|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML17347B5881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 ML15217A1031990-02-28028 February 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) ML20006G0621990-02-22022 February 1990 Forwards Revised Proprietary Pages to DPC-NE-2004, Core Thermal Hydraulic Methodology Using VIPRE-01, Reflecting Minor Methodology Changes Made During Review & Approval Process.Pages Withheld ML20006E5881990-02-20020 February 1990 Forwards Proprietary Response to NRC 890725 Questions Re Vipre Core Thermal Hydraulic Section of Topical Rept DPC-NE-3000 & Rev 2 to Pages 3-69,3-70,3-78 & 3-79 of Rept. Encls Withheld (Ref 10CFR2.790) ML20006E1441990-02-16016 February 1990 Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals ML20006E9071990-02-16016 February 1990 Discusses Plants Design Control Program.Util Adopted Concept of Design Change Implementation Package (Dcip).Dcip Will Contain or Ref Design Change Notice Prepared Per Approved Procedures ML20006E4201990-02-14014 February 1990 Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 ML18094B3291990-02-14014 February 1990 Forwards Printouts Containing RW-859 Nuclear Fuel Data for Period Ending 891231 & Diskettes ML20011E6151990-02-12012 February 1990 Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21) ML20011E5571990-02-0808 February 1990 Forwards Us Bankruptcy Court for Eastern District of Tennessee Orders & Memorandum on Debtors Motion to Alter or Amend Order & Opinion Re Status of Sales Agreement Between DOE & Alchemie.Doe Believes Agreement Expired on 890821 ML20011E4991990-02-0606 February 1990 Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested ML20011E5981990-02-0505 February 1990 Requests That Listed Individuals Be Deleted from Svc List for Facilities.Documents Already Sent to Dept of Environ Protection of State of Nj ML20006D6911990-02-0202 February 1990 Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle ML20006C5661990-01-31031 January 1990 Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants ML20006D6611990-01-29029 January 1990 Advises That 900117 License Amend Request to Remove Certain cycle-specific Parameter Limits from Tech Specs Inadvertently Utilized Outdated Tech Specs Pages.Requests That Tech Specs Changes Made Via Amends 101/83 Be Deleted ML20011E2521990-01-29029 January 1990 Forwards Proprietary Safety Analysis Physics Parameters & Multidimensional Reactor Transients Methodology. Three Repts Describing EPRI Computer Code Also Encl.Proprietary Rept Withheld (Ref 10CFR2.790) ML20006C6711990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Plants Have Established Preventive Maint Program for Intake Structure & Routine Treatment of Svc Water Sys W/Biocide to Control Biofouling ML20006B7961990-01-29029 January 1990 Forwards Summaries of Latest ECCS Evaluation Model Changes ML18153C0951990-01-29029 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Belief in Appropriateness to Address Generic Ltr 89-13 Concerns within Context of Established Programmatic Improvements Noted ML20006D2431990-01-26026 January 1990 Provides Info Re Emergency Response Organization Exercises for Plants.Exercises & Callouts Would Necessitate Activation of Combined Emergency Operations Facility Approx Eight Times Per Yr,W/Some Being Performed off-hours & Unannounced ML18153C0871990-01-26026 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures to Be Revised & Familiarization Sessions Will Be Conducted Prior to Each Refueling Outage ML18094B2861990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Aggressive Program of Monitoring,Insp & Matl Replacement Initiated in Advance of Generic Ltr 89-13 Issuance ML19354E4191990-01-25025 January 1990 Comments Re Issuance of OL Amends & Proposed NSHC Determination Re Transfer of Operational Mgt Control of Plants & Views on anti-trust Issues Re Application for Amend for Plants ML19354E6711990-01-24024 January 1990 Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226 ML17347B5451990-01-24024 January 1990 Informs of Plans to Apply ASME Code Case N-356 at Plants to Allow Certification Period to Be Extended to 5 Yrs.Rev to Inservice Insp Programs Will Include Use of Code Case ML19354E4461990-01-22022 January 1990 Forwards Proprietary Rev 1 to DPC-NE-2001, Fuel Mechanical Reload Analysis Methodology for MARK-BW Fuel, Adding Section Re ECCS Analysis Interface Criteria & Making Associated Administrative Changes.Rev Withheld ML19354E4451990-01-22022 January 1990 Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters ML20005G7161990-01-20020 January 1990 Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl ML20006A8001990-01-19019 January 1990 Forwards Response to NRC 891220 Ltr Re Violations Noted in Plant Insps.Response Withheld (Ref 10CFR73.21) ML16152A9091990-01-18018 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. W/900131 Release Memo ML18153C0771990-01-17017 January 1990 Forwards North Anna Power Station Emergency Plan Table 5.1, 'Min Staffing Requirements for Emergencies' & Surry... Table 5.1, 'Min Staffing Requirements...', for Approval,Per 10CFR50.54(q),NUREG-0654 & NUREG-0737,Suppl 1 ML20006A6241990-01-16016 January 1990 Forwards Draft Qualified Master Trust Agreement for Decommissioning of Nuclear Plants,For Review.Licensee Will Make Contributions to Qualified & Nonqualified Trust as Appropriate ML20006A2011990-01-16016 January 1990 Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel in Anchor Darling Swing Check Valves.Eight Subj Valves Identified in Peach Bottom Units 1 & 2 & Will Be Returned to Mfg ML18153C0731990-01-15015 January 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or or Valves.... Util Replaced Studs in twenty-five Valves ML20006A8201990-01-10010 January 1990 Forwards Errata to Rev 3 to BAW-1543,Tables 3-20 & E-1 of Master Integrated Reactor Vessel Surveillance Program Reflecting Changes in Insertion Schedule for A5 Capsule for Davis-Besse & Crystal River ML20006B8821990-01-10010 January 1990 Reissued Ltr Correcting Date of Util Ltr to NRC Which Forwarded Updated FSAR for Byron/Braidwood Plants from 881214 to 891214.W/o Updated FSARs ML20005G6431990-01-10010 January 1990 Responds to Generic Ltr 89-21 Re Implementation of USI Requirements,Consisting of Revised Page to 891128 Response, Moving SER Ref from USI A-10 to A-12 for Braidwood ML20005G7601990-01-0404 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Plan. Privacy Info Should Be Deleted Prior to Placement in Pdr.W/ D Grimsley 900118 Release Memo ML18153C0491990-01-0303 January 1990 Advises of Implementation of fitness-for-duty Program Which Complies w/10CFR26.Util Support Objective of Providing Assurances That Nuclear Power Plant Personnel Will Perform Tasks in Reliable & Trustworthy Manner ML20005F4641990-01-0303 January 1990 Advises That Licensee Implemented 10CFR26 Rule Re fitness-for-duty Program W/One Exception.Util Has Not Completed Background Check for Some of Program Administrators.Checks Expected to Be Completed by 900105 ML18094B2331990-01-0303 January 1990 Certifies Util Implementation of fitness-for-duty Program, Per 10CFR26.Training Element Required by Rule Completed on 891215.Chemical Testing for Required Substances Performed at Min Prescribed cut-off Levels,Except for Marijuana ML17347B5051990-01-0202 January 1990 Certifies That Util Has fitness-for-duty Program Which Meets Requirements of 10CFR26.Util Adopted cut-off Levels Indicated in Encl ML20042D3731990-01-0202 January 1990 Forwards Revised Crisis Mgt Implementing Procedures, Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9, Rev 1 to CMIP-14 & Rev 30 to CMIP-21 ML17347B4961989-12-28028 December 1989 Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Considering Expansion of Plants to Include Addl safety-related & Position Changeable Valves W/ Emphasis on Maint & Testing ML20042D3381989-12-28028 December 1989 Forwards Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. Util Will Comply W/Ltr Recommendations W/Noted Exceptions.Response to Be Completed When Ltr Uncertainties Cleared ML18094B2201989-12-27027 December 1989 Advises of Intent to Provide follow-up Response to Generic Ltr 89-10 by 900831 to Describe Status of Program, Recommendation Exceptions & Any Schedule Adjustments ML18094B2291989-12-27027 December 1989 Requests to Apply ASME Section XI Code Case N-460 to Facilities Re Reduction in Exam Coverage on Class 1 & 2 Welds.Fee Paid 1990-03-01
[Table view] Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20055C3521990-02-26026 February 1990 Notification of 900305 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Facility ML20248E9391989-09-29029 September 1989 Forwards AEOD Technical Review Rept on Debris in Containment Recirculation Pumps.No Occurrences Found to Involve Actual Accumulation of Debris in Containment Sumps.Immediate Corrective Actions Completed ML20248C8311989-09-20020 September 1989 Request for Hearing by Alchemie.* Forwards Response & Request for Hearing,In Response to NRC 890818 Order Modifying License & Order to Show Cause Why Licenses Should Not Be Revoked,For Appropriate Action ML20247H9261989-09-0909 September 1989 Advises That SALP Meeting for Facilities Scheduled for 891115.Assessment Input Should Be Submitted by 891016 ML20245E8501989-08-0707 August 1989 Advises of Reassignments in Project Mgt Duties Due to Recent Reorganization of Standardization & Life Extension Project Directorate ML20245H6451989-08-0404 August 1989 Requests Closure of Outstanding Action Item 87-0198,per 870617 Request Re Review & Evaluation of Acceptability of Fairbanks-Morse Diesel Generator Bearings.Action Completed W/Submittal of Transfer of Lead Responsibility to NRR ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247B7541989-07-19019 July 1989 Confirms That Licensee 880711,890221 & 0630 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Licensing Action for TACs 69886,69887,69893 & 69894 Considered Complete ML20247E6721989-07-17017 July 1989 Proposes Closeout of Plant Correspondence Control Ticket Re Environ Conservation Organization Request for Notification Whenever License Amend Requests Result in Impairment of Plant Operability.Intervenor Will Be Placed on Svc List ML20246K5991989-07-12012 July 1989 Notification of 890725 Meeting W/Util in Birmingham,Al to Discuss Status of Current Licensing Activities & Corporate Initiatives for Plants.Meeting Agenda Encl ML20246L6801989-07-10010 July 1989 Notification of Significant Licensee Meeting 89-101 W/Util on 890718 in King of Prussia,Pa to Discuss Util Engineering Reorganization ML20247A9561989-07-0606 July 1989 Notification of 890717 Meeting W/Lead Plant Utils in Rockville,Md to Discuss Implementation of Revised STS ML20246H3771989-05-12012 May 1989 ALAB-913.* Advises That Time Provided within Which Commission May Act to Review Aslab Decision ALAB-913 Expired.Commission Declined Review.Decision Became Final on 890501.W/Certificate of Svc.Served on 890512 ML20246P9601989-05-10010 May 1989 Discusses 890413 Meeting W/Rosemount & Industry Re Malfunctions of Rosemount Transmitters.List of Attendess, Agenda,Nrc Info Notice 89-042 & Viewgraphs Encl ML20245E9781989-04-17017 April 1989 Forwards Regulatory History AC83-2 Re Licensee Action During Natl Security emergency,10CFR50 (54FR7178) ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20244E2681989-04-12012 April 1989 Summary of Operating Reactors Events Meeting 89-015 on 890412.Discussion of Events,List of Attendees & Three Significant Items Identified for Input Into NRC Performance Indicator Program & Summary of Reactor Scrams Also Encl ML20244A5571989-04-10010 April 1989 Notification of 890502 Meeting W/Util in Rockville,Md to Discuss Nonlinear Piping Analysis to Remove Snubbers & Pipe Supports ML20244A5461989-04-10010 April 1989 Notification of 890503 Meeting W/Util in Rockville,Md to Discuss Using Leak Before Break Methodology on Lines Connected to RCS ML20247B7351989-03-24024 March 1989 Notification of 890503 Meeting W/B&W,Inel & Util in Rockville,Md to Discuss Licensing Submittals for Plants ML20236A9721989-03-0707 March 1989 Forwards Feb 1989 Status Rept Re Current Review Milestones for Each Std Plant Project ML20235S6271989-02-28028 February 1989 Notification of 890307 Meeting W/Bwr Owners Group in Rockville,Md to Discuss Items of Current Interest.Agenda Encl ML20246N3171989-02-23023 February 1989 Notification of 890313 Meeting w/C-E in Rockville,Md to Discuss Results of Salem Project & Licensing of Future C-E Projects ML20245E9441989-01-31031 January 1989 Forwards Proposed plant-specific Backfit for Improved Auxiliary Feedwater Sys Reliability Analyses for Required Improvement in Secondary DHR Capability at Plant ML20196C2701988-12-0202 December 1988 Notification of 881207 Meeting W/Util in Rockville,Md to Discuss Dcrdr Submittal of 880825 ML20196B6081988-11-29029 November 1988 Forwards Status Rept for Nov 1988 Re Std Plant Design Technical Reviews ML20206M9231988-11-23023 November 1988 Lists Questions Raised by Board Study of Licensee Environ Repts on Facilities,For Responses & Comments.Served on 881125 ML20195J0141988-11-22022 November 1988 Notification of 881214 Meeting W/Util in Rockville,Md to Discuss Licensing Actions at Plants ML20206J6441988-11-16016 November 1988 Requests Responses to Listed Questions Re Proceeding, Including Explanation of Environ Consequences Caused by Movement of Centrifuges from State of Oh to State of Tn. Served on 881117 ML20206E6361988-11-14014 November 1988 Forwards Fr Notice Re Applications for Amends to Licenses DPR-51,NPF-6 & NPF-38,authorizing Addition of Sys Energy Resources,Inc as Licensee & Requests Comments on Antitrust Issues ML20206J5741988-11-10010 November 1988 Forwards H Thompson as Balance of NRC Response to State of Tn Re Enrichment of Naturally Occurring Radionuclides in Proposed Facilities,Per NRC ML20206J5571988-11-0909 November 1988 Forwards NRC Review & Evaluation of Facilities Security Plans Discussing Equipment & Procedures Used by Applicant to Meet Requirements in 10CFR95.W/o Encl ML20195G2581988-11-0808 November 1988 Partially Deleted Memo Re Commissioner Carr 880113-15 Visit to Plant,Meeting W/State of Mo Officials & Visit to Mallinckrodt,Inc ML20205T6491988-11-0707 November 1988 Ack Receipt of to Chairman Zech Re Alchemie Applications to Operate Facility for Separation of Stable Isotopes at Oak Ridge,Tn & Construct Similar Facility at Oliver Springs,Tn ML20205T5821988-11-0707 November 1988 Notification of 881115 Meeting W/Devonrue & Util in Rockville,Md to Discuss Proposed Std Alternate AC Design to Meet Station Blackout Rule ML20205R6731988-11-0404 November 1988 Forwards NRC Testimony of Jj Swift Addressing ASLB Inquiries of 881018 & Two Attachments.Related Correspondence ML20205N3691988-10-28028 October 1988 Advises That ASLB Tentatively Calling for Telcon on 881109 W/Parties & State of Tn to Discuss Need for Further Prehearing Conference & Other Scheduling Matters,Per 881026 Request.Served on 881031 ML20206B2481988-10-27027 October 1988 Notice of Significant Licensee Meeting 88-174 on 881118 in King of Prussia,Pa to Discuss Configuration Mgt ML20195B6131988-10-26026 October 1988 Forwards Status Rept on Std Plant Design Technical Reviews ML20205K3321988-10-26026 October 1988 Forwards SER Re Const Mod & Licensing of & Application for CP for Facilities.Nrc Review of Safeguards/Security Plans for Two Proposed Facilities Sent to Board & Applicant.Telcon to Discuss Scheduling Matters Requested.W/O Encls ML20155H3621988-10-18018 October 1988 Requests Addl Info Re NRC Environ Assessments Submitted on 880914 for Uncontested Proceedings,To Complete Review of Adequacy of NEPA Assessments.Served on 881018 ML20204G0741988-10-17017 October 1988 Forwards Mh Mobley from State of Tn to NRC Not Received Until 881014.NRC Will Address Matters in Ltr in SER ML20204J5841988-10-12012 October 1988 Forwards AEOD/E807, Pump Damage Due to Low Flow Cavitation, in Response to Item 5 of Actions Directed by EDO to Respond to Diagnostic Evaluation Team Rept.Nrr Issued Bulletin 88-004 Addressing Low Flow Problem ML20205L2281988-10-12012 October 1988 Forwards AEOD/e807, Pump Damage Due to Low Flow Cavitation, in Response to Action Item 5 Assigned by EDO in 880406 Memo Re Diagnostic Evaluation Team Rept for Plant. NRR Issued Bulletin 88-004 Addressing Recirculation Problem ML20155C6941988-10-0505 October 1988 Advises That Review Briefing for Listed Plants Scheduled for 881013.Viewgraphs Encl ML20205Q4941988-10-0303 October 1988 Discusses Concerns Raised by State of Tn Re Abundance of Naturally Occurring Radioactivity in Alchemie Processing. Enrichment of Naturally Occurring Radioisotopes Will Not Pose Significant Health Hazard ML20206E0861988-09-28028 September 1988 Requests Verbal Concurrence W/Publishing Notice of Receipt of Petition for Rulemaking PRM-50-50,per 880926 Telcon W/ C Young.Related Info Encl 1990-02-26
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20055C3521990-02-26026 February 1990 Notification of 900305 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Facility ML20248E9391989-09-29029 September 1989 Forwards AEOD Technical Review Rept on Debris in Containment Recirculation Pumps.No Occurrences Found to Involve Actual Accumulation of Debris in Containment Sumps.Immediate Corrective Actions Completed ML20248C8311989-09-20020 September 1989 Request for Hearing by Alchemie.* Forwards Response & Request for Hearing,In Response to NRC 890818 Order Modifying License & Order to Show Cause Why Licenses Should Not Be Revoked,For Appropriate Action ML20247H9261989-09-0909 September 1989 Advises That SALP Meeting for Facilities Scheduled for 891115.Assessment Input Should Be Submitted by 891016 ML20245E8501989-08-0707 August 1989 Advises of Reassignments in Project Mgt Duties Due to Recent Reorganization of Standardization & Life Extension Project Directorate ML20245H6451989-08-0404 August 1989 Requests Closure of Outstanding Action Item 87-0198,per 870617 Request Re Review & Evaluation of Acceptability of Fairbanks-Morse Diesel Generator Bearings.Action Completed W/Submittal of Transfer of Lead Responsibility to NRR ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247B7541989-07-19019 July 1989 Confirms That Licensee 880711,890221 & 0630 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Licensing Action for TACs 69886,69887,69893 & 69894 Considered Complete ML20247E6721989-07-17017 July 1989 Proposes Closeout of Plant Correspondence Control Ticket Re Environ Conservation Organization Request for Notification Whenever License Amend Requests Result in Impairment of Plant Operability.Intervenor Will Be Placed on Svc List ML20246K5991989-07-12012 July 1989 Notification of 890725 Meeting W/Util in Birmingham,Al to Discuss Status of Current Licensing Activities & Corporate Initiatives for Plants.Meeting Agenda Encl ML20246L6801989-07-10010 July 1989 Notification of Significant Licensee Meeting 89-101 W/Util on 890718 in King of Prussia,Pa to Discuss Util Engineering Reorganization ML20247A9561989-07-0606 July 1989 Notification of 890717 Meeting W/Lead Plant Utils in Rockville,Md to Discuss Implementation of Revised STS ML20246D8841989-06-19019 June 1989 Staff Requirements Memo Re 890601 Briefing on Operating Reactors & Fuel Facilities in Rockville,Md.Commission Expressed Disappointment in Long Term Operating Performance of Turkey Point Nuclear Power Plant ML20246H3771989-05-12012 May 1989 ALAB-913.* Advises That Time Provided within Which Commission May Act to Review Aslab Decision ALAB-913 Expired.Commission Declined Review.Decision Became Final on 890501.W/Certificate of Svc.Served on 890512 ML20246P9601989-05-10010 May 1989 Discusses 890413 Meeting W/Rosemount & Industry Re Malfunctions of Rosemount Transmitters.List of Attendess, Agenda,Nrc Info Notice 89-042 & Viewgraphs Encl NUREG-1353, Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-13531989-05-0202 May 1989 Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-1353 ML20245E9781989-04-17017 April 1989 Forwards Regulatory History AC83-2 Re Licensee Action During Natl Security emergency,10CFR50 (54FR7178) ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20244E2681989-04-12012 April 1989 Summary of Operating Reactors Events Meeting 89-015 on 890412.Discussion of Events,List of Attendees & Three Significant Items Identified for Input Into NRC Performance Indicator Program & Summary of Reactor Scrams Also Encl ML20244A5571989-04-10010 April 1989 Notification of 890502 Meeting W/Util in Rockville,Md to Discuss Nonlinear Piping Analysis to Remove Snubbers & Pipe Supports ML20244A5461989-04-10010 April 1989 Notification of 890503 Meeting W/Util in Rockville,Md to Discuss Using Leak Before Break Methodology on Lines Connected to RCS ML20247B7351989-03-24024 March 1989 Notification of 890503 Meeting W/B&W,Inel & Util in Rockville,Md to Discuss Licensing Submittals for Plants ML20236A9721989-03-0707 March 1989 Forwards Feb 1989 Status Rept Re Current Review Milestones for Each Std Plant Project ML20235S6271989-02-28028 February 1989 Notification of 890307 Meeting W/Bwr Owners Group in Rockville,Md to Discuss Items of Current Interest.Agenda Encl ML20246N3171989-02-23023 February 1989 Notification of 890313 Meeting w/C-E in Rockville,Md to Discuss Results of Salem Project & Licensing of Future C-E Projects NUREG/CR-5176, Updated Board Notification 89-01 Re Lll NUREG/CR-5176, Seismic Failure & Cask Drop Analyses of Spent Fuel Pools at Two Representative Nuclear Power Plants1989-02-14014 February 1989 Updated Board Notification 89-01 Re Lll NUREG/CR-5176, Seismic Failure & Cask Drop Analyses of Spent Fuel Pools at Two Representative Nuclear Power Plants ML20245E9441989-01-31031 January 1989 Forwards Proposed plant-specific Backfit for Improved Auxiliary Feedwater Sys Reliability Analyses for Required Improvement in Secondary DHR Capability at Plant ML20196C2701988-12-0202 December 1988 Notification of 881207 Meeting W/Util in Rockville,Md to Discuss Dcrdr Submittal of 880825 ML20196B6081988-11-29029 November 1988 Forwards Status Rept for Nov 1988 Re Std Plant Design Technical Reviews ML20206M9231988-11-23023 November 1988 Lists Questions Raised by Board Study of Licensee Environ Repts on Facilities,For Responses & Comments.Served on 881125 ML20195J0141988-11-22022 November 1988 Notification of 881214 Meeting W/Util in Rockville,Md to Discuss Licensing Actions at Plants ML20206J6441988-11-16016 November 1988 Requests Responses to Listed Questions Re Proceeding, Including Explanation of Environ Consequences Caused by Movement of Centrifuges from State of Oh to State of Tn. Served on 881117 ML20206E6361988-11-14014 November 1988 Forwards Fr Notice Re Applications for Amends to Licenses DPR-51,NPF-6 & NPF-38,authorizing Addition of Sys Energy Resources,Inc as Licensee & Requests Comments on Antitrust Issues ML20206J5741988-11-10010 November 1988 Forwards H Thompson as Balance of NRC Response to State of Tn Re Enrichment of Naturally Occurring Radionuclides in Proposed Facilities,Per NRC ML20206J5571988-11-0909 November 1988 Forwards NRC Review & Evaluation of Facilities Security Plans Discussing Equipment & Procedures Used by Applicant to Meet Requirements in 10CFR95.W/o Encl ML20195G2581988-11-0808 November 1988 Partially Deleted Memo Re Commissioner Carr 880113-15 Visit to Plant,Meeting W/State of Mo Officials & Visit to Mallinckrodt,Inc ML20205T5821988-11-0707 November 1988 Notification of 881115 Meeting W/Devonrue & Util in Rockville,Md to Discuss Proposed Std Alternate AC Design to Meet Station Blackout Rule ML20205T6491988-11-0707 November 1988 Ack Receipt of to Chairman Zech Re Alchemie Applications to Operate Facility for Separation of Stable Isotopes at Oak Ridge,Tn & Construct Similar Facility at Oliver Springs,Tn ML20205R6731988-11-0404 November 1988 Forwards NRC Testimony of Jj Swift Addressing ASLB Inquiries of 881018 & Two Attachments.Related Correspondence ML20205N3691988-10-28028 October 1988 Advises That ASLB Tentatively Calling for Telcon on 881109 W/Parties & State of Tn to Discuss Need for Further Prehearing Conference & Other Scheduling Matters,Per 881026 Request.Served on 881031 ML20206B2481988-10-27027 October 1988 Notice of Significant Licensee Meeting 88-174 on 881118 in King of Prussia,Pa to Discuss Configuration Mgt ML20205K3321988-10-26026 October 1988 Forwards SER Re Const Mod & Licensing of & Application for CP for Facilities.Nrc Review of Safeguards/Security Plans for Two Proposed Facilities Sent to Board & Applicant.Telcon to Discuss Scheduling Matters Requested.W/O Encls ML20195B6131988-10-26026 October 1988 Forwards Status Rept on Std Plant Design Technical Reviews ML20155H3621988-10-18018 October 1988 Requests Addl Info Re NRC Environ Assessments Submitted on 880914 for Uncontested Proceedings,To Complete Review of Adequacy of NEPA Assessments.Served on 881018 ML20204G0741988-10-17017 October 1988 Forwards Mh Mobley from State of Tn to NRC Not Received Until 881014.NRC Will Address Matters in Ltr in SER ML20205L2281988-10-12012 October 1988 Forwards AEOD/e807, Pump Damage Due to Low Flow Cavitation, in Response to Action Item 5 Assigned by EDO in 880406 Memo Re Diagnostic Evaluation Team Rept for Plant. NRR Issued Bulletin 88-004 Addressing Recirculation Problem ML20204J5841988-10-12012 October 1988 Forwards AEOD/E807, Pump Damage Due to Low Flow Cavitation, in Response to Item 5 of Actions Directed by EDO to Respond to Diagnostic Evaluation Team Rept.Nrr Issued Bulletin 88-004 Addressing Low Flow Problem 1990-02-26
[Table view] |
Text
~
d '
}
y.. ' h .g,y. .[ . _ . q.
' . s sl ~ c '
($ ,
.l/ )
,*. ,.e
.. ..s .
. a h
^
Pobruary 25,196k er .
'[.IO..Itt*
, ~%,c.c.
. C 0 FY , #-
-l %!M.5 ... .-
j g.. :TW ;
I i
.I
~
s li s-
d Eenorab3n Glenn T. Seaborg ;
d Chairman l6~ U. 8. Atomia Energr Cansdssian
- l. Weshington, D. C. .
+ J. 1
'h2l ., Subject SEIBMIC DESIM CF BUCIEAR POWER PLANTS
- w. ,o ~
7,r l
.. Dear Dr. Seeborg's ' 4- '
- N : P tUm -
4 w y: !
P- The guestian of appropriate selsde design of nuclear power plants I
^.y;. has resently esenpf ta h uttention of the Advisory Cosetttee en e L, Beactor Safeguards. Most of this study has been ealled for because y of proposals to sonstruet unclear power plants in seismically actiw 1y senes. There have, heuver, also;been.guestians relatin to plants .
L- to be built in regions ukere seismie activity is low er where h l l.$$p .eeisnio history is besea en 1sacertain doeusentation of earth movement' '
that took plane lang ago. . s o
,c . . . .
~ .
sy,r.es , . s .. }.
',~
h Committee believes,that, especial 1F in, esses of W 1atter kind, 1y . useertsiaties tu W geology or h seisats,ity may eause a trend - '
'13 toward shoosing design methods or design parameters with mon een-gF servatism ha is meesssary Adeguate seisnie design guides that ,
@~ ' provide protection eenparable with that provided by other safety '. j j finatures of muelear pisats are needst. - - '
l
.3 ~'
y Before seisnie design guides er parsmaters are adopted for sones of ;
relative seismie gaiet, h Committee suggests further eensideration l of the guestion of earthquake probability and magnitude for these ,
{
- I sones, and of the guestion of adeguate engineering for small earth -
I s movements, t
},
Sincerely yours, d w.m . , I.,
q
/s/ Herbert Kouts.5gg }
d j 8709180053 851217 PDR FOIA Berbert routs k $/ I A W $UI
<f...'i v -
6 J a
FIRESTOB5-665 PDR ,- Chairiaan ..
fm@4,- -
l 4 I t
CDPY )
J
. L ._ . - . _ , . _ - . - . . ,
j
- e. - ,-- -- - .
= =-m
- - - - - - - - - ~
. ~ . . - - __
-c-.
~ . . o / _
- *\ '\
5= a'ut **- F**a*""'""- / F*' ***a-
, g 40UTE SUP Nste and return.
For signature.
For information.
, g. a uss, -
Gev. MSF 14.1947)
/' To (Name and unJt) fMITIALS / R WARKS At my requeste Williamson has written the attached
- C. );./eck e
i B y y DATE! report in response to the ACRS letter (attached) on i seismic design criteria. I think it would be M 71ALS RMARKS a r _TO (Hame and unt0 /
appropriate to send his report to the ACRS for oArc - information. Do you agree?
/ /
/
1 F To (N.me .nd un,0 . R-. .
' ' - ~ -
R. Lowens n
-}
9 Jan k. ~
m .= h A b h2 M d $ -
M V
}~- - . ,
~
o) (Name and un30 mpARKs Vk j)
-.,._-~. e ON- sg,
. . . . 4.--6. vas e l* . .E
, , - uV l ;;,g,.,,,, .-* s
' .n[5 k -
- c. . ~ PHONE feCL DATI
.s .-
Th11 5/12 USE CffHER $10E FOR ADDITIONAL RMARKS SP0 eM 36 7799 e 1
-v-'--.. - _ _ _ . - _
__ * . [, .t ' ' _*
g . * *Q .
g' .,rg
, . s ;,
.4 4,, , ""*.* p* . e7g .,,,, n' mes. h . __ _
' ',. 4.
W dWS._
AM. g '[
p..h_"",
g% y,f.* me-w de - ..wa6.*e.4' --. .
,- ~ . ~ . . -. .
u__-ee.- w
.,M u
, a' .--,
- , 2j;, g . ". .g,g- e,9. y g._*
--. .. . _x l'y. - 'd. g._ * , ,
. ._.2. _ t:; . .~, . i k,~.--,.~...m.,,,2,,n,-+..g,.,,
^'
- _~ ^ -
4 $1 ,N #
~
[kif@[
g N$'D1ydN,, y g .~ -r- YW~=fN5Nb m - , . m -. -
.::y . g n ={.K.EL$. a g m h" p .__[;,.h 4 m $ dE g :t%. f3f N,5QE
.3
.. W W*t5 5 2 h M ' 'r -l* ~ Q V.--c75 ' - 7.e :-# r-;Wh . &gy,t; ::Om -- - r4 n _
m,~*Mwa:;
' -:;.D... . ,..>*p-m.m.-
. w&_ . a.w,.u. %_e.-~.
r,7. .M5swa-G-n w
~--~#*
~,; . ..,-s. . m-w
===. a. * . ,_- y- ..:;w;.W. _. .. - . - -
.w
~M<:,,%si; ;;&Q:g;.,
. - .: a.W%.
m- = .m
.. .,-~4 g.*"*"*
~
w+
~.;--+ ,,,ws. .
~ -.
w i %c ;m_ m.e.n w .-
p%~n;n.
w
. -me
?. .r,,,.*%. .h , wa.
" ,,"ja-
-.+-".
-i"*
Y.e.e .
.**_18.l ,m. . .yyear -f1l mar. ,
g $**; ,-- ,g gQ g n **=.- .,..Z6~Cf WQl^
- yf- ~w[ G &.l.-w<.g,,; ,, . .. - _%. '*",'*'** ., g. 4.i,"w .r--'-;7.-
, .Q%. - - 4. ;% ,k- " '~ -
,,p,.
, C,,,p .'. U;[,=W'~M. ., , _W> ?"2 ,,,,,m,,*-..~.,
,.s..sGWL~~&," . .ff..,R-- . ', '*'***'* Q
- . . . . , . ,y m.,,,,; m. _. $4. . 8 g.. . ,.,,._., _,,,g
- - - * , . -**un . , g a *,;;.s
. 2. %*,?~T'M,n-=** 4m .p* wy ' ~ . , y5 L -- ~ * - mQ*; -" % ".'. ,, , ~~.m"L .Q :*.g*%~~.:.1* --- P ;; . ~, , -
..g%...
b:* "
~
- : .. gf.L"[' * '~ *~, s.&:.;;; . . --- :: -
._c. : .a,, , ,.,.a ,;,. .q.,p, . : , . _" :.
ux.*~~~,~-",, ... .+-3 6
- .; ,.:==~ .- ~
c,4,,,.,;m,. Q-% y .3.=CR;l:.
w:. .p,y p..,16y,, .,, :;-g.w7 ;;jpg, ;;,l=;,,,;;c-:-- ,. p.,,, - _..
ng: y~+ - pyom . . ._ _ _7 .
. e . ,
3,..> _ , .4 -- ~,
_. ~ . . . ~,_u',._ ..
. .w e a n s . . ,
,%.a..."',.,.g v ,, : sk w'*
g__.,,p._.._,
+ ,,,- _,. w . ~ . a
-g %, pg .
ej
- e. - .
s s.
4 ,g,.ea A "'*'5 j g.
-,g * "'
-g . pS. g m P .*
p- d,
wae;. i,'.
(g
.. r P
. .u;,,.;..., --
. e.- .
E' I
B t
t i
?
4 .,
j p *
J '4
....y.
- _ - - _ . _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _