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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20033E2851990-03-0101 March 1990
[Table view]Responds to Generic Ltr 90-01 Re Request for Voluntary Participation in NRC Regulatory Impact Survey.Completed Questionnaire Includes Info on NRC Insps,Required QA Audits, Nelia & Maelu Insps,State of Mi Insps & FEMA Insps B13454, Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Approx Two NRC Team Insps Conducted at Facilities Each Yr.Two SSFIs Conducted in 19881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Approx Two NRC Team Insps Conducted at Facilities Each Yr.Two SSFIs Conducted in 1988 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 ML20012A0231990-02-27027 February 1990 Informs of Organizational Changes within Div of Reactor Projects,Project Directorate III/2.Change Reassigned Project Managers to Listed Facilities ML20033E2941990-02-26026 February 1990 Informs of Address Change for Correspondence Control Desk to Reflect Move of Nuclear Group to Chesterbrook 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) 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 ML18094B3111990-02-23023 February 1990 Forwards Safety Insp Repts 50-272/90-04,50-311/90-04 & 50-354/90-01 on 900101-0212.No Violations Noted 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) 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 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 ML20033E4551990-02-15015 February 1990 Amends 881128 Application for Amends to Licenses NPF-9 & NPF-17,clarifying Tech Spec 6.2.3 Re Safety Review Group,Per 900212 Discussions W/Nrc.Listed Criteria Replace That of Previous Submittal ML20006E6251990-02-15015 February 1990 Requests Determination That 10CFR26 App a Section 2.7(0)(3)(ii) Does Not Require That Alcohol Breath Analysis Equipment Conform to Both Natl Safety Highway Traffic Safety Admin Stds & State Statutes or Exemptions to 10CFR26 A08496, Ack Receipt of Listed Invoices for Costs Incurred During Routine Reviews of Plant1990-02-15015 February 1990 Ack Receipt of Listed Invoices for Costs Incurred During Routine Reviews of Plant 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) ML20006E1511990-02-12012 February 1990 Advises That 891201 Rev 57 to QA Topical Rept CE-1-A Consistent W/Provisions of 10CFR50.App B & Acceptable ML20006F1301990-02-12012 February 1990 Lists Suggested Topics for Licensee Info Conference,Per 900117 Request ML20006D6751990-02-0909 February 1990 Partial Response to FOIA Request for Documents.App Q Documents Encl.App Q & Documents Available in Pdr.App R Documents Totally Withheld (Ref FOIA Exemption 5) ML20006D7831990-02-0808 February 1990 Advises That Board Concluded That Holding Prehearing Telcon Re Scheduling Considered Premature Due to Lack of Record,Per .Request for Future Scheduling Suggested to Be Submitted.W/Certificate of Svc.Served on 900209 B13447, Advises of Changes to Util Distribution Lists for Correspondence from NRC Due to Organizational Title Changes. Revs to Distribution List Encl1990-02-0808 February 1990 Advises of Changes to Util Distribution Lists for Correspondence from NRC Due to Organizational Title Changes. Revs to Distribution List Encl 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 ML18094B2991990-02-0707 February 1990 Advises That 891227 Request to Apply ASME Section XI Code Case N-460 Has Been Reviewed & Approved for Application to Plants 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 ML20006C4491990-02-0101 February 1990 Requests Telephone Conference Be Set Up at Board Convenience Due to Author Not Being Able to Reach Licensee Counsel ML20006C5661990-01-31031 January 1990 Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants 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 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 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 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) ML20006C0431990-01-29029 January 1990 Forwards Response to NRC Bulletin 89-003.Util Nuclear Fuels Dept Designs or Reviews & Approves Each Core Reload for Plants & Refueling Operations Recently Reviewed to Ensure Appropriate Procedural Controls in Place B13244, Informs of Plans to Resolve Problems Experienced During Last Two Summers W/High Svc Water Temps Slightly Above 90 F. Proposed License Amend Requests Will Be Submitted Limiting UHS Temps for Haddam Neck & Millstone Unit 21990-01-29029 January 1990 Informs of Plans to Resolve Problems Experienced During Last Two Summers W/High Svc Water Temps Slightly Above 90 F. Proposed License Amend Requests Will Be Submitted Limiting UHS Temps for Haddam Neck & Millstone Unit 2 ML20006C4621990-01-26026 January 1990 Responds to 900117 Joint Request on How NRC & Applicant Counsel Expect to Move Proceeding on Hearing Calendar in New Yr.Applicant Has Expressed Desire to Have Proceeding Held in Abeyance Indefinitely Although NRC Does Not Agree 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 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 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 A08383, Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Personnel Trained in Overall Control Procedure for Fuel Movement1990-01-25025 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Personnel Trained in Overall Control Procedure for Fuel Movement A08201, Forwards Response to Recommended Actions in Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Recommended Hardware Mods to Be Included as Isap 1.1201990-01-25025 January 1990 Forwards Response to Recommended Actions in Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Recommended Hardware Mods to Be Included as Isap 1.120 ML18094B2631990-01-25025 January 1990 Advises That Fee Not Required Re 891227 Application for Approval of Use of ASME Section XI Code Case N-460.Fee Will Be Retained by NRC & Credited When Invoice Issued for Review ML20006B2011990-01-24024 January 1990 Advises That 891027 Response to Generic Ltr 88-20 Re Individual Plant Exam Approach,Methodology & Schedule Acceptable ML20033E6931990-01-24024 January 1990 Requests NRC Consideration of Encl Constituent,Jm Mchugh to a Damato Forwarding St Lawrence Environ Mgt Council .Nrc 820212 Press Release Citing Operators at Eight Plants for Emergency Planning Violations Also Encl 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 1990-03-01 Category:INCOMING CORRESPONDENCE MONTHYEARB13454, Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Approx Two NRC Team Insps Conducted at Facilities Each Yr.Two SSFIs Conducted in 19881990-03-0101 March 1990
[Table view]Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Approx Two NRC Team Insps Conducted at Facilities Each Yr.Two SSFIs Conducted in 1988 ML20033E2851990-03-0101 March 1990 Responds to Generic Ltr 90-01 Re Request for Voluntary Participation in NRC Regulatory Impact Survey.Completed Questionnaire Includes Info on NRC Insps,Required QA Audits, Nelia & Maelu Insps,State of Mi Insps & FEMA Insps 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 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 ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 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 ML20033E2941990-02-26026 February 1990 Informs of Address Change for Correspondence Control Desk to Reflect Move of Nuclear Group to Chesterbrook 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) 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 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 A08496, Ack Receipt of Listed Invoices for Costs Incurred During Routine Reviews of Plant1990-02-15015 February 1990 Ack Receipt of Listed Invoices for Costs Incurred During Routine Reviews of Plant ML20006E6251990-02-15015 February 1990 Requests Determination That 10CFR26 App a Section 2.7(0)(3)(ii) Does Not Require That Alcohol Breath Analysis Equipment Conform to Both Natl Safety Highway Traffic Safety Admin Stds & State Statutes or Exemptions to 10CFR26 ML20033E4551990-02-15015 February 1990 Amends 881128 Application for Amends to Licenses NPF-9 & NPF-17,clarifying Tech Spec 6.2.3 Re Safety Review Group,Per 900212 Discussions W/Nrc.Listed Criteria Replace That of Previous Submittal 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) ML20006F1301990-02-12012 February 1990 Lists Suggested Topics for Licensee Info Conference,Per 900117 Request B13447, Advises of Changes to Util Distribution Lists for Correspondence from NRC Due to Organizational Title Changes. Revs to Distribution List Encl1990-02-0808 February 1990 Advises of Changes to Util Distribution Lists for Correspondence from NRC Due to Organizational Title Changes. Revs to Distribution List Encl 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 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) 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 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 B13244, Informs of Plans to Resolve Problems Experienced During Last Two Summers W/High Svc Water Temps Slightly Above 90 F. Proposed License Amend Requests Will Be Submitted Limiting UHS Temps for Haddam Neck & Millstone Unit 21990-01-29029 January 1990 Informs of Plans to Resolve Problems Experienced During Last Two Summers W/High Svc Water Temps Slightly Above 90 F. Proposed License Amend Requests Will Be Submitted Limiting UHS Temps for Haddam Neck & Millstone Unit 2 ML20006C0431990-01-29029 January 1990 Forwards Response to NRC Bulletin 89-003.Util Nuclear Fuels Dept Designs or Reviews & Approves Each Core Reload for Plants & Refueling Operations Recently Reviewed to Ensure Appropriate Procedural Controls in Place 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 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 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 A08383, Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Personnel Trained in Overall Control Procedure for Fuel Movement1990-01-25025 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Personnel Trained in Overall Control Procedure for Fuel Movement A08201, Forwards Response to Recommended Actions in Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Recommended Hardware Mods to Be Included as Isap 1.1201990-01-25025 January 1990 Forwards Response to Recommended Actions in Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Recommended Hardware Mods to Be Included as Isap 1.120 ML20033E6931990-01-24024 January 1990 Requests NRC Consideration of Encl Constituent,Jm Mchugh to a Damato Forwarding St Lawrence Environ Mgt Council .Nrc 820212 Press Release Citing Operators at Eight Plants for Emergency Planning Violations Also Encl 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 B13419, Submits Revised Schedule to Resolve USI A-46 Re Generic Implementation Procedures Developed by Seismic Qualification Util Group.If Final NRC SER Issued During First Quarter 1990 Walkdowns Could Be Done During Second Refueling Outage1990-01-22022 January 1990 Submits Revised Schedule to Resolve USI A-46 Re Generic Implementation Procedures Developed by Seismic Qualification Util Group.If Final NRC SER Issued During First Quarter 1990 Walkdowns Could Be Done During Second Refueling Outage 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 A08416, Advises That Fee for Second Quarterly Installment of 1990 Annual Fee Will Be wire-transferred on 9001311990-01-11011 January 1990 Advises That Fee for Second Quarterly Installment of 1990 Annual Fee Will Be wire-transferred on 900131 1990-03-01 Category:UTILITY TO NRC MONTHYEARB13454, Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Approx Two NRC Team Insps Conducted at Facilities Each Yr.Two SSFIs Conducted in 19881990-03-0101 March 1990
[Table view]Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Approx Two NRC Team Insps Conducted at Facilities Each Yr.Two SSFIs Conducted in 1988 ML20033E2851990-03-0101 March 1990 Responds to Generic Ltr 90-01 Re Request for Voluntary Participation in NRC Regulatory Impact Survey.Completed Questionnaire Includes Info on NRC Insps,Required QA Audits, Nelia & Maelu Insps,State of Mi Insps & FEMA Insps 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 ML20033E2941990-02-26026 February 1990 Informs of Address Change for Correspondence Control Desk to Reflect Move of Nuclear Group to Chesterbrook 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 ML20033E4551990-02-15015 February 1990 Amends 881128 Application for Amends to Licenses NPF-9 & NPF-17,clarifying Tech Spec 6.2.3 Re Safety Review Group,Per 900212 Discussions W/Nrc.Listed Criteria Replace That of Previous Submittal ML20006E6251990-02-15015 February 1990 Requests Determination That 10CFR26 App a Section 2.7(0)(3)(ii) Does Not Require That Alcohol Breath Analysis Equipment Conform to Both Natl Safety Highway Traffic Safety Admin Stds & State Statutes or Exemptions to 10CFR26 A08496, Ack Receipt of Listed Invoices for Costs Incurred During Routine Reviews of Plant1990-02-15015 February 1990 Ack Receipt of Listed Invoices for Costs Incurred During Routine Reviews of Plant 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) ML20006F1301990-02-12012 February 1990 Lists Suggested Topics for Licensee Info Conference,Per 900117 Request B13447, Advises of Changes to Util Distribution Lists for Correspondence from NRC Due to Organizational Title Changes. Revs to Distribution List Encl1990-02-0808 February 1990 Advises of Changes to Util Distribution Lists for Correspondence from NRC Due to Organizational Title Changes. Revs to Distribution List Encl 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 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 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 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) B13244, Informs of Plans to Resolve Problems Experienced During Last Two Summers W/High Svc Water Temps Slightly Above 90 F. Proposed License Amend Requests Will Be Submitted Limiting UHS Temps for Haddam Neck & Millstone Unit 21990-01-29029 January 1990 Informs of Plans to Resolve Problems Experienced During Last Two Summers W/High Svc Water Temps Slightly Above 90 F. Proposed License Amend Requests Will Be Submitted Limiting UHS Temps for Haddam Neck & Millstone Unit 2 ML20006C0431990-01-29029 January 1990 Forwards Response to NRC Bulletin 89-003.Util Nuclear Fuels Dept Designs or Reviews & Approves Each Core Reload for Plants & Refueling Operations Recently Reviewed to Ensure Appropriate Procedural Controls in Place 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 A08383, Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Personnel Trained in Overall Control Procedure for Fuel Movement1990-01-25025 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Personnel Trained in Overall Control Procedure for Fuel Movement A08201, Forwards Response to Recommended Actions in Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Recommended Hardware Mods to Be Included as Isap 1.1201990-01-25025 January 1990 Forwards Response to Recommended Actions in Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Recommended Hardware Mods to Be Included as Isap 1.120 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 B13419, Submits Revised Schedule to Resolve USI A-46 Re Generic Implementation Procedures Developed by Seismic Qualification Util Group.If Final NRC SER Issued During First Quarter 1990 Walkdowns Could Be Done During Second Refueling Outage1990-01-22022 January 1990 Submits Revised Schedule to Resolve USI A-46 Re Generic Implementation Procedures Developed by Seismic Qualification Util Group.If Final NRC SER Issued During First Quarter 1990 Walkdowns Could Be Done During Second Refueling Outage 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 A08416, Advises That Fee for Second Quarterly Installment of 1990 Annual Fee Will Be wire-transferred on 9001311990-01-11011 January 1990 Advises That Fee for Second Quarterly Installment of 1990 Annual Fee Will Be wire-transferred on 900131 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 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 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 A08184, Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking in Anchor Darling Model S350W Swing Check Valves & Similar Valves.Haddam Neck & Millstone Unit 1 Have No Valves Subj to Bulletin.Valves in Other Units Will Be Inspected1990-01-0505 January 1990 Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking in Anchor Darling Model S350W Swing Check Valves & Similar Valves.Haddam Neck & Millstone Unit 1 Have No Valves Subj to Bulletin.Valves in Other Units Will Be Inspected ML20005F4981990-01-0404 January 1990 Advises of Change of Address for Correspondence to Util 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 1990-03-01 |
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TENNESSEE VAL. LEY AUTHORIT1 i
CH ATTANCiOG A. TENNESSEE 374ot
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76 391 June 11, 1976 30,gfs kC/fg h
tdf497, e Dinctor of Nuclear Reactor Regulatica hang
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Attention: Mr. Roger S. Boyd 8
Division of Project Management g
U.S. Nuclear Re6ulatory Comission p
l Washington, DC 20555
Dear Mr. Boyd:
In the Matter of the Application of )
Docket Nos. S N 50-5 m Tennessee Valley Authority
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STN 50-554 Enclosed are bl copies of revision 1 to the Phipps Bend Nuclear Plant Units 1 and 2 Environmental Report which consists of a revised chapter 1.
This revision primarily reflects changes in the scheduled commercial operating dates and also updates the projected loads with our most recent load forecast, Sectica 1.1.1, " Load Characteristics," discusses the new load forecast which, in addition to TVA's basic forecasting methods, is based on new methods--particularly econometric nodels by additional staff expertise and additional information from surveys and publications. Also, this section has been erpanded l
to give more detail on forecasting methodology.
J As a result of our latest assessment, the long-term Browth out-look for the econog in the 1980's is now estimated to be somewhat lower than the outlook one year ago. Consequently, 1
the commercial and industrial loads were lowered, which results in a decrease in forecast of winter peaks in the mid-1980's.
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An Equal Opportunity Employer 8709250199 B70922 I
^ a Director of Nuclear Reactor Regulation June 11, 1976 Section 1.3 has been modified to reflect the effect of the consequences of delay with revised unit schedules.
Very truly yours,
/
L H
. E. Gilleland Assistant Manager of Pc,ver Sworn to and subscribed before me this // day of h ed -1975 L
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[I My cosmission expires /8-3-Ib l
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CC: Mr. kegis Boyle (Enclosure)
Environmental Projects Branch 3 Division of Site Safety and Environmental Analysis U.S. Nuclear Regulatory Cosmaission Washington, DC 20555
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l TENNESSEE VALLEY AUTHORITY PHIPPS BEND NUCLEAR PLANT UNITS 1 AND '2 DocxeT Nos, STN 50-553,50-55l1 ENVIRONMENTAL REPORT EVISION 1 i
C REVISION 1 TO THE PHIPPS BEND NUCLEAR PLANT ~
UNITS 1 AND 2 ENVIRONMENTAL REPORT Revision 1 to the Phipps Bend Nuclear Plant Units 1 and 2 Environmental Report consists of a revised chapter 1.
Remove the old chspter 1 and insert the ene2.osed new chapter 1 in its entirety.
This sheet should be fileil in front of Volume' 1 as a record of the changed chapter.
l 1
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