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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:EDUCATIONAL INSTITUTION TO NRC
MONTHYEARML20195C1421988-06-13013 June 1988 Informs That Dk Gehmlich,Associate Dean for Academic Affairs,Replaced Re Stephenson as Reactor Administrator Effective on 880609.Current Membership of Reactor Safety Committee Listed ML20151A3451988-03-0303 March 1988 Informs That Listed Personnel Make Up New Reactor Operations Staff at Triga (R-126) & Agn (R-25) Reactors ML20235B8211987-08-0707 August 1987 Requests That Sending of Unneeded Circular Info Be Discontinued.School No Longer Has Nuclear Reactor ML20207R8261987-03-0202 March 1987 Forwards Ltr Requesting Commission to Review Director'S Decision DD-87-02,per 2.206 (c)(1),to Determine If Director Grossly Abused Discretion by Misrepresenting Petition,Not Responding to Important Points & Deceiving Petitioners ML20206G9281987-02-0606 February 1987 Discusses Scoping Analysis for Direct Heating in Plant. Analysis of Plant Containment Continuing.Aim to Develop Methodology That Can Be Used in Categorizing Other Containments ML20203G3381986-06-12012 June 1986 FOIA Request for Documents Re Reactor & Senior Reactor Operator Licensing Exam Results for Jan 1983 - Dec 1984 ML20141N3711985-12-17017 December 1985 Appeals Denial of FOIA Request for Four Categories of Documents Re Fraudulent Computer Programs ML20138F5071985-10-25025 October 1985 FOIA Request for Four Categories of Documents Re Leak Rate Testing ML20141N2851985-10-21021 October 1985 Responds to 850927 Order to Show Cause Re Removal of Highly Enriched Fuel from Research Reactor.Indefinite Stay of Execution Requested for Listed Reasons,Per Item 3 of Order ML20141N2821985-10-0808 October 1985 Responds to 850927 Order to Show Cause Re Removal of Highly Enriched U to Secure Facility.No Unirradiated High Enriched U Kept on Hand ML20147E7671984-09-24024 September 1984 Forwards INPO Accreditation:Board Members Perspective, Presented at ANS 1984 Annual Meeting in New Orleans.Proposed Rule Should Contain Min Requirements to Avoid Discouraging INPO Initiatives ML20128N9521984-04-30030 April 1984 Forwards Comments Re Quest Study of Surry Tmlb Scenario. Clarification Needed Re Where Data Obtained for Solid Triangle (Sascha) Data Points in Figure A-3 ML20210E6661984-02-27027 February 1984 Forwards Newspaper Ad Re Reasons for 840211 Civil Disobedience Over Plant Emergency Plan ML20210E7141984-02-0101 February 1984 Provides General Concept of Evacuation Time Estimates Re Baseline Scenarios Such as Normal & Adverse Weather.Time Estimates Technically Sound & Based on Best Available Data ML20210E7101984-01-30030 January 1984 Forwards Repts on Fog & Rain.Copies of Questions on Plant & Responses to Date Requested.W/O Encls ML20210E6701984-01-0909 January 1984 Ack 831230 Response to Concerns Over Emergency Response Plan at Plant,Including FEMA Response from R Vickers.Fema Response Inadequate Re Evacuation Time Considerations & Evacuation Routes ML18089A4731983-12-20020 December 1983 Forwards Summary of Facility Evacuation Time Estimates Based on Review Against NUREG-0654,Rev 1.No Deficiencies Noted ML20210E7001983-12-0909 December 1983 Ack 851202 Response to Re Concerns in Emergency Response Plans.Concerns Expressed Re Rebuilding of Twin Bridges & Siren Backup ML20210E6841983-11-0404 November 1983 Forwards Examples from Newspaper Re Concerns Over Plants Emergency Response Plan ML20105B3561982-06-0101 June 1982 Submits Rept Re Security Incident in Response to 10CFR73.71(c) Detailing Loss of Security Effectiveness, Responses Made & Efforts to Revise Sys & Procedures to Reduce Chance of Recurrence.Portions Deleted ML20239A4041964-08-17017 August 1964 Forwards Bodega Bay Meteorological Hazard Implications Repts for Info.W/O Encls ML20234B7891964-08-0505 August 1964 Discusses Ongoing Studies of Sonoprobe Lines in Tomales Bay. About 150 Miles of Lines Completed & Indicate Complex Structures.Sonoprobe Survey Will Also Be Conducted by Scripps Institution of Oceanography.Related Info Encl ML20234E3421964-04-25025 April 1964 Discusses 640318 Visit to Proposed Reactor Site Re Geology of Bodega Head.Controversy Lies W/Displacement of Shaft Fault.Diagrams Encl ML20234F5981964-04-0808 April 1964 Advises That F Neumann Suffered Stroke & Remains in Critical Condition in Hosp.Ha Coombs & Author Available to Assist AEC in Connection W/F Neumann Work ML20235C6131964-03-27027 March 1964 Ack Receipt of Re Amend 6 to PG&E Application for Bodega Bay Reactor & Notes That Amend Supersedes Amend 4. Comments on Questions Raised at Preceeding Meeting in Washington,Dc Not Completed ML20234D7781963-07-16016 July 1963 Ack Receipt of & Inquires If Possibly Incomplete. Expresses Doubt as to Whether Dilution Factor Determined by Diffusion or Dye Extrapolated to Apply to Heat Loss of Large Water Flow ML20234D2791963-07-15015 July 1963 Advises That Matl Sent Earlier Will Probably Be Revised Following Receipt of Written Matl from Pg&E.Suggestions from Legal Staff to Answer Encl Ltrs Opposing Proposed Plant at Bodega Bay Requested ML20234F4431963-07-10010 July 1963 Informs That by End of Wk,All Modified Illustrations to Be Completed.Forwards Results on El Centro Analysis,Per Discussion of Resultant Accelerations & Velocities at Last Meeting.Illustrations to Be Included in Final Rept ML20234D9771963-06-24024 June 1963 Ack Receipt of Forwarding Matl Re Engineering Plans for Proposed Bodega Head Power Plant.Some Questions Still Unanswered & Commented on in Replies to Recent Inquiries ML20234D9131963-06-21021 June 1963 Informs of Expected Arrival on 630624 & Reservation on Jet Leaving 630626 ML20235A8491963-06-19019 June 1963 Forwards Rept on Seismological Aspects of Proposed Nuclear Power Plant on Bodega Head,Ca,Per 630613 Conference ML20235A5611963-06-0808 June 1963 Urges AEC to Consider Listed Facts in Deciding Util Application for Nuclear Power Generating Plant at Bodega Head,Ca,Including Fact That Proposed Site Located Near San Andreas Fault.Tj Edmonds Ltr to President Kennedy Encl ML20235A3161963-06-0505 June 1963 Comments on ACRS 630418 Rept Re Proposed Reactor at Bodega Head.Committee May Have Been Misled Re Potential Impact of Condensor Coolant Discharge on Local Marine Life.L Watters to President Kennedy Encl ML20234F5011963-05-29029 May 1963 Forwards Critical Review of Gw Housner Paper Entitled Behavior of Structures During Earthquakes, Ref in Hazards Rept Submitted to AEC in Connection W/Bodega Head Power Plant.Citizen Ltrs to President Kennedy & Udall Encl ML20239A5571963-05-22022 May 1963 Forwards Answers to Three Questions Raised at Urbana Conference Re Estimate of Magnitude of Max Credible Earthquake,Credible Ground Acceleration (Peak & Average) & Amount of Permanent (Faulting) Displacement of Head ML20234B2281959-12-18018 December 1959 Requests Statement of Limits Now in Force or Being Proposed for Some Larger Power Reactors in Us.Requests Specific Info on First Seven Reactors Listed on Page 6 of Info Bulletin TID-8200 1988-06-13
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17347B5881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 ML15217A1031990-02-28028 February 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML20006G0621990-02-22022 February 1990 Forwards Revised Proprietary Pages to DPC-NE-2004, Core Thermal Hydraulic Methodology Using VIPRE-01, Reflecting Minor Methodology Changes Made During Review & Approval Process.Pages Withheld ML20006E5881990-02-20020 February 1990 Forwards Proprietary Response to NRC 890725 Questions Re Vipre Core Thermal Hydraulic Section of Topical Rept DPC-NE-3000 & Rev 2 to Pages 3-69,3-70,3-78 & 3-79 of Rept. Encls Withheld (Ref 10CFR2.790) ML20006E1441990-02-16016 February 1990 Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals ML20006E9071990-02-16016 February 1990 Discusses Plants Design Control Program.Util Adopted Concept of Design Change Implementation Package (Dcip).Dcip Will Contain or Ref Design Change Notice Prepared Per Approved Procedures ML20006E4201990-02-14014 February 1990 Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 ML20011E6151990-02-12012 February 1990 Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21) ML20011E5571990-02-0808 February 1990 Forwards Us Bankruptcy Court for Eastern District of Tennessee Orders & Memorandum on Debtors Motion to Alter or Amend Order & Opinion Re Status of Sales Agreement Between DOE & Alchemie.Doe Believes Agreement Expired on 890821 ML20011E4991990-02-0606 February 1990 Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested ML20011E5981990-02-0505 February 1990 Requests That Listed Individuals Be Deleted from Svc List for Facilities.Documents Already Sent to Dept of Environ Protection of State of Nj ML20006D6911990-02-0202 February 1990 Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle ML20006C5661990-01-31031 January 1990 Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants ML20006B7961990-01-29029 January 1990 Forwards Summaries of Latest ECCS Evaluation Model Changes ML20006C6711990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Plants Have Established Preventive Maint Program for Intake Structure & Routine Treatment of Svc Water Sys W/Biocide to Control Biofouling ML20006D6611990-01-29029 January 1990 Advises That 900117 License Amend Request to Remove Certain cycle-specific Parameter Limits from Tech Specs Inadvertently Utilized Outdated Tech Specs Pages.Requests That Tech Specs Changes Made Via Amends 101/83 Be Deleted ML20011E2521990-01-29029 January 1990 Forwards Proprietary Safety Analysis Physics Parameters & Multidimensional Reactor Transients Methodology. Three Repts Describing EPRI Computer Code Also Encl.Proprietary Rept Withheld (Ref 10CFR2.790) ML18153C0951990-01-29029 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Belief in Appropriateness to Address Generic Ltr 89-13 Concerns within Context of Established Programmatic Improvements Noted ML18094B2861990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Aggressive Program of Monitoring,Insp & Matl Replacement Initiated in Advance of Generic Ltr 89-13 Issuance ML18153C0871990-01-26026 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures to Be Revised & Familiarization Sessions Will Be Conducted Prior to Each Refueling Outage ML20006D2431990-01-26026 January 1990 Provides Info Re Emergency Response Organization Exercises for Plants.Exercises & Callouts Would Necessitate Activation of Combined Emergency Operations Facility Approx Eight Times Per Yr,W/Some Being Performed off-hours & Unannounced ML19354E4191990-01-25025 January 1990 Comments Re Issuance of OL Amends & Proposed NSHC Determination Re Transfer of Operational Mgt Control of Plants & Views on anti-trust Issues Re Application for Amend for Plants ML19354E6711990-01-24024 January 1990 Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226 ML17347B5451990-01-24024 January 1990 Informs of Plans to Apply ASME Code Case N-356 at Plants to Allow Certification Period to Be Extended to 5 Yrs.Rev to Inservice Insp Programs Will Include Use of Code Case ML19354E4451990-01-22022 January 1990 Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters ML19354E4461990-01-22022 January 1990 Forwards Proprietary Rev 1 to DPC-NE-2001, Fuel Mechanical Reload Analysis Methodology for MARK-BW Fuel, Adding Section Re ECCS Analysis Interface Criteria & Making Associated Administrative Changes.Rev Withheld ML20005G7161990-01-20020 January 1990 Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl ML20006A8001990-01-19019 January 1990 Forwards Response to NRC 891220 Ltr Re Violations Noted in Plant Insps.Response Withheld (Ref 10CFR73.21) ML16152A9091990-01-18018 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. W/900131 Release Memo ML18153C0771990-01-17017 January 1990 Forwards North Anna Power Station Emergency Plan Table 5.1, 'Min Staffing Requirements for Emergencies' & Surry... Table 5.1, 'Min Staffing Requirements...', for Approval,Per 10CFR50.54(q),NUREG-0654 & NUREG-0737,Suppl 1 ML20006A2011990-01-16016 January 1990 Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel in Anchor Darling Swing Check Valves.Eight Subj Valves Identified in Peach Bottom Units 1 & 2 & Will Be Returned to Mfg ML20006A6241990-01-16016 January 1990 Forwards Draft Qualified Master Trust Agreement for Decommissioning of Nuclear Plants,For Review.Licensee Will Make Contributions to Qualified & Nonqualified Trust as Appropriate ML18153C0731990-01-15015 January 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or or Valves.... Util Replaced Studs in twenty-five Valves ML20005G6431990-01-10010 January 1990 Responds to Generic Ltr 89-21 Re Implementation of USI Requirements,Consisting of Revised Page to 891128 Response, Moving SER Ref from USI A-10 to A-12 for Braidwood ML20006A8201990-01-10010 January 1990 Forwards Errata to Rev 3 to BAW-1543,Tables 3-20 & E-1 of Master Integrated Reactor Vessel Surveillance Program Reflecting Changes in Insertion Schedule for A5 Capsule for Davis-Besse & Crystal River ML20006B8821990-01-10010 January 1990 Reissued Ltr Correcting Date of Util Ltr to NRC Which Forwarded Updated FSAR for Byron/Braidwood Plants from 881214 to 891214.W/o Updated FSARs ML20005G7601990-01-0404 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Plan. Privacy Info Should Be Deleted Prior to Placement in Pdr.W/ D Grimsley 900118 Release Memo ML18094B2331990-01-0303 January 1990 Certifies Util Implementation of fitness-for-duty Program, Per 10CFR26.Training Element Required by Rule Completed on 891215.Chemical Testing for Required Substances Performed at Min Prescribed cut-off Levels,Except for Marijuana ML18153C0491990-01-0303 January 1990 Advises of Implementation of fitness-for-duty Program Which Complies w/10CFR26.Util Support Objective of Providing Assurances That Nuclear Power Plant Personnel Will Perform Tasks in Reliable & Trustworthy Manner ML20005F4641990-01-0303 January 1990 Advises That Licensee Implemented 10CFR26 Rule Re fitness-for-duty Program W/One Exception.Util Has Not Completed Background Check for Some of Program Administrators.Checks Expected to Be Completed by 900105 ML20042D3731990-01-0202 January 1990 Forwards Revised Crisis Mgt Implementing Procedures, Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9, Rev 1 to CMIP-14 & Rev 30 to CMIP-21 ML17347B5051990-01-0202 January 1990 Certifies That Util Has fitness-for-duty Program Which Meets Requirements of 10CFR26.Util Adopted cut-off Levels Indicated in Encl ML17347B4961989-12-28028 December 1989 Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Considering Expansion of Plants to Include Addl safety-related & Position Changeable Valves W/ Emphasis on Maint & Testing ML20042D3381989-12-28028 December 1989 Forwards Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. Util Will Comply W/Ltr Recommendations W/Noted Exceptions.Response to Be Completed When Ltr Uncertainties Cleared ML18094B2201989-12-27027 December 1989 Advises of Intent to Provide follow-up Response to Generic Ltr 89-10 by 900831 to Describe Status of Program, Recommendation Exceptions & Any Schedule Adjustments ML18094B2291989-12-27027 December 1989 Requests to Apply ASME Section XI Code Case N-460 to Facilities Re Reduction in Exam Coverage on Class 1 & 2 Welds.Fee Paid ML20005E1911989-12-26026 December 1989 Forwards Revised Page 2 Correcting Plant Implementation Date for USI A-24 Requirements in Response to Generic Ltr 89-21 ML18153C0261989-12-26026 December 1989 Responds to Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & surveillance.Motor-operated Valve Program Structured to Allow Similar Approach to motor-operated Dampers.Results Will Be Submitted in 30 Days 1990-03-01
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. F' RANK NEUMANN ~ g3 y *b SEssMOLOSiev. GEcLosY DEPARTMENT UNIVERSITY OF WASHIN 5?DN SEATTLE S.WASHIN GTON June 24,1963. *
- Dr. Robert H. Bryan, Chief, Research and Power Reactor Safety Branch, Division of Licensing and Regulation, U. S. Atomic Energy Commission, Washington 25, D. C.
Dear Dr. Bryan:
Over the week end I have reviewed the material for-warded with your letter of June 20 and in other ways have endeavored to reconcile my views with PG&E's engineering plans for the proposed
. Bodega Head power plant. There are still some unanswereiquestions
._ which I shall touch on briefly in ocumenting on the rglios to the recent inquiries. Reference is made to the questions in Mr. Lowen-stein's letter of May 24, 1963 and the PG&E replies in Aamendment No. 3 (Docket No. 50-205) .
The answer io question 1 is straightforward enough; I sm just a little skeptica.'. about the optimism expressed in view of the fact that Housner in his paper " Behavior of Structures During Earthquakes" (Journ. Eng. Mech. Div., ASCE, Oct.1959) and-Blume, Newmark and Corn-ing in their book "' Design'of Multistory Reinforced Conorate ~ Buildings for Earthquake Motions" both give the impression that one should never ;
expect even a well designed structure to escape damage entirely in an I earthquake of abnormal intensity. Housner says (p.128):"It is more !
, - reasonable to take,the point of view that -- in the more rare event' ,
of a very strong ground motion, damage would be tolerated so'long as it was not a hasard to life and limb. This is the usual point of view of engineers". Blume, Newmark and Corning state (p.vi) " The -
]
objective is to proportion a structure in such a way that -- the structure should not collapse even when subjected to the motions of . i an earthquake of abnormal intensity". This- evidently is what the Uniform Building Code contemplates and this is the code that will be '
used in designing critical structures at Bodogs. Head.
In question 2 Mr. Lowenstein asked "What ground motions are to be used for dynsaio design?". Housner answered by stating "The design of critical structures will be based on the design velocity spectrum ;
shown on the attached sheet". This is not an answer to the question. ;
It is noted thsit for the respective' dampings of 15%, 7.5% and 2.5%
the spectra 1Tr reformational motions would be only about 1.5, 2.0 and 3.5 times greater than the El Centro . ground motions. If the El i Centro ground motions were doubled as suggested in my recent report . -
to you the reformational motions would be only".75,1.0 and 1.6 '
times the ground motions. . What concerns me is that Coast and Geodetic seismographs placed on the top floors of building,s show approximately 5 to 10 times as much motion on top floors as in basements. The higher:
1 slues no doubt indicate resonance' or partia oe. Realizing
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thatthese top floor motions are not reformational motions (Building '
notions relative to the round motion) and that at the building's' t centers the motions ma uly about half the top floor motions the
'l resulting ratios are never-the-less so much greater than indiented in
- I the. proposed velocity spectrum sad the El Centro ground motion as to ,
- I. be a cause for some second thoughts. Considerable data on top floor '-
i building motions during earthquakes are available but ' engineers seem
! to prefer using theoretical building motions (velocity spoetra) in.
J their estimates of structural deformations. (I believe a test.or-r- two was made with controlled explosions with this in mind).
If you do not have the B1tane,' Newmark, Corning book you should l
-i by all means get it; the preface is especially interesting. It is (
( difficult to reconcile the unquestionable sureness that permeates j j the PG&E proposals and ammendments with the sometimes almost epolo-gotic attitude found in professional papers on the same subject where ,
researchersadmittheexploratorynatureoftheentirejoissiodesign problem and the dearth of adequate knowledge in so many important .,
r :- phases of it.
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, In answerg No. 3 Housner states:"a further analysis will be made j to insure that ground motion five times as intense as the design spoo-d i- - trian will be required to produce incipient failure of structure". Ii' )
L the design velocity spectra are multiplied by 5 and drawn on a 4-way
, log chart it will be_seen that the tround motions will range from
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2.5 to 4.6 g. Is this what is meant? If not, just what is the ground motion that is related to the ' design spoetra -- same as question No. 2.
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With reference to the design lateral acceleration at'the roof level-of the reactor structure being nine times larger than is specified by
~
the Uniform Building Code does this refer to a design acceleration in
!n Zone 1 (minor damage) or Zone.3 (major damage)? In Zone 3 the code a calls for increasing lateral force factors four times over those used r in Zone 1. This would sesmingly represent a doubling of the lateral
- force factor over that called for anywhere in Zone 3 earthquake areas "
l
,l - -- to take care of maximum forces in the epioentral area. Just what i, intensity does Zone 3 signity? -
).
) The proposed damping factors are less than had been anticipated.
i! They would on11 for quite large ratios between expectable building l: -
(spectral) motions and ground motions; not the minimum so often found
.f in the computations of oscillator spectra.
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The answer to question No. 4 should be left to geologists exclus-s
]. ively.
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- Sincerely yo e, !
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,* N" Frank Neumann, Seismologist.
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