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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:INCOMING CORRESPONDENCE
MONTHYEARML17347B5881990-03-0101 March 1990
Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits
ML18094B3221990-02-28028 February 1990
Forwards Executed Amend 14 to Indemnity Agreement B-74
ML15217A1031990-02-28028 February 1990
Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals
ML20011F3821990-02-26026 February 1990
Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices
ML20006G0621990-02-22022 February 1990
Forwards Revised Proprietary Pages to DPC-NE-2004, Core Thermal Hydraulic Methodology Using VIPRE-01, Reflecting Minor Methodology Changes Made During Review & Approval Process.Pages Withheld
ML20006E5881990-02-20020 February 1990
Forwards Proprietary Response to NRC 890725 Questions Re Vipre Core Thermal Hydraulic Section of Topical Rept DPC-NE-3000 & Rev 2 to Pages 3-69,3-70,3-78 & 3-79 of Rept. Encls Withheld (Ref 10CFR2.790)
ML20006E1441990-02-16016 February 1990
Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals
ML20006E9071990-02-16016 February 1990
Discusses Plants Design Control Program.Util Adopted Concept of Design Change Implementation Package (Dcip).Dcip Will Contain or Ref Design Change Notice Prepared Per Approved Procedures
ML20006E4201990-02-14014 February 1990
Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690
ML20011E6151990-02-12012 February 1990
Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21)
ML20011E5571990-02-0808 February 1990
Forwards Us Bankruptcy Court for Eastern District of Tennessee Orders & Memorandum on Debtors Motion to Alter or Amend Order & Opinion Re Status of Sales Agreement Between DOE & Alchemie.Doe Believes Agreement Expired on 890821
ML20011E4991990-02-0606 February 1990
Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested
ML20011E5981990-02-0505 February 1990
Requests That Listed Individuals Be Deleted from Svc List for Facilities.Documents Already Sent to Dept of Environ Protection of State of Nj
ML20006D6911990-02-0202 February 1990
Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle
ML20006C5661990-01-31031 January 1990
Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants
ML20006B7961990-01-29029 January 1990
Forwards Summaries of Latest ECCS Evaluation Model Changes
ML20006C6711990-01-29029 January 1990
Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Plants Have Established Preventive Maint Program for Intake Structure & Routine Treatment of Svc Water Sys W/Biocide to Control Biofouling
ML20006D6611990-01-29029 January 1990
Advises That 900117 License Amend Request to Remove Certain cycle-specific Parameter Limits from Tech Specs Inadvertently Utilized Outdated Tech Specs Pages.Requests That Tech Specs Changes Made Via Amends 101/83 Be Deleted
ML20011E2521990-01-29029 January 1990
Forwards Proprietary Safety Analysis Physics Parameters & Multidimensional Reactor Transients Methodology. Three Repts Describing EPRI Computer Code Also Encl.Proprietary Rept Withheld (Ref 10CFR2.790)
ML18153C0951990-01-29029 January 1990
Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Belief in Appropriateness to Address Generic Ltr 89-13 Concerns within Context of Established Programmatic Improvements Noted
ML18094B2861990-01-26026 January 1990
Forwards Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Aggressive Program of Monitoring,Insp & Matl Replacement Initiated in Advance of Generic Ltr 89-13 Issuance
ML18153C0871990-01-26026 January 1990
Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures to Be Revised & Familiarization Sessions Will Be Conducted Prior to Each Refueling Outage
ML20006D2431990-01-26026 January 1990
Provides Info Re Emergency Response Organization Exercises for Plants.Exercises & Callouts Would Necessitate Activation of Combined Emergency Operations Facility Approx Eight Times Per Yr,W/Some Being Performed off-hours & Unannounced
ML19354E4191990-01-25025 January 1990
Comments Re Issuance of OL Amends & Proposed NSHC Determination Re Transfer of Operational Mgt Control of Plants & Views on anti-trust Issues Re Application for Amend for Plants
ML19354E6711990-01-24024 January 1990
Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226
ML17347B5451990-01-24024 January 1990
Informs of Plans to Apply ASME Code Case N-356 at Plants to Allow Certification Period to Be Extended to 5 Yrs.Rev to Inservice Insp Programs Will Include Use of Code Case
ML19354E4451990-01-22022 January 1990
Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters
ML19354E4461990-01-22022 January 1990
Forwards Proprietary Rev 1 to DPC-NE-2001, Fuel Mechanical Reload Analysis Methodology for MARK-BW Fuel, Adding Section Re ECCS Analysis Interface Criteria & Making Associated Administrative Changes.Rev Withheld
ML20005G7161990-01-20020 January 1990
Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl
ML20006A8001990-01-19019 January 1990
Forwards Response to NRC 891220 Ltr Re Violations Noted in Plant Insps.Response Withheld (Ref 10CFR73.21)
ML16152A9091990-01-18018 January 1990
Forwards Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. W/900131 Release Memo
ML18153C0771990-01-17017 January 1990
Forwards North Anna Power Station Emergency Plan Table 5.1, 'Min Staffing Requirements for Emergencies' & Surry... Table 5.1, 'Min Staffing Requirements...', for Approval,Per 10CFR50.54(q),NUREG-0654 & NUREG-0737,Suppl 1
ML20006A2011990-01-16016 January 1990
Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel in Anchor Darling Swing Check Valves.Eight Subj Valves Identified in Peach Bottom Units 1 & 2 & Will Be Returned to Mfg
ML20006A6241990-01-16016 January 1990
Forwards Draft Qualified Master Trust Agreement for Decommissioning of Nuclear Plants,For Review.Licensee Will Make Contributions to Qualified & Nonqualified Trust as Appropriate
ML18153C0731990-01-15015 January 1990
Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or or Valves.... Util Replaced Studs in twenty-five Valves
ML20005G6431990-01-10010 January 1990
Responds to Generic Ltr 89-21 Re Implementation of USI Requirements,Consisting of Revised Page to 891128 Response, Moving SER Ref from USI A-10 to A-12 for Braidwood
ML20006A8201990-01-10010 January 1990
Forwards Errata to Rev 3 to BAW-1543,Tables 3-20 & E-1 of Master Integrated Reactor Vessel Surveillance Program Reflecting Changes in Insertion Schedule for A5 Capsule for Davis-Besse & Crystal River
ML20006B8821990-01-10010 January 1990
Reissued Ltr Correcting Date of Util Ltr to NRC Which Forwarded Updated FSAR for Byron/Braidwood Plants from 881214 to 891214.W/o Updated FSARs
ML20005G7601990-01-0404 January 1990
Forwards Public Version of Rev 33 to Crisis Mgt Plan. Privacy Info Should Be Deleted Prior to Placement in Pdr.W/ D Grimsley 900118 Release Memo
ML18094B2331990-01-0303 January 1990
Certifies Util Implementation of fitness-for-duty Program, Per 10CFR26.Training Element Required by Rule Completed on 891215.Chemical Testing for Required Substances Performed at Min Prescribed cut-off Levels,Except for Marijuana
ML18153C0491990-01-0303 January 1990
Advises of Implementation of fitness-for-duty Program Which Complies w/10CFR26.Util Support Objective of Providing Assurances That Nuclear Power Plant Personnel Will Perform Tasks in Reliable & Trustworthy Manner
ML20005F4641990-01-0303 January 1990
Advises That Licensee Implemented 10CFR26 Rule Re fitness-for-duty Program W/One Exception.Util Has Not Completed Background Check for Some of Program Administrators.Checks Expected to Be Completed by 900105
ML20042D3731990-01-0202 January 1990
Forwards Revised Crisis Mgt Implementing Procedures, Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9, Rev 1 to CMIP-14 & Rev 30 to CMIP-21
ML17347B5051990-01-0202 January 1990
Certifies That Util Has fitness-for-duty Program Which Meets Requirements of 10CFR26.Util Adopted cut-off Levels Indicated in Encl
ML17347B4961989-12-28028 December 1989
Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Considering Expansion of Plants to Include Addl safety-related & Position Changeable Valves W/ Emphasis on Maint & Testing
ML20042D3381989-12-28028 December 1989
Forwards Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. Util Will Comply W/Ltr Recommendations W/Noted Exceptions.Response to Be Completed When Ltr Uncertainties Cleared
ML18094B2201989-12-27027 December 1989
Advises of Intent to Provide follow-up Response to Generic Ltr 89-10 by 900831 to Describe Status of Program, Recommendation Exceptions & Any Schedule Adjustments
ML18094B2291989-12-27027 December 1989
Requests to Apply ASME Section XI Code Case N-460 to Facilities Re Reduction in Exam Coverage on Class 1 & 2 Welds.Fee Paid
ML20005E1911989-12-26026 December 1989
Forwards Revised Page 2 Correcting Plant Implementation Date for USI A-24 Requirements in Response to Generic Ltr 89-21
ML18153C0261989-12-26026 December 1989
Responds to Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & surveillance.Motor-operated Valve Program Structured to Allow Similar Approach to motor-operated Dampers.Results Will Be Submitted in 30 Days
1990-03-01
[Table view]
Category:STATE/LOCAL GOVERNMENT TO NRC
MONTHYEARML20011E5981990-02-0505 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
ML18094A6231989-08-11011 August 1989
Requests Addition of Ofc of Peoples Counsel to NRC Svc Lists for Insps,Events & Mgt of Facilities.Ofc of Peoples Counsel Represents Residential Customers of Utils Regulated by State of MD PSC
ML20206C5901988-11-0909 November 1988
Forwards Withdrawal of Request of State of Tn to Participate as Interested Party,Per 10CFR2.715(c).Requests That Mh Mobley Remain on Svc List for Purpose of Receiving All Pertinent Correspondence,Filings & Notices
ML20207M0691988-09-29029 September 1988
Comments on Environ Assessments & Finding of No Significant Impact Documents Re Alchemie Facilities.Blind Approach of Addressing Stable Isotope Enrichment Appalling
ML20154A0931988-08-30030 August 1988
Forwards Comments on from Alchemie,Inc Re Radiological Hazards.Clarification Desired
ML20151G6531988-07-18018 July 1988
Advises That State of Tn Will Forgo Appearance at 880721 Prehearing Conference in Knoxville,Tn Based on Concerns Already or in Process of Being Addressed
ML20195G6951987-09-0202 September 1987
Opposes Plant Restart Pending Revs to Radiological Emergency Response Plan.Current Plan,Dtd May 1985,inadequate W/Respect to Response Time,Evacuation Procedures & Reception Ctrs
ML17347A5661987-06-0505 June 1987
Advises That Verbal Notification of Release of Amends to NRC Licenses in State of Fl Not Necessary.Written Notification of Proposed Amends Soliciting Comments & Written Rept of Release Adequate
ML20235G2131987-05-28028 May 1987
Requests Info Re NRC Insp of Detroit Edison Safeteam Files, Including Insp Results,Corections to Problems,Adequacy of Util Investigations & Manner NRC Selected Files to Examine
ML20204F2681987-03-19019 March 1987
Requests Removal from Distribution List for Listed Dockets
ML20213G5481987-03-12012 March 1987
Requests Timely Review of Encl Draft Legislation Creating Onsite Monitoring Presence for State of Me at Facility & MOU Between NRC & State of or
ML20211G5061987-02-13013 February 1987
Advises of Change of Address for State of Oh Dept of Health. Functions of Power Siting Commission Transferred to Board Operating Under Auspices of Puc of State of Oh
ML20211G5301987-01-14014 January 1987
Forwards Rept of Emergency Evacuation Review Team on Emergency Response Plans for Perry & Davis-Besse Nuclear Power Plants. Rept Concluded That Current Emergency Response Plan Inadequate.Served on 870128
ML20237C8811986-12-22022 December 1986
Forwards Rept to Governor on Emergency Preparedness for Accident at Pilgrim Nuclear Power Plant, Presented on 861216.Governor Accepted Finding That Current Offsite Radiological Emergency Response Plans for Plant Inadequate
ML20211A9381986-10-0909 October 1986
Requests to Be Placed on Mailing Lists for Publications Re Perry,Davis-Besse & Beaver Valley Nuclear Plants.Puc of Oh Directed to Conduct Investigations. Comprehensive Assessment of Perry First Study to Be Conducted
ML20205F3051986-08-15015 August 1986
Withdraws State of Oh Support for Evacuation Plans & Expects NRC to Withhold Full Power Ols,Pending State Review of 860131 Earthquake Near Perry & 850609 Event at Davis-Besse. Full Exercise of State Rights Anticipated.Served on 860818
ML20204F1911986-07-29029 July 1986
Requests Notification Prior to Issuance of Amends to OLs Per 10CFR50.91(b).NRC Adherence to State Notification Practice Generally Acceptable,W/Some Exceptions
ML20204F2571986-07-29029 July 1986
Requests Notification Before Issuance of License Amends for State of Il Nuclear Power Plants,Per 10CFR50.91(b)
ML20199L5831986-05-0707 May 1986
Raises Concerns Re NRC Poor Record of Enforcing High Safety Stds in State of Oh.Reconsideration of Earthquakes as Safety Issue Requested
ML20206U8211986-02-25025 February 1986
Responds to Acceptance Appraisal on 851017-18.One Technician Added to Div of Labs & Split Sampling Program for Cooper Nuclear Station Initiated in Jan 1986
ML20154L4851986-02-25025 February 1986
Ack Receipt of Re Acceptance Appraisal Rept 99990004/85-10 on 851017-18 for Proposed Nrc/State of Ne Environ Monitoring Agreement Around Fort Calhoun & Cooper Plants.Response to Rept Concerns Listed
ML20137A3631986-01-0707 January 1986
Advises of No Adverse Findings as Result of Review of Proposed Tech Spec Amend to License NPF-37 Re Closure of Valves SI 8809A & B During Check Valve Surveillance Testing
ML20136F6741986-01-0303 January 1986
Requests That NRC Continue to Send Copies of Correspondence W/Util to State & Delete as Cauger & EA Eisen from Svc List.Ltr to Wl Clements & NRC 841211 Memo Encl
ML20136A5621985-12-11011 December 1985
Lists New Address for Cd Jones,Director,State of Il Emergency Svcs & Disaster Agency
ML20213F3831985-07-15015 July 1985
Requests Suspension of Low Power Testing at Facility Until Investigation of Accident Causing Hot Shutdown of Plant & Review of Training of Personnel & Condition of Equipment Complete
ML20213F3871985-07-11011 July 1985
Requests Immediate Halt of Low Power Testing at Facility Until Investigation of 850710 Accident in Which Valve Sys in Primary Containment Bldg Improperly Left Open Releasing Gas Into Atmosphere Complete
ML20137E9721985-07-11011 July 1985
Discusses Interim Environ Surveillance Program Under Cooperative Agreement NRC-31-83-671.Proposed State Program Will Be Implemented by End of 1985
ML20127N5501985-06-27027 June 1985
Discusses Proposed Exemption from 10CFR50.71 to Submit Updated FSAR for Both Plants 12 Months After Issuance of Braidwood Unit 2 Ol.Updated FSAR for Byron Should Be Issued by 880214,per 850627 Discussion W/L Olshan
ML20215L2171985-05-23023 May 1985
Notifies That Agreement Between Valley Stream Union Free School District Thirteen,American Red Cross & Util Re Use of Congregate Care Ctrs in Event of Nuclear Plant Emergency Nonexistent.Served on 850603
ML20215L2201985-05-20020 May 1985
Notifies That Roslyn Board of Education Agreement W/Util Re Use of Congregate Care Ctrs in Event of Plant Emergency Nonexistent.Served on 850603
ML20215L2271985-05-17017 May 1985
Notifies That Island Park School District Agreement W/Red Cross & Util Re Relocation in Event of Radiological Emergency Nonexistent.Served on 850603
ML20215L2381985-05-13013 May 1985
Notifies That Westbury Union Free School District Agreement W/American Red Cross or Util Re Svc as Relocation Ctr in Event of Plant Emergency Nonexistent.Served on 850603
ML20215L2491985-05-10010 May 1985
Protests That Willingness to Participate W/American Red Cross in Event of Natural Emergency Extended by Red Cross to Include Any Emergency Occurring from Plant Atomic Energy Generators.Served on 850603
ML20215L2581985-05-0909 May 1985
Notifies That Freeport Public Schools Not Consulted by Util Re Emergency Evacuation Plan & Unaware of Inclusion in Plan Until After Publication.Served on 850603
ML20215L2661985-05-0808 May 1985
Notifies That Permission to Include School in Evacuation Plan,Consistent W/Plan Evacuation Schedule,Granted to No One.Served on 850603
ML20215L2621985-04-0808 April 1985
Informs That No Legal Agreement Exists Between Nassau County & Util Re Use of Plant.Served on 850603.W/service List & Certificate of Svc
ML20136F6811985-02-14014 February 1985
Forwards Info to Update Svc Lists Per NRC 841211 Memo
ML20213F1201984-12-20020 December 1984
Supports Resolution, Sense of Legislature Resolution Requesting That NRC Permit Suffolk County to Present Oral Arguments Opposing Util Request for Low Power License for Shoreham Nuclear Power Plant. Resolution Encl
ML20213F1081984-12-19019 December 1984
Decries Licensee Refusal to Provide Info to Public Re Status of Fuel Loading.Immediate NRC Order Directing Util to Provide Regular,Full & Accurate Disclosure of Fuel Loading & Low Power Testing Requested
ML20215L2421984-12-0707 December 1984
Requests Opportunity to Present Oral Arguments Against Issuance of Low Power License for Plant.Served on 841213
ML20128Q7911984-11-14014 November 1984
Addresses NRC Concern Re Inservice Criteria for rate-setting & Effect Criteria May Have on Unduly Speeding Up Plant Const.Order on Inservice Criteria Encl
ML20133H6931984-11-14014 November 1984
Discusses Concerns Re Decision by PSC of Mo Concerning Inservice Criteria for Facility.Rept & Order - Phase I Re Procedural History Encl.Ack NRC Jurisdiction Over Facility Safety
ML20095E0091984-07-0505 July 1984
Requests NRC Safety Investigation Repts for Past 8 Months & Notification of Current Investigations.Info Needed to Determine Possible Financial Effect on State of Ak,Which May Need to Fund & Buy Energy from Facilities
ML20084G2101984-05-0202 May 1984
Requests Mo Public Svc Commission Representative Be Allowed to Accompany NRC on 840510 Site Visit to Wolf Creek. Representative Will Be at Fulton,Mo for NRC Meeting Re Callaway to Ensure NRC Rules Not Violated
ML20084G2131984-04-19019 April 1984
Requests Resumption of Caseload Forecasts for Facilities. Independent Caseload Forecasts Useful in Estimating Project Costs,Scheduling Plant Audits & Preparing Rate Cases
ML20087L8361984-02-17017 February 1984
Requests Explanation as to Why Facility Not Considered for Insp for Cracks in Vent Header Similar to Crack Found at Hatch
ML20206H1311984-01-30030 January 1984
Informs of Allegations of Defective Weld 1-W or W-1 on Generator B,Problems W/Ej Sys,Defective Long Seam Welds at Elbows of Some Pipes,Defective Pressurized & Generation Sys & Lost Documentation
ML20134M8881983-11-17017 November 1983
Forwards San Diego Gas & Electric Application for Financing, for Review.Requests Oral or Written Response W/Preliminary Indication as to Whether Project Would Qualify for Certification
ML20080G9801983-09-0909 September 1983
Requests Institution of Proceedings to Modify,Revoke or Suspend Facility Ols,Per 10CFR2.206
ML20024C9701983-07-0808 July 1983
Requests Available Nontechnical Info Re Problems W/ Engineering Design/Specs & or Implementation of Engineering Work for Plants
1990-02-05
[Table view] |
Text
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(3) an answer as to the remaining allegations.- The A.E.Cf' , gy N. 'probably not be concerned with the Demur,per or Answers pu .
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