ML20059M949
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| ML20059M949 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/13/1990 |
| From: | Hickman D NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| To: | Rich Smith ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| NUDOCS 9010050383 | |
| Download: ML20059M949 (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:NRC TO UTILITY MONTHYEARML20058E6671990-10-25025 October 1990
[Table view]Forwards Physical Security Insp Rept 50-244/90-21 on 900910-14.No Violations Noted ML20059M9491990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248G0391989-09-27027 September 1989 Forwards Amend 11 to Indemnity Agreement B-38 Reflecting Changes to 10CFR140, Financial Protection Requirements & Indemnity Agreements ML20247A6401989-05-0303 May 1989 Extends Invitation to Attend Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Agenda & Info Re Lodging Arrangements Encl ML20235U3871989-03-0101 March 1989 Advises That 890213 Submittal of Financial Info for 1989 Satisfies Requirements of 10CFR140,Section 140.21 Which Requires Maint of Approved Guarantee of Payment of Deferred Premiums for Each Operating Reactor Owned Over 100 Mwe ML20151R6161988-04-20020 April 1988 Forwards Table Listing Status of Current Licensing Actions on Plant.Table Will Be Revised to Reflect Changes in Dates for Completion &/Or New Issues That Need Licensing Reviews ML20196D1371988-02-0505 February 1988 Forwards Safeguards Insp Rept 50-244/87-28 on 871116-20.No Violations Noted ML20147C8601987-12-0707 December 1987 Forwards Exam Rept 50-244/87-22OL of Exam Administered During Week of 871005 ML20245C3551987-10-27027 October 1987 Forwards Amend 24 to License DPR-18 & Safety Evaluation. Amend Revises Requirements of Tech Specs Re Definition of Operability ML20235E8751987-09-22022 September 1987 Informs That on 870831,operator Licensing Responsibility Reassigned from Div of Reactor Projects to Operations Branch in Div of Reactor Safety.Rm Gallo Appointed Chief of Operations Branch,Div of Reactor Safety ML20238A8771987-08-31031 August 1987 Recommends That Site Specific Info Sheets & Appropriate Training Re Use Be Developed & Provided to Emergency Notification Sys & Health Physics Network Communicators to Facilitate Responses to NRC Requests for Data.Samples Encl ML20237H5441987-08-12012 August 1987 Forwards Results of Nonradiological Chemistry Stds Insp Activities for All Region I Licensees During 1985-1986. Results of Measurements Made by BNL Also Included ML20236E3421987-07-27027 July 1987 Ack Receipt of 861202 Proposed Amend to Plant Physical Security Plan.Addl Info & Revs to Plan Required Prior to Approval.Response to Encl Comments Requested within 30 Days of Ltr Receipt ML20214S7421987-06-0404 June 1987 Forwards Revised NRC Form-398, Personal Qualifications Statement - Licensee. New Applicants Required to Complete Each Category Completely,Including All Education,Training & Experience Received Up to Date of Application ML20205G9161987-03-25025 March 1987 Forwards Insp Rept 50-244/87-06 on 870224-27.No Violation Noted ML20205G6171987-03-24024 March 1987 Forwards Occupational Radiation Protection Insp Rept 50-244/87-05 on 870224-27.No Violations Noted ML20211P9081987-02-20020 February 1987 Forwards Safety Insp Rept 50-244/87-02 on 870104-0207.No Violations Noted.Concern Identified Re Monthly Surveillance Testing of Liquid Radwaste Monitor R-18.Response Requested within 30 Days of Ltr Receipt ML20211G5371987-02-18018 February 1987 Informs That 1987 Financial Info Submitted in Satisfies 10CFR140.21 Requirements That Each Licensee Maintain Approved Guarantee of Payment of Deferred Premiums for Each Operating Reactor Over 100 Mw(E) ML20210V0161987-02-0505 February 1987 Forwards Occupational Radiation Protection Insp Rept 50-244/87-01 on 870105-09.No Violations Noted IR 05000244/19870031987-01-28028 January 1987 Confirms Dates of 870209-13 for Equipment Qualification Insp 50-244/87-03.Insp Will Involve Review of Equipment Qualification Documentation Files & Physical Insp of Selected Plant Equipment & Selected Field Wiring ML20212M1521987-01-16016 January 1987 Forwards Safety Insp Rept 50-244/86-22 on 861215-19.No Violations Noted ML20207P8541987-01-14014 January 1987 Forwards Insp Rept 50-244/86-21 on 861109-870103.No Violations Noted ML20207P2401987-01-0707 January 1987 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-244/86-12 ML20211Q3271986-12-16016 December 1986 Requests Cooperation in Increasing Resident Inspector Visibility at Site.Nrc Plans to Present Videotaped Presentation of Senior Resident Inspector During General Employee Training ML20215H0391986-10-15015 October 1986 Forwards Safety Insp Rept 50-244/86-12 on 860826-29. Violation Noted.Notice Not Issued Due to Violation Being self-identified & Satisfying Criteria in 10CFR2,App C. Response Requested within 30 Days of Ltr Receipt ML20215C4511986-10-0303 October 1986 Forwards Safety Insp Rept 50-244/86-13 on 860909-11.No Violation Noted ML20215C6441986-10-0101 October 1986 Informs of Plans for 861020-24 Insp Re Ability to Provide Safe Shutdown in Event of Fire.Requests Analysis,Procedures & Other Documentation Re Subj Be Available at Facility During Insp ML20214F6671986-09-10010 September 1986 Notifies of 861029-30 Physical Protection Seminar in Cherry Hill,Nj to Discuss Results of 12-yr Implementation of 10CFR73 for Protection Against Radiological Sabotage. Preliminary Agenda Encl ML20203Q1411986-04-29029 April 1986 Provides Guidelines for Submittal of Objectives & Scenario Required Prior to 860910 Emergency Exercise.Schedule Similar to Least Restrictive Submittal Schedule Noted in Rev 1 to FEMA Guidance Memo 17 ML20141A1751986-03-26026 March 1986 Notifies That RM Gallo Is Section Chief for Facility Based on Realignment of Projects within Region I,Effective 860331 ML20210D9351986-03-24024 March 1986 Forwards FEMA Transmitting Rept of 850926 Full Participation Emergency Exercise for State of Ny & Wayne & Monroe Counties ML20154M3031986-03-0606 March 1986 Forwards,For Comment,Two Draft Repts Re Technical Insights Gained from Pras,Including Core Melt Frequency Mods as Result of Pras,Contributions to Measures of Risk & Insights Into PRA Methodologies.W/O Encls ML20214D4731986-02-19019 February 1986 Ack Receipt of 851220 Rev 11 of QA Program Per 10CFR50.54. Changes Acceptable & Do Not Reduce Commitments Previously Accepted in QA Program Description IR 05000244/19850181986-01-23023 January 1986 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-244/85-18 ML20137J2661986-01-16016 January 1986 Forwards Safety Insp Repts 50-454/85-49 & 50-455/85-34 on 851118-22,1209-12 & 860110.No Violation Identified.Response to Items in Paragraph 3.9 Re Control of Welding & Cutting Activities Requested within 30 Days of Ltr Receipt ML20140B0251986-01-0909 January 1986 Forwards Exam Rept 50-244/OL-85-23 of Operator Licensing Exams Conducted on 851111-15.Conduct & Administration of Exams Discussed on 851115 ML20134A2831985-10-30030 October 1985 Forwards Safety Insp Rept 50-244/85-20 on 850925-27.No Violation Noted.Proposed Actions to Upgrade Performance of Emergency Operations Facility Dose Assessment Team Requested within 30 Days ML20133E4271985-07-17017 July 1985 Forwards Exam Rept 50-244/85-11 of Exams Administered on 850624 IR 05000244/19820231983-04-27027 April 1983 Ack Receipt of 830111 & 0224 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in IE Insp Rept 50-244/82-23.Item C of Notice of Violation Re Spent Fuel Storage Grid Map Rescinded ML20062F6531982-07-29029 July 1982 Forwards IE Insp Rept 50-244/82-13 on 820628-0701.No Noncompliance Noted ML20055B0421982-07-0909 July 1982 Advises That 10 & 50-mile Radius Emergency Planning Maps & Emergency Response Photographs Will Be Forwarded Under Separate Cover.List of Maps & Explanation of Use Encl IR 05000244/19800161982-06-23023 June 1982 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in IE Health Physics Appraisal Insp Rept 50-244/80-16 ML20054M5611982-06-22022 June 1982 Forwards IE Insp Rept 50-244/82-11 on 820517-19.No Noncompliance Noted ML20054K8921982-06-16016 June 1982 Forwards IE Insp Rept 50-244/82-10 on 820501-31 & Notice of Violation ML20148B2931978-10-10010 October 1978 Informs That Normal Channels of Oral Communication Will Be Followed for Review of SEP ML20148F4191972-10-0404 October 1972 Requests Info Justifying Reactor Operation W/Core 10 at 600 Mwt.Fuel Pellet Separation & Fuel Cladding Collapse Discovered at Ginna Should Be Considered.Sar Transients & Accidents Should Be re-examined & Addl Limits Established 1990-06-13 Category:OUTGOING CORRESPONDENCE MONTHYEARIR 05000244/19990081999-10-14014 October 1999
[Table view]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 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 ML20195H6861998-11-16016 November 1998 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 981019-23 at Facility.Four Individuals Were Administered Examination & Four Passed.Copy of Licensee Ltrs Issued & Individual Test Results Encl.Without Encl ML20151W5061998-09-10010 September 1998 Informs That as Part of NRC Probabilistic Risk Assessment Implementation Plan,Commission Assigned Two Senior Reactor Analysts (Sras) to Each Regional Ofc.T Shedlosky & J Trapp Has Been Assigned SRAs for Region I ML20236J9871998-06-24024 June 1998 First Final Response to FOIA Request for Documents.Documents Listed in App a Already Available in Pdr.Documents Listed in App B Being Released in Entirety ML20217C0861997-09-29029 September 1997 Ack Receipt of & Payment for Civil Penalty Proposed by NRC in .C/As Will Be Examined During Future Insps ML20211E7471997-09-22022 September 1997 Partially Deleted Ltr Contract:Task Order 47 Entitled, Requalification Exam Insp for Ginna Nuclear Power Plant, Under Contract NRC-03-94-035 ML20217Q1371997-08-21021 August 1997 Forwards Corrected Page 1 of Forwarding NOV & Proposed Imposition of Civil Penalty of $55,000 IR 05000244/19960081997-08-15015 August 1997 Discusses Insp Rept 50-244/96-08 on 970521-30 & Forwards NOV & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Involved Insp Finding That Vehicle Barrier Sys Found Inadequate ML20217Q1481997-08-15015 August 1997 Corrected Page 1 of Forwarding NOV & Proposed Imposition of Civil Penalty for Violations of Security Requirements.Corrections Made to Insp Rept Ref & Date of Insp ML20137N1591997-03-31031 March 1997 Informs That Licensee Facility Scheduled to Administer NRC GFE on 970409.Sonalsts,Inc Authorized Under Contract to Support NRC Administration of GFE Activities ML20137A2111997-03-14014 March 1997 Transmits Info Pertaining to NRC Staff Review of Weld Defects in CE Designed SG Tube Sleeves ML20136C4211997-03-0606 March 1997 Fifteenth Partial Response to FOIA Request for Records. App Y Records Encl & Available in PDR ML20134B9581997-01-30030 January 1997 Ack Receipt of & Check for $100,000 in Payment for Civil Penalty Proposed by NRC in ML20132H0661996-12-13013 December 1996 Discusses Insp Rept 50-244/96-08 on 960722-26 & 0806-09 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000 ML20128G9071996-10-0303 October 1996 Forwards ERDS Implementation Documents & Data Point Library Updates for Listed Plant.W/O Encl ML20128Q4151996-10-0303 October 1996 Responds to Which Requested Info Re Transport of Used SG for Plant & Whether Discarded SG from Nuclear Power Plants May Be Shipped W/O Package Certification Issued by NRC ML20059E9511994-01-0707 January 1994 Requests Addl Info Re Graded Approach for GL 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance ML20058F0171993-11-16016 November 1993 Discusses Proposed Rule for Protection Against Malevolent Use of Vehicles at Nuclear Power Plants.Forwards Safeguards Info Providing Proposed Characteristics of Design Basis Vehicle & Guidance for Barrier Design.W/O Encl ML20059A2321993-10-20020 October 1993 Forwards Individual Exam Results for Licensee Applicants for Initial Exam Conducted During Wk of 930913.Encl Withheld Ref 10CFR2.790 ML20058M6391993-09-28028 September 1993 Forwards Peak Ground Acceleration & Spectral Values,Per 930927 Fax Request for Plants ML20059C5761993-09-27027 September 1993 Ltr Contract,Definitizing Task Order 17, Training & Qualification Effectiveness Insp - Re Ginna ML20057C1261993-09-16016 September 1993 Forwards FEMA Exercise Rept for 910911,full-participation Exercise at Plant.No Deficiencies Noted ML20057A7521993-09-0808 September 1993 Forwards Safety Evaluation Informing That Licensee Third 10-yr Interval ISI Program Plan,Rev 2 as Submitted 930125, Not Acceptable,Per 10CFR50.55a(g) & TS 4.2.1.5.Record Copy ML20057A5851993-08-31031 August 1993 Ack Receipt of in Response to Violations Noted in Insp Rept 50-244/93-15 ML20128P5051992-11-23023 November 1992 Final Response to FOIA Request for Documents Re SECY-87-100 & 870622 Memo from Sj Chilk to V Stello & Wc Parler.Forwards Documents Listed in App a Which Are Being Made Available in PDR ML20058E6671990-10-25025 October 1990 Forwards Physical Security Insp Rept 50-244/90-21 on 900910-14.No Violations Noted ML20055F4221990-07-0303 July 1990 Final Response to FOIA Request.No Agency Records Subj to Request Located.Guidance Given Orally During Telcon ML20059M9491990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248G0391989-09-27027 September 1989 Forwards Amend 11 to Indemnity Agreement B-38 Reflecting Changes to 10CFR140, Financial Protection Requirements & Indemnity Agreements ML20247A6401989-05-0303 May 1989 Extends Invitation to Attend Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Agenda & Info Re Lodging Arrangements Encl ML20235U3871989-03-0101 March 1989 Advises That 890213 Submittal of Financial Info for 1989 Satisfies Requirements of 10CFR140,Section 140.21 Which Requires Maint of Approved Guarantee of Payment of Deferred Premiums for Each Operating Reactor Owned Over 100 Mwe ML20154A1521988-08-17017 August 1988 Final Response to FOIA Request for Documents.Forwards Documents Listed in App A.Documents Also Available in Pdr. App B Documents Totally Withheld (Ref FOIA Exemption 5).App C Documents Partially Withheld (Ref FOIA Exemption 5) ML20207D1121988-07-0505 July 1988 Partial Response to FOIA Request for Documents.Forwards App M Documents.App L Documents Maintained in Pdr.Apps N & O Documents Partially & Totally Withheld,Respectively (Ref FOIA Exemption 5) ML20195F8041988-06-15015 June 1988 First Partial Response to FOIA Request for Documents. Forwards Apps B & C Documents.Documents Available in Pdr.App a Documents Also Available in Pdr.Apps D Through G Documents Withheld (Ref FOIA Exemption 5).Releasable Portion Encl ML20151R6161988-04-20020 April 1988 Forwards Table Listing Status of Current Licensing Actions on Plant.Table Will Be Revised to Reflect Changes in Dates for Completion &/Or New Issues That Need Licensing Reviews ML20151M6061988-04-19019 April 1988 Responds to FOIA Request for Info Re Scores of Reactor Operators & Senior Reactor Operators.Forwards Requalification Exam Summary Source Sheets Listed in Encl App W/Personal Privacy Info Deleted ML20151D3921988-04-0606 April 1988 Provides Listed Info Requested in Re Operating Nuclear Power Units Located at Twelve Sites Along Great Lakes ML20148C4961988-03-18018 March 1988 Final Response to FOIA Request for Documents.Forwards App C Documents.Documents Available in PDR ML20196D1371988-02-0505 February 1988 Forwards Safeguards Insp Rept 50-244/87-28 on 871116-20.No Violations Noted ML20237C8201987-12-10010 December 1987 Partial Response to FOIA Request for Records on Emergency Response Data Sys.Forwards App a & B Documents.App A,B & C Documents Also Available in PDR ML20147C8601987-12-0707 December 1987 Forwards Exam Rept 50-244/87-22OL of Exam Administered During Week of 871005 ML20236V7341987-12-0101 December 1987 Partial Response to FOIA Request for Documents.Forwards Documents Listed in App C ML20245C3551987-10-27027 October 1987 Forwards Amend 24 to License DPR-18 & Safety Evaluation. Amend Revises Requirements of Tech Specs Re Definition of Operability IR 05000244/19870201987-10-22022 October 1987 Forwards Insp Rept 50-244/87-20 on 870823-1003.No Violations Noted ML20235E8751987-09-22022 September 1987 Informs That on 870831,operator Licensing Responsibility Reassigned from Div of Reactor Projects to Operations Branch in Div of Reactor Safety.Rm Gallo Appointed Chief of Operations Branch,Div of Reactor Safety ML20235B3081987-09-21021 September 1987 Responds to FOIA Request for Documents,Including AEC to ACRS Forwarding Safety Evaluation Re Zimmer.App a Documents Cannot Be Located.App B Documents in Pdr.App C & D Documents Withheld (Ref 10CFR2.790) ML20238A8771987-08-31031 August 1987 Recommends That Site Specific Info Sheets & Appropriate Training Re Use Be Developed & Provided to Emergency Notification Sys & Health Physics Network Communicators to Facilitate Responses to NRC Requests for Data.Samples Encl ML20237H5441987-08-12012 August 1987 Forwards Results of Nonradiological Chemistry Stds Insp Activities for All Region I Licensees During 1985-1986. Results of Measurements Made by BNL Also Included ML20236E3421987-07-27027 July 1987 Ack Receipt of 861202 Proposed Amend to Plant Physical Security Plan.Addl Info & Revs to Plan Required Prior to Approval.Response to Encl Comments Requested within 30 Days of Ltr Receipt 1999-09-24 |
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+ UNITED STATES i
'!' 'e'? NUCLEAR REGULATORY COMMISSION :
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- j W ASHINGT ON, D. C. 20b66 ,
- % , , , , , * ,a- June 13, 1990 Mr. Robert Smith Vice President, Production and Engineering ,
Rochester Gas and Electric Corp. ,
89 East Ave. !
Rochester, NY 14649 :
Dear Mr. Smith:
The Nuclear Regulatory Commission's Performance Indicator Program '
provides eight performance indicators for use by NRC senior managers to monitor trends in the overall performance of individual nuclear power plants. These indicators provide an additional view l of operational performance to supplement that obtained through other NRC programs. The purpose of this letter is to transmit to ;
you the NRC performance indicators for R. E. Ginna Nuclear Power Plant for the first quarter of 1990. I have also included ;
Announcement No. 200 on the use of performance indicators and the definitions of the indicators, which are contained in each issue of the report.
You will routinely be sent a copy of future quarterly performance t indicators for Ginna.
If I can be of any further assistance, you may contact me at (301) i 492-4361. l t
Fincerely, l Donald E. Hickman, Chief Performance Indicators Section Office for Analysis and Evaluation ,
of Operational Data U.S. Nuclear Regulatory Commission
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ADOCK 05000244 PDC p
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