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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 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 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 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 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 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) 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response 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 ML20210F3731999-07-23023 July 1999 Submits Confirmation That,Iaw 10CFR50.80,PSE&G Is Requesting NRC Approval of Transfer of Ownership Interests in PBAPS, Units to New Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML20210E6211999-07-22022 July 1999 Submits Rev to non-limiting Licensing Basis LOCA Peak Clad Temps (Pcts) for Limerick Generating Station (Lgs),Units 1 & 2 & Pbaps,Units 2 & 3 ML20210E5811999-07-21021 July 1999 Forwards Final Tech Specs Pages for License Change Application.Proposed Change Will Revise Tech Specs to Delete Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS ML20216D8041999-07-19019 July 1999 Submits Summary of Final PECO Nuclear Actions Taken to Resolve Scram Solenoid Pilot Valve Issues Identified in Info Notice 96-007 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217F3021999-10-12012 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 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 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 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 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 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 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 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 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 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 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML20210F3731999-07-23023 July 1999 Submits Confirmation That,Iaw 10CFR50.80,PSE&G Is Requesting NRC Approval of Transfer of Ownership Interests in PBAPS, Units to New Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML20210E6211999-07-22022 July 1999 Submits Rev to non-limiting Licensing Basis LOCA Peak Clad Temps (Pcts) for Limerick Generating Station (Lgs),Units 1 & 2 & Pbaps,Units 2 & 3 ML20210E5811999-07-21021 July 1999 Forwards Final Tech Specs Pages for License Change Application.Proposed Change Will Revise Tech Specs to Delete Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS ML20216D8041999-07-19019 July 1999 Submits Summary of Final PECO Nuclear Actions Taken to Resolve Scram Solenoid Pilot Valve Issues Identified in Info Notice 96-007 05000278/LER-1999-002, Forwards LER 99-002-01 to Correct Title Contained in Box (4) of LER Coversheet Form.Rev Does Not Change Reportability Requirements or Any Other Info Contained in Original Submittal of LER1999-07-12012 July 1999 Forwards LER 99-002-01 to Correct Title Contained in Box (4) of LER Coversheet Form.Rev Does Not Change Reportability Requirements or Any Other Info Contained in Original Submittal of LER ML20209G9121999-07-0909 July 1999 Informs That Ja Hutton Has Been Appointed Director,Licensing for PECO Nuclear,Effective 990715.Previous Correspondence Addressed to Gd Edwards Should Now Be Sent to Ja Hutton ML20209D9781999-07-0808 July 1999 Forwards Addl Info to Support EA of Proposed 990212 License Application ECR 98-01675,correcting Minor Administrative Errors in TS Figure Showing Site & Exclusion Areas Boundaries & Two TS SRs ML20209D8821999-07-0707 July 1999 Submits Estimate of Number of Licensing Actions Expected to Be Submitted in Years 2000 & 2001,as Requested by Administrative Ltr 99-02.Renewal Applications for PBAPS, Units 2 & 3,will Be Submitted in Second Half of 2001 ML20209D2671999-07-0202 July 1999 Responds to NRC 990322 & 0420 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20209E1131999-06-30030 June 1999 Forwards Proprietary NRC Form 398, Personal Qualification Statement-Licensee, for Renewal of RO Licenses for EP Angle,Md Lebrun,Jh Seitz & Zi Varga,Licenses OP-10646-1, OP-11081,OP-11082 & OP-11085,respectively.Encls Withheld ML20209B7001999-06-30030 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20209C1201999-06-30030 June 1999 Informs of Util Intent to Request Renewed License for PBAPS, Units 2 & 3,IAW 10CFR54.Licensee Anticipates That License Renewal Application Will Be Submitted in Second Half of 2001 05000277/LER-1999-004, Forwards LER 99-004-00 Re Unplanned ESF Actuations During Planned Electrical Bus Restoration Following Maint Activities1999-06-20020 June 1999 Forwards LER 99-004-00 Re Unplanned ESF Actuations During Planned Electrical Bus Restoration Following Maint Activities ML20196A5291999-06-14014 June 1999 Forwards Final Pbaps,Unit 3 TS Pages for License Change Request ECR 98-01802 Re Installation of Digital Power Range Neutron Monitoring (Prnm) Sys & Incorporation of long-term thermal-hydraulic Stability Solution Hardware ML20195E6051999-05-27027 May 1999 Requests Exemption from Requirements of 10CFR72.44(d)(3) Re Submittal Date for Annual Rept of Principal Radionuclides Released to Environ.Exemption from 10CFR72.72(d) Re Storage of Spent Fuel Records,Additionally Requested ML20195B8171999-05-25025 May 1999 Forwards Final TS Pages for License Change Application ECR 96-01511 Re Rev to Loss of Power Setpoints for 4 Kv Emergency Buses ML20195B6191999-05-19019 May 1999 Forwards PBAPS Units 2 & 3 Annual Radiological Environ Operating Rept 56 for 980101-1231, Per Section 6.9.2 of Ol. Trace Concentrations of Cs-137 Were Found in Sediment Consistent with Levels Observed in Previous Years ML20206P9171999-05-10010 May 1999 Updates Some of Transmitted Data Points Provided in Data Point Library ERDS for Pbaps,Units 2 & 3.Data Point Info Format Consistent with Guidance Specified in NUREG-1394 ML20206K6581999-05-0404 May 1999 Forwards PBAPS Bases Changes Through Unit 2 Bases Rev 25 & Units 3 Bases Rev 25.Bases Reflect Change Through Apr 1999, Thereby Satisfying Frequency Requirements of 10CFR50.71 ML20206D4651999-04-29029 April 1999 Forwards Rev 16 to UFSAR & Rev 11 to Fire Protection Program (Fpp), for Pbaps,Units 2 & 3.Page Replacement Instructions for Incorporating Rev 16 to UFSAR & Rev 11 to Fpp,Encl ML20207B8431999-04-23023 April 1999 Forwards Final Rept for 981117,plume Exposure Pathway Exercise of Offsite Radiological Emergency Response Plans site-specific for Peach Bottom Atomic Power Station.One Deficiency & 27 Areas Requiring C/A Identified ML20206C5461999-04-20020 April 1999 Forwards Radioactive Effluent Release Rept 41 for Jan-Dec 1998 for Pbaps,Units 1 & 2. Revs Made to ODCM & Station Process Control Program (PCP) During Rept Period,Encl 05000277/LER-1999-003, Forwards LER 99-003-00 Re 990318 Failure to Maintain Provisions of Fire Protection Program to Properly Address Effects of Flooding1999-04-16016 April 1999 Forwards LER 99-003-00 Re 990318 Failure to Maintain Provisions of Fire Protection Program to Properly Address Effects of Flooding ML20205K4541999-04-0808 April 1999 Forwards Revised Info Re 990330 NRC Nuclear Power Reactor Licensee Financial Qualifications & Decommissioning Funding Assurance Status Rept 05000278/LER-1999-001, Forwards LER 99-001-00 Re 990312 ESF Actuation of Rcics Due to High Steam Flow Signal During Sys Restoration.Rept Submitted Per 10CFR50.73(a)(2)(iv)1999-04-0808 April 1999 Forwards LER 99-001-00 Re 990312 ESF Actuation of Rcics Due to High Steam Flow Signal During Sys Restoration.Rept Submitted Per 10CFR50.73(a)(2)(iv) ML18106B1431999-03-31031 March 1999 Forwards Pse&G Rept on Financial Min Assurance for Period Ending 981231 for Hope Creek,Salem,Units 1 & 2 & Pbaps,Units 2 & 3,IAW 10CFR50.75 ML20205F8981999-03-31031 March 1999 Provides Info Re Status of Decommissioning Funding for LGS, Units 1 & 2,PBAPS,Units 1,2 & 3 & Sgs,Units 1 & 2,per Requirements of 10CFR50.75(f)(1) ML18106B1411999-03-30030 March 1999 Forwards Decommissioning Info on Behalf of Conectiv Nuclear Facility License Subsidiaries,Atlantic City Electric Co & Delmarva Power & Light Co,For Listed Nuclear Facilities ML20205J0831999-03-26026 March 1999 Requests Enforcement Discretion from Requirements of PBAPS, Units 2 & 3 Ts.Enforcement Discretion Pursued to Avoid Unneccessary Plant Transient Which Would Result from Compliance with TS ML20205B6421999-03-24024 March 1999 Submits 1998 Annual Decommission Rept for Pbaps,Unit 1. There Were No Reportable Events Involving Unit 1 for 1998 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML20064A7171990-09-18018 September 1990 Comments on SALP Board Repts 50-277/89-99 & 50-278/89-99. Author Pledges Continued Mgt Support of & Attention to Rate of Improvement,Achievement of Goals & Performance of Routine Activities ML20065D4421990-09-14014 September 1990 Responds to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule. Proposed Schedules for Operator Licensing Exams, Requalification Exams & Generic Fundamental Exams Encl ML20064A7751990-09-13013 September 1990 Advises That Ba Stambauth No Longer Maintains Need to Hold Senior Operator License ML20065D3741990-09-11011 September 1990 Forwards Rev to Relief Request 10-VRR-2 Re RHR stay-fill Supply Check Valves,Per ML20059F0541990-08-31031 August 1990 Responds to NRC Re Violations Noted in Safety Insp Repts 50-277/90-13 & 50-278/90-13.Corrective Actions: Training Will Be Provided for Personnel Re Requirements of Drawing E1317 & Administrative Procedures A-2 & A-6 ML20028G8181990-08-27027 August 1990 Forwards Peach Bottom Atomic Power Station Semiannual Effluent Release Rept,Jan-June 1990. No Revs Made to ODCM During Rept Period ML20059A6461990-08-15015 August 1990 Responds to Violation Noted in Insp Repts 50-277/90-200, 50-278/90-200,50-277/90-06 & 50-278/90-06 & Payment of Civil Penalty in Amount of $75,000.Corrective Actions:Emergency Svc Water Sys Restored to Operable Status ML20058N1991990-08-0909 August 1990 Advises of Change of Address for Correspondence Re Util Operations.All Incoming Correspondence Must Be Directed to One of Listed Addresses ML20058Q4051990-08-0606 August 1990 Forwards Public Version of Revised Emergency Response Procedures,Including Rev 12 to ERP-140,App 2,Rev 13 to ERP-140,App 3,Rev 4 to ERP-230,Rev 3 to ERP-305 & Rev 3 to ERP-660 ML20058M6631990-08-0303 August 1990 Responds to NRC 890406 Integrated Assessment Team Insp Repts 50-277/89-81 & 50-278/89-81.Based on Encl Schedule,Overall Projected Implementation Date Will Be 901119 ML20056A9611990-08-0303 August 1990 Notifies That Be Saxman Terminated Employment & Operating Responsibilities W/Util on 900706 ML20081E1581990-07-30030 July 1990 Forwards List of 1990 QA Program Changes for Plant.List Identifies Page & Paragraph Number,Brief Description & Type of Change ML20056A0421990-07-27027 July 1990 Forwards Updated Human Resource Status Rept for Jan-Jul 1990 for Areas Identified in Integrated Assessment Team Insp Repts 50-277/89-81 & 50-278/89-81 ML18095A3761990-07-26026 July 1990 Forwards Decommissioning Repts & Certification of Financial Assurance for Plants ML18095A3661990-07-26026 July 1990 Forwards Decommissioning Repts for Hope Creek,Peach Bottom & Salem Nuclear Generating Stations ML18095A3721990-07-24024 July 1990 Forwards Rept & Certification of Financial Assurance for Decommissioning for Plants,Per 10CFR50.75 ML20055H8331990-07-20020 July 1990 Submits Change of Addresses for Correspondence Re Util Nuclear Operations ML20044B2621990-07-12012 July 1990 Forwards Annual Progress Rept on Implementation of Control Room Enhancements,Per NUREG-0737.Corrective Actions for All Priority 1 Human Engineering Discrepancies Completed for Unit.Remaining Priority 2 Discrepancies Under Reevaluation ML20055G5481990-07-11011 July 1990 Forwards Public Version of Revised Epips,Including Rev 12 to ERP-140,App 3 & Revs 3 to ERP-310 & ERP-317 ML20043H7041990-06-21021 June 1990 Forwards Endorsements 143-146 to Nelia Policy NF-140 & Endorsements 93-96 to Maelu Policy MF-67 ML20044A2961990-06-21021 June 1990 Submits Revised Response to NRC Bulletin 89-002 Re safety- Related Swing Check Valves to Be Installed on Emergency Diesel Generator.Bolts Will Not Be Replaced Because Valves W/Original Internal Bolts Meet Requirements of Bulletin ML20043H6081990-06-19019 June 1990 Corrects 900427 Response to Generic Ltr 87-07, Info Transmittal of Final Rulemaking for Revs to Operator Licensing - 10CFR55 & Conforming Amends. ML20055C7621990-06-18018 June 1990 Informs NRC of Plans Re Licensing of Senior Reactor Operators (Sros) Limited to Fuel Handling at Plants.Util in Process of Implementing New Program for Establishment & Maint of Licensed SROs Limited to Fuel Handling at Plants ML20043G8131990-06-13013 June 1990 Responds to NRC 900515 Ltr Re Violations Noted in Insp Repts 50-277/90-06 & 50-278/90-06.Corrective Actions:Surveillance Test 6.16, Motor Driven Fire Pump Operability Test, Will Be Revised ML20043H0111990-06-12012 June 1990 Advises That AR Wargo Reassigned from Operating Shift Responsibilities & Will Be Resigning License,Effective on 900514 ML20055D1141990-06-0808 June 1990 Forwards Public Version of Revs to Emergency Response Procedures,Including Rev 9 to ERP-140 & Rev 3 to ERP-315 ML20043D7351990-06-0404 June 1990 Responds to NRC 900504 Ltr Re Violations Noted in Insp Repts 50-277/90-04 & 50-278/90-04.Corrective Actions:Procedural Controls Strengthened to Preclude Licensed Operators from Performing Licensed Duties W/O Successfully Passing Exams ML20043E9261990-06-0404 June 1990 Forwards Response to 900327 Request for Addl Info Re Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. ML20043D2681990-05-31031 May 1990 Forwards Response to NRC Requests Re PECo-FMS-0006, Methods for Performing BWR Reload Safety Evaluations. Util Core Monitoring Activities Routinely Access Accuracy of steady-state Physics Models Used in Evaluation of Parameter ML20043D6451990-05-30030 May 1990 Responds to NRC 900503 Ltr Re Violations Noted in Insp Repts 50-277/90-08 & 50-278/90-08.Corrective Actions:Glaucoma Testing Program Initiated for Security Personnel & Necessary Equipment to Perform Glaucoma Testing Onsite Obtained ML20055C5491990-05-18018 May 1990 Forwards Response to Request for Addl Info on 900412 Tech Spec Change Request 89-20 Re Postponement of Next Snubber Visual Insp,Due 900526,until Scheduled mid-cycle Outage in Fourth Quarter 1990 ML20055C5121990-05-18018 May 1990 Provides Info Inadvertently Omitted in Re Property Insurance Coverage for Plants.Limerick Generating Station Unit 2 Should Have Been Ref as Being Included Under Insurance Coverage ML20055C4851990-05-15015 May 1990 Forwards Annual Financial Repts for 1989 for Philadelphia Electric Co,Pse&G,Atlantic Energy,Inc & Delmarva Power & Light Co ML20043A3341990-05-14014 May 1990 Advises of Util Proposal to Provide Response to NRC Request for Schedule for Compliance W/Reg Guide 1.97 Re Neutron Monitoring Instrumentation 3 Months After NRC Concurrence W/Bwr Owners Group Design Criteria ML20042E7651990-04-27027 April 1990 Informs That Mod 2285 Completed on Unit 3,but That Mod 2285 Will Not Be Completed on Unit 2 During 8th Refueling Outage ML20042E8931990-04-27027 April 1990 Responds to Violation Noted in Insp Rept 50-278/90-01. Corrective Actions:Automatic Depressurization Sys Logic Sys Functional Tests Will Be Revised to Include Guidance in Unique Application of Test Lights ML20042F3241990-04-27027 April 1990 Advises That Organizational Changes Made in Advance of Approval of Tech Spec Change Request 88-06.Changes Do Not Present Unreviewed Safety Question ML20042E8741990-04-27027 April 1990 Responds to Generic Ltr 87-07, Info Transmittal of Final Rulemaking for Revs to Operator Licensing. Certifies That Limerick Operator Requalification Training Program Renewed on 900125 & Peach Bottom Subj Program Renewed on 890622 ML20012F4801990-04-0202 April 1990 Forwards Errata to Unit Shutdowns and Power Reductions Monthly Operating Rept for Feb 1990 ML20012F0971990-03-22022 March 1990 Forwards Summary of ASME Repairs & Replacement Completed, Per Facility Second 10-yr Interval Inservice Insps Completed During 900331-891111 Extended Refueling Outage ML20012E2151990-03-20020 March 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants,' for Peach Bottom.Response for Limerick Generating Station Will Be Provided by 900504 ML20012C2931990-03-12012 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey, Per 900118 Request ML20012B6211990-03-0808 March 1990 Provides Actions Taken to Ensure & Verify Sys Design Basis Performance,Per 900205 SSFI at Facility ML20012B9011990-03-0606 March 1990 Forwards 870331-891111 Inservice Insp Program Final Rept for Peach Bottom Atomic Power Station Unit 3 1987-1989 Extended Refuel Outage. Several Indications Identified ML20012A2661990-02-26026 February 1990 Forwards Application for Amends to Licenses DPR-44 & DPR-56, Consisting of Tech Spec Change Requests 89-13 & 89-14, Revising Nuclear Review Board Membership & Meeting Frequency & Adding Independent Safety Engineering Group Requirements ML20011F2541990-02-23023 February 1990 Forwards Revs to Physical Security Plan.Encls Withheld (Ref 10CFR73.21 & 2.790) ML20011F3791990-02-21021 February 1990 Provides Revised Schedule for Installation of Hardened Wetwell Vent,Per Generic Ltr 89-16 & Explanation Why Jan 1993 Completion Date Cannot Be Met Due to Unavailability of Matls.Intallation Scheduled for Cycle 9 Outage ML20006F5491990-02-16016 February 1990 Certifies That 891122 Tech Spec Change Request (Tscr) 89-15, 891228 Tscr 88-18 & 900214 Tscr 90-04 Mailed to Commonwealth of Pa,Dept of Environ Resources ML20006F1621990-02-15015 February 1990 Forwards Progress Rept Re Implementation of Control Room Enhancements as of End of Seventh Refueling Outage,Per NUREG-0737.Rept Delayed to Allow for Independent Verification of Control Room Enhancement Status ML20012B1731990-02-15015 February 1990 Forwards Public Version of Revs to Epips,Including Rev 5 to ERP-101,App 1 to Rev 13 to ERP-110,App 2 to Rev 10 to ERP-110,App 1 to Rev 7 to ERP-140,App 2 to Rev 10 to ERP-140,App 3 to Rev 11 to ERP-140 1990-09-18
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PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 SHIELDS L. DALTROFF rLecInic"ra$oS"c som July 23, 1986 Docket No. 50-278 Inspection Report No. 50-278/86-09 Mr. James M. Taylor, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555
REFERENCE:
Letter, T. E. Murley, USNRC, to S. L. Daltroff, PECo, Dated June 9, 1986
Dear Sir:
The referenced letter transmitted a Notice of Violation and Proposed Imposition of Civil Penalties relative to Inspection Report No. 50-278/86-09 for Peach Bottom Atomic Power Station Unit 3. A base civil penalty of $50,000 for each of two violations was proposed with an increase of 100% for each penalty. The increase of 100% for each penalty was proposed "to emphasize the need for increased management involvement and attention in station activities to assure improved personnel performance".
Two items were identified in the Notice which do not appear to be in full compliance with Nuclear Regulatory Commission requirements. These items are restated below followed by Philadelphia Electric Company's response to the Notice in accordance with Section 2.201 of the Commission's regulations and the instructions in the Notice. Also included is the Company's answer, pursuant to 10 CFR Section 2.205, which seeks mitigation of the amount of the proposed civil penalties.
P
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4 Mr. James M. Taylor July 23, 1986 i Page 2 Restatement of Violations:
i I.A. Technical Specification 6.8.1 requires that written procedures shall be established, implemented, and maintained covering the activities of Appendix A of Regulatory Guide 1.33, November 1972. Appendix A of l Regulatory Guide 1.33 states in part that the activity I of " Hot. Standby to Minimum Load (nuclear Startup)"
requires procedures.
! Technical Specification 6.8.1 is implemented by the Peach Bottom General Procedure GP-2, Appendix 1, j Revision 3, "Startup Rod Withdrawal Sequence
- Instructions." Step 13 of GP-2 requires the reactor operator to withdraw control rod 02-23.
f . t
- Contrary to the above, at 1:28 a.m. on March 18, 1986
) while at step 13 of GP-2, Appendix 1, the reactor
- operator withdrew control rod 10-23 rather than rod
- 02-23 and incorrectly documented that rod 02-23 had i
been withdrawn.
i l B. Technical Specification Limiting Condition for
]~ Operation 3.3.B.3.b requires that whenever the reactor is in the startup or run mode below 25% rated power,
- the Rod Worth Minimizer shall be operable or a second licensed operator shall verify that the operator at the reactor console is following the control rod i program.
4 Contrary to t he above, at 1:28 a.m. on March 18, 1986, I
> while the reactor was in the startup mode below 25%
j power and the Rod Worth Minimizer was inoperable, the
- second licensed operator did not' verify adherence to-
- the control rod program and identify that a wrong control rod (10-23) was withdrawn. The second
~
l licensed operator also incorrectly documented that rod 02-23 had been withdrawn.
This is a Severity Level III problem (Supplen.ent I)..
! (Civil Penalty - $100,000 assessed equally among the j violations).
t II.A. Technical Specification Limiting Condition for Operation 3.3.B.3.a and 3.3.A.2.d require that
- whenever the reactor is in the startup or run mode
- below 21%_ rated power, the Rod Sequence Control System
- (RSCS) shall be operable, and no position switches a shall be bypassed unless'the control rods are moved in sequence to their correct postion and the actual rod position is known.
i I
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Mr. James M. Taylor July 23, 1986 Page 3 Contrary to the above, between 2:30 and 2:55 a.m. on March 18, 1986, when a Group 3 rod withdrawal was attempted while the reactor was in the startup mode below 21% rated power, a rod block occurred. The RSCS position switch for rod 02-23 was bypassed to the full-out position by the Shift Supervisor and the Shift Superintendent when in fact the rod was full-in.
B. Technical Specification Surveillance Requirement 4.3.A.2.d requires that a second licensed operator verify a control rod is in its correct position before the RSCS function is bypassed.
Contrary to the above, on March 18, 1986 when the RSCS function was bypassed for control rod 02-23, the second licensed operator failed to verify that control rod 02-23 was in the correct position.
This is a Severity Level III problem (Supplement I).
(Civil Penalty - $100,000, assessed equally among the violations).
Licensee's Section 2.201 Response to Notice of Violation and Proposed Imposition of Civil Penalties Admission of Alleged Violations:
Philadelphia Electric Company acknowledges the alleged violations as stated above.
Reasons for the Violations:
The violations were caused by a series of personnel errors involving failure of the reactor operator to withdraw the correct control rod, failure of a second operator to verify that the correct withdrawal sequence was being followed, and failure of a' Shift Supervisor and Shift Superintendent to verify the proper position of a control rod prior to bypassing the RSCS input for that rod.
Consequences of the Event:
The Philadelphia Electric Company Nuclear Fuel Management Section and GenerzL Electric (GE) Company have reviewed this e' rent and determit ed that the current Unit 3 reload analysis 2nd Drop Accident (RDA) results bound this event. The
Mr. James M. Taylor July 23, 1986 Page 4 various RDA scenarios associated with this event were identified during the review. The worst case RDA results of the scenarios show a peak enthalpy deposition of approximately 120 calories / gram compared to the RDA design criteria of 280 calories / gram. The 280 calories / gram design criteria value bounds all currently licensed fuel bundle exposure values. Therefore the Unit 3 reactor operated in a condition such that RDA consequences would not have exceeded the design criteria.
Corrective Actions Taken and Results Achieved:
The Operations Superintendent directed a manual scram of the reactor because that was the most prudent, conservative, and expeditious response to ensure compliance with the Technical Specifications.
The four individuals responsible for this event were disciplined. Disciplinary measures involved three suspensions and one written reprimand.
Detail Prior to discovery of the out-of-sequence control rod, the dayshift Shift Superintendent requested that the reactor engineer reset the process computer in an effort to return the RWM to service. Within 20 minutes the computer had been reset and the RWM was reinitialized. It then displayed an insert error for control rod 02-23. The Control Room Shift Supervisor checked the position of that control rod and found that it was full-in and that the RSCS input for that rod was bypassed to give the RSCS a full-out signal for that rod. He immediately returned the bypass switch to normal to comply with Technical Specification 3.3.A.2.d. The Shift Superintendent, the Shift Supervisor, and the Reactor Engineer discussed the Technical Specification implications of this situation and possible corrective actions. By 8:30 AM, the Shift Superintendent reported the rod position error to the Operations Engineer and Operations Superintendent. '
At 3:42 AM control rod insertion was begun to return the l reactor to a control rod pattern in accordance with the RSCS and RWM.
When the decision was made to manually scram, the NRC Site )
Inspector was informed and he reported to the Control Room 1 within a few minutes. The Plant Manager and the I Superintendent-Nuclear Generation, who were in Philadelphia I at the corporate headquarters, were immediately dispatched to the plant to investigate the matter.
Mr. James M. Taylor July 23, 1986 Page 5 An investigation was begun, and all of the operators who were involved were contacted immediately by a Shift Superintendent to develop the investigation report and determine the cause of the Technical Specification violations. On March 18, 1986, that investigation report was presented to station management and corrective actions were developed. Later that day the sequence of events and the corrective actions were presented to Philadelphia Electric Company Electric Production Department management and USNRC Region 1 personnel by conference call. The restart of the unit was delayed until this event was analyzed and appropriate corrective actions were developed and presented to Operations personnel, including the revision and PORC approval of procedures necessary to prevent recurrence.
Corrective Actions Taken to Prevent Recurrence:
To prevent recurrence, the following actions have been developed and implemented:
- 1. A letter was issued on March 18, 1986 from the 1
Operations Superintendent to all licensed personnel outlining the event and describing interim requirements for verification of proper rod positioning.
- 2. A procedural control has been implemented to use the plant process computer to generate a rod position map at the completion of withdrawal of specific rod groups if the RWM is out of service. The computer generated map will be compared to a rod position map which is attached to the operator's rod withdrawal sheet. The two maps will then be verified to be identical before proceeding to the next rod group.
- 3. Six procedures involving RWM and RSCS have been revised and PORC approved to enhance the procedural requirements. Included in these revisions is the RSCS bypass procedure which has been revised to require a Shift Supervision signature for proper verification of rod position prior to bypassing the RSCS input for any rod.
- 4. On March 24, 1986 the Plant Manager issued a letter to
, Shift Supervision to ensure that best efforts are made to place the RWM in service prior to commencing reactor startup. In accordance with this direction, the procedure for manual bypass of the RWM has been revised to require the permission of the Plant
I
- i Mr. James M. Taylor July 23,'1986 Page~6 4
4 i Manager, Operations Superintendent, or Operations l Engineer as a prerequisite to such manual bypass.
! 5. When rod movements are being performed with the RWM bypassed, the RWM manual bypass procedure requires that the second licensed operator shall have no other duties and shall verify that the proper rod sequence i is being followed.
- 6. Plant. staff management meetings have been held with i all Operations Personnel to discuss the event and
- individual responsibilities. I i
- 7. The four individuals responsible for this event were ,
disciplined. Disciplinary measures involved three !
suspensions and one written reprimand.
J j Further, Philadelphia Electric has begun the process
~
of implementing the Human Performance Evaluation System (HPES) at
- both Peach Bottom and Limerick. The HPES has been developed i through a pilot program by the Institute of Nuclear Power ,
! Operations (INPO) and several nuclear utilities. HPES's i objective is to identify and correct situations that cause human j errors. The success of this program is' dependent on operating,
, maintenance and testing personnel reporting actual or potential
{ situations that can cause human errors so that they can be i
corrected before someone else is put into thelsame situation.
)
Date When Full Compliance was Achieved:
Full compliance with the Technical Specifications which were l violated during this event was achieved on March 18, 1986
] when Unit 3 was manually scrammed at 0855 hours0.0099 days <br />0.238 hours <br />0.00141 weeks <br />3.253275e-4 months <br />. j t
i l Licensee's Answer Pursuant to 10 CFR Section'2.205 and Request i 1 for Mitigation of Amount of Proposed Civil Penalties !
{ Concerning the imposition of civil penalties as l discussed in the referenced letter, Philadelphia Electric Company i believes that the additional increase of 100% for each of the two l penalties is excessive, unwarranted and fails to properly balance I the factors enumerated in Appendix-C to Part 2 in determining the j appropriate penalty level. Accordingly, Philadelphia Electric '
j Company requests that consideration be given to reducing the ;
j proposed penalty of $200,000 to the base penalty of $100,000. q Your letter of June 9, 1986 additionally stated, "We view such problems as being indicative of a lack of management i
involvement in and attention to station activities to assure that l l
i
! l l
~___._____._ ___ ___.__.__..___ _ _,_._-_ _ -.
Mr. James M. Taylor July 23, 1986 Page 7 the station personnel respect, understand the need for, and adhere to your policies and procedures for the safe operation of the facility."
Four specific instances were referenced in support of assessment that there is a continuing inattention to detail, failure to adhere to procedural requirements, and a generally complacent attitude of staff toward performance of their duties being indicative of a lack of management involvement and attention to station activities to assure improved personnel performance. These examples covered the time period of 1983 to the present. Four violations of containment integrity that resulted from the failure of non-licensed individuals to follow procedures in 1983 was the earliest event referenced. The second referenced violation occurred June 18, 1984 involving control room personnel errors including two instances when heat up rates were exceeded, and one instance when the reactor vessel was pressurized above limits. Indeed, the 1984 Civil Penalty associated with the violation was mitigated from $40,000 to
$30,000 because of our unusually prompt and extensive corrective actions taken. An unreferenced 1985 Civil Penalty was mitigated from $50,000 to $25,000 because of PECo's " comprehensive corrective actions". The third event cited involved a 1985 event concerning the apparent inattentiveness of a licensed operator while at the controls of the reactor, an event which resulted in removal of this individual from nuclear related work under our fitness for duty program for medical reasons. This event did not involve inattention to detail but fitness for duty.
The fourth event cited was the most recent one detailed in the report proposing these civil penalties. Our investigation determined that the cause was human error wherein ,
the operators believed they were following the procedures. The 1 error was one in which they failed to view the limit lights. The management does not condone this error, and dispensed prompt discipline, as described in Corrective Actions Taken and Results Achieved.
We can not agree that increased emphasis is required to improve management involvement in order to assure personnel performance, nor do we see a pattern of inattention to detail, failure to adhere to procedural requirements, and a general complacent attitude on the part of the staff. We do recognize unrelated occurrences resulting from human error. Our management and supervisors continually express the need to follow procedures and pay close attention when conducting operations.
We do not believe that our staff has a complacent attitude. It is not uncommon for our staff to propose alternative ways for conducting an activity. These proposals, although not always implemented, are directed toward betterment
Mr. James M. Taylor July 23, 1986 Page 8 of operations. We encourage this and view such proposals as indications of a healthy attitude, an attitude not expected of a complacent group.
On May 20, 1985, Philadelphia Electric reorganized the nuclear station management structure to provide for improved management attention to day-to-day activities by splitting the major station responsibilities between two Superintendents who report to a Station Manager. Further, we announced on March 27, 1986 the further strengthening of Nuclear Production Management by providing a Superintendent for Limerick 2 Construction and Startup and appointing an experienced Manager from Limerick to the position of Superintendent Nuclear Generation, the position to which the Plant Manager reports.
This appointment was made with the direction that close attention be paid to the activities at Peach Bottom with the aim of strengthening those weaknesses which had been identified by INPO and the NRC. The Superintendent - Nuclear Generation has been meeting frequently with the power plant staff to develop programs to eliminate these weaknesses. He reviews and assesses progress and has daily discussions with corporate
! management. While the full effect of these changes has yet to be seen, we believe that the initial favorable effects were observed by the recent NRC evaluation team during a two-week inspection of l Peach Bottom. Note that the planning of this action pre-dates the March 18 incident.
]
In further support of the requested mitigation of the proposed penalties and as directed by the referenced letter, the 1 five factors contained in Section V.B of Appendix C to Part 2 are 1 addressed below.
- 1. Prompt Identification and Reporting (reduction of up to 50% of the base civil penalty may be given when a Licensee identifies the violation and promptly reports
- the violation to NRC).
The Unit 3 reactor was operated with control rod 02-23 out-of-sequence for a relatively short period of time.
The error was identified by the control room operators, was promptly reported to the NRC Resident Inspector, and the NRC was kept fully advised of developments in this matter (See discussion, Corrective Actions Taken and Results Achieved).
Further, the unit was promptly shutdown. After discovery of the error, Philadelphia Electric Company is convinced that prompt and appropriate actions both relating to the reporting to the Commission and the recovery of the plant to a safe status were taken by i
management and shift personnel. Philadelphia Electric 4
4 k
-l
Mr. James M. Taylor July 23, 1986 Page 9 Company requests that the Commission consider the prompt managerial actions taken in recognition of this condition and consider this a factor to mitigate these penalties.
- 2. Corrective Action to Prevent Recurrence (reduction or increase by as much as 50% of the base civil penalty may be given depending upon the promptness and extensiveness of Corrective Actions and Actions Taken to Prevent Recurrence).
Philadelphia Electric Company believes it did take prompt and extensive corrective action to prevent recurrence. Technical and process oriented corrective action was promptly taken including prompt institution of an investigation to determine root cause.
Immediate cause was determined to be personnel error.
Management, after in-depth investigation of the error, determined that failure to follow approved procedures was the root cause. Disciplinary action, -
considered severe within the Philadelphia Electric Company, was taken against the operators and supervisors involved. While specific actions have been taken such as reviewing procedures and improving them where required, and holding meetings specific to this incident with all operating shifts, Philadelphia Electric believes that the basic failing was with certain individuals and, therefore, the NRC should give positive consideration to these comprehensive actions when analyzing this request for mitigation of the proposed penalties.
- 3. Past Performance (reduction or increase by as much as 100% of the base civil penalty may be given depending upon past performance in the general area of concern).
l Philadelphia Electric Company is convinced that the, root cause in this case is failure to follow its approved procedures. In this particular case the procedures were followed as to the technical aspects, except that human effort combining failure to observe j and proceeding on an untrue assumption permitted rod '
withdrawal out of sequence. Philadelphia Electric '
believes its past performance as a nuclear operating utility, as demonstrated by the lack of enforcement action in these areas, should support mitigation of the action doubling the proposed civil penalties.
- 4. Prior Notice of Similar Event (an increase of as much as 50% of the base civil penalty may be given if the Licensee had prior knowledge of a problem as a result l
I
. s Mr. James M. Taylor July 23, 1966 Page 10
's of a Licensee audit, or specific NRC or industry
. notification, and had failed to take effective
/ preventive steps).
t This event occurred as a result of personnel errors in that personnel neglected to observe the actual rod position of rod 02-23. It was not the result of e
failure to consider prior notices of similar events.
- 5. kultipleOccurrences(anincreaseofasmuchas50%of the base civil penalty may be given where multiple examples of a particular violation are identified during the inspection period).
No similar violations were identified during the inspection period.
Based upon the foregoing, it is our belief that the Company has responded promptly and extensively in resolving the underlying causes of the violations which resulted in the Notice i
of Violation and Proposed Imposition of Civil Penalties. We believe that the Company has demonstrated a recognition of the seriousness of the occurrence and that we have taken strong and effective measures to prevent recurrence. It is our view that in determining the amount of a civil penalty, the NRC should consider our discussion of its concerns with management attention and should balance the positive factors, described more fully above, regarding prompt identification and reporting and ;
corrective actions taken against the factors identified in the Notice of Violation as the bases for the 100% increase in the civil penalties. Accordingly, it is hereby requested that the proposed penalties be mitigated as described herein.
Should you have any questions or require additional information, please do not hesitate to contact us.
Very trul yours,
./
l/ /
./
cc: Dr. T. E. Murley, Administrator, Region I, USNRC Mr. T. P. Johnson, Resident Site Inspector l
l 1
- - - _, . -- - . -- l
COMMONWEALTH OF PENNSYLVANIA : ,
- ss.
COUNTY OF PHILADELPHIA :
S. L. Daltroff, being first duly sworn, deposes and says:
That he is Vice President of Philadelphia Electric Company, that he has read the Company's foregoing Section 2.201 Response to Notice of Violation and Proposed Imposition of Civil Penalties concerning NRC Inspection Report No. 50-278/86-09 and the Company's answer, Pursuant to 10 CFR 2.205, and Request for Mitigation of Amount of Civil Penalties and knows the contents 1 thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.
n a L,7 J ll Subscribed and sworn to rcl before me this23 day of j , /fYb
//a/O / A
,, Notary Public MELANIE R. CAMPANELt.A Notary Public Phitadcl;:hia, Phifade?ph!a Co.
My Commission Empires February 12,19SQ
.