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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:NRC TO UTILITY
MONTHYEARML20055C3921990-02-26026 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) ML20248G9731989-09-20020 September 1989 Forwards Unexecuted Amend 13 to Indemnity Agreement B-69, Reflecting Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu ML20247H6411989-09-12012 September 1989 Advises That 890816 Revisions to ATWS Mitigation Sys Acceptable W/Requirements of 10CFR50.62(c)(1) ML20247K2231989-09-11011 September 1989 Forwards Amends 123 & 41 to Licenses DPR-61 & NPF-49, Respectively & Safety Evaluation.Amends Change Tech Specs 4.10.1.D.1.h & 4.4.5.4.a.8 to Allow Insp of Steam Generator Tubes by Insertion of Ultrasonic Test Probe ML20247E3371989-09-0707 September 1989 Forwards Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Change Tech Spec Sections 6.10.2.m & 6.10.3 Re Records Retention for Radiological Effluent Monitoring & ODCM IR 05000029/19890141989-08-31031 August 1989 Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted ML20246Q0121989-08-31031 August 1989 Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted ML20246C3941989-08-15015 August 1989 Forwards Safeguards Insp Repts 50-272/89-19,50-311/89-17 & 50-354/89-15 on 890710-14.No Violations Noted ML20246C8211989-08-11011 August 1989 Confirms 890808 Telcon Re Util Participation in NRC Regulatory Impact Survey on 891023 in Berlin,Ct.Schedule & General Discussion Groups Shown in Encl ML20248D6921989-08-0404 August 1989 Advises That Rev 6b to Generating Stations Emergency Plan Transmitted by Util 890710 Form Acceptable & Does Not Decrease Effectiveness of Plan ML20248C0561989-08-0303 August 1989 Forwards Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants.Nrc Requested to Be Notified Upon Completion of Human Factors Review ML20245H5331989-08-0202 August 1989 Advises That 890519 Changes to QA Program Described in CPC-2A Acceptable.Issues Addressed Listed ML20247H6891989-07-25025 July 1989 Requests Proposed Design Change to Containment Hydrogen Monitoring Sys,W/Schedule for Implementing Change or Justification for Existing Configuration ML20246A2951989-06-29029 June 1989 Forwards Request for Addl Info Re NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs ML20246L2211989-06-26026 June 1989 Forwards Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Revise Tech Specs by Removing Tech Spec Figures 6.2-1 & 6.2-2 Re Organizations Functional Requirements ML20245J3301989-06-22022 June 1989 Provides Background Info on Regulatory Analysis Supplementing NRC Proposed Backfit,Per 890413 Request.Util Expected to Provide Schedule for Implementation of Required Improvements ML20245F2691989-06-16016 June 1989 Forwards SER Accepting Licensee 850612 Response to Generic Ltr 83-28,Item 4.5.3 Re Trip Reliability & on-line Functional Testing of Trip Sys ML20245B1731989-06-15015 June 1989 Ack Receipt of Rev 55 to QA Topical Rept CE-1-A.Program Satisfies Requirements of 10CFR50,App B & Acceptable ML20245H1491989-06-15015 June 1989 Submits Correction/Clarificaton to Util 890508 Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Program on Critical Air Demand Equipment Is in Addition to Investigations Performed ML20244C2941989-06-0909 June 1989 Advises Tht Util 890329 Request for Approval to Use Fuses for Electrical Isolation of non-Class 1E Dc Power Sys Acceptable Provided That Circuit Breaker in Parallel to Two Fuses Locked Open ML20244C5091989-06-0101 June 1989 Advises That Bunker Ramo Penetration Assemblies Environmentally Qualified to Perform Intended Functions for Plants,Per 890224 Rept & .Concerns Expressed in Re Byron Unit 2 Satisfied ML20248C2671989-05-31031 May 1989 Forwards Insp Repts 50-321/88-37,50-366/88-37 & 50-424/88-53 on 881102-890106 & Notice of Violation.Notice of Violation Withheld (Ref 10CFR2.790(d) & 73.21) ML20247M7731989-05-26026 May 1989 Forwards Director'S Decision Re Ohio Citizens for Responsible Energy 10CFR2.206 Petition Re 880309 Power Oscillation Event at Lasalle,Unit 2 ML20247J7801989-05-19019 May 1989 Informs of Implementation Schedule for Item 1.b of NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification, Mutually Agreed Upon Between NRC & Westinghouse During 890411 Meeting ML20247H3511989-05-19019 May 1989 Advises That Licensee Response to Generic Ltr 82-33 Re post-accident Monitoring Instrumentation,Per Rev 3 to Reg Guide 1.97,acceptable,except for Four Items Listed in Technical Evaluation Rept ML20247G5241989-05-18018 May 1989 Responds to Re Util Position on Dealing W/Dc Grounds After Discussion W/Nrc in 890301 Meeting.Continued Plant Operation Will Be Allowed Only So Long as Applicable Limiting Conditions/Or Action Statements Met ML20247C1521989-05-18018 May 1989 Informs of Implementation Schedule for Item 1.b of NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification. Understands That Westinghouse Will Provide Util W/Generic Bounding Analysis Re Seismic Loadings ML20247B2411989-05-17017 May 1989 Comments on Expeditious Actions & Notice of Audit on Generic Ltr 88-17 Re Potential Loss of Dhr.Requests Addl Info Re Training Packages,Administrative Controls for Containment Closure & RCS Level Indications ML20246Q1511989-05-16016 May 1989 Informs of Implementation Schedule for Item 1.b of NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification, Per 890411 Meeting W/Westinghouse Owners Group.Proposed Schedule for Analysis Must Be Accelerated ML20246P8141989-05-15015 May 1989 Requests Addl Info Re 881130 Application for Amends to Licenses Per Generic Ltr 87-09.Affirmation Should Be Provided That Procedures,Mgt Directives & Onsite Reviews Limit Use of Spec 3.0.4 Exceptions ML20246L2741989-05-11011 May 1989 Forwards Anl Draft Rept Re Main Steam Line Breaks in Plants Ice Condenser,Per Util 880613,0907 & 1012 Ltrs & WCAP-10988 & WCAP-10986P,for Review & Comments within 60 Days.W/O Encl ML20246Q0731989-05-0808 May 1989 Forwards Revised Tech Spec Page B 3/4 4-2,clarifying Operability Requirements for PORVs in Manual or Automatic Mode,In Response to Util 881212 Request ML20247A7781989-05-0303 May 1989 Extends Invitation to Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Meeting Agenda Encl ML20247A5941989-05-0303 May 1989 Extends Invitation to Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Meeting Agenda Encl ML20246Q3711989-05-0303 May 1989 Extends Invitation to Attend Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Agenda & Info Re Lodging Arrangements Encl ML20245L3221989-04-28028 April 1989 Ack Receipt of 881223 Submittal of Rev 8 of QA Topical Rept CPC-2A Re Transfer of QA Assigned Functions to Other Plant Organizations & Continuing QA Organizations Program Control. Topical Rept Acceptable & Meets 10CFR50,App B ML20245J0621989-04-25025 April 1989 Forwards Amends 114,30,141 & 33 to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Modify Tech Specs of Four Units to Be Consistent W/Plant Restart Provision in 10CFR50.36 If Safety Limit Exceeded ML20245C3571989-04-20020 April 1989 Forwards Revised Plant Emergency Operating Procedure Insp Schedule ML20245D8511989-04-19019 April 1989 Requests Schedule to Implement Alternate Rod Injection/ Reactor Trip Sys Design in Full Compliance W/Atws Rule, within 60 Days ML20244E2811989-04-14014 April 1989 Requests Prompt Review & Reporting of Status of Implementation of TMI Action Plan Items at Plants.Printout of All TMI Items Annotated Where Tracking Sys Indicates That Implementation Not Complete Encl ML20245C8221989-04-14014 April 1989 Requests Prompt Review & Reporting of Status of Implementation of TMI Action Plan Items at Facilities. Printout of TMI Items Annotated Where Tracking Sys Indicates That Implementation Incomplete,Encl ML20244C2041989-04-10010 April 1989 Accepts Util Actions in Response to Generic Ltr 88-10 Re Nonconforming molded-case Circuit Breakers & Date of 890701 for Providing Summary of Traceability Determinations & Replacement of non-traceable Breakers ML20244A8391989-04-0606 April 1989 Advises That Emergency Operating Procedures Insp Will Be Conducted at Facilities on 890508-19.List of Required Documents & Insp Schedule Encl ML20248K5451989-04-0505 April 1989 Responds to 890224 & 0322 Ltrs Re NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification. NRC Agrees W/Suggestion for 890407 Meeting to Discuss Util Schedular Proposal ML20247P2781989-03-31031 March 1989 Concurs W/Position Delineated in Re Fire Barrier Penetration Internal Conduit Seals ML20247P0461989-03-16016 March 1989 Consents to Proposed Restructuring of Util.Proposed Action Will Not Affect Qualifications of Util as co-owner & Operator of Plants Consistent W/Applicable Provisions of Law,Regulations & Other Requirements Issued by Commission ML20235Z6501989-03-0707 March 1989 Ack Receipt of 890127 Submittal of Rev 54 to QA Topical Rept CE-1-A.Program Continues to Satisfy Requirements of 10CFR50,App B & Acceptable ML20246L7481989-03-0303 March 1989 Confirms 890323 Meeting in Glen Ellyn,Il to Discuss Util Quality Verification Program,Per ML20236A9971989-03-0101 March 1989 Comments on Licensee Response to Generic Ltr 88-17 Re Expeditious Actions for Loss of Dhr.Advises That Licensee May Wish to Consider Several Observations in Order to Assure That Actions Adequately Addressed ML20235R0811989-02-25025 February 1989 Advises That Incorporation of ASME Code Case N-401-1 Into Inservice Insp Programs at Plants Acceptable,Per 880815 Request.Code Case N-401, Eddy Current Exam & Rev to Code, Code Case N-401-1 Found to Be Technically Equivalent 1990-02-26
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20055C3921990-02-26026 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) IA-89-409, Final Response to FOIA Request.App a & B Records Available in PDR & Encl.Portions of App B Record Withheld (Ref FOIA Exemption 6)1989-09-26026 September 1989 Final Response to FOIA Request.App a & B Records Available in PDR & Encl.Portions of App B Record Withheld (Ref FOIA Exemption 6) ML20247R3361989-09-26026 September 1989 Final Response to FOIA Request.App a & B Records Available in PDR & Encl.Portions of App B Record Withheld (Ref FOIA Exemption 6) ML20248G9731989-09-20020 September 1989 Forwards Unexecuted Amend 13 to Indemnity Agreement B-69, Reflecting Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu ML20248F0321989-09-14014 September 1989 Forwards Rept of AOs at Licensed Facilities for First Calendar Quarter 1989.Plug Failure Resulted in Steam Generator Tube Leak at North Anna Unit 1 & Steam Generator Ruptured at McGuire Unit 1.W/o Encl ML20247L2401989-09-13013 September 1989 Responds to Re K Barnes Concerns Regarding Safety at Plants.Advises That to Date,Releases from Plants Remain Well within Accepted Stds ML20247G2781989-09-13013 September 1989 Partial Response to FOIA Request for Records.Apps F & G Records Available in Pdr.App H Records Partially Withheld & App I Record Completely Withheld (Ref FOIA Exemption 5) ML20247H6411989-09-12012 September 1989 Advises That 890816 Revisions to ATWS Mitigation Sys Acceptable W/Requirements of 10CFR50.62(c)(1) ML20247K2231989-09-11011 September 1989 Forwards Amends 123 & 41 to Licenses DPR-61 & NPF-49, Respectively & Safety Evaluation.Amends Change Tech Specs 4.10.1.D.1.h & 4.4.5.4.a.8 to Allow Insp of Steam Generator Tubes by Insertion of Ultrasonic Test Probe ML20247E3371989-09-0707 September 1989 Forwards Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Change Tech Spec Sections 6.10.2.m & 6.10.3 Re Records Retention for Radiological Effluent Monitoring & ODCM IR 05000029/19890141989-08-31031 August 1989 Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted ML20246Q0121989-08-31031 August 1989 Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted ML20246K8571989-08-25025 August 1989 Discusses NRC Actions in Reponse to Constituent Concerns Re Excessive Overtime Worked by Employees of Plants ML20246C7101989-08-18018 August 1989 Forwards Order,Effective Immediately,Modifying CPs CPEP-1 & CPEP-2 to Require Notification of Commission Before Taking Possession of Any Classified Equipment & to Show Cause Why CPs Should Not Be Revoked ML20246B6591989-08-18018 August 1989 Forwards 40th Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants from Apr-June 1989. Lilco Shareholders Voted to Accept Terms That Provide for Sale of Plant to State of Ny ML20246C3941989-08-15015 August 1989 Forwards Safeguards Insp Repts 50-272/89-19,50-311/89-17 & 50-354/89-15 on 890710-14.No Violations Noted ML20246C8211989-08-11011 August 1989 Confirms 890808 Telcon Re Util Participation in NRC Regulatory Impact Survey on 891023 in Berlin,Ct.Schedule & General Discussion Groups Shown in Encl ML20248D6921989-08-0404 August 1989 Advises That Rev 6b to Generating Stations Emergency Plan Transmitted by Util 890710 Form Acceptable & Does Not Decrease Effectiveness of Plan ML20248C0561989-08-0303 August 1989 Forwards Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants.Nrc Requested to Be Notified Upon Completion of Human Factors Review ML20245H5331989-08-0202 August 1989 Advises That 890519 Changes to QA Program Described in CPC-2A Acceptable.Issues Addressed Listed ML20247P9581989-08-0101 August 1989 Partial Response to FOIA Request.App a Records Available in Pdr.App B Records Encl & Available in PDR ML20247H6891989-07-25025 July 1989 Requests Proposed Design Change to Containment Hydrogen Monitoring Sys,W/Schedule for Implementing Change or Justification for Existing Configuration ML20247F0481989-07-25025 July 1989 Partial Response to FOIA Request for Records.App L Record Available in Pdr.App M Records Partially Withheld Ref (FOIA Exemption 7).App N Record Provided to Requestor But Not Made Publicly Available at This Time ML20246P0181989-07-17017 July 1989 Forwards Request for Addl Info Re 890620 Filing for Reorganization in Us Bankruptcy Court.Nrc Will Initiate Proceeding for Suspension or Revocation of CPs Should Licensee Fail to Respond by 890815 ML20246A2951989-06-29029 June 1989 Forwards Request for Addl Info Re NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs ML20246L2211989-06-26026 June 1989 Forwards Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Revise Tech Specs by Removing Tech Spec Figures 6.2-1 & 6.2-2 Re Organizations Functional Requirements ML20245J3301989-06-22022 June 1989 Provides Background Info on Regulatory Analysis Supplementing NRC Proposed Backfit,Per 890413 Request.Util Expected to Provide Schedule for Implementation of Required Improvements ML20245B4271989-06-21021 June 1989 Final Response to FOIA Request.App U Records Encl & Available in Pdr.App V Record Withheld (Ref FOIA Exemption 5) ML20245F2691989-06-16016 June 1989 Forwards SER Accepting Licensee 850612 Response to Generic Ltr 83-28,Item 4.5.3 Re Trip Reliability & on-line Functional Testing of Trip Sys ML20245H1491989-06-15015 June 1989 Submits Correction/Clarificaton to Util 890508 Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Program on Critical Air Demand Equipment Is in Addition to Investigations Performed ML20245B3881989-06-15015 June 1989 Responds to Re Flow & Pressure Drop Calculations for RWCU & Feedwater & Condensate Sample Panels.Util Actions Do Not Have Adverse Impact on Nuclear Reactor Safety to Extent That Protection of Safety of Environ Affected ML20245B1731989-06-15015 June 1989 Ack Receipt of Rev 55 to QA Topical Rept CE-1-A.Program Satisfies Requirements of 10CFR50,App B & Acceptable ML20244C2941989-06-0909 June 1989 Advises Tht Util 890329 Request for Approval to Use Fuses for Electrical Isolation of non-Class 1E Dc Power Sys Acceptable Provided That Circuit Breaker in Parallel to Two Fuses Locked Open ML20245B4531989-06-0808 June 1989 Forwards Encl Listed Info on Decommissioned & Shutdown Reactors Requested During Discussions at Saxton on 890511 ML20244C5091989-06-0101 June 1989 Advises That Bunker Ramo Penetration Assemblies Environmentally Qualified to Perform Intended Functions for Plants,Per 890224 Rept & .Concerns Expressed in Re Byron Unit 2 Satisfied ML20248C2671989-05-31031 May 1989 Forwards Insp Repts 50-321/88-37,50-366/88-37 & 50-424/88-53 on 881102-890106 & Notice of Violation.Notice of Violation Withheld (Ref 10CFR2.790(d) & 73.21) ML20247M7731989-05-26026 May 1989 Forwards Director'S Decision Re Ohio Citizens for Responsible Energy 10CFR2.206 Petition Re 880309 Power Oscillation Event at Lasalle,Unit 2 ML20247H3511989-05-19019 May 1989 Advises That Licensee Response to Generic Ltr 82-33 Re post-accident Monitoring Instrumentation,Per Rev 3 to Reg Guide 1.97,acceptable,except for Four Items Listed in Technical Evaluation Rept ML20247J7801989-05-19019 May 1989 Informs of Implementation Schedule for Item 1.b of NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification, Mutually Agreed Upon Between NRC & Westinghouse During 890411 Meeting ML20247C1521989-05-18018 May 1989 Informs of Implementation Schedule for Item 1.b of NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification. Understands That Westinghouse Will Provide Util W/Generic Bounding Analysis Re Seismic Loadings ML20247G5241989-05-18018 May 1989 Responds to Re Util Position on Dealing W/Dc Grounds After Discussion W/Nrc in 890301 Meeting.Continued Plant Operation Will Be Allowed Only So Long as Applicable Limiting Conditions/Or Action Statements Met ML20247B2411989-05-17017 May 1989 Comments on Expeditious Actions & Notice of Audit on Generic Ltr 88-17 Re Potential Loss of Dhr.Requests Addl Info Re Training Packages,Administrative Controls for Containment Closure & RCS Level Indications ML20246Q1511989-05-16016 May 1989 Informs of Implementation Schedule for Item 1.b of NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification, Per 890411 Meeting W/Westinghouse Owners Group.Proposed Schedule for Analysis Must Be Accelerated ML20246P8141989-05-15015 May 1989 Requests Addl Info Re 881130 Application for Amends to Licenses Per Generic Ltr 87-09.Affirmation Should Be Provided That Procedures,Mgt Directives & Onsite Reviews Limit Use of Spec 3.0.4 Exceptions IR 05000097/19890011989-05-12012 May 1989 Forwards Safety Insp Repts 50-097/89-01 & 50-157/89-01 on 890425-26.Weakness Identified in Area of Documentation ML20247C0111989-05-12012 May 1989 Forwards NRC Quarterly Status Rept to Congress Covering First Quarter 1989.On 890303,NRC Dismissed Shoreham Intervenors from Licensing Proceeding for Misconduct During Proceeding.W/O Encl ML20246L2741989-05-11011 May 1989 Forwards Anl Draft Rept Re Main Steam Line Breaks in Plants Ice Condenser,Per Util 880613,0907 & 1012 Ltrs & WCAP-10988 & WCAP-10986P,for Review & Comments within 60 Days.W/O Encl ML20246Q0731989-05-0808 May 1989 Forwards Revised Tech Spec Page B 3/4 4-2,clarifying Operability Requirements for PORVs in Manual or Automatic Mode,In Response to Util 881212 Request ML20247A5941989-05-0303 May 1989 Extends Invitation to Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Meeting Agenda Encl ML20247A7781989-05-0303 May 1989 Extends Invitation to Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Meeting Agenda Encl 1990-02-26
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l' Mr. C. C. '.ihelchel l Vice-President Pacific Cas and Electric Company 245 Market street San Francisco, California
Dear Mr. Whelchel:
Question 64 of our letter of May 19, 1964, referred to the need for clarification of the procedures and critaria Pacific Cas and Electric Company proposes to use in the design of the structures and components t.o withstand oscil-lations and vibrations from major earthquakes. After further study and discussions with our consultants and advisers it appears that some amplification of this question and its relation to question fl of our previous letter is in order.
The opinion is held by some that the spectrum of ground motions in case of another r.sajor earthquake on the San Andreas fault may be more severe than that which occurred in the El Centro earthquake. Further, such an earthquake might be accompanied by shear displacement. up to a possible 3 feet, and would likely be followed by aftershocks which might be as large as the El centro earthquake of 1940.
Against the possibility of earthquakes of these dissensions, we would like to explore the design arrangements and their feasibility in protecting the plant against damage which would result in hazards to the health and safety of the public. We request Pacific Cas and Electric Company to consider these questions:
- 1. Assume an earthquake having a vibration spectrum similar to that of El Centro but with maximum acceleration of 2/3 g* velocities up to 2k f t./sec. ; ground displacements
- The marimum of acceleration , velocity and displacement would not occur for the same periods of vibrations.
8709240549 051217 PDR FOIA FIRESTOBS-665 PDR I
4 C. C. Whelchel up to 3 ft.; shear displacement (faulting) of 2 ft, in the foundations of the plant, and with the occurrence of an after-shock equal to El Centro before remedial action could be taken.
- Mtat plant arrangements , design criteria and procedures could be developed to prevent i
- apairment of functions of struc tures ,
equipcent and systems important. to safety? This should include an analysis indicating the margins to allowable stress or deformation limits.
- 2. Assume an earthquake having a vibration spectru:n siailar to that of El Centro but with accelerations generally s up to 2/3 g plus intermittent pulses of acceleration up to 1 g*;
velocities up to 2 ft./sec.; ground displacements up to 3 ft.;
shear displacement (faulting) in the plant foundations of 3 f t. , and with the occurrence of an af tershock equal to El Centro before remedial action could be taken. What plant arrangements, design criteria and procedures could be developed which would assure shutdown and maintenance of the plant in safe shutdown conditioni Sincerely yours.
Harold L. Price Director of Regulation
- See footnote on page 1 REG.
HLPrice:vl 6/2/64
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- Williamson - 5/15/64 Revised - 6/1/64 QUESTIONS RESULTING FROM ACRS MEETING OF MAY 8 '
' Differential Displacement under Reactor
' Displacement isolation of a structure of this nature, to the writer's '
. knowledge, has no precedent. Consequently, all vital problem areas involved must be thoroughly explored and solutions provided as a pre-requisite to acceptance. .
.'Accordingly, it is importa.nt'that the applicant develop a complete pre- .
timinary design of a displacement isolation syste'm to accomodate diff- '
erential displacements of rnagnitudes acceptable to the AEC. This effort should include ' complete back-up calculations and drawings, and ,
I test data where needed. The scheme should be submitted for review, and should be reviewed by one or more authorities in this field,'such as Dr. Newmark.
The displacement isolation schemes whi.ch have been considered utilize an annular space between the surface of the excavation and the exterior j
i wall of the structure. This space may be open or filled. These schemes j j
.~ involve certain general problem areas involving ' questions and considerations e' F l
- such as the following: '
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. J With regard to the open annulus, can a ring wall be designed to prevent
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encroachment on the clearance due to cave-ins before or during an earth- N N.
quake?
The filled annulus leads to questions relating to the filler material. # [
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3 l l (1) The material must be sufficiently compressible and of the necessary thickness to accommodate the required displacement without locking. On the other hand it must not be so rigid as to overstress the walls of the containment. Data should be provided regarding stress strain charac-teristics under the anticipated strain rates, including effect of pore water.
(2) The material in place must have properties which are predb..able and consistent. (3) The materiati must be durable and must undergo negligible change in properties with time or environmental conditions. A specific question arising here is the effect of ground water, both with regard to the factor of durability and compressibility. The material preferably should not yield significantly under earthquake vibrations in absence of differential displacement and should not compact under the weight of the material above. If there is this possibility, the thickness, or strength, should be increased, appropriately. (4) Buoyancy of the material must be properly considered if ground water is present.
Further questions arise, with regard to the integrity of the structure. If the isolation system contemplates contact of the structure with the rock wall of the excavation at the shear plane, it should be demonstrated that the wall can resist the resulting pressures with a reserve margin suffi-cient to permit some further displacement without violating the containment.
If the isolation ' scheme contemplates sliding of the structure to accommodate a part of the total displacement, it should be shown that this can occur without violating the containment. If a filled annulus is used, this calculation I
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3 should account for the fact that the load along the line contact at the shear plane may be greatly increased due to compression of the fill on the far side. It is likely that pressures at the contact will puncture l
the wall locally before movement of the structure can occur. l In addition to demonstrating integrity of the structure walls, it should
- be shown that all internal load paths , including those provided by floors ,
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and radial walls are adequafe' to transmit the loads. Where appropriate, these components should be considered as rings and diaphragms trans-ferring loads by shear into the outside walls or other resisting elements. ~ -
If vertical displacements arte considered credibic, the annular space provided should be adequate to accommodate tilt of the structure in com-bination with horizontal displacement. The base of the structure and all other features should be shown to be adequate for the resulting stresses ,
when combined with stresses from the horizontal displacement. It is
, equally as important to be certain that tilt does not lead to internal mal-function of the reactor of a hazardous nature.
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If it is found necessary to enlarge the existing excavation, a reasonable approach that avoids uncertainties which otherwise could occur would be to provide sufficie~.c ent'argement to prevent contact between the structure and the displaced rock surface under the anticipated displacements... The, g
w gap separating structure and displaced rock surface should be sufficient l
to allow some additional di,splacement without causing structural damage.
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It should be noted that the cost of an annulus of concrete fill would be something less than $40,000 per foot of thickness, which is not a large price to pay for using this kind of an approach. The cost of additional excavation per foot of thickness is perhaps less certain, and might depend on the increase in diameter. However, it is doubtful that this cost would exceed the cost of the concrete fill.
1 ;
It is likely that, at the present time, the applicant has not sized the i i
structural components of the building in final form or determined the i reinforcing steel requirements. Hence, in theory, it is not possible at this time to evaluate the effect of stresses due to differential dis- f placem ent. In actual fact,' what is desired is not a precise stress '
analysis. What is needed is an estimate of feasibility to determine whether it is possible to resist all forces involved under the hypothetical i s
carthquake and associated displacement, plus all other concurrent loads, using member sizes, wall thicknesses, and steel percentages which are r
within the realm of reason. I
. Self Sufficiency of the Reactor Structure and its Internals
~
Particularly where large displacements are considered, the question arises ;
regarding the extent to which safety is dependent upon integrity of umbilical i features (vital components not supported by the reactor structure but con-nected to it.) These might include, for example, external water and power r
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5-N sources and associated piping. Verbal statements during the meeting '
of May 8 appeared to indicate that for a period of several hours or more the power and water sources within the reactor structure were sufficient without augmentation from outside sources. It seemed to be inferred
, that the station battery was ' sufficient to provide all power needs for at least a part of this period. This point needs clarification. ,- %
W It is a known fact that auxiliary diesel generator units are not highly reliable. This prompts the question as to whether a backup unit is provided.
It also seems appropriate to ask for data regarding the type and frequency of maintenance and checkout procedures for such equipment.
If integrity of steam and feed water lines under the maximum differential displacement is considered essential from a safety viewpoint, then the feasibility of their survival should be supported by rough calculations.
These would serve to prove or disprove verbal statements previously made to the effect that this was not a problem. '
Tsunami Effects At the meeting of May 8 the problem of damage from tsunamis was argu ed to be negligible largely on the grounds that the yard elevation of + 25 gave protection on the harbor side, and the high bluffs gave protection on the ocean side.
Nothing was said regarding any special provisions for pro-s tecting the intake and discharge features from the effects of tsunamis, c
Further elaboration on protection of these features may be warrante'd, depending on how critical they are considered to be from a safety viewpoint.
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