ML20049J878
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| ML20049J878 | |
| Person / Time | |
|---|---|
| Site: | Vallecitos Nuclear Center, 05000000, Vallecitos |
| Issue date: | 03/22/1982 |
| From: | Cunningham G GENERAL ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20049J879 | List: |
| References | |
| NUDOCS 8203290180 | |
| Download: ML20049J878 (1) | |
Category:CORRESPONDENCE-LETTERS
MONTHYEARIR 05000070/19993011999-07-0101 July 1999
[Table view]Forwards Insp Repts 50-070/99-301,50-073/99-201 & 50-183/99-201 on 990607-10.No Safety Concern or Noncompliance to NRC Requirements Was Identified ML20206P6541999-01-0707 January 1999 Forwards Insp Rept 50-070/98-01 on 981116-19.No Violations Noted.Major Activities Reviewed as Part of Insp Focused on Program to Maintain Safstor Condition of General Electric Test Reactor IR 05000070/19982011998-05-0404 May 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-070/98-201, 50-073/98-201 & 50-183/98-201.First Example of Violation 2 Has Been Withdrawn.Actions Examined During Future Insp ML20217B7081998-04-14014 April 1998 Submits Errata to Annual Rept 29 for ESADA - Vallecitos Experimental Superheat Reactor ML20217C1171998-03-18018 March 1998 Forwards Insp Repts 50-070/98-201,50-073/98-201 & 50-183/98-201 on 980209-13 & Notice of Violation ML20198K2711998-01-0909 January 1998 Forwards Insp Repts 50-018/97-01,50-070-97-01 & 50-183/97-01 on 971204.No Violations Noted.One Unresolved Item Identified & Discussed in Section 1.2 of Encl Rept ML20059E3841993-12-21021 December 1993 Accepts Cost Estimate Related to Licenses DPR-1,R-33,TR-1 & DPR-10,per Review of Documents Provided Via 931013,1202 & 17 Ltrs in Support of 930831 Request for Decrease in Chemical Bank Ltr of Credit Amend & Trust Agreement Amount ML20059E4141993-12-0202 December 1993 Explains 1993 Cost Estimate for Regulatory Assurance Reduction,W/Respect to GE Ltr of Credit IR 05000183/19930041993-11-24024 November 1993 Forwards Insp Rept 50-183/93-04 on 931101-05.No Violations Noted ML20059E4021993-10-13013 October 1993 Explains 1993 Cost Estimate for Regulatory Assurance Reduction,W/Respect to GE Ltr of Credit ML20127D7751992-09-0404 September 1992 Forwards USGS Study of Seismic Potential of Northern Calaveras Fault,For Actions Required to Ensure That Safety Analysis Remain Valid ML20059F6501990-08-27027 August 1990 Advises That 900820 Request for Petition for Reconsideration of Denial of Specific Exemption from Financial Assurance Instrument Requirements of 10CFR50 & 70 Under Review.Request for Temporary Extension of 900831 Filing Deadline Granted ML20033H0511990-04-0606 April 1990 Forwards Amend 5 to License DR-10 & Safety Evaluation.Amend Changes License Condition 3.E.2 to Delete Requirement That Annual Rept Be Submitted 60 Days After Each Annual Insp Completed 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 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 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 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 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 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 ML18094B3291990-02-14014 February 1990 Forwards Printouts Containing RW-859 Nuclear Fuel Data for Period Ending 891231 & Diskettes 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 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 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) 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 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 ML20011F5111990-02-0808 February 1990 Confirms Telecon Request Re 900223 Visit Re Decommissioning Funding Requirements & Estimated Decommissioning Cost Methodology 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 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 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 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 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 1999-07-01 Category:INCOMING CORRESPONDENCE MONTHYEARML20217B7081998-04-14014 April 1998
[Table view]Submits Errata to Annual Rept 29 for ESADA - Vallecitos Experimental Superheat Reactor ML20059E4141993-12-0202 December 1993 Explains 1993 Cost Estimate for Regulatory Assurance Reduction,W/Respect to GE Ltr of Credit ML20059E4021993-10-13013 October 1993 Explains 1993 Cost Estimate for Regulatory Assurance Reduction,W/Respect to GE Ltr of Credit 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 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 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 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) 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 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 ML20011F5111990-02-0808 February 1990 Confirms Telecon Request Re 900223 Visit Re Decommissioning Funding Requirements & Estimated Decommissioning Cost Methodology 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 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 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 ML20006B7961990-01-29029 January 1990 Forwards Summaries of Latest ECCS Evaluation Model Changes 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 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 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 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 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 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 1998-04-14 Category:VENDOR/MANUFACTURER TO NRC MONTHYEARML20011F5111990-02-0808 February 1990
[Table view]Confirms Telecon Request Re 900223 Visit Re Decommissioning Funding Requirements & Estimated Decommissioning Cost Methodology ML19325E9001989-10-19019 October 1989 Forwards Text of Info Communicated to All Util W/ Westinghouse NSSS Design on Pressurizer Safety Valve Set Pressure Deviation Info Request Response ML19327A8441989-10-11011 October 1989 Forwards Pleadings,Motions & Orders Filed in Alchemie Reorganization Action.Alchemie Currently Preparing Reorganization Plan Which Will Serve as Framework for Future Company Business Activities ML19327B2491989-10-0606 October 1989 Forwards Justification for Extension of Applicability of 890807 SER Re Acceptance of BAW-10175, Rod Exchange Methodology Topical Rept ML19327A8511989-10-0505 October 1989 Forwards Wh Arowood & Other Supplemental Info to Replace Info Previously Filed ML20247F4121989-08-31031 August 1989 Advises That Response to Order Modifying Licenses & Order to Show Cause Why Licenses Should Not Be Revoked Will Be Sent. Responses to NRC Three Basic Questions Re Status of Licensee Finances & Rationale for Having License Provided ML20246B1671989-08-0808 August 1989 Forwards Response to 890717 Request for Info Re Filings W/ Us Bankruptcy Court & Financial Capabilities.Ownership of Unclassified Equipment Remains Unchanged ML20247Q5521989-05-24024 May 1989 Notifies That J Smelser Contract Ended,Effective 890517. Mgt of Company by Listed Board of Director Members Will Continue Until New Chief Executive Officer Selected ML20247P8071989-04-0404 April 1989 Forwards Ltr in Which Concerns for Potential Significant Deficiency Under 10CFR21 Expressed ML20247G4991989-03-30030 March 1989 Forwards Proprietary BAW-10175P, Rod Exchange Methodology, Developed for Calculating Parameters While Performing Control Rod Measurements Using Rod Exchange Technique to Be Used at Plants.Rept Withheld (Ref 10CFR2.790) ML19324C3151989-02-20020 February 1989 Informs of Change in Vendor Plans for Inspecting Fuel Rods Containing Fuel Pellets Supplied by Ge.Ultrasonic Insp of Fuel Rods at Oconee 1 Found No Failed Rods in three-cycle, Discharged Fuel Assemblies ML20235M8971989-02-10010 February 1989 Requests Withholding of Proprietary WCAP 12125, Catawba Unit 1 Evaluation for Tube Vibration Induced Fatigue, Per 10CFR2.790 ML20206D6241988-11-11011 November 1988 Forwards Projected Decommission Costs of Centrifuge Machines to Be Transferred to New Facility at Oliver Spring,Tn. Licensee Will Be Able to Offset Total Decommissioning Costs by Setting Aside Annual Decommissioning Cost Plus Reserve ML20205Q6331988-11-0202 November 1988 Forwards Revised Proprietary Pages to BAW-10164P, RELAP5/Mod2-B&W,Advanced Computer Program for LWR LOCA & Non-LOCA Transient Analysis. Cso Film Boiling Correlation Replaced w/Condie-Bengston IV Correlation & Typos Corrected ML20205P9511988-11-0101 November 1988 Forwards Rev 6 to Security Plan for Alchemie Facility 1 - Cpdf,Oak Ridge,Tn & Rev 6 to Security Plan for Alchemie Facility 2 - Oliver Springs,Oliver Springs,Tn. Revs Withheld (Ref 10CFR2.790(d)) ML20195E4291988-10-31031 October 1988 Forwards Numbers 1-5 of Rev 5 to Alchemie Security Plans. Requests Replacement of Pages 23-25 & 35 & Encl Rev Page ML20205N3301988-10-27027 October 1988 Forwards Sketch of Feed Sys,Withdrawal Sys Refrigeration Cart & Typical Withdrawal,Large & Small,Pumping Stations ML20195B6091988-10-21021 October 1988 Forwards Summary of B&W Fuel Co Position Re Small Break LOCA Calculations Contained in Util FSARs for Upcoming Reload Cores Which Will Contain Fuel Mfg by B&W ML20195B7681988-09-26026 September 1988 Requests Withholding of Encl Proprietary Matl Entitled, Steam Generator Tube Rupture Analysis for Byron & Braidwood Plants, Per 10CFR2.790 ML20154K3841988-09-12012 September 1988 Forwards Enhanced Facts Re Adequacy of Funding for Decontamination & Decommissioning (D&D) of Facilities. Intends to Establish Funded Reserve for D&D at Completion of Sale of Unclassified Equipment Not Needed for Production ML20154Q5621988-09-0606 September 1988 Requests That Proprietary Addendum 2 to WCAP-10988, COBRA- Nc,Analysis for Main Steamline Break in Catawba Unit 1 Ice Condenser Containment (Response to NRC Questions) Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20154E6451988-08-31031 August 1988 Requests That 880722 & 0812 Ltrs Re Security Sys Components Be Withheld from Public Disclosure (Ref 10CFR2.790(d)) ML20207L7651988-08-30030 August 1988 Requests That Proprietary WCAP 11935, McGuire Unit 2 Evaluation for Tube Vibration Induced Fatigue, Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20151H9381988-07-25025 July 1988 Forwards Proprietary BAW-10168P, B&W LOCA Evaluation Model for Recirculating Steam Generator Plants ML20151M9211988-07-20020 July 1988 Responds to 880621 Request for Addl Info Re Enrichment of Naturally Occurring radioisotopes.Te-123 Will Be Enriching Approx 60 G to About 50% ML20151L3321988-07-20020 July 1988 Forwards DOE Ltr Indicating Acceptance of Classified Matter. Licensee Agrees to Remove Any Toxic or Hazardous Matl from Classified Equipment Prior to Transfer to DOE for Disposal ML20151G9761988-07-14014 July 1988 Forwards Rev 2 to Security Plan for Shipment of Classified Matter.Rev Withheld (Ref 10CFR2.790) ML20150F1561988-07-0808 July 1988 Advises of Changes to Alchemie Board of Directors,Per 880618 Annual Stockholders Meeting ML20155F4441988-05-0404 May 1988 Responds to NRC & Request at 880504 Meeting Describing GE Program to Reconfirm Design Adequacy of Associated Circuits in GE Bwrs.Upon Completion of Phases 1 & 2 of Evaluation of Bwrs,Ge Will Submit Summary by 881104 ML20151F7661988-03-29029 March 1988 Forwards Updated Pages to Proprietary BAW-10171P, REFLOD3B- Model for Multinode Core Reflooding Analysis, Per ECCS Methodology for Facilities Reloads.Mod Removes Henry Quench Temp Criteria & Potential Conflict in Logic.Pages Withheld ML20234C2231987-12-28028 December 1987 Forwards Proprietary BAW-10164P, RELAP5/MOD2-B&W,Advanced Program for LWR LOCA & Non-LOCA Transient Analysis. Rept Describes Computer Code Used to Analyze RCS Behavior During Blowdown Phase of LOCA Transient.Rept Withheld ML20234D1101987-12-14014 December 1987 Forwards Proprietary BAW-10171P, REFLOD3B,Model for Multinode Core Reflooding Analysis. Rept Describes Computer Code That B&W Will Be Using to Analyze RCS Behavior During Refill of LOCA Transient.Rept Withheld ML20237C3611987-11-24024 November 1987 Requests That Proprietary Rev 2 to WCAP-11386, Byron/ Braidwood T-Hot Reduction Final Licensing Rept, Be Withheld (Ref 10CFR2.790(b)(4)) ML20236C0261987-10-22022 October 1987 Forwards Proprietary BAW-10165P, FRAP-T6-B&W:Computer Code for Transient Analysis of LWR Fuel Rods. Rept Describes Computer Code That B&W Will Be Using for Future Transient Analyses of LWR Fuel Rods.Rept Withheld (Ref 10CFR2.790) LD-87-056, Forwards Summary of C-E Fuel Irradiated &/Or Discharged in 1986 on plant-by-plant Basis in Response to 870807 Request1987-09-18018 September 1987 Forwards Summary of C-E Fuel Irradiated &/Or Discharged in 1986 on plant-by-plant Basis in Response to 870807 Request ML20236H4971987-07-29029 July 1987 Forwards Draft Proprietary Topical Rept BAW-10166P, Beach Computer Code for Reflood Heat Transfer During Loca. Draft Submitted to Permit Interaction Between B&W,Nrc & Util. Affidavit for Withholding Encl.Fee Paid ML20236B4141987-07-13013 July 1987 Forwards Proprietary Draft 1 of BAW-10168P, ...B&W LOCA Evaluation Model for Recirculating Steam Generator Plants, to Be Used for LOCA Analysis of Catawba & McGuire Reload Fuel Cycles.Rept Withheld (Ref 10CFR2.790).Fee Paid ML20196K1621987-07-0909 July 1987 Partially Deleted Ltr Submitting Addl Info in Response to NRC 861230 & 870211 Requests Re 860918 Application for Exemption from Requirement to Convert from High Enriched U to Low Enriched U for Reactor Fuel,Per Generic Ltr 86-12 ML20215L0591987-06-22022 June 1987 Responds to Request for Assurance That Facility Neutron Monitoring Sys Design Similar to Design of Other Plants.List of Plants W/Similar Design,Already Reviewed & Approved by Nrc,Encl ML20215D4081987-05-15015 May 1987 FOIA Request for Reactor Vessel Surveillance Capsule Repts for Turkey Point 4,Zion 2 & DC Cook 1 ML20237D2761987-04-27027 April 1987 Forwards List of 200 Parameters That Company Will Provide to Offsite Agencies,Per Request to D Schultz.List of Parameters That Will Be Available to NRC Via Zion Data Link During Coming Federal Field Exercise & Dryrun Also Encl ML20212R4711987-04-15015 April 1987 Forward Proprietary Draft 1 to BAW-10171P, REFLOD3B,Model for Multinode Core Reflooding Analysis, for Review of ECCS Methodology for Plants Fuel Reloads,Per . W/Affidavit.Draft Withheld (Ref 10CFR2.790).Fee Paid LD-87-017, Responds to 870327 Questions Re Steam Generator Tube Vibration Observed at Palo Verde Units 1 & 2.Definition & Scope of Program to Review Phenomenon Will Be Available for Review W/Nrc in Approx 90 Days1987-04-10010 April 1987 Responds to 870327 Questions Re Steam Generator Tube Vibration Observed at Palo Verde Units 1 & 2.Definition & Scope of Program to Review Phenomenon Will Be Available for Review W/Nrc in Approx 90 Days ML20206E7851987-04-0202 April 1987 Confirms Intention to Use FOAM2 Computer Program as Part of ECCS Evaluation Model for Westinghouse Designed Plants. Review of Applicability of Code to Westinghouse Designed Plants Requested Prior to 880701 ML20237D6431987-03-25025 March 1987 Forwards Technical & Cost Proposal for Task Order 009, Continuing Exercise Support to NRC Operations Ctr, Electronic Transmission of Plant Parameters During Exercises, Under Contract NRC-05-86-170 ML20237D6681987-03-0404 March 1987 Forwards Revised Draft Statement of Work Proposed for Task Order 009, Continuing Exercise Support to NRC Operations Ctr,Electronic Transmission of Plant Parameters During Exercises, for Contract NRC-05-86-170 ML20237D6881987-02-14014 February 1987 Forwards Parameters & Computer Points That Author Will Be Attempting to Get Util to Make Available for Transmission to NRC During Federal Field Exercise - 2 ML20205G1591987-01-20020 January 1987 Requests Proprietary Responses to NRC Review Questions Re Resistance Temp Detector Bypass Elimination Be Withheld (Ref 10CFR2.790) NRC-87-3194, Documents 861231 Telcon Re Anomalous Plant Data at Callaway & Wolf Creek.Investigation Initiated.Data Specs for McGuire, Catawba & Millstone Will Be Transmitted1987-01-0707 January 1987 Documents 861231 Telcon Re Anomalous Plant Data at Callaway & Wolf Creek.Investigation Initiated.Data Specs for McGuire, Catawba & Millstone Will Be Transmitted ML20214P1911986-11-19019 November 1986 Forwards Proprietary NEDC-31336, GE Instrument Setpoint Methodology, Per Lrg Instrument Setpoint Methodology Group .Rept Applicable to Listed Plants & Withheld (Ref 10CFR2.790) 1990-02-08 |
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G E N E R A L $; E LE CT R I C ENGINEERING GENERAL ELECTRIC COMPANY. P.O. BOX 460, PLEASANTON, CALIFORNIA 94566 DIVISION March 22,1982 3;l12 ' *,'
f/
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N 21 Mr. H. R. Denton, Director S -.
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Division of Operating Reactors
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Office of Nuclear Reactor Regulation s
U. S. Nuclear Regulatory Commission Washington, D. C.
20555
'3 jy References : 1) Docket 50-18
- 2) Docket 50-70
- 3) Docket 50-73
- 4) Docket 50-183
Dear Mr. Denton:
As is customary, copies of the General Electric Annual Report are forwarded to the Commission in order to provide updated General Electric corporate and financial information.
Accordingly, copes of the 1981 Annual Report are enclosed for the ref,*enced dockets.
Sincerely,
(
~
G. E. Cunningham Sr. Licensing Er
+r GEC:sg Enclosures I i 8203290100 820322 PDR ADOCK 05000
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