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MONTHYEARML20195J6251988-06-16016 June 1988 Requests Addl Info Re Facility Pump & Inservice Testing Program to Complete Review.Info Requested Identified in Encl,Including App J,Type C Leak Rate Tested Valve Listing Project stage: Other ML20150E4221988-07-0808 July 1988 Notification of 880816,17 & 18 Meetings W/Util in Cornelius, Nc to Review Pump & Valve Inservice Testing Program Project stage: Meeting ML20151U5061988-08-11011 August 1988 Responds to Ds Hood 880616 Request for Addl Info Re Plant Pump & Valve Inservice Testing Program for 10-yr Insp Interval.Nrc Approval Sought by End of Year in Accordance W/ Proposed Schedule Outlined in 880506 Submittal Project stage: Request ML20155D6341988-10-0606 October 1988 Forwards NRC Stating Position on Exercising PORVs & PORV Block Valves to Help Resolve Unresolved Item Noted in 880908 Inservice Testing Meeting Summary Project stage: Meeting ML20205P2241988-10-31031 October 1988 Forwards Revs 11 & 7 to Pump & Valve Inservice Testing Program, for Units 1 & 2,respectively.Rev Reflects Results of 880816-17 Meetings Between Util & NRC & Eg&G to Finalize Inservice Testing Program Project stage: Meeting ML20245G1971989-04-19019 April 1989 Forwards Unit 1 Rev 12 & Unit 2 Rev 8 to Plant Pump & Valve Inservice Testing Program.Rev Corrects Typos & Other Errors in 881031 Revs 11 & 7 Program Submittal,Per Generic Ltr 89-04 Project stage: Other ML20247H4361989-05-16016 May 1989 Advises That All Valves Added to Rev 11 & 7 to Units 1 & 2 Pump & Valve IST Program,Respectively W/Listed Exceptions Project stage: Other ML20244D0621989-06-0606 June 1989 Informs That Util Will Pursue Change from Displacement to Velocity Vibration Measurements by 891010 Project stage: Other ML20065R8501990-12-10010 December 1990 Forwards Rev 15 to Unit 1 Pump Inservice Testing Program & Rev 11 to Unit 2 Pump Inservice Testing Program. Revs Are Result of Program Enhancements Identified by Plant Desgin Study 0106 & Recently Issued Design Basis Documents Project stage: Other ML20072T6731991-04-0808 April 1991 Forwards Rev 16 to Unit 1 Pump & Valve Inservice Testing Program & Rev 12 to Unit 2 Pump & Valve Inservice Testing Program, Consisting of Relief Request 91-01 Project stage: Request 1988-08-11
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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
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11 I fint e Ihu er l'ompany M S 1Iase\\
%<leor1 %iviIvatIhjt \ rt l'in %!t u'
/*ll ILA luit, w in rl % rdirns Cham,ttr \ (' ?l.10 I ! 701 G 7.1 R.;l i DUKE POWER April 8, 1991 U.S. Nuclear Regulatory Commission AT*1'N : Document Cont rol Desk Washington, D.C. 20555
Subject:
McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 and 50-370 Pump and Valve Inservice Testing Program Program Revleion 16 (Unit 1) and 12 (Unit 2)
{Rollef Request No. 91-01)
(TACS 61271/61272)
Gentlemen:
Please find enclosed (pursuant to 10CFR 50.4 and 50.55a(g)) for NRC staff use and review ten copies of Unit. 1 Revision 16 and Unit 2 Revision 12 of the McGuire Nuclear Station Pump and Valve (IWP/IWV)
Inservice Testing Program.
These revisions are the result of nrogram enhancements identified by McGuire Design Study 0106, recently issued Design Basis Documents, and the recently received Safety Evaluation Report (SER) of the IST program.
The changes to the valve portion are summarized on Attachment 1, and the pump portion on Attachment 2. Only the affected pages are attached.
The McGuire SER was based on Unit 1 Revision 14 and Unit 2 Revision 10 of the IST program. Unit 1 Revision 15 and Unit 2 Revision 11 were issued prior to receiving this SER, and the changes included in them are not recognized by the NRC. The attached revisions resubmit those changes previously identified in the last revision, as well as additional changes.
Since this revision includes additions and deletions which are outside .
the scope of Generic Lotter 89-04, Section D, it is requested that the NRC review this material and notify Duke Power Compn.ny by July 1, 1991 as to its acceptability.
If you have any questions regarding the enclosed material, please call L.J. Rudy at (704) 373-3413.
Very trul yours, R.s. \ ww M.S. Tuckman LJR/s Attachments / Enclosures
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l Document Cont rel Desh April B, 1991 Page 2 a
4 xes (With Attachments / Enclosures) 1 Mr. S.D. Ubneter I
-Regional Administrator, Region 11 ]
U.S. Nuclear Regulatory Comm18Hlon )
101 Mariett a St. , NW,- Suite 2900 ,
Atlanta, Georgia 30323 l Mr. C.R. Ransom EC&G Idaho, Inc.
Idaho Nationa.1 Engineering 1.aboratory 1520 Sawtcllo St. 4 Idaho Falls, Idaho 83407 l Mr. T. A.- Hood, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulat ory Commission One White Flint. North, Hall Stop 9113 ,
-Washingson, D.C. 20555 Hr. P.K. Van Doorn [
NRC Sentot Roaldent-Inspector McGuirn Nutlear Station k
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A T T A CllM Eff T 1 McGUIRE Uti!TS 1 A!1D 2 IWV PROGRAM REVISIOf1S ,
1 11ote: Revisions are for both Units unless indicated otherwise.
- 1. Table of Contents a) Added Airlock (I A) system b) Added Diesel Generator Cooling Water (KD) system l c) Added control Area Ventilation (VC) system - Unit 1 only d) Changed page numbers appropriately, l
- 2.Section II.2 Table of Abbreviations a) Added FS Tail Safe to Legend
- 3.Section II.3 Definitions a) Added railsafe (PS) and defined how failsafe testing will be conducted.
- 4. Section 11.4 Data Sh9ets a) All data shoets were revised to exclude stroke time requirements. " Rapid Acting" 2 second valves were identified in the remarks column of revision 15 & 11, but removed in revision 16 & 12.
b) Data sheet page numbers changed to reflect addition of IA,KD and VC systems in both units.
c) CA-0020AB, CA-0027A, CA-0032B Changed category to AC and added LT to test requirements. It was determined that leakage past these valves is critical because it would not be directed to the S/G's, d) CA-0161C, CA-0162C Deleted from the program because the valves were determined not to have a safety functior per Design Study MGDS-0106, e) CA-0165, C A-0166 Added MTC to valves. Design Study 0106 determined valves have a safety function to close.
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f) FD-0092, FD-0104 Added MTC to valves. Design Study 0106 determined the valves have a safety function to close, g) FD-0093, FD-0105 New valves added to the program identified by Design Study 0106.
h) I A-5080, IA-5160, IA-5340, IA-5350, I A-5360, I A-5370, IA-5380, IA-5390 New system and valves added to program as a result of review of program and modification to airlock valves.
- 1) 1RC-0001 A Removed one of two listings for this valve - Unit 1 only.
j) 1KC-0340 Corrected typographical error. Changed LY to LT.
k) 2KC-0340 Corrected test requirements. Deleted ST-Q. Added LT-RF.
- 1) KC-0800 New valve added to the program identified by Design Study MODS-0106, m) 1KC-0897,1XC-0903, IRC-0958 New valves added to the program identified by Design Study MODS-0106, n) KC-0972 Changes Test Requirement frequency from SP-RF to SP-3R.
Addition of KC-0600 into this test group changes the frequency interval, o) KD.-0009, KD-0029 New system and valves added to program identified by Design Study 0106.
i.
p) NF-0228a, NF-0233b, NF-0234A i Deleted relief request NF-? as a result of SER.
q) NI-01368-Changed to cold shutdown valve.
r) NS-0004, NS-0021 Added MTC to valves. Determined to have a safety function to close per Design Study 0106.
s) NS-0038B, NS-0043A Changed to cold shutdown valves.
t) NV-0001A, NV-0002A, NV-0022. NV-0842AC NV-0844, NV-1007, N'/-1008, NV-1009 NV-1010, NV-1012C, NV-1013C Valves deleted from IwV program. They were d6: ermined not to have a safety f inction per Design Study '0106.
u) NV-1002 Deleted test requirement Mio. Valve evaluated not to have a safety function per Design Study 0106.
-v) NV-1046 Added valve to program. Identified by Design Study MGDS-0106.
W) 2NV-0035A Added valve to program. New valve in system to serve same function as 2NV-0459A. Added per NSM MG-22123.
- x) 2NV-0459A l Deleted valve from program. Valve replaced with 2NV-0035A per NSM MG-22123.
l y) ORN-0004AC, ORN-0148AC l Last revision incorrectly deleted these valves from L submittal. This revision adds them back to submittal.
They were never removed from testing program.
- 2) RN-0021A, RN-0022A, RN-0025B, RN-0026B l- Cold shutdown justification deleted. Timing method now permits quarterly testing, i
e- W ;' -- w
aa) 1RN-0042A,1RN-0063B , IRN-0064 A,1RN-0252B 1R N-0253 A , 1RN-0276 A , 1 R N-0277 B Corrected cold shutdown justification numbers, bb) 1 R N-0442, 1 R N-0445, 1 R N-0457, 1 RN-0460 New valves added to the program. Identified by Design Study MODS-0106.
cc) 2RV-0126, 2RV-0130 Deleted valves from program. NSM MG2-2247 removed these valves ,
dd) 2RV-0445, 2RV-0446 Added valves to program. NSM MO2-2247 installed these valves, ee) SM-0009 AB , SM-0010AB , SM-0011 AB , SM-0012 AB Cold shutdown justification deleted. Timing method now permits quarterly testing.
ff) 1VC-0001 A, IVC-0002A, IVC-0003B,1VC-0004B IVC-0009A, IVC-0010A, IVC-0011B, IVC-0012B New system and valves added to the program identified by Design Basis document MCS-1578.VC-00-0001.
gg) VG-0003, VO-0004, VG-0017, VO-0018 VG-0019, VO-0020 New valves added to the program identified by Design Basis document MCS-1609.VO-00-0001, hh) 1VI-0040,1VI-0124, IVI-0129B, IVI-0148B IVI-0149,1VI-0150B, IVI-0160B,1VI-0161 IVI-0362A Flow diagram numbers and coordinates changed to reflect redrawn flow diagrams.
11 ) VI-0135, VI-0136, VI-0137, VI-0138 VI-0139, VI-0140, VI-0141, VI-0142 Valves added to the program. Identified with PIR 0-MC9-0239.
jj) 2WE-0013, 2WE-0023 Deleted valves from program. NSM MG2-2244 capped penetration and removed these from the containment isolation valve list, kk) 1 Y C -0054 , 1Y C -0076, 1 Y C -0113, 1 Y C -0135 1 Y C -0148, 1 Y C - 0162, 1 Y C -0176, 1 Y C -0190 1 Y C-0204, 1 Y C -0218, 1 Y C -0232, 1 Y C-0246 1YC-0347,1YC-0357 Valves added to the program. Identified with PIR 0-MB9-72.
- 4. Section 11.6 Specific Relief Requests a) RR-CA1 Added description of why valves cannot be partial stroke tested, b) R R-I A1 New relief request added as a result of adding valves to program, c) RR-NB1 Clarified alternate testing will performed in accordance with Appendix J.
d) RR-NF1 Deleted basis 82. Tech specs allow testing this penetration without draining glycol.
e) RR-NF2 Deleted relief request. Tech Specs allow testing this penetration without draining glycol.
f) RR-RV1 Deleted relief request. Valves removed by modification NSM MG2-2247. Unit 2 only.
i g) RR-VI3 New relief request added as a result of adding *es to program.
- 5. Section 11.7 Cold Shutdown Justifications a) CS-TW1 Deleted 'but prior to Mode 3 (Hot Standby)' in alternate testing . FW-0027A can be cycled closed for testing pursuant to Tech Spec 4.4.6.2.2 in Moda 3. The valve may be tested at that time.
b) CS-FW2 Deleted ' and partial stroked quarterly.' Testing method avatlable does not verify partial stroke, c) CS-ND4 Corrected typographical error on Unit 1. Changed ' seal' to ' seat' in alternate testing. Added 'and depressurized' following 'at cold shutdown.' ND-70 can not be seat leak tested unless the NC system is depressurized, d) CS-NDS Replaced ' done at refueling' with ' performed at cold shutdown' to altminate the conflict of terms. Added
' and depressurized' following 'at cold shutdown.'
ND-71 can not be seat leak tested unless the NC system is depressuri:ed, e) CS-ND6 Corrected spelling error on Unit 1. Changed ' presure' to ' pressure' in Basis, f) C S-NI17 Deleted ' by acoustic emission monitoring' in Alternate Testing. This method of testing is not used on these valves .
g) CS-NI21 New shutdown justification for NI-136B. Stroking NI-136B on line degrades the ND system.
h) CS-NS1 New shutdown justification for NS-38B and NS-43A.
Stroking these valves on line degrades the ND system.
- 1) CS-NV3 Shutdown justification deleted because NV-1 A and NV-2A were deleted from the scope of IWV per Design Study MOD S-0106.
j) CS-NV5 Shutdown justification deleted because NV-22 was deleted from the scope of IWV per Design Study 0106.
k) CS-NV6 Shutdown justification deleted because NV-1007, NV-1000, NV-1009 and NV-1010 were deleted from the scope of IWV per Design Study 0106,
- 1) C S-NV10 (Unit 2 Only)
Shutdown justification deleted because 2NV-459A has had its function replaced by 2NV-35A per NSM MG-22123. With new valve characteristics, the vibration concerns are no longer valid.
m) CS-NV16 New shutdown justification added because of NV-1046 added to the program identified by Design Study 0106.
n) CO-RN1 Shutdown justification deleted. Valves RN-21A, RN-22A, RN-25B and RN-26B have enhanced timing methods that allow the valves to be timed quarterly, o) CS-RN4 Replaced ' the charging pump' with ' heat exchangers' in Basis to eliminate confusion, p) CS-SM2 Shutdown justification deleted. Valves SM-0009AB, SM-0010AB, SM-0011 AB, SM-0012AB have timing methods that allow the valves to be timed quarterly.
l q) CS-VG1 tiew shutdown justification added because of adding VG-17, VG-18, VG 19 and VG-20 to the program identified by Design Basis document MCS-1578.VC-00-0001.
r) CS-FW2, CS-tid 4, CS-tf DS, CS-IID6, CS-11113, CS-title, CS-ti115, CS-lil16, CS-11117, CS-ill18, CS-til19, CS-til20, CS-tiV14, CS-liv 15 In Alternate Testing, deleted ' but not more often than once per nine months' for the above Cold Shutdown Justifications.
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