ML20009B046
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| ML20009B046 | |
| Person / Time | |
|---|---|
| Site: | Ginna, Berkeley Research Reactor |
| Issue date: | 07/07/1981 |
| From: | Kaplan S CALIFORNIA, UNIV. OF, BERKELEY, CA |
| To: | John Miller Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8107140702 | |
| Download: ML20009B046 (2) | |
Similar Documents at Ginna, Berkeley Research Reactor | |
|---|---|
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 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 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 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 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 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 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 ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 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 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 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) ML17309A6491999-02-12012 February 1999 Forwards Ginna Station EOPs ML17265A5451999-02-12012 February 1999 Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) 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:EDUCATIONAL INSTITUTION TO NRC MONTHYEARML20012D1401990-02-27027 February 1990
[Table view]Informs That Annual Rept for Reactor Operation for 1989 Will Not Be Submitted.Decommissioning Final Rept & Termination Radiation Survey Results Will Be Submitted to NRR in Washington,Dc on Apr 1990 ML19332D2091989-10-12012 October 1989 Discusses QA for Berkeley Research Reactor Decommissioning. Reg Guide 2.5 Provides Adequate and Relevant Regulatory Basis for Research Reactor Removal Project QA Program ML20248F3081989-09-29029 September 1989 Advises NRC of Proposed Changes in Decommissioning Organization Personnel,Functions & Responsibilities.Bj Mann & Rs Patenaude Resumes Encl ML20245H3081989-08-0101 August 1989 Advises That Return & Transfer of Triga III Fuel to DOE or DOE Designated Facilities Completed ML20245D1321989-04-14014 April 1989 Responds to 890406 Request for Addl Info Re Facility Decommissioning Plan.Exposure Rate Measurements Will Be Made W/Gamma Scintillation Detector & Pressurized Ionization Chamber ML20247N5291989-03-14014 March 1989 Forwards 1988 Annual Rept.W/O Encl ML20206G2871988-11-10010 November 1988 Informs of Change in Arrangements for Emergency Care Re Emergency Response Plan for Facility.Alta Bates Hosp in Berkeley Will Provide Emergency Svcs for Contaminated Patients.Revised Pages to Plan Encl ML20207E6771988-08-0808 August 1988 Forwards Rev 3 to Facility Requalification Program,Per 880101 Termination of Operation of Reactor ML20151D7941988-06-22022 June 1988 Informs of Change in Arrangements for Emergency Care Re Emergency Response Plan for Univ of California Triga Mark III Berkeley Research Reactor. Alta Bates Hosp Will Honor Existing Agreement W/Herrick Hosp ML20150A7871988-06-22022 June 1988 Informs of Change in Arrangement Re Emergency Response Plan for Univ of California Triga Mark II Berkeley Research Reactor.Plan Now Calls Upon Herrick Hosp to Provide Emergency Svcs for Contaminated Patients ML20151A8161988-06-0909 June 1988 Requests Advance Route Approval as Required,Per 10CFR73.37(b)(7) ML20154H9311988-05-13013 May 1988 Informs That Univ of California Has Decided Not to Enter Opposition to City of Berkeley,Ca Petition to Intervene & Request for Hearing in Proceeding.Declaration of Svc Encl ML20151D4311988-01-12012 January 1988 Discusses Changes in Reactor Surveillance,Per Termination of Operation on 880101 ML20147D7441988-01-0808 January 1988 Forwards Environ Rept for Triga Mark III & Decommissioning Plan for Triga Mark III ML20238B1941987-08-20020 August 1987 Forwards Mn Christensen to Author Informing of Steps Taken to Correct Violations Noted in NRC . Corrective Actions:Frequency of Reactor Operations Audits Corrected & Personnel Advised of Reporting Requirements ML20203G3381986-06-12012 June 1986 FOIA Request for Documents Re Reactor & Senior Reactor Operator Licensing Exam Results for Jan 1983 - Dec 1984 ML20154S1501986-03-24024 March 1986 Forwards Revised Pages 8 & 10 to 1985 Annual Rept Reflecting Revised Max Concentration at Stack Discharge ML20099B9231984-11-0909 November 1984 Advises That 840813 Revised Upgraded Emergency Plan Implemented on 841109 ML20096C5921984-08-24024 August 1984 Forwards Revised Emergency Response Plan for Univ of California Triga Mark II Berkeley Research Reactor. Plan Will Be Fully Implemented 120 Days from Approval Date ML20096C6041984-08-24024 August 1984 Authorizes Th Lim to Sign Notarized Ltr Transmitting Amended Emergency Plan ML20024D1081983-07-25025 July 1983 Notifies That Th Pigford Will Replace Sn Kaplan as Administrator,Effective 830801 ML20085E2601983-06-21021 June 1983 Forwards Public Version of Revised Pages & New Attachment to Emergency Plan,In Response to ML20071E8351983-03-0808 March 1983 Forwards Berkeley Research Reactor Annual Rept of Operations ML20028A2021982-10-25025 October 1982 Forwards Public Version of Emergency Response Plan ML20042B7911982-03-18018 March 1982 Forwards Berkeley Research Reactor Annual Rept of Operations,Jan-Dec 1981. ML20009B0461981-07-0707 July 1981 Amends 810611 Request for Change in Feb 1964 SAR Pages 6-8, Lines 21,22, & 23 & Pages 6-9,Line 1.Clarifies Types of Personnel Working Around Reactor Who Must Have Physical Exams Every 24 Months ML20004F1291981-06-11011 June 1981 Requests Changes to Feb 1964 Sar,Mandating Physical Exam for Operators & Supervisors Every 24 Months,But at Intervals Not to Exceed 28 Months.Change Does Not Constitute Unreviewed Safety Question ML19344E4581980-08-25025 August 1980 Forwards Revised Page 15 of Proposed Security Plan.Plan Withheld (Ref 10CFR2.790) ML19344E3591980-08-11011 August 1980 Forwards Revised Emergency Plan,App C, Fuel Element Cladding Failure - Assessment of Exposure Doses, & App D, Direct Radiation Dose at Etcheverry Hall Patio Due to Loss of Pool Water. ML19320B0881980-07-0303 July 1980 Advises NRC That V Schrock Is No Longer Reactor Administrator.S Kaplan Has Been Reactor Administrator Since 791005 ML19305C0551980-03-20020 March 1980 Forwards Annual Rept of Operations,1979. ML19290F1781980-03-0505 March 1980 Forwards Revised Security Plan.Plan Withheld (Ref 10CFR2.790) ML19260D9181980-02-0505 February 1980 Requests That All Amends Re Indemnity Agreements E-15,E-16, E-53 & E-58 Be Forwarded to Univ of CA for Approval ML19210D9061979-11-21021 November 1979 Forwards Preliminary Draft of Facility Emergency Action Levels.Security Plan Not Received ML19256E8301979-11-0707 November 1979 Notifies That Amend 14 to Indemnity Agreement E-15 Was Signed by Unauthorized Employee.Requests Clean Copy for Execution by Proper Authority ML19260A4951979-10-25025 October 1979 Responds to NRC 791010 Ltr Re Violations Noted in IE Insp Rept 50-224/79-04.Corrective Actions:Required 1979 Rept Will Be Prepared & Stack Monitoring Sys Tests Will Be Noted on Printout Tape ML19254D9321979-10-23023 October 1979 Forwards Executed Amend 14 to Indemnity Agreement E-15 ML19250A0081979-10-0505 October 1979 Informs NRC of Change in Administrative Assignments. Sn Kaplan Is Reactor Administrator for Research Reactor ML20064J7701979-08-15015 August 1979 Forwards Info in Response to 790730 Request.Info Withheld (Ref 10CFR2.790) ML19241B3971979-07-0909 July 1979 Notifies That Ve Schrock Will Be Reactor Administrator of Berkeley Research Reactor,As of 790710 ML19241A7151979-06-29029 June 1979 Notifies That s Kaplan Will Continue as Reactor Administrator ML19261D7881979-06-21021 June 1979 Forwards Executed Amend 8 to Indemnity Agreement E-16,Amend 4 to Indemnity Agreement E-58,Amend 8 to Indemnity Agreement E-53 & Amend 13 to Indemnity Agreement E-15 ML19259C1001979-05-25025 May 1979 Forwards Annual Operating Rept 1978 ML20071G4571979-02-26026 February 1979 Requests Tech Spec Change for License R-101,covering Fuel Element & Fuel Follower ML20155K2531975-07-15015 July 1975 Updates Security Plan & Provides Addl Info on Status of Security Sys Following 750520 Security Insp.Forwards Emergency Procedure 1990-02-27 Category:INCOMING CORRESPONDENCE 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 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 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 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 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 ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 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 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 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 ML17265A7451999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) 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 ML17265A5111999-01-11011 January 1999 Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl ML17265A5101999-01-11011 January 1999 Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl 1999-09-30 |
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UNIVERSITY OF CALIFORNIA, BERKELEY BERKELEY
- DAVIS
- IRVINE
- LOS ANGELES
- RIVER $1DE
- SAN DIECO
- SAN FRANCISCD EANTA BARBAIM
- SANTA CBt'Z COLLEGE OF ENCINEERING BERKELEY, CALIFORNI A 94720 -
".- - i, 1
DEPARTMENT OF NL* CLEAR ENGINEERINC July 7, 1981 Vs Docket No. 50-224 (6- J y , /, n -
License No. R-101 7a .g[n-2 n.
' l,,,
-1 m Mr. James A. Miller, Chief M*-
Standardization and Special Project Branch M Division of Licensing U.S. Nuclear Regulatory Commission d7TG'P Washington, D.C. 20555
Dear Mr. Miller:
Based on Dr. Tek H. Lim's conversation with your staff, we would like to amend our request in our letter dated June 11, 1981, Docket No. 50-224, License No. R-101, in relation to a change in our Safety Analysis Report for the University of California Berkeley Research Reactor, February 1964 lines 21, 22 and 23 on pages 6-8 and line 1 of pages 6-9, to read as follows:
All personnel working around the reactor will be part of the medical program which is administrated by Environmental Health and Safety. This program calls for bi-annual physical exami-nations and alternate bi-annual clinical laboratory tests.
to:
Al l -pe rs enne l -we rking -a reund - the - reae te r -wil l -be -pa r t -e f- the medieal pregram-whieh-is-administrated-by-Envirenmental-Health and - Sa fe ty r - -Th is -pregram-e a ll s - fer -b i-annual -phys ieal - exami -
natiens-and-alternate-bi-annual-elinical-laberatery-tests.
All full time operators, full time senior operators, including the Chief Reactor Operator and Reactor Supervisor, and all full time health physics personnel working around the reactor will have a physical examination every 24 months but at intervals not to exceed 28 months.
'Ihese changes were reviewed by the Reactor Hazards Committee, Environmental Health and safety and the Reactor Staff.
This change does not constitute an unreviewed safety question in that:
(1) It does not increase the probability of occurrence of an accident analyzed in the bafety Analysis Report (2) It does not increase the consequences of an accident analyzed in the 0p Safety Analysis Report 8107140702 810707 PDR ADOCK 05000244 p' P PDR -
. o a
Safety Analysis Report July 6, 1981 (3) It does not create the possibility of occurrence of nuclear accident not previously analyzed in the Safety Analysis Report.
Sincerel vyours, a 4_
Selig N. Kaplan SNK: irs Reactor Administrator
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