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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P2061999-10-26026 October 1999 Forwards for First Energy Nuclear Operating Co Insp Rept 50-346/99-17 on 990928-1001.Insp Was Exam of Activities Conducted Under License Re Implementation of Physical Security Program.No Violations Identified ML20217N3851999-10-20020 October 1999 Forwards RAI Re Licensee 990521 Request for License Amend to Allow Irradiated Fuel to Be Stored in Cask Pit at Davis-Besse,Unit 1.Response Requested within 60 Days from Receipt of Ltr ML20217N2321999-10-15015 October 1999 Requests NRC Approval to Use Alternative to Requirements of 10CFR50.55a(f)(4)(ii).Licensee Requests Extension to Specified Schedule for Implementing Updates to IST Program ML20217G9201999-10-14014 October 1999 Discusses Utils Request for Approval of Quality Assurance Program Changes PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F8371999-10-0808 October 1999 Forwards Insp Rept 50-346/99-10 on 990802-0913.One Violation Occurred Being Treated as NCV ML20217A5641999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Davis-Besse on 990901.Informs That NRC Plans to Conduct Addl Insps to Address Questions Raised by Issues Re Operator Errors & Failure to Commit to JOG Topical Rept on MOV Verification ML20212L0691999-09-30030 September 1999 Forwards,For Review & Comment,Copy of Preliminary ASP Analysis of Operational Condition Discovered at Unit 1 on 981014,as Reported in LER 346/98-011 ML20216J6701999-09-24024 September 1999 Forwards Post Examination Documentation for Written Operator Initial License Examination Administered at Davis-Besse Nuclear Power Station on 990920.Without Encls ML20212D3501999-09-21021 September 1999 Forward Copy of Final Accident Sequence Precursor Analysis of Operational Event at Plant,Unit 1 on 980624,reported in LER 346/98-006 05000346/LER-1998-001, Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached1999-09-0909 September 1999 Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached ML20216E5961999-09-0707 September 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation ML20211P3001999-09-0707 September 1999 Forwards FEMA Transmitting FEMA Evaluation Rept for 990504 Emergency Preparedness Exercise at Davis-Besse Nuclear Power Plant.No Deficiencies Identified.One Area Requiring C/A & Two Planning Issues Identified ML20211K6681999-08-30030 August 1999 Forwards Copies of Certified Personal Qualification Statement - Licensee (NRC Form 398) for Operator Candidates Listed Below.Without Encls ML20211K6611999-08-30030 August 1999 Forwards Copies of Operator License Renewal Applications for Individuals Listed.Operators Have Successfully Completed Appropriate Operator Requalification Training Program at Dbnps.Without Encls ML20211K0951999-08-30030 August 1999 Forwards Request for Addl Info Re Fire & Seismic Analyses of IPEEE for Davis-Besse Nuclear Power Station,Unit 1. Response Requested within 60 Days ML20211H0201999-08-25025 August 1999 Forwards semi-annual FFD Rept for 990101-0630 for DBNPS, Unit 1,IAW 10CFR26.71(d) ML20211D1171999-08-20020 August 1999 Forwards Insp Rept 50-346/99-09 on 990623-0802.Violations Identified & Being Treated as Noncited Violations ML20211G3911999-08-20020 August 1999 Forwards Update to Estimated Info for Licensing Action Requests Through 010930,re Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates PY-CEI-NRR-2411, Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl1999-08-19019 August 1999 Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl ML20211J9201999-08-13013 August 1999 Urges NRC to Find Funds for Stockpiling Radiation Pills for Residents Living Near Plant ML20211B0161999-08-13013 August 1999 Forwards SE Accepting Evaluation of Second 10-year Interval Inservice Insp Program Request for Relief Numbers RR-A16, RR-A17 & RR-B9 for Plant,Unit 1 ML20210T1061999-08-12012 August 1999 Forwards Preliminary NRC Forms 398 & 396 for Listed Candidates,Per Operator License Exam Scheduled for Week of 990913.Encl Withheld ML20210S6071999-08-11011 August 1999 Provides Final Response to NRC RAI Re GL 98-01, Y2K Readiness of Computer Systems at Npps ML20210P8051999-08-0909 August 1999 Forwards Insp Rept 50-346/99-15 on 990712-16.No Violations Noted.However,Several Deficiencies Were Identified with Implementation of Remp,Which Collectively Indicated Need for Improved Oversight of Program IR 05000346/19980211999-08-0606 August 1999 Refers to NRC Insp Rept 50-346/98-21 Conducted on 980901- 990513 & Forwards Nov.Two Violations Identified Involving Failure to Maintain Design of Valve & Inadequate C/A for Degraded Condition Cited in Encl NOV 05000346/LER-1998-009, Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl1999-08-0606 August 1999 Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl ML20210H6101999-07-30030 July 1999 Informs That Region III Received Rev 21 to Various Portions of Davis-Besse Nuclear Power Station Emergency Plan.Revision Was Submitted Under Provisions of 10CFR50.54(q) in Apr 1999 ML20210H0491999-07-28028 July 1999 Forwards Application for Amend to License NPF-3,revising TS 3/4.7.5.1, Ultimate Heat Sink, to Allow Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G5521999-07-28028 July 1999 Provides Addl Response to 980923 OL Licensing Exam Rept 50-346/98-301 Re OL Exam Administered in Aug 1998.Results of Root Cause Investigation & Corrective Actions,Discussed ML20210G3831999-07-27027 July 1999 Forwards Application for Amend to NPF-3,changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20211P3071999-07-26026 July 1999 Forwards Final Rept for 990504 Biennial Radiological Emergency Preparedness Exercise for David-Besse Power Station.No Deficiencies Identified for Any Jurisdiction During Exercise ML20210G4391999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1, Safety Features Actuation Sys Instrumentation, & Associated Bases 3/4.3.1 & 3/4.3.2, Reactor Protection Sys & Safety Sys Instrumentation ML20210G7151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising TSs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrument - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs for Implementation of 10CFR50,App J,Option B for Type B & C Containment Leakage Rate Testing ML20210G3211999-07-26026 July 1999 Forwards Written OL Exam & Supporting Matl for Exam to Be Administered at DBNPS During Week of 990913.Listed Encls Withheld from Public Disclosure Until After Exam Complete ML20210C4381999-07-20020 July 1999 Forwards Insp Rept 50-346/99-08 on 990513-0622.Unidentified RCS Leak Approached TS Limit of 1 Gallon Per Minute Prior to Recently Completed Maint Outage.Three Violations of NRC Requirements Identified & Being Treated as NCVs ML20209G3681999-07-15015 July 1999 Advises That Info Submitted in & 990519 Affidavit Re Design & Licensing Rept,Davis-Besse,Unit 1 Cask Pit Rack Installation Project,Holtec Intl, HI-981933,marked Proprietary,Will Be Withheld from Public Disclosure ML20207H6401999-07-0909 July 1999 Discusses Closure of TAC MA0540 Re Util Responses to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. Staff Has Revised Info in Rvid & Releasing It as Rvid Version 2 ML20209D1341999-07-0808 July 1999 Forwards Notice of Withdrawal of Application for Amend to Operating License.Proposed Change Would Have Modified Facility TSs Pertaining to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves 05000346/LER-1998-012, Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached1999-07-0707 July 1999 Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached ML20209C3981999-07-0101 July 1999 Responds to NRC Re Violations Noted in Insp Rept 50-346/98-21.Corrective Actions:Developed Rev to Boric Acid Control Program & Work Process Guideline on Plant Leakage ML20209B5821999-06-24024 June 1999 Provides Justification for Rev to Completion Date for One of Insp follow-up Items Cited in Insp Rept 50-346/98-03, Designated as Inspector follow-up Item 50-346/97-201-10 ML20196G1251999-06-23023 June 1999 Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20196E5321999-06-17017 June 1999 Forwards Addl Info Re Relief Request RR-A16 to Support NRC Approval of Relief Request ML20195K2751999-06-16016 June 1999 Forwards Safety Evaluation Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 ML20195F9071999-06-10010 June 1999 Forwards Application for Amend to NPF-3,changing Tech Specs 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20195F8851999-06-0707 June 1999 Withdraws 950929 License Amend Application,Proposing Mod to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves ML20207G0751999-06-0707 June 1999 Forwards Insp Rept 50-346/99-04 on 990323-0513.Violations Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058H6411990-11-0909 November 1990 Forwards Final SALP Rept 50-346/90-01 Covering Mar 1989 to June 1990 ML20058E7141990-10-30030 October 1990 Forwards Exam Forms & Answer Keys,Grading Results & Individual Answer Sheets for Each Applicant ML20058D6771990-10-25025 October 1990 Forwards Exemption Request for Reactor Operators Selected for NRC Requalification Exam ML20058F4811990-10-24024 October 1990 Forwards Safety Insp Rept 50-346/90-16 on 900814-1009.No Violations Noted ML20062C6811990-10-18018 October 1990 Forwards Safeguards Insp Rept 50-346/90-19 on 900924-28.No Violations Noted ML20059N6661990-10-0909 October 1990 Forwards Correction to SER Re Request for Relief from ASME Boiler & Pressure Vessel Code,Section XI Requirements.W/O Encl IR 05000346/19900091990-09-26026 September 1990 Forwards Insp Repts 50-346/90-09,50-346/90-12 & 50-346/90-13 on 900417-0717 & Notice of Violation ML20059M2101990-09-25025 September 1990 Forwards Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exams to Be Administered on 901010,including Map of Area Where Exams Will Be Taken, Preliminary Instructions for Exam & Equation Sheet ML20059L6041990-09-14014 September 1990 Confirms 901002 Meeting at Plant Site to Present Initial SALP 8 Rept for Facility ML20059J2511990-09-13013 September 1990 Forwards Safety Insp Rept 50-346/90-17 on 900827-31.No Violations Noted ML20059G1431990-09-0404 September 1990 Forwards Safety Insp Rept 50-346/90-15 on 900701-0813. Violation Noted But Not Cited.Util Implemented Corrective Actions as Result of Violation & Will Be Examined During Future NRC Insps ML20056B2701990-08-20020 August 1990 Forwards Safety Evaluation Granting 900710 Request for Relief from ASME Code for Class 3 Piping in Svc Water Sys. Request Granted Until Next Scheduled Outage Exceeding 30 Days But No Later than Dec 1991 ML20059A6821990-08-13013 August 1990 Forwards Safety Insp Rept 50-346/90-09 on 900417-0717. Violations Noted But Not Cited.Util Will Be Notified by Separate Correspondence of NRC Decision Re Enforcement Action Based on Findings of Insp ML20059A6721990-08-10010 August 1990 Forwards Safety Insp Rept 50-346/90-13 on 900605-30 & 0709. Violation Noted But Not Cited ML20059A6631990-08-10010 August 1990 Forwards Enforcement Conference Rept 50-346/90-14 on 900601 & 900717 Telcon Re Violations Noted in Insp Repts 50-346/90-09 & 50-346/90-12 ML20059A7161990-08-0808 August 1990 Provides Comments on 900105 Response to Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & Surveillance. Util Should Provide Description of Methodology for Periodic Verification of motor-operated Valve Switch Settings ML20058M6141990-08-0707 August 1990 Forwards Sample Registration Ltr for 901010 Generic Fundamentals Section of Written Operator Licensing Exam. Registration Ltr Listing Names of Candidates Taking Exam Should Be Submitted to Region 30 Days Prior to Exam Date ML20055J2761990-07-24024 July 1990 Confirms 900731 Meeting in Region III Ofc to Discuss Util Response to Violation Re Instrumented Insp Techniques ML20055G6621990-07-20020 July 1990 Forwards Safety Insp Rept 50-346/90-10 on 900430-0518.No Violations Noted ML20055G3051990-07-13013 July 1990 Confirms 900718 Tour of Plant & Mgt Meeting to Discuss Sixth Refueling Outage & Other Items of Mutual Interest ML20055F2231990-07-0606 July 1990 Ack Receipt of Containing Scope & Objectives for 1990 Emergency Plan Exercise Scheduled on 900919 ML20055D9781990-06-29029 June 1990 Advises That 900614 Changes to QA Program Meet 10CFR50,App B Requirements & Acceptable.Nrc Should Be Notified of Changes to QA Commitments Existing in Docketed Correspondence Outside QA Program Description ML20055D3181990-06-29029 June 1990 Advises of Safety & Performance Improvement Program Implementation Audit Scheduled for Wk of 900716-20.Selected Samples of Technical Recommendations Encl ML20059M8631990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248D8211989-09-29029 September 1989 Forwards Safety Evaluation Accepting Util 890228 & 0630 Proposed plant-specific Designs to Comply w/10CFR50.62 ATWS Rule Requirements.Proposed Date of May 1990 for Implementing ATWS Mods Also Acceptable ML20248C5691989-09-27027 September 1989 Forwards Amend 6 to Indemnity Agreement B-79,reflecting Changes in 10CFR140, Financial Protection Requirements & Indemnity Agreements, Effective 890701 ML20248A4711989-09-25025 September 1989 Requests Submission of Update Rept or Replacement Pages to Updated FSAR Submitted on 890721 to Appropriate Regional Ofc,Per 10CFR50.4(b)(6).Review of Updated QA Program Description,Section 17.2 Will Require More than 60 Days ML20247H9201989-09-0707 September 1989 Responds to Requesting Emergency Notification Sys Phone at Plant.Proposed Method for Recording Would Involve Emergency Notification Sys Phones Located in Control Room, Technical Support Ctr,Emergency Control Ctr & Inspector Ofc ML20247B4361989-09-0505 September 1989 Forwards Safety Insp Rept 50-346/89-18 on 890807-11.No Violations Noted ML20246L6571989-08-30030 August 1989 Responds to Re Annual Requalification Exam Grading Results.Based on Reviews & Consultations W/Nrc, Remedial Training,Consistent W/Identified Weaknesses, Provided & Intent of Requalification Program Met ML20246C4561989-08-17017 August 1989 Forwards Safety Insp Rept 50-346/89-16 on 890605-0716 & 24 & Notice of Violation.Violation Noted in Paragraph 7 of Rept Identified by Util Meets Criteria of 10CFR2,App C,Section V.G,Therefore Notice of Violation Will Not Be Issued ML20245J7641989-08-0909 August 1989 Forwards Insp Rept 50-346/89-20 on 890724-28.No Violations Noted ML20245F1061989-08-0303 August 1989 Confirms That Written & Oral Exams Scheduled for Wk of 891211.Ref Matl Listed on Encl & Reactor Operator License Applications Should Be Submitted at Least 60 Days Prior to Exam Date ML20247N8521989-07-28028 July 1989 Confirms 890908 Enforcement Conference in Glenn Ellyn,Il to Suppl & Clarify Info Provided by Util in 890228 Response to 880128 Insp Rept 50-346/88-04 & Notice of Violation Re Approval of Procedure AD 1805,Rev 27 ML20247C2911989-07-19019 July 1989 Forwards Addendum to Insp Rept 50-346/89-08 Transmitted by ,Consisting of Comparisons of Results of Liquid Sample Collected During Insp & Criteria for Comparing Analytical Measurements ML20247C3271989-07-19019 July 1989 Advises That 890616 Rev 7 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable IR 05000346/19890121989-07-18018 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violation Noted in Insp Rept 50-346/89-12 Re Failure to Assemble Fire Brigade Immediately Upon Receipt of Any Unplanned Fire Alarm ML20246E7781989-07-0505 July 1989 Forwards Safety Insp Rept 50-346/89-17 on 890614-16.No Violations Noted ML20245K9891989-06-23023 June 1989 Forwards Safety Insp Rept 50-346/89-15 on 890605-09.No Violations Noted.Response to Concerns Re Use of Request for Info Forms & Document Change Requests to Correct Deficiencies Identified in Design Documents Requested ML20245G1371989-06-22022 June 1989 Forwards Safety Insp Rept 50-346/89-14 on 890424-0604. No Response to Violations Required ML20245H1941989-06-21021 June 1989 Requests That Results of Review of Encl Allegation RIII-89-A-0081 & Disposition of Matter Be Submitted within 30 Days of Ltr Date.Encl Withheld (Ref 10CFR2.790) ML20244D7791989-06-12012 June 1989 Comments on Util 890103 Response to Generic Ltr 88-17 Re Expeditious Actions for Loss of Dhr.Expeditious Actions to Achieve Immediate Reduction in Risk Associated W/Reduced Inventory Operation Will Be Replaced by Program Enhancement ML20244B6911989-06-0606 June 1989 Forwards Safety Insp Rept 50-346/89-13 on 890315-19.No Violations Noted ML20248A0581989-06-0202 June 1989 Informs That Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Response Indicated Rev to CCW Sys Operating & Alarm Procedure Prior to Restart for Cycle 6 to Ensure That 4-hr Limit on Min Flow Not Exceeded ML20247N9471989-05-31031 May 1989 Advises of Conclusion That Allegation RIII-88-A-0057 Re Improper Work Practices for Duct Work Unsubstantiated ML20247G4041989-05-18018 May 1989 Forwards Safeguards Insp Rept 50-346/89-07 on 890221-0417.No Violations Noted.Requests That Util Retain Supporting Documentation for Investigation of Allegation for Min of 1 Yr from Date of Ltr ML20247J8181989-05-18018 May 1989 Forwards Amend 133 to License NPF-3 & Safety Evaluation. Amend Deletes from License All Remaining Sections of App B ML20247D1211989-05-12012 May 1989 Forwards Safety Insp Rept 50-346/89-11 on 890301-0423.Notice of Violation Will Not Be Issued Since Violations Identified by Licensee ML20246K7541989-05-0505 May 1989 Forwards Insp Rept 50-346/89-12 on 890313-17 & 0418 & Notice of Violation ML20246H7951989-05-0303 May 1989 Forwards Insp Rept 50-346/89-06 on 890131-0209.No Violations or Deviations Noted.Written Statement within 30 Days to Resolve Items,Including Operator Entry Into Emergency Procedure from Abnormal Procedures,Requested within 30 Days 1990-09-04
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217P2061999-10-26026 October 1999 Forwards for First Energy Nuclear Operating Co Insp Rept 50-346/99-17 on 990928-1001.Insp Was Exam of Activities Conducted Under License Re Implementation of Physical Security Program.No Violations Identified ML20217N3851999-10-20020 October 1999 Forwards RAI Re Licensee 990521 Request for License Amend to Allow Irradiated Fuel to Be Stored in Cask Pit at Davis-Besse,Unit 1.Response Requested within 60 Days from Receipt of Ltr ML20217G9201999-10-14014 October 1999 Discusses Utils Request for Approval of Quality Assurance Program Changes ML20217F8371999-10-0808 October 1999 Forwards Insp Rept 50-346/99-10 on 990802-0913.One Violation Occurred Being Treated as NCV ML20217A5641999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Davis-Besse on 990901.Informs That NRC Plans to Conduct Addl Insps to Address Questions Raised by Issues Re Operator Errors & Failure to Commit to JOG Topical Rept on MOV Verification ML20212L0691999-09-30030 September 1999 Forwards,For Review & Comment,Copy of Preliminary ASP Analysis of Operational Condition Discovered at Unit 1 on 981014,as Reported in LER 346/98-011 ML20212D3501999-09-21021 September 1999 Forward Copy of Final Accident Sequence Precursor Analysis of Operational Event at Plant,Unit 1 on 980624,reported in LER 346/98-006 ML20211P3001999-09-0707 September 1999 Forwards FEMA Transmitting FEMA Evaluation Rept for 990504 Emergency Preparedness Exercise at Davis-Besse Nuclear Power Plant.No Deficiencies Identified.One Area Requiring C/A & Two Planning Issues Identified ML20211K0951999-08-30030 August 1999 Forwards Request for Addl Info Re Fire & Seismic Analyses of IPEEE for Davis-Besse Nuclear Power Station,Unit 1. Response Requested within 60 Days ML20211D1171999-08-20020 August 1999 Forwards Insp Rept 50-346/99-09 on 990623-0802.Violations Identified & Being Treated as Noncited Violations ML20211B0161999-08-13013 August 1999 Forwards SE Accepting Evaluation of Second 10-year Interval Inservice Insp Program Request for Relief Numbers RR-A16, RR-A17 & RR-B9 for Plant,Unit 1 ML20210P8051999-08-0909 August 1999 Forwards Insp Rept 50-346/99-15 on 990712-16.No Violations Noted.However,Several Deficiencies Were Identified with Implementation of Remp,Which Collectively Indicated Need for Improved Oversight of Program IR 05000346/19980211999-08-0606 August 1999 Refers to NRC Insp Rept 50-346/98-21 Conducted on 980901- 990513 & Forwards Nov.Two Violations Identified Involving Failure to Maintain Design of Valve & Inadequate C/A for Degraded Condition Cited in Encl NOV ML20210H6101999-07-30030 July 1999 Informs That Region III Received Rev 21 to Various Portions of Davis-Besse Nuclear Power Station Emergency Plan.Revision Was Submitted Under Provisions of 10CFR50.54(q) in Apr 1999 ML20210C4381999-07-20020 July 1999 Forwards Insp Rept 50-346/99-08 on 990513-0622.Unidentified RCS Leak Approached TS Limit of 1 Gallon Per Minute Prior to Recently Completed Maint Outage.Three Violations of NRC Requirements Identified & Being Treated as NCVs ML20209G3681999-07-15015 July 1999 Advises That Info Submitted in & 990519 Affidavit Re Design & Licensing Rept,Davis-Besse,Unit 1 Cask Pit Rack Installation Project,Holtec Intl, HI-981933,marked Proprietary,Will Be Withheld from Public Disclosure ML20207H6401999-07-0909 July 1999 Discusses Closure of TAC MA0540 Re Util Responses to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. Staff Has Revised Info in Rvid & Releasing It as Rvid Version 2 ML20209D1341999-07-0808 July 1999 Forwards Notice of Withdrawal of Application for Amend to Operating License.Proposed Change Would Have Modified Facility TSs Pertaining to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves ML20195K2751999-06-16016 June 1999 Forwards Safety Evaluation Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20207G0751999-06-0707 June 1999 Forwards Insp Rept 50-346/99-04 on 990323-0513.Violations Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20207G0621999-06-0404 June 1999 Forwards Insp Rept 50-346/98-21 on 980901-1201 & 990425-0513.Violations Identified & Licensee Being Provided Opportunity to Either Respond to Violations within 30 Days or Inform NRC That LER Rept Already Contain Info Requested ML20207B8161999-05-25025 May 1999 Confirms Discussion Between Members of Staffs to Have Mgt Meeting on 990608 in Oak Harbor,Oh to Discuss Recent Performance at Davis-Besse as Described in Plant Performance Review ML20207B3141999-05-24024 May 1999 Informs That in September 1998,Region III Received Revision 20 to Various Portions of Davis-Besse Nuclear Power Station Emergency Plan.Rev Submitted Under Provisions of 10CFR50.54(q) ML20206T0881999-05-18018 May 1999 Confirms 990517 Telcon Between Lindsey & M Bielby Re Arrangements Made for Administration of Licensing Exam at Facility for Week of 990913 ML20206N5311999-05-11011 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Aj Mendiola Will Be Section Chief for Davis-Besse Npp.Organization Chart Encl ML20206H2291999-05-0707 May 1999 Forwards Proposed Change to Plant,Unit 1,TS Bases Section 2.2.1, Limiting Safety Sys Settings - Reactor Protection Sys Instrumentation Setpoints - Rc Pressure - Low,High & Pressure Temp ML20206B8171999-04-27027 April 1999 Forwards Insp Rept 50-346/99-05 on 990405-09.No Violations Noted.Purpose of Insp Was to Examine on-line Maint Risk Assessment Program Recently Implemented in Response to Maint Work Control Weaknesses ML20205G5681999-03-26026 March 1999 Advises of Completion of Plant Performance Review on 990202 to Develop Integrated Understanding of Safety Performance. Overall Performance of Plant Acceptable.Plant Issues Matrix & Insp Plan Encl ML20207G1701999-03-0505 March 1999 Forwards Insp Rept 50-346/99-01 on 990102-0212.No Violations Noted ML20207D4351999-02-25025 February 1999 Forwards Insp Rept 50-346/99-02 on 990202-05.No Violations Noted.Examples of Deficiencies with Station Procedures, Similar to Those Identified Through Staff self-assessments & in Previous NRC Insps,Were Noted IR 05000346/19960141999-02-17017 February 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-346/96-14 on 970225.Ack That Due to Plant Events,There Has Been Delay in Completion of C/As for Violation 50-346/96-14c ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20206S0811999-01-22022 January 1999 Forwards Insp Rept 50-346/98-18 on 981110-990102.No Violations Identified.Conduct of Activities at Davis-Besse Generally Characterized by Conservative Plant Operations, & Effective Engineering Involvement in Plant Issues ML20199H5821999-01-20020 January 1999 Forwards SE Re Ampacity Derating Issues Due to Application of Thermo-Lag Fire Barrier Matl at Plant ML20198E6821998-12-17017 December 1998 Forwards Insp Rept 50-346/98-20 on 981116-20.No Violations Noted.Implementation of Licensed Operator Requalification Program Was Generally Characterized by Safety Conscious Operations & Sound Evaluation of Operator Performance ML20198C9881998-12-15015 December 1998 Informs That as Part of NRC PRA Implementation Plan, Commission Assigned Two SRAs to Each Regional Ofc.Sras Will Routinely Assess Licensee Event Repts,Plant Event,Insp Findings & EAs from Risk Perspective ML20198B5391998-12-0909 December 1998 Forwards Insp Rept 50-346/98-17 on 980918-1109 & NOV Re Inadequate Maint Work Order Used by Electrician During Removal of Primary Water Storage Tank Temp Indicator ML20196G1621998-12-0303 December 1998 Submits Response to Request for TS Interpretation Re Surveillance Interval Extension Allowances ML20196H4411998-12-0303 December 1998 Confirms Plans to Hold Meeting on 981216 in Lisle,Il,To Discuss Recent Performance at Davis-Besse & Actions Being Implemented by Licensee ML20198B1511998-12-0202 December 1998 Forwards Insp Activity Plan for Next 6 Months & Plant Issues Matrix.Infor Provided to Minimize Resource Impact on Staff & to Allow for Scheduling Conflicts & Personnel Availability to Be Resolved in Advance of Inspector Arrival Onsite ML20196J5111998-12-0101 December 1998 Fowards Year 2000 Readiness Audit Rept,Which Documents Results of NRR Audit Conducted at Facility from 981027-29 ML20196D4371998-11-25025 November 1998 Discusses Concerns Re Announced Asset Transfer Between Firstenergy Corp & Duquesne Light Co ML20196C6491998-11-20020 November 1998 Forwards Insp Rept 50-346/98-19 on 981014-23.No Violations Noted.Inspectors Reviewed Circumstances Surrounding Events Leading Up to & Following Reactor Trip IR 05000346/19983011998-11-0909 November 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-346/98-301OL Issued on 980923.Effectiveness of C/A Will Be Reviewed Following Submittal of Root Cause Investigation Results ML20155J1471998-11-0303 November 1998 Informs That on 981007,NRC Administered GFE Section of Written Operator Licensing Exam to Employees of Facility. Exam Answer Key for Forms a & B,Grading Results & Individual Answer Sheets Encl.Without Encl ML20155B6641998-10-28028 October 1998 Forwards Safety Evaluation Re Request for Reduction in Commitment Changes in QA Program Matl Receipt Insp Process ML20154Q6711998-10-16016 October 1998 Forwards Insp Rept 50-346/98-15 on 980914-18.No Violations Noted.Emergency Preparedness Program Effectively Implemented During 980624 Tornado Event & Station Personnel Responded Well to Event ML20154Q5891998-10-14014 October 1998 Forwards Insp Rept 50-346/98-14 on 980808-0918.No Violations Noted.Online Safety Equipment Outages Were Performed Well & IAW Established Procedures ML20154H0241998-10-0606 October 1998 Discusses Arrangements Made During 980924 Telcon for Insp of Licensed Operator Requalification Program at Davis Besse Nuclear Power Station During Wk of 981116 ML20154D1801998-09-30030 September 1998 Forwards Insp Rept 50-346/98-16 on 980831-0904.No Violations Noted 1999-09-07
[Table view] |
See also: IR 05000346/1988006
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JUl. 6 '1988
Docket No.'50-346
Toledo Edison Company-
' ATTN: Mr., Donald Shelton
Vice-President
Nuclear
Edison Plaza
300 Madison Avenue
Toledo, OH 43652
Gentlemen:
Thank you for your letter dated June 9,1988, informing 'us of the steps you'
have taken to correct the noncompliances which we brought to your attention
in our letter dated April 20, 1988.
With regard to violation 88006-05, we have determined the following:
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1) The sightglass was installed (1977) seven years before the: event witho'ut'
detailed drawings and instructions;
2) No design criteria or design guides were used in the seismic qualification
calculation. Licensee's engineering calculation did not contain
appropriate acceptance criteria which were required by.the 10_CFR-50,'
Appendix B, Criterion V;
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3) At the time of the inspection, design criteria were still being developed
for the sightglass and the safety-related component modifications; and
4) The seismic qualification calculation should have been performed at the
time of installation instead of nine years (1986) later.
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Based on the above, we have concluded that_the violation was not adequately
self identified and the corrective actions taken were neither prompt, effective,
nor complete. Therefore, your request that we retract the , violation is denied.
You are requested to submit a written reply to this letter within thirty (30)
days of the dates of this letter including: (1) corrective action taken and
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the results achieved; (2) corrective action to be taken to avoid further
violations; and (3) the date when full compliance will be achieved.
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Should you have any questions .concerning this' matter, please feel free to -
contact me.
S incerely,-
0,jginal Signed by J.'J. llarricon
J. J. Harrison, Chief--
Engineering Branch'
cc: L. Storz, Plant Manager
cc w/1tr- dtd 6/9/88:
DCD/DCB (RIDS)
Licensing Fee Management Branch
Resident Inspector, Rlll
Harold W. Kohn, Ohio EPA
James W. Harris, State of Ohio
Robert M. Quillin, Ohio
Department of Health
State of Ohio', Public
Utilities Comission
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TOLEDO
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DONALO C. SHELTON
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Docket No. 50-346
License No. NPF-3
Serial No. 1-806
June 9, 1988
Document Control Desk
United States Nuclear Regulatory Commission
Vashington, D. C. 20555
Subject: Response to Inspection Report 88006
Gentlemen:
Toledo Edison has received Inspection Report 08006 (Log No. 1-1783 dated April
20, 1938) and provides the following response. Based on our discussion with
Mr. F. Jablonski on June 1,1988, the response to Inspection Report 88-006 vas
extended to June 10, 1988.
Violation 88006-05:
10CFR50, Appendix B, Criterion V, requires that activities affecting quality
be prescribed by documented instruction, procedures, or dravings and be
accomplished in accordance with these instructions, procedures, or dravings.
Instructions / procedures or dravings shall include appropriate acceptance
criteria for determination that activities have been satisfactorily
accomplished.
Contrary to the above, a review of FCR 78-024 pertaining to the installation
of containment spray pump oil sightglass as.aemblies revealed the following:
a. No design drawings or detailed dravings were used during the installation
of the assemblies,
b. No instructions / procedures vere found for installation and inspection.
c. No design criteria / instructions vere utilized in the scismic qualification
evaluation.
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Dockst Ns. 50-346
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License No. NPF-3
Serial No. 1-806
Page 2
Response:
Acknowledgment Or Denial of the Alleged Violation
Toledo Edison does not believe the issuance of.a Notice of Violation is
varranted for the installation of the containment spray pump oil sightglass
for the following reasons.
Following the June 9, 1985 event, Toledo Edison initiated a System Reviev &
Test Program (SRTP). The SRTP was established to review the history of
systems important to the safe operation of the Davis-Besse Nuclear Power
Station (DBNPS). One of the objectives of the SRTP reviev vas to identify
problems which may impact the ability of those systems to perform the
necessary functions for safe operation of the plant and to propose corrective
actions to resolve those concerns. The Containment Spray (CS) system was one
of the systems revleved under the SRTP.
One of the concerns documented during the review of the Containment Spray
System was thnt no documentation was found that listed the vendor,
qualification, specification or appropriate installation instructions for the
oil level sight glasses added to the pumps in 1977. This concern was
documented, its safety significance determined and corrective action proposed.
Subsequent reviews confirmed there was no safety concern due to the installed
configuration. An engineering calculation, a Facility Chr.nge Request (FCR)
safety evaluation and the NRC inspection each concluded that: the calculated
stresses vere below the allovable stresses; the installation was seismically
qualified; and the sightglasses could perform their intended function during a
seismic event.
Following the June 9, 1985 event, Toledo Edison received and acknowledged
violations relating to programmatic control of modifications to the facility.
In response to those violations and as part of overall improvement efforts,
the processes for the design of modifications, control of vork, and reviews
for changes to safety related systems have been improved. Nuclear Group
Procedure NG-NE-304 requires a safety review and if applicable a safety
evaluation for proposed changes to identified systems, structures and
components important to safe operation. The Containment Spray System is one
of the systems identified in this procedure.
10CFR2 Appendix C, Section V.G.2, Exercise of Discretion, allows the NRC to
refrain from issuing a Notice of Violation for violations meeting the
following criteria
a. (i) NRC has taken significant enforcement action based upon a major
safety event contributing to an extended shutdovn of an operating
reactor or a material licensee (or a work stoppage at a construction
site), or the licensee is forced into an extended shutdown or vork i
stoppage related to generally poor performance over a long period: '
(11) the licensee has developed and is aggressively implementing
during the shutdown a comprehensive program for problem
identification and corrections and (iii) NRC concurrence is needed
by the licensee prior to restart.
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License No. NPF-3 l
Serial No. 1-806
Page 3
b. Non-villful violations are identified by the licensee (as opposed to
the NRC) as the result of its comprehensive program, or the
violations are identified as-a result of an employee allegation to
the licensee. If NRC identifies the violation, the NRC should
determine whether enforcement action is necessary to achieve remedial
action.
c. The violations are based upon activities of the licensee prior to the
events leading to the shutdown, and
d. The non-villful violations would normally not be categorized as
higher than Severity Level III violations under the NRC's Enforcement
Policy.
The sight glass installation meets the criteria set forth in this section. In
keeping with the stated objectives accompanying the revision to this section
of the code (i.e. to encourage prompt corrections of existing violations and
adverse conditions, to deter future violations and adverse conditions, and to
encourage improved performance by the licensee, while at the same time, not
discouraging a licensee's aggressive and comprehensive implementation of a
structured program to identify and correct problems), Toledo Edison urges the
NRC to exercise its authorized discretion to refrain from issuing a violation
in this instance.
Violation 88006-10:
10CFR50, Appendix B, Criterion III, requires that measures be established to
assure that applicable regulatory requirements and the design basis, as
defined in 5 50.2 and as specified in the license application, for those
structures, systems, and components to which this appendix applies are
correctly translated into specifications, drawings, procedures, and
instructions. Design changes, including field changes, shall be subjected to
design control measures commensurate with those applied to the original design
unless the applicant designates another responsible organization.
Contrary to the above, Specifications No. 12501-E-180 vas changed
administrative 1y to include a revised load profile for the station battery
performance test without going through the Facility Change process or applying
appropriate design control.
Response:
peknowledgment or Denial of the Alleged Violation
Toledo Edison acknowledges the alleged violation.
Reason for the Violation
Nuclear Engineering Procedure (NEP)-021, Specifications, controls the
revision, review and approval of design specifications. Generically, once a
change to a specification is identified, it is evaluated by Design Engineering
to determine whether it is a significant change. Depending on the
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I Docket No. 50-346
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License No. NPF-3
Serial No. 1-806
Page 4
significance of the change required, the specification change follows 1 of 2
paths. If the change is determined to be significant, _the specification
undergoes immediate revision and the change is incorporated. When the
specification is revised a formal design review is performed. Changes to
interfacing plant procedures are identified during the formal design review
process.
If the change is determined not to be significant, a Specification Change
Notice (SCN) is issued against the specification. A SCN is a document used to
temporarily modify the specification instead of revising the specification as
described above. SCNs can be used when specification changes, not associated
with physical plant modifications, are identified such as typographical
errors, incorrect index pages or incorrect information. The SCN is attached
to the specification indicating the change to the specification. No formal
design review is required. SCNs issued against a specification are
incorporated into the specification _(by the specification revision process)
when a total of five non-plant modification related SCNs are accumulated or
one year passes. When the specification is revised the design reviev is
performed.
In the case of the ststion battery load profile change, it was determined that
this change could be processed as an editorial ("incorrect information") SCN
(SCN 12501-E-180-01-03). This SCN documented various changes to the load
profile but did not change the battery size or result in a physical change to
the facility. Therefore per NEP-021, no formal design reviews (including
changes to applicable plant procedures) were immediately required for the
issuance of SCN 12501-E-180-01-03.
Corrective Steps Taken And Results Achieved
Subsequent to this NRC inspection, a more detailed review of the battery load
profile was conducted. As a result, Calculation C-EE-002-005, Rev. 0.vas
performed to better define and document the accident scenario to which the
batteries are sized and to incorporate 5th Refueling Outage Modifications I
affecting the DC system. j
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Document Change Request (DCR) 88-0158 and USAR Change Notice (UCN)88-031 vere
issued to incorporate the new load profile into the affected design documents.
This changed the load profile for the Battery Service Test making it the same i
as that in Specification 12501-E-180 On April 16, 1988 the Battery Service l
Test was successfully completed.
Corrective Steps Vhich Vill Be Taken To Avoid Further Violation
Procedure NEP-021 vill be revised to allow the preparation of non-plant
modification related SCNs be used only in conjunction with a Document Change
Request (DCR) per NG-NE-0312, Design Document Updates and NEP-202, Processing
Document Change Request. The DCR is used for "paper work only" design
document changes. The use of the DCR process vill require a design reviev to
ensure interfacing plant procedures are reviewed for changes. Therefore
changes to specifications vill undergo the full design reviev controls imposed
by the FCR/ MOD or DCR process upon their initiation.
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License No. NPF-3
Serial No. 1-806
Page 5
Date When Full Compliance Vill Be Achieved
Full compliance vill be achieved upon issuance of EN-DP-01021 R0 (NEP-021) by
June 20, 1988.
Very truly yours,
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JCS:tlt
cc:fA.'B.: Davis,' Regional Administrator; 4
A. V. DeAgazio, DB-1 Projec t Manager
DB-1 Resident Inspector
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