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| , Euclear l'rw!urtwn llept. nce l*resulent l'D flox 10n7 Nuclear Operatwin Charintre N C .? Col 1007 (70 tat:i;tGI i DUKEPOWER Dece.aber'19, 1990 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Subj ect: Catawba Nuclear Station, Units 1 and 2 , | | , Euclear l'rw!urtwn llept. nce l*resulent l'D flox 10n7 Nuclear Operatwin Charintre N C .? Col 1007 (70 tat:i;tGI i DUKEPOWER Dece.aber'19, 1990 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Subj ect: Catawba Nuclear Station, Units 1 and 2 , |
| Docket Nos. 50-413 and 50-414 l NRC Inspection Report No. 50-413, 414/89-09 l Inspector Follow-up Items Request for Commitment Date Extension Gentlemen: | | Docket Nos. 50-413 and 50-414 l NRC Inspection Report No. 50-413, 414/89-09 l Inspector Follow-up Items Request for Commitment Date Extension Gentlemen: |
| Inspection Report 50-413, 414/89-09 identified several Inspector Follow-up Items (IFI) involving weaknesses in the maintanance of plant emergency and abnormal procedures. Mr. H. B. Tucker's letter dated October 10, 1989 provided our reply to these items. Attached are revised responses to specified Inspector Follow-up Items in Inspection Report 89-09. | | Inspection Report 50-413, 414/89-09 identified several Inspector Follow-up Items (IFI) involving weaknesses in the maintanance of plant emergency and abnormal procedures. Mr. H. B. Tucker's {{letter dated|date=October 10, 1989|text=letter dated October 10, 1989}} provided our reply to these items. Attached are revised responses to specified Inspector Follow-up Items in Inspection Report 89-09. |
| 'A full review and reissue of the emergency and abnormal procedures was to be completed on December 31, 1990. Due to reductions in available resources and the interjection of other required work activities, the review and reissue process will take another five months to complete. | | 'A full review and reissue of the emergency and abnormal procedures was to be completed on December 31, 1990. Due to reductions in available resources and the interjection of other required work activities, the review and reissue process will take another five months to complete. |
| .The weakness involving labeling of the steam generator steam pressure meters has not been fully resolved due to a relabeling error that will require correction during the next refueling outage. | | .The weakness involving labeling of the steam generator steam pressure meters has not been fully resolved due to a relabeling error that will require correction during the next refueling outage. |
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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:INCOMING CORRESPONDENCE
MONTHYEARML20217H0041999-10-13013 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 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 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 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 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 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 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 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 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 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 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 ML20216D3941999-07-14014 July 1999 Forwards Revs to Catawba Nuclear Station Selected Licensee Commitments Manual 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 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 ML20196G7461999-06-22022 June 1999 Requests Exemption from Requirements of 10CFR54.17(c) That Application for Renewed Operating License Not Be Submitted to NRC Earlier than 20 Yrs Before Expiration of Operating License Currently in Effect ML20196E9541999-06-18018 June 1999 Forwards SG Tube Insp Conducted During Unit 1 End of Cycle 11 Refueling Outage.Attachments 1,2,3 & 4 Identify Tubes with Imperfections in SGs A,B,C & D,Respectively ML20195K4571999-06-14014 June 1999 Forwards MORs for May 1999 & Revised MORs for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20195J1691999-06-10010 June 1999 Forwards Written Documentation of Background & Technical Info Supporting Catawba Unit 1,notice of Enforcement Discretion Request Re TS 3.5.2 (ECCS-Operating),TS 3.7.12 (Auxiliary Bldg Filtered Ventilation Exhaust Sys) ML20217G5771999-06-0909 June 1999 Forwards Post Exam Comments & Supporting Reference Matls for Written Exams Administered at Catawba Nuclear Station on 990603 05000414/LER-1999-002, Forwards Abstract of LER 99-002-00 Re Forced Shutdown of Plant as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Final LER Will Be Submitted No Later than 9907081999-06-0303 June 1999 Forwards Abstract of LER 99-002-00 Re Forced Shutdown of Plant as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Final LER Will Be Submitted No Later than 990708 ML20207F2381999-06-0101 June 1999 Forwards Copy of Catawba Nuclear Station Units 1 & 2 1998 10CFR50.59 Rept, for NRC Files ML20195J1131999-05-26026 May 1999 Requests Approval to Change Cycle Dates for Two Year Requalification Training Program Required by 10CFR55.59,to Improve Scheduling of Requalification Exams to non-outage Periods 05000413/LER-1999-007, Forwards LER 99-007-00,re Operation Prohibited by TS 3.4.7. Commitments Identified in LER Are Listed in Planned Corrective Actions Section1999-05-26026 May 1999 Forwards LER 99-007-00,re Operation Prohibited by TS 3.4.7. Commitments Identified in LER Are Listed in Planned Corrective Actions Section ML20195B4751999-05-24024 May 1999 Forwards Rev 7 to UFSAR Chapter 2 & Chapter 3 from 1998 UFSAR for Catawba Nuclear Station.List of Instructions on Insertion Encl ML20196L1851999-05-20020 May 1999 Forwards Proprietary & non-proprietary Version of Rev 1 to TR DPC-NE-3004, Mass & Energy Release & Containment Response Methodology, Consisting of Finer Nodalization of Ice Condenser Region.Proprietary Info Withheld ML20196L1791999-05-20020 May 1999 Communicates Util Licensing Position Re Inoperable Snubbers. Licensee Has Determined That Structure of ITS Has Resulted in Certain Confusion Re Treatment of Inoperable Snubbers 05000413/LER-1997-009, Forwards LER 97-009-02, Unanalyzed Postulated Single Failure Affecting SG Tube Rupture Analysis, Suppl Revises Planned C/A Described in Suppl 1 to Ler.Current Status of C/As & Addl C/As Planned,Provided in Rept1999-05-17017 May 1999 Forwards LER 97-009-02, Unanalyzed Postulated Single Failure Affecting SG Tube Rupture Analysis, Suppl Revises Planned C/A Described in Suppl 1 to Ler.Current Status of C/As & Addl C/As Planned,Provided in Rept ML20206T4481999-05-13013 May 1999 Forwards Rev 3 to Topical Rept DPC-NE-3002-A, UFSAR Chapter 15 Sys Transient Analysis Methodology, IAW Guidance Contained in NUREG-0390 ML20206R1721999-05-13013 May 1999 Forwards Monthly Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 & Revised Monthly Operating Repts for Mar 1999 ML20206T0281999-05-12012 May 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual. Document Constitutes Chapter 16 of UFSAR 05000413/LER-1999-006, Forwards LER 99-006-00,re CR Ventilation Sys Inoperability. Root Cause & Corrective Actions for Occurence Are Being Finalized & Will Be Reported in Supplement Rept on 9906071999-05-10010 May 1999 Forwards LER 99-006-00,re CR Ventilation Sys Inoperability. Root Cause & Corrective Actions for Occurence Are Being Finalized & Will Be Reported in Supplement Rept on 990607 ML20206N8201999-05-10010 May 1999 Forwards Revs 15 & 16 to Catawba Unit 1 Cycle 12 COLR, Per TS 5.6.5.Rev 15 Updates Limits for New Catawba 1 Cycle 12 Reload Core & Rev 16 Revises Values Re Min Boron Concentrations for Rwst,Cla & SFP ML20206J4431999-05-0303 May 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e).Document Constitutes Chapter 16 of UFSAR ML20206D2141999-04-29029 April 1999 Forwards 1998 Annual Radioactive Effluent Release Rept for Catawba Nuclear Station,Units 1 & 2, Per Plant TS 5.6.3. Rept Contains Listed Documents ML20206E4101999-04-26026 April 1999 Forwards Four Copies of Rev 9 Todpc Nuclear Security & Contingency Plan,Per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 1999-09-08
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II: I lluke hm et Company MS llaves
, Euclear l'rw!urtwn llept. nce l*resulent l'D flox 10n7 Nuclear Operatwin Charintre N C .? Col 1007 (70 tat:i;tGI i DUKEPOWER Dece.aber'19, 1990 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Subj ect: Catawba Nuclear Station, Units 1 and 2 ,
Docket Nos. 50-413 and 50-414 l NRC Inspection Report No. 50-413, 414/89-09 l Inspector Follow-up Items Request for Commitment Date Extension Gentlemen:
Inspection Report 50-413, 414/89-09 identified several Inspector Follow-up Items (IFI) involving weaknesses in the maintanance of plant emergency and abnormal procedures. Mr. H. B. Tucker's letter dated October 10, 1989 provided our reply to these items. Attached are revised responses to specified Inspector Follow-up Items in Inspection Report 89-09.
'A full review and reissue of the emergency and abnormal procedures was to be completed on December 31, 1990. Due to reductions in available resources and the interjection of other required work activities, the review and reissue process will take another five months to complete.
.The weakness involving labeling of the steam generator steam pressure meters has not been fully resolved due to a relabeling error that will require correction during the next refueling outage.
Portions of the Inspector Follow-up Items have been completed. All IFI weaknesses related to the EP/AP Writer's Guide have been addressed in the reissue of this document on May 31, 1990. With the exception of one meter ~(ISMP-5160, S/G iC SM Press), all Control Room steam generator steam pressure gauges were. relabeled during respective unit refueling outages to show the proper red range markings.
An extension of the commitment date to the end of U1E0CS, (currently scheduled for June 1991), is requested.
Very truly yours, G b /h, l M. S. Tuckman, Vice President Nuclear Operations l
WRC/207/lcs p j
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Wf' PDR ADOCK 05000413 [/ l Q PDR ,
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. U. S,. Nuclear Regulatory Commission December 19, 1990 Page 2 l
xc: Mr. Stewart D. Ebneter Regional Administrator, Region 11 U. S. Nuclear Regulatory Commission 101 Marietta St., NW., Suite 2900 Atlanta. Georgia 30323 Mr. W. T. Orders NRC Resident Inspector Catawba Nuclear Station
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1 PUr.E POWER COMPANY i REPI.Y TO A WEAKNESS (IFI) !
iG-413,414/89-09-11 ;
1 There are many sign 2ficant deviations between the EOPs and l the PSTG (Plant Specific Technical Guidelines) where there should be none. This is primarily due to changes being made in the EOPs before being made in the guidance document (PSTG). (Paragraph 3 and Appendix B).
RESPONSE
- 1. Corrective Action Taken and Results Achieved A plan has been agreed upon between the Safety Analysis section and the station Document Development section to review all the comments in Appendix B listed as PSTG Deviatione. The result of this review will be a change to either document so that the difference in guidance is eliminated. Technical Verification of the EOPs, a required step in the Verification and Validation program, will serve as the process by which this plan will be implemented. The Safety Analysis section performs the Technical Verification process.
All of the identified deficjercies wil4 be corrected through this review process oy the end of U1EOC5.
- 2. Corrective Action to be Taken to 7 void Further Incidents The Technical Verification prccc. is designed to provide a means by which changes r ade to the EOPs are verified to be technically correU;. Verification of j t.echnical correctness may lead to a modification of the PSTG, with appropriate justification, or a rejection of the EOP change as written. This process provides a functional means to ensure the EOPs accurately and
! consistently reflect the guidance in PSTG. Sufficient resources and timely efforts will be committed to this i
process to avoid future inconsistencies between EOPs and PSTG.
l 3. Date of Full Compliance l
Duke Power will be in full compliance by the end of U1EOC5.
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DUKE POWER COMPANY REPLY TO A WEAKNESS (IFI) 50-413,414/89-09-12 Many technical and human factor discrepancias were identified in the EOPs. Each one is l' (Paragraph 3.b i l and Appendix B). )
RESPONSE
- 1. Corrective Action Taken and Results Achieved A. A formal process for the inclusion or dismissal of 4
the items listed in Appendix B into +he EOPs has been planned, but not implemented. Consideration will-be given to each item based on the benefit realized to make the procedure mcto user friendly ;
or technically correct. To ensure those items deemed beneficial are incorporated into ' he procedure properly and consistently, the actual rewrite of the EOPs will follow the publishing of the revised EP/AP Writer's Guide.
B. AOPs are currently under revision to upgrade them to the current standard for EOPs. The AOP revision.took priority over the EOPs based on the .i request of. licensed operators and the inspection team's recommendation. Complete revision of the AOPs to address the items identified by the inspection team will be accomplished after the publishing of the revised EP/AP Writer's Guide.
C. Discrepancies between PSTG and EOPs will be l resolved in the process of Technical Verification of EOPs during the revision to address inspe'ction team concerns.
'2 . Corrective Action to-be Taken to Avoid Further Incidents ,
A. Revising of.the EP/AP Writer's Guide will
-establish a new standard for future EOP/ AOP-development. The methods for maintaining the standard are already. established and well documented ~by the Verification.and Validation (V&V) proces;es as described in Operations ~
Management" Procedures.
B. AOPs, which were not formally subjected to the V&V process in previous revisiens, will be scrutinized under V&V criteria in subsequent revisions.
- 3. Date of Full Compliance Duke Power will be in full compliance by the end of-U1EOC5.
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REPLY TO A WEAKNESS (IFI) 50-413,414/09-09-13 Many labeling discrepancies between EOPs and panel indication wo o identified. Each one is listed (paragraph 3.c and Appendix D).
RESPONSE
- 1. Correctivo Action Taken and Results Achloved A. Consideration of the labeling discrepancies noted in Appendix D will be accomplished during the revision of the EP/AP Writer's Guide. Control board / panel labeling is not necessarily the nomenclature by which the operator identifies his indication / controls. Based on training and day in day operation, a functional nomenclature has evolved. Guidance provided to the procedure writer in the EP/AP Writer's Guide must allow enough flexibility so that nomenclat,re familiar to the operator can be used.
B. Consideration of the labeling discrepancies will also include proposals to change control board / panel labeling so as to more functionally describe the indication / control items.
- 2. Corrective Action to bo Taken to Avoid Further Incidents A. Revising the EP/AP Writer's Guide to establish a standard for referring to indications /and controls and maintaining the standard by the Verification and Validation processes will provide a method of quality control for the EOPs and AOPs.
B. Control Board / panel nomenclature is a controlled item. To change this nomenclature requires approval of management at various levels based on plant configuration control. This process is considered adequate and will not require modification to make changes, deemed necessary, based on this inspection.
- 3. Date of Full Compliance Duke Power will be in full compliance with our commitment to consjder the labeling concerne listed in Appendix D by June 1, 1990. Based on the EP/AP Writer's Guide, those concerns involving only a procedure revision will be completed by the end of U1EOC5. For those items of concern requiring Control Board / panel labeling modification, the full compliance date will coincide with the end of the respective unit refueling outage in 1991; 1EOCS and 2EOC4.
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DUKE POWER COMPANY
, REPLY TO A WEAKNESS 50-413,414/89-09-14 There is a discrepancy between the EOPs and the S/G pressure meter in the control room (paragraph 3.d and Appendix B ltem 1.g).
RESPONSE
- 1. Corrective Actions Taken and Results Achieved The marking of the S/G steam pressure gauges has been addressed by origination of' work requests 432120PS and 511720PS_(Unit 2 and Unit I respectively). The ranges, which depict abnormal conditions of normal at power operation, have been specified.- The corrective action will redesignate the lower red range on each S/G pressure' meter starting at 725 psig (Low S/G Steam Pressure SI setpoint) and ending at 0 PSIG on the scale. This. work _ requires removal of the meter,from the control board and thus has not been completed with the units at operating temperature and pressure.
- 2. Corrective Actions'to be Taken'to Avoid Further Incidents .
The red range marking of control panel meters is a .
functional-process and considered an_ operator aid, when performed correctly. ' Individual responsibility for this process hes been reassigned to better utilize our personnel resources and assure the process functions as intended.
- 3. Date of Full Compliance Duke Power will be in full compliance by the end of-U1EOC5.
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DUKE POWER COMPANY REPLY TO A WEAKNESS (IFI) 50-413,414/89-09-15 Many writer's guide discrepancies were identified in the EOPs. Each one is listed (paragraph 3.c and appendix C).
.?'SPONSE :
- 1. Correctivo Action Taken and Results Achieved A. A decision has been made to revise the EP/AP Writer's Guide. Based on the comments of the inspection team, it is evident that more detailed guidance should be provided to the EOP and AOP writer.
Many of the discrepancies noted in Appendices B, C B.
and D can only be addressed after decisive guidance is established in the EP/AP Writer's Guide. Thus revisions to the EOPs and AOPs will be made based on the revised EP/AP Writer's Guide and comments deemed appropriate from reports 50-413,414/89-09.
'2 1 Correctivo Actions to be Taken to Avoid Further Incidents A. The current processes of Verification and Validation _(V&V) provide an efficient and adequate means of assuring EOPs. conform to written guidance. No corrective action is'necessary.
B. AOPs will be-subjected to the V&V processes to assure conformity with written guidance and compatibility with operational experience.
, 3.. pate of-Full ComplianPe '
Duke Power will be in full-compliance with regard to the-EP/AP Writer's Guide by June 1, 1990 and, with
-regard to the revised EOPs and AOPs, by the end=of-UlEOC5.- i l
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O s-DUKE POWER COMPANY REPLY 'IV A WEAKNESS (IFI)
'30-413,414/89-09-17 Deficiencies were identified in simulator effectiveness in training on EOPs (paragraph 3.d).
RESPONSE
- 1. Corrective Action Taken and Results Achieved A. The concurrent use of AOPs is justifiable based on l the quantity and control of resources available during a multi-failure scenario. By conscientious decision the Shift supervisor may use more than one AOP at a time. This is allowed since the AOPs are written to provide various options to stabilize the plant after a particular malfunction. We do not consider this a deficiency.
B. The EOP/AOP filing methods will be reviewed to !
determine whether an identification and retrieval problem exists for Control Room personnel. The deficiency noted was based on the observation of a staff person's performance. Appropriate corrective action will be taken, if required.
C. Entry conditions for EOP/AOPs will be reviewed in conjunction with the review of procedures for other' deficiencies noted in this report. The E0P/AOPs will be revised as deemed necessary.
2 '. Corrective Actions to be Taken to Avoid Further Incidents A. Discrepancies-discussed in Item 1, with exception of 1.c., are not expected to recur. Thus surveillance programs, to monitor for the
. repetition of the discrepancy, are not required.
B.- The EP/AP Writer's Guide and the Verification and Validation processes will ensure that future s revisions to EOP/AOP entry conditions are written to an established standard.
3 Date of Full Compliance:
Duke Powe'r will'be in full compliance for the following corrective actions as listed:
. EOP/AOP filing method review - January 2, 1990
. EOP/AOP entry condition review - U1EOC5 and U2EOC4 l
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