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MONTHYEARML20138L8321985-10-24024 October 1985 Forwards marked-up Draft SAIC-85/1524-3, Review of Licensee & Applicant Responses to Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, Technical Evaluation Rept Project stage: Draft Approval 1985-10-24
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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for Approval of Quality Assurance Program Changes PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F8371999-10-0808 October 1999 Forwards Insp Rept 50-346/99-10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 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 ML20059A6721990-08-10010 August 1990 Forwards Safety Insp Rept 50-346/90-13 on 900605-30 & 0709. Violation Noted But Not Cited 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 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 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 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 ML20247C3271989-07-19019 July 1989 Advises That 890616 Rev 7 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable 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 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 ML20247J8181989-05-18018 May 1989 Forwards Amend 133 to License NPF-3 & Safety Evaluation. Amend Deletes from License All Remaining Sections of App B 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 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 ML20246E3091989-05-0303 May 1989 Forwards Request for Addl Info Re ATWS Rule (10CFR50.62). Subjs Include Diversity from Existing Reactor Protection Sys & Electrical Independence from Existing Reactor Protection Sys 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
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Ootober 24, 1985 Docket No. 50-346 DISTRIBUTION Docket' File- JPartlow WPaulson NRC~PDR ACRS-10 GEdison Mr. Joe Williams, Jr. L POR RIngram JKramer Vice President, Nuclear ORB #4 Rdg GDick ABournia Toledo Edison Company HThompson ADeAgazio Edison Plaza - Stop 712 OELD Gray File 300 Madison Avenue EJordan EBrach Toledo, Ohio 43652 BGrimes H0rnstein
Dear Mr. Williams:
SUBJECT:
DRAFT TECHNICAL EVALUATION REPORT (TER) 0F RESPONSE TO GENERIC LETTER 83-28, ITEM 1.2 (POST TRIP REVIEW--DATA AND INFORMATION CAPABILITY) DAVIS-BESSE NUCLEAR POWER STATION The staff has completed a preliminary review to assess the completeness and adequacy of the Toledo Edison (TED) response to Generic Letter 83-28, Item
- 1.2. The enclosed TER provides a technical evaluation representing the
! staff's initial judgement of the areas evaluated.
Based on the information submitted by TED, the post trip review data and information capabilities are not adequate in the following areas:
Only a portion of the parameters that should be recorded for post-trip review (Table 1.2-2 of the draft TER) are recorded. Those parameters that are absent are indicated on page 12 of draft TER.
Time history recorders, as described in the submittal, do not meet the I minimum performance characteristics.
l The data retention procedures, as described in the submittal, may not ensure that the information recorded for the post-trip review is maintained in an accessible manner for the life of the plant.
We believe that the outstanding items can be resolved during a conference telephone call. Consequently, we request that the cognizant member (s) of your staff contact Mr. George Dick of my staff within one week of receipt of this letter to arrange for such a call. Mr Dick's telephone number is (301) 492-8174 Sgggrp,1bs n na s. nuw. '
John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing
Enclosure:
As Stated:
cc w/ enclosure:
See next page
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/g3/85 10/g/85 10/J 5 i 8510310420 851024 PDR P ADOCK 05000346 PDR
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Mr. J. Williams Davis-Besse Nuclear Power Station Toledo Edison Company Unit No. I cc: .
Donald H. Hauser, Esq. Ohio Department of Health The Cleveland Electric ATTN: Radiological Health Illuminating Company Program Director P. O. Box 5000 P. O. Box 118 Cleveland, Ohio 44101 Columbus, Ohio 43216 ,
Mr. Robert F. Peters Attorney General Manager, Nuclear Licensing Department of Attorney Toledo Edison Company General Edison Plaza 30 East Br'oad Street 300 Madison Avenue Columbus, Ohio 43215 Toledo, Ohio 43652 _
Gerald Charnoff, Esq. Division of Power Generation Shaw, Pittman, Potts Ohio Department of Industrial Relations and Trowbridge 2323 West'5th Avenue 1800 M Street, N.W. P. O. Box 825 Washington, D.C. 20036 Columbus, Ohio 43216 Paul M. Smart, Esq. Mr. Harold Kohn, Staff Scientist :
Fuller & Henry Power Siting Commission 300 Madison Avenue 361 East Broad Street P. O. Box 2088 Columbus, Ohio 43216 Toledo, Ohio 43603 Mr. Robert B. Borsum President, Boar of Babcock & Wilcox Ottawa County Nuclear Power Generation Port Clinton, Ohio 43452 Division Suite 200, 7910 Woodmont Avenue Bethesda, Maryland 20814 Resident Inspector U.S. Nuclear Regulatory Commission 5503 N. State Route 2 Oak Harbor, Ohio 43449 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinoi:- 60137 emme e , -
SAIC-85/1524-3 REVIEW OF LICENSEE AND APPLICANT RESPONSES TO NRC GENERIC LETTER 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events), Item 1.2
" POST-TRIP REVIEW: DATA AND INFORMATION CAPABILITIES" FOR -
DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 (50-346)
\ . Technical Evaluation Report Prepared by Science Applications International Corporation 1710 Goodridge Drive McLean, Virginia 22102 Prepared for U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Contract No. NRC-03-82-096 l
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FOREWORD This report contains the technical evaluation of the Davis-Besse Nuclear Power Station, Unit I response to Generic Letter 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events), Item 1.2 " Post Trip Review: Data and Information Capabilities."
For the purposes of this evaluation, the review criteria, presented in part 2 of this report, were divided into five separate categories. Th6se are:
- 1. The parameters monitored by the sequence of events and the time history recorders,
- 2. The performance chara_cteristics of the sequence of events recorders,
- 3. The performance characteristics of the time history recorders,
- 4. The data output format, and
- 5. The long-term data retention capability for post-trip review material. :
All available responses to Generic Letter 83-28 were evaluated. The plant for which this report is applicable was found to have adequately responded to, and met, categories 2 and 4.
The report describes the specific methods used to determine the cate-gorization of the responses to Generic Letter 83-28. Since this evaluation report was intended to apply to more than one nuclear power plant specifics regarding how each plant met (or failed to meet) the review criteria are not
- presented. Instead, the evaluation presents a categorization of the responses according to which categories of review criteria are satisfied and which are not. The evaluations are based on specific criteria (Section 2) derived from the requirements as stated in the generic letter.
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TABLE OF CONTENTS Section Page Introduction. . . . . . . . . . . . . . . . . . . . . . . . . I
- 1. Background. . . . . . . . . . . . . . . . . . . . . . . . . . 2
- 2. Review Criteria . . . . . . . . . . . . . . . . . . . . . . . 3
- 3. Evaluation. . . . . . . . ._. . . . . . . . . . . . . . . . . 8
- 4. Conclusion. . . . . . . . . . . . . . . . . . . . . . . . . . 9
- 5. Re fe re n c e s . . . . . . . . . . . . . . . . . . . . . . . . . . 10
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INTRODUCTION SAIC has reviewed the utility's response to Generic Letter 83-28, htem 1.2 " Post-Trip Review: Data and Information Capability." The response (see references) contained sufficient information to determine that the data and information capabilities at these plants are acceptable in the following areas. _
e The sequence-of-events recorder (s) performance charac-teristics.
e The output format of the recorded data.
However, the data and information capabilities, as described in the submittal, either fail to meet the review criteria or provide insufficient information to allow determination of the adequacy of the data and information capabilities in the following areas.
e The parameters monitored by both the sequence-cf-events and time history recorders.
e The time history recorder (s) performance characteris-tics.
e The long-term data retention, record keeping, capa-bility.
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- 1. Backaround l
On February 25, 1984, both of the scram circuit breakers at Unit 1 of. I the Salem Nuclear Power Plant failed to open upon an automatic reactor trip signal from the reactor protection system. This incident occurred during the plant startup and the reactor was tripped manually by the opera. tor a. bout 30 seconds after the initiation of the automatic trip signal. The failure of the circuit breakers has been determined to be related to the sticking of the under voltage trip attachment. Prior to this incident; on February 22, 1983; at Unit 1 of the Salem Nuclear Power Plant an automatic trip signal was generated based on steam generator low-low level during plant startup.
In this case the reactor was tripped manually by the operator almost coinci-1 dentally with the automatic trip. At that time, because the utility did not ,
have a requirement for the systematic evaluation of the reactor trip, no investigation was performed to determine whether the' reactor was tripped automatically as expected or manually. The utilities' written procedures required only that the cause of the trip be determined and identified the responsible personnel that could authorize a restart if the cause of the .
trip is known. Following the second trip which clearly indicated the problem with the trip breakers, the question was raised on whether the circuit breakers had functioned properly during the earlier incident. The most useful source of information in this case, namely the sequence of events printout which would have indicated whether the reactor was tripped automatically or manually during the February 22 incident, was not retained
.after the incident. Thus, no judgment on the proper functioning of the trip system during the earlier incident could be made.
Following these incidents; on February 28, 1983; the NRC Executive Director for Operations (E00), directed the staff to investigate and report on the generic implications of these occurrences at Unit 1 of the Salem Nuclear Power Plant. The results of the staff's inquiry into the generic implications of the Salem Unit incidents is reported in NUREG-1000, " Generic Implications of ATWS Events at the Salem Nuclear Power Plant." Based on the results of this study, a set of required actions were developed and included in Generic Letter 83-28 which was issued on July 8,1983 and sent to all licensees of operating reactors, applicants for operating license, and construction permit holders. The required actions in this generic letter consist of four categories. These are: (1) Post-Trip Review (2) Equipment 2
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l Classification and Vender Interface, (3) Post Maintenance Testing, and (4)
Reactor Trip System Reliability Improvements.
The first required action of the generic letter, Post-Trip Rev'iew, is the subject of this TER and consists of action item 1.1 " Program Description and Procedure" and action item 1.2 " Data and Information Capability." In the next section the review criteria used to assess the adequacy of the ;
- utilities' responses to the requirements of action item 1.2 will be i discussed.
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- 2. Review Criteria 4 The intent of the Post Trip Review requirements of Generic Letter 83-28 is to ensure that the licensee has adequate procedures and data and i
information sources to understand the cause(s) and progression of a reactor j trip. This understanding should go beyond a simple identification of the ,
l course of the event. It should include the capability to determine the root cause of the reactor trip and to determine whether safety limits have been !
- exceeded and if so to what extent. Sufficient information about the reactor trip event should be available so that a decision on the acceptability of a reactor restart can be made.
f The following are the review criteria developed for the requirements of Generic Letter 83-28, action item 1.2:
The equipment that provides the digital sequence of events (SOE) record and the anaiog time history records of an unscheduled shutdown should pro-vide a reliable source of the necessary information to be used in the post trip review. Each plant variable which is necessary to determine the cause(s) and progression of the event (s) following a plant trip should be monitored by at least one recorder [such as a sequence-of-events recorder or i a plant process computer for digital parameters; and strip charts, a plant
- process computer or analog recorder for analog (time history) variables].
Each device used to record an analog or digital plant variable should be described in sufficient detail so that a determination can be made as to whether the following performance characteristics are met:
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e Each sequence-of-events recorder should be capable of detecting and recording the sequence of events with a sufficient time discrimination capability to ensure that the time responses asso-ciated with each monitored safety-related system can be'ascer-tained, and that a determination can be made as to whether the time response is within acceptable limits based on FSAR Chapter 15 Accident Analyses. The recommended guideline for the SOE time discrimination is approximately 100 msec. If current $0E recorders do not have this time discrimination capability the licensee or applicant should show that the current time discrimi-nation capability is sufficient for an adequate reconstruction of the course of the reactor trip. As a minimum this should include the ability to adequatel'y reconstruct the accident scenarios pre-sented in Chapter 15 of the plant FSAR.
e Each analog time history data recorder should have a sample inter-val' small enough so that the incident can be accurately reconstructed following a reactor trip. As a minimum, the ;
licensee or applicant should be able to reconstruct the course of the accident sequences evaluated in the accident analysis of the plant FSAR (Chapter 15). The recommended guideline for the sample interval is 10 sec. If the time history equipment does not meet this guideline, the licensee or applicant should show that the current time history capability is sufficient to accurately recon-struct the accident sequences presented in Chapter 15 of the FSAR.
e To support the post trip analysis of the cause of the trip and the proper functioning of involved safety related equipment, each analog time history data recorder should be capable of updating and retaining information from approximately five minutes prior to the trip until at least ten minutes after the trip.
e The information gathered by the sequence-of-events and time history data collectors should be stored in a manner that will allow for retrieval and analysis. The data may be retained in either hardcopy (computer printout, strip chart output, etc.) or in an accessible memory (magnetic disc or tape). This information should be presented in a readable and meaningful for. mat, taking
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into consideration good human factors practices (such as those outlined in NUREG-0700).
e All equipment used to record sequence of events and time
- history information should be powered from a reliable and non-interruptible power source. The power source used need not be saf ty related. ,
The sequence of events and time history recording equipment should monitor sufficient digital and analog parameters, respectively, to assure that the course of the reactor trip can be reconstructed. The parameters monitored should provide sufficient information to determine the root cause g of the reactor trip, the progression of the reactor trip, and the response of the plant parameters and systems to the reactor trip. Specifically, all '
input parameters associated with reactor trips, safety' injections and other safety-related systems as well as output parameters sufficient to record the '
proper functioning of .these systems should be recorded for use in the post trip review. The parameters deemed necessary, as a minimum, to perform a :
post-trip review (one that would determine if the plant remained within its design envelope) are presented on Tables 1.2-1 and 1.2-2. If the appli-cants' or licensees' SOE record' as and time history recorders do not monitor all of the parameters suggested in these tables the applicant or licensee should show that the existing set of monitored parameters are sufficient to establish that the plant remained within the design envelope' for the appro-priate accident conditions; such as those analyzed in Chapter 15 of the plant Safety Analysis Report.
Information gathered during the post trip review is required input for future post trip reviews. Data from all unscheduled shatdowns provides a valuable reference source for the determination of the acceptability of the plant vital parameter and equipment response to future unscheduled shut-downs. It is therefore necessary that information gathered during all post trip reviews be maintained in an accessible manner for the life of the plant.
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Table 1.2-1. PWR Parameter List SOE Time History ,
Recorder Recorder Parameter / Signal x Reactor Trip (1) x Safety Injection .
x Containment Isolation (1) x Turbine Trip x Control Rod Position.
(1) x x Neutron Flux, Power x x Containment Pressure h (2) Containment Radiation x Containment Sump Level (1) x x Primary System Pressure (1) x x Primary System Temperature (1) x .
Pressurizer Level (1) x Reactor Coolant Pump Status (1) x x Primary System Flow (3) Safety Inj.; Flow, Pump / Valve Status x MSIV Position
- x x Steam Generator Pressure (1) x x Steam Generator Level (1) x x Feedwater Flow (1) x x Steam Flow (3) Auxiliary Feedwater System; Flow.
Pump /Value Status x AC and DC System Status (Bus Voltage) x Diesel Generator Status (Start /Stop,
- On/Of f) x PORV Position
-(1): Trip parameters (2): Parameter may be monitored by either an SOE or time history recorder.
(3): Acceptable recorder options are: (a) system flow recorded on an SOE recorder, (b) system flow recorded on a time history recorder, or (c) equipment status recorded on an SOE recorder.
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Table 1.2-2. BWR Parameter List SOE Time History Recorder Recorder Parameter / Signal -
x Reactor Trip x Safety Injection x Containment Isolation x Turbine Trip x Control Rod Position x (1) x Neutron Flux, Power '
x (1) Main Steam Radiation
's (2) ' Containment (Dry Well) Radiation x (1) x Drywell Pressure (Containment Pressure)
(2) Suppression Pool Temperature x (1) x Primary System Pressure x (1) .x Primary System level x MSIV Position ;
x (1) Turbine Stop Valve / Control Valve Position x Turbine Bypass Valve Position x Feedwater Flow x Steam Flow (3) Recirculation; Flow. Pump Status x (1) Scram Discharge Level x (1) ,
Condenser Vacuum x AC and DC System Status (Bus Voltage)
(3)(4) Safety Injection; Flow. Pump / Valve Status x Diesel Generator Status (On/Off, Start /Stop) 1 (1): Trip parameters.
(2): Parameter may be recorded by either an SOE or time history recorder.
(3): Acceptable recorder options are: (a) system flow recorded on an SOE recorder, (b) system flow recorded on a time history recorder, or (c) equipment status recorded on an SOE recorder.
(4): Includes recording of parameters for all applicable systems from the following: HPCI, LPCI, LPCS, IC, RCIC. --
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- 3. Evaluation The parameters identified in part 2 of this report as a part of the review criteria are those deemed necessary to perform an adequate post-trip review. The recording of these parameters on equipment that meets the guidelines of the review criteria will result in a source of information thct can be used to determine the cause of the reactor trip and the plant rt ?:3nse to the trip, including the responses of important plant systems.
Th? :e.rameters identified in this submittal as being recorded by the sequence of events and time history recorders do not correspond to the parameters specified in part 2 of this report. -
The review criteria require that the equipment being used to record the sequence of events and time history data required for a post-trip review meet certain performance characteristics. These c.haracteristics are intended to ensure that, if the proper parameters are ' recorded, the record-ing equipment will provide en adequate source of information for an effec-tive post-trip review. The information provided in this submittal does not ,
indicate that the time history equipment used would meet the intent of the performance criteria outlined in part 2 of this report. Information supplied in the submittal does indicate that the SOE equipment meets the performance criteria specified in part 2 of this report.
The data and information recorded for use in the post-trip review should be output in a format that allows for ease of identification and use
' of the data to meet the review criterion that calls for information in a readable and meaningful format. The information contained in this submittal indicates that this criterion is met.
The data and information used during a post-trip review should be retained as part of the plant files. This information could prove useful during future post-trip reviews. Therefore, one criterion is that infor-mation used during a post-trip review be maintained in an accessible manner i for the life of the plant. The information contained within this submittal does not indicate that this criterion will be met. ,
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- 4. Conclusion l The information supplied in response to Generic Letter 83-28 indicates i that the current post-trip review data and information capabilities are adequate in the following areas:
- 1. The recorded data is output in a readable and meaningful ' format.
- 2. The sequence of events recorders meet the minimum performance characteristics.
The information supplied in response to Generic Letter 83-28 does not indicate that the post-trip review data and information capabilities are adequate in the following areas:
- 1. Based upon the information contained in the submittal, all of the parameters specified in part 2 of this report that should be recorded for use in a post-trip review are not recorded.
- 2. Time history recorders, as described in the submittal, do not meet the minimum performance characteristics.
- 3. The data retention procedures, as described in the submittal, may not ensure that the information recorded for the post-trip review is maintained in an accessible manner for the life of the plant.
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It is possible that the current data and information capabilities at this nuclear power plant are adequate to meet the intent of these review criteria, but were not completely described. Under these circumstances, the licensee should provide an updated, more complete, description to show in more detail t'he data and information capabilities at this nuclear power plant. If the information provided accurately represents all current data and information capabilities, then the licensee should show that the data and information capabilities meet the intent of the criteria in part 2 of this report, or detail future modifications that would enable the, licensee to meet the intent of the eva'luation criteria.
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Se REFERENCES NRC Generic Letter 83 28. " Letter to all licensees of operating reactors, applicants for operating license, and holders of construction permits regarding Required Actions Based on Generic Implications of Salem ATWS Events." July 8, 1983.
NUREG-1000 Generic Implications of ATWS Events at the Salem Nuclear Power Plant April 1983.
Letter from R.P. Crouse. Toledo Edison, to J.F. Stolz, N:r re 9M23 NRC, of ..ovo40-
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4.199?, Accession Number S2'.1:017" in response to Generic Letter 83-28 of July 8,1983, with attachment PJ ill 502 35
'. Reactor Trip Breaker Shunt Trip Circuit Modification, Davis-Besse, Unit Number 1.
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J O fr# N O ot.u g e,g_,y 47%y Davis-Besse
- 1. Parameters recorded: Unsatisfactory -
See attached table for discrepancies.
- 2. SOE recorders performance characteristics: Satis factory Plant process computer: (2 redundant MODCOMP 7870 CPUs) 5 millisecond time discrimination with a non-interruptible power supply
- 3. Time history recorders performance characteristics: Unsatisfactory Plant process computer: 15 sec sample interval for 15 minutes pre- and post-trip DADS (Data Acquisition and Display System): 1 sec sample interval for a total period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, non-interruptible power supply Analog Alarm printer sample rates of from 1-60 secs (prints value only when setpoint (alarm pt) is exceeded)
(Although DADS meets requirements it does not record all necessary parameters and the process computer is the only device to record some of the required parameters.)
- 4. Data output format: Satisfactory SOE: output includes parameter / event descriptor, pt ID and time Analog: outputs include parameter name and value and time of recording
- 5. Data retention capability: Unsatisfactory Data is ' retained but for an unspecifled period.
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Desirable PWR Parameters for Post-Trip Review (circled parameters are not recorded)
SOE Time History Recorder Recorder Parameter / Signal .
x Reactor Trip (1) x Safety Injection x Containment Isolation -
(1) x Turbine Trip x Control Rod Position '
(1) x x Neutron Flux, Power x x Containment Pressure (2) -
Containment Radiation x Containment Sump Level (1) x x Primary System Pressure (1) x x Primary System Temperature l (1)@ Pressurizer Level (1) x Reactor Coolant Pump Status .
(1) x x Primary System Flow 3 Safety Inj.; Flow. Pump / Valve Status x MSIV Position 8x x Steam Generator Pressure (1) x Steam Generator Level (1) x Feedwater Flow (1) x Steam Flow
! (3) Auxiliary Feedwater System; Flow.
l Pump /Value Status x AC and DC System Status (Bus Voltage) x Diesel Generator Status (Start /Stop,
, On/Off)
@ PORY Position (1): Trip parameters
- (2)
- Parameter may be monitored by either an SOE or time history recorder.
j (3): Acceptable recorder options are: (a) system flow recorded on an SOE recorder (b) system flow recorded on a time history recorder, or (c) equipment status recorded on an SOE recorder. ~
IA L. _ .. _ _ _ .. _ _ .... . _