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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:UTILITY TO NRC
MONTHYEARML20059L0101990-09-19019 September 1990 Provides Addl Response to Violations Noted in Insp Repts 50-369/90-11 & 50-370/90-11,per .Corrective Action:Operations & Compliance Mgt Further Examined Event & Concluded That Trains Vc/Yc Inoperable Per Special Order ML20059L0091990-09-18018 September 1990 Informs of Delay in Response to Violations Noted in Insp Repts 50-369/90-14 & 50-370/90-14.Delay Due to Ongoing Review ML20059L5491990-09-14014 September 1990 Forwards Proprietary Response to Question Re Scope of Review of Topical Rept, Safety Analysis Physics Parameter & Multidimensional Reactor Transients Methodology, Per & 900723 Meeting.Response Withheld ML20059J7121990-09-14014 September 1990 Forwards Monthly Operating Rept for Aug 1990 for McGuire Nuclear Station Units 1 & 2 & Monthly Operating Status Rept for Jul 1990 ML20059L5521990-09-14014 September 1990 Forwards Response to 18 Questions Re Topical Rept DPC-NE-2004,per NRC 900802 Request for Addl Info.Encl Withheld (Ref 10CFR2.790) ML20065D4671990-09-11011 September 1990 Informs of Delay in Response to Violation Noted in Insp Repts 50-369/90-11 & 50-370/90-11,per Commitment in ML20064A8031990-09-10010 September 1990 Responds to NRC Ltr Re Violations Noted in Insp Repts 50-369/90-13 & 50-370/90-13.Corrective Actions:Procedures Dealing W/Fuel Handling Will Be Enhanced by Adding Sign Off to Sections Which Ref Fuel Handling in Tech Specs ML20059G3011990-09-0404 September 1990 Forwards Response to NRC 900327 Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire ML20064A5741990-09-0404 September 1990 Discusses Re Info to Support Util Position Relative to Resolving Issue of Main Steam Line Breaks Inside Ice Condenser Containments & Requests That Info Be Withheld (Ref 10CFR2.790) ML20064A5671990-09-0101 September 1990 Advises That Corrective Actions Re Violation of Insp Rept 50-369/89-01 & 50-370/89-01 Will Be Completed by 910101 ML20059D3461990-08-30030 August 1990 Forwards Semiannual Effluent Release Rept for First Half of CY90 & Revs to Process Control Program ML20059G9141990-08-22022 August 1990 Forwards Public Version of Revised Epips,Including Change 0 to RP/O/A/5700/01,Change 0 to RP/O/A/5700/02 & Change 0 to RP/O/A/5700/03 ML20059D1901990-08-22022 August 1990 Responds to Violations Noted in Insp Repts 50-369/90-11 & 50-370/90-11.Corrective Actions:Valves VC-1,VC-2,VC-3,VC-4, VC-9,VC-10,VC-11 & VC-12 Reopened Upon Discovery of VC-1 - VC-4 Being Closed & Procedure IP/0/13/3006/09 Revised ML16259A2391990-08-22022 August 1990 Forwards Public Version of Rev 27 to Company Crisis Mgt Implementing Procedure CMIP-2, News Group Plan. W/ Dh Grimsley 900906 Release Memo ML20059C1201990-08-20020 August 1990 Forwards Rept Summarizing Util Findings Re Three False Negative Blind Performance Urine Drug Screens Which Occurred During Jan & Feb 1990.Recommends That NRC Consider Generic Communication to Clearly State Reporting Requirement ML20059B4451990-08-20020 August 1990 Requests That NRC Approval of Original Relief Request 89-02 Be Extended to Include Changes to Mods MG-22233 & MG-22243 as Described.Hydrostatic Testing Impractical Due to Inadequacy of Test Boundaries ML20059C1591990-08-17017 August 1990 Suppls by Providing Addl Info to Support Util Position Re Anl Confirmatory Analysis of Main Steamline Breaks in Ice Condenser Plants.Encl Withheld ML20063Q0901990-08-15015 August 1990 Forwards Monthly Operating Repts for Jul 1990 for McGuire Nuclear Station Units 1 & 2 & Revised Rept for June 1990 ML20063Q2671990-08-14014 August 1990 Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 36 to CMIP-1,Rev 32 to CMIP-4,Rev 36 to CMIP-5,Rev 41 to CMIP-6,Rev 40 to CMIP-7,Rev 27 to CMIP-8 & Rev 35 to CMIP-9.W/DH Grimsley 900821 Release Memo ML20058N0181990-08-0808 August 1990 Forwards Response to Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire ML20063Q0181990-08-0707 August 1990 Confirms That Planned Corrective Actions Listed in Paragraph 3 of Insp Repts 50-369/90-10 & 50-370/90-10,appropriately Described ML20056A9541990-08-0101 August 1990 Provides Final Response to NUREG-0737,Item II.D.1, Performance Testing of Safety Relief Valves. Util Will Change Seal Configuration for Existing Valves to Seal on Steam Medium & Install Continuous Drain for Loop Piping ML20058L4061990-08-0101 August 1990 Forwards Rev 0 to Inservice Insp Rept Unit 1 McGuire 1990 Refueling Outage 6 ML20058L1811990-08-0101 August 1990 Forwards Safety Evaluation of Large Break LOCA Event Reanalysis Per 10CFR50.46 Re Peak Clad Temp Increases ML20059K0291990-08-0101 August 1990 Forwards Comments on Reactor Operator & Senior Reactor Operator Written Exams Administered on 900730 ML20056A1571990-07-23023 July 1990 Forwards Public Version of Change 0 to RP/0/A/5700/10 & Rev 25 to Section 18.2 of Radiation Protection Manual.W/ Dh Grimsley 900730 Release Memo NLS9000259, Responds to Violations Noted in Insp Repts 50-369/90-09 & 50-370/90-09.Corrective actions:in-house Training Will Be Provided on Correct Method for Determining Proper Response to Problem Investigation Processes1990-07-16016 July 1990 Responds to Violations Noted in Insp Repts 50-369/90-09 & 50-370/90-09.Corrective actions:in-house Training Will Be Provided on Correct Method for Determining Proper Response to Problem Investigation Processes ML20055F7721990-07-13013 July 1990 Forwards Monthly Operating Repts June 1990 for McGuire Nuclear Station Units 1 & 2 & Status Rept for May 1990 ML20044B0561990-07-0303 July 1990 Forwards Public Version of Epips,Consisting of RP/0/A/5700/02 & RP/0/A/5700/03 & RP/0/A/5700/04.W/ Dh Grimsley 900716 Release Memo ML20044A7941990-06-19019 June 1990 Forwards Public Version of Epips,Including HP/0/B/1009/06, HP/0/B/1009/10 & HP/0/B/1009/20 ML20043H5541990-06-18018 June 1990 Forwards Supplemental Info to Tech Spec Rev Request Re Auxiliary Bldg Filtered Ventilation Sys ML20043G1531990-06-15015 June 1990 Forwards Monthly Operating Repts for May 1990 & Corrected Unit Shutdowns & Power Reductions for Apr 1990 ML20043G1741990-06-0707 June 1990 Responds to Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire. Correct RCS Operating Pressure Would Be 2,250 Psia as Identified in Table 3-1 ML20043G3451990-06-0707 June 1990 Forwards Proprietary Response to Request for Addl Info Re Topical Rept BAW-10174, Mark-BW Reload Safety Analysis for Catawba & Mcguire. Response Withheld ML20043G7171990-06-0606 June 1990 Forwards Population Dose Analysis Summary for Plant Liquid Release Pathways Based on 1986 Release Estimates ML20043G6321990-06-0505 June 1990 Responds to Violations Noted in Insp Repts 50-369/90-01 & 50-370/90-01.Corrective Actions:Memo Issued Reemphasizing Importance of Frisking & Outlining Frisking Requirement & Personnel Counseled Re Completing Required Documentation ML20043G6281990-06-0404 June 1990 Advises That Corrective Actions Re Departmental Interface Issues to Resolve & Train on Revised Directive Will Be Completed by 900901,per Insp Repts 50-369/89-01 & 50-370/89-01 ML20043F4761990-05-30030 May 1990 Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Consisting of Rev 20 to CMIP-13 & Deletion of CMIP-15 & CMIP-17.W/900612 Release Memo ML20043B5691990-05-23023 May 1990 Advises That Responses to Violations Noted in Insp Repts 50-369/90-01 & 50-370/90-01 Will Be Delayed Until 900601 ML20043C0781990-05-22022 May 1990 Responds to Violations Noted in Insp Repts 50-369/90-04 & 50-370/90-04.Corrective Actions:Correct Procedure Adherence Reemphasized to Job Supervisor & Engineering Group Involved in Authorization for Torque Change ML20043B9351990-05-16016 May 1990 Forwards Public Version of Epips,Including HP/1/B/1009/15 & HP/2/B/1009/15.W/DH Grimsley 900529 Release Memo ML20043A1041990-05-15015 May 1990 Forwards Monthly Operating Rept for Apr 1990 & Corrected Mar 1990 for McGuire Nuclear Station Units 1 & 2 ML20042G8221990-05-10010 May 1990 Forwards Addl Info Re Events Leading to 900509 Emergency Tech Spec (TS) Request Re TS 4.6.1.8,per Ds Hood 900510 Telcon & Requests That Changes Also Be Made to Unit 2 Ts. Proposed TS Encl ML20043A8621990-05-10010 May 1990 Forwards Info for Facility 1990 Refueling Outage Re Steam Generator F* Tubes & Tubes Removed from Svc or Repaired ML16152A9621990-05-0909 May 1990 Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 35 to CMIP-1,Rev 26 to CMIP-2,Rev 31 to CMIP-4,Rev 35 to CMIP-5,Rev 40 to CMIP-6,Rev 39 to CMIP-7 & Rev 26 to CMIP-8.W/DH Grimsley 900517 Release Memo ML20042G8331990-05-0808 May 1990 Forwards Info for Facility Tube Rupture Outage Re Steam Generator Inservice Insp,Per Tech Spec 4.4.5.5 & 6.9.2 ML16152A9531990-05-0202 May 1990 Forwards Proprietary DPC-NE-2000P-A & Nonproprietary DPC-NE-2000-A, DCHF-1 Correlation for Predicting Heat Flux in Mixing Vane Grid Fuel Assemblies. Proprietary Rept Withheld ML20042F2611990-04-30030 April 1990 Forwards Technical Evaluation That Concludes Fireproofing of Supports for safety-related HVAC Ducts Not Required & Amends Fire Protection Commitment Re HVAC Sys Support Fireproofing ML20042F8331990-04-26026 April 1990 Forwards Public Version of Revised Epips,Including Change 0 to RP/0/A/5700/01,RP/0/A/5700/02 & RP/0/A/5700/03 ML20042E0631990-04-13013 April 1990 Forwards Monthly Operating Repts for McGuire Nuclear Station for Mar 1990 & Feb 1990 Rept Re Personnel Exposure 1990-09-04
[Table view] |
Text
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DUKE POWER COMPANY Powra Dust.otwo 422 Socin Cucacu Stazzi. CHARLOTTz, N. C. 26242 w s LLIA s4 O. Pa n s t a, J R.
v.e,p.ts.ec=' ''*"
Steam Paoovctio= April 23. 1981 ^**'.e's*
273 a Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Ms. E. Adensam, Chief Licensing Branch No. 4
Subject:
McGuire Nuclear Station Docket Nos. 50-369 and 50-370
Dear Mr. Denton:
On January 23, 1981 the NRC issued License No. NPF-9 to Duke Power Company for fuel loading and zero power testing of McGuire Nuclear Station Unit 1. Con-dition 5 of this license requires that Duke provide a schedule for bringing McGuire in compliance with Regulatory Guide 1.97, Revision 2. The attached pages discuss those areas where the McGuire design meets this Regulatory Guide and provides a schedule for upgrading the remaining areas. Duke requests a meeting with the appropriate NRC personnel to discuss those areas identified in the attached as neading clarification.
Very truly yours, William O. Parker, Jr.
THH:pw Attachment
! cc: T. J. Donat Senior Resident Inspector McGuire Nuclear Station
\
h, i I
810.4290 N7
REG GUIDE 1.97 RESPONSE A detailed review of the McGuire Nuclear Station instrumentation has been performed per the guidance given in Regulatory Guide 1.97 (Rev. 2) and a Duke Power Company position established. The significant points of this position and the compliance of McGuire Nuclear Station are discussed in this document.
Variables All of the variable measurement channels required to assess plant and environment conditions during and following an ace? dent are presently in-stalled and operating at McGuire Nuclear Station (Refer to following table).
Certain variables tabulated in the 197 document are not measured by McGuire instrumentation. These particular variables either do not apply to the McGuire plant design or would not be utilized for operator action and accident analysis. An example of this type of variable is " heat removal by the con-tainment fan heat removal systed" as listed in Table 2 under Type D variables.
This variable does not apply to the McGuire station since the containment is of Ice condenser design and no credit is taken for ventilation system cooling during an accident.
Some new instrumentation (e.g. reactor vessel level) is being installed at McGuire as a result of new requirements stemming from the TMl-2 accident.
This Instrumentation has been or will be installed per the commitments and schedules provided previously in the document " Duke Power Company, McGuire Nuclear Station, Response to TMI Concerns."
Duke Power Company Positions on Regulatory Guide 1.97 Rev. 2 Type A Variables Regulatory Guide 1.97 Rev. 2 provides no new significant guidance concerning Type A variables.* The McGuire station Type A variables have been addressed previously in licensing documents submitted by Duke to the NRC.
Nuclear Safety Related Equipment The instrumentation installed at McGuire Nuclear Station as nuclear-safety related per the FSAR licensing basis meets the intent of the RG 1.97 Rev. 2 definition of Category 1 instrumentation.
i l
- As defined in RG 1.97 Section C.1.1 and including footnote 2 which defines primary information.
Qualification The environmental qualification of Category 1 Instrumentation located in .
a harsh environment has been addressed in the Duke response to NUREG-0588,
" Interim Staff Position of Environmental Qualification of Safety Related Electrical Equipment," dated October 14, 1980. Seismic qualifications are discussed in McGuire FSAR Chapter 3, " Design Criteria." Environmental qualification of Category 2 Instrumentation will require further discussion and clarification.
Quality Assurance information concerning the Quality Assurance program followed for McGuire Nuclear Station may be found in the McGuire FSAR, Chapter 17, " Quality Assurance." QA requirements for Category 2 instrumentation will require further discussion.
Ranges The Duke analysic has determined that more than 98% of the existing McGuire ranges for variables listed in Table 2 of RG 197 Rev. 2 are adequate for system operation under normal and accident conditions. (Refer to the attached table) However, these ranges do not always envelope the RG l.97 Rev. 2 ranges. Examples of this are the reactor coolant hot and cold leg temperatures, which are specified to be 50-750 F. .'n the RG 1 97 Table 2 listing. The Duke range of 0-700 0 F. is adequate since at 7000F, the saturation pressure is 3090 psia and system relief design pressure is well below that point.
For certain variables, plant accident procedures such as direct sampling of a variable are utilized to gather primary information where wide range instantaneous data is either unavailable or unnecessary. During accident conditions, these procedures are the preferred means of gathering this in-formation due to accuracy considerations. An example of this is the reactor coolant radioactivity monitor, which was not designed to quantify accident conditions and cou. . cot be assured of flow af ter RCP's are tripped. Direct sampling would then be a more accurate and appropriate means of measuring activity during and af ter an accident.
The instrument 6 tion (<2%) which Duke has determined requires recalibration of I the existing range for accident conditions will be modified by June, 1983 or by the end of the first refueling outage thereaf ter.
Diversity A diverse means of information verification has been provided at McGuire Nuclear Station for Category 1 instrumentation where failure of one channel could result in information ambiguity that could lead operators to defeat or fail to accomplish a required safety function.
Controls Layout Instrument grouping and identification will be addressed in the Duke response for Task 1.D.1 of NUREG-0660 and the yet-to-be issued NUREG-0700.
Neteorological Variables A discussion of the McGuire Meteorological System capabilities as they per-tain to NUREG-0654 is contained in an April 3,1981 letter from Mr. W. O.
Parker to Mr. Harold R. Denton. This letter deals with the McGuire Nuclear Station Emergency Plan.
Labora tory Capabili ties and Environs Moni toring The plant portable Instrumentation, sampling and laboratory analysis capabilities which now exist at McGuire Nuclear Station are adequate for normal and accident conditions and meet the intent of RG 1.97 Rev. 2. Further Information can be obtained in the McGuire FSAR Chapter 12, " Radiation Protection," and " Duke Power Company, McGuire Nuclear Station, Response to TMl Concerns."
Information concerning fixed radiation exposure meters at McGuire Nuclear Station will be provided as part of the Duke response for NUREG-0654 which is currently under development.
Processing Equipment Most of the variables specif'ed in RG 1.97 Rev. 2 are monitored by independent, dedicated instrument loops. Instrumentation to monitor the remaining variables is contained in the following McGuire systems: process instrumentation hard-ware, radiation monitoring hardware and Incore thermocouples.
Process Ins trumenta tion Hardware The Process Control System (PCS) is divided into Protection Cabinets and Control Cabinets.
The PCS Protection Cabinets were p ovided as nuclear safety related equip-ment and were seismically qualified. The instrumentation loops are sepa-rated into four redundant channels with each having its own independent, safety-related vital power source.
i Each instrument loop within a channel has an output isolation device which provides a signal for a control board Indicator and a second output iso-lation device which provides a signal for a strip chart recorder and the plant operator-aid computer.
The signal being provided to the computer is isolated such that an open circuit or short circuit will not affect the signal to the recorder or the control board indicator.
l l
Cable separat 8 on has been provided between the four instrumentation channels from the sensor up to and including the output isolation de-vice. in addition, instruments previously defined as post-accident-monitoring (PAM) devices have had one channel per variable separated from the other channels. This separation is from the output isolation device to the indicating device on the main control board.
Due to the above considerations, Duke concludes that the instrumentation in the Protection Cabinets meets the intent of the RG 1.97 Rev. 2 de-finition for Category 1 Ins t rumen ta t ion. Refer to the McGuire FSAR, Chapter 7. " Instrumentation and Control" for further discussion.
The PCS Control Cabinets were provided as high-quality instrumentat!on for use in non-safety related application. The power for these Control Cabinets is supplied from both a battery-backed auxiliary control power. <
bus and a reliable regulated AC bus. See the McGuire FSAR Chapter 8 for a description of the McGuire power systems. Output signals to Indication and/or recording equipment is provided through output isolation devices.
Due to the above-listed considerations, Duke concludes that the instru-mentation in the PCS control cabinets meets the intent of the RG 197 Rev. 2 definition of Category 2 Instrumentation.
Radiation Monitor Hardware Each instrument loop of the McGuire Radiation Monitoring System has an in-dividual power supply which is powered from a reliable battery-backed auxiliary control bus. All process radiation monitors are continuously indicated and recorded in the main control room, with additional hardware for trending capability. All area radiation monitors are continuously in-dicated in the main control room, with monitors pertinent to station operation providing inputs to the operator-aid computer.
Due to the above considerations, Duke concludes that the instrumentation in the Radiation Monitoring System meets the intent of the RG 1.97 Rev. 2 defini tion of Category 2 instrumentation. Refer to McGuire FSAR, Chapter 11, " Radioactive Waste Management, " Chapter 12 " Radiation Protection,"
and " Duke Power Company, McGuire Nuclear Station, Response to TMI Concerns" for further discussion of this system.
Incore Thermocouples Refer to Appendix 2.
A-
APPENDIX 1 Subcooling Monitor The McGuire Subcooling Monitor meets the requirements for Category 2 equipment, as called for in RG 1 97 Rev. 2. The subcooling margin is continuously monitored and is powered by a high reliability battery-backed power source (computer has a dedicated inverter). The display is a CRT in the main control room, with a " quick" call-up featJre as well as normal graphic display. The " quick" call-up utilizes one button for display access. The functional speci f ications for the Subcooling Monitor are given on page 11-9 of " Duke Power Company, McGuire Nuclear Station, Response to TMI Concerns."
This response is in answer to questions pertaining to NUREG-0737, item 11.F.2.
I i
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AITINIllX 7
- Incore Thermocouples 4 The following analysis is In response to NUREG-0737, i tem II .F.2 Attachment I,
" Design and quali fication Cri teria for Press,urized-Wa ter Reactor incore Thermocouples." Points are-addressed in the same order and format as -
followed in Attachment I of II .F.2:
(I) The McGuire incore Thermocouples are located at the core exit for cach quadrant, and in conjunction wi th core inlet RTD data, are sufficient to provide indication of radial distribution of the 1 coolant enthalpy rise across representative sections of the core. L There are a total of 65 core-exi t thermocouples. ,
(2) The primary operator display is on the operator-aid computer CRT. This system has the following capabilitics:
(a) A spatially oriented core map is available on demand which
- indicates the temperature at each core exit thermocouple location. This map can be displayed or printed on demand.
(b) An example of the McGuire selective readings is an on-demand tabular listing of all instantaneous incore thermocouple values.
This listing can be displayed or printed on demand.
(c) Di rect readou t of average and instantaneous values, as well as hard-copy capabilities, are provided for all thermocouple I tempe ra tu re s . The range is 0-2300* F.
] (d) Trend capabili ty showing temperature-time histories is designed into the system. Strip chart recorder points are available .to assign to any incore thermocouples on demand. In addition, a point-value trend printout is available on the control room typer.
(e) Alarm capabili ty is provided in conjunction wi th the Subcooling Moni tor, which uses the average, of all valid thermocouple ,
readings in its calculations and alarms when the value drops '
below the setpoint.
(f) The CRT displays are designed for rapid operator access and ease of viewing da ta , in addition, the incore program has a i validi ty-check comparison which reduces the probabili ty of accessing false readings.
(3) A back-up analog readout is provided wi th **no capabili ty of selective
, reading of any thermocouples in the system. The range will be extended
! to 2300' F. as di scussed in a telephone conversation with the NRC -
on March 24, 1981 and described in a letter of March 25, 1981 by Mr.
W. O. Parker to Mr. H. R. Ocnton.
4 4
(4) The displays for Incore thermocouples take the human-factors criteria listed into account. The same display is utilized for both normal and abnormal plant conditions. The validity-check feature only allows valid readings to be displayed. In addition the operators are trained in the use of tht; type of graphic display.
(5) Duke has reviewed the feasibility of upgrading the qualification of the existing McGuire incore thermocouples. This review has revealed that thermocauples which meet all of the NUREG 0737 requirements are not available at this time. However, Duke will continue to pursue the de-velopment of such incore thermocouples.
(6) Isolation between the primary and backup channels is implemented in the form of electrical switches.. The primary and back-up display channels are powered by a highly reliable battery-backed power source.
(7) (8) (9) Theexistingincorethermocoupleshstemisaverysimpleset of hardware which should, by virtue of its very simplicity, be a highly reliable and accessible system. The reliable and accessible normal CRT display and the existence of a backup display are additional factors which contribute to the overall system reliability.
1
3 t VARIABLE RG 1 97 ' DUKE RG 1.97 'tiUMBER OF ' tt0TES rat 1GE rat!GE CATEGORY CHAtli:E'_ S Reactor Vessel Core bot tom to Core bottom 1 2 channels level RV top to RV top 2 indicated (1) i recorded (R) 2 compute r points (CP)
Containment Sump Level 0 to 600,000 0-1,000,000 1 2 channels gal, level gal. level 2 I IR 2 CP Containment Hydrogen 0 to 30'/. O to 307, 1 2 channels Concentration 2 I IR
' 2 CP 100 to 10 7R/hr 0 0 Containment High Range 10 to 10 R/hi 1 2 channels Radiation Monitor 2I I R 2 CP Containment isolation Closed-!!ot Closed-flot i 1 channel Switch lights, monitor lights Valve Position Closed Closed 1 I I CP Prese .ri ze r t. eve l Top to bottom 0-1007, 1 3 channels PCS Protection Cabine t 3I 3 CP Sel. Rec.
Steam Generator Wide Tube Sheets 0-1007, 1 1 channel per SG PCS Protect ior. Cabi ne t Range level to Separators 1 Rec.
9 O
, VARIABLE RG 1 97 DUKE RG 1 97 nut 1BER OF NOTES RANGE RAf1G E CATEGORY CHANNELS Neutron Flux 10 107X 100 - 106 cps 1 2 Source Range Power 10-II 3 A 2 Intermediate 0- 12UX power la Power Range
- Selectable Rec.
capability incore Instrumentation 200*F-2300*F 200*F-2300*F I Computer Display (core-Exit Thermocouples) and Printout.
i Backup is an analog indicator.
Auxi liary Feedwate r Guaran- Plant Speci fi c ; Guaranteed so'u rce for Aux..ree -
teed Source water is provided by the '.uc ~ ea 4
Service Water Syster. See Mc3_:
o FSAR, Chapte r 9, " Aux iiia. y Systems" for furt* er i nfc ea:: c-NC Pressure O to 3000 psig. O to 3000 psig I 2 channels PCS Protect ion Ca':i ne:
21 iR I CP NC Hot Leg Temp. 50 to 750* F 0 to.700* F I I channel per loop FCS Protection Ca:ine:
IR I CP
- NC Cold Leg Temp. 50 to 750* F 0 to 700* F 1 1 channel per loop PCS Protect ion Ca
- i r.e:
1R I CP NC Radioactivity 5x10-I -3x10 10-2 -103 uC i /m i 1 i channel uCi/gm t I ~
I CP l Selectable Rec.
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'l VARIABLE P.G 1.97 DUKE i
pat 4GE RG 1.97 't1 UMBER OF tt0TES RAtJG E CATEGORY C HANilELS Steam Release Rad. 10'I to 103 uci/c Monitoring 102 tol03R/hr 2 I channel per steamlIne Loca tion wil l determine range in uCi/cc.
I I Total steam release program is being developed.
RHR Heat Exchanger 32-350*F Outlet Tempe ra t u re 50 f00*F 4
2 2 channels (1 per PCS Control Cabinet heat exchanger) 2R fil Accumulator Tank Level 10-90X Z_ .
0-100% 2 2 channels per PCS Control Cabinet Y---==
(0- Ilt i tMD) Accumulator 2 I per Accum.
M Containmbnt Spray F 6 O 0-110Z of design 0 f00 gpm4 2
~
2 channels (1 per PCS Cont rol Cab ine t M header)'
i 2I Q Volume Cont rol Tank Level Top to bottom
- Q 0-100% 2 1 channel PCS Cont rol Cabine t b
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Residual Heat Removal Floss 0 to 1107 Desigr. O'to 2500 gpm 2 O to 5000 gpm 2 channels (1 ea. Comauter point i s corron return (3000 gpm per heat exchanger) flow.
2 i design) PCS Control Cahiret I CP Boric Acid Charging Flow 0 to 1I0/ design 0 10 gpm4 2 1 channel PCS Cont rol Cab ir.i t (35 gpm design) l I
! I CP lR High Pressure inj. Flow ] to IIO7 design 0 to 1000 gpm 2 1 channel. *
(boron inj.,
i I PCS Cor t rol Cab i r.e t 550 gpm designi i CP O to 800 gpm 2 2 channels (I per (sa fe t y i nj . , header)
PCS Control Cabi..et 650 gpm designi 21 4
- . - ~
VA R I ABLE RG 1.97 DU KE RG 1.97 i iluttBER OF tt0TES RAtlG E RAtlG E CATEGORY CHAtitlELS Containment Wide Range -5 to 60 psig -5 to 60 psig I 2 channels 1
Pressure 1I 1R 2 CP Accumulator Isol. Open-Closed Open-Closed 2 1 chan-,el per viv. Annunciator, Monitor light Valve Pos i t i on 2I 1 CP Pressurizer PORV's Open-Closed Open-Closed 2 1 channel per viv.
I 2 l 1 CP Pressurizer Code Relief Open-Closed Open-Closed 2 I channel per viv. Annunciator Valves
- 2 i Low Pressure inj . Flow 0 to 1107 design 0 to 2500 gpm 2 2 channels ( l ea . Computer Point is ccmmon return (RHR Fic.9) O to 5000 gpm per header) flow (3000 gpm desig i) 21 PCS Control Cabinet I CP Ma i n S t ean Fl ow 0 to 1107 design 0-1207 2 2 channels (per SG) PCS Control Cab inet 21 2 CP CVCS Hakep-up Flow 0 to 110/ design 0 to 200 gpm 2 Ichannel PCS Cont rol Cab ine t in (100 gpm i I design)
CVCS Letdown Flow Out 0 to 1107 design 0 to 200 gpm 2 1 channel PCS Control Cabinet (120 gpm design. I I Degree of Subcooling 200*F subcooled calculated 2. I channel Calculations done continuously b3 to 35' super- value I graphic OAC. Displayed on demand.
. heat
VARlABLE RG 1.97 DUKE RG I.97 i ilVMBER OF !!0TES RAtlGE rat 4G E CATEGORY CilAtlflELS Emergency Vent Damper Jpen-Closed (' pen-Closed 2 I channel per Switch indicator and/or Position damper (a t least) status light.
Active dampers and isolation valves which are ac:uated u-Yc accident conditions whoce failure could resul: in a radioactive release to atmos: :
are indicated. Also, Contro' Room isolati on is i-dicated.
Pressurizer Relief Tank lop to bottom 0-100% 2 I channel FCS Control Cabinet Level (0-100 INWD) 1 I I CP
-6 -2 Containment Release Gas 10 to 10 N/A 2 Moni tor is rot requ: red, ra'c_.
Rad. Monitor uCl/cc is through Unit Ver:.
til Accumulator Tank Pressure O to 750 psig 0 to 750 psig 2 2 channels per tank PCS Contro! Cabine: === I 8i <
Pressurizer lleater Status current Bkr. status 2 I channel per Z
contactor statu- device 13I!
1 I ea. gg 1 C P ea . Q SG Pressure O to 20'/ above 0 to 1300 psig 2 3 channels per loop PCS Protec: ion Ca: inet g=gwa low safety valve (0 to 10% 3 1/ loop g===g set point 3 CP/ loop above low safet) g= mag valve set point, gg Unit Vent Radiation 10-6to 10b uti/cc 10-6 to 103 2 Monitoring for 0 to 110/, 100 to uClfcc 10 R/br vent flow e
VARIABLE RG l.97 DUKE RG 1.97 t! UMBER OF NOTES PAtJGE PAtJG E CATEGORY C HAtitiELS Other Release Point 10-6 to 10 2 10-6 to 10-I 2 I channel per devica Radiation Monitoring uCl/cc uCi/cc I I/ device (Contaminated Materials Whse. and Interim Radwaste Faci l i t y)
Containment Heat Removal plant speci fic N/A 2 by AHU Containment Sump Wa ter 50 to 250' F none 2 Variable is nc: used for o: era::
Temperature action nor necessary for accide-analysis.
Area Radj at ion Moni tori ng 10-I to 10 bR/h IO-I to 10b mR 'h r 2 1 channel per device 1 1/ device i
)
Auxiliary Feedwa te r Flow 0 to l107, design 0-400 gpn 2 4 channels ( l per SG) -
4i RWST Level top to bottom 0 to 160" WD 2 3 channels 3I 3 CP 160 to 500" WD 2 I channel i I I CP Component Cool ing Va te r 32 to 200* F So to 150' F 2 I channel (per Temperature to ESF header) 1 CP Component' Cooli ng Va te r 0 to l107 design 0 to 6000 gpm 2 1 channel ( per flow to ESF (5000 gpm desigi ) header)
. i. ,
t
. VARIABLE RG l.97 DUKE RG l.97 '
NUMBER OF NOTES RANGE RANG E CATEGORY C HANNEL S i
Containment Atmosphere 40 to 400*F 0 to 300* F 2 8 channels (4 i n j Temperature upper Contai nment i and 4 in lower l con ta i nment )
8 CP l Sa f e t y Powe r S t a tus Current, voltage status and 2 All safety poaer systems are i
a l a rms alarmed in the control roon l tc indicate abnornal ooeration.
I Local indication is provided for analyzing sys tem t rouble.
High Level Radaaste Tank Top to bottom 0-100% 2 I channel Local indicator and High Leve; Level , 1 CP Ar.nunciator also available.
Boron Concentration 0-6000 ppm 0-5000 ppm 3 1 channel .
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Pressuri zer Relief 50 to 750* F 50 to 300* F 3 1 channel F S Control ebinet Tank Tempera ture ! I i
l Condensate. Storage Tank Plant speci fi c 0 to 100% 3 1 channel A nunciator a 'arn when tar'< -
l Level (o to 12 f t .) 1I is not full.
Radioactive Gas Holdup 0 to 150Z design 0 to 150 psig 3 I channel Tank Press (100 psig desig n) 1 CP HC Pump Status Motor Current 0 to 800A 3 1 channel per pump 1 l l
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