copy of a letter dated August 26, 1988 from the Director Office of Nuclear Reactor Regulation to the Representative of the Ohio citizens for Responsible Energy (OCRE). The letter (1) acknowledges receipt of a Petition filed by OCRE under 10 CFR 2.206 of the Comission's regulations, (2) responds in the negative to the Petitioner's request for irrmediate action with respect to all Boiling Water Reactors (BWRs), and (3) states that the Petition is being treated under 10 CFR 2.206 of the Conmission's regulations.
Please contact me if you have questions on this isst '
Sincerely,
/S/
Robert E. Martin, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Original signed by l h!R O $ 77 Ric rd J. C1 rk, Project Manager P PNU Project Directorate 1-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosure:
- As stated cc: Service List i
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- September 23, 1988 t, * . . . . #
Docket Nos. 50-277/278 50-352/353 Mr. William Alden Director-Licensing Philadelphia Electric Cerrpany Correspondence Control Desk P.O. Box 7520 Philadelphia, Pennsylvania 19101
Dear Mr. Alden:
SUBJECT:
NRC LETTER ACKNOWLEDGING RECEIPT OF ?.206 PETITION REGARDING BWR STABILITY
, RE: PEACH BOTTOM ATCMIC POWER STATION, UNITS 2&3 LIMERICK GENERATING STATION, UNITS 182 Enclosed for your information is a copy of a letter dated August 26, 1988 from i the Director, Office of Nuclear Raactor Reculation to the Representative of the Ohio citizens for Responsible Energy {0CRE). The letter (1) acknowledges receipt of a Petition filed by OCRE under 10 CFR ?.206 of the Comission's regulations. (2) responds in tne negative to the Petitioner's reauest for irrnediate action with respect to all Boiling Water Reactors (BWRs), and (3) states that the Petition is being treated under 10 CFR 2.206 of the Comission's regulations.
Please contact me if you have questions on this issue.
Sincerely.
i %.
QRobet//
Project Directorate I-2
. M rti , Project Manager Division of Reactor Projects I/II Office of Nucl ar Reactor Regulation
~
Clark, Project Manager roject D rectorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosure:
As stated cc: Service List
Nr. William M. Alden Limerick Generating Station Philadelphia Electric Company Units 1 & 2 cc:
Troy B. Conner, Jr., Esquire Mr. Robert Gramm Conner and Wetterhahn Senior Resident Inspector 1747 Pennsylvania Ave., N.W. U.S. Nuclear Regulatory Commission Washington, D. C. 20006 P. O. Box 596 Pottstown, Pennsylvania 19464 Mr. Charles Menger: 57-1 Philadelphia Electric Company Mr. Ted Ullrich 2301 Market Street Manager - Unit 2 Startup Philadelpi.ia, Pennsylvania 19101 Limerick Generating Station P. O. Box A Mr. David Honan N2-1 Sanatoga, Pennsylvania 19464 Philadelphia Electric Company 2301 Market Street Mr. John Doering Philadelphia, Pennsylvania 19101 Superintendent-0perations Limerick Generating Station Mr. Grahm M. Leitch, Vice President P. O. Box A Limerick Generating Station Sanatoga, Pennsylvania 19464 Post Office Box A Sanatoga, Pennsylvania 19464 Thomas Gerusky, Directnr Bureau of Radiation Protection PA Dept. of Environmental Resources Mr. James Linville F. O. Box 2063 U.S. Nuclear Regulatory Commission Harrisburg, Pennsylvania 17120 Region I 475 Allendale Road Governor's Office of State King of Prussia, PA 19406 Planning and Development '
ATTN: Coordinator, Pennsylvania Mr. Thomas Kenny State Clearinghouse Senior Resident Inspector P. O. Box 1323 US Nuclear Regulatory Commission Harrisburg, Pennsylvania 17102 P. O. Box 596 Pottstown, Pennsylvania 19464 Mr. Philip J. Duca Superintendent-Technical Mr. Joseph W. Gallagher Limerick Generating Station !
Vice President Nuclear Services P. O. Box A Philadelphia Electric Company Sanatoga, Pennsylvania 19464 2301 Market Street Philadelphia, Pennsylvania 19101 Mr. John S. Kemper Senior Vice President-Nuclear Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101 i
.Mr. William M. Alden Peach Bottom Atomic Power Station, Philadelphia Electric Company Units 2 and 3 cc:
Troy B. Conner, Jr. , Esq. Mr. R. A. Heiss, Coordinator 1747 Pennsylvania Avenue, N.W. Pennsylvania State Clearinghouse Washington, D.C. 20006 Governor's Office of State Planning and Development Philadelphia Electric Company P. O. Box 1323 ATTN: Mr. D. M. Smith, Vice President Harrisburg, Pennsylvania 17120 Peach Bottom Atomic Power Station Route 1 P* 208 Mr. Thomas 'i. Gerusky, Director Delta , Pe- vivania 17314 Bureau of Radiation Protection Pennsylvania Department of H. Chris Schwem Environmental Resources Vice President, Production P. O. Box 2063 Atlantic Electric Harrisburg, Ponnsylvania 17120 P.O. Box 1500 1199 Black Horse Pike Mr. Albert R. Steel, Chairman Pleasantville, New Jersey 08232 Board of Supervisors Psach Bottom Township Resident Inspector R. D. #1 U.S. Nuclear Regulatory Comission Delta, Pennsylvania 17314 Peach Botten Atomic Power Statien P.O. Box 399 Pr. Gary Mock Delta, Pennsylvania 17314 P. O. Box 09181 Columbus, Ohio 43209 Regional Administrator, Region i U.S. Nuclear Regulatory Comission Delmarv6 rower and Light Company 475 Allendale Road cio Jack Urban King of Prussia, Pennsylvania 19406 General Haneger, Fuel Supply 800 King Street Mr. Bryan W. Gorman P.O. Box 231 Manager - External Affairs Wilmington, DE 19999 Public Service Electric & Gas Company P.O. Box 236, N?8 Mr. Tom Magette Hancocks Bridge, New Jersey 08038 Power Plant Research Program Department of Natural Resources B-3 Tawes State Office Building Annapolis, Maryland 21401 Mr. Roland Fletcher Department of Environment 201 West Preston Street Baltimore, Maryland 21201
- / UNITED STATES
[ c n NUCLEAR REGULATORY COMMlf.3lON
$ e WASHING TON, D. C. 20044
o .! August 26, 1988 Ms. Susan L. Hiatt Representative of Ohio Citizens for Responsible Energy, Inc.
8275 Hunson Road Mentor, OH 44060
Dear Ms. Hiatt:
This is in response to your Petition of July 22, 1988, requesting that the Director, Office of Nuclear Reactor Regulation (Director), take imediate action with respect to Boiling Water Reactors (BWRs) to relieve what you allege to be undue risks to the public health and safety posed by the thermal-hydraulic instability of boiling water reactors, as revealed by an event at LaSalle County Station Unit 2 on March 9,1988.
The specific relief requested is to order all BWR licensees to (1) place their reactors in cold shutdown, (2) develop and implement specified procedures relating to the thermal-hydraulic instability issues, (3) demonstrate that certain specified training has been provided relating to these procedures, (4) demonstrate the capability of instrumentation related to power oscil-lations, (5) develop simulators capable of modeling power oscillations similar ,
to those occurring at LaSalle and out-of-phase power oscillations, (6) report to the NRC regarding all past incidents in which recirculation pumps have tripped off (7) submit to the NRC justification for continued operation of BWRs and (8) submit a report to the NRC within one year demonstrating compliancewithGDC12. You also request that the Comissich reopen Generic Issues B-19, B-59, the ATWS rulemaking and reconsider the use of End-of-Cycle Recirculation Pump Trip on CWRs.
Your request for inrediate relief is denied because the allegations which form the basis for your Petition do not reveal any new operational safety issues r which pose an imediate safety concern for continued BWR operation. The staff has determined that continued operation of BWR3 is justified for the following reasons:
(1) Current BWR Technical Specifications place restrictions on power i operation of the retetor under conditions of natural circulation or ,
j single recirculation loop cooling such that operation in regions of low thermal-hydraulic stability is limited to infrequent, short-term transient conoitions following anticipated operational occurrences.
(2) Neutron flux oscillations are detectable with proper monitoring and can be easily suppress *d by inserting control rods. If large oscillations should occur, and a manual scram is not initiated, it is expected that the high power level Average Power Range Monitor (APRM) scram protection, which terminated the LaSalle event, would provide backup protection as was the case during the LaSalle event. g f
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Susan L. Hiatt (3) The magnitude of neutron flux oscillations induced by thermal-hydraulic instability is considerably higher than the oscillations in the average cladding heat flux because of inherent delay in the transfer of heat through the fuel rods. The NRC Augmented Inspection Team (AIT) for the March 9, 1988 LaSalle event reported that the amplitude of the heat flux oscillations during the event were estimated to be less than 10% of the value for the neutron flux oscillations and that because of the smaller changes in heat flux, thermal limits for the fuel were not exceeded.
(4) General Electric Company has provided BWR licensees with guidance on the proper methods to monitor for therinal-hydraulic instabilities and on the actions that should be taken to suppress such oscillations if they should occur. Most BWRs have implemented such methods in response to NRC Generic Letter 86-02 which provided for the technical resolution of Generic Issue B-19. The operating limita- e tions which ensure compliance with GDC 12 are enforced by plant technical specifications.
(5) Compliance with the recorinendations in NRC Bulletin No. 88-07 will l ensure that any licensed reactor operator or shif t technical advisor performing shift duties at a BWR will have been thoroughly briefed regarding the LaSalle event; and that all BWR licensees will have adequate procedures and operatur training programs in place to address power oscillations, regardless of the results of any previous thermal hydraulic stability analysis. The NRC will perform inspections and take any necessary follow-up action to ensure that procedures and training programs at.ceptable to the technical staff l
have been put in place.
1 Your Petition is being treated under 10 CFR 2.206 of the Comission's regulations. Appropriate action will be taken within a reasonable tine. A copy of the notice that is being filed for publication with the Office of the Federal Register is enclosed for your inforration. Copies of this letter are being sent to those named on the service lists for facilities listed in Enclosure 2.
Sincerely, Thomas E. Murley, Director Office of Nuclear Reactor Regulation
Enclosures:
- 1. Federal Register Notice
- 2. List of Facilities for cc
[7590-01]
NUCLEAR REGULATORY COMMISSION
[ DOCKET NO. 50-374]
COMMONWEALTH EDISON COMPANY (LaSalle County Station, Unit 2)
RECEIPT OF PETITION FOR DIRECTOR'S DECISION UNDER 10 CFR 2.206 Notice is hereby given that by Petition dated July 22, 1988, Ohio Citizens for Responsible Energy, Inc. requested the Director of Nuclear Reactor Regulation to take imediate action with respect to Boiling Water Reactors to relieve what Petitioner alleged to be undue risks to the public health and safety posed by an event at LaSalle County Station, Unit 2, in Illinois on March 9, 1988. Petitioner's request for imediate relief was .
denied because the allegations hhich form the basis of the Petition did not reveal any new operational safety issues which pose en imediate safety concern for continued BWR operation.
The Petition is being treated pursuant to 10 CFR 2.206 of the Comission's regulations. As provided by i 2.206, appropriate action will be O ken on the Petition within a reascnable time.
A copy of the Petition is available for inspection in the Comission's Public Document Roosi,1717 H Street, NW., Washington, D.C. 20555 and in the local public document room for LaSalle County Station Unit 2 at Jacobs Memorial Library, Illinois Valley Coesmnity College, Rural Route One, Oglesby, Illinois 61348.
FOR THE NUCLEAR REGULATORY COP 911SS10N f W-T omas E. Murley, Director Office of Nuclear Reactor Regu a Dated at Rockville, Maryland this 26 day of August, 1988
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N SusagL.Hiatt Enclosure 2 List of Facilities for cc BOSTON EDISON CO. (PilgrimNuclearPowerStation,DocketNo.50-293)
CAROLINA POWER & LIGHT CO. (Brunswick Station, Units 1 & 2, Docket Hos. 50-324 & 50-325)
CLEVELAND ELECTRIC ILLUMINATING CO., ET AL. (Perry Nuclear Power Plant, UnitI,DocketNo.50-440)
COMMONWEALTH EDISION CO. (Dresden Nuclear Power Plant, Units 2 & 3, Docket Nos. 50-237 1. 50-249 ; (Quad Cities Nuclear Power Plant, Units 1 & 2, Docket Nos. S0-254 & 50-265 ; (LaSalle County Station, Units 1 & 2, Docket Nos. 50-373 & 50-374 CONSUMERS POWER CO. (Big Rock Point, Docket No. 50-155)
DETROIT EDISON CO. (Fermi Unit 2, Docket No. 50-341)
GEORGIA POWER CO. (Hatch Nuclear Power Plant, Units 1 & 2, Docket No. 50-321&50-366)
GULF STATES UTILITIES CO. (River Bend Station, Docket No. 50-458)
ILLIN0ISPOWERCO.(ClintonNuclearPlant,DocketNo.50-461)
IOWA ELECTRIC LIGHT & POWER CO. (Duane Arnold Nuclear Power Plant, Docket 50-331)
GENERAL PUBLIC UTILITIES (Oyster Creek Station, Docket No. 50-219)
LONGISLANDLIGHTINGCO.(ShorehamNuclearPowerPlant,DocketNo.50-322)
MISSISSIPPI POWER & LIGHT CO. (Grand Gulf Nuclear Station, Docket No. 50-416)
NEBRASKA PUBLIC POWER DISTRICT (Cooper Station, Docket No. 50-298)
N!AGARA MOHAWK POWER CORP. (Nine Mile Point, Units 1 & 2, Docket Hos. 50-220 & 50-410) i NORTHEASTUTILITIES(Millstone, Unit 1DocketNo.50-245)
NORTHERNSTATESPOWERCO.(MonticelloNuclearPowerPlant,DocketNo.50-263)
PENNSYLVANIA POWER & LIGHT CO. (Susquehanna Steam Electric Station, Units 1 & 2, Docket No. 50-387 & 50-388).
PHILADELPHIA ELECTRIC CO. (Peach Bottom Nuclear Station, Units 2 & 3, Docket No.
50-277 & 50-278); (Limerick Nuclear Power Plant, Unit 1 Docket No. 50-352) j POWER AUTHORITY OF THE STATE OF NEW YORK (James A. Fitzpatrick Station,.
DocketNo.50-333)
PUBLIC SERVICE ELECTRIC & GAS CO. (P,1pe Creek Generating Station, Docket No. 50 354)
TENNESSEE VALLEY AUTHORITY (Browns Ferry Nuclear Station, Units 1, 2, & 3 Docket Nos 50-259, 50-260, and 50 296)
! YERMONT YANKEE NUCLEAR POWER CORP. (Ver1nont Yankee Nuclear Plant, Docket No. 50-271)
WASHINGTONPUBLICPOWERSUPPLYSYSTEM(WNPUnit2,DocketNo.50397) l
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