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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 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 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 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 IR 05000277/19990061999-09-0808 September 1999 Forwards Insp Repts 50-277/99-06 & 50-278/99-06 & 72-1027/99-06 on 990628-0809.No Violations Noted 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 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 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 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 ML20062C7451990-10-26026 October 1990 Forwards Safety Evaluation Accepting Response to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow ML20058D2371990-10-26026 October 1990 Informs of Impending fitness-for-duty Program Insp & Requests 10CFR26.20 Required Policies & Procedures 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 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 IR 05000277/19900041990-06-25025 June 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-277/90-04 & 50-278/90-04 ML20044A4651990-06-18018 June 1990 Extends Invitation to Attend Power Reactor Operator Licensing Seminar on 900801 in King of Prussia,Pa to Discuss Recent Changes to Format for Requalification/Initial Exams. Agenda & Info Re Lodging Accomodations Encl 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 ML20043E4061990-06-0606 June 1990 Forwards Safety Insp Repts 50-277/90-12 & 50-278/90-12 on 900514-18.No Violations Noted ML20058K1961990-05-31031 May 1990 Forwards Results & Conclusions of Regulatory Effectiveness Review on 900507-11.Encl Withheld (Ref 10CFR73.21) ML20042G3831990-05-0303 May 1990 Forwards Physical Security Insp Repts 50-277/90-08 & 50-278/90-08 on 900326-30 & Notice of Violation ML20042G0601990-04-30030 April 1990 Forwards Safety Insp Repts 50-277/90-09 & 50-278/90-09 on 900402-06.No Violations Noted.Complete Data from Independent Measurements Will Be Reported in Subsequent Insp Rept ML20042F1331990-04-26026 April 1990 Forwards Requalification Reexam Repts 50-352/90-14(OL) & 50-353/90-13(OL) Administered on 900406.Two Operators That Passed Exam Can Resume Performing Licensed Duties NUREG-0991, Forwards Safety Evaluation Accepting Response to Generic Ltr 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Matls & Impact on Plant Operation1990-04-23023 April 1990 Forwards Safety Evaluation Accepting Response to Generic Ltr 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Matls & Impact on Plant Operation IR 05000277/19902001990-03-29029 March 1990 Provides List of More Significant Concerns Identified During SSFI Insp Repts 50-277/90-200 & 50-278/90-200 on 900205- 0302.Complete List of Insp Findings Will Be Provided in Insp Repts IR 05000353/19890321990-03-12012 March 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violation Noted in Insp Rept 50-353/89-32 ML20033F1121990-03-0707 March 1990 Forwards Enforcement Conference Rept 50-352/90-04 on 900223 Re Violations Involving 10CFR50,App R Fire Safe Shutdown Issues at Plant.Notice of Significant Licensee Meeting 90-023 Also Encl 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 ML20011E0621990-01-23023 January 1990 Forwards Exam Repts 50-277/89-18OL & 50-278/89-18OL Administered During Wks of 890814 & 0918 ML20042D3521989-12-26026 December 1989 Forwards Safety Insp Repts 50-277/89-23 & 50-278/89-23 on 891008-1120.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 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 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 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 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 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 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 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 IR 05000277/19990061999-09-0808 September 1999 Forwards Insp Repts 50-277/99-06 & 50-278/99-06 & 72-1027/99-06 on 990628-0809.No Violations Noted 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 ML20211H2571999-08-26026 August 1999 Informs of Individual Exam Result on Initial Retake Exam on 990812.One Individual Was Administered Exam & Passed 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 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 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 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 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 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 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 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 ML20206K1921999-05-0606 May 1999 Discusses 990503 Telcon Between J Williams & B Bierly Re Arrangements Made for Administration of Licensing Exam at Peach Bottom Facility During Week of 990913 1999-09-09
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UNITED STATEb E
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WASHINGTON, D C. 20555 c'
NUCLEAR REGULATORY COMMISS'ON
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AU6101988 Docket Nos.
50-277; 50-278 License Nos. OPR-44; DPR-56 EA 88-04 Philadelphia Electric Company ATTN: Mr. J. Paquette, Jr.
President and Chief Operating Officer 2301 Market Street Philadelphia, Pennsylvania 19101 Gentlemen:
SUBJECT:
ORDER AND NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF CIVIL PENA 1.TY (NRC Office of Investigation Report No. 1-87-003)
In March 1987, the NRC received information that control room operators at your Peach Bottom Atomic Power Station had been observed sleeping while on duty in the control room, reading materials not directly job related, and being other-wise inattentive to the obligations of their license.
The NRC confirmed this infonnation during the initial phase of the investigatien and also determined that all levels of plant management at that time either knew or should have known of these facts and either took no action or inadequate action to correct this situation. As a result, the NRC no longer had reasonable assurance that the facility would be operated in a manner to assure that the health and safety of the public would be protected, and therefore, issued an Order to Philadelphia Electric Company (PEco) on March 31, 1987 suspending operations of the Peach Bottom reactors.
Subsequently, the NRC determined that the inattentiveness described in the Order had occurred over an extended period of time and was pervasive, and the failure by site and corporate management to identify, investigate, and correct these conditions, and report it to the NRC, demonstrated a significant lack of management attention to, and control of, operations at Peach Bottom. These deficiencies constitute serious violations of NRC requirements.
The violations, which are set forth in the enclosed Notice, involved:
(1) PEco's willful violation of control room staffing requirements, in that licensed operators and senior licensed operators were sufficiently inatten-tive so as not to be considered present for purposes of meeting the staffing requirements, and this inattentiveness was condoned by shift supervisors and shift superintendents; (2) the failure by plant operations management (Opera-tions Engineer and Superintendent of Operations) who knew of this significant condition adverse to safety, and the failure by the then plant manager and corporate management who should have known of this condition, to investigate.
identify and correct this condition; and (3) PECo's failure to report this adverse condition to the NRC even though operations management (including Shift y;perintendents and Shif t Supervisors) perations Engineer, and fonner the for er Operation Superintendent, fonner O had credible infonration for an l
extended period regarding this significant safety concern.
@I G808190243 880810 PDR ADOCK 05000277 O
PDC
l Philadelphia Electric Company.
These instances of inattentiveness by licensed and senior licensed operators also included: control room personnel routinely reclined in a resting position with their head back and eyes closed for indeterminate periods of time; control room personnel playing video games either on a hand held computer or on a con-trol room computer display; and horseplay in the control room. Such conduct was indicative of a complacent and unprofessional attitude by these individuals toward their responsibilities described in their licenses, and constituted serious dereliction of duties by these individuals in carrying out those responsibilities. While these adverse conditions in themselves are unaccept-able and could have contributed to inadequate operator response to degraded plant conditions, this pervasive inattentiveness, as well as management's failure to detect and correct it, are even more disturbing when viewed in light of the overali enforcement history that existed at Peach Bottom in the four years prior to the shutdown.
During that time, the NRC issued six civil penalties and an Order to PECo, and also conducted fourteen enforcement con-ferences with PECo senior management, to discuss numerous violations of NRC requirements at Peach Bottom, including violations involving inattention to detail, failure by licensed individuals to follow procedural requirements, failure to respond to indications of problems, and numerous personnel errors by several licensed individuals, including shift supervisors and shift superintendents.
In the letter transmitting a $200,000 civil penalty issued on June 9, 1986, the NRC indicated that the problems that were the subject of that penalty were indicative of a "lack of management involvement in and attention to station activities to assure that the station personnel respect, understand the need for, and adhere.to your policies and procedures for safe operation of the facility." Notwithstanding these prior NRC concerns, and a prior enforcement conference conducted on June 21, 1985 for another situation in which an operator gave the appearance of sleeping, operators continued to exhibit a generally complacent and unprofessional attitude toward their roles and responsibilities, and continued to disregard the administrative procedure which set forth the requirement that an operator be alert and attentive to his duties.
Furthermore, shift supervisors and shift superintendents participated in and condoned this unacceptable performance; operations management outside the control room, when confronted with this problem, did not aggressively pursue resolution; and corporate and plant managenent did not aggressively pursue related problems, such as continuing inadequate staffing leading to chronic excessive overtime on the part of operators, which would have made identifi-cation and correction of this condition more likely.
These deficiencies represented a continuation of a declining trend in performance at Peach Bottom, and demonstrated a significant lack of accountability throughout the PECo organization.
The NRC recognizes that PEco has, since the shutdown, (1) made extensive per-sonnel changes within their organization, including the Chainnan of the Board and Chief Executive Officer, President and Chief Operating Officer, Executive Vice-President - Nuclear, Vice President - Peach Bottom, Plant Manager, and i
Operations Management, and has created the new Shift Manager position respon-sible for the daily operation and supervision of each shift, and (2) replaced or rescinded, as applicable, the licenses and senior licenses of several individuals, including the fonner Superintendent of Operations, the former Oper-ations Engineer, and the Shift Superintendents.
Further, the other licensed individuals who comprised the operations staff at the time of the shutdown were 1
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Philadelphia Electric Company I placed in an extensive rehabilitation program and have been subjected to indi-vidual enforcement conferences with the NRC.
Notwithstanding these actions, given the nature and number of previous NRC concerns, and the pervasive and extended inattentiveness and dereliction of duty identified during the NRC investigation, as well as an independent investigation conducted by PECo's Claims Security Division, the failure by corporate management to be aware of this condition at Peach Bottom and to take appropriate corrective action con-stitutes a significant regulatory concern, and is viewed by the NRC as a primary cause of the events that contributed to NRC issuance of the shutdown Order. While the NRC holds licensed operators individually accountable to the NRC for their actions, as evidenced by civil penalties issued concurrently to all but three of these individuals, this complacent and unprofessional attitude by the operators was consistent with the similar attitude exhibited by nine levels of management extending from shift supervisors to the Chainnan of the Board.
Additionally, should you seek to relicense the former shift superintendents the NRC may at a minimum require that either they (1) participate in a rehabilitation program similar to your "People, Foundation for Excellence," course or (2) justify to the NRC why participation in such a program is unnecessary.
Therefore, the violations described in the enclosed Notice of Violation and Proposed Imposition of Civil Penalty (Notice) are classified in the aggregate as a Severity Level II problem in accordance with Section III of the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR 2, AppendixC(EnforcementPolicy)(1988), A Saverity Level II classification is warranted because of the very significant regulatory concern and the high potential impact on the public health and safety resulting from the number of operators involved, the nature of their actions, and the pervasiveness throughout the shif t and operations management hierarchy.
The NRC recognizes that (1) the Peach Bottom facilities were shut down by the NRC, have remained shutdown for over a year despite various submittals of corrective actions, and will remain shut down until the NRC has reasonable assurance that the measures taken to correct this condition are suitable to prevent recurrence; and (2) the Order and its associated shutdown costs should have sent a clear message to PECo, as well as all other licensees, that the NRC will not tolerate such conduct and will apply its maximum enforcement authority, when warranted, to ensure that such conduct does not occur. However, in recognition of the fact that weaknesses in both corporate and site management oversight and inattentive-ness on the part of the operators were long standing problems at Peach Bottom that PECo could have addressed, I have decided that additional action is needed to (1) further emphasize to the licensee and its Board of Directors, as well as all other utilities, the significance of this problem, and to ensure that corrective actions taken are long lasting, and (2) emphasize to all licensees that in addition to the cost of corrective action, a licensee may face the additional costs of sanctions for significant safety violations.
Therefore, after consultation with the Comission, I am iv;uing the enclosed Notice of Violation and Proposed Imposition of Civil Penalty in the cumulative amount of One Million Two Hundred and Fifty Thousand Dollars ($1,250,000) for the violations set forth in the enclosed Notice. The amount of the civil penalty is based on issuance of a civil penalty of $25,000 per day for the period extending from when your management personnel clearly had credible evidence of the problem on February 2, 1987 until the day (March 24,1987) the NRC established 24-hour coverage in the Peach Bottom control room. By selecting this date the NRC staff does not mean to imply that prior to that date your plant and corporate management did
i Philadelphia Electric Company I l
l not know or should have not known of the inattentiveness in the control room rather, February 2, 1987 represents a date certain on which two levels of plant I
management knew of the problems.
In addition to the civil penalty, although PECo has removed the three levels of plant management who knew or should have known of this condition, the NRC is also issuing the enclosed Order restricting their involvement in any responsible management or operations position with PEco without prior Commission approval.
Such action is necessary because the then Operations Engineer and the then Superintendent of Operations knew of this condition, yet took no action to correct it, and the then Plant Manager as the senior site representative should have been aware of this condition.
You are required to respond to this letter and should follow the instructions specified in the enclosed Notice when preparing your response. After reviewing your response to this Notice, including your proposed corrective actions and the results of future inspections, the NRC will detemine whether further NRC enforcement action is necessary to ensure compliance with NRC regulatory requitements.
In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2, Title 10 Code of Federal Regulations, a copy of this letter and its enclosure will be placed in the NRC Public Document Room.
Furthermore, a copy of this enforcement action is also being sent to the Chairman of the Board of each reactor utility in the United States as a notification and reminder that the l
NRC will not tolerate such activities.
i The responses directed by this letter and the enclosed Fotice are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, Pub. L. No.96-511.
Sincerely.
/
Nb mes M. Tay1
, Deputy Executive Director for Reg <onal Operations
Enclosures:
1.
Notice of Violation and Proposed Imposition of Civil Penalty 2.
Order Modifying License 3.
01 Report Synopsis I
See next page for cc's.
i
Philadelphia Electric Company ec w/encis:
Corbin McNeill, Executive Vice President, Nuclear Dickinson M. Smith, Vice President, Peach Bottom Atomic Power Station John S. Kemper, Senior Vice President, Nuclear J. Gallagher, Vice President, Nuclear Services Thomas S. Shaw, Jr., Vice President, Production John F. Franz, Plant Manager, Peach Bottom Atomic Power Station Troy B. Conner, Jr., Esquire W. H. Hirst, Director, Joint Generation Projects Department, Atlantic Electric 1
Eugene J. Bradley, Esquire, Assistant General Counsel Raymond L. Hovis, Esquire i
Thomas Hagette, Power Plant Siting, Nuclear Evaluations W. M. Alden, Engineer in Charge, Licensing Section Doris Poulsen, Secretary of Harford County Council Public Document Room (PDR)
LocalPublicDocumentRoom(LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector Connonwealth of Pennsylvania Chairman of the Board, all Reactor Utilities State of Maryland i
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j Philadelphia Electric Company i
bCC W/encls.
- d og Docket 7 Room (w/ concurrences ))
Congressional Affairs J. Taylor, DEDO W. Russell, RI D. Holody, RI J. Liebenran, OE Enforcement Directors, RII-RIII Enforcement Officers, RIV-V J. Crooks, AE0D B. Hayes, 01 S. Connelly, 01A F. Miraglia, NRR D. Nussbaumer, 0GPA OE/ES File OE/EA File EDO Rdg File 005 L. Chandler, 0GC OE RI NRR OGC
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