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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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DUKE POWER GOMPANY l'.o. nox 33180 GHARLOTTE, N.C. 28242 IIAL II. TUCKEH reternoxe m e rer.aoe=, (yo4) 373 433 METE.EA. PINDDUCTRO4 February 14, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: McGuire Nuclear Station, Unit 2 Docket No. 50-370
Dear Mr. Denton:
Attached is a letter from Duke Power Company to the U. S. Department of Energy (DOE) dated February 8, 1983 which provides three copies of Duke Power Company's comments on the proposed Contract for Disposal of Spent Nuclear Fuel and/or High Level Radioactive Waste. In addition to providing comments on the proposed contract, the attached letter also affirms Duke Power Company's intention to execute the required agreement with DOE as specified in Section 302(b) of the Waste Act of 1983.
This letter is being provided to the NRC in advance of the anticipated notice from DOE to the NRC advising the NRC of Duke Power Company's " good faith nego-tiating" with DOE in order to allow the NRC to proceed with necessary actions for licensing of McGuire Nuclear Station, Unit 2.
Please advise if there are any questions regarding this matter.
Very truly yours,
//L/ $ NcE' W n ol Hal B. Tucker GAC/php Attachment g;
D cc: (w/ attachment) g.s)Ws Mr. W. T. Orders Senior Resident Inspector McGuire Nuclear Station Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 l
Atlanta, Georgia 30303 l
8302170327 830214 PDR ADOCK 05000370 PDR A
Mr. Harold R. Denton, Director 3-February 14, 1983 Page 2 cc: (w/ attachment)
Mr. R. A. Birkel
- Office of Nuclear. Reactor Regulation i U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. J. M. Cutchin 4
Office of Executive Legal Director U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. W. J. Olmstead Office of Executive Legal Director U. S. Nuclear Regulatory Commission Washington, D. C. 20555 t
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. DUKE POWER GOMPANY P.O. HOx 33189 CHARLOTTE, N.C. 28242 HAL B. TUCKER Tzt.crosown vwn Paesinen (704)373-4531 fr00 LEAR PRUDON February 8, 1983 Mr. Robert Morgan, Project Director Nuclear Waste Policy Act Project Office U. S. Department of Energy 1000 Independence Avenue, S. W., Room 7B-084 Washington, D. C. 20585
Subject:
Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste (48 F. R. 5458; Friday, February 4,1983; 10 CFR 961) Preliminary Comments
Dear Sir:
Duke Power Company appreciates the opportunity to provide the enclosed preliminary comments on the subject proposed Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste. Ten copies of these comments are provided as requested in the Federal Register notice.
l l As you know, these comments are being provided substantially in advance of the date (March 7, 1983) called for in the Federal Register notice. As noted below, we have prepared and submitted these preliminary comments to enable DOE to provide information to the NRC pursuant to Section 302 (b) (ii) l of the Waste Act. We hope that these early comments will be useful to the l Department in meeting the tight schedules for contract execution mandated by P. L.97-425; the Nuclear Waste Policy Act (Waste Act). Althcugh we are covering here most of the major substantive issues with which we believe we.
must deal in executing a final agreement, we do wish to reserve the right to amend, or expand, these comments during the comment period provided pursuant to the Federal Register notice.
l Section 302 (b) of the Waste Act provides in pertinent part that "[t]he l [ Nuclear Regulatory] Commission shall not issue or renew a licensa to any
! person to use a utilization or production facility under the authority of Section 103 or 104 of the Atomic Energy Act of 1954 (42 U.S.C. 2133, 2134) unless - (i) such person has entered into a contract with the Secretary (of Energy] under this section; or (ii) the Secretary affirms in writing that such person is actively and in good faith negotiating with the Secretary l
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Mr. R:bart Margin
. Pagn .2
,Februtry 8, 1983 for a contract under this section." We are scheduled to load fuel in Unit 2 of our McGuire Nuclear Station on March 1, 1983. Therefore we seek the grant of an operating license for that unit from the NRC on or before t* tat date.
As you can see, prior to that date DOE must affirm to NRC that "is .nd DOE are engaged in good faith negotiations for a contract under tb section of the Waste Act.
We believe that the preliminary comments submitted on the DOE proposal con-stitute such good-faith negotiations on the part of Duke, and we would re-quest that, at the earliest possible date, DOE affirm, in writing, that Duke and. DOE are actively involved in such good-faith negotiations. However, if further input is required from Duke Power Company in order that the Department be able to render the aforementioned affirmation to the Commission, please advise us immediately. We look forward to completion of negotiations with the Department, and hereby state our intention, upon completion of such negotiations, to execute the requisite agreement for disposal services on or before the date specified by the Act.
If there are questions regarding this submittal, please contact Mr. R. Greg Snipes Nuclear Production Department, Duke Power Company, P. O. Box 33189, Charlotte, North Carolina 28242 (Phone 704-373-8704). Thank you for your consideration.
Very truly yours, L ,
" /- $ (
H. B. Tucker Vice President Nuclear Production Department HBT/two l
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Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste (48 F. R. 5458; Friday, February 4, 1983; 10 CFR 961)
Duke Power Company 1 4
Preliminary Comments February 8,1983 1
General Comments First, it is extremely important that the contract be fully reflective of the intent of the Nuclear Waste Policy Act (P.L.97-425), hereafter referred j to as "the Act." This necessitates that the contract provide that DOE accept for transportation and disposal all spent fuel and/or high level waste pro-duced by the facilities covered by the contract. The responsibilities of the Purchaser should be simply to pay the prescribed fees and deliver, f.o.b.
carrier at the Purchaser's designated site, spent nuclear fuel (SNF) or high-level water (HLW) in such configuration as can be handled and transported in accordance with all regulatory requirements.
Further, the fees to be established should be in keeping with the concept j of full cost recovery. More specifically, payments to be made into the Waste Fund should be used only to defray those costs defined in Section 302 (d) of the Act. Use of this fund for purposes other than disposal-related activities is explicitly contrary to the Act.
Second, given the magnitude of the Civilian Radioactive Waste Management Program and the Waste Fund supporting it, we believe it is appropriate that the Purchaser be granted audit rights regarding DOE r.xpenditures from the fund and access to decision-making information. The precise ' role of the Purchaser in this area needs to be well thought out and precisely defined. We would reserve further comment on this point until a later date, except to remark that the alternative program management study man-dated by Section 303 of the Act might be the place to better define this role.
Third, inasmuch as there will be a much greater inventory of SNF and/or HLW existent at the time of commencement of operation of the first repository than can be received on a short time schedule, an equitable ranking of priority from Purchaser to Purchaser must be established. The contract as drafted provides priority on the basis of age, i.e. , time from discharge i
from che reactor to delivery to DOE, with a special priority given to fuel which needs to be removed from the plant site such that decommissioning
( activities can begin. On first thought, we believe this is a logical ap-l proach. However, we would specifically request the opportunity, should we l so desire, to propose during the comment period alternative ranking schemes which would ensure that each Purchaser be allotted some space at the reposi-tory during each year of repository operation.
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2 Further to this point, we believe it particularly desirable that the con-tract provide the opportunity,for Purchasers to swap allotments between and among themselves,'up to the point of setting the final delivery schedule, and subject to DOE approval as to the feasibility of shipping arrangements.
In our view this would take considerable pressure off of DOE itself in responding to requests for emergency deliveries.
. Fourth, it is important from the standpoint of spent fuel storage planning that uncertainty be reduced as to the possibility of storage requirements peaking after 1998. This would be the case if the initial repository receipt I rate were less than the rate of spent fuel generation as of 1998. Therefore, we believe DOE should design the first repository and the associated front-end facilities in such a way that initial receipt rates are at least equal to the rate of spent fuel generation. This intent should be embodied in con-tract language.
Fifth, we endorse the concept of a simple, industry average dollars per kilogram charge on prior spent fuel. The simplicity of this approach makes it highly desirable in terms of dealing with public utility commissions, in keeping with the rationale of the ongoing mil per kilowatt hour charge. While we understand DOE is to provide additional information regarding the working
- of Article VIII.A.2 of the draft contract, our initial reaction is that a i different dollar per kilogram charge for fuel in different burnup ranges is overly burdensome and not in keeping with the simple intent of the Act.
As a possible compromise, we believe the following procedure might merit con-sideration: Inasmuch as the ongoing mil per kilowatt hour charge will, as we understand it, provide adequate' funding for the waste program over the next several years, without resort to borrowing, the Purchaser could be offered two options regarding the determination of the one-time fee for prior fuel. The first option could be the 1 mil per kilowatt hour charge applied to the in-dustry average burnup value, and spread over all kilograms of spent fuel dis-charged from civilian reactors as of 4/7/83. The second option could be a mil per kilowatt hour charge applied on a fuel assembly by fuel assembly basis. The Purchaser would be allowed to choose the lower value.
i While admitted not contemplated by the Act, this procedure could assuage the I feelings of any Purchaser that he was being adversely treated by the applica-tion of a single fee calculation method. Further, any monetary shortfall resulting from the application of such options would be compensated for by future adjustments of the mil per kilowatt hour ongoing charge. We may wish to comment further on this point at a later date.
i Sixth, we note that DOE contemplates future adjustment, not only of the on-going mil per kilowatt hour charge, but also of the dollar per kilogram fee
- for prior spent fuel. Although Section 302 (a) (4) of the Act is somewhat ambiguous on this point, we believe it was the intent of Congress that all adjustments apply to the ongoing charge, not to the one-time fee. We do believe, however, that under our interpretation of the intent of the Act, '
finance charges to time of payment would be appropriate.
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- : 3 Failing this interpretation of adjustability of the fee for prior fuel, at the very least we expect that some payment option be provided which fixes, once and for all, the fee for prior fuel as of the time the Purchaser com-mences payment of this fee to DOE. This we believe has been incorporated into Article VIII B.2.(a) of the proposed contact.
Finally, although it is not clear from the language of the proposed contract, we believe that we should enter into but one agreement for disposal of SNF and/or HLW for all reactors which we own or operate. We do not currently have reason to suspect that DOE thinks otherwise.
Section-by-Section Comments Article I- Definitions Definition 1 - Assigned Three-Month Period. In line 1, change "the period" to "each period" and "each Purchaser" to "the Purchaser."
Definition 12 - Full Cost Recovery. In lines 7 and 8, delete "and all other uses specified in the Act, such as, but not limited to," and insert the word
" including."
Definition 17 - Shipping Lot. In line 2, insert the word "beginning" after the word " DOE."
Definition 18 - Spent Nuclear Fuel. In line 2, insert after the word "irradia-tion" the phrase, "without intent to reinsert." The major concern here is that if, for instance, a reactor has'to offload a full core to correct an operational problem, that fuel should not be considered SNF for the purposes of this agree-ment.
Article III - Term Modify this article as follows. In line 1, insert the phrase "and shall continue" after the word " execution." In line 2, delete the phrase " DOE has accepted" and insert the word "all." Add at the end of the existing article the phrase "has been disposed of as provided for in this contract."
Article IV - Delivery of SNF and/or HLW Paragraph B 1st Sentence. A mechanism needs to be established which triggers the first submittal of Appendix B. Once triggered, submittals would be made annually thereafter. Assuming the first year DOE will accept fuel for dis-posal is FY1998, the first submittal of Appendix B information should be made on or before July 1, 1992 (63 months prior to the beginning of FY1998).
Paragraph B Last Sentence 1st Paragraph. Since Appendix B does not specify month of delivery, we assume the intent is to allow delay of some reasonable portion of a year's delivery commitment into the first 2 months of the sub-sequent fiscal year.
Addition at the end of Paragraph B. DOE should allow exchange of allotments among utilities up until time of finallization of the delivery schedule, sub-ject to DOE's transportation constraints. See our general comments. The sug-gested language is:
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" Purchasers may exchange delivery commitments with other owners and generators of SNF and/or HLW of domestic origin from civilian nuclear power reactors prior to submittal of the final delivery schedule by Purchaser subject' to the approval of DOE, which approval shall not be unreasonably withheld."
Paragraph C. We interpret the language to mean:
(1) A separate Appendix C must be submitted for each shipping lot, or cam-paign, for each site.
(2) The required date for submittal of each Appendix C is determined by backing cff 12 months from the beginning of the shipment window for each lot - not from the beginning of the delivery commitment fiscal year.
Please confirm this understanding.
Article V - Responsibilities of the Parties Paragraph A.1.(a). It seems somewhat unreasonable to require Appendix D -
type information as early as October 1, 1983, We would suggest such sub-mittals begin October 1,1987 (essentially 10 years before repository opera-tion).
We would assume that after the first submittal of Appendix D, which would bring DOE up to date on historic discharges, subsequent October 1 submittals need cover only the prior year's actual discharges, as well as a new 10 year proj ection. Please confirm.
Paragraph A.2.(a). Fourth line'. Need the notification contain anything other than the commencement date for the preparatory activities?
Paragraph B. DOE's primary responsibility, is the obligation to accept for transportation and disposal all SNF and/or HLW generated by the facilities ,
covered under the agreement and properly described and prepared for shipment as specified in Article VI. This does not appear in the list of DOE respon-sibilities.
Paragraph B.I. 90 day approval of final delivery schedule is inconsistent with Article IV.C which states 45 days.
Paragraph B.2. Delete period at end of paragraph and insert "and shall be in compliance with the requirements of all regulatory authorities having jurisdiction. DOE shall be responsible for all normal maintenance and repair of such casks."
Paragraph B.3. Add "f.o.b. carrier" at the end of the first sentence.
Paragraph B.6. See general comments. Although this seems one fair way to allocate respository space, we may wish to. propose another during the comment period.
Article VI - Criteria for Disposal Paragraph A.1 Second Line. Delete the words "only such" and insert the word "all."
- 5 Paragraph A.2. When is Appendix F information due?
Paragraph B.1 First Sentence. We would suggest in DOE's own interest that it not commit to being present for all cask loadings. It would be more ap-propriate for DOE to have the right to have a representative present.
Paragraph B.1 Second Sentence. Delete the balance of the paragraph after the word " accept" and insert "for transportation and disposal all SNF and/or HLW properly identified, packaged and labeled pursuant to all applicable regula-tions." This contract should not attempt to rephrase existing regulation, i.e.,
specific DOE requirements should only be delineated here if not covered by regulation. See 49CFR172.204 and .200.
Paragraph B.3.(a) First Line. Delete "(2)" and insert "(b)." Also, same general comment as Article V.B.6 above.
Article VII - Title Second Line. Delete " Article VI" and insert " Article V."
In addition, at the end of this acticle should be added this sentence.
"Should DOE elect to reprocess SNF provided by Purchaser pursuant to this contract, a credit to the Waste Fund shall be made in an amount equal to the value of the recovered products."
Article VIII - Fee and Terms of Payment Paragraph A.1. Insert after the word " mil" the term "($0.001)."
Paragraph A.2. See general comment. We understand the burnup ranges are yet to be defined. Also, when a " dollar per kilogram" charge is referred to, it must be defined as to whether this is kilograms uranium initially loaded (and even if that is actual or nominal design value), or kilograms of discharged heavy metal (uranium plus plutonium). We realize that it is .
really only important that DOE's basis for calculation of the charge and our application of the charge to actual spent fuel is consistent, but it must be defined. We would suggest initial, nominal design values of uranium loading.
This would be much simpler to administer.
Paragraph A.3. Section 302(a)(4) of the Act states that the Secretary is to
" annually review the amount of the fees. 's te r in that same paragraph the Act states the Secretary "shall propo*t to ijustment to the fee" in light of his review. We suggest that the i rset < Congress was to review the total costs of the program as against all <avc~.. thence the word " fees"), but that,
, in light of the review of total exps,ditures versus total revenues, only the mil per kilowatt hour fee was to be adjusted on a prospective basis.
As a further comment on this section, it is difficult for a utility to respond to changes in the mil per kilowatt hour charge, in terms of collections from its ratepayers, in less than a year. We recognize the.90 day effectiveness period is consistent with the requirements of the Act; neverths'.ess, it may be desirable to address this subject in later technical amendments to the Act.
6 Paragraph A.4. We do not fully understand this paragraph. We believe this language calls for 1 mil per kilowatt hour to be paid for prior generation of all fuel which is in-reactor as of April 7,1983; if this is the case, it is not clear this was the intent of Section 302(a)(3) of the Act.
Should not the word " unburned" in line 6 read " burned?"
Paragraph B.1. Four assigned three month periods should be specified. Also, what time periods of generation are the one-time adjustment period and the July 7, 1983 payment intended to cover?
Paragraph B.2.(a). It would appear that interest for 10 years at the ten year Treasury note rate ow' uld be applied to the total fee for prior fuel.
This appears inequitable; rather, the financing arrangement should provide that interest be applied on the unpaid balance only. Further, the Purchaser should be allowed at any time to pay the entire unpaid balance or any portion thereof at no penalty. Also, we are unaware as to where the ten year Treasury note rate is published (see also reference in Appendix G).
Paragraph B.3.(a) First Line. Delete the word "by" and insert "either by check or." Insert after the word " transfer," the phrase "provided payment is received by the due date,."
Paragraph B.3. (b) Third Line. Insert after the word " advice" the phrase "together with check, provided check is used as the method of payment,".
Paragraph C.I. We are not aware of a publication wherein we may find the Quarterly Treasury Rate. We would suggest this paragraph reference the 26 Week Treasury Bill Rate (as reported in the Wall Street Journal on the due date specified in Article VIII B.I.).
Paragraph E. It would be helpful to separate the type of records related to administration of this agreement. One category is records relating to iden-tification and physical characteristics of SNF and HLW delivered to DOE under the contract. It is reasonable to retain such records related to given waste shipments for a period of three years after the shipment in question. The other type of record relates to the fee payments; i.e., energy generation and financial information. These records should be retained for a period of three years after the payment period in question.
Article IX - Delays Paragraph A - General Comment. The language proposed by DOE seems appropriate as applied to day-to-day operational problems. For instance, a crane compo-nent fails at a DOE facility, and, because of the unavailability of a spare part a shipment must be postponed for a month. However, we would distinguish this from a case where DOE fails to meet the repository operation schedule mandated by the Act. We desire to reserve additional comment on this point during the comment period.
Paragraph A Line 3. Insert the word " reasonable" before the word " control."
Paragraph A Line 7 and 8. Insert the word "promptly" before the word " notify."
and delete the phrase "as soon as possible."
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- 7 Paragraph B Line 5. Delete " estimated" and insert " reasonably" after the word
" Costs."
Article X - Suspension Paragraph 1 Line 6. Insert the word " reasonable" before the word " control."
Article XIV - Representation Concerning Nuclear Hazards Indermnity Line 9. The term " contract location" needs to be defined.
Article XV - Assignment Delete the phrase "a party to this contract" and insert the phrase "the Purchaser."
Eign,alure Page In phrase beginning " WITNESSES," delete the word " CONTRACTOR" and insert the word " PURCHASER."
Appendix A Capacity should be specified by megawatt thermal and/or megawatt electrical net.
"Date of Commencement of Operation" should be changed to read "Date of Com-merica1 Operation."
AEpendix B Line 7. Delete the words "and approved" and insert the words "for approval."
Shipping Lot No. - We assume DOE would establish a convention of some type for designation of lot numbers such that there is some consistency (and absence of duplication) amon,1 Purchasers.
Page 2. What would DOE consider " suitable proof of ownership of the SNF and/
or HLW7" Page 2. Signature Section. The phrase " Approval for DOE" should read
" Approved by DOE."
Appendix C For ease of administration, we would suggest that the required " Metric Tons Uranium" be specified as the initial, unirradiated nominal mass.
Signature Section. The phrase " Approved for DOE" should read " Approved by DOE."
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. *; 8 Appendix D Why are shipping lot numbers and commitment year for delivery required pursuant to Appendix D? This information should be applicable to Appendix B.
Suggest the term " Metric Tons Uranium" be specified as initial, unirradiated nominal values.
Appendix E Paragraph B.2.(b). and following Note. Does this mean if fuel has nonfuel component is it NS-2? Or if it requires special handling it is NS-27 Paragraph B.3. The phrase "these specifications" should read "this specifica-tion."
Parat.aph B.S.a. Third Line. The word " classing" should read " cladding.'
Paragraph B.S.b. The economic and operational impact of leak testing as re-quired by this paragraph will be quite serious, will undoubtedly impede the progress of spent fuel shipping, and, most importantly, be of little or no practical value. Using current state of the art, fuel sipping after five years of decay time gives virtually meaningless results.
In the case of fuel which has been sipped or otherwise tested soon after discharge from the reactor for operational reasons, and found to be leaking, we would of course be willing to make that information known to DOE.
The reference to percentages of regulatory limits regarding coolant activities must be omitted or clarified. The regulatory limit specified in 10CFR71.35(a)4 is overridden by some cask certificates of compliance. It would be more reason-able to require that only for fuel sipped and found leaking as Failed Fuel -
Class F2, DOE has the right to require Purchaser to sample cask gas or water.
These samples would have to meet the requirements of 10CFR71.35(a)(4) or 71.36 (a)(2).
Paragraph B General Comment. It would probably be appropriate to establish a fuel classification for consolidated fuel, with its own unique set of al-lowable physical dimensions and handling characteristics.
Appendix F Paragraph A.1. Omit 1.2 through 1.5 if possible. These drawings are difficult to obtain.
Paragraph A.2. Add subsection (d) for nonfuel components. Designate fuel assembly in which inserted, weight, length, cladding materials and absorber material.
Paragraph A.3. Reference to " Delivery Commitment." This should read " Shipping Lot."
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- . '; 9 Paragraph D. Omit all information except items 5 and 6. No information should be required on a cycle of cycle basis. If there is good reason for DOE to re-quire such detailed information, we would be pleased to discuss; otherwise, the requirements are overly burdensome.
! Appendix H - General Terms and Conditions Limited rights Legend - paragraph (a). Insert the word "be" before the word
" retained."
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