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| document type = CORRESPONDENCE-LETTERS, NRC TO EDUCATIONAL INSTITUTION, OUTGOING CORRESPONDENCE | | document type = CORRESPONDENCE-LETTERS, NRC TO EDUCATIONAL INSTITUTION, OUTGOING CORRESPONDENCE | ||
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Latest revision as of 17:03, 6 October 2021
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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 EDUCATIONAL INSTITUTION MONTHYEARIR 05000097/19890011989-05-12012 May 1989
[Table view]Forwards Safety Insp Repts 50-097/89-01 & 50-157/89-01 on 890425-26.Weakness Identified in Area of Documentation IR 05000072/19880011988-10-28028 October 1988 Ack Receipt of 880804 & 25 Ltrs Informing NRC of Steps Taken to Correct Violations & Deviations Noted in Insp Repts 50-072/88-01 & 50-407/88-01 & Order.Concludes That W/ Exception of Violation 5.c,violations Did Not Occur ML20147D0421988-02-29029 February 1988 Requests That Recipient Resubmit Proposal to Convert to Low Enriched U Fuel to Meet 10CFR50.64(6)(2) or (3) Requirements by 880327.Identical Ltrs Sent to Listed Dockets ML20206C6061987-04-0808 April 1987 Ack Receipt of & Payment of $3,000 for Civil Penalty Imposed on 870313.Corrective Actions Described in Will Be Examined During Future Insps ML20212P1851987-03-11011 March 1987 Responds to 870309 10CFR2.206 Petition for Commission Review of Director'S Decision DD-87-2.Time Period for Commission Review Expired & Decision Became Final Agency Action on 870310.Served on 870312 ML20136G3791985-11-18018 November 1985 Discusses Actions Re Claims of Alleged Inadequacies in Containment Leak Rate Tests Performed at LWR Plants.Matter Will Not Be Considered Further ML20126E4311985-03-25025 March 1985 Responds to FOIA Request for Records Re FIN B-0489, Containment Leak Rate Testing Program & Quadrex Corp/Nrc Contracts.Forwards Documents Re FIN B-0489.Documents Also Available in Pdr.No Documents Re Quadrex Subj to Request ML20128P3091984-12-0404 December 1984 Responds to 841126 & 27 Telcon Requests for Listed Info. Diagram of Mark II Containment Encl.S&W Will Forward Correct Diagram of Surry Containment.Experimental Data for Decay Heat Curve Does Not Exist.W/O Encl ML20128P2691984-11-20020 November 1984 Forwards Diagrams Illustrating Core Concrete Interaction, Based on Corcon Calculations for Facility.Concrete Consists of Limestone ML20128P2331984-11-14014 November 1984 Forwards Microfiche of EPRI Mar 1980 Revised Rept NSAC-1, Analysis of TMI-2 Accident. Version Out of Print.W/O Encl NUREG-0850, Forwards Vol 1 to NUREG-0850, Preliminary Assessment of Core Melt Accidents at Zion & Indian Point Nuclear Power Plants & Strategies for Mitigating Effects. Vol 1 Only Vol Available at Present1984-08-14014 August 1984 Forwards Vol 1 to NUREG-0850, Preliminary Assessment of Core Melt Accidents at Zion & Indian Point Nuclear Power Plants & Strategies for Mitigating Effects. Vol 1 Only Vol Available at Present ML20128N9361984-08-14014 August 1984 Forwards Vol 1 to NUREG-0850, Preliminary Assessment of Core Melt Accidents at Zion & Indian Point Nuclear Power Plants & Strategies for Mitigating Effects. Vol 1 Only Vol Available at Present NUREG/CR-3028, Forwards NUREG/CR-3028, Review of Limerick Generating Station PRA & Vols 1 & 2 to NUREG/CR-0027, Proceedings of Intl Meeting on Thermal Nuclear Reactor Safety. Advises That NUREG/CR-3300 Not Published.W/O Encls1984-05-31031 May 1984 Forwards NUREG/CR-3028, Review of Limerick Generating Station PRA & Vols 1 & 2 to NUREG/CR-0027, Proceedings of Intl Meeting on Thermal Nuclear Reactor Safety. Advises That NUREG/CR-3300 Not Published.W/O Encls ML20128N3851984-05-31031 May 1984 Forwards NUREG/CR-3028, Review of Limerick Generating Station PRA & Vols 1 & 2 to NUREG/CR-0027, Proceedings of Intl Meeting on Thermal Nuclear Reactor Safety. Advises That NUREG/CR-3300 Not Published.W/O Encls ML20210E6761984-03-23023 March 1984 Forwards Region V Evaluation of Emergency Preparedness Concerns Expressed in 831104,1209 & s Included in Latest Plant Sser NUREG/CR-1250, Forwards Vols 1 & 2 to NUREG/CR-1250, TMI - Rogovin Rept1984-03-18018 March 1984 Forwards Vols 1 & 2 to NUREG/CR-1250, TMI - Rogovin Rept ML20128N2001984-03-18018 March 1984 Forwards Vols 1 & 2 to NUREG/CR-1250, TMI - Rogovin Rept ML20210E6891983-12-30030 December 1983 Ack Providing Addl Data Re Concern About Method of Notifying Population in Case of Flood.Siren Concern Being Addressed.Fema Ltr Addressing Items Identified in Initial Encl ML20128M7001983-11-0101 November 1983 Forwards Draft Vols I-III to BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20128M7311983-09-12012 September 1983 Forwards Draft Vols I-III of BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20128M7601983-09-12012 September 1983 Forwards Draft Vols I-III of BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20128M7741983-09-12012 September 1983 Forwards Draft Vols I-III of BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20128M7951983-09-0909 September 1983 Forwards Draft Vols I-III of BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20128M7981983-08-12012 August 1983 Forwards Draft Vols I-III of BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20128M8191983-08-12012 August 1983 Forwards Draft Vols I-III of BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20054L3881982-06-16016 June 1982 Ltr to All Research & Test Reactor Licensees Requesting That Reg Guide 2.6 (for Comment) & ANSI/ANS-15.16 (Draft II Dtd 811129) Be Used to Meet Requirement of Final Amend to 10CFR50.54(r) Re Emergency Planning.Fr Notice Encl ML20137G4721971-06-23023 June 1971 Advises That Presence & Irradiation of Explosives in Reactor Must Be Evaluated Due to Potential for Damage to Reactor. Evaluation Requested Establishing Operating Restrictions,Max Quantity of Explosives Allowed in Facility & Form ML20235C9201968-08-28028 August 1968 Requests Nm Newmark Consulting Engineering Svcs Provide Listed Svcs,Including Analyses of Engineering Factors Included in Proposed Design to Minimize Damage from Seismically Induced Ground Motion for Proposed Plant Const ML20151W9761967-02-14014 February 1967 Requests Listed Svc for Commission Per Conditions of Contract AT(49-5)2667 Re Proposed Const of PWR by PG&E at Diablo Canyon Site,Including Rept on Analyses of Engineering Factors by 670415 ML20234D9591964-11-0909 November 1964 Forwards Repts Released Re Proposed Nuclear Power Plant at Bodega Head,Ca in Accordance W/Telcon.Util Has Withdrawn Application for CP on Project.W/O Encls ML20235A3801964-09-23023 September 1964 Forwards 640916 Amend 9 to License Application for Proposed Nuclear Reactor at Bodega Bay,Ca.W/O Encl ML20239A4371964-08-0606 August 1964 Confirms Telcons W/Eg Case Re Preparations for ACRS 640824 Meeting Re Bodega Bay Reactor.Aec Has Understanding That Rept Re Seismic Aspects of PG&E Application Will Be Furnished at 640810 Meeting in Chicago,Il.Guide Encl ML20234C0651964-07-24024 July 1964 Forwards 640720 Amend 8 to PG&E Application to Construct Reactor at Bodega Head & Informs of ACRS Meeting on 640824 to Discuss Amend.W/O Amend ML20234B2981964-06-0808 June 1964 Forwards Background Info on High Energy Physics Program & Proposed Stanford Linear Electron Accelerator Project, 1961 Rept to Joint Committee on Atomic Energy,Per Re Const of Reactor at Bodega Head.W/O Encl ML20234B1921964-05-20020 May 1964 Forwards AEC to PG&E Re Bodega Head Case.Several Members of ACRS Will Be Present at Meeting at Anl on Fri, Which May Include Kv Steinbrugge ML20234B2071964-05-18018 May 1964 Confirms 640522 Meeting at Anl to Discuss Bodega Head Case, Per Telcons Last Wk.Ltr Being Prepared to Send to PG&E Re Questions Worked Out W/Acrs Members ML20234E8131964-04-0303 April 1964 Forwards Amend 7 to Util Application for License for Bodega Bay Atomic Park.W/O Encl ML20234D9511964-04-0303 April 1964 Forwards Amend 7 to Util Application for License to Unit 1 for Bodega Bay Atomic Park.W/O Encl ML20235C4831964-03-24024 March 1964 Forwards PG&E Amend 6 to Application Re Earthquake Deign Criteria for Proposed Bodega Head Reactor,Superseding Amend 4.Rept on Adequacy of Amend Criteria Will Be Discussed at ACRS May 1964 Meeting.W/O Encl ML20235C5221964-03-24024 March 1964 Forwards PG&E Amend 6 to Application Re Earthquake Design Criteria for Proposed Bodega Bay Reactor,Superseding Amend 4.Rept on Adequacy of Amend Criteria Will Be Discussed at ACRS May 1964 Meeting.W/O Encl ML20235B2061964-01-27027 January 1964 Forwards USGS Dec 1963 Rept Entitled Engineering Geology of Proposed Nuclear Power Plant Site on Bodega Head,Sonoma County,Ca for Review.Will Contact to Schedule Meeting.W/O Encl ML20235B2521964-01-24024 January 1964 Forwards Amend 5 Filed by PG&E Consisting of Bodega Head Site Repts for Review.Will Contact to Discuss Rept.W/O Encl ML20235B2701964-01-24024 January 1964 Forwards Amend 5 Filed by PG&E Consisting of Bodega Head Site Repts for Review.Will Contact.W/O Encl ML20235B1361964-01-21021 January 1964 Forwards USGS Dec 1963 Rept Entitled Engineering Geology of Proposed Power Plant Site on Bodega Head,Sonoma County,Ca. Will Contact to Schedule Meeting.W/O Encl ML20234A9761963-09-0404 September 1963 Advises That Anyone Inquiring About Proposed Plant Should Be Informed That Recipient Serving as Consultant to AEC to Assist in Evaluation of Structural Design,Per ML20234C0731963-08-15015 August 1963 Forwards Amend 4 to Facility License Application from PG&E for Proposed Nuclear Power Reactor at Bodega Bay,Ca.W/O Encl ML20234B7301963-08-15015 August 1963 Forwards Amend 4 to Facility License Application from PG&E for Proposed Nuclear Power Reactor at Bodega Bay,Ca.W/O Encl ML20234C9301963-07-26026 July 1963 Informs That Effect of Operation of Proposed Reactor on Marine Environ of Bodega Head Being Given Careful Consideration,Per ML20234C9731963-07-11011 July 1963 Forwards Us Bureau of Commercial Fisheries Review of Effects of Reactor Operations on Marine Environ at Bodega Bay,Per Re ACRS Rept on PG&E Plant.Util Will Continue Oceanographic Studies for at Least One Annual Cycle ML20234F4521963-07-10010 July 1963 Responds to to Chairman Seaborg Re Proposed Const of Nuclear Power Reactor at Bodega Head.Pamphlet Describing Procedures Re Licensing of Power Reactors by AEC Encl.W/O Encl 1989-05-12 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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9 March 2k, 1964 l
l Dr. Frank Neuman University of Washington Seattle, Washington Dear Dr. Heunan Enclosed is a copy of Amendment No. 6 to the Pacific Gas l
and Electric Company application. This amendment sets l
forth further details with regard to the earthquake design I criteria for the Company's proposed Bodega Bay reactor and supersedes Amendment No. k to the application and the material superseded by that amendment.
We pnssent3y plan to provide a report on the adequacy of the criteria discussed in this amendment to the Advisory Committee on P.eactor Safeguards for consideration at its I Huy 196h meeting. For this reason we would appreciate your review and comments at your earliest convenience.
Our tentative plans are to arrange a meeting with all of ,
our consultants on this pro. ject sowstine during the watek l l
of April 6 to discuss this matter. We vill be in touch vith you further concerning this teeting when our plans )
are more firm.
Sincerely yours, Onginal S.l;ad Ly L G. C:se Edson G. Case Assistant Director for Facilities Licensing Division of Licensing and Regulation Enclosure :
Amendment No. 6 I .....
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