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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F8231999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of Catawba Nuclear Station.Based on Review,Nrc Did Not Identify Any New Areas That Warranted More than Core Insp Program Over Next Five Months.Historical Listing of Issues,Encl ML20217H0041999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217F1301999-10-0707 October 1999 Forwards Rev 1 to Request for Relief 99-03 from Requirements of ASME B&PV Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting (Vg) Sys ML20212J3011999-10-0101 October 1999 Forwards Exemption from Certain Requirements of 10CFR54.17(c) Re Schedule for Submitting Application for Operating License Renewal.Se Also Encl ML20217K2651999-10-0101 October 1999 Forwards Retake Exams Repts 50-413/99-302 & 50-414/99-302 on 990921-23.Two of Three ROs & One SRO Who Received Administrative Section of Exam Passed Retake Exam, Representing 75 Percent Pass Rate 05000414/LER-1999-004, Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments1999-09-27027 September 1999 Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments 05000413/LER-1999-015, Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept1999-09-27027 September 1999 Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept ML20217A7911999-09-24024 September 1999 Forwards Insp Repts 50-413/99-05 & 50-414/99-05 on 990718- 0828 at Catawba Facility.Nine NCVs Identified Involving Inadequate Corrective Actions Associated with Degraded Svc Water Supply Piping to Auxiliary Feedwater Sys ML20212E6471999-09-24024 September 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for Catawba NPP & 990615.Informs That NRC Reviewed Response for Catawba & Concluded That All Requested Info Provided.Considers GL 98-01 to Be Closed for Catawba ML20212F0941999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals for Cns,Units 1 & 2 ML20212M2001999-09-20020 September 1999 Confirms 990913 Telcon Between M Purser & R Carroll Re Management Meeting to Be Conducted on 991026 in Atlanta,Ga to Discuss Operator Licensing Issues 05000414/LER-1999-005, Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments1999-09-20020 September 1999 Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20212B4641999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for Catawba Nuclear Station,Units 1 & 2 ML20212A4131999-09-14014 September 1999 Informs That TR DPC-NE-2009P Submitted in 990817 Affidavit, Marked Proprietary,Will Be Withheld from Public Disclosure, Pursuant to 10CFR2.709(b) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20212M1931999-09-13013 September 1999 Refers to 990909 Meeting Conducted at Region II Office Re Presentation of Licensee self-assessment of Catawba Nuclear Station Performance.List of Attendees & Licensee Presentation Handout Encl ML20212A3751999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementation Code Case for Duration of Insp Interval ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 05000413/LER-1999-014, Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment1999-09-0101 September 1999 Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment 05000414/LER-1999-003, Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev1999-08-31031 August 1999 Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev 0 of LER ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting 05000413/LER-1999-013, Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER1999-08-25025 August 1999 Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER ML20211M8191999-08-25025 August 1999 Confirms 990825 Telcon Between G Gilbert & R Carroll Re Mgt Meeting to Be Held on 990909 in Atlanta,Ga,To Allow Licensee to Present self-assessment of Catawba Nuclear Station Performance ML20211A9641999-08-20020 August 1999 Forwards SE Authorizing Licensee 990118 Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section XI for Plant,Units 2 ML20211C1191999-08-18018 August 1999 Forwards ISI Rept Unit 1 Catawba 1999 RFO 11, Providing Results of ISI Effort Associated with End of Cycle 11 ML20211B9471999-08-18018 August 1999 Forwards Request for Relief 99-02,associated with Limited Exam Results for Welds Which Were Inspected During Unit 1 End of Cycle 11 RFO ML20211C3651999-08-17017 August 1999 Forwards Rev 25 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program, Which Includes Reformatting of Manual & Addl Changes as Noted in Attached Summary of Changes ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 05000413/LER-1999-011, Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment1999-08-16016 August 1999 Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire ML20210V0321999-08-13013 August 1999 Forwards Insp Repts 50-413/99-04 & 50-414/99-04 on 990606- 0717.Six Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20210S2751999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210Q3751999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date,In Order to Register Individuals for Exam ML20210N9521999-08-0404 August 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual.Documents Constitutes Chapter 16 of Ufsar.With List of Effective Pages IR 05000413/19980131999-08-0202 August 1999 Discusses Integrated Insp Repts 50-413/98-13,50-414/98-13, 50-413/98-16,50-414/98-16 & NRC Special Repts 50/413/99-11 & 50-414/99-11 Conducted Between Aug 1998 & May 1999.Six Violations Occurred,Based on OI Investigation & Insp ML20210M6411999-07-29029 July 1999 Forwards Request for Relief 99-03 from Requirements of ASME Boiler & Pressure Vessel Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting Air (Vg) Sys 05000413/LER-1999-010, Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units1999-07-22022 July 1999 Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units IR 05000413/19990101999-07-22022 July 1999 Discusses Insp Rept 50-413/99-10 & 50-414/99-10 on 990314- 0424 & Forwards Notice of Violation Re Failure to Comply with TS 3.7.13,when Misalignment of Two Electrical Breakers Rendered SSS Inoperable from 981216-29 ML20217G5241999-07-20020 July 1999 Forwards Exam Repts 50-413/99-301 & 50-414/99-301 on 990524- 27,0603,07-10 & 16.Of Fourteen SRO & RO Applicants Who Received Written Exams & Operating Tests,Eight Applicants Passed & Six Failed Exam 05000413/LER-1999-009, Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept1999-07-19019 July 1999 Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept 05000414/LER-1999-001, Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed1999-07-15015 July 1999 Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed ML20209H4431999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for May 1999 on Unit Shutdowns Also Encl ML20210A5771999-07-14014 July 1999 Forwards Revsied Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e),changing Sections 16.7-5,16.8-5,16.9-1,16.9-3,16.9-5 & 16.11-7.Manual Constitute Chapter 16 of UFSAR ML20216D3941999-07-14014 July 1999 Forwards Revs to Catawba Nuclear Station Selected Licensee Commitments Manual NUREG-1431, Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation1999-07-0909 July 1999 Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196L0371999-07-0808 July 1999 Approves Requested Schedule Change of Current two-year Requalification Examinations to non-outage dates.Two-year Cycle Will Start on 991001 & Will End on 020930 05000413/LER-1999-008, Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach1999-07-0808 July 1999 Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach ML20196J9001999-07-0606 July 1999 Informs That 990520 Submittal of Rept DPC-NE-3004-PA,Rev 1, Mass & Energy Release & Containment Response Methodology, Marked Proprietary Will Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 IR 05000413/19990031999-07-0101 July 1999 Discusses Insp Repts 50-413/99-03 & 50-414/99-03 Completed on 990605 & Transmitted by Ltr .Results of Delibrations for Violation Re Discovery of Potentially More Limiting Single Failure Affecting SGTS Analysis Provided 1999-09-08
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058J1251990-11-13013 November 1990 Advises That Re Martin Recently Assigned as Project Manager for Facility ML20058F6161990-10-26026 October 1990 Forwards Insp Repts 50-413/90-28 & 50-414/90-28 on 901001-04.Violation Re Corrective Actions Which Appear to Be Ineffective in Preventing Recurrence of Similar Violation Noted.Enforcement Conference Scheduled for 901105 ML20058F0891990-10-22022 October 1990 Confirms 901031-1102 & 12-16 & 26-30 as Dates for Maint Team Insp of Plant Per 901011 Telcon ML20058B4551990-10-17017 October 1990 Forwards Insp Repts 50-413/90-25 & 50-414/90-25 on 900924-28.No Violations or Deviations Noted ML20062B7051990-10-12012 October 1990 Requests Completion of Analysis of Liquid Samples Spiked W/ Radionuclides within 60 Days of Receipt of Ltr ML20062A0951990-10-0303 October 1990 Forwards Insp Repts 50-413/90-24 & 50-414/90-24 on 900803- 0905 & Notice of Violation ML20059L4141990-09-14014 September 1990 Forwards Insp Repts 50-413/90-23 & 50-414/90-23 on 900730-0803.No Violations or Deviations Noted IR 05000413/19900151990-09-0505 September 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-413/90-15 & 50-414/90-15 ML20059L5241990-09-0505 September 1990 Ack Receipt of 900810 Supplemental Response to Violations Noted in Insp Repts 50-413/90-09 & 50-414/90-09 ML20059H0121990-08-31031 August 1990 Forwards Insp Repts 50-413/90-19 & 50-414/90-19 on 900624- 0802 & Notice of Violation.Util Should Detail Measures to Be Taken to Place Addl Emphasis on Compensatory Actions Program ML20059E3121990-08-30030 August 1990 Advises That Util Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Further NRC Review,If Any,Will Be Performed Either by Insp or Audit ML20059G6171990-08-28028 August 1990 Forwards Insp Repts 50-413/90-20 & 50-414/90-20 on 900724-26.Unresolved Item Identified Re Procedure of Equating self-referral to Employee Assistance Program as First Positive Drug Test ML20056A5571990-08-0202 August 1990 Requests Addl Info Re DPC-NE-2004, Core Thermal-Hydraulic Methodology Using VIPRE-01 for McGuire & Catawba. Requests Response Expeditiously IR 05000413/19900111990-08-0101 August 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-413/90-11 & 50-414/90-11 ML20058P8761990-07-31031 July 1990 Forwards Insp Repts 50-413/90-22 & 50-414/90-22 on 900709-13.No Violations or Deviations Noted ML20055H9131990-07-27027 July 1990 Forwards Safety Evaluation Accepting Actions Taken to Resolve NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes ML20055J2931990-07-23023 July 1990 Forwards Request for Addl Info Re Util 900315 Submittal of General Relief Request for Pumps in Inservice Testing Program.Addl Info Re Certain Areas That Deviate from OM-6, Identified in Encl,Required to Complete NRC Review IR 05000413/19900171990-07-23023 July 1990 Discusses Insp Repts 50-413/90-17 & 50-414/90-17 on 900611- 19 & Forwards Notice of Violation.Insp Included Review of Actions Re 900611 Inadvertent Transfer of Reactor Coolant Water to Refueling Water Storage Tank at Unit 1 ML20056A5071990-07-20020 July 1990 Forwards Insp Repts 50-413/90-15 & 50-414/90-15 on 900527-0623 & Notice of Violation.Violations,Refs Pertinent to Requirements & Elements to Be Included in Response Presented in Encl Notice of Violation ML20055H4191990-07-19019 July 1990 Forwards Insp Repts 50-413/90-21 & 50-414/90-21 on 900627-29.No Violations or Deviations Noted ML20055H4101990-07-18018 July 1990 Forwards Summary of Enforcement Conference on 900712 Re Unit 1 Inadvertent Diversion of Higher Pressure Reactor Coolant Water to Refueling Water Storage Tank on 900611,per Insp Repts 50-413/90-17 & 50-414/90-17.Handouts Also Encl ML20055H5881990-07-13013 July 1990 Forwards Insp Repts 50-413/90-16 & 50-414/90-16 on 900611-15.Violations Noted But Not Cited ML20058M9361990-07-13013 July 1990 Forwards Insp Repts 50-413/90-18 & 50-414/90-18 on 900625-29.No Violations or Deviations Noted ML20055H3601990-07-10010 July 1990 Advises That Reactor Operator & Senior Operator Licensing Exams Scheduled for Wk of 901015.Encl Ref Matls Requested by 900806 ML20055E3711990-07-0909 July 1990 Ack Receipt of Re Payment of Civil Penalties in Amount of $100,000,per NRC ML20055H4411990-07-0202 July 1990 Ack Receipt of 900607 Response to Violations Noted in Insp Repts 50-413/90-09 & 50-414/90-09.Implementation of Corrective Actions Will Be Examined During Future Insp ML20055C9911990-06-27027 June 1990 Confirms Region II Insp of fitness-for-duty Program on 900724-26.Brief Itinerary to Expedite Util Support of Program Encl ML20055C8421990-06-13013 June 1990 Forwards Insp Repts 50-413/90-14 & 50-414/90-14 on 900521-25.No Violations or Deviations Noted ML20059M9241990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248J3891989-10-16016 October 1989 Forwards Insp Repts 50-413/89-28 & 50-414/89-28 on 890911-15.Violations Noted ML20248D2921989-09-28028 September 1989 Discusses Util Response to Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Boundary Components in PWR Plants ML20248B6881989-09-25025 September 1989 Forwards Insp Repts 50-413/89-25 & 50-414/89-25 on 890801-28 & 0912-15.No Notice of Violation Issued for Violations Identified.Enforcement Conference to Discuss Violations Scheduled for 890928 ML20248B0921989-09-22022 September 1989 Confirms Arrangements for Enforcement Conference on 890928 to Discuss Failure to Take Adequate Corrective Action in Response to Failed Surveillance Test on Unit 2 Turbine Driven Auxiliary Feedwater Pump.Items to Discuss Encl IR 05000413/19890021989-09-20020 September 1989 Ack Receipt of Util Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-413/89-02 & 50-414/89-02 IR 05000413/19890161989-09-20020 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-413/89-16 & 50-414/89-16 ML20248B7431989-09-20020 September 1989 Forwards Insp Repts 50-413/89-26 & 50-414/89-26 on 890821-24.No Violations or Deviations Noted.Attention Invited to Unresolved Items Identified IR 05000413/19890091989-09-20020 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-413/89-09 & 50-414/89-09.Extension of Reply Due Date to 891010 for Weaknesses Identified in Insp Approved in 890823 Telcon ML20247G7421989-09-12012 September 1989 Forwards Insp Repts 50-413/89-24 & 50-414/89-24 on 890807-11.No Violations or Deviations Noted ML20246J6491989-08-31031 August 1989 Forwards Order Imposing Civil Penalty in Amount of $75,000, Per Violations Noted in Insp Repts 50-413/88-38 & 50-414/88-38 Re Inoperability of Containment Air Return & Hydrogen Skimmer Sys Due to Electrical Wiring Error IR 05000413/19880381989-08-31031 August 1989 Forwards Order Imposing Civil Penalty in Amount of $75,000, Per Violations Noted in Insp Repts 50-413/88-38 & 50-414/88-38 Re Inoperability of Containment Air Return & Hydrogen Skimmer Sys Due to Electrical Wiring Error IR 05000414/19890191989-08-31031 August 1989 Discusses Insp Rept 50-414/89-19 on 890616-28 & Forwards Notice of Violation.Violation Noted:On 890602,upper-range Pressurizer Transmitter Isolation Valves on Reactor Vessel Level Instrumentation Not Opened Prior to Entering Mode 3 ML20247C5541989-08-30030 August 1989 Advises That 890405 Rev 29 to Crisis Mgt Plan Consistent W/Provisions of 10CFR50.47(b) & Requirements of App E & Acceptable ML20246J9191989-08-29029 August 1989 Requests Addl Info Re Direct Generation Response Spectra & Snubber Reduction Program.Response Requested within 30 Days ML20247A1781989-08-29029 August 1989 Forwards Summary of 890720 & 0815 Enforcement Conferences Re Findings in Insp Repts 50-413/89-19 & 50-414/89-19 on Inoperability of Reactor Vessel Level Instrumentation Sys. List of Attendees & Viewgraphs Also Encl ML20246N1671989-08-28028 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-413/89-17 & 50-414/89-17 ML20246M5061989-08-22022 August 1989 Forwards Insp Repts 50-413/89-22 & 50-414/89-22 on 890723-28.No Violations Noted IR 05000413/19890141989-08-16016 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-413/89-14 & 50-414/89-14 ML20246C7051989-08-14014 August 1989 Forwards Insp Repts 50-413/89-18 & 50-414/89-18 on 890717-21.Violations Noted in Rept But Not Cited ML20245K4051989-08-11011 August 1989 Forwards Insp Repts 50-413/89-20 & 50-414/89-20 on 890717-21.No Violations or Deviations Noted ML20246A7411989-08-0808 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-413/89-13 & 50-414/89-13 1990-09-05
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217F8231999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of Catawba Nuclear Station.Based on Review,Nrc Did Not Identify Any New Areas That Warranted More than Core Insp Program Over Next Five Months.Historical Listing of Issues,Encl ML20217K2651999-10-0101 October 1999 Forwards Retake Exams Repts 50-413/99-302 & 50-414/99-302 on 990921-23.Two of Three ROs & One SRO Who Received Administrative Section of Exam Passed Retake Exam, Representing 75 Percent Pass Rate ML20212J3011999-10-0101 October 1999 Forwards Exemption from Certain Requirements of 10CFR54.17(c) Re Schedule for Submitting Application for Operating License Renewal.Se Also Encl ML20212E6471999-09-24024 September 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for Catawba NPP & 990615.Informs That NRC Reviewed Response for Catawba & Concluded That All Requested Info Provided.Considers GL 98-01 to Be Closed for Catawba ML20217A7911999-09-24024 September 1999 Forwards Insp Repts 50-413/99-05 & 50-414/99-05 on 990718- 0828 at Catawba Facility.Nine NCVs Identified Involving Inadequate Corrective Actions Associated with Degraded Svc Water Supply Piping to Auxiliary Feedwater Sys ML20212F0941999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals for Cns,Units 1 & 2 ML20212M2001999-09-20020 September 1999 Confirms 990913 Telcon Between M Purser & R Carroll Re Management Meeting to Be Conducted on 991026 in Atlanta,Ga to Discuss Operator Licensing Issues ML20212A4131999-09-14014 September 1999 Informs That TR DPC-NE-2009P Submitted in 990817 Affidavit, Marked Proprietary,Will Be Withheld from Public Disclosure, Pursuant to 10CFR2.709(b) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20212M1931999-09-13013 September 1999 Refers to 990909 Meeting Conducted at Region II Office Re Presentation of Licensee self-assessment of Catawba Nuclear Station Performance.List of Attendees & Licensee Presentation Handout Encl ML20212A3751999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementation Code Case for Duration of Insp Interval ML20211M8191999-08-25025 August 1999 Confirms 990825 Telcon Between G Gilbert & R Carroll Re Mgt Meeting to Be Held on 990909 in Atlanta,Ga,To Allow Licensee to Present self-assessment of Catawba Nuclear Station Performance ML20211A9641999-08-20020 August 1999 Forwards SE Authorizing Licensee 990118 Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section XI for Plant,Units 2 ML20210V0321999-08-13013 August 1999 Forwards Insp Repts 50-413/99-04 & 50-414/99-04 on 990606- 0717.Six Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20210Q3751999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date,In Order to Register Individuals for Exam IR 05000413/19980131999-08-0202 August 1999 Discusses Integrated Insp Repts 50-413/98-13,50-414/98-13, 50-413/98-16,50-414/98-16 & NRC Special Repts 50/413/99-11 & 50-414/99-11 Conducted Between Aug 1998 & May 1999.Six Violations Occurred,Based on OI Investigation & Insp IR 05000413/19990101999-07-22022 July 1999 Discusses Insp Rept 50-413/99-10 & 50-414/99-10 on 990314- 0424 & Forwards Notice of Violation Re Failure to Comply with TS 3.7.13,when Misalignment of Two Electrical Breakers Rendered SSS Inoperable from 981216-29 ML20217G5241999-07-20020 July 1999 Forwards Exam Repts 50-413/99-301 & 50-414/99-301 on 990524- 27,0603,07-10 & 16.Of Fourteen SRO & RO Applicants Who Received Written Exams & Operating Tests,Eight Applicants Passed & Six Failed Exam NUREG-1431, Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation1999-07-0909 July 1999 Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196L0371999-07-0808 July 1999 Approves Requested Schedule Change of Current two-year Requalification Examinations to non-outage dates.Two-year Cycle Will Start on 991001 & Will End on 020930 ML20196J9001999-07-0606 July 1999 Informs That 990520 Submittal of Rept DPC-NE-3004-PA,Rev 1, Mass & Energy Release & Containment Response Methodology, Marked Proprietary Will Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 IR 05000413/19990031999-07-0101 July 1999 Discusses Insp Repts 50-413/99-03 & 50-414/99-03 Completed on 990605 & Transmitted by Ltr .Results of Delibrations for Violation Re Discovery of Potentially More Limiting Single Failure Affecting SGTS Analysis Provided ML20209E2701999-07-0101 July 1999 Forwards Insp Repts 50-413/99-03 & 50-414/99-03 on 990425- 0605.Six Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20209E3931999-06-28028 June 1999 Informs of 990618 Meeting Conducted at Facility to Present Results of Most Recent Periodic Plant Performance Review for Plant.List of Attendees Encl ML20196G8861999-06-24024 June 1999 Discusses GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structrual Integrity 950816 & 960729 Responses.Rvid,Version 2 Released as Result of Review.Rvid Should Be Reviewed & Comments Should Be Received by 990901 If Not Acceptable for Plant ML20196G6541999-06-17017 June 1999 Confirms 990614 Telephone Conversation Re Rescheduling of Two Predecisional Enforcement Conferences Originally Scheduled for 990623.SSS Conference Rescheduled for 990712 & Ice Condenser Conference Rescheduled for 990720 ML20196A5781999-06-14014 June 1999 Discusses Notice of Enforcement Discretion for Duke Energy Corp Re Catawba Nuclear Station Unit 1 TSs 3.5.2 & 3.7.12 ML20195E9171999-06-0303 June 1999 Confirms Conversation with Bradshaw on 990526 Re Rescheduling 990607 Predecisional Enforcement Conference to Discuss Apparent Violation in Insp Repts 50-413/99-10 & 50-414/99-10.Conference Will Be on 990623 in Atlanta,Ga ML20195F4141999-06-0202 June 1999 Forwards Insp Repts 50-413/99-11 & 50-414/99-11 on 990422-23 & 0503.Apparent Violation Identified & Being Considered for Escalated Enforcement Action.Violation Involved Failure to Maintain Unit 1 Ice Condenser Lower Inlet Door Operable ML20207D0671999-05-20020 May 1999 Informs That During Meeting on 990512,arrangements Modified for Administration of Licensing Exams at Catawba Nuclear Station During Weeks of 990524 & 0607,respectively ML20207C8721999-05-20020 May 1999 Forwards Insp Repts 50-413/99-02 & 50-414/99-02 on 990314-0424.Three Violations Occurred & Being Treated as non-cited Violations.Activities Generally Characterized by Safety Conscious Operations & Sound Engineering & Maint ML20207C8061999-05-19019 May 1999 Confirms 990510 Telcon with R Jones Re Predecisional Enforcement Conference Requested by NRC & Scheduled for 990607 in Atlanta,Ga to Discuss Apparent Violation Associated with Potential Inoperability of SSS ML20207C7761999-05-19019 May 1999 Informs That on 990618,NRC Will Meet with Mgt of Duke Energy Corp to Discuss Performance of Catawba Facility & Extends Invitation to Attend Meeting as Observer ML20206P4911999-05-14014 May 1999 Forwards Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20206M4201999-05-11011 May 1999 Informs That NRC Ofc of Nuclear Regulation (NRR) Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt (DLPM) Created.Reorganization Chart Encl ML20206U4091999-05-10010 May 1999 Forwards Insp Repts 50-413/99-10 & 50-414/99-10 on 990314-0424.One Violation Occurred & Being Considered for Escalated Enforcement Action Involving Inoperability of Standby Shutdown Sys from 981216-29 ML20206N4191999-05-0606 May 1999 Informs That Team Will Inspect Dam at Standby Nuclear Service Water Pond on 990609.Purpose of Insp Will Be to Confirm That Structure Conforms with Design Documents & Capability of Performing Design Functions ML20205S5491999-04-21021 April 1999 Forwards SE Discussing DPC Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions. Response Acceptable ML20206B7941999-04-16016 April 1999 Confirms 990331 Telcon Between M Purser of Util & R Franovich of NRC Re Public Meeting Scheduled for 990618 in York,Sc to Discuss Results of NRC Recent Plant Performance Review for Catawba Nuclear Station ML20205N3471999-04-12012 April 1999 Forwards Safety Evaluation & Eri/Nrc 95-506, Technical Evaluation Rept on Submittal Only Review of IPE of External Events at Catawba Nuclear Station,Units 1 & 2 ML20205T3491999-04-0909 April 1999 Informs That on 990317,T Beedle & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Catawba Nuclear Station for Y2K.No Y2K Exam Scheduled.Initial Exam Requested for Apr 2001 for Approx 18 Candidates ML20205N0531999-04-0606 April 1999 Forwards Insp Repts 50-413/99-01 & 50-414/99-01 on 990124-0313.DPC Conduct of Activities at Catawba Facility Generally Characterized by Safety Conscious Operations & Sound Engineering.Five Violations Noted & Treated as NCVs ML20196K9961999-03-30030 March 1999 Forwards Synopsis of NRC OI Completed Rept Re Alleged Compromise of Initial Licensed Operator Exam at Cns.Oi Did Not Substantiate Allegation That Initial Operator Exam Compromised.Plans No Further Action Re Matter ML20205M2651999-03-25025 March 1999 Discusses PPR Completed 990201.Advises of Planned Insp Effort Resulting from Catawba PPR Review.Forwards Plant Issues Matrix & Insp Plan ML20207L7741999-03-15015 March 1999 Requests That NRC Exercise Discretion Not to Enforce Compliance with Actions Required by Plant,Units 1 & 2 Re TS Limiting Conditions for Operation 3.3.7 & 3.3.8 ML20207M9091999-03-0505 March 1999 Informs That Info Submitted by Application, Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20207A5821999-02-17017 February 1999 Forwards Insp Repts 50-413/98-12 & 50-414/98-12 & Notice of Violation.One Violation Being Considered for Escalated Enforcement Action ML20203G5161999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Listing of Candidates for Exam ML20203A2421999-02-0505 February 1999 Forwards SE Accepting Proposal to Revise Methodology in TR DPC-NE-3002-A,to Permit Use of single-node Model,Instead of multi-node Model,To Represent SG Secondary Sys for post-trip Phase of Loss of Normal Feedwater Analysis for Plant,Unit 2 ML20202J4751999-01-29029 January 1999 Responds to Concern Raised on 981020 Re Appropriateness of Interaction of NRC Headquarters Operations Officer with on-shift Operations Staff During Event ML20202C2511999-01-27027 January 1999 Forwards Request for Addl Info Re Util 980331 Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, for Catawba Nuclear Station. Response Requested within 60 Days of Date of Ltr 1999-09-24
[Table view] |
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y1 o UNITED STATES
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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 g ....+ ,/ May 16, 1985 vDocket:Nos:: 150-4137 eTand { 502414[
Mr. H. B. Tucker, Vice President Nuclear Production Department Duke Power Company 422 South Church Street Charlotte, North Carolina 28242
Dear Mr. Tucker:
SUBJECT:
DRAFT TECHNICAL EVALUATION REPORT (TER) FOR SALEM ATWS ITEM 1.2 (GENERIC LETTER 83-28)
Re: Catawba Nuclear. Station, Unit 1 The staff has completed a preliminary review to assess the completeness and adequacy of licensee responses to Generic Letter 83-28 Item 1.2. For the Catawba Nuclear Station Unit 1, your response was found to be incomplete in three of the areas evaluated.
The enclosed TER provides a technical evaluation representing the staff's initial judgment of the areas evaluated. Pen anc ink changes have been made to the TER by your project manager to make the wording consistent with our approach.
In order to preserve our present review schedul_e, we would appreciate your cooperation in obtaining additional information that will permit us to complete our review. It would appear that the needed information on your facility could be obtained by telephone conference within one week of your receipt of the DRAFT TER. Your project manager will be working with you to arrange an acceptable time to conduct the necessary conference calls.
2 Sincerely.
A RL k
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- Ii p Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Enclosure:
DRAFT TER on Salem ATWS Item 1.2 DESIGN TED ORIGIN.ti, cc w/ enclosure: Certified By JM [( h% g See next page [/
8505310190 850516 PDR- ADOCK 05000413 P pg
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4 ENCLOSURE 1 SAIC-85/1516-1 REVIEW OF LICENSEE AND APPLICANT RESPONSES TO NRC GENERIC LETTER 83-28 t
(Required Actions Based on Generic Implications of Salem ATWS Events), Item 1.2
" POST-TRIP REVIEW: DATA AND INFORMATION CAPABILITIES" FOR CATAWBA NUCLEAR STATION, UNIT 1 (50-413 )
i Technical Evaluation Report
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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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e -se , j-4 FOREWORD This report contains the technical evaluation of the Catawba Nuclear Station Unit I response to Generic Letter 83-28 (Required Actions Based Review: onData Generic Implications of Salem ATWS Events). Item 1.2 " Post Trip and Information Capabilities."
For the purposes of this evaluation, the review criteria, presented in part are: 2 of this report, were divided into five separate categories. These 1.
The paremeters monitored by the sequence of events and the time history recorders, 2.
The performance characteristics of the sequence of events recorders, 3.
The performance characteristics of the time history recorders,
- 4. The data output fonnat, and S.
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 3.
(4VittJ C/l btri A-The report describes the specific methods used to dete gorization of the responses to Generic Letter 83-28. Sint thisine the cate-evaluation report was intended to apply to more than one nuclear pow plant s regarding how each plant met (or failed to meet) the :, '-----':pecifics presented. are not Instead, 'the evaluation presents a categorization of the responses which are not.
according to which categories of :, 'm:C are satisfied and The evaluations are based on spe ific criteria (Section 2) derived from the requirements as stated in the g eric letter.
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TABLE OF CONTENTS Section Page Introduction. . . . . . . . . . . . . . . . . . . . . . . . . I
- 1. Background. . . . . . . . . . . . . . . . . . . . . . . . . . 2
- 2. Review Criteria . . . . . . . . . . . . . . . . . . . . . . . 3
- 3. Evaluation. . . . . . . . . . . . . . . . . . . . . . . . . . 8
- 4. Conclusi..). ......................... 8
- 5. Re fe re nc e s . . . . . . . . . . . . . . . . . . . . . . . . . . 10 (o . $pread2xV pocHMenT Pod. MCOM - ~ - ~
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INTRODUCTION git),'J SAIC has reviewed the,subetttals prepared in response to Generic Letter 83-28, item 1.2 " Post-Trip Review: Data and Information Capability" The submittat (see references) contained sufficient information to determine that the data and information capabilities at.this plant are acceptable in the following areas.
e The sequence-of-events recorder (s) performance charac-teristics.
e The time history recorder (s) performance characteris- ,
tics.
However, the data and information capacilities, 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, i
j e The parameters monitored by both the sequence-of-events i and time history recorders.
e The output format of the recorded data, o The long-term data retention, record keeping, capa--
bility.
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- 1. Background On February 25, 1984, both of the scram circuit breakers at Un{t 1 of the Salem Nuclear Pow' e r Plant failed to open upon an automatic reactor trip signal from the reactor protection system. This incident occurred during j the plant startup and the reactor was tripped manually by the operator about 4 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-dentally with the automatic trip. At that time, because the utility did not have a requirement for the systematic evaluation of the reat ~ or 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 4
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 4
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 (EDO), 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 Implic tions of ATWS Events at the Salen Nuclear Power Plant." Based on the results of this study, a set of required actions were developed and included l 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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Classification and Vender Interface. (3) Post Maintenance Testing, and (4) l Reactor Trip System Reliability Improvements.
The first required action of the generic letter, Post-Trip Revihw, 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 discussed.
- 2. Review Criteria l The intent of the Post Trip Review requirements of Generic Letter 83-28 l
1s to ensure that the licensee has adequge procedures and data and information sources to understand the caust and progression of a reactor trip. This understanding should go beyond a simple identification of the 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 i
reactor restart can be made.
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 analog time history records of an unscheduled shutdown should pro-v'ide 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 buch as a sequence-of-events recorder or a plant process computer for digital parameters; and strip charts, a plant process computer or analog recorder for analog (time history) variables}
Ea.ch 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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t 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 ressionses. 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 SSAR Chapter 15 Accident Analyses. The
, recommended guideline for the SOE time discrimination is approxi-mately 100 usec. If current SOE recorders do not have this time discrimination capability the licensee or applicant should show that the current time discrimination capability is sufficient for an adequate reconstruction of the course of the reactor trip. As a minimum this should include the ability to adequately recon-struct the accident scenarios presented in Chapter 15 of the plant FSAR.
o Each analog time history data recorder should have a sample inter-val small enough so that the incident can be accurately 3 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 snould 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 maaner 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 il
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.9 information should be. presented in a readable and meaningful format, taking into consideration good human factors, practices (such as those outlined in NUREG-0700).
s 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 safety 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 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 licElsees' SOE recorders 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 remaine,d within the design envelope for the appro-i priate accident conditions; such as those analyzed in Chapter 15 of the plant Safety Analysis Report.
I Information gathered during the post trip review is required input for future post trip reviews. Data from all unscheduled shutdowns provides a valuable reference source for the determination of the acceptability of the plant vital parameter and equipment response to future unscheduled shut--
I 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 (I) 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 K Containment Pressure (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/0ff) x PORY 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 (2) Containment (DryWell) 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 I
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): 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 revice 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 that can be used to determine the cause of the reactor trip and the plant response to the trip, including the responses of important plant systems.
The parameters 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 information provided in the submittal indicates that the equipment used to monitor the digital and analog parameters meets the. minimal requirements set forth in part 2 of this report. The sequence of events and analog time history recorders are powered from a non-interruptable power supply. The monitoring characteristics are all within the guidelines of the review criteria.
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 does not indicate that this requirement is set. .i .
(r LCf rton The data and information used during a post-trip review should be retained as part of the plant files. This information ould prove useful during future post-trip reviews. Therefore one n;M, xxt presented in part 2 of this report is that information used during a post-trip review be maintained in an accessible manner for the life of the plant. Information contained within this submittal does not indicate that this criterion will be met.
- 4. Conclusion -
The information supplied in response to Generic Letter 83-28 indicates l that the current post-trip review data and information capabilities are adequate in the following areas:
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- 1. The SOE recorders meet the minimum performance characteristics.
- 2. The time history recorders meet the minimum performance" char.acter-1stics.
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. As described in the submittal, sufficient analog and digital parameters are not recorded for use in the post-trip review.
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- 2. As described in the submittal, the recorded data may not be output in a readable and meaningful format.
- 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.
It is possible that the current data and information capabilities at thig #
nuclear power plant are adequate to meet the intent of these #, '
but were not completely described. Under these circumstances, the licensee should provid? an updated, more complete, description to show in more detail the data and information capabilities at this nuclear power plant. If the information provided accurately represents all current data and information capabilties, then the licensee should either show that the present data and information capabilities meet the intent of the criteria in part 2 of this r'eport, or detail future modifications that would enable the licensee to meet the intent of the evaluation criteria.
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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 Sales Nuclear Power Plant, April 1983.
Letter from H.8. Tucker, Duke' Power Company, to D.G. Eisenhut, NRC, dated November 4,1983 Accession Number 8311150312 in response to Generic Letter 83-28 of July 8,1983, with untitled attachment.
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- 1. Parameters recorded: Unsatisfactory See attached table for discrepancies.
- 2. SOE recorders performance characteristics: Satisfactory Sequence of Events Recorder: Ims time discrimination with a non-interruptible power supply An alarm typer is also used.
- 3. Time history recorders performance characteristics: Satisfactory
, Plant process computer: sampling rate of I sec for the period from 10 minutes before to 30 minutes after the trip with a non-1 interruptible power supply
- 4. Data output format: Unsatisfactory SOE data output includes time of event and data input point (sensor ID)
Analog data output includes time, parameter name ar.d value, and sensor ID
- 5. Data retention capability: Unsatisfactory Data is retained but for an unspecified period of time.
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": ;h. 2 PWR Parameters for Post Trip Review (circled parameters are not recorded)
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SOE Time History
- Recorder Recorder Parameter / -Signal x Reactor Trip (1) x Safety Injection
@ Containment Isolation (1) Turbine Trip Control Rod Position (1) x Neutron Flux, Power h Containment Pressure (2) Containment Radiation
@ Containment Sump Level (1)@ Primary System Pressure (Vessel Pressure, PressurizerPressure)
(1) x x Primary System Temperature (1) x Pressurizer Level (1) Reactor Coolant Pump Status (1) x Primary System Flow Safety Inj.; Flow. Pump / Valve Stt.ius MSIV Position x Steam Generator Pressure (1) x Steam Generator Level (1) x Feedwater Flow (1) x Steam Flow (4) Auxiliary Feedwater System; Flow.
Pump /Value Status x AC and DC System Status x Diesel Generator Status
@ PORY Position (1): Trip parameters; pressurizer or primary pressure is a trip parameter (depending on plant).
(2): Parameter may be monitored by either an SOE or time history recorder.
(3): Acceptable recorder options are: (a) reactor vessel pressure recorded on both an SOE and time history recorder, or (b) pressurizer pressure recorded on both an SOE and time history recorder.
(4): Acceptable recorder options are: (a) system flow recorded on an SOE recorder (b) system flow recorded on a time history recorder, or (c) equipmer.t status recorded on an SOE recorder.
Ih
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