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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17347B5881990-03-0101 March 1990
[Table view]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 Category:NRC TO U.S. CONGRESS MONTHYEARML20248F0321989-09-14014 September 1989
[Table view]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 ML20246K8571989-08-25025 August 1989 Discusses NRC Actions in Reponse to Constituent Concerns Re Excessive Overtime Worked by Employees of Plants 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 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 ML20247C3541989-03-17017 March 1989 Forwards Detailed Info Re Status of Implementation of TMI Action Plan Items at Listed Plants.Small Number of Action Items Still Need Resolution ML20236D4761989-03-0909 March 1989 Forwards NRC 38th Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants for Oct-Dec 1988 ML20195G8521988-11-10010 November 1988 Forwards Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants for Jul-Sept 1988.Inability of Commission to Forecast Licensing Schedule for Shoreham & Seabrook Noted ML20245D6531988-09-14014 September 1988 Responds to Re Requested Response to Concerns of H Nickerson Long Work Hrs for Personnel at Various Central Illinois Nuclear Generating Plants.Related Info Encl ML20245D5811988-08-22022 August 1988 Forwards 36th Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants Covering Apr-June 1988.Licensing Schedule Cannot Be Realistically Forecast Due to Unresolved Emergency Preparedness Issues ML20207G2211988-08-15015 August 1988 Responds to Requesting Response to P Birnie Re Event at LaSalle Involving Recirculation Pump. NRC Response to P Birnie Identical to Ltr Addressed to Recipient ML20195G6681988-06-10010 June 1988 Provides Info in Response to Rl Spaulding Re Problems Associated W/Full Power Operation Authorization & Plant Shutdown.Plants Must Demonstrate Satisfactory Solutions to Issues Before Restart or Full Power Operation ML20151D3921988-04-0606 April 1988 Provides Listed Info Requested in Re Operating Nuclear Power Units Located at Twelve Sites Along Great Lakes ML20148E0961988-02-29029 February 1988 Forwards Quarterly Rept Covering Fourth Quarter of 1987,in Response to House Rept 97-850 ML20196G9691988-02-29029 February 1988 Forwards 34th Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants for Oct-Dec 1987. Commission Unable to Forecast Licensing Schedule for Shoreham & Seabrook Because of Unresolved Issues ML20195J6611988-01-20020 January 1988 Responds to Concerns Raised in Re Stainless Steel Matl Designated as E-Brite 26-1.Actions Taken to Address Allegation That E-Brite 26-1 Unsuitable for Use in Nuclear Power Plants Listed ML20236K8761987-11-0303 November 1987 Responds to Sztaba Expressing Concerns Re Safe Operation of State of CT Nuclear Power Plants.Plants in State Not Rated Among Most Troublesome in Nation.Licensee Performance Monitored in Publicly Available SALP Repts ML20236G1831987-10-27027 October 1987 Responds to Re Proposed Rule 10CFR50 & Congressional Ltrs Received on Morning of 871022 Meeting. Commission Stands Behind Declaring Process for Proposed Rule Open ML20235J1171987-09-28028 September 1987 Responds to Requesting Info Re Ucs 870210 Petition Requesting Mods to B&W Facilities,Per E Gallizzi to Recipient Requesting Support of Petition. Gallizzi Statements Discussed.Petition Under Review ML20235J5351987-09-28028 September 1987 Responds to Constituent Tf Gross Ltr Supporting Ucs 870210 10CFR2.206 Petition to Suspend OLs & CPs of Any Util Operating or Bldg Nuclear Power Reactors Designed by B&W,Per 870803 Request.Nrc Statements Re Plants Discussed ML20236L1811987-08-0404 August 1987 Responds to Addressed to Chairman Zech,Requesting That Commission Keep Recipient Fully Apprised of All Developments Re Both Petition Filed by Ucs & Ongoing Reassessment of B&W Reactors.Review of Petition Continuing ML20215K5981987-06-10010 June 1987 Responds to 870508 Request for Testimony at 870514 Hearing on External Influence on NRC Adjudicatory Procedures in Shoreham Proceeding.Index of Pertinent Documents Encl ML20215H9431987-06-0505 June 1987 Advises That Review of B&W Designed Nuclear Power Plants Will Not Satisfactorily Address Safety Issues Associated W/ B&W Design.Supports Efforts to Create Independent Safety Review Board ML20214J5261987-05-15015 May 1987 Responds to Recipient Expressing Support for NRC Shut Down of Peach Bottom Atomic Power Station & Concern Re Emergency Planning Issues at Seabrook.Commission Unable to Comment on Issues Before Commission or Adjudicatory Boards ML20214P8401987-05-15015 May 1987 Responds to Rj Mrazek Re Util Request to Operate Facility at 25% Power.Commission Will Not Make Decision on Merits of Request Until All Parties Have Opportunity to Have Views Considered ML20207A2061987-04-17017 April 1987 Responds to Request for Rept Re Legal & Institutional Aspects Under NRC Jurisdiction on Possible Conversion of Unit 1 to Defense Matls Production Reactor.Cp Still in Effect.Util Plans to Mothball Reactor by June 1988 ML20210N2161986-09-25025 September 1986 Discusses Governor Celeste Opposing Full Power Operations of Plants.Order Bars Commission from Voting Until Further Order by Us Court of Appeals.Served on 860930 NUREG-0396, Forwards Chronology of Meetings & Discussions W/Util & Other Groups,Internal Meetings & Lists of Public & Internal Documents,Per 860828 Request for Info Re Reducing Emergency Planning Zones for Seabrook & Calvert Cliffs1986-09-10010 September 1986 Forwards Chronology of Meetings & Discussions W/Util & Other Groups,Internal Meetings & Lists of Public & Internal Documents,Per 860828 Request for Info Re Reducing Emergency Planning Zones for Seabrook & Calvert Cliffs ML20209E6291986-08-26026 August 1986 Responds to 860731 Request to Be Kept Informed of Proceedings Re Facilities NUREG-1068, Responds to Constituent Inquiry Re Nuclear Reactor Containment Sys Designed by G.E.Probability of Severe Reactor Accidents Quite Low.Third Party Liability Insurance Provided Under Price-Anderson Legislation.W/O Stated Encls1986-08-26026 August 1986 Responds to Constituent Inquiry Re Nuclear Reactor Containment Sys Designed by G.E.Probability of Severe Reactor Accidents Quite Low.Third Party Liability Insurance Provided Under Price-Anderson Legislation.W/O Stated Encls ML20206Q1321986-08-20020 August 1986 Submits Interim Response to Re Alleged Falsification of Welding Certificates for Welders at Plants Employed by Powerplant Specialists,Inc ML20204F9361986-07-30030 July 1986 Responds to from R Blank,Addressing Concerns Re Safety of Older Nuclear Plants,Per SO Conte 860701 Request ML20215L2051986-06-16016 June 1986 Responds to to NRC Requesting That FEMA Conduct Public Meeting Re FEMA Assessment of 861213 Emergency Planning Exercise.Commission Addressed Similar Response in 860606 Memorandum & Order NUREG-1195, Forwards Response to Re NRC Reexam of B&W Reactor Design.Review Efforts Intensified After TMI Accident.Nrr Reorganized Last Yr to Increase Attention to Major Vendor Product Lines.Action Plan Under Development for Rancho Seco1986-04-23023 April 1986 Forwards Response to Re NRC Reexam of B&W Reactor Design.Review Efforts Intensified After TMI Accident.Nrr Reorganized Last Yr to Increase Attention to Major Vendor Product Lines.Action Plan Under Development for Rancho Seco NUREG-0560, Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress1986-04-23023 April 1986 Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress ML20137P5121986-01-24024 January 1986 Provides Info Concerning Financial Qualifications of Utils Re Safety of Plants.Nrc Regulation of Commercial Nuclear Power Based on Responsibility of Licensees for Safe Operation.Addl Views of Asselstine Encl ML20132G6251985-09-19019 September 1985 Forwards Responses to Gao Rept, NRC Should Rept on Progress in Implementing Lessons Learned from TMI Accident ML20140H5551985-08-13013 August 1985 Forwards Press Release 85-108 Re Proposed Fine Concerning Util Alleged Violation of NRC Requirements Which Prohibit Discrimination Against Employee for Identifying Safety Concerns to Mgt ML20140H5741985-08-12012 August 1985 Forwards Press Release 85-106 Re Proposed Fine for Util Alleged Violation of NRC Requirements Concerning Employee Discrimination in Cleanup Program ML20140H5911985-07-23023 July 1985 Forwards Press Release 85-99 Re NRC Proposed Civil Penalty in Amount of $150,000 Against Util for Violation of Requirements Concerning Reactor Vessel Water Level Instruments ML20132B8341985-07-18018 July 1985 Forwards Quarterly Status Rept for Second Quarter CY85. Licensing Delay for Limerick 1 Projected to Be 5 Months. Delay Cannot Be Quantified for Shoreham Due to Litigation. Full Power OL Issued for Palo Verde 1 on 850601 IR 05000409/20050311985-07-16016 July 1985 Forwards Notice of Violation Issued to Util Based on 850409-0531 Insp ML20140H6231985-07-15015 July 1985 Forwards Press Release 85-95 Re NRC Proposed Fine Against Util for Alleged Violations of Safety Requirements During Apr 1985 ML20141H1081985-07-0909 July 1985 Forwards Responses to 850610 Questions Re Diablo Canyon OL Proceeding.Responses Delayed Due to Press of Other Business ML20140H6461985-06-0404 June 1985 Forwards Press Release 85-80 Re NRC Proposed Civil Penalty in Amount of $500,000 Aginst Util for Alleged Matl False Statements Made to NRC Concerning Operator Qualifications & Training ML20140H6701985-06-0303 June 1985 Forwards Press Release 85-78 Re NRC Proposed Fine Against Util for Alleged Violations of Requirements Concerning Unplanned Occupational Radiation Exposures & Failure to Control Contractor Work Forces ML20140H7211985-05-24024 May 1985 Forwards Press Release 85-75 Re NRC Proposed Fine Against Util for Alleged Violations of Requirements Concerning Failure to Take Corrective Action When Warranted Concerning QA Program ML20140H7451985-05-17017 May 1985 Forwards Press Release 85-70 Re NRC Proposed Civil Penalty in Amount of $50,000 Against TVA for Alleged Violation of Security Requirements ML20140H8121985-05-0909 May 1985 Forwards Press Release 85-66 Re NRC Proposed Imposition of Civil Penalty in Amount of $112,500 Against TVA for Alleged Noncompliance W/Requirements Concerning 840419 Event When Tube Used to Insert Instrumentation Ejected ML20140H7791985-05-0909 May 1985 Forwards Press Release 85-68 Re NRC Proposed Fine Against Util for Alleged Noncompliance Concerning Improperly Conducted Preoperational Testing Program 1989-09-14 Category:OUTGOING CORRESPONDENCE MONTHYEARML20055C3921990-02-26026 February 1990
[Table view]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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4 CCT 2 e 99
) '
Mr. John T. Conway /
Executive Director Joint Commaittee on Atosnic Energy Congress of the United States Dear Mr. Conveys Attached for the infomation of the Joint comunittee are a report frees the Advisory Commaittee on Reactor Safaguards and an analysis by the comunission's Regulatory staff concerning the application of Pacific Gas and Electric Campany to construct a nuclear power plant at Rodega Head in California.
The Advisory Connaittee has concluded that there is reasonable assurance that the reactor can be constructed and operated at the proposed location without undue risk to the health and safety of the public.
For the reasons discussed in our analysis, the Requistory Staff has concluded that Bodega Head is not a suitable location for the proposed nuclear power plant at the present state of our knowledge.
We are enclosing copies of reports from the U.S. Geological Survey and the U.S. Coast and Geodetic Survey, dated October 1%4, concerning the geology and seianology of the Bodega Head site and a report by Dr. Nathan M. Neumark, a consultant to the Eagulatory Staf f. Also enclosed is a copy of the public announcement we plan to issue at
- 1
- 00 p.m., Tuesday, October 27.
We will keep you advised of any further developments in this matter.
> 0 g 0- Sincerely yours, 5D* 2 ( signed ) Harold L Price i
8<c e
r e*CD oco Harold L. Price
&W Director of Regulation m e.
Enclosures:
A. noted .bove e c: Cry 4 6~N 8709.74 0 2 4~1 oma ,. V
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