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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
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{{#Wiki_filter:.
DUKE POWEH COMPANY Powen Unitnixo 422 SorTn Curucu STnEET, CHARLOTTE, N. C. 28242 wauw o. pan a cn. s n. March 23, 1979 Vice PREssOFNT ICLEPwCNE AREA 704 STEAM FRODvC?iOM 373-4083 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. Robert L. Baer, Chief Light Water Reactor Project Branch No. 2 Re: McGuire Nuclear Station Units 1 and 2 Docket Nos. 50-369, 50-370
Dear Mr. Denton:
Your letter of February 7, 1979 identified several deficiencies in Duke's proposed radiological effluent technical specifications, in particular a lack of technical specifications on waste solidification. Attached are pages from the standard technical specifications concerning solidification marked to reflect reasonable requirements on solid waste control for McGuire Nuclear Station.
We will be happy to meet with you to discuss this matter.
Ve truly yours,
/ .
O %.1 O. _-
William O. Parker, Jr GAC:scs Attachment 0*gPROGqES,S 4
vL h * *o t
*2 6'
e a \
th 4"ni = sary 7 9 0 3 2 7 0 3 8'l %eAoWgg0A 19 /
i i.
l.0 DEFINITIONS CHANNEL CALIBRATION I
- 1.9 A CHANNEL CALIBRATION shall .be the adjustment, as necessary, of the
- i I
chennel output such that it responds with the necessary range and cccuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBkATION shall encompass the entire channel including the sensor e.1d i alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.
The CHANNEL CALIBRATION may be performed by any series of sequential, over-l, lapping or total channel steps such that the entire channel is calibrated.
, CHANNEL CHECK l
'l.10 A CHANNEL CHECK shall be the qualitative assessment of channel be-havior during operation by observation.. This determination shall include, qwhere possible, comparison of the channel indication and/or status with
' ; other indications and/or status derived from independent instrunentation ichannels measuring the same parsneter.
t
., CHANNEL FUNCTIONAL TEST 9
l1.11 A CHANNEL FUNCTIONAL TEST shall be:
i n
; j, a. Analog channels - the injection of a simulated signal into
! if the channel as close to the sensor as practicable to verify
., OPERABILITY including alarm and/or trip functions. "~~
l
! b. Bistable channels - the injection of a simulated signal into
' the sensor to verify OPERABILITY including alarm and/or trip
! functions.
SOURCE CHECK i
1.29 A SOURCE CHECK shall be the qualitative asses: ment of channel response when the channel sensor is exposed to a radioactive source.
PROCESS CONTROL PROGRAM 1.30 A PROCESS CONTROL PROGRAM (PCP) shall be the manual or set of Operat?"; procedures detailing the program of sampling, analysis, and evaluation within which SOLIDIFICATION cf ccdiccctive ::t:0 ' ;r liquid ca;t: : is assured. Requirements of the PCP are provided in Specifica-tion 6.14.
PWR-STS-1 1-1 i
f
l -
N 1.0 DEFINITIONS (Continued)
SOLIDIFICATION
@,. ,a ,rc ;
1.31 SOLIDIFICATION shall be the conversion of radioactive rwastes 4*sn liquid :y:te~ to a bemogerecut Tuniformly distributedf, mencl*thic, l immobilized solid.t;'tb def'-ite volere Ord b:pe, bcurded by : t:ble-sw4 ace of distinct Outli .c on al' ide: ( frec : tan 44my).
2 OFFSITE 00SE CALCULATION MANUAL (0DCM)
-{
' 1.32 An 0FFSITE DOSE CALCULATION MANUAL (0DCM) shall be' a manual contain-ing the methodology and parameters to be used in the calc 01ation of off-l site doses due to radioactive gaseous and liquio effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints. Requirements of the ODCM are provided in Specification 6.15.
i GASEOUS RADWASTE TREATHENT SYSTEM l 1.33 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and in-i stalled to reduce radioactive gaseous effluents by collecting primary l coolant system offgases from the primary system and providing for delay
+
or holdup for the purpose of reducing the total radioactivity prior to
; release to the environment.
I
{ VENTILATION EXHAUST TREATHENT SYSTEM i
1.34 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radiciodine or radioactive material in parti-culate form in effluents by passing ventilation or vent exhaust gases throuch charcoal adsorbers and/or HEPA filters for the purpose of removing fodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gr.s effluents. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
9
, PWR-STS-1 1-2
l RADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLID RADI0 ACTIVE WASTE ;
l' LIMITING CONDITION FOR OPERATION l
, p ..o..<,*vry--anw; 3.11.3.1 The solid radwaste system shall/be OPERABLE and used to pro- ,
vide for the SOLIDIFI A and packaging of othe,C,d,T, ION wastes, r radioactive of vict clidhastes, and to c ruforc the the SOLICIFICl, meeti"; cf TION the requirements of 10 CFR Part 20 and of'10 CFR Part 71 prior to ship-
, ment of 4efst4ve containers of radioactive wastes from the site.
APPLICABILITY: At all times.
ACTION: -
- a. With the requirements of 10 CFR Part 20,10 CFR Part 71, and the PROCESS CONTROL PROGRAM of Specification 6.14 not satisfied, suspend shipments of defective containers of solid radioactive wastes from the site.
- b. With the solid radwaste system not OPERABLE for more than 31 days, when required to meet 10 CFR Part 20 and 10 CFR Part 71, I prepare and submit to the Commission within 30 days, pursuant
! to Specification 6.9.2, a Special Report which includes the
! following information:
- 1. Identification of equipment of subsystems not OPERABLE and the reasons for inoperability.
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status.
t
- 3. A description of alternative used for SOLIDIFICATION and packaging of wastes.
- 4. Summary description of action (s) taken to prevent a re-currence.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not appl icabl e.
SURVEILLANCE REQUIREMENTS 4
4.11.3.1.1 The solid radwaste system shall be demonstrated OPERABLE at least once per 92 days, or there be the capability for SOLIDIFICATION of waste by meeting one er more of the conditions below:
l PWR-STS-1 3/4 11-20
, L w - ,
s;.(
SURVEILLANCE RE0VIREMENTS (Continued)
- a. By perfomance of functional tests of the equipment and com-ponents of the solid radwaste system.
- b. By operating the solid radwaste system at least once in the previous 92 days in accordance with the PROCESS CONTROL PROGRAM. '
- c. Verificaticr of the f:xistence of a valid contract for SOLIDIFI-i i
CATION to be perfomed in accordance with a PROCESS CONTROL '
. PROGRAM.
I 4.11.3.1.2 The PROCESS CONTROL PROGRAM of Specification 6.14 shall be l used to verify the SOLIDIFICATION of at least one cprc:^ntative tcst
-spaci cr '~' :t le=t every tenth batch of each type of ws4-radioactive sLrry d mal' waste.(e a., #4'ter ciudget, pent recia. , evaporator bottomsr-bor-ic-ac-id-sclutions, codium tul fetc sclutten:, :nd fil ter media). The test peci .cn; '
shall be prccened ir the radicchrical er .;=tc procc::ing labcratcry in s e. e_ m. .a .. .,. .. . . 4. +. w, m.
,. ..m. , m a . . m ,. . . m . ,, e, + u. mn. .o. n.,r. e c. e.,
. . e,, n. u. .r. ,.
,. n, ., n,,
,n .n, n en. ,a,,u, .
- o. T. t. ..,.a.
m
. .,.J._..-.
.m . . E. 2 1. .,
A T,
- - ent J. r. ,. s v T e t t- T e a v. .Tun,
...mn nu AL-uns svui-e nt T Am
. r. . .,.. ,k..
n .t r-
. . T..me a v. T...n u. A L. . - L.
. . . .ec
. + h. ..,3 1 km ...
.,.m,,m,. A. n..A.
. . . . n. &. t. i.
- uch time = cdditional test ,p^ciment-car be ob+2iacd 21- ,
teenative___,
SOLIDIFIC,"T0" par =cter . c= be dete-t .cd 4a
. _.,. -,.wn ... u.. - nn .m. nr ec.e,
... n. i n.n.
.n n.. u. .e n. n e.n, ,, u. , .a , , ,
... ... . ... . . .x.
. m. ,. . . m. , t i
te;t verific , SOLIDIFIC^TIONMDIFICAT10" of-the4atch-may [
rr_ : _
then-be __a resumed-ttsing-the-elternatiye-SOL-IDIFICATION-parameters d . ._m_ . u., . .- n.n r-
. . . . . u, . m,. . . .ne.r e. . e,
. e. n. u.r.
. . n. n i.m nn nenm AM. i
- b. If the initial test spec-imen from-a-batch-cf waste fails to- ~
verify SGL-IBIFIGAT-ION,-the-PROGESG-CONTROL P20GRA" hall peo-vide-foe-the-coMeet4en-and-test 4ng-o-f-reprcrentativc test spee4 men fr= coeh-consecutive 4atch-of-the :=c type-of-
- et m.ste until 3 con ccut've initici tc t pec' c= d=cr -
strate .c,.o' '..n..' .c .' e .^.". . .a.". .
. ^
. ."o . .0GE.c..c,
. . e, n. ."T. o. m'.
, Do. n,.c"..a.u. , u. . .s. s. i..s,e e
}
modi-fied-as-requi ,
redr-as-prov4ded-in--Spec 4f4 cat 4en-6vl4rto *
...e.,n
.v. n. .v. e v e. . .v. m, . , . . n., .u.. .x . m m y.
. . m. .. x.. ..
. , u. m. n, m. .e , + n. .
I e
4.11.3.1.3 Reports - The semiannual Radioactive Effluent Release Report shall include the following infomation for each type of solid waste l shipped offsite during the report period: :
- a. container volume, i
- b. total curie quantity (detemined by measurement or estimate), t l
PWR-STS-1 3/4 11-21 9
- 9. SG
SURVEILLANCE REQUIREMENTS (Continued)
\
- c. principal radionuclides (determired by measurement or estima te),
i
- d. type of waste (e.g., spent resin, compacted dry waste ,
evaporator bottoms), t
- e. type of container (e.g., LSA, Type A, Type B, Large !
Quantity), and !
- f. solidification agent (e.g., cement, urea formaldehyde).
}
i PWR-STS-1 3/4 11-22 l i
8 .s .
f l
ADMINISTRATIVE CONTROLS I
l 6.14 PROCESS CONTROL PROGRAM (PCP) 6 d q'Z% e h- se.t ob 6.14.1 The PCP shall beMmanual]centaining the equip ent ^a^-'+'
terc .cet po4ntw-dr-awi-ngs-and-contrcl s, and tAe '
cdueen-peocess-pagi!dEk labe atery procedures the program of sampling, analysis, and evaluation within which solidification cf adicactive statte: # c- 'iquid 3., stems is assured, consistent with Specification 3.11.3.1 and the sur-veillance requirenents of these Technical Specifications.
The PCP chall bc submitted--tMhe-Comn4ssion-at-the time of properbd Radio-logical Ef" cent Technical Specification: :nd shal' be cubject +^ reviev and apprev:1 by the Cem-iccier prier to ".plc=enution.
6.14.2 Changes to the PCP shall be made by either of the following methods:
A. Licensee initiated changes:
; 1. Shall be submitted to the Commission by inclusion in the semiannual Radioactive Effluent Release Report for the ;
period in which the change (s) was made and shall contain:
[
fl a. sufficiently detailed infomation to totally support the rationale for the change without benefit of addi-
. tional or supplemental information; l f
i; b. a detemination that the change did not reduce the i i, overall confomance of the solidified waste product !
l; to existing criteria for solid wastes; and I
l i
- c. documentation of the fact that the change has been reviewed and found acceptable by the (URG).
- 2. Shall become effective upon review and acceptance by the (URG), unless otherwise acted upon by the Commission through written notification to the licensee.
B. Commission initiated changes: , a _ug
- 1. Shall be detemined by the (URG) to bedpplicable to the facility after consideration of facility design. ~ ~
- 2. The licensee shall provide the Commission with written notification of their detemination of applicability in- j cluding any necessary revisions to reflect facility design, i, f d"PM- ;
- 3. Shall be reviewed by the (CNRAG) at its next regularly !
scheduled meeting.
PWR-STS-1 6-27 4 4 9 A
9}}
