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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H5811999-10-15015 October 1999 Forwards 1999 Update to FSAR, for McGuire Nuclear Station.With Instructions,List of Effective Pages for Tables & List of Effective Pages for Figures ML20217G7861999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20217F3591999-10-13013 October 1999 Forwards Info Copy of Cycle 14 COLR for McGuire Nuclear Station,Unit 1 ML20217F3261999-10-13013 October 1999 Submits Quantity of Tubes Insp from Either Side of SGs A-D & Lists Tubes with Imperfections,Locations & Size.No Tubes Removed from Svc by Plugging.Total of Eleven Tubing Wear Indications Identified at Secondary Side Supports in SGs ML20217F8011999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of McGuire Nuclear Station.Areas That Warranted More than Core Insp Program Over Next Five Months,Not Identified.Historical Listing of Plant Issues Encl ML20217J5091999-10-0606 October 1999 Forwards Revs to Section 16.15-4.8.1.1.2.g of McGuire Selected Licensee Commitments Manual.Section Has Been Revised to Allow Testing of Portions of DG Fuel Oil Sys Every 10 Yrs ML20217C8351999-10-0505 October 1999 Communicates Correction to Info Provided During 990917 Meeting with Duke Energy & NRC Region Ii.Occupational Radiation Safety Performance Indicator Values Should Have Been Presented as 1 Instead of 0 ML20217C4471999-10-0404 October 1999 Forwards Insp Repts 50-369/99-06 & 50-370/99-06 on 990801- 0911.Determined That One Violation Occurred & Being Treated as Non-Cited Violation ML20212J2191999-10-0404 October 1999 Informs That Util 980326 Response to GL 97-06, Degradation of SG Internals Provides Reasonable Assurance That Condition of Steam Generator Internals Are in Compliance with Current Licensing Bases for Facility ML20212J7801999-10-0404 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for McGuire NPP & 990615.Informs That NRC Reviewed Responses & Concluded That All Requested Info Re Y2K Readiness Provided.Subj GL Considers to Be Closed ML20212M1651999-09-23023 September 1999 Refers to 990917 Meeting at Region II Office Re Licensee Presentation of self-assessment of McGuire Nuclear Station Performance.List of Attendees & Licensee Presentation Handouts,Encl ML20212D1671999-09-20020 September 1999 Forwards Exemption & SER from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Re Isolation of Main Steam Branch Lines Penetrating Containment.Exemption Related to Licensee Application ML20212B6491999-09-15015 September 1999 Informs That Encl Announcement Re 990913 Application for Amend to Licenses NPF-9 & NPF-7 Forwarded to C Observer in North Carolina,For Publication 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 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 ML20216E8791999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for July 1999 for McGuire Nuclear Station ML20212A0501999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementing Code Case for Duration of Insp Interval ML20212A2631999-09-0909 September 1999 Forwards Rev 25 to McGuire Nuclear Station,Units 1 & 2 Pump & Valve Inservice Testing Program, IAW 10CFR50.55a. Section 8.0 Contains Summary of Changes & Detailed Description of Changes Associated with Rev 25 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 ML20211J3671999-08-31031 August 1999 Forwards Public Notice of Application for Amend to License NPF-9 Seeking one-time Extension of Surveillance Frequency for TS SR 3.1.4.2 Beyond 25% Extension Allowed by TS SR 3.0.2 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 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 ML20211K8831999-08-26026 August 1999 Forwards Insp Repts 50-369/99-05 & 50-370/99-05 on 990620-0731.Two Violations Occurred & Being Treated as NCVs ML20211G5181999-08-24024 August 1999 Forwards SE Re second-10-yr Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 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 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 ML20210V0171999-08-13013 August 1999 Confirms Conversation Between M Cash & M Franovich on 990806 Re Mgt Meeting,Scheduled for 990917 to Present self- Assessment of Plant Performance.Meeting Will Be Held in Atlanta,Ga ML20210S2231999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210T4511999-08-10010 August 1999 Forwards Response to NRC RAI Re 981014 Standby Nuclear Svc Water Pond Dam Audit Conducted by FERC ML20210R4311999-08-10010 August 1999 Forwards Summary Rept of Mods,Minor Mods,Procedure Changes & Other Misc Changes Per 10CFR0.59 ML20210R0031999-08-10010 August 1999 Forwards Revised TS Bases Pages to NRC for Info & Use. Editorial Changes Were Made to Correct Incorrect UFSAR Ref Number Associated with Certain Reactor Coolant Sys Pressure Isolation Valves ML20210Q3701999-08-0505 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 to Take Exam ML20210H7691999-07-21021 July 1999 Submits Summary of 990715 Meeting at Facility Re Presentation of Results of Most Recent Periodic Ppr.List of Meeting Attendees Encl ML20209H1551999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for May 1999 Also Encl ML20210E1931999-07-13013 July 1999 Forwards Insp Repts 50-369/99-04 & 50-370/99-04 on 990509-0619.Four Violations of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy 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 ML20209G5151999-07-0808 July 1999 Forwards Amended Pages to Annual Radioactive Effluent Release Repts, for 1997 & 1998 for McGuire Nuclear Station. Portion of Rept Was Inadvertently Omitted Due to Administrative Error,Which Has Been Corrected 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 ML20196J4381999-06-29029 June 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1,NRC Revised Info in Rvid & Releasing Rvid Version 2 ML20196G3721999-06-24024 June 1999 Documents Verbal Info Provided to NRR During Conference Call Re Relief Requests 98-002 & 98-003 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 ML20195K3601999-06-14014 June 1999 Forwards MORs for May 1999 for McGuire Nuclear Station,Units 1 & 2 & Revised MORs for Apr 1999.Line 6 Max Dependable Capacity (Gross Mwe) on Operating Data Rept Should Be Revised to 1114 from Jan 1998 to Apr 1999 ML20195D5691999-06-0303 June 1999 Submits Ltr to Facilitate Closing of Inspector Follow Up Item 50-369,370/97-15-05,re Revising Site Drawings in UFSAR Into Summary one-line Flow Diagrams,Per NRC 990327 Telcon ML20195F1851999-06-0202 June 1999 Forwards Insp Repts 50-369/99-03 & 50-370/99-03 on 990328- 0508.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20195E8771999-06-0202 June 1999 Confirms Telcon with M Cash on 990524 Re Public Meeting for 990715.Purpose of Meeting to Discuss Results of NRC Most Recent PPR ML20207D0521999-05-21021 May 1999 Informs That in Telcon on 990519 Between a Orton & Rf Aiello Arrangements Made for Administration of Initial Written Exam for McGuire Nuclear Station on 990603.Exam Will Be Administered at Catawba Simultaneously with Written Exam 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 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 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 ML20206R0791999-05-13013 May 1999 Forwards Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 & Revised Monthly Operating Repts for Mar 1999 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217H5811999-10-15015 October 1999 Forwards 1999 Update to FSAR, for McGuire Nuclear Station.With Instructions,List of Effective Pages for Tables & List of Effective Pages for Figures ML20217F3261999-10-13013 October 1999 Submits Quantity of Tubes Insp from Either Side of SGs A-D & Lists Tubes with Imperfections,Locations & Size.No Tubes Removed from Svc by Plugging.Total of Eleven Tubing Wear Indications Identified at Secondary Side Supports in SGs ML20217F3591999-10-13013 October 1999 Forwards Info Copy of Cycle 14 COLR for McGuire Nuclear Station,Unit 1 ML20217G7861999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20217J5091999-10-0606 October 1999 Forwards Revs to Section 16.15-4.8.1.1.2.g of McGuire Selected Licensee Commitments Manual.Section Has Been Revised to Allow Testing of Portions of DG Fuel Oil Sys Every 10 Yrs ML20217C8351999-10-0505 October 1999 Communicates Correction to Info Provided During 990917 Meeting with Duke Energy & NRC Region Ii.Occupational Radiation Safety Performance Indicator Values Should Have Been Presented as 1 Instead of 0 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 ML20216E8791999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for July 1999 for McGuire Nuclear Station ML20212A2631999-09-0909 September 1999 Forwards Rev 25 to McGuire Nuclear Station,Units 1 & 2 Pump & Valve Inservice Testing Program, IAW 10CFR50.55a. Section 8.0 Contains Summary of Changes & Detailed Description of Changes Associated with Rev 25 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 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 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 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 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 ML20210S2231999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210T4511999-08-10010 August 1999 Forwards Response to NRC RAI Re 981014 Standby Nuclear Svc Water Pond Dam Audit Conducted by FERC ML20210R0031999-08-10010 August 1999 Forwards Revised TS Bases Pages to NRC for Info & Use. Editorial Changes Were Made to Correct Incorrect UFSAR Ref Number Associated with Certain Reactor Coolant Sys Pressure Isolation Valves ML20210R4311999-08-10010 August 1999 Forwards Summary Rept of Mods,Minor Mods,Procedure Changes & Other Misc Changes Per 10CFR0.59 ML20209H1551999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for May 1999 Also Encl ML20209G5151999-07-0808 July 1999 Forwards Amended Pages to Annual Radioactive Effluent Release Repts, for 1997 & 1998 for McGuire Nuclear Station. Portion of Rept Was Inadvertently Omitted Due to Administrative Error,Which Has Been Corrected ML20196G3721999-06-24024 June 1999 Documents Verbal Info Provided to NRR During Conference Call Re Relief Requests 98-002 & 98-003 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 ML20195K3601999-06-14014 June 1999 Forwards MORs for May 1999 for McGuire Nuclear Station,Units 1 & 2 & Revised MORs for Apr 1999.Line 6 Max Dependable Capacity (Gross Mwe) on Operating Data Rept Should Be Revised to 1114 from Jan 1998 to Apr 1999 ML20195D5691999-06-0303 June 1999 Submits Ltr to Facilitate Closing of Inspector Follow Up Item 50-369,370/97-15-05,re Revising Site Drawings in UFSAR Into Summary one-line Flow Diagrams,Per NRC 990327 Telcon 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 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 ML20206R0791999-05-13013 May 1999 Forwards Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 & Revised Monthly Operating Repts for Mar 1999 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 ML20206S9151999-05-11011 May 1999 Forwards Rev 29 to McGuire Nuclear Station Selected Licensee Commitments. Section 16.11-16.2 Has Been Revised to Apply Guidance of NUREG-0133 for Performing Gaseous Effluent Dose Pathway Calculations ML20206K1341999-05-0303 May 1999 Forwards 1999 Interim UFSAR for McGuire Nuclear Station. UFSAR Update Includes Items Relocated During Improved Tech Specs Implementation.Next Regular UFSAR Update as Required 10CFR50.71(e) Is Due in Oct 1999 ML20206F3321999-04-28028 April 1999 Forwards Annual Radioactive Effluent Release Rept for 1998 for McGuire Nuclear Station. Listed Attachments Are Contents of Rept.Revised ODCM Was Submitted to NRC on 990203 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 ML20206B4791999-04-20020 April 1999 Requests Exemption from GDC 57 Re Reactor Containment - Closed Sys Isolation Valves,As Described in 10CFR,App a for Containment Penetrations M393 & M261.Detailed Technical Evaluation & Justification for Exemption Request,Encl ML20205S9731999-04-19019 April 1999 Submits Info Re Quantity of SG Tubes Inspected,Tube Indications of Imperfections & Tubes Removed from Svc by Plugging,Per TS 5.6.8,part B 05000369/LER-1999-001, Forwards LER 99-01(S)-00 Re Contract Employee Submittal of False Info Resulting in Gaining Unescorted Access.No Licensee Planned Corrective Actions or Other Regulatory Commitments Were Identified as Result of Incidence1999-04-16016 April 1999 Forwards LER 99-01(S)-00 Re Contract Employee Submittal of False Info Resulting in Gaining Unescorted Access.No Licensee Planned Corrective Actions or Other Regulatory Commitments Were Identified as Result of Incidence ML20205P8891999-04-13013 April 1999 Forwards Monthly Operating Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for Feb 1999 Encl ML20206K3561999-04-13013 April 1999 Forwards Revised McGuire Nuclear Station Selected Licensee Commitments (SLC) Manual. Significant Changes Are Marked by Vertical Bars on Right Margin ML20205K5131999-04-0707 April 1999 Forwards Complete Response to NRC 981209 & 990105 RAIs on Question 11 Re LARs for McGuire & Catawba Nuclear Stations. Addl Info Received from W & Contained in Encl W ML20205B6011999-03-23023 March 1999 Requests That NRC Place Technical Interface Agreement 97-02 Re URI 96-11-03,raising Operability & Design Criteria Conformance Issues Re Hydraulic Snubbers Installed at Plant & NRR Response on Dockets to Provide Record of Issue ML20205C4611999-03-23023 March 1999 Submits Correction to Violation Against 10CFR50 App B, Criterion VII, Control of Purchased Matl,Equipment & Svcs, Issued to McGuire Nuclear Station on 980807 ML20205B6161999-03-23023 March 1999 Provides Addl Info & Correction to Typo in Re License Bases Record Change Re License Amend Submittals ,approved as FOL NPF-9 & NPF-17,amends 184 & 166, respectively.Marked-up TS Pages,Encl ML20204J0051999-03-19019 March 1999 Forwards Response to 990127 & 28 RAIs Re GL 96-05 for Catawba & McGuire Nuclear Stations ML20204E1791999-03-18018 March 1999 Reflects 990318 Telcon Re License Bases Record Change for License Amend Submittals ,approved as Amends 184 & 166,respectively for Licenses NPF-9 & NPF-17.TS Pages Encl ML20204C8821999-03-15015 March 1999 Forwards Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for Jan 1999 Encl ML20207C2071999-02-25025 February 1999 Informs of Revised Expected Submittal Date of Proposed License Amend Presented at 990127 Meeting Re Soluble Boron & Boraflex.Util Plans to Submit Proposed License Amend in First Quarter of 1999 ML20207C7691999-02-22022 February 1999 Forwards Annual Occupational Radiation Exposure Rept for 1998. Rept Provides Tabulation of Number of Station,Utility & Other Personnel Receiving Exposure Greater than 100mRem/yr Followed by Total Dose for Each Respective Worker ML20207C6851999-02-22022 February 1999 Forwards Revised TS Bases Pages,Reflecting Removal of SI Signal on Low Steamline Pressure on Page B 3.3.2-16 & Adding Clarification for Increasing Hydrogen Recombiner Power During Testing on Page B 3.6.7-4 ML20206S3341999-01-28028 January 1999 Forwards Proprietary & non-proprietary Responses to NRC 981209 & 990105 RAIs Re Util Lars,Permitting Use of W Fuel at McGuire & Catawba Stations.Proprietary Info Withheld,Per 10CFR2.790 ML20199E0081999-01-12012 January 1999 Forwards MOR for Dec 1998 & Revised MOR for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 ML20199C9861999-01-0707 January 1999 Forwards Annual Lake Norman Environ Summary Rept for 1997,as Required by NPDES Permit NC0024392,including Detailed Results & Data Comparable to That of Previous Years.With Corrected Pages 3 & 19 to 1994-95 Lake Norman Creel Rept 1999-09-09
[Table view] Category:RESEARCH INSTITUTION/LABORATORY TO NRC
MONTHYEARML20153G9251988-05-0909 May 1988 Forwards Trip Rept of 880428 Visit to Plant Re Evaluation of Inadequate Core Cooling Instrumentation ML20234F5061987-06-22022 June 1987 Comments on Facility Scenario for 870911-12 Exercise. Scenario Should Support Reasonable Demonstration of Licensee Emergency Response Capability.No Major Deficiencies Noted ML19350A2331981-01-23023 January 1981 Forwards Some Very Preliminary Results of Short-Term Analysis (3-Wk Study) of Hydrogen Combustion During Degraded Core Accidents in Sequoyah Nuclear Power Plant in Presence of Glow Plugs. ML19343A1781980-09-10010 September 1980 Submits Bimonthly Rept for Period Ending 800831 Re Review of Nuclear Plants Structural Design. Finite Computer Program Ansys Used to Analyze Strength of Sequoyah Containment Vessel.Mcguire Vessel Analysis Almost Ready 1988-05-09
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ENCLOSURE-2 OAK RIDGE NATIONAL LABORATORY Post ornce nox x oAA 400t,itWS$tt 3753t ,
OPERATED BY MARTW MARrETTA (te(RGY SYSTEMS, NC May 9, 1988 Dr. Tai L. Huang Reactor Systems Branch MS WF1 8E23 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Dr. Huang:
Attached is our Trip Report of the post-implementation audit of the McGuire Nuclear Station Inadequate Core Cooling Instrumentation.
Sincerely, 9
W John L. Anderson Instrumentation and Controls Division JiA Attachment cc: E. W. Hagen T. C. Morelock ,
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TRIP REPORT EVALUATION OF INADEQUATE CORE COOLING INSTRUMENTATION AT McCUIRE NUCLEAR STATION, UNITS 1 AND 2 APRIL 28, 1988
?URPOSE On April 28, 1988, a trip was made to the McGuire Nuclear Plant of Duke Power Company (DPC) to evaluate the installation, performance, and maintenance history of Inadequate Core Cooling Instrumentation (ICCI) installed in response to the NRC requirements of NUREG 0737 and Generic Letter 82-28. The visit team consisted of the NRC/McGuire Project Manager Mr. Darl Hood, the NRC/ICCI Technical Manager Dr. Tai Huang, and Oak Ridge National Laboratory (OR ',) Principal Investigators J. L. Anderson and E. W. Hagen.
The purpose of the visit was not to evaluate the Utilities conformance to the requirements of NUREG-0737, Item II.F.2, as this was done with previous reviews and audits. Rather, the purpose was to collect and evaluate information derived form experience of installation, calibration and operation at selected plants typical of the different types of ICCI systems installed. This information will be used to assist in the assessment of the effectiveness and impact of the implementation of the ICCI requirements. The McGuire visit was the first of several visits planned to obtain a cross section of the several different types of systems that were installed by different utilities.
DESCRIPTION OF ICC INSTRUMENTATION SYSTEM As required by NKC, the ICCI system at McGuire Units 1 and 2 consists of a Subcooling Margin Monitor (SMM), Reactor Vessel Level Instrumentation ;
System (RVLIS), and Core Exit Thermocouples (CET). The system l
installation was approved by NRC and became operational in 1984 Subcooling Margin Monitoring The SMM system consists of two redundant trains of instrumentation with appropriate separation and independence and ate separately powered from Class IE power sources. Each train uses a digital processor with '
isolated inputs from reactor coolant system wide range pressure, reactor coolant system low range pressure, core exit thermocouples, and wide range reactor coolant hot leg RTD's. The primary display for SMM information is on a color-graphics cathode ray tube (CRT) display from an Operational Aids Computer (OAC). The CRT is located above control panel MC2 and the keyboard control is on the operators' desk MC15 (see attached sketch -
Fig. 1). The OAC is not a qualified system, but provides coordinated integration of important plant information and includes the Safety Parameter Display System (SPDS). The redundant qualified backup displays for the SMM are Plasms Display Units (PDU) located on the vertical portion of control panel MCl. These programmable displays provide both graphical
m l
. 2 and numeric indication of subcooling margin and other pertinent parameters (Fig. 2).
Reactor Vessel Level Instrumentation System The McGuire RVLIS is a generic Westinghouse design using two redundant trains of three differential pressure (dp) transmitters each.
The "Upper Range" measures from the top of the vessel head to the bottom of the hot leg. The "Lower Re.1ge" measures from the bottom of the hot leg to the bottom of the vessel. The "Dynamic Head" sensor measures in the same location as the Lower Range, but is scaled to indicate the dp craated by the dynamic head of the primary coolant pumps. The Dynamic Head indication will respond to increasing void fraction when the primary coolant pumps are running. The Upper and Lower Range indications provide more accurate level indication in their respective regions when the coolant pumps are not running, but are normally off-scale with the pumps in operation. The Westinghouse system uses sealed sense lines and hydraulic isolators (bellows) to minimize the quantity of primary system water in the lines. The temperature of the vertical runs of sense lines inside containment are measured with RTD's to provide compensation signals for changes in containment environment. The dp transmitters are located outside containment. Two types of electronic processing equipment are available for the Westinghouse systems, McGuire originally installed the analog signal processing version identified as the "7300" system. Later, in 1986, they replaced the analog system with digital microprocessor electronics. This was partly to benefit from the improved accuracy and stability of the microprocessor system and partly so that all of the DPC systems (McGuire, Catawba and Oconee) would be alike to minimize maintenance and training problems. The two redundant trains of RVLIS are independent and separately powered from Class 1E sources. The primary display is via the Operational Aids Computer and the qualified backup displays are the same PDUs described above for the SMM systems. Two of the RVLIS display screens are shown in Figs. 3 and 4.
Core Exit Thermocouple system Each McGuire unit has 65 CETs. 40 of these have been upgraded and qualified and are divided into two trains of 20 each. Separate thermocouple containment penetrations are used for the two trains and separation is maintained to the processing cabinets in an equipment room near the control room. Signal processing and cold junction compensation is accomplished in these cabinets in a controlled environment. The 25 unqualified CETs have cold junction compensation inside containment and feed directly to the OAC. Isolated outputs from the qualified trains also feed the OAC where core maps and other primary displays are generated.
The qualified backup displays for the qualified CETs are the PDUs also used for the SMM and RVLIS. The layout of the CET system is shown in Fig. 5.
Selected CET outputs also are used in the SMM system.
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.. l INSTALLATION AND MAINTENANCE EXPERIENCE RVLIS The impressions given by the engineering staff involved are that the RVLIS system is now an accurate and reliable system. Some infant mortality was experienced with components and a few chronic problems with components, design, and installation techniques required early attention.
They feel that these problems are now resolved and maintenance is routine.
Several early failures were experienced with the dp transmitters and hydraulic isolators.
Both are manufactured by Barton and one DPC engineer expressed the opinion that perhaps the Barton quality control was not adequate. The failures were due to improper internal clearances and internal electrical short circuits.
Another chronic problem was the filling procedures and maintaining leak tightness of the sealed capillary system. Apparently, it is very difficult to maintain the capillary system leak tight over a long period.
Very small pinhole leaks or minute leaks through valve seals cause trouble in times shorter than a refueling cycle. The hydraulic isolators have position indicators on the bellows. These positions are monitored routinely and if the system leaks, early warning is provided before the system ba:omes inoperable. The capillary system can be back-filled on-line to restore the original isolator bellows positions. One source of slow leaks is the fill valves. A procedure was developed to cap and weld the fill lines after the system is filled to prevent leaks through the fill valves.
Evacuating and refilling the sealed system is an expensive and time consuming operation. The Westinghouse field charge for this service is over $50,000. DPC has purchased equipment and has developed their own capability for this operation. Since initial installation, the McGuire once per year).sealed capillary systems have required refilling four times (about DPC and Westinghouse are investigating the feasibility of a design modification to eliminate the sealed capillary system because of its high maintenance cost.
When the analog signal processing system was in use, DPC found that the circuitry experienced considerable drift and that frequent recalibration was necessary. Although this was a relatively easy calibration process, it was time consuming and therefore expensive. When new RVLIS systems were purchased for other DPC plants the microprocessor systems were specified because of this experience with the analog systems.
In addition, DPC opted to purchase a replacement microprocessor based signal processing system for the McGuire units that is essentially the same as the other units (Catawba, Oconee). DPC purchased ICCI systems for all 7 of their units at one time. Maintenance experience with the digital systems has been much better than with the analog systems.
CET The new head connectors and mineral insulated cable for the qualification upgrade of the CETs creates new handling problems during refueling operations. The bulky connectors at the head ports require special care and handling because of tight fits through the access t - - _ _ _ _ _ _ _ _ _
l 4 l sleeves, and special waterproofing is needed when disconnected. Although I the handling time during refueling is somewhat increased, no performance problems have been identified with the qualified CET installations. The remaining unqualified CETs are more susceptible to mishandling because they do not have elaborate seals, and some have been damaged.
When the new signal processing cabinets (also including RVLIS and SMM) were installed, a few early problems were experienced. Field connections were made to screw terminals on printed circuit cards which also have card edge connectors. Screw force applied in making field connections sometimes misaligned the card edge connector pins and caused failures and mis operation. The field connection cards were replaced with an upgraded design which eliminated this problem. In addition to the connector problems, some infant mortality of parts was experienced, but improved replacements have apparently solved this problem as well. DPC has been somewhat unhappy about the repair costs for circuit cards and other components from the manufacturer. DPC has developed their own diagnostic and repair capability, but was frustrated in this effort by deficiencies in documentation for the instrumentation and particularly for the software. Apparently Westinghouse guards the propriety of the designs carefully and regards DPC as a competitor for engineering services.
Initial software problems were apparently due to quality control deficiencies. Some of the proV ms included incorrect designations or locations on data displays and core maps, improper coefficients in compensation algorithms for impulse line temperature and system density (data confused with another plant), and incorrect functioning of failure auctioneering algorithms. These problems were readily identified during initial checkout and calibration and have been corrected by appropriate software upgrades (ROM chips). After initial debugging, DPC is pleased with the signal processing system performance. The system includes a software self-calibration routine that works well and effectively eliminates the problems experienced earlier with the analog system. Under normal conditions, McGuire attempts to maintain overall accuracy of 1.5%
in the signal processing system. A complete system checkout and calibration after refueling requires two weeks per train. DPC was not satisfied with all of the displays provided with the system and has customi::ed the displays to their own satisfaction through sof tware modifications. The displays shown in Figs. 1-5, although similar to the original Westinghouse displays, are unique to McGuire.
SMM The SMM system uses much of the same processing equipment as the RVLIS and CET systems and has experienced no special problems except as described for the other functions.
PERFORMANCE, TECHNICAL SPECIFICATIONS, PROCEDURES AND 'IRAINING The CET and SMM portions of the system are used routinely and perform well.
Since RVLIS is a post accident monitoring system and gives no useful information in normal operation, its acceptance is less well defined. It was indicated that the RVLIS is very useful during drain and fill operations and is usually kept operational until the sense lines are
, 5 removed for refueling. Comparison with manometer indications during draining shows agreement within a few inches and operators have developed confidence in the indications. All operators are trained in the use of ICCI and ICCI indications are incorporated into operating and emergency procedures. The current McGuire training simulator does not have ICCI installed as a new simulator is on order and will be installed soon. The new simulator will have the full complement of ICC instrumentation as does the simulator at the Catawba plent.
It was pointed out that the ICCI systems are not referred to explicitly in the procedures'and status trees, but the information displayed by the systems is referred to and used in many procedures and status trees. A number of examples were illustrated. It was noted on a typical status tree that reference was made to a particular vessel water level, but no branch or specific reference to pump status was indicated.
However, the specific procedures reference by the tree include checks of pump status in relation to level information.
A visit to the control room revealed that the primary and secondary displays are well located for operator access and visibility. The secondary display panels are appropriately close to the primary pump controls and indications. Each backup display is multi purpose being used for all three functions, SMM, CET, and RVLIS. The redundant displays are side by side and in normal operation the practice is to leave one display paged to SMM information and the other to CET information. Additional information is available on the color CRT display of the OAC. A software problem persists in the RVLIS which causes a malfunction annunciator occasionally in response to the self-checking routine. The problem has been identified and will be corrected soon with a revised ROM chip.
Our overall impressions are that the systems are performing satisfactorily and that maintenance problems have been reduced to an acceptable level by gradual modifications. Operator acceptance is good and confidence in the indications is high.
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