|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML17347B5881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 ML15217A1031990-02-28028 February 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) ML20006G0621990-02-22022 February 1990 Forwards Revised Proprietary Pages to DPC-NE-2004, Core Thermal Hydraulic Methodology Using VIPRE-01, Reflecting Minor Methodology Changes Made During Review & Approval Process.Pages Withheld ML20006E5881990-02-20020 February 1990 Forwards Proprietary Response to NRC 890725 Questions Re Vipre Core Thermal Hydraulic Section of Topical Rept DPC-NE-3000 & Rev 2 to Pages 3-69,3-70,3-78 & 3-79 of Rept. Encls Withheld (Ref 10CFR2.790) ML20006E1441990-02-16016 February 1990 Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals ML20006E9071990-02-16016 February 1990 Discusses Plants Design Control Program.Util Adopted Concept of Design Change Implementation Package (Dcip).Dcip Will Contain or Ref Design Change Notice Prepared Per Approved Procedures ML20006E4201990-02-14014 February 1990 Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 ML18094B3291990-02-14014 February 1990 Forwards Printouts Containing RW-859 Nuclear Fuel Data for Period Ending 891231 & Diskettes ML20011E6151990-02-12012 February 1990 Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21) ML20011E5571990-02-0808 February 1990 Forwards Us Bankruptcy Court for Eastern District of Tennessee Orders & Memorandum on Debtors Motion to Alter or Amend Order & Opinion Re Status of Sales Agreement Between DOE & Alchemie.Doe Believes Agreement Expired on 890821 ML20011E4991990-02-0606 February 1990 Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested ML20011E5981990-02-0505 February 1990 Requests That Listed Individuals Be Deleted from Svc List for Facilities.Documents Already Sent to Dept of Environ Protection of State of Nj ML20006D6911990-02-0202 February 1990 Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle ML20006C5661990-01-31031 January 1990 Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants ML20006D6611990-01-29029 January 1990 Advises That 900117 License Amend Request to Remove Certain cycle-specific Parameter Limits from Tech Specs Inadvertently Utilized Outdated Tech Specs Pages.Requests That Tech Specs Changes Made Via Amends 101/83 Be Deleted ML20011E2521990-01-29029 January 1990 Forwards Proprietary Safety Analysis Physics Parameters & Multidimensional Reactor Transients Methodology. Three Repts Describing EPRI Computer Code Also Encl.Proprietary Rept Withheld (Ref 10CFR2.790) ML20006C6711990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Plants Have Established Preventive Maint Program for Intake Structure & Routine Treatment of Svc Water Sys W/Biocide to Control Biofouling ML20006B7961990-01-29029 January 1990 Forwards Summaries of Latest ECCS Evaluation Model Changes ML18153C0951990-01-29029 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Belief in Appropriateness to Address Generic Ltr 89-13 Concerns within Context of Established Programmatic Improvements Noted ML20006D2431990-01-26026 January 1990 Provides Info Re Emergency Response Organization Exercises for Plants.Exercises & Callouts Would Necessitate Activation of Combined Emergency Operations Facility Approx Eight Times Per Yr,W/Some Being Performed off-hours & Unannounced ML18153C0871990-01-26026 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures to Be Revised & Familiarization Sessions Will Be Conducted Prior to Each Refueling Outage ML18094B2861990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Aggressive Program of Monitoring,Insp & Matl Replacement Initiated in Advance of Generic Ltr 89-13 Issuance ML19354E4191990-01-25025 January 1990 Comments Re Issuance of OL Amends & Proposed NSHC Determination Re Transfer of Operational Mgt Control of Plants & Views on anti-trust Issues Re Application for Amend for Plants ML19354E6711990-01-24024 January 1990 Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226 ML17347B5451990-01-24024 January 1990 Informs of Plans to Apply ASME Code Case N-356 at Plants to Allow Certification Period to Be Extended to 5 Yrs.Rev to Inservice Insp Programs Will Include Use of Code Case ML19354E4461990-01-22022 January 1990 Forwards Proprietary Rev 1 to DPC-NE-2001, Fuel Mechanical Reload Analysis Methodology for MARK-BW Fuel, Adding Section Re ECCS Analysis Interface Criteria & Making Associated Administrative Changes.Rev Withheld ML19354E4451990-01-22022 January 1990 Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters ML20005G7161990-01-20020 January 1990 Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl ML20006A8001990-01-19019 January 1990 Forwards Response to NRC 891220 Ltr Re Violations Noted in Plant Insps.Response Withheld (Ref 10CFR73.21) ML16152A9091990-01-18018 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. W/900131 Release Memo ML18153C0771990-01-17017 January 1990 Forwards North Anna Power Station Emergency Plan Table 5.1, 'Min Staffing Requirements for Emergencies' & Surry... Table 5.1, 'Min Staffing Requirements...', for Approval,Per 10CFR50.54(q),NUREG-0654 & NUREG-0737,Suppl 1 ML20006A6241990-01-16016 January 1990 Forwards Draft Qualified Master Trust Agreement for Decommissioning of Nuclear Plants,For Review.Licensee Will Make Contributions to Qualified & Nonqualified Trust as Appropriate ML20006A2011990-01-16016 January 1990 Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel in Anchor Darling Swing Check Valves.Eight Subj Valves Identified in Peach Bottom Units 1 & 2 & Will Be Returned to Mfg ML18153C0731990-01-15015 January 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or or Valves.... Util Replaced Studs in twenty-five Valves ML20006A8201990-01-10010 January 1990 Forwards Errata to Rev 3 to BAW-1543,Tables 3-20 & E-1 of Master Integrated Reactor Vessel Surveillance Program Reflecting Changes in Insertion Schedule for A5 Capsule for Davis-Besse & Crystal River ML20006B8821990-01-10010 January 1990 Reissued Ltr Correcting Date of Util Ltr to NRC Which Forwarded Updated FSAR for Byron/Braidwood Plants from 881214 to 891214.W/o Updated FSARs ML20005G6431990-01-10010 January 1990 Responds to Generic Ltr 89-21 Re Implementation of USI Requirements,Consisting of Revised Page to 891128 Response, Moving SER Ref from USI A-10 to A-12 for Braidwood ML20005G7601990-01-0404 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Plan. Privacy Info Should Be Deleted Prior to Placement in Pdr.W/ D Grimsley 900118 Release Memo ML18153C0491990-01-0303 January 1990 Advises of Implementation of fitness-for-duty Program Which Complies w/10CFR26.Util Support Objective of Providing Assurances That Nuclear Power Plant Personnel Will Perform Tasks in Reliable & Trustworthy Manner ML20005F4641990-01-0303 January 1990 Advises That Licensee Implemented 10CFR26 Rule Re fitness-for-duty Program W/One Exception.Util Has Not Completed Background Check for Some of Program Administrators.Checks Expected to Be Completed by 900105 ML18094B2331990-01-0303 January 1990 Certifies Util Implementation of fitness-for-duty Program, Per 10CFR26.Training Element Required by Rule Completed on 891215.Chemical Testing for Required Substances Performed at Min Prescribed cut-off Levels,Except for Marijuana ML17347B5051990-01-0202 January 1990 Certifies That Util Has fitness-for-duty Program Which Meets Requirements of 10CFR26.Util Adopted cut-off Levels Indicated in Encl ML20042D3731990-01-0202 January 1990 Forwards Revised Crisis Mgt Implementing Procedures, Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9, Rev 1 to CMIP-14 & Rev 30 to CMIP-21 ML17347B4961989-12-28028 December 1989 Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Considering Expansion of Plants to Include Addl safety-related & Position Changeable Valves W/ Emphasis on Maint & Testing ML20042D3381989-12-28028 December 1989 Forwards Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. Util Will Comply W/Ltr Recommendations W/Noted Exceptions.Response to Be Completed When Ltr Uncertainties Cleared ML18094B2201989-12-27027 December 1989 Advises of Intent to Provide follow-up Response to Generic Ltr 89-10 by 900831 to Describe Status of Program, Recommendation Exceptions & Any Schedule Adjustments ML18094B2291989-12-27027 December 1989 Requests to Apply ASME Section XI Code Case N-460 to Facilities Re Reduction in Exam Coverage on Class 1 & 2 Welds.Fee Paid 1990-03-01
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17347B5881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 ML15217A1031990-02-28028 February 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML20006G0621990-02-22022 February 1990 Forwards Revised Proprietary Pages to DPC-NE-2004, Core Thermal Hydraulic Methodology Using VIPRE-01, Reflecting Minor Methodology Changes Made During Review & Approval Process.Pages Withheld ML20006E5881990-02-20020 February 1990 Forwards Proprietary Response to NRC 890725 Questions Re Vipre Core Thermal Hydraulic Section of Topical Rept DPC-NE-3000 & Rev 2 to Pages 3-69,3-70,3-78 & 3-79 of Rept. Encls Withheld (Ref 10CFR2.790) ML20006E1441990-02-16016 February 1990 Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals ML20006E9071990-02-16016 February 1990 Discusses Plants Design Control Program.Util Adopted Concept of Design Change Implementation Package (Dcip).Dcip Will Contain or Ref Design Change Notice Prepared Per Approved Procedures ML20006E4201990-02-14014 February 1990 Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 ML20011E6151990-02-12012 February 1990 Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21) ML20011E5571990-02-0808 February 1990 Forwards Us Bankruptcy Court for Eastern District of Tennessee Orders & Memorandum on Debtors Motion to Alter or Amend Order & Opinion Re Status of Sales Agreement Between DOE & Alchemie.Doe Believes Agreement Expired on 890821 ML20011E4991990-02-0606 February 1990 Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested ML20011E5981990-02-0505 February 1990 Requests That Listed Individuals Be Deleted from Svc List for Facilities.Documents Already Sent to Dept of Environ Protection of State of Nj ML20006D6911990-02-0202 February 1990 Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle ML20006C5661990-01-31031 January 1990 Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants ML20006B7961990-01-29029 January 1990 Forwards Summaries of Latest ECCS Evaluation Model Changes ML20006C6711990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Plants Have Established Preventive Maint Program for Intake Structure & Routine Treatment of Svc Water Sys W/Biocide to Control Biofouling ML20006D6611990-01-29029 January 1990 Advises That 900117 License Amend Request to Remove Certain cycle-specific Parameter Limits from Tech Specs Inadvertently Utilized Outdated Tech Specs Pages.Requests That Tech Specs Changes Made Via Amends 101/83 Be Deleted ML20011E2521990-01-29029 January 1990 Forwards Proprietary Safety Analysis Physics Parameters & Multidimensional Reactor Transients Methodology. Three Repts Describing EPRI Computer Code Also Encl.Proprietary Rept Withheld (Ref 10CFR2.790) ML18153C0951990-01-29029 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Belief in Appropriateness to Address Generic Ltr 89-13 Concerns within Context of Established Programmatic Improvements Noted ML18094B2861990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Aggressive Program of Monitoring,Insp & Matl Replacement Initiated in Advance of Generic Ltr 89-13 Issuance ML18153C0871990-01-26026 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures to Be Revised & Familiarization Sessions Will Be Conducted Prior to Each Refueling Outage ML20006D2431990-01-26026 January 1990 Provides Info Re Emergency Response Organization Exercises for Plants.Exercises & Callouts Would Necessitate Activation of Combined Emergency Operations Facility Approx Eight Times Per Yr,W/Some Being Performed off-hours & Unannounced ML19354E4191990-01-25025 January 1990 Comments Re Issuance of OL Amends & Proposed NSHC Determination Re Transfer of Operational Mgt Control of Plants & Views on anti-trust Issues Re Application for Amend for Plants ML19354E6711990-01-24024 January 1990 Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226 ML17347B5451990-01-24024 January 1990 Informs of Plans to Apply ASME Code Case N-356 at Plants to Allow Certification Period to Be Extended to 5 Yrs.Rev to Inservice Insp Programs Will Include Use of Code Case ML19354E4451990-01-22022 January 1990 Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters ML19354E4461990-01-22022 January 1990 Forwards Proprietary Rev 1 to DPC-NE-2001, Fuel Mechanical Reload Analysis Methodology for MARK-BW Fuel, Adding Section Re ECCS Analysis Interface Criteria & Making Associated Administrative Changes.Rev Withheld ML20005G7161990-01-20020 January 1990 Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl ML20006A8001990-01-19019 January 1990 Forwards Response to NRC 891220 Ltr Re Violations Noted in Plant Insps.Response Withheld (Ref 10CFR73.21) ML16152A9091990-01-18018 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. W/900131 Release Memo ML18153C0771990-01-17017 January 1990 Forwards North Anna Power Station Emergency Plan Table 5.1, 'Min Staffing Requirements for Emergencies' & Surry... Table 5.1, 'Min Staffing Requirements...', for Approval,Per 10CFR50.54(q),NUREG-0654 & NUREG-0737,Suppl 1 ML20006A2011990-01-16016 January 1990 Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel in Anchor Darling Swing Check Valves.Eight Subj Valves Identified in Peach Bottom Units 1 & 2 & Will Be Returned to Mfg ML20006A6241990-01-16016 January 1990 Forwards Draft Qualified Master Trust Agreement for Decommissioning of Nuclear Plants,For Review.Licensee Will Make Contributions to Qualified & Nonqualified Trust as Appropriate ML18153C0731990-01-15015 January 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or or Valves.... Util Replaced Studs in twenty-five Valves ML20005G6431990-01-10010 January 1990 Responds to Generic Ltr 89-21 Re Implementation of USI Requirements,Consisting of Revised Page to 891128 Response, Moving SER Ref from USI A-10 to A-12 for Braidwood ML20006A8201990-01-10010 January 1990 Forwards Errata to Rev 3 to BAW-1543,Tables 3-20 & E-1 of Master Integrated Reactor Vessel Surveillance Program Reflecting Changes in Insertion Schedule for A5 Capsule for Davis-Besse & Crystal River ML20006B8821990-01-10010 January 1990 Reissued Ltr Correcting Date of Util Ltr to NRC Which Forwarded Updated FSAR for Byron/Braidwood Plants from 881214 to 891214.W/o Updated FSARs ML20005G7601990-01-0404 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Plan. Privacy Info Should Be Deleted Prior to Placement in Pdr.W/ D Grimsley 900118 Release Memo ML18094B2331990-01-0303 January 1990 Certifies Util Implementation of fitness-for-duty Program, Per 10CFR26.Training Element Required by Rule Completed on 891215.Chemical Testing for Required Substances Performed at Min Prescribed cut-off Levels,Except for Marijuana ML18153C0491990-01-0303 January 1990 Advises of Implementation of fitness-for-duty Program Which Complies w/10CFR26.Util Support Objective of Providing Assurances That Nuclear Power Plant Personnel Will Perform Tasks in Reliable & Trustworthy Manner ML20005F4641990-01-0303 January 1990 Advises That Licensee Implemented 10CFR26 Rule Re fitness-for-duty Program W/One Exception.Util Has Not Completed Background Check for Some of Program Administrators.Checks Expected to Be Completed by 900105 ML20042D3731990-01-0202 January 1990 Forwards Revised Crisis Mgt Implementing Procedures, Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9, Rev 1 to CMIP-14 & Rev 30 to CMIP-21 ML17347B5051990-01-0202 January 1990 Certifies That Util Has fitness-for-duty Program Which Meets Requirements of 10CFR26.Util Adopted cut-off Levels Indicated in Encl ML17347B4961989-12-28028 December 1989 Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Considering Expansion of Plants to Include Addl safety-related & Position Changeable Valves W/ Emphasis on Maint & Testing ML20042D3381989-12-28028 December 1989 Forwards Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. Util Will Comply W/Ltr Recommendations W/Noted Exceptions.Response to Be Completed When Ltr Uncertainties Cleared ML18094B2201989-12-27027 December 1989 Advises of Intent to Provide follow-up Response to Generic Ltr 89-10 by 900831 to Describe Status of Program, Recommendation Exceptions & Any Schedule Adjustments ML18094B2291989-12-27027 December 1989 Requests to Apply ASME Section XI Code Case N-460 to Facilities Re Reduction in Exam Coverage on Class 1 & 2 Welds.Fee Paid ML20005E1911989-12-26026 December 1989 Forwards Revised Page 2 Correcting Plant Implementation Date for USI A-24 Requirements in Response to Generic Ltr 89-21 ML18153C0261989-12-26026 December 1989 Responds to Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & surveillance.Motor-operated Valve Program Structured to Allow Similar Approach to motor-operated Dampers.Results Will Be Submitted in 30 Days 1990-03-01
[Table view] Category:UTILITY TO NRC
MONTHYEARML17347B5881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 ML15217A1031990-02-28028 February 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML20006G0621990-02-22022 February 1990 Forwards Revised Proprietary Pages to DPC-NE-2004, Core Thermal Hydraulic Methodology Using VIPRE-01, Reflecting Minor Methodology Changes Made During Review & Approval Process.Pages Withheld ML20006E1441990-02-16016 February 1990 Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals ML20006E9071990-02-16016 February 1990 Discusses Plants Design Control Program.Util Adopted Concept of Design Change Implementation Package (Dcip).Dcip Will Contain or Ref Design Change Notice Prepared Per Approved Procedures ML20006E4201990-02-14014 February 1990 Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 ML20011E6151990-02-12012 February 1990 Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21) ML20011E4991990-02-0606 February 1990 Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested ML20006D6911990-02-0202 February 1990 Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle ML20006C5661990-01-31031 January 1990 Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants ML20006B7961990-01-29029 January 1990 Forwards Summaries of Latest ECCS Evaluation Model Changes ML18153C0951990-01-29029 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Belief in Appropriateness to Address Generic Ltr 89-13 Concerns within Context of Established Programmatic Improvements Noted ML20006C6711990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Plants Have Established Preventive Maint Program for Intake Structure & Routine Treatment of Svc Water Sys W/Biocide to Control Biofouling ML20006D6611990-01-29029 January 1990 Advises That 900117 License Amend Request to Remove Certain cycle-specific Parameter Limits from Tech Specs Inadvertently Utilized Outdated Tech Specs Pages.Requests That Tech Specs Changes Made Via Amends 101/83 Be Deleted ML20011E2521990-01-29029 January 1990 Forwards Proprietary Safety Analysis Physics Parameters & Multidimensional Reactor Transients Methodology. Three Repts Describing EPRI Computer Code Also Encl.Proprietary Rept Withheld (Ref 10CFR2.790) ML18094B2861990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Aggressive Program of Monitoring,Insp & Matl Replacement Initiated in Advance of Generic Ltr 89-13 Issuance ML18153C0871990-01-26026 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures to Be Revised & Familiarization Sessions Will Be Conducted Prior to Each Refueling Outage ML20006D2431990-01-26026 January 1990 Provides Info Re Emergency Response Organization Exercises for Plants.Exercises & Callouts Would Necessitate Activation of Combined Emergency Operations Facility Approx Eight Times Per Yr,W/Some Being Performed off-hours & Unannounced ML19354E6711990-01-24024 January 1990 Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226 ML17347B5451990-01-24024 January 1990 Informs of Plans to Apply ASME Code Case N-356 at Plants to Allow Certification Period to Be Extended to 5 Yrs.Rev to Inservice Insp Programs Will Include Use of Code Case ML19354E4451990-01-22022 January 1990 Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters ML19354E4461990-01-22022 January 1990 Forwards Proprietary Rev 1 to DPC-NE-2001, Fuel Mechanical Reload Analysis Methodology for MARK-BW Fuel, Adding Section Re ECCS Analysis Interface Criteria & Making Associated Administrative Changes.Rev Withheld ML20005G7161990-01-20020 January 1990 Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl ML20006A8001990-01-19019 January 1990 Forwards Response to NRC 891220 Ltr Re Violations Noted in Plant Insps.Response Withheld (Ref 10CFR73.21) ML16152A9091990-01-18018 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. W/900131 Release Memo ML18153C0771990-01-17017 January 1990 Forwards North Anna Power Station Emergency Plan Table 5.1, 'Min Staffing Requirements for Emergencies' & Surry... Table 5.1, 'Min Staffing Requirements...', for Approval,Per 10CFR50.54(q),NUREG-0654 & NUREG-0737,Suppl 1 ML20006A2011990-01-16016 January 1990 Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel in Anchor Darling Swing Check Valves.Eight Subj Valves Identified in Peach Bottom Units 1 & 2 & Will Be Returned to Mfg ML18153C0731990-01-15015 January 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or or Valves.... Util Replaced Studs in twenty-five Valves ML20006A8201990-01-10010 January 1990 Forwards Errata to Rev 3 to BAW-1543,Tables 3-20 & E-1 of Master Integrated Reactor Vessel Surveillance Program Reflecting Changes in Insertion Schedule for A5 Capsule for Davis-Besse & Crystal River ML20006B8821990-01-10010 January 1990 Reissued Ltr Correcting Date of Util Ltr to NRC Which Forwarded Updated FSAR for Byron/Braidwood Plants from 881214 to 891214.W/o Updated FSARs ML20005G6431990-01-10010 January 1990 Responds to Generic Ltr 89-21 Re Implementation of USI Requirements,Consisting of Revised Page to 891128 Response, Moving SER Ref from USI A-10 to A-12 for Braidwood ML20005G7601990-01-0404 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Plan. Privacy Info Should Be Deleted Prior to Placement in Pdr.W/ D Grimsley 900118 Release Memo ML20005F4641990-01-0303 January 1990 Advises That Licensee Implemented 10CFR26 Rule Re fitness-for-duty Program W/One Exception.Util Has Not Completed Background Check for Some of Program Administrators.Checks Expected to Be Completed by 900105 ML18094B2331990-01-0303 January 1990 Certifies Util Implementation of fitness-for-duty Program, Per 10CFR26.Training Element Required by Rule Completed on 891215.Chemical Testing for Required Substances Performed at Min Prescribed cut-off Levels,Except for Marijuana ML18153C0491990-01-0303 January 1990 Advises of Implementation of fitness-for-duty Program Which Complies w/10CFR26.Util Support Objective of Providing Assurances That Nuclear Power Plant Personnel Will Perform Tasks in Reliable & Trustworthy Manner ML17347B5051990-01-0202 January 1990 Certifies That Util Has fitness-for-duty Program Which Meets Requirements of 10CFR26.Util Adopted cut-off Levels Indicated in Encl ML20042D3731990-01-0202 January 1990 Forwards Revised Crisis Mgt Implementing Procedures, Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9, Rev 1 to CMIP-14 & Rev 30 to CMIP-21 ML17347B4961989-12-28028 December 1989 Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Considering Expansion of Plants to Include Addl safety-related & Position Changeable Valves W/ Emphasis on Maint & Testing ML20042D3381989-12-28028 December 1989 Forwards Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. Util Will Comply W/Ltr Recommendations W/Noted Exceptions.Response to Be Completed When Ltr Uncertainties Cleared ML18094B2291989-12-27027 December 1989 Requests to Apply ASME Section XI Code Case N-460 to Facilities Re Reduction in Exam Coverage on Class 1 & 2 Welds.Fee Paid ML18094B2201989-12-27027 December 1989 Advises of Intent to Provide follow-up Response to Generic Ltr 89-10 by 900831 to Describe Status of Program, Recommendation Exceptions & Any Schedule Adjustments ML20005E1911989-12-26026 December 1989 Forwards Revised Page 2 Correcting Plant Implementation Date for USI A-24 Requirements in Response to Generic Ltr 89-21 ML18153C0261989-12-26026 December 1989 Responds to Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & surveillance.Motor-operated Valve Program Structured to Allow Similar Approach to motor-operated Dampers.Results Will Be Submitted in 30 Days ML17347B5041989-12-22022 December 1989 Forwards Annual Financial Info,Per 10CFR140.21 ML19354D6611989-12-20020 December 1989 Responds to Generic Ltr 89-15, Emergency Response Data Sys (Erds), Per 890821 Request.Informs That P Blackiston Will Be Licensee Contact to Participate in ERDS Program ML19332F6621989-12-14014 December 1989 Forwards Amend 12 to, Byron/Braidwood Stations Fire Protection Rept. Amend Reflects Changes to Facility & Procedures Effective 890630 ML17347B4601989-12-13013 December 1989 Forwards USI A-46 & Generic Ltr 87-02 & Proprietary Rev 1 to Plant-Specific Seismic Adequacy Implementation Procedure to Resolve USI A-46 & Generic Ltr 87-02. ML18153C0111989-12-0808 December 1989 Discusses Mod of Startup Physics Test Program Using Rod Swap Technique for Determination of Control Rod Worths.Mods Have No Significant Impact on Adequacy of Startup Physics Testing Program & Consistent W/Ansi/Ans - 19.6.1 -1985, Reload.... 1990-03-01
[Table view] |
Text
e SW '
1 2 Washingt:n Public Pcwcr Supply Systarn
] '* A JOINT OPERATING AGENCY j l 2 P. O. 844 988 3000 Gao. WaswsNoToM Way ReceLamo. WasMtMGTON 99352 PMons t SO9, 948 14 81
E.-
July 19,1976
.. s. ". . . . ...'.,g,. , . . - - - *
- g..- ,*' . J J .. 5 ..**t.. . . . .
e
- S-
- ul,y Director of Nuclear Reactor Regulation ~
h$
ATTN: Mr.-Olan D. Parr y a= '88% %
Light Water Reactor Project P Branch No. 3 4 '
U. S. Nuclear Regulatory Commission tu Washington, D. C. 20555
Subject:
WPPSS NUCLEAR PROJECT NO. 4 CONTRACTUAL AND FINANCIAL ARRANGEMENTS
References:
- 1) Letter, N. O. Strand, WPPSS, to A. Giambusso.
NRC, Contractual and Financial Arrangement for WPPSS Nuclear Project No. 4, dated October 22, 1975.
- 2) Letter, J. J. Stein, WPPSS, to A. Giambusso, NRC, Submittal of Financial Data, dated May 29, 1975.
Dear Mr. Parr:
In Reference 1 we requested that tion of the Supply System's finan,,the Staff temporarily dial qualifications defer considera-to construct WPPSS Nuclear Project No. 4 (WNP-4). The basis for this request was that execution of the Participants' Agreements for WNP-4 had been delayed pending completion of secondary environmental impact statements pursuant to the Washington State Environmental Policy Act.
This letter is to inform the NRC Regulatory Staff that particioants'_
~Aareements have been fully executed for 100% nf the outnut of WMP 4 and
.for the Supply System's share Olue) of the output of WPPSS Nuclear Pro-ject Na. 5 (WNP-5). As mentioned in Reference 2, WNP-4 and the Supply System's share of WNP-S will be financed as one system. The partici-pants in WNP-4 and WNP-5 are approximately 89 public and cooperative utilities (consisting of 21 municipalities, 24 public utility districts and 44 electric cooperatives) located principally in Washington, Oregon, Idaho, and Mnntana.
As you may be aware, by letter dated July 9. 1976, we requested that he l Atomic Safety and Licensing Board take steps to receive additional evidence from the Applicant and the Staff by the end of July,1976, with 8409270088 840824 PDR FOIA ry q r) aj COHENB4-603 PDR s u & s>
1
r
. Mr. Olan D. Parr Pag] 2 -
July 19, 1976 m -
s a view toward supplementing its Initial' Decision with appropriate
' findings relating to the Applicant's financial qualifications to con-struct WNP-4..s We are hopeful that a favorable su.pplemental Initial Decision will 'be issued promptly thereaf ter, leading to the issuance of -
a construction permit for WNP-4 in the first or second full week of September, 1976. , __ . , , , , _ . ,._.,, ,.,a;_ .
.g-. ....
The method of financing WNP-4 and the Supply System's share of WNP-5 was pre'sented to the Staff in Reference 2 in response to Staff Questions
.1.(a) and 1.(b). In addition, the Atomic Safety and Licensing Board .,
. explored this method of financing at some length at the radiolo 850-
,' 852).. health and safety hearings held in November,1
.~ An updated estimate of the total cost of WNP-4 (current as of May 31,
(a) Total nuclear production plant costs
$ 991,463,000 V
(b) Transmission and general plant costs 12,327,000 (c) Nuclear fuel inventory cost-2/ for first core 91,210,000 Total Estimated Cost $1,095,000,000 Siting, fuel cycle costs, payments to vendors and preliminary construc-tion expenditures through May 31, 1976, for WNP-4 and WNP-5 are $21,074-,000-and $7,896,000, respectively. Current estimates for WNP-4 and WNP-5 future expenditures (including fuel and owners' cost) are as follows:
WNP-4 'WNP-5 Year Expenditures Expenditures s '* %
Thru 1976 $ 72,997,000 $ 15,624,000 1977 108,358,000 100,442,000
- 1978 229,672,000 160,091,000 1979 326,031,000 271,351,000 ,
1980 198,567,000 293,651,000
- 1981 131,970,000 228,899,000 :
1982 27,405,000 164,426,000 '
1983 36,359,000 i 1984 157,000 i
1/ Including net interest during construction, owner's costs, and allowances for escalatica and contingencies.
y Nuclear fuel will be purchased rather than leased. ,
'l
.I
r- , , ,
Mr. Olan D. Parr .
Page 3 July 19. 1976 With the executiori of Participants' Agreements, financing of WNP-4 and Yi . WNP-5 will be continued by the issuance of approximately $2,718,000,000 of tax exempt revenue bonds in series from time to time during the phriod of construction. The Supply System plans to issue these bonds in the following approximate amounts and on the following schedules:
Date of Issue Amount ., ., .
1977 $300,000,000 1978 300,000,000 -
1979 450,000,000 1980 600,000,000' 1981 750,000,000 1982 318,000,000 Each series of bonds issued will be on a parity.with other bonds issued.
A scheduled summarizing financing activities through June 15, 1976, for all WPPSS construction projects is attached hereto.
Very truly yours,
/
D. L. RENBERGER !
Assistant Director Generation & Technology DLR:AGH:km .
. Attachments i "ap cc: JB Knotts - Conner & Knotts - w/att. -
HW Phillips - UE&C - w/att.
JR Schmieder - UE&C - w/att.
EG Ward - B&W - w/att. .
CR Bryant - BPA - w/att.
W Albert - NRC I&E - w/att. - - -
l l
]
..n.......... . . . . . . . .
CONSTRUCTION. PROJECTS FINANCING ACTIVITIES '
June 15, 1976
. . 1 PROCEEDS EFFECTIVE MATURITY PAR RECEIVED INT. RATE PROJECT TYPE RATING SALE DATE 77,000,000 $ 76,722,800 6.050 WNP1 Notes MIG-1;AA 5/22/74 12/15/1976 $
175,000,000 172,159,750 7.7269 W N P 1' Bonds Aaa';AAA 9/18/75 7/01/2017 " 6.83734 7/01/2017 180,000,000 179,715,934 WNP1 Bonds Aaa;AAA 2/04/76 ,
150,000,000 149,628,930 5.650 WHP2 Bonds A-1;Aa* '6/26/73 7/01/2012 79,864,055 7.2035 A-1;AA* '7/23/74 7/01/2012 80,000,000 WHP2 Bonds 125,000,000
.124,458,992 7.6667 WNP2 Bonds AA;AA-* 11/26/74 7/01/2012 6.7097 125,000,000 126,813,477_
WNP2 -
Bonds Aaa;AAA 3/06/75 7/01/2012 118,845,130 6.634 Aaa;AAA 6/03/,76 7/01/2012 120,000,000 WNP2 . Bonds . 9 150,000,000 147,876,742 7.867599 WNP3 Bonds Aaa;AAA 12/03/75 7/0'/2018 99,444,851 6.481385 Aaa;AAA 4/13/76 7/01/2018 100,000,000 W N.P 3 Bonds 6/01/1981 100,000,000 99,419,902 7.04099
' W N P 4/5' Bonds A-1;A 7/24/75 Total Outstanding $1,382j000,000
" NOTES RETIRED -
x 12/15/1975 2,500,000 ' 2,500,000 4:700 W N P 4/5 - Notes 3/20/74 15,056,867 8.007 MIG-1;A 8/01/74 6/15/1976 15,000,000 W N P 4/5 Notes ,
8/24/1973 1,500,000 1,492,879 2.925 WNP1 Notes 8/24/72 24,984,325 4.270 A-1;AA 2/15/73 12/15/1975 25,000,000 WNP1 Notes 15,000,000 s 14,775,100 3.550 WNP2
- Notes A-1;AA 7/01/71 7/01/1974 12/15/1974 40,000,000 40,000,401 3.500 WNP2 Notes ;A-1 12/15/72 12/17/1973 2,000,000 2,004,026 4.050 WNP3 Notes 5/15/73 29,004,640 4.368 MIG-1;AA 10/01/73 6/15/1976 29,000,000 WNP3 Notes
- *The first series of bonds for WNP-2 were upgraded to AAA ratings
- by both services subsequent to their issuance.
I .
i a n .
C..
n.
, . s a :
- I i
. y
. Docket No. _50-513 'WPPSS NUCLEAR PROJECT NO. 4
( - Contractual and Financial Arra.ngements s .
STATE OF WASHINGTON )
~ ~ ) ss
--. COUNTY OF BENTON- )
- - ~~'
-.e- .
R. E. SMITH, Being first duly sworn, deposes and says: That,he is the Manager, Operations Division, for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that he is authorized to submit the fore- I
. going on behalf of said applicant; that he has read the foregoing and 1 knows the contents thereof; and believes the same to be true to the best of his knowledge.
, i DATED /k , 1976
. / .
R. E. SMITH A $
On this day personally appeared before me R. E. SMITH to me known to be the individual who executed the foregoing instrument and acknowledged that he signed the same as his free act and deed for the uses and purposes therein, mentioned. ,
GIVEN under my hand and seal this /9&/.dayof kg, , 1976.
, Y '~
W4j 8 YYescio '
,l. . , , ' ' ?.'!
- i Notary Public in and for the State of
.: Washington
"",i-[! ,
Residing at M M s
.,..**, , b
\\ ', c t
J
Cr:nM 195 U.S. NUCLE AR REOULATERY C MMISSl!N DOCKET NUMIE R
- M . SO'b] S NRC DISTRIBUTION rO4\# ART 50 DOCKET MATERIAL Ts FROM: WPPSS
- oATE OF oOCUMENT MR O D PARR g ' ASH 74b% .
D L RENBERGER -
oATE RcCEivEo l 7-2/-76 !
h0TORl2ED PROP INPUT FORM NUMBER OF COPIES RECEIVED
% LETTER f MORIGIN AL UNC LASSiFIE D aCm .
/ S, s,.a ~
ossCRIPTION ENCLOSURE I IlfR REF THEIR 10-22-75 & 5-29-75 LTRS..... l FURNIEIIING INFO ON THE CON.TRACTUAL AND '
FINANCIAL ARRANGEMENTS....... .
s PLANT NAME! \A.) P f S'S %
. .1 i SAFETY FOR ACTION /INFORMATION ENVTRn #1 'lD -7 t* f/.S.
_ ASSIGNED AD: e .s n ' ASSIGNED ADr
>1 RANCH CHIEF: Vo) (RElik. BRANCH CMTEP*
l'ROJECT MANAGER: i s i PROJECT MANAGER! *-
ap'110. ASST. :
(/7) duSHSROCK LIC. ASST.!
-- --- - -- INTERNAL DISTRIBUTION L W' . REG FILE . SYSTEMS SAFETY T' PLANT RYSTFSM SITE SAFETV &
M NRC PDR_ _ HEINEMAN . ' Trnrnen ENVIRO ANALYSIS
_ W I&E (E) SCHROEDER BENAROYA DENTON & MUT T.FR
_. V OELD LAINAS GOSSICK & STAFF ENGINEERING IPPOLITO ENVIRO TECHr- "
_ MIPer .MACCARRY KIBKWOOD FRNRT CASE KNIGHT BALLARD
_ HANAUER SIIIWEIL OPERATING REACTORS SPANCLER
._. _ E6ELESS PAWLICKI STELLO -
,1 .- MYTE Tt'cM
_ _ _ PROJECT MANAGEMENT REACTOR SAFETY OPERATJNC TECH. CAMMTLL
.__., BOYD ROSS X EISENHU_T STEPP I
_ P. COLLINS NOVAK Y SHA0 HULMAN
- _ HOUSTON ROSZTOCZY Y BAER APSON CHECK Y BITTLER SITE ANALYSIS l ZTIELTZ \ V CRIMES VOLLF"'R i l[~ tit.LTEMES . AT & I BUNCll l
., R SKOVHOLT SALTZMAN Y .T. COLLINS l IlliTRE.C KRPCf'M EXTERNAL DISTRIBUTION CON TROL NUMBE R L LPDR: M D i kJA .. ... NAT LAB: HR00KilAJfELUMT LAB Y TIC: REC. VIE ULRIKSON(OltNL)
'.'.4JiSIc.
ASLB; LA PDR CONSULTANTS I
I Q3
,._ _A_CRS MeCYS _. NN ]