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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 PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA
MONTHYEARML20247R3361989-09-26026 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) 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) 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 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 ML20245B4531989-06-0808 June 1989 Forwards Encl Listed Info on Decommissioned & Shutdown Reactors Requested During Discussions at Saxton on 890511 ML20245B4051989-04-14014 April 1989 Responds to 881004 & 890119,23 & 0310 Ltrs Re Status of Investigation of Concerns About Corrosion Inhibitors & Design of Sampling Sys.Low Velocity of Liquid in Hotwell Sampling Considered Satisfactory ML20246N1521989-02-22022 February 1989 Responds to Re Amended Indemnity Agreement W/ Utils to Permit Storage of Spent Nuclear Fuel.Fr Notice Encl ML20206D9201988-11-0909 November 1988 Responds to Re NRC 880331 Response to Questions Raised Concerning Conditions at Plants & Recipient Proposal to Station Senior Operator in Control Room at All Nuclear Plants to Oversee Plant Operations ML20195G2121988-11-0808 November 1988 Final Response to FOIA Request for Documents.Forwards App D Document & Releasable Portions of Documents E/1 Through E/3. App D & Releasable Portions of Documents E/4 Through E/6 Available in Pdr.Portions Withheld (Ref FOIA Exemption 5) ML20195G5361988-11-0808 November 1988 Final Response to FOIA Request for Documents.Forwards App a Documents.App a Documents Also Available in PDR ML20206D8871988-11-0808 November 1988 Responds to 881015 Postcard Recommending Keeping Seabrook & Pilgrim Facilities Closed & Question Re Nuclear Waste Disposal.Two Levels of Waste for Commercial Nuclear Power Plants Considered ML20205S3841988-10-13013 October 1988 Partial Response to FOIA Request for Documents.App D,E & F Records Encl & Available in Pdr.App F Records Partially Withheld (Ref FOIA Exemption 6) ML20154D3891988-08-22022 August 1988 Partial Response to FOIA Request for Documents.Forwards App T Documents.Apps & T Documents Available in PDR ML20245D6581988-08-0404 August 1988 Discusses to Congressman Hastert Re Concern That Maint & Operations Employees of Listed Nuclear Power Plants in Vicinity of Seneca,Il Working Excessive Hrs ML20206E0051988-07-27027 July 1988 Responds to Enclosing Prior Correspondence W/Nrc Re Conditions at Ref Plants & 10CFR50.54(x) & (Y).Issues Raised Will Be Given Wide Dissemination in Fr & Careful Consideration by NRC ML20207D1121988-07-0505 July 1988 Partial Response to FOIA Request for Documents.Forwards App M Documents.App L Documents Maintained in Pdr.Apps N & O Documents Partially & Totally Withheld,Respectively (Ref FOIA Exemption 5) ML20195F8041988-06-15015 June 1988 First Partial Response to FOIA Request for Documents. Forwards Apps B & C Documents.Documents Available in Pdr.App a Documents Also Available in Pdr.Apps D Through G Documents Withheld (Ref FOIA Exemption 5).Releasable Portion Encl ML20155K0211988-06-13013 June 1988 Partial Response to FOIA Request for Documents.Forwards App D Documents.App C Documents Available in Pdr.App E Documents Completely Withheld (Ref FOIA Exemption 5) ML20151Y4681988-04-15015 April 1988 Partial Response to FOIA Request for Documents Re Event Involving Problems W/Msiv.App a & B Documents Available in Pdr.App B Documents Also Encl ML20151C6641988-04-0404 April 1988 Partial Response to FOIA Request for Documents Re Info Assessment Team Notification & Alleged Valve Tampering. App a Documents Available in Pdr.Forwards App B Documents. App B Documents Also Available in PDR ML20150D8641988-03-18018 March 1988 Informs of Relocation of NRR to Rockville,Md.Official Mailing Address Still Remains Same & Project Managers Have New Locations & Phone Numbers.Ts Michaels Still Lead Project Manager for Facility & a Adams Will Serve as Backup ML20150D9721988-03-18018 March 1988 Informs of NRC Relocation to Stated Address.Mailing Address Unchanged.A Adams Project Manager & TS Michaels back-up Project Manager ML20149H8811988-02-18018 February 1988 Partial Response to FOIA Request for Documents.Forwards App a Documents.Documents Also Available in PDR ML20149G0731988-02-10010 February 1988 Responds to Re Announced Reorganization of NRC at TMI-2.NRC Personnel Stationed at Site,Region I & NRC Headquaters Will Continue to Provide Effective Regulatory Oversight of Cleanup Activities ML20147E6621988-01-19019 January 1988 Partial Response to FOIA Request.App G Documents Already Available in Pdr.App H Documents,Re INPO Accreditation Training,Encl & Available in PDR ML20147C0281988-01-12012 January 1988 Final Response to FOIA Request for Documents Re Safeteam Program.Forwards App I & J Documents.App H & I Documents Available in Pdr.Other Records Available in Pdr.App J Documents Partially Withheld (Ref FOIA Exemption 6) ML20147D4821988-01-0606 January 1988 Partial Response to FOIA Request for Documents.Forwards App B Documents.Documents Also Available in Pdr.Portions of App B Documents Withheld (Ref FOIA Exemptions 6 & 7) ML20236V7511987-12-0202 December 1987 Partial Response to FOIA Request for All NRC Records & Info Re Petition for Issuance of Show Cause Order.Forwards App N Documents.App M & N Documents Available in Pdr.Portions of App N Documents Deleted (Ref FOIA Exemption 6) ML20236L6761987-11-0909 November 1987 Ninth Partial Response to FOIA Request for Records,Including Notes of Interview of K Mcmahon.Forwards App K Documents. App K & L Documents Partially & Completely Withheld (Ref FOIA Exemptions 6 & 7,respectively) ML20245C4051987-10-29029 October 1987 Final Response to FOIA Request for Records.App a & B Documents Available in Pdr.App a Documents Encl ML20236D4491987-10-23023 October 1987 Partial Response to FOIA Request for Documents,Including Rd Martin 850716 Memo Re Allegation Processing Programs.Encl App E & F Documents in Pdr.App F & G Documents Partially & Completely Withheld (Ref FOIA Exemptions 5 & 6) ML20235K3461987-09-30030 September 1987 Partial Response to FOIA Request.App C Documents Re Deficient Practices by Util Bolt Supplier Encl & Available in PDR ML20235R8521987-09-30030 September 1987 Responds to Re EIS for Meltdown of Large Reactors & NRC Compliance W/Nepa.As Result of TMI-2 Accident on 790329,NRC Included Class 9 Accidents in Assessments in Fes Re Licensing of Plants.Related Info Encl ML20235F8141987-09-24024 September 1987 Partial Response to FOIA Request for Documents.Forwards App B,C & D Documents.App a & B Available in Pdr.App C Documents Partially Withheld (Ref FOIA Exemption 4).App D Documents Withheld in Entirety (Ref FOIA Exemptions 5 & 6) ML20235A4371987-09-17017 September 1987 Final Response to Appeal Re Denial of FOIA Request for Documents Re Concerns of Individual About Util & S&W Technical Svcs.Records Two Through Five on Encl App Forwarded.Record One Withheld (Ref FOIA Exemption 7) ML20238F7581987-09-14014 September 1987 Partial Response to FOIA Request Re Lers.App C Documents Available in Pdr.App D Documents Encl & Available in Pdr.App E Documents Partially Withheld (Ref FOIA Exemption 4).Listed LERs Not Issued Bu Licensees IA-87-512, Partial Response to FOIA Request Re Lers.App C Documents Available in Pdr.App D Documents Encl & Available in Pdr.App E Documents Partially Withheld (Ref FOIA Exemption 4).Listed LERs Not Issued Bu Licensees1987-09-14014 September 1987 Partial Response to FOIA Request Re Lers.App C Documents Available in Pdr.App D Documents Encl & Available in Pdr.App E Documents Partially Withheld (Ref FOIA Exemption 4).Listed LERs Not Issued Bu Licensees ML20238E3931987-09-10010 September 1987 Final Response to FOIA Request.App D Documents Re SALP Rept Preparation Encl & Available in Pdr.App E Documents Completely Withheld (Ref FOIA Exemption 5).App F Documents Partially Withheld (Ref FOIA Exemption 4) ML20238E0081987-09-0101 September 1987 Responds to 870715 Questions Re Plant Concerning GE Pumps ML20237F5921987-08-19019 August 1987 Partial Response to FOIA Request.Lers Indicated in Request for Dockets 50-220,322 & 410 Not Issued by Licensee.Forwards Documents Listed in Apps a & B.App a Documents Available in Pdr.App B Documents Being Made Available in PDR ML20236K2621987-08-0404 August 1987 Partial Response to FOIA Request for Records Re AO Reporting.Forwards App D & E Documents.Documents Also Available in PDR ML20236H0831987-07-30030 July 1987 Responds to Re Possibility of LOCA at Plants. Majority of LOCA Research Complete & Understanding of ECCS Performance During LOCA Greatly Improved.Conservatism of Methods Specified in Commission Rules Demonstrated ML20235Y6091987-07-21021 July 1987 Forwards Photocopy of Fr Notice That Incorporates DOJ 740304 Advice Ltr in Entirety,Per Request for DOJ Advice Ltrs Rendered in Conjunction W/Cp Antitrust Review of Plants ML20215H4231987-06-19019 June 1987 Final Response to FOIA Request for Documents Re Plant Feedwater Line Failure.Forwards App H Documents.App G & H Documents Available in Pdr.Document Listed in App I Completely Withheld (Ref FOIA Exemption 5) ML20238E0341987-05-28028 May 1987 Responds to Questions Raised in Re Plant ML20214E2841987-05-18018 May 1987 Final Response to FOIA Request.No PRAs on File for McGuire 1,Bellefonte 1 & Gassar.Pras for Susquehanna 1 & Oyster Creek Available in PDR IA-87-221, Final Response to FOIA Request.No PRAs on File for McGuire 1,Bellefonte 1 & Gassar.Pras for Susquehanna 1 & Oyster Creek Available in PDR1987-05-18018 May 1987 Final Response to FOIA Request.No PRAs on File for McGuire 1,Bellefonte 1 & Gassar.Pras for Susquehanna 1 & Oyster Creek Available in PDR ML20213G1241987-05-12012 May 1987 Final Response to FOIA Request.App a Documents Already Available in Pdr.App B Documents Encl & Available in PDR ML20215H8901987-05-0505 May 1987 Sixth Partial Response to FOIA Request for Documents Re Allegations.Forwards App C & D Documents.App B Documents Also Available in PDR ML20215K5311987-05-0505 May 1987 Informs That Because Plants Adjudicatory Hearings Currently Before Nrc,Comments on Merits of Plant Issues Would Be Inappropriate,Per Encl Recipient .Served on 870506 1989-09-26
[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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Dear vrs. f.,
sunsjs Your latter of . ecentist f6,1960, with enclosure, to Mr. P.ichard Smith of ottr San Francisco Operations Office, protestinr tl.e construction or a cuclear power plant at bodsrs J1ead, Califorada, has been referred to my attention.
sithough t!w Commincion is evere that the Pacific Cas and 714ctric Compatay is studying the possibility of instmUing t a nuclear power plant at this location, no application ham I been received from the company for the necessary licenas to construct and operate euch a facility.
As incicatec in my letter dated Farch 17, 1960, tie Atomic inergy Consr.iesion does not become involved in such matters as property rights, land acquisition araa soning cocsider-ations in its regulstery control over nucimar reactors.
These ratters are rerraally dealt with by the prospective anticant with local and state officials prior to his sub-rittal of an ap;: Lies.tio:. to the Commission.
I In corsiccrict any ap;,ticatiot, for a cecetruction permit or an oreratir.c license for a nt. clear power facility, a detailed i safety review is made by W Cn-insion's technical staff ard by tbc 'dvisory Ct.maittee or, Reactor Saferuania. If yacific r,ac ant: ilectric Cotapar;y submits an application for a facility
' at nodega head, the review will incluce examinstian of the enviroenental characteristics of the site auch as the geological, hydrologienl, meteorolerical, and seismological featuress the nature end uee of the surrounding area; and the design features incorpers.tec in the facility for public protect $on. Further, before action is taken on tlw issuance of a~ construction perait .
a formal puclic hearint in the. matter will be bald.
Distributions
, A, Morris (2)
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Harold L. Price, nin.
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(Na m. a nd Enclosed for action, if any, are the followi ng:
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AtjeAAKS cov memo. Smith to Low,1/12/61
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3 Ltr w/ enc 1. Mrs. Rose Gaffney to 6! Sm TO (Na . and untt) coy ltr. Smith to Mrs. Rose Gaffney,1/12/6 4
L 4}',}^ % m' HT6ALS REMARKS
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CO Lawrence D. Low, Dir_
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C-1.s60 j[j prv
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