|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20149G1941993-09-13013 September 1993 Partial Response to FOIA Request for Listed OI Repts.Record Listed in App D Being Withheld from Public Disclosure Because It Consists of Records Compiled for Law Enforcement Purposes.Nrc Continuing to Review Records Re FOIA Request IA-93-355, Partial Response to FOIA Request for Listed OI Repts.Record Listed in App D Being Withheld from Public Disclosure Because It Consists of Records Compiled for Law Enforcement Purposes.Nrc Continuing to Review Records Re FOIA Request1993-09-13013 September 1993 Partial Response to FOIA Request for Listed OI Repts.Record Listed in App D Being Withheld from Public Disclosure Because It Consists of Records Compiled for Law Enforcement Purposes.Nrc Continuing to Review Records Re FOIA Request ML20072C9611993-06-18018 June 1993 FOIA Request for Listed OI Repts ML20079D3191991-06-10010 June 1991 Forwards B Tatalovich Correspondence Re Plant ML17347B5881990-03-0101 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 1993-09-13
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20072C9611993-06-18018 June 1993 FOIA Request for Listed OI Repts ML20079D3191991-06-10010 June 1991 Forwards B Tatalovich Correspondence Re Plant ML17347B5881990-03-0101 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 1993-06-18
[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
. _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
,A } $ $ / ' N ' '
,g g ,,_. . -
Tile CINCINNATl (,AS E: *t i l .. 4 El.ECTRIC COMPANY EU . ._ _ .-d_. ** > .
D,'_ - '
cer u. .. s. w i. c s c m <
" '!8$E."O.'.7" April 19, 1972 United States Atomic Energy Commission Washington, D. C. 20545 Attention:
Mr. Roger S. Boyd, Asst. Director for Boiling Water Reactors Division of Reactor Licensing RE: WM. H.
ZIEER NUCLEAR POWER ST17_' ION -
UNIT #1 - 10CFR50 CHANGES PILATED TO SITE OF CONST?.UCTION, PREPARATIONS AND CO:01ENCEMENT W.O. 57300-956, JOB E-5590, DOCKET FO. 50-358 Gentlemen:
in ansucr to your letter of MarchReference 23, 1972, is made to our letter of March 31, 1972 pertaining
,Pover Station. to the construction of the hTa. H. Docket No. 50-358 Zimmer Nuclear
" Activities of Site Preparation" at the Zimmer siteWe . These hereby ap g activitics were temporarily suspended in September in order !
to fully ascertain the aspects of the Calvert Cliffs decision .
In accordance with 10CFR50.10 (d) , we request permission to resume the follouing site preparation activities that arc in progress with the parcont completion listed below:
- a. Grading of the power plant site
- 70%
- b. Construction and permanent roads a- - 50%
y@ c. Site drainage - - - - - - -
o -
- 90%
@ d. Source of potable water system - - 500 5<O e. L a..,o . a r y 'c; o w e i co? ^ -- - -
50%
PSn O. f. Fencing - - - - - - - - -
cez - -
E00 gg g.
Const.ruction parking . lot -
1 i
- - 900
)9$h20@ l 6.I- - - - _ _ - _ - _ - . -
To:
U.S. Atomic Energy Cor. mission
- f April 19, 1972 Me: Wm. II .
{ =
Unit #1 Zimmer Nuclear l'o. er Station -
.10CFR50 Changes Related to Page #2 i
i Site Preparations and Commencement of Construction, W.O. 57300-956, t
t Job E-5590, Docket No. 50-358
-~
1
? -
.{ h.
?_ Soil borings
[
90%
v i. Deep well pumps -
- - 50%
h j.
i Excavation and recompaction in
! the circulating water piping,
- i. reactor, and turbine generator L
areas - - - - - -
- - 60%
k.
,1 Excavation of borrow pit -
5%
} 1.
- i Outside laydown storage area - - 75%
!E- m.
!I
' River terminals and related i facilities - -
- 10 %
f n.
.i Temporary construction buildings and related facilities -----30%
?
- - to the following factors with respect to 50.10 (2) :
gd)We requ
[ .
1.
The continuation of' the site preparation E
activities will not adversely affect the environment.
e The principal environmental impact of construction has already occurred i
!4' and continuation of the site activities that we request would not give rise to additional significant adverse impact on the environment.
- g. ,
. All site activities requested to be continued lS will have some minical effect on the environ-ment.
(; in nature; as grading and drainage areThis minimal i..
1 completed to final elevations, seeding and
+' planting vill enhance, rather that decrade 4: the environment.
i' 2 j; Redress of any adverse environmental impact
- 3) ;
resulting from recurption of site activities can easily be achieved since the site has g already been cleared and the requested activi-ties grade
_ite would levels.
be prir.arily restricted to below 4
Ledress of any adversc
4 f
t 4"
To: U.S.
. Atomic Energy Ccrnission Re: hb . H. April 19. 1972 Unit Zim:ner ! uclear Powar Station -
f.1 - 10Crr.50 Chtnges telated to Page li 3 Site Preparaticrs and Commencement of Cons 9 uction, F.O. 57300-956, Job :-5590, Domt '1c. 5 0--3 5 8 environmental impact from such limited any structures to the extent necessary toconstr restore and the site by grading andtolandscaping.
its natural condition 3.
The construction authorized would not activities that would preclude adoption of be Additional costs would not be incurred duealte .
to design alternatives af ter preliminary" Site Pr this letter have been accomplished.
delayed,If the "In-Service Date" of this unit is a serious shortage of system
, Alternate methods of procuring power arecapacity .
detailed in the it'. H.
Report Supplenent 2 Section 9.0Zimmer Environinental It is obvious fron a cost and reliability standpoint whenthat n Zimmer Nuclesr Pouer Station Unit 1 compared to the .
4.
Columbus and Dayttn CompanicsThe anticipated : , ponr r that the Em. H. (CCD) indicates be placed in service by early 1977 in order toZirner Kucl meet the 1977 summr peak loads.
meet this In order to preparations he completed during the 1972 schedule, it i construction season.
Grading and corpacted backfill work in the So uth-between Ohio western arca De cci:r anf. pnerally
- 'ay. Ifcc: .ot be conductc:
permission is no:.
granted to cc .;inut pacte] b a c % fi _1, dring the this ucrh, including ccm-sencon, the G. _;.y 1972 construction n to weather conditions mc; x
\
add Imre than six t:nths to the overall schedub .
i
To: U.S. Atomic Energy Commicsion April 19,1972 Re: Em. H. 7immer Nuclear Powcr Station - Paga #4 Unit fl - 10C1'r:50 Changes 7.clated to Site Preparations and Coconcement of Construction, W.O. 57300-956, Job E-5590, Docket No. 50-358 l
k The one year delay, primarily caused by the
((
g Calvert Cliffs decisica and AEC regulatory process, .in plant conpletion has already j increased the total capital investment of ,
the unit by approxinetely $14 million. This
{
j capital cost increase vill result in addi-tional revenue requirements to cover fixed l l
charges during the lifetime of the unit, l l
}'
I The additional cost of generatica incurred by the CCD companics. as a direct result of
! delaying the in-service date of the Zimmer Unit from 1975 to 1976 is estimated to be 3
$16.9 million, measured at 1976 cost levels. t
{
This makes the cost to the CCD companies, as )
a result of delays to date, a total of $30.9 million, $14 million of which is additional i
costs to the Zimmer Project and $16.9 million l of which is added operating and other construc-tion costs made necessary by tha delay.
l.
If site activities roguested arc not completed o
during the construction season cf 1972, the in-i service date will be delayed beyond the first quarter of 1977 and the additional costs g resulting from delays vill amount to in excess i
of $2 million a month.
"y Any delay of the in-service date will result in Clermont County, Uashington Township, and the New Richmond Schecl Distric: losing a
& substantial amount of property tax revenues.
I Presently the unemployment late in Clermont County is 14.5 0. The construction schedule indicates that over 1200 craft cnployees will be required during the peak of ccnctructirn.
Man;. of the craf t empicyees will be from .o Clermont County area.
\
6 '
\
S'o: U.
A -
S.1:tomic rnergy Corission -
April'19, 1972 Rc:
Wm. 11 . ?,iinnor "uclear Pc.tcr Station -
Unit f:1 - 10cm50 Chanc,u Related to - Page il5 Site Preparations and Ce.:mnca ant
' of Construction, W.O. 57200-956, Job E 5590,_ l'oc!:e t No . I.'-358 Continuation 'of the activitics requested such as b:ckfilling, construction of an adequate road system, drcinaqo ditches 7:id river terminals would permit finish grading, prepar drainage, auf landscaping to procaed at an erosion and silting during construction. earlier date minimizing In summary, that permission be granted to continu? based on the above factors, we requ already started for the follc ing rencons:the site preparation 1.
Ma::imum the change environment of the site1f'innact rom itsassociated foruer with undeveloped state _lready has occurred.
2.
Redress of the site environment will be possible due to the limited scope of the requested activity continuation.
3.
1 Continuation will not further degrade the environitent ; in fcet, the environment will 1
be enhanced.
4.
The effects of delay from not continuing site activitics would net be in the public interest.
Increased be incurredconstruction and pasrad on andtointerest costs would the consumer. ,
t 5.
Unicss grcding is permitted to continue, will be difficult to control .:: oil erosion,it i i
6.
Continuation of sito work will aid in alleviating unempicyr.ent in Clerr.ont County.
P2rsuant toIf lthe activities Z:'n50. l(' (d) , are permitted to be continued ti :j shall be conducted in such {
a tr.nner as will rainimire er reduce their environmental
.U . ;> h L . j
)
\
'Jery truly fours, l
l I
C;; ah U. H. Dichh:ncr l
- - _ _ _