NUREG-0821, Forwards Suppl to NUREG-0821, Integrated Plant Safety Assessment Program. Provisional OL Will Not Be Issued Until 830930.W/o Encl
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| ML20024F278 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/02/1983 |
| From: | Matt Young NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | Cole R, Grossman H, Luebke E Atomic Safety and Licensing Board Panel |
| References | |
| RTR-NUREG-0821, RTR-NUREG-821, TASK-***, TASK-RR NUDOCS 8309090173 | |
| Download: ML20024F278 (1) | |
Similar Documents at Ginna | |
|---|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML17250B3041999-10-20020 October 1999
[Table view]Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated IR 05000244/19990081999-10-14014 October 1999 Forwards Insp Rept 50-244/99-08 on 990809-0919.Severity Level IV Violation of NRC Requirements Occurred & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML17265A7651999-10-0808 October 1999 Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request ML17265A7631999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000 ML17265A7641999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel ML20212J3561999-09-30030 September 1999 Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21 ML20212J3801999-09-30030 September 1999 Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21 IR 05000244/19990051999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7571999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs IR 05000244/19992011999-09-24024 September 1999 Forwards Insp Rept 50-244/99-201 (Operational Safeguards Response Evaluation) on 990621-24.No Violations Noted. Primary Purpose of Osre to Assess Licensee Ability to Respond to External Threat.Insp Rept Withheld ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 ML17265A7401999-08-26026 August 1999 Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components ML17265A7411999-08-26026 August 1999 Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded ML17265A7451999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) ML17250B3021999-08-23023 August 1999 Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806 ML17265A7271999-07-30030 July 1999 Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply ML17265A7151999-07-23023 July 1999 Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions ML17265A7061999-07-22022 July 1999 Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations ML17265A7191999-07-21021 July 1999 Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 ML17265A7141999-07-21021 July 1999 Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future ML17265A7041999-07-16016 July 1999 Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603 ML17265A6911999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached ML17265A6871999-06-22022 June 1999 Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl ML17265A6841999-06-21021 June 1999 Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment ML17265A6741999-06-15015 June 1999 Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT ML17265A6751999-06-11011 June 1999 Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification ML17309A6551999-06-0707 June 1999 Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML17265A6671999-06-0101 June 1999 Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 ML17265A6641999-05-25025 May 1999 Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested ML17265A6611999-05-24024 May 1999 Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 ML20206U0921999-05-13013 May 1999 Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 ML17265A6461999-05-12012 May 1999 Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP ML17265A6411999-05-12012 May 1999 Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 ML20206E7221999-04-29029 April 1999 Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 ML20206H6911999-04-22022 April 1999 Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls ML17265A6271999-04-19019 April 1999 Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 ML17309A6501999-04-14014 April 1999 Forwards Revised Ginna Station EOPs & Procedures Index ML17265A6121999-03-29029 March 1999 Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231 ML17265A6041999-03-24024 March 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618 ML17265A5671999-03-0101 March 1999 Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl ML17265A5641999-03-0101 March 1999 Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl ML17265A5551999-02-25025 February 1999 Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr ML17265A5561999-02-22022 February 1999 Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d) ML17265A5451999-02-12012 February 1999 Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) ML17309A6491999-02-12012 February 1999 Forwards Ginna Station EOPs ML17265A5431999-02-0909 February 1999 Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301 ML17265A5361999-02-0202 February 1999 Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl ML17311A0691999-01-25025 January 1999 Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date ML17311A0671999-01-14014 January 1999 Forwards Revised Emergency Operating Procedures for Re Ginna NPP ML17265A5131999-01-12012 January 1999 Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date 1999-09-30 Category:INTERNAL OR EXTERNAL MEMORANDUM MONTHYEARML20196F4021998-12-0101 December 1998
[Table view]Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam Submittal & as-given Operating Exam for Tests Administered on 981019-23 ML20236N4031997-09-15015 September 1997 Forwards SER for Operability Assessment of Intermediate Range Neutron Monitoring Instrument While Instrument Undercompensated for Proper Detector Voltage for Re Ginna Nuclear Plant ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML17309A6041996-09-12012 September 1996 Summarizes Editorial Error within Improved TS Believed to Be Candidate for Correction Outside License Amend Process ML20138E9311995-12-21021 December 1995 Forwards Agenda for 960122 IPE Senior Review Board Meeting Re contractor-developed Requests for Addl Info for Plants NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20058K8631990-07-19019 July 1990 Forwards D Kwiatkowski Re FEMA Region I Rept for 890816 Full Participation Exercise at Plant ML19332F7431989-07-21021 July 1989 Provides Summary of Station Blackout Responses & Staff Review Schedule Per Request.Cursory Check of Licensee Responses to Station Blackout Rule Has Been Performed in Order to Provide Overview of Industry Approach ML20206L9141988-11-15015 November 1988 Notification of Significant Licensee Meeting on 881122 in King of Prussia,Pa to Discuss Ipat Insp & Long Term Improvement Program ML20151D8791988-07-14014 July 1988 Notification That 880719 Meeting Rescheduled for 880720 W/Util in Rockville,Md to Discuss Steam Generator Sleeving Utilizing a New Technique for Sleeve Installation ML20196G4051988-06-23023 June 1988 Forwards AEOD Technical Review Rept T809, Blocked Thimble Tubes/Stuck Incore Detector, for Consideration Due to Recent Events at Braidwood Unit 1 ML20147C7031988-03-0101 March 1988 Forwards Corrected Summary Rept on Multi-Plant Action D-05 Re Upper Plenium Injection,Recommendation Concerning Generic Priority & Items for Senior Mgt Attention ML20237B2681987-12-11011 December 1987 Requests That Encl 10CFR50.App I Evaluations,For Listed Facilities Not Already Covered by Repts in Dcs,Be Entered Into DCS Sys on Microfiche ML20195G7341987-12-10010 December 1987 Forwards SALP Input Re Emergrncy Preparedness at Plant for June 1986 - Nov 1987 ML20195G6551987-12-0909 December 1987 Forwards Input to SALP Rept for 860606-871130.SALP Input Summarizes Strengths,Weaknesses & Other Observations Noted in Individual Insp Repts & Accompanying SALP Input ML20153E9181987-11-16016 November 1987 Forwards Oct 1987 Significant Intergovernmental Activities & Issues Rept.Rept Represents Combined Efforts of NRC Regional State Liaison Officers,State,Local & Indian Tribes Programs Staff & Regional State Agreement Representatives ML20154A2831986-12-13013 December 1986 Forwards Assessments by Enforcement Staff of Regional Performance in Enforcement Area from Jul-Nov 1985 ML20214R9971986-09-17017 September 1986 Notification of Licensee Meeting 86-110 on 861007 W/Util in Rochester,Ny to Discuss SALP ML20211M9071986-06-20020 June 1986 Discusses Rj Bores 850502 Response to RW Krimm 860422 Request to Members of Federal Radiological Preparedness Coordinating Committee for Concurrence w/FEMA-REP-2-NY-3. Bores Concurred W/Reservation.No Addl Info Needed ML20151Q9751986-01-29029 January 1986 Requests Identification of Div Contact for Regional Insp Team Leaders to Arrange NRR Alternative Shutdown & Fire Protection Reviewer Technical Assistance on region-based post-fire Safe Shutdown Insps.Schedule of Insps Submitted ML20133F8921985-10-0202 October 1985 Notification of 851011 Meeting W/Exxon Nuclear Co,Inc in Bethesda,Md to Discuss Recent Exxon Activities Toward Resolving Safety Analysis Issues ML20128L1111985-07-0505 July 1985 Forwards Results of ALARA-related Radiation Program Evaluations.Most Licensees Generally Performing Satisfactorily ML20127F3061985-06-18018 June 1985 Forwards Tabular Summary of Key Results from Regional Survey of plant-specific Info Re Potential for Uncontrolled Radiation Exposures in PWR Cavities,Per Jg Partlow 850315 Request.No Further Generic Action Needed ML20033D8481985-01-30030 January 1985 Informs That,Based on Large Sampling of Operating Plants, Multi-Plant Action B-24 Criteria for Complete Purge & Vent Line Motor Operated Containment Isolation Valve Closure within 15 After LOCA Satisfied.Table Encl ML20090J3691984-11-0909 November 1984 Recommends That TRAC-PF1/MOD1 & RELAP5/MOD2 Be Benchmarked Against Plant Data on Steam Generator Tube Rupture Event. Pc Disc Containing TRAC-PF1/MOD1 Deck for Plant Encl. W/O Encl ML20090J3521984-08-21021 August 1984 Forwards Ginna Steam Generator Tube Rupture Event - Retran Calculations. Rept Confirms NRC Position Re Thermal & Hydraulic Conditions & Consequences of Not Terminating ECCS, Per HR Denton .Transmittal of Rept Requested ML20090H6171984-02-23023 February 1984 Provides Status Re Facility Anl Steam Generator Tube Rupture (SGTR) Analysis.Reanalysis of SGTR Event Not Straightforward or Uncomplicated.Present Funding Inadequate ML20090H6031984-02-14014 February 1984 Forwards Reactor Sys Branch SER of long-term Restart Requirements 6 & 10 Re Steam Generator Tube Rupture Procedures.Procedures & Sys Review Branch SER for Items 11, 12 & 20 Also Encl ML20105B8461984-01-30030 January 1984 Provides Results of Review of NSHC Package Re Facility Enrichment Fuel Assembly.Package Acceptable.Staff Technical Review & Analysis Skimpy & Inadequate ML20105B8821983-12-22022 December 1983 Provides Results of Review of NSHC Package Re Working Hours & Reporting Requirements ML20105C3961983-10-19019 October 1983 Comments on License Amend Package Re Hydraulic Snubbers.Use of Example 7 Inappropriate ML20102B2141983-09-27027 September 1983 Provides Results of Review of NSHC Package Re Tech Spec Amend Concerning Consolidation of Responsibilities.Package Will Be Returned W/O Concurrence Due to Insufficient Basis for Proposed NSHC Determination NUREG-0821, Forwards Suppl to NUREG-0821, Integrated Plant Safety Assessment Program. Provisional OL Will Not Be Issued Until 830930.W/o Encl1983-09-0202 September 1983 Forwards Suppl to NUREG-0821, Integrated Plant Safety Assessment Program. Provisional OL Will Not Be Issued Until 830930.W/o Encl ML20090G5781983-08-23023 August 1983 Forwards Evaluation of Response to long-term Items 11,12 & 20 in Restart SER (NUREG-0916) Re Steam Generator Tube Rupture Event.Licensee Responses Acceptable ML20090G5311983-07-28028 July 1983 Forwards SER Input Re Ventilation Procedures During Steam Generator Tube Rupture Releases.No Effect on safety-related Equipment Operation Anticipated ML20090G5271983-07-22022 July 1983 Forwards Reactor Sys Branch Safety Evaluation Re Steam Generator Tube Rupture thermal-hydraulic Analysis,Reactor Coolant Pump Alternate Trip & Restart Criteria & Stagnant Flow Scenarios & Pressurized Thermal Shock ML20090E6831983-05-16016 May 1983 Informs of Review & Acceptance of Util as Discharging long-term Commitment Item 16 Re Steam Generator Tube Rupture Incident.Issue Closed ML20090E6861983-05-0303 May 1983 Forwards Safety Evaluation Accepting Alarm Setpoints & Operational Surveillance Requirements Contained in Licensee 821122 Rept Responses to Long-Term Commitments in Ginna Steam Generator Tube Rupture Incident Restart Ser ML20027C9411982-10-26026 October 1982 Updates 820730 Status Rept on NRC Issuances.Final Integrated Plant Safety Assessment Rept to Be Issued on 821029. Conversion Safety Evaluation Rept & Update to Fes to Be Issued in Nov ML20027D7091982-10-0707 October 1982 Notification of 821103 Meeting W/Utils & Franklin Research Ctr in Bethesda,Md to Discuss Design (IE Bulletin 80-11) & Use of Energy Balance Technique & Arching Theory ML20090B6591982-10-0101 October 1982 Submits Daily Highlight for 821001.Fish-mouth Rupture Found in Previously Plugged Tube.Small Piece of Weld Rod Found in Each Steam Generator ML20027D2141982-09-29029 September 1982 Forwards s Re SEP Phase III for Distribution ML20062D3291982-07-29029 July 1982 Forwards Incident Reporting Sys Repts Re Effects of Fire Protection Sys Actuation on safety-related Equipment & Seismic Qualification of safety-related Sys for Transmission to NEA ML20058B3781982-07-0606 July 1982 Requests That Encl Incident Reporting Sys Repts Be Forwarded to Otsuka of NEA ML20090B5451982-06-21021 June 1982 Forwards Response to J Barton Re Emergency Preparedness Re Steam Generator Tube Rupture Accident ML20023A4651982-06-15015 June 1982 Forwards Mechanical Engineering Branch Input to Restart SER Sections 4.5 Through 4.8,5.1,5.2,5.4,6.1 & 6.2,per 820423 Request ML20054E6271982-06-0808 June 1982 Releases Public Version of Revision 18 to Emergency Plan & Revised Implementing Procedures ML20090B5071982-05-26026 May 1982 Advises That Problem Areas Listed in 800814 SER Input for SEP Topics II-3.A,B & C Re Hydrology Were Addressed Either in Draft Version of Plant Integrated Assessment or in Comments Transmitted by 820518 Memo ML20090B5281982-05-25025 May 1982 Forwards Generic Recommendations from Review of NUREG-0909, NRC Rept on 820125 Steam Generator Tube Rupture on Re Ginna Nuclear Power Plant ML20090B5111982-05-24024 May 1982 Submits Recommendations Re Generic Implications of 820125 Steam Generator Tube Rupture Event 1998-12-01 Category:MEMORANDUMS-CORRESPONDENCE MONTHYEARML20196F4021998-12-0101 December 1998
[Table view]Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam Submittal & as-given Operating Exam for Tests Administered on 981019-23 ML20236N4031997-09-15015 September 1997 Forwards SER for Operability Assessment of Intermediate Range Neutron Monitoring Instrument While Instrument Undercompensated for Proper Detector Voltage for Re Ginna Nuclear Plant ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML17309A6041996-09-12012 September 1996 Summarizes Editorial Error within Improved TS Believed to Be Candidate for Correction Outside License Amend Process ML20138E9311995-12-21021 December 1995 Forwards Agenda for 960122 IPE Senior Review Board Meeting Re contractor-developed Requests for Addl Info for Plants NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20058K8631990-07-19019 July 1990 Forwards D Kwiatkowski Re FEMA Region I Rept for 890816 Full Participation Exercise at Plant ML19332F7431989-07-21021 July 1989 Provides Summary of Station Blackout Responses & Staff Review Schedule Per Request.Cursory Check of Licensee Responses to Station Blackout Rule Has Been Performed in Order to Provide Overview of Industry Approach ML20206L9141988-11-15015 November 1988 Notification of Significant Licensee Meeting on 881122 in King of Prussia,Pa to Discuss Ipat Insp & Long Term Improvement Program ML20151D8791988-07-14014 July 1988 Notification That 880719 Meeting Rescheduled for 880720 W/Util in Rockville,Md to Discuss Steam Generator Sleeving Utilizing a New Technique for Sleeve Installation ML20196G4051988-06-23023 June 1988 Forwards AEOD Technical Review Rept T809, Blocked Thimble Tubes/Stuck Incore Detector, for Consideration Due to Recent Events at Braidwood Unit 1 ML20147C7031988-03-0101 March 1988 Forwards Corrected Summary Rept on Multi-Plant Action D-05 Re Upper Plenium Injection,Recommendation Concerning Generic Priority & Items for Senior Mgt Attention ML20237B2681987-12-11011 December 1987 Requests That Encl 10CFR50.App I Evaluations,For Listed Facilities Not Already Covered by Repts in Dcs,Be Entered Into DCS Sys on Microfiche ML20195G7341987-12-10010 December 1987 Forwards SALP Input Re Emergrncy Preparedness at Plant for June 1986 - Nov 1987 ML20195G6551987-12-0909 December 1987 Forwards Input to SALP Rept for 860606-871130.SALP Input Summarizes Strengths,Weaknesses & Other Observations Noted in Individual Insp Repts & Accompanying SALP Input ML20153E9181987-11-16016 November 1987 Forwards Oct 1987 Significant Intergovernmental Activities & Issues Rept.Rept Represents Combined Efforts of NRC Regional State Liaison Officers,State,Local & Indian Tribes Programs Staff & Regional State Agreement Representatives ML20154A2831986-12-13013 December 1986 Forwards Assessments by Enforcement Staff of Regional Performance in Enforcement Area from Jul-Nov 1985 ML20214R9971986-09-17017 September 1986 Notification of Licensee Meeting 86-110 on 861007 W/Util in Rochester,Ny to Discuss SALP ML20211M9071986-06-20020 June 1986 Discusses Rj Bores 850502 Response to RW Krimm 860422 Request to Members of Federal Radiological Preparedness Coordinating Committee for Concurrence w/FEMA-REP-2-NY-3. Bores Concurred W/Reservation.No Addl Info Needed ML20151Q9751986-01-29029 January 1986 Requests Identification of Div Contact for Regional Insp Team Leaders to Arrange NRR Alternative Shutdown & Fire Protection Reviewer Technical Assistance on region-based post-fire Safe Shutdown Insps.Schedule of Insps Submitted ML20133F8921985-10-0202 October 1985 Notification of 851011 Meeting W/Exxon Nuclear Co,Inc in Bethesda,Md to Discuss Recent Exxon Activities Toward Resolving Safety Analysis Issues ML20005D1921985-08-27027 August 1985 Board Notification 85-081:forwards Sanitized Versions of Ltrs Discussing Employee Allegations Re Westinghouse Analyses & QA at Listed Facilities.Insp at Westinghouse Scheduled for Late Aug 1985 ML20128L1111985-07-0505 July 1985 Forwards Results of ALARA-related Radiation Program Evaluations.Most Licensees Generally Performing Satisfactorily ML20127F3061985-06-18018 June 1985 Forwards Tabular Summary of Key Results from Regional Survey of plant-specific Info Re Potential for Uncontrolled Radiation Exposures in PWR Cavities,Per Jg Partlow 850315 Request.No Further Generic Action Needed ML20033D8481985-01-30030 January 1985 Informs That,Based on Large Sampling of Operating Plants, Multi-Plant Action B-24 Criteria for Complete Purge & Vent Line Motor Operated Containment Isolation Valve Closure within 15 After LOCA Satisfied.Table Encl ML20090J3691984-11-0909 November 1984 Recommends That TRAC-PF1/MOD1 & RELAP5/MOD2 Be Benchmarked Against Plant Data on Steam Generator Tube Rupture Event. Pc Disc Containing TRAC-PF1/MOD1 Deck for Plant Encl. W/O Encl ML20090J3521984-08-21021 August 1984 Forwards Ginna Steam Generator Tube Rupture Event - Retran Calculations. Rept Confirms NRC Position Re Thermal & Hydraulic Conditions & Consequences of Not Terminating ECCS, Per HR Denton .Transmittal of Rept Requested ML20090H6171984-02-23023 February 1984 Provides Status Re Facility Anl Steam Generator Tube Rupture (SGTR) Analysis.Reanalysis of SGTR Event Not Straightforward or Uncomplicated.Present Funding Inadequate ML20090H6031984-02-14014 February 1984 Forwards Reactor Sys Branch SER of long-term Restart Requirements 6 & 10 Re Steam Generator Tube Rupture Procedures.Procedures & Sys Review Branch SER for Items 11, 12 & 20 Also Encl ML20105B8461984-01-30030 January 1984 Provides Results of Review of NSHC Package Re Facility Enrichment Fuel Assembly.Package Acceptable.Staff Technical Review & Analysis Skimpy & Inadequate ML20105B8821983-12-22022 December 1983 Provides Results of Review of NSHC Package Re Working Hours & Reporting Requirements ML20105C3961983-10-19019 October 1983 Comments on License Amend Package Re Hydraulic Snubbers.Use of Example 7 Inappropriate ML20102B2141983-09-27027 September 1983 Provides Results of Review of NSHC Package Re Tech Spec Amend Concerning Consolidation of Responsibilities.Package Will Be Returned W/O Concurrence Due to Insufficient Basis for Proposed NSHC Determination NUREG-0821, Forwards Suppl to NUREG-0821, Integrated Plant Safety Assessment Program. Provisional OL Will Not Be Issued Until 830930.W/o Encl1983-09-0202 September 1983 Forwards Suppl to NUREG-0821, Integrated Plant Safety Assessment Program. Provisional OL Will Not Be Issued Until 830930.W/o Encl ML20090G5781983-08-23023 August 1983 Forwards Evaluation of Response to long-term Items 11,12 & 20 in Restart SER (NUREG-0916) Re Steam Generator Tube Rupture Event.Licensee Responses Acceptable ML20090G5311983-07-28028 July 1983 Forwards SER Input Re Ventilation Procedures During Steam Generator Tube Rupture Releases.No Effect on safety-related Equipment Operation Anticipated ML20090G5271983-07-22022 July 1983 Forwards Reactor Sys Branch Safety Evaluation Re Steam Generator Tube Rupture thermal-hydraulic Analysis,Reactor Coolant Pump Alternate Trip & Restart Criteria & Stagnant Flow Scenarios & Pressurized Thermal Shock ML20090E6831983-05-16016 May 1983 Informs of Review & Acceptance of Util as Discharging long-term Commitment Item 16 Re Steam Generator Tube Rupture Incident.Issue Closed ML20090E6861983-05-0303 May 1983 Forwards Safety Evaluation Accepting Alarm Setpoints & Operational Surveillance Requirements Contained in Licensee 821122 Rept Responses to Long-Term Commitments in Ginna Steam Generator Tube Rupture Incident Restart Ser ML20027C9411982-10-26026 October 1982 Updates 820730 Status Rept on NRC Issuances.Final Integrated Plant Safety Assessment Rept to Be Issued on 821029. Conversion Safety Evaluation Rept & Update to Fes to Be Issued in Nov ML20027D7091982-10-0707 October 1982 Notification of 821103 Meeting W/Utils & Franklin Research Ctr in Bethesda,Md to Discuss Design (IE Bulletin 80-11) & Use of Energy Balance Technique & Arching Theory ML20090B6591982-10-0101 October 1982 Submits Daily Highlight for 821001.Fish-mouth Rupture Found in Previously Plugged Tube.Small Piece of Weld Rod Found in Each Steam Generator ML20027D2141982-09-29029 September 1982 Forwards s Re SEP Phase III for Distribution ML20062D3291982-07-29029 July 1982 Forwards Incident Reporting Sys Repts Re Effects of Fire Protection Sys Actuation on safety-related Equipment & Seismic Qualification of safety-related Sys for Transmission to NEA ML20058B3781982-07-0606 July 1982 Requests That Encl Incident Reporting Sys Repts Be Forwarded to Otsuka of NEA ML20090B5451982-06-21021 June 1982 Forwards Response to J Barton Re Emergency Preparedness Re Steam Generator Tube Rupture Accident ML20023A4651982-06-15015 June 1982 Forwards Mechanical Engineering Branch Input to Restart SER Sections 4.5 Through 4.8,5.1,5.2,5.4,6.1 & 6.2,per 820423 Request ML20054E6271982-06-0808 June 1982 Releases Public Version of Revision 18 to Emergency Plan & Revised Implementing Procedures ML20090B5071982-05-26026 May 1982 Advises That Problem Areas Listed in 800814 SER Input for SEP Topics II-3.A,B & C Re Hydrology Were Addressed Either in Draft Version of Plant Integrated Assessment or in Comments Transmitted by 820518 Memo ML20090B5281982-05-25025 May 1982 Forwards Generic Recommendations from Review of NUREG-0909, NRC Rept on 820125 Steam Generator Tube Rupture on Re Ginna Nuclear Power Plant 1998-12-01 Category:NRC TO ASLP MONTHYEARNUREG-0821, Forwards Suppl to NUREG-0821, Integrated Plant Safety Assessment Program. Provisional OL Will Not Be Issued Until 830930.W/o Encl1983-09-0202 September 1983
[Table view]Forwards Suppl to NUREG-0821, Integrated Plant Safety Assessment Program. Provisional OL Will Not Be Issued Until 830930.W/o Encl ML20027C9411982-10-26026 October 1982 Updates 820730 Status Rept on NRC Issuances.Final Integrated Plant Safety Assessment Rept to Be Issued on 821029. Conversion Safety Evaluation Rept & Update to Fes to Be Issued in Nov 1983-09-02 |
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A (NW September 2, 1983 Herbert Grossman, Esq., Chairman Dr. Richard F. Cole Administrative Judge Administrative Judge Atomic Safety and Licensing Board Atomic Safety and Licensing Board U.S. Nuclear Regulatory Comission U.S. Nuclear Regulatory Comission Washington, D. C.
20555 Washington, D. C.
20555 Dr. Emmeth A. Luebke Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D. C.
20555 In the Matter of ROCHESTER GAS & ELECTRIC CORPORATION (R.E. Ginna Nuclear Power Plant, Unit No.1)
Docket No. 50-244
Dear Ad;;;inistrative Judges:
The Staff has issued a supplement to the Ginna Integrated Plant Safety AssessmentReport(NUREG-0821). Enclosed is a copy for your information.
The Staff Safety Evaluation Report related to the conversion of the i
Ginna Provisional Operating License has been delayed and will not issue until September 30.
Sincerely, Mitzi A. Young Counsel for NRC Staff
Enclosure:
As stated cc w/ enclosure: H.Grossman
' r]
E. Luebke Q
R. Cole
~
H. Voight MM\\Q S. Klimberg t\\1 New York State Attorney General's Office M. Slade cc w/o enclosure: Remainder of service list OFC :0 ELD p:0E
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NAME :MYoung:pl
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s DATE :9/.'L./83
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/83 _ _ _
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