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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20205B8961999-03-25025 March 1999 Forwards Insp Rept 50-326/99-201 on 990223-25.No Violations Noted.Various Aspects of Reactor Operations,Maint, Engineering Programs & Security Were Inspected ML20202A6841999-01-22022 January 1999 Forwards Amend 4 to License R-116 & Safety Evaluation.Amend Provides Surveillance Requirement Applicable to Shutdown Conditions,Air Effluent Release Limits Consistent with Current 10CFR20 & Clarifying,Editorial Changes ML20197J7101998-12-0707 December 1998 Responds to Recent Telcon in Which NRC Requested Clarification of Few Items Re Request for Amend to TS for Univ of Ca,Irvine Triga Reactor ML20151Z2901998-09-17017 September 1998 Forwards RAI Re Changes to Univ of California,Irvine Triga Research Reactor TSs for Surveillances During Shutdown Conditions Submitted on 980824.Response Requested within 60 Days of Date of Ltr ML20217E9371998-03-26026 March 1998 Forwards Insp Rept 50-326/97-201 on 971208-11 of Triga Research Reactor.No Significant Safety Issues Were Identified ML20199L6461997-11-29029 November 1997 Forwards Licensee Rept of Items of TS non-compliance & Facility Annual Rept for 960701-970630 ML20199L6571997-11-29029 November 1997 Informs of Several Violations of TS at Facility.Corrective Actions:Full Insps & Recalibrations Have Been Carried Out & Specific Schedule Established & Posted in Facility Detailing Dates of Required Surveillance Activities Projected ML20100E5021996-02-12012 February 1996 Responds to Violations Noted in License R-116.Corrective Actions:New Channel Instruments Designed to Provide Normally Closed Set of Contacts Initiated by bi-stable,providing Same Scram & Interlock Functions as Equipment ML20094S3951995-11-29029 November 1995 Informs of Omissions Found During Review of Records in Conjunction w/on-site Insp by Region IV Re Implementation of Operator Requalification Plan ML20091L3721995-08-13013 August 1995 Forwards Univ of CA Irvine Nuclear Reactor Facility Annual Rept for Jul 1994 - June 1995. Error Identified in Distribution of Previous Annual Rept.Rept for Jul 1993 - June 1994 Encl.W/O Jul 1993 - June 1994 Rept ML20065L7601994-04-12012 April 1994 Informs That Reactor Operations Committee for Facility Failed to Meet in Period 930624-1217,in Violation of Requirements in TS Section 6.2f Due to Lack of Urgent Business,Heavy Staff Teaching Loads & Busy Schedules ML20058K0841990-11-26026 November 1990 Advises of Changes Re Identity of Individuals in Administration Chain ML20058J0111990-11-0909 November 1990 Ack Receipt of Transmitting Rev 2 to Physical Security Plan & Supplemental Info Re Performance Characteristics of Intrusion Alarm Sys.Changes Acceptable IR 05000326/19900021990-07-24024 July 1990 Forwards Safeguards Insp Rept 50-326/90-02 on 900709-10.No Violations or Deviations Identified.Rept Withheld Per 10CFR2.790 ML20055G9271990-07-19019 July 1990 Provides Decommissioning Statement for Facility.Revised Estimates Will Be Reported to Commission at Intervals Not to Exceed 5-yrs ML20043H2191990-06-0505 June 1990 Forwards Updated Version of Physical Security Plan.Alarm Reporting Sys Redescribed to Agree W/Changes in Instrumentation Made Over Last 2 Yr Period.W/O Encl 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 ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) ML20006G0621990-02-22022 February 1990 Forwards Revised Proprietary Pages to DPC-NE-2004, Core Thermal Hydraulic Methodology Using VIPRE-01, Reflecting Minor Methodology Changes Made During Review & Approval Process.Pages Withheld ML20006E5881990-02-20020 February 1990 Forwards Proprietary Response to NRC 890725 Questions Re Vipre Core Thermal Hydraulic Section of Topical Rept DPC-NE-3000 & Rev 2 to Pages 3-69,3-70,3-78 & 3-79 of Rept. Encls Withheld (Ref 10CFR2.790) 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 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) 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 ML20006C6711990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Plants Have Established Preventive Maint Program for Intake Structure & Routine Treatment of Svc Water Sys W/Biocide to Control Biofouling ML20006B7961990-01-29029 January 1990 Forwards Summaries of Latest ECCS Evaluation Model Changes 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 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 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 ML19354E6711990-01-24024 January 1990 Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226 ML17347B5451990-01-24024 January 1990 Informs of Plans to Apply ASME Code Case N-356 at Plants to Allow Certification Period to Be Extended to 5 Yrs.Rev to Inservice Insp Programs Will Include Use of Code Case ML19354E4461990-01-22022 January 1990 Forwards Proprietary Rev 1 to DPC-NE-2001, Fuel Mechanical Reload Analysis Methodology for MARK-BW Fuel, Adding Section Re ECCS Analysis Interface Criteria & Making Associated Administrative Changes.Rev Withheld ML19354E4451990-01-22022 January 1990 Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters ML20005G7161990-01-20020 January 1990 Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl ML20006A8001990-01-19019 January 1990 Forwards Response to NRC 891220 Ltr Re Violations Noted in Plant Insps.Response Withheld (Ref 10CFR73.21) ML16152A9091990-01-18018 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. W/900131 Release Memo ML19354E6331990-01-18018 January 1990 Responds to NRC 891222 Ltr Re Violations Noted in Insp of License R-116.Corrective Actions:All 13 Required Aspects for Each Licensed Individual Will Be Examined on Single Day & Retraining Performed Until Deficient Item Correct 1999-03-25
[Table view] Category:EDUCATIONAL INSTITUTION TO NRC
MONTHYEARML20055G9271990-07-19019 July 1990 Provides Decommissioning Statement for Facility.Revised Estimates Will Be Reported to Commission at Intervals Not to Exceed 5-yrs ML20043H2191990-06-0505 June 1990 Forwards Updated Version of Physical Security Plan.Alarm Reporting Sys Redescribed to Agree W/Changes in Instrumentation Made Over Last 2 Yr Period.W/O Encl ML19354E6331990-01-18018 January 1990 Responds to NRC 891222 Ltr Re Violations Noted in Insp of License R-116.Corrective Actions:All 13 Required Aspects for Each Licensed Individual Will Be Examined on Single Day & Retraining Performed Until Deficient Item Correct ML20005G1241989-12-18018 December 1989 Responds to Violations Noted in Exam Rept 50-326/OL-89-01. Corrective Action:Use of Lower Ranges of Linear Channel Will Be Fully Investigated & Mode Switch Electrical Transients Will Be Cleaned & Examined ML19324B4361989-10-25025 October 1989 Responds to NRC 890927 Ltr Re Violations Noted in Insp of License R-116.Corrective Actions:Reactor Daily Startup Checklist Modified to Require Reactor Operators to Verify Completion & Signoff of Appropriate Checklists ML19324B4391989-05-0505 May 1989 Informs That Reactor Operations Committee for Univ of California,Irvine Nuclear Reactor Facility Failed to Meet During 880818-890131,in Violation of Tech Specs,Due to Routine Operations Discontinued,Including Staff Reduction ML20195C1421988-06-13013 June 1988 Informs That Dk Gehmlich,Associate Dean for Academic Affairs,Replaced Re Stephenson as Reactor Administrator Effective on 880609.Current Membership of Reactor Safety Committee Listed ML20151G4091988-04-0404 April 1988 Responds to NRC Re Violations Noted in Insp Rept 50-326/88-01.Corrective Actions:Review Sheet Being Created to Assure Review of All Checklists During Insps & Reactor Supervisor & Radiation Safety Officer Reviewed Issues ML20151A3451988-03-0303 March 1988 Informs That Listed Personnel Make Up New Reactor Operations Staff at Triga (R-126) & Agn (R-25) Reactors ML20235B8211987-08-0707 August 1987 Requests That Sending of Unneeded Circular Info Be Discontinued.School No Longer Has Nuclear Reactor ML20207R8261987-03-0202 March 1987 Forwards Ltr Requesting Commission to Review Director'S Decision DD-87-02,per 2.206 (c)(1),to Determine If Director Grossly Abused Discretion by Misrepresenting Petition,Not Responding to Important Points & Deceiving Petitioners ML20206G9281987-02-0606 February 1987 Discusses Scoping Analysis for Direct Heating in Plant. Analysis of Plant Containment Continuing.Aim to Develop Methodology That Can Be Used in Categorizing Other Containments ML20203G3381986-06-12012 June 1986 FOIA Request for Documents Re Reactor & Senior Reactor Operator Licensing Exam Results for Jan 1983 - Dec 1984 ML20141N3711985-12-17017 December 1985 Appeals Denial of FOIA Request for Four Categories of Documents Re Fraudulent Computer Programs ML20137B7751985-10-28028 October 1985 Responds to NRC Re Violations Noted in Insp Rept. Corrective Actions:Reactor Operations Committee Established Firm Schedule for Holding Meetings & Senior Reactor Operator Exams Will Be Conducted ML20138F5071985-10-25025 October 1985 FOIA Request for Four Categories of Documents Re Leak Rate Testing ML20141N2851985-10-21021 October 1985 Responds to 850927 Order to Show Cause Re Removal of Highly Enriched Fuel from Research Reactor.Indefinite Stay of Execution Requested for Listed Reasons,Per Item 3 of Order ML20141N2821985-10-0808 October 1985 Responds to 850927 Order to Show Cause Re Removal of Highly Enriched U to Secure Facility.No Unirradiated High Enriched U Kept on Hand ML20147E7671984-09-24024 September 1984 Forwards INPO Accreditation:Board Members Perspective, Presented at ANS 1984 Annual Meeting in New Orleans.Proposed Rule Should Contain Min Requirements to Avoid Discouraging INPO Initiatives ML20095E9131984-08-20020 August 1984 Ack Receipt of Re Proposed Research Reactor Emergency plan.Sixty-day Extension of Deadline for Response to Questions Raised by NRC Requested ML20128N9521984-04-30030 April 1984 Forwards Comments Re Quest Study of Surry Tmlb Scenario. Clarification Needed Re Where Data Obtained for Solid Triangle (Sascha) Data Points in Figure A-3 ML20210E6661984-02-27027 February 1984 Forwards Newspaper Ad Re Reasons for 840211 Civil Disobedience Over Plant Emergency Plan ML20210E7141984-02-0101 February 1984 Provides General Concept of Evacuation Time Estimates Re Baseline Scenarios Such as Normal & Adverse Weather.Time Estimates Technically Sound & Based on Best Available Data ML20210E7101984-01-30030 January 1984 Forwards Repts on Fog & Rain.Copies of Questions on Plant & Responses to Date Requested.W/O Encls ML20210E6701984-01-0909 January 1984 Ack 831230 Response to Concerns Over Emergency Response Plan at Plant,Including FEMA Response from R Vickers.Fema Response Inadequate Re Evacuation Time Considerations & Evacuation Routes ML18089A4731983-12-20020 December 1983 Forwards Summary of Facility Evacuation Time Estimates Based on Review Against NUREG-0654,Rev 1.No Deficiencies Noted ML20210E7001983-12-0909 December 1983 Ack 851202 Response to Re Concerns in Emergency Response Plans.Concerns Expressed Re Rebuilding of Twin Bridges & Siren Backup ML20210E6841983-11-0404 November 1983 Forwards Examples from Newspaper Re Concerns Over Plants Emergency Response Plan ML20081J1571983-10-31031 October 1983 Requests All Interested NRC Branches Be Made Aware of Changes in Mailing Address for Univ.Mail Continues to Be Sent to Old Mailing Address Which Delays Internal Distribution ML20065B4901983-02-0202 February 1983 Responds to NRC Re Violations Noted in IE Insp Rept 50-326/82-04.Corrective Actions:Reactor Operations Committee Met on 821202 & 830107.Future Meetings Will Be Held on Schedule ML20066G4131982-11-0202 November 1982 Forwards Public Version of Revision 0 to Emergency Plan ML20055C1551982-08-0606 August 1982 Notifies of Change in Administrative Personnel.Future Official Communications Re Licensing Matters Should Be Addressed to Wj Lillyman,Vice Chancellor ML20062D7871982-07-30030 July 1982 Forwards Annual Rept for Jul 1981-June 1982,License:R-116 ML20105B3561982-06-0101 June 1982 Submits Rept Re Security Incident in Response to 10CFR73.71(c) Detailing Loss of Security Effectiveness, Responses Made & Efforts to Revise Sys & Procedures to Reduce Chance of Recurrence.Portions Deleted ML20054L8021982-05-0707 May 1982 Responds to NRC Re Violations Noted in IE Insp Rept.Corrective Actions:Std Operating Procedures Revised & Fuel Element Handling Tool Will Be Padlocked & Key Retained by Reactor Supervisor ML20005B6011981-06-30030 June 1981 Forwards Response to 810619 Request for Addl Info Re Revision 1 to Physical Security Plan.Info Withheld (Ref 10CFR2.790) ML19343D3371981-04-27027 April 1981 Forwards Revised Physical Security Plan for License R-116. Plan Withheld (Ref 10CFR2.790) ML19341C4401980-12-24024 December 1980 Responds to NRC 801208 Ltr Re Violations Noted in IE Insp Rept 50-326/80-02.Corrective Actions:Escort Provided to Any Person Required to Perform Work in Facility Which Is Not Directly Associated with Radiation Producing Device ML20148K0891980-11-24024 November 1980 Forwards Executed Amends 8 to Indemnity Agreements E-16 & E-53.Amend 8 Supersedes Amend 7,therefore Execution of Superseded Amends Not Necessary ML19340C1721980-11-0505 November 1980 Repts Two Changes in Administrative Personnel & Const & Occupation of Addl Living Spaces on Campus.Forwards Map Showing Current Status of Residential Occupancy.Const Is in Accordance W/Mar 1968 SAR ML19340C1091980-10-31031 October 1980 Informs That Endorsements,Indemnity Agreements or Most Current Amends Have Not Been Received & Requests Provision of All Referenced Agreements ML19344F1411980-08-21021 August 1980 Responds to NRC 800812 Ltr Re Violations Noted in IE Insp Rept 50-326/80-01.Corrective Actions:Operating Procedure Revised to Include Annual Review of Reactor Operational Records ML19344F1431980-07-24024 July 1980 Responds to NRC 800703 Ltr Re Violations Noted in IE Insp Rept 50-326/80-01.Corrective Actions:Reactor Operations Committee Will Establish Regular Schedule for Review of Facility Operations & Schedule Quarterly Committee Meetings ML19320B9951980-07-0808 July 1980 Forwards Annual Rept for Period 790701-800630. 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 ML20064J7701979-08-15015 August 1979 Forwards Info in Response to 790730 Request.Info Withheld (Ref 10CFR2.790) ML19248D2101979-08-0606 August 1979 Forwards Annual Operating Rept Jul 1978-June 1979 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 ML19276F1351979-03-21021 March 1979 Submits Annual Rept for Triga Reactor for Jul 1977-June 1978.Because Rept Is Late,Includes Matl Related to Unloading & Reloading of Reactor from Oct & Nov 1978 ML20064G0051978-10-23023 October 1978 Forwards Incident Rept on 780928 Involving Finger Dosimeter Ring Dropped Into Reactor Core.Present Status:Ban on Reactor Oper Pending Decision on Whether Removal of Objects Below the Core Should Be Attempted 1990-07-19
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20197J7101998-12-0707 December 1998 Responds to Recent Telcon in Which NRC Requested Clarification of Few Items Re Request for Amend to TS for Univ of Ca,Irvine Triga Reactor ML20199L6461997-11-29029 November 1997 Forwards Licensee Rept of Items of TS non-compliance & Facility Annual Rept for 960701-970630 ML20199L6571997-11-29029 November 1997 Informs of Several Violations of TS at Facility.Corrective Actions:Full Insps & Recalibrations Have Been Carried Out & Specific Schedule Established & Posted in Facility Detailing Dates of Required Surveillance Activities Projected ML20100E5021996-02-12012 February 1996 Responds to Violations Noted in License R-116.Corrective Actions:New Channel Instruments Designed to Provide Normally Closed Set of Contacts Initiated by bi-stable,providing Same Scram & Interlock Functions as Equipment ML20094S3951995-11-29029 November 1995 Informs of Omissions Found During Review of Records in Conjunction w/on-site Insp by Region IV Re Implementation of Operator Requalification Plan ML20091L3721995-08-13013 August 1995 Forwards Univ of CA Irvine Nuclear Reactor Facility Annual Rept for Jul 1994 - June 1995. Error Identified in Distribution of Previous Annual Rept.Rept for Jul 1993 - June 1994 Encl.W/O Jul 1993 - June 1994 Rept ML20065L7601994-04-12012 April 1994 Informs That Reactor Operations Committee for Facility Failed to Meet in Period 930624-1217,in Violation of Requirements in TS Section 6.2f Due to Lack of Urgent Business,Heavy Staff Teaching Loads & Busy Schedules ML20058K0841990-11-26026 November 1990 Advises of Changes Re Identity of Individuals in Administration Chain ML20055G9271990-07-19019 July 1990 Provides Decommissioning Statement for Facility.Revised Estimates Will Be Reported to Commission at Intervals Not to Exceed 5-yrs ML20043H2191990-06-0505 June 1990 Forwards Updated Version of Physical Security Plan.Alarm Reporting Sys Redescribed to Agree W/Changes in Instrumentation Made Over Last 2 Yr Period.W/O Encl 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 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) 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 ML20006E4201990-02-14014 February 1990 Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 ML20011E6151990-02-12012 February 1990 Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21) ML20011E5571990-02-0808 February 1990 Forwards Us Bankruptcy Court for Eastern District of Tennessee Orders & Memorandum on Debtors Motion to Alter or Amend Order & Opinion Re Status of Sales Agreement Between DOE & Alchemie.Doe Believes Agreement Expired on 890821 ML20011E4991990-02-0606 February 1990 Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested ML20011E5981990-02-0505 February 1990 Requests That Listed Individuals Be Deleted from Svc List for Facilities.Documents Already Sent to Dept of Environ Protection of State of Nj ML20006D6911990-02-0202 February 1990 Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle ML20006C5661990-01-31031 January 1990 Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants 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 ML20006C6711990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Plants Have Established Preventive Maint Program for Intake Structure & Routine Treatment of Svc Water Sys W/Biocide to Control Biofouling ML20006B7961990-01-29029 January 1990 Forwards Summaries of Latest ECCS Evaluation Model Changes ML18153C0951990-01-29029 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Belief in Appropriateness to Address Generic Ltr 89-13 Concerns within Context of Established Programmatic Improvements Noted 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 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 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 ML17347B5451990-01-24024 January 1990 Informs of Plans to Apply ASME Code Case N-356 at Plants to Allow Certification Period to Be Extended to 5 Yrs.Rev to Inservice Insp Programs Will Include Use of Code Case ML19354E6711990-01-24024 January 1990 Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226 ML19354E4451990-01-22022 January 1990 Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters ML19354E4461990-01-22022 January 1990 Forwards Proprietary Rev 1 to DPC-NE-2001, Fuel Mechanical Reload Analysis Methodology for MARK-BW Fuel, Adding Section Re ECCS Analysis Interface Criteria & Making Associated Administrative Changes.Rev Withheld ML20005G7161990-01-20020 January 1990 Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl ML20006A8001990-01-19019 January 1990 Forwards Response to NRC 891220 Ltr Re Violations Noted in Plant Insps.Response Withheld (Ref 10CFR73.21) ML19354E6331990-01-18018 January 1990 Responds to NRC 891222 Ltr Re Violations Noted in Insp of License R-116.Corrective Actions:All 13 Required Aspects for Each Licensed Individual Will Be Examined on Single Day & Retraining Performed Until Deficient Item Correct ML16152A9091990-01-18018 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. W/900131 Release Memo ML18153C0771990-01-17017 January 1990 Forwards North Anna Power Station Emergency Plan Table 5.1, 'Min Staffing Requirements for Emergencies' & Surry... Table 5.1, 'Min Staffing Requirements...', for Approval,Per 10CFR50.54(q),NUREG-0654 & NUREG-0737,Suppl 1 ML20006A2011990-01-16016 January 1990 Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel in Anchor Darling Swing Check Valves.Eight Subj Valves Identified in Peach Bottom Units 1 & 2 & Will Be Returned to Mfg ML20006A6241990-01-16016 January 1990 Forwards Draft Qualified Master Trust Agreement for Decommissioning of Nuclear Plants,For Review.Licensee Will Make Contributions to Qualified & Nonqualified Trust as Appropriate ML18153C0731990-01-15015 January 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or or Valves.... Util Replaced Studs in twenty-five Valves ML20006B8821990-01-10010 January 1990 Reissued Ltr Correcting Date of Util Ltr to NRC Which Forwarded Updated FSAR for Byron/Braidwood Plants from 881214 to 891214.W/o Updated FSARs ML20006A8201990-01-10010 January 1990 Forwards Errata to Rev 3 to BAW-1543,Tables 3-20 & E-1 of Master Integrated Reactor Vessel Surveillance Program Reflecting Changes in Insertion Schedule for A5 Capsule for Davis-Besse & Crystal River ML20005G6431990-01-10010 January 1990 Responds to Generic Ltr 89-21 Re Implementation of USI Requirements,Consisting of Revised Page to 891128 Response, Moving SER Ref from USI A-10 to A-12 for Braidwood ML20005G7601990-01-0404 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Plan. Privacy Info Should Be Deleted Prior to Placement in Pdr.W/ D Grimsley 900118 Release Memo 1998-12-07
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June 1, 1982 U. S. Nuclear Regulatory Commission Division of Human Factors Safety Operator Licensing Branch Washington, D. C. 20555 Gentlemen:
Please find enclosed a report on a security incident submitted in response to Federal Regulations 10CFR 73.71(c) . The repcrt attempts to detail the occurrence of the loss of security eff ectiveness, the responses made, and our ef forts to revise systems and procedures to reduce the chance of a recurrence.
We are aware that this report is late by the criteria necessary for
- report of moderate loss of effectiveness which has not been compensated for. As noted below, we f eel that there are miticatinc circumstances in this case which lead to uncertainty as to how much compensation is j required to fall into the non-reportable categcry.
We wish to point out the following important it ems :
- l. All evidence shows that there have been no breaches of security, l
no unauthorized activities and no threat whatsoever of material diversion.
2.
elements do not necessarily meet the "self-protect:.ng criteria" as defined by NRC, they are all highly radioactive, and not handleable with saf ety or without detection by radiation monitoring eculpment.
- 3. The present authqrized security plan for the f acilitywas submitted in July, 1974, following recuests for chan in the clan from NRC in June, 1974. This clan does described under " surveillance" section. .
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.Q eC H U. S. Nuclcnr R gulotory Commiccion Pego 2 June 1, 1982
- 4. A revised security plan was submitted to NRC on April 27th, 1981.
Additional comments were submitted on June 30th, 1981 in response to a request from NRC dated June 19th, 1981. No response has been received from NRC since that date, with the exception of a brief telephone request from Carol Rossomondo regarding clarification of personnel qualifications for admittance to the facility. This latter was in May, 1982.
- 5. On the advice of Region V NRC personnel, and under the guideline that we were increasing the level of security we croceeded with installation of the hardware and aspects of the revised security plan, and these nave oeen s stantially completed for some time. We have not completed documentation of procedures, nor any formal retraining of personnel for the new plan, pending further revision.
- 6. In response to a perceived difficulty with the new plan, emphasized by this incident, we are proceding to make additional changes -
further increasing the level of security. These changes will necessitate minor revisions in the new security plan. These revisions are being prepared and will be submitted to NRC very shortly. These
- hanges address the issue of system reliability, " compensation" for loss of system effectiveness, and improve the communication beyond the current level.
- 7. We believe our present system already exceeds the requirements f or a low strategic significance f acility as given in 73.67 (a).
- 8. The incident has identified the need for changes in some of our procedures in implementation of the new plan. Some of these are detailed in the attachment.
We submit this report in the belief that the major difficulties with operation of security at our facility, pointed out by this incident, have been identified and are being addressed so as to minimize the probability of a similar incident occurring.
At the time of submitting this report, security is back at the level existing prior to the incident.
I In our discussions, we have chosen to focus on improvements to be made.
The history of the incident is discussed only as it relates to identi-fication of problems with security operations, since no actual security breach occurred.
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I F. S. Rowland Reactor Administrator N hM G. E. Miller l Reactor Superviscr i RM/km .
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UCI TRIGA Nuclear Reactor Facility Security Incident Report. Period 4/1/82-6/1/82 Report Date 6/2/82 Description of event.
On approximat til 1st, problems devel wi t 4
1 spate point.
i ese pro ems resu ted in removal o the unit for service a few days' l
i later.
On the week-end of May 1st, the Reactor Supervisor became aware that the was not in operation, and began preliminary contact with t on Monday, May 3rd. By Thursday, May 6th, the supervisor had been made aware tha l
On Monday, May 10th, now that matters locally were in order, the Reactor
- Supervisor called NRC to report the possible moderate loss of security effectiveness as a historical event.
! The was placed back in service sometime around May 25th and proper checks conducted as to comunications between the systems.
The security at the facility had, all this time, kept l complete track o a even s - entries, exits, movement, radiation e.larm i occurrences, etc. The system has to be manually reset following any untoward incident. No manual resets were needed in this period. All
- fuel elements in inventory were still in place in the Thus no actual security breach had occurred or had been attemp e .
Discussion.
Problems had been occurring with the system for l'
a while, but all had been quickly re onvec aise a ams, etc). As far as facility staff is aware, no attemot was made to infom the facilit that the system was to be removed from service for repair, and no I
g were initiated prior to May 6th, i
Personnel at the facility enter and leave on a frequent, but random basis.
A complete record ess and realam and t i is recorded on a 1
1
.i *ii
! ca or 7-6/1/82. t wouto oe possi se e" through
! this log and record every time period inat the facility was unoccupied.
l This exercise is clearly not worth it since no security breach occurred.
l Further Actions.,
The following actions have been taken or are being planned. A brief analysis of the reason for each action is also included here.
- 1. Installation of a nit has comenced.
- This unit will, on t a siana ro j iine. he unit w111 als i
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. Incident Report,6/2/82
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Page 2.
Further actions (continued)
Since the was not described as part of our new plan, I a plan revi n is being prepared for submittal as soon as ossible to l cover this. It is our intent that both systems should remain in operation when possi e. In the event o al ure of n or the other, reporting
^
capability would be maintained. would be initiated only if both units fail.
- 2. A procedure for more fr ki of l the comunications link is being prepared and will be imp emente as soon as possi e. he exact ,
frequency is still under discussion, but would not be less frequently than In the interim,M will be made.
- 3. A procedure for recycling of '
M output on a basis such that recorcs or at east can be researched has been established.
- 4. A recuest has been made for setting up discussions with the M ,
M with the aim of initiating personnel training sessions at which the full new plan will be implemented. Such procedures will include the need for adequate reporting of trouble with systems and for implementation of as soon as system difficulties are identified. We aim to carry out a complete review of all procedures relevant to the new plan. It will be helpful if we can finalize this plan and assume that new revisions will not be iminent, except at our initiative.
As noted, we are of the opinion that these actions will greatly reduce the chance of a recurrence of this situation. We hope to have all phases of these improvements implemented within 30 days.
G.E. Miller, Reactor Supervisor Department of Chemistry 1
l
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