ML20127L754
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20072U2211991-04-12012 April 1991
[Table view]Forwards Response to NRC 901221 Request for Addl Info Re SSAR for Design Certification (CESSAR-DC) LD-91-014, Forwards Response to NRC Request for Addl Info Re Design Certification,CESSAR-DC,per1991-03-26026 March 1991 Forwards Response to NRC Request for Addl Info Re Design Certification,CESSAR-DC,per ML20029C1001991-03-15015 March 1991 Forwards Response to NRC 890626 Request for Addl Info Re C-E Std SAR - Design Certification (CESSAR-DC),including Revs to CESSAR-DC LD-91-012, Forwards Response to NRC 890119 Request for Addl Info to Enable NRC to Continue Review of CESSAR - Design Certification (CESSAR-DC)1991-03-15015 March 1991 Forwards Response to NRC 890119 Request for Addl Info to Enable NRC to Continue Review of CESSAR - Design Certification (CESSAR-DC) LD-91-013, Forwards Response to NRC 890626 Request for Addl Info Re C-E Std SAR - Design Certification (CESSAR-DC),including Revs to CESSAR-DC1991-03-15015 March 1991 Forwards Response to NRC 890626 Request for Addl Info Re C-E Std SAR - Design Certification (CESSAR-DC),including Revs to CESSAR-DC LD-91-011, Forwards Amend 1 to CESSAR - Design Certification (CESSAR-DC)1991-03-0404 March 1991 Forwards Amend 1 to CESSAR - Design Certification (CESSAR-DC) LD-91-010, Responds to NRC 881223 Request for Addl Info Re CESSAR-DC. Forwards Proposed Revisions to CESSAR-DC1991-03-0404 March 1991 Responds to NRC 881223 Request for Addl Info Re CESSAR-DC. Forwards Proposed Revisions to CESSAR-DC ML20029A6211991-02-15015 February 1991 Forwards Request for Addl Info Re Chapters 5 & 6 of CESSAR-DC,Sys 80+ Design,Based on NRC Review LD-91-006, Forwards Summary of Amend I to Std SAR for Design Certification,For Info & Planning Purposes1991-01-30030 January 1991 Forwards Summary of Amend I to Std SAR for Design Certification,For Info & Planning Purposes ML20028H3931990-12-24024 December 1990 Forwards Request for Addl Info on DC Application for C-E Sys 80 Design Project 675.Response Required within 90 Days of Reciept of Request LD-90-097, Forwards Response to 901106 Request for Discussion of Differences Between Certain Provisions of EPRI Advanced LWR Util Requirements Document & Sys 80+ Std Design1990-12-21021 December 1990 Forwards Response to 901106 Request for Discussion of Differences Between Certain Provisions of EPRI Advanced LWR Util Requirements Document & Sys 80+ Std Design LD-90-075, Forwards Amend H to CESSAR - Design Certification1990-10-0303 October 1990 Forwards Amend H to CESSAR - Design Certification LD-90-060, Forwards Proposed Changes to Sys 80+ Licensing Review Basis Document,Per1990-08-28028 August 1990 Forwards Proposed Changes to Sys 80+ Licensing Review Basis Document,Per LD-90-046, Forwards Addl Copies of Amend G to CESSAR-DC1990-07-12012 July 1990 Forwards Addl Copies of Amend G to CESSAR-DC LD-90-043, Advises That Licensee Will Submit Application for Final Design Approval & Design Certification of Process Inherent Ultimate Safety Reactor in FY92 & That Safe Integral Reactor Anticipated in FY93,in Addition to Sys 80+ Under Review1990-06-18018 June 1990 Advises That Licensee Will Submit Application for Final Design Approval & Design Certification of Process Inherent Ultimate Safety Reactor in FY92 & That Safe Integral Reactor Anticipated in FY93,in Addition to Sys 80+ Under Review LD-90-031, Forwards Amend G to CESSAR-design Certification,Per Draft Licensing Review Basis Document1990-04-30030 April 1990 Forwards Amend G to CESSAR-design Certification,Per Draft Licensing Review Basis Document LD-90-030, Forwards Amend F to CESSAR-DC & Affidavit,Per 10CFR50.4(b) & 50.30(b)1990-04-26026 April 1990 Forwards Amend F to CESSAR-DC & Affidavit,Per 10CFR50.4(b) & 50.30(b) B13454, Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Approx Two NRC Team Insps Conducted at Facilities Each Yr.Two SSFIs Conducted in 19881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Approx Two NRC Team Insps Conducted at Facilities Each Yr.Two SSFIs Conducted in 1988 ML20033E2851990-03-0101 March 1990 Responds to Generic Ltr 90-01 Re Request for Voluntary Participation in NRC Regulatory Impact Survey.Completed Questionnaire Includes Info on NRC Insps,Required QA Audits, Nelia & Maelu Insps,State of Mi Insps & FEMA Insps ML17347B5881990-03-0101 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 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 ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 ML20012A0231990-02-27027 February 1990 Informs of Organizational Changes within Div of Reactor Projects,Project Directorate III/2.Change Reassigned Project Managers to Listed Facilities ML20033E2941990-02-26026 February 1990 Informs of Address Change for Correspondence Control Desk to Reflect Move of Nuclear Group to Chesterbrook 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) 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 ML20033E4551990-02-15015 February 1990 Amends 881128 Application for Amends to Licenses NPF-9 & NPF-17,clarifying Tech Spec 6.2.3 Re Safety Review Group,Per 900212 Discussions W/Nrc.Listed Criteria Replace That of Previous Submittal ML20006E6251990-02-15015 February 1990 Requests Determination That 10CFR26 App a Section 2.7(0)(3)(ii) Does Not Require That Alcohol Breath Analysis Equipment Conform to Both Natl Safety Highway Traffic Safety Admin Stds & State Statutes or Exemptions to 10CFR26 A08496, Ack Receipt of Listed Invoices for Costs Incurred During Routine Reviews of Plant1990-02-15015 February 1990 Ack Receipt of Listed Invoices for Costs Incurred During Routine Reviews of Plant ML18094B3291990-02-14014 February 1990 Forwards Printouts Containing RW-859 Nuclear Fuel Data for Period Ending 891231 & Diskettes 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) ML20006E1511990-02-12012 February 1990 Advises That 891201 Rev 57 to QA Topical Rept CE-1-A Consistent W/Provisions of 10CFR50.App B & Acceptable ML20006F1301990-02-12012 February 1990 Lists Suggested Topics for Licensee Info Conference,Per 900117 Request ML20006D6751990-02-0909 February 1990 Partial Response to FOIA Request for Documents.App Q Documents Encl.App Q & Documents Available in Pdr.App R Documents Totally Withheld (Ref FOIA Exemption 5) ML20006D7831990-02-0808 February 1990 Advises That Board Concluded That Holding Prehearing Telcon Re Scheduling Considered Premature Due to Lack of Record,Per .Request for Future Scheduling Suggested to Be Submitted.W/Certificate of Svc.Served on 900209 B13447, Advises of Changes to Util Distribution Lists for Correspondence from NRC Due to Organizational Title Changes. Revs to Distribution List Encl1990-02-0808 February 1990 Advises of Changes to Util Distribution Lists for Correspondence from NRC Due to Organizational Title Changes. Revs to Distribution List Encl 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 ML20006C4491990-02-0101 February 1990 Requests Telephone Conference Be Set Up at Board Convenience Due to Author Not Being Able to Reach Licensee Counsel ML20006C5661990-01-31031 January 1990 Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants 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 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) 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 1991-04-12 Category:INCOMING CORRESPONDENCE MONTHYEARML20072U2211991-04-12012 April 1991
[Table view]Forwards Response to NRC 901221 Request for Addl Info Re SSAR for Design Certification (CESSAR-DC) LD-91-014, Forwards Response to NRC Request for Addl Info Re Design Certification,CESSAR-DC,per1991-03-26026 March 1991 Forwards Response to NRC Request for Addl Info Re Design Certification,CESSAR-DC,per ML20029C1001991-03-15015 March 1991 Forwards Response to NRC 890626 Request for Addl Info Re C-E Std SAR - Design Certification (CESSAR-DC),including Revs to CESSAR-DC LD-91-013, Forwards Response to NRC 890626 Request for Addl Info Re C-E Std SAR - Design Certification (CESSAR-DC),including Revs to CESSAR-DC1991-03-15015 March 1991 Forwards Response to NRC 890626 Request for Addl Info Re C-E Std SAR - Design Certification (CESSAR-DC),including Revs to CESSAR-DC LD-91-012, Forwards Response to NRC 890119 Request for Addl Info to Enable NRC to Continue Review of CESSAR - Design Certification (CESSAR-DC)1991-03-15015 March 1991 Forwards Response to NRC 890119 Request for Addl Info to Enable NRC to Continue Review of CESSAR - Design Certification (CESSAR-DC) LD-91-010, Responds to NRC 881223 Request for Addl Info Re CESSAR-DC. Forwards Proposed Revisions to CESSAR-DC1991-03-0404 March 1991 Responds to NRC 881223 Request for Addl Info Re CESSAR-DC. Forwards Proposed Revisions to CESSAR-DC LD-91-011, Forwards Amend 1 to CESSAR - Design Certification (CESSAR-DC)1991-03-0404 March 1991 Forwards Amend 1 to CESSAR - Design Certification (CESSAR-DC) LD-91-006, Forwards Summary of Amend I to Std SAR for Design Certification,For Info & Planning Purposes1991-01-30030 January 1991 Forwards Summary of Amend I to Std SAR for Design Certification,For Info & Planning Purposes LD-90-097, Forwards Response to 901106 Request for Discussion of Differences Between Certain Provisions of EPRI Advanced LWR Util Requirements Document & Sys 80+ Std Design1990-12-21021 December 1990 Forwards Response to 901106 Request for Discussion of Differences Between Certain Provisions of EPRI Advanced LWR Util Requirements Document & Sys 80+ Std Design LD-90-075, Forwards Amend H to CESSAR - Design Certification1990-10-0303 October 1990 Forwards Amend H to CESSAR - Design Certification LD-90-060, Forwards Proposed Changes to Sys 80+ Licensing Review Basis Document,Per1990-08-28028 August 1990 Forwards Proposed Changes to Sys 80+ Licensing Review Basis Document,Per LD-90-046, Forwards Addl Copies of Amend G to CESSAR-DC1990-07-12012 July 1990 Forwards Addl Copies of Amend G to CESSAR-DC LD-90-043, Advises That Licensee Will Submit Application for Final Design Approval & Design Certification of Process Inherent Ultimate Safety Reactor in FY92 & That Safe Integral Reactor Anticipated in FY93,in Addition to Sys 80+ Under Review1990-06-18018 June 1990 Advises That Licensee Will Submit Application for Final Design Approval & Design Certification of Process Inherent Ultimate Safety Reactor in FY92 & That Safe Integral Reactor Anticipated in FY93,in Addition to Sys 80+ Under Review LD-90-031, Forwards Amend G to CESSAR-design Certification,Per Draft Licensing Review Basis Document1990-04-30030 April 1990 Forwards Amend G to CESSAR-design Certification,Per Draft Licensing Review Basis Document LD-90-030, Forwards Amend F to CESSAR-DC & Affidavit,Per 10CFR50.4(b) & 50.30(b)1990-04-26026 April 1990 Forwards Amend F to CESSAR-DC & Affidavit,Per 10CFR50.4(b) & 50.30(b) ML20033E2851990-03-0101 March 1990 Responds to Generic Ltr 90-01 Re Request for Voluntary Participation in NRC Regulatory Impact Survey.Completed Questionnaire Includes Info on NRC Insps,Required QA Audits, Nelia & Maelu Insps,State of Mi Insps & FEMA Insps B13454, Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Approx Two NRC Team Insps Conducted at Facilities Each Yr.Two SSFIs Conducted in 19881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Approx Two NRC Team Insps Conducted at Facilities Each Yr.Two SSFIs Conducted in 1988 ML17347B5881990-03-0101 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 ML20033E2941990-02-26026 February 1990 Informs of Address Change for Correspondence Control Desk to Reflect Move of Nuclear Group to Chesterbrook 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) 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 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 A08496, Ack Receipt of Listed Invoices for Costs Incurred During Routine Reviews of Plant1990-02-15015 February 1990 Ack Receipt of Listed Invoices for Costs Incurred During Routine Reviews of Plant ML20006E6251990-02-15015 February 1990 Requests Determination That 10CFR26 App a Section 2.7(0)(3)(ii) Does Not Require That Alcohol Breath Analysis Equipment Conform to Both Natl Safety Highway Traffic Safety Admin Stds & State Statutes or Exemptions to 10CFR26 ML20033E4551990-02-15015 February 1990 Amends 881128 Application for Amends to Licenses NPF-9 & NPF-17,clarifying Tech Spec 6.2.3 Re Safety Review Group,Per 900212 Discussions W/Nrc.Listed Criteria Replace That of Previous Submittal 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) ML20006F1301990-02-12012 February 1990 Lists Suggested Topics for Licensee Info Conference,Per 900117 Request B13447, Advises of Changes to Util Distribution Lists for Correspondence from NRC Due to Organizational Title Changes. Revs to Distribution List Encl1990-02-0808 February 1990 Advises of Changes to Util Distribution Lists for Correspondence from NRC Due to Organizational Title Changes. Revs to Distribution List Encl 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 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 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) 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 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 ML20006C0431990-01-29029 January 1990 Forwards Response to NRC Bulletin 89-003.Util Nuclear Fuels Dept Designs or Reviews & Approves Each Core Reload for Plants & Refueling Operations Recently Reviewed to Ensure Appropriate Procedural Controls in Place B13244, Informs of Plans to Resolve Problems Experienced During Last Two Summers W/High Svc Water Temps Slightly Above 90 F. Proposed License Amend Requests Will Be Submitted Limiting UHS Temps for Haddam Neck & Millstone Unit 21990-01-29029 January 1990 Informs of Plans to Resolve Problems Experienced During Last Two Summers W/High Svc Water Temps Slightly Above 90 F. Proposed License Amend Requests Will Be Submitted Limiting UHS Temps for Haddam Neck & Millstone Unit 2 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 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 A08383, Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Personnel Trained in Overall Control Procedure for Fuel Movement1990-01-25025 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Personnel Trained in Overall Control Procedure for Fuel Movement 1991-04-12 Category:OTHER U.S. GOVERNMENT AGENCY/DEPARTMENT TO NRC MONTHYEARML20011E5571990-02-0808 February 1990
[Table view]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 ML20005D7501989-12-0404 December 1989 Forwards Rept for State of Mn off-hours & Unannounced Drill Conducted on 891019 for Plants.One Area Requiring Corrective Action Re Staffing Activation Inadequacy Corrected at Monticello 890726 Exercise.Preparedness Deemed Adequate ML20247J7721989-07-19019 July 1989 Forwards Rept for Unannounced off-hours Drills on 881020 for State of WI,site-specific to Zion,Point Beach,Kewaunee & Prairie Island Nuclear Power Stations.No Deficiencies or Areas Requiring Corrective Actions Noted ML18101A4911989-06-26026 June 1989 Forwards Final Exercise Rept of 881129 Exercise of Offsite Radiological Emergency Preparedness Plans site-specific to Artificial Island Generating Station.No Deficiencies Noted ML20235N3421989-02-15015 February 1989 Responds to 890201 Request for Estimates for Centrifuge Plant Demonstration Facility (Cpdf) & Oliver Springs Plus Cpdf.Doe Intends to Ensure That Sufficient Finances Exist for Decontamination & Decommissioning Liabilities ML20151A1321988-06-29029 June 1988 Forwards Artificial Island Nuclear Generating Stations Site Specific Offsite Radiological Emergency Preparedness Alert & Notification Sys QA Verification. Sys Satisfies NUREG-0654/ FEMA-REP,Rev 1 & FEMA-REP-10 Requirements ML18093A8641988-05-27027 May 1988 Forwards FEMA & Region III Final Exercise Rept of 870909 Exercise of State of DE Offsite Radiological Emergency Preparedness Plans site-specific to Artificial Island Generating Station ML20237C0831987-12-0707 December 1987 Forwards Kewaunee Nuclear Plant & Point Beach Nuclear Plant Site-Specific Offsite Radiological Emergency Preparedness Alert & Notification Sys QA Verification. Alert & Notification Sys Satisfies NUREG-0654/FEMA-REP-1,Rev 1 ML20236L2461987-07-30030 July 1987 Discusses Participation of Certain Ingestion Exposure Pathway EPZ-only States in Qualifying Exercises Used by NRC in Making Licensing Decisions for Operating Exercises.Listed Plants Noncompliant as of 870331 ML20245B6361987-06-17017 June 1987 Forwards Post-Exercise Assessment of 861112 Exercise of Radiological Emergency Response Plans of State of Nj,Salem County.... FEMA Requested Schedule of Corrective Actions from State by 870626.Offsite Preparedness Adequate for EPZ ML20199B2561986-06-0505 June 1986 Notifies NRC That State of DE & Local Radiological Emergency Plans Adequate,Conditioned on FEMA Verification of Alert & Notification Sys ML20214E2311986-02-28028 February 1986 Forwards Medical Svcs Info for State of Ny & Oswego County Radiological Emergency Preparedness Plan.Info Confirms List of Medical Facilities Identified for Use in Event of Emergency ML20151V0191986-02-0404 February 1986 Forwards 851029 Full Participation Exercise Rept of Offsite Radiological Emergency Preparedness Plans & Results of 851115 Remedial Exercise.Deficiency Identified Re Failure to Complete Public Alert within Time Period ML20140A8921986-01-14014 January 1986 Forwards Interim Findings on Adequacy of Radiological Emergency Response Preparation of State & Local Govts..., Based on State of Nj Emergency Response Plan & Exercises Conducted at Salem from 810408-841023.Plans Adequate ML18092A7771985-09-16016 September 1985 Informs That Remaining Category B Deficiency Identified During Salem 831026 Exercise Corrected.Util Agreed to Underwrite Cost of Installing Decontamination Showers & Sleeping Quarters at State of DE Emergency Operations Ctr ML20133G6411985-08-0606 August 1985 Supports Pennsylvania Emergency Mgt Agency Request to Exempt Chester County from Full Participation in Joint Exercises Involving Peach Bottom,Providing County Participates in Limerick Exercise ML20127J8811985-06-14014 June 1985 Advises That State & Local Plans for Radiological Emergencies Adequate,Subj to Criteria of App 3 of NUREG- 0654/FEMA-REP-1,Rev 1 & FEMA-43, Std Guide for Evaluation of Alert & Notification Sys for Nuclear Power Plants ML20133A5121985-04-30030 April 1985 Forwards PA Bradley FOIA Request for Documents Re Vogtle & Ei Hatch Antitrust Reviews ML20108F3801984-12-13013 December 1984 Forwards Final Findings 44CFR350,NY State & Oswego County Plans & Preparedness,Nine Mile Point/Ja Fitzpatrick Nuclear Power Generating Stations, for Review.Comments Requested by 850108 ML20199H6301984-09-26026 September 1984 Forwards Ltr of Determination on Complaint of M Gregory V Brown & Root,Inc.Related Info Also Encl ML20199H8121984-08-27027 August 1984 Forwards Complaint of M Gregory V Brown & Root,Inc & Ltrs of Notification ML20138C1821984-08-23023 August 1984 Forwards Project & Budget Proposals for NRC Work for Rev 1 to, Evaluation of Selected NRC Open Items Before Plant Fuel Load & Evaluation of Selected Open NRC Activities at Near-Term OL Sites Needing Action.. ML20095A2061984-08-13013 August 1984 Informs That FEMA Does Not Intend to Conduct full-scale Evaluation of Hope Creek 1985 Exercise.Since Salem Unit 1 OL Issued Prior to 820713,full Participation in 1985 Not Required by NRC or FEMA Rules ML20126D8341984-03-0808 March 1984 Forwards FEMA 840216 Review of Util Emergency Planning Zone Public Info Brochure,Per ASLB 830526 Partial Initial Decision.All Recommended Changes/Mods Incorporated ML17346A5701984-02-15015 February 1984 Approves State & Local Plans & Preparedness for Alerting & Protecting Public in Event of Radiological Emergency. Approval Conditional on Verification of Alert & Notification Sys,Per Criteria of App 3 of NUREG-0654/FEMA-REP-1,Rev 1 ML20106A0681984-01-27027 January 1984 Discusses Savannah District Dam Safety Plan.Plan & Related Maps Forwarded Under Separate Cover.Plan Addresses Emergencies Re Above Normal Reservoir Water Levels &/Or Rapid Release of Large Vol of Water Past Dam ML20210E7061984-01-18018 January 1984 Provides Info in Response to Request for Assistance in Addressing Issues Raised in R Kranzdorf Re Emergency Preparedness of Offsite Jurisdictions.Issues Addressed Include Flooding at Twin Bridges & Siren Sys ML20210E6951983-12-16016 December 1983 Responds to Request for Assistance in Formulating Response to R Kranzdorf Re Emergency Plans & Preparedness. Info Provided Includes Evacuation Time Considerations, Evacuation Transportation Routes & Emergency Broadcast Sys ML20127N1911983-11-16016 November 1983 Forwards Executed Std Order for DOE Work: Safety Evaluation of Core-Melt Accidents:Operating Reactor Reviews for Indian Point & Zion ML20127E9941983-11-16016 November 1983 Forwards Std Order for DOE Work for FIN A-3711, Safety Evaluation of Core Melt Accidents:GESSAR-FDA,Limerick-OL & FNP-ML ML20127L8421983-11-0404 November 1983 Forwards Executed Std Order for DOE Work: Safety Evaluation of Core-Melt Accidents:CESSAR-FDA,Westinghouse Std Plant- Fda. W/O Order ML20083H9381983-10-18018 October 1983 Responds to Jj Cummings Re Alleged Violations by Bahnson Co Employees.Criminal Prosecution Declined Due to Inability to Prove Criminal Intent ML20127M8981983-09-14014 September 1983 Forwards Executed Std Order for DOE Work: Safety Evaluation of Core-Melt Accidents:Operating Reactor Reviews for Indian Point & Zion. W/O Encl ML20127E8521983-09-14014 September 1983 Forwards Executed Std Order for DOE Work for FIN A-3346, Safety Evaluation of Core Melt Accidents:GESSAR-FDA, Limerick-OL & FNP-ML ML20127M7581983-08-26026 August 1983 Forwards Executed Std Order for DOE Work: Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor ML20024D2441983-07-18018 July 1983 Responds to 830325 Memo Advising FEMA of Region I Concerns That Fixed Sirens Installed at Facilities Will Not Assure Adequate Coverage.Operability of Sys Met Criteria During 830309 Activation for Indian Point ML20117L9281983-05-25025 May 1983 Forwards Correspondence Addressed to President Reagan Re Safety Problems at Nuclear Power Plants & DOE Reply ML20127L7541983-05-0303 May 1983 Forwards Executed Std Order for DOE Work: Safety Evaluation of Core-Melt Accidents:Cessar - Final Design Approval, Westinghouse Std Plant - Final Design Approval. Project Identification Summary Also Encl.W/O Std Order ML20155D3261983-03-22022 March 1983 Responds to Approval Request for Info Collection Re 10CFR50, Domestic Licensing of Production & Utilization Facilities. Request Approved for Use Through 850430 ML20134A8321983-03-17017 March 1983 Informs That Mc Beard Will Be Available on 830405 to Provide Briefing for Commission Re FAA Sys of Civil Aviation Regulation,In Response to 830303 Request ML20127M5691983-02-25025 February 1983 Forwards Property Certification of Equipment Purchased Under FIN A-3392.Disposition Instructions Requested by 830315 ML20127M4941983-02-10010 February 1983 Forwards Executed Std Order for DOE Work, Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor ML20127E4801983-01-11011 January 1983 Forwards Std Order for DOE Work 20-83-209 for FIN A-3711, Safety Evaluation of Core Melt Accidents:GESSAR-FDA, Limerick-OL & FNP-ML ML20127M3751983-01-10010 January 1983 Forwards Executed Std Order for DOE Work: Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor ML20067D5281982-11-18018 November 1982 Clarifies Position Re Seismic Potential of Certain Regions of Eastern Us.Deterministic & Probabilistic Evaluations of Seismic Hazard Should Be Made for Individual Sites to Establish Seismic Engineering Parameters ML20052E7261982-04-13013 April 1982 Confirms Plans for 820428 Meeting W/Utils in King of Prussia,Pa Re Radiological Emergency Preparedness Alert & Notification Sys ML20064E1331982-03-19019 March 1982 Requests Completion Date of Insp at Facility.Criminal Investigation Might Impair NRC Civil Enforcement Efforts. Related Info Encl ML17276B1011982-02-19019 February 1982 Forwards Input for Des Re Potential Use of Water Stored in Fdr Lake ML20071H1881981-03-26026 March 1981 Forwards Sealed Ltrs for Delivery to Houston Lighting & Power & Brown & Root.Ltrs Deal W/Investigation at South Tx Project ML20064E4191981-03-13013 March 1981 Responds to 810302 Request Re Authority of Ofc of Special Counsel,Merit Sys Protection Board,Under 5 U.S.C. 1206(b)(2) & (7).NRC Not Required to Furnish Counsel Rept on Complaint Alleging Govt Mismanagement & Gross Waste at Facility 1990-02-08 |
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.. OFFICE OF NUCLEAR REACTOR RE6._ATION d
PROJECTIDENTIFICATION
SUMMARY
(PIDS)
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CONTRACT UMBER (Non-DOE):
B&R NUMBER.
3RR E TI G
~
20-19-40-44-3
'INDEX NO.:
DIVISION: DSI BRANCH:RSB PROJECT MANAGER: J. Meyer CONTRACTOR: ENL CONTRACT METHOD: DOE Work Order i
CITY, STATE (Non-DOE):e SHAll. BUSINESS / MINORITY CONTRACT (Non-DOE):
SUB-CONTRACTOR (S):
.M-YES / /
NO.. /. /
AMOUNT $
PROJECTED PERIOD OF PERFORMANCE.
- START: li,i/pA(est) END: 9/30/85 f,
i ~,,
PROJECTED FINANCIAL DATA (000's)
%/kbD PROJECT FY 1983
~~
TOTAL TOTAL TOTAL CARRY FY 83 FY 84 FY 85 VALUE OBLIG COSTED
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BUDG BUDG 00 M (0 l&
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APPLICATION (RELATE THE PROJECT TO A SPECIFIC PLANNED ACCOMkISHI5NYI Review of PRA studies for:
1.
CESSAR System 80 FDA review l
2.
Westinghouse Standard Plant FDA review
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~ WORK REQUIREMENTS (DESCRIBE WHAT IS TO BE PERFORMED)
Tha followin'g analyses and asse'ssmerits will belerformd by this project: core-melt accident progressions with emphasis on containment loadings (pressure and temperature) x and containment failure characteristic; evolution and release of radiological source term during core-melt accidents from fuel, primary system, and containment system; radiological consequences to the public from core-melt accidents; and safety benefit from features to mitigate the consequences of core melt accidents. To support these analyses, the contractor will be required to maintain and modify the MARCH, CORRAL, MATADOR'and CPAC-Ccdes as required in 1:;ht of the current RES MARCH-2 and MELCOR development assimilate results of pnenomenological studies (RES, ID00R, foreign, and DOE) program and and engineering research programs.
In addition, an overall integrated assessment which considers '
all of these factors will b'e prepared for design. Products: miscellaneous letter reports for ir.put to SERs, input to hearing testimony, if required.
Major Product:
(2) NUREG/CRs - FY 1985.
t
- 1. :
MODIFICATIONS (DESCRIBE MAJOR CHANGES TO THE PROJECT) e COMPLETE AS APPLICABLE -
Reconsnended:
Endorsed:
Endorsed:
Endorsed:
Approved:
PROJECT MANAGER SECTION LDR BRANCll CHF ASST DIR.
DIV. DIR (Initials)
(Date)
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