ML20138A752
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| ML20138A752 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point, River Bend, 05000000 |
| Issue date: | 10/08/1985 |
| From: | Baer R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | Denham F LIMITORQUE CORP. |
| References | |
| NUDOCS 8510090492 | |
| Download: ML20138A752 (1) | |
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L7971999-10-20020 October 1999
[Table view]Submits Results of Review of 990521 & 0709 Ltrs Which Provided Core Shroud Insp Results & Tie Rod Stabilizer Assemblies ML20217L7681999-10-19019 October 1999 Forwards Insp Rept 50-458/99-12 on 990822-1002.Four Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy RBG-45125, Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams1999-10-18018 October 1999 Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams ML20217J3751999-10-15015 October 1999 Informs That Applicable Portions of NEDC-32778P, Safety Analysis Rept for River Bend 5% Power Uprate, Marked as Proprietary Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) ML20217G1291999-10-15015 October 1999 Forwards Errata to Safety Evaluation for Amend 168 Issued to FOL DPR-63 on 990921.Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20217K2831999-10-14014 October 1999 Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001 ML20217H3211999-10-0808 October 1999 Forwards Changed Pages for Issue 5,rev 1 of Nine Mile Point Station Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p).Without Encls ML20212K8601999-10-0606 October 1999 Responds to Concern in 990405 Petition Re Residual Heat Removal Alternate Shutdown Cooling Modes of Operation at Nine Mile Point Nuclear Station,Unit 2 IR 05000458/19990071999-10-0505 October 1999 Refers to Util Ltr Re Apparent Violations Described in Insp Rept 50-458/99-07 Issued on 990804 & Forwards Nov.Insp Described Two Apparent Violations Related to River Bend Station Division I EDG ML20212K8641999-09-30030 September 1999 Informs That During 990927 Telcon Between J Williams & J Bobka,Arrangements Were Made for Administration of Exams at Plant During Wk of Feb 14,2000.Preliminary RO & SRO License Applications Should Be Submitted 30 Days Prior Exam ML20212J8831999-09-30030 September 1999 Informs That Util 980810 & 990630 Responses to GL 98-01 & Suppl 1, Y2K Readiness of Computer Sys at NPPs Acceptable. NRC Considers Subj GL to Be Closed for Plant ML20212J4651999-09-30030 September 1999 Informs of Completion of mid-cyle PPR of Nine Mile Point Nuclear Station on 990916.Determined That Problems in Areas of Human Performance & Work Control Required Continued Mgt Attention.Historical Listing of Plant Issues Encl ML18040A3701999-09-30030 September 1999 Provides Changes to Application for Amend Re Volumes 1-11 of 981016 Submittal & Discard & Insertion Instructions Re Integration of Proposed Changes,In Response to NRC RAIs ML20216J9311999-09-30030 September 1999 Forwards Response to NRC 981119 Suppl RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions RBG-45123, Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required1999-09-30030 September 1999 Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required RBG-45124, Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl1999-09-24024 September 1999 Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl RBG-45122, Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-471999-09-23023 September 1999 Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-47 ML20212E9801999-09-23023 September 1999 Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03 RBG-45113, Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp1999-09-21021 September 1999 Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp ML20216F7101999-09-17017 September 1999 Forwards Response to NRC 990806 RAI Re USI A-46,verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.Nrc Is Informed That Actions Required for Resolution of USI A-46 Have Been Completed ML20212D8901999-09-16016 September 1999 Discusses 6 Month Review of Plant Midcycle Ppr.Advises of Plans for Future Insp Activities.Forwards Historical Listing of Plant Issues,Referred to as PIM ML20216F7881999-09-15015 September 1999 Forwards Insp Rept 50-458/99-10 on 990830-990903.No Violations Noted.Insp Covered Licensed Operators Requalification Training Program & Observation of Requalification Activities ML20212D8981999-09-14014 September 1999 Forwards ISI Summary Rept for Refueling Outage 15 & Flaw Indication Repts.Supporting Info Repts & Calculations, Encl ML20212B2821999-09-14014 September 1999 Responds to 990712 Correspondence Which Responded to NRC Ltr Re High Failure Rate for Generic Fundamentals Exam of 990407 for Nine Mile Point.Considers Corrective Actions Taken to Be Acceptable ML20212B2581999-09-10010 September 1999 Requests That Name of Bm Bordenick Be Removed from Nine Mile Point,Units 1 & 2 Service List ML20211P5771999-09-10010 September 1999 Forwards Application for Amends to Licenses DPR-63 & NPF-69, to Transfer Licenses to Amergen Energy Co,Llc.Ts Pages & Proprietary Addendum,Included.Proprietary Encl Withheld ML20211Q7721999-09-0909 September 1999 Expresses Appreciation for ,In Response to NRC 990702 Re Denial of Notice of Violation Cited in Concerning Insp Rept 50-458/98-16.Reply Found to Be Responsive to Concerns Raised in NOV 05000458/LER-1998-003, Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents1999-09-0909 September 1999 Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents ML20211Q3921999-09-0808 September 1999 Forwards Insp Rept 50-458/99-08 on 990711-0821.One Violation Being Treated as Noncited Violation ML20211Q5541999-09-0808 September 1999 Discusses Meeting Conducted on 990830 in St Francisville,La Re Overall Performance Issues During 990403-0703 Refueling/ Maintenance Outage.Due to Proprietary Nature of Some Subject Matters,Meeting Closed to Public.Attendance List Encl RBG-45109, Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted1999-09-0808 September 1999 Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted RBG-45095, Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status1999-09-0707 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20212A1341999-09-0707 September 1999 Forwards Summary Rept Secondary Containment Leakage Testing, Dtd June 1999 for Nine Mile Point,Unit 1,IAW TS 6.9.3.f ML20211L9221999-09-0101 September 1999 Confirms That Licensee Will Retain Weld 32-WD-050 as IGSCC Category F Until Completion of Reinspection Program,In Response to NRC ML20211K8141999-09-0101 September 1999 Forwards Reactor Containment Bldg Ilrt,Iaw Plant TS 6.9.3.e.Testing Confirmed That TS 3.3.3/4.3.3 & 6.16 Primary Containment Leakage Requirements Were Satisfactorily Met RBG-45097, Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves1999-08-31031 August 1999 Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves ML20211K5031999-08-30030 August 1999 Responds to Ltr Addressed to Chairman Dicus, Expressing Concerns Involving 990624 Automatic Reactor Shutdown.Insp Findings & Conclusions Will Be Documented in Insp Repts 50-220/99-06 & 50-410/99-06 by mid-Sept 1999 ML20211K3001999-08-30030 August 1999 Forwards Semi-Annual Radioactive Effluent Release Rept for 990101-990630 & Revised ODCM, for Nine Mile Point,Unit 1. Format Used for Effluent Data Is Outlined in App B of Regulatory Guide 1.21,rev 1 ML20211J6461999-08-30030 August 1999 Forwards Response to NRC 990625 RAI Re NMPC Responses to GL 92-01,rev 1,supplement 1, Reactor Vessel Structural Integrity ML20211H1921999-08-26026 August 1999 Forwards Application for Amend to License DPR-63,supporting Implementation of Noble Metal Chemical Addition by Raising Reactor Water Conductivity Limits in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b ML20211G4921999-08-26026 August 1999 Advises That Info Re Comments Addressing 10CFR2.206,dtd 990405 Will Be Withheld from Public Disclosure,In Response to ML20211P5161999-08-26026 August 1999 Discusses Submitted on Behalf of Niagara Mohawk Power Corp Written Comments Addressing 10CFR2.206 Petition & Request That Ltr & Attached Response Be Withheld from Public Disclosure.Request Denied RBG-45094, Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation1999-08-25025 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation ML20211E2071999-08-23023 August 1999 Discusses Insp Rept 50-458/99-07 in Which 2 Violations Were Identified & Being Considered for Escalated Enforcement Action.Response Should Be Submitted Under Oath or Affirmation ML20211D7731999-08-20020 August 1999 Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20211B9371999-08-18018 August 1999 Provides Addl Info Re Application of Method a at Nmp,Unit 1 as Described in Generic Implementation Procedure,Rev 2 (GIP-2),NRC Supplemental SER 2 & Documents Ref in GIP-2 Upon Which GIP-2 Is Based RBG-45093, Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept1999-08-17017 August 1999 Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept ML20211A9291999-08-17017 August 1999 Forwards Insp Rept 50-458/99-11 on 990719-23.Areas Examined Included Portions of Licensee Physical Security Program. No Violations Noted 1999-09-09 Category:NRC TO VENDOR/MANUFACTURER MONTHYEARML20246C7101989-08-18018 August 1989
[Table view]Forwards Order,Effective Immediately,Modifying CPs CPEP-1 & CPEP-2 to Require Notification of Commission Before Taking Possession of Any Classified Equipment & to Show Cause Why CPs Should Not Be Revoked ML20246P0181989-07-17017 July 1989 Forwards Request for Addl Info Re 890620 Filing for Reorganization in Us Bankruptcy Court.Nrc Will Initiate Proceeding for Suspension or Revocation of CPs Should Licensee Fail to Respond by 890815 ML20246P4171989-03-23023 March 1989 Advises That 890210 Condition III.6 of CP Issued to Alchemie Re Financial Assurances for Protection of Common Defense & Security by Control of Classified Machinery Not Applicable ML20235N9801989-02-22022 February 1989 Forwards Notices of Issuance of CPs for Alchemie Centrifuge Plan Demonstration & Oliver Springs Facilities ML20205T5991988-11-0707 November 1988 Requests Survey of Proposed Oliver Spring Site to Look for Evidence of Threatened or Endangered Species ML20205T6961988-11-0303 November 1988 Notifies of 890110 Meeting W/Region V in San Francisco,Ca to Discuss NRC Reactor Operator Licensing Program in Region ML20205R7171988-11-0303 November 1988 Requests 880912 Submittal Re Ability to Assure Funding for Decontamination Over Entire Period of License Be Revised. NRC Expects That Sale of Unneeded,Unclassified Matl Will Realize Sufficient Funds to Cover Costs of Removal of Matl ML20205M9061988-10-28028 October 1988 Advises That Addendum 2 to WCAP-10988, COBRA-NC,Analysis for Main Steamline Break in Catawba Unit 1 Ice Condenser Containment, Forwarded by Will Be Withheld from Public Disclosure,Per Request ML20205L0381988-10-27027 October 1988 Informs That WCAP-11935, McGuire 2 - Evaluation for Tube Vibration-Induced Fatigue Will Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20205Q5661988-10-25025 October 1988 Forwards SERs Re Company 871117 Application for Authority to Construct & Operate Facilities to Enrich Stable Isotopes at Facility-1 Cpdf & to Construct Facility for Same Purpose at Facility-2 Oliver Springs ML20154E7171988-09-0808 September 1988 Forwards Notice of Issuance of Environ Assessment & Finding of No Significant Impact & Environ Assessments Re 871107 Application to Construct & Operate Facility for Enriching Stable Isotopes ML20153B1541988-03-15015 March 1988 Informs of Relocation of NRR to Stated Address in Rockville, MD ML20148B5101988-03-15015 March 1988 Informs of Relocation of NRR to Stated Address in Rockville,Md ML20235T2431987-09-24024 September 1987 Forwards Insp Repts 50-018/87-01,50-070/87-01,50-073/87-01 & 50-183/87-01 on 870901-03 & Notice of Violation ML20214M6631987-05-22022 May 1987 Forwards Revised NRC Form 398.Rev Reflects Changes to 10CFR55 Effective on 870526.Revised Form Requires New Applications to Complete Each Category Including Educ, Training & Experience.Changes Detailed in Encl 2 ML20205L6971987-03-27027 March 1987 Requests Further Info & Documentation Re Steam Generator Tube Vibration Problem for Generic CESSAR Sys 80 Steam Generator Design by 870410.Specific Questions Re Request Encl ML20207H6641986-07-22022 July 1986 Ack Receipt of 860508 Application for Approval of Transfer of Ga Co Control for Licenses R-38,R-67 & SNM-0696. Application Fee Required ML20199F2211986-02-19019 February 1986 Further Response to FOIA Requests for Documents Re Humboldt Bay File Up to 761231,Bodega Bay file,4x4 Test Info & Wuergassen Plant 1972 Incident.Forwards App J Documents.App J Documents Withheld Due to Proprietary Nature ML20140F3691986-01-14014 January 1986 Further Response to FOIA Request for Several Categories of Documents Re Pressure Suppression Containment.Fsar & SER for Limerick Only Documentation Re 4x4 Tests.Encl Apps D-G Documents Responsive to Item 4 Also Available in PDR ML20137C5151986-01-13013 January 1986 Forwards Summary of Changes & Revised Pages Incorporating Changes to Braidwood Draft Tech Specs.Byron Tech Specs Should Address diesel-driven Essential Svc Water Makeup Batteries.Amend Request Will Be Needed ML20239A1971985-12-17017 December 1985 Further Response to 850927 & 1106 FOIA Requests for Documents Re Pressure Suppression Containment,Including Humboldt Bay & Bodega Bay Docket Files.Bodega Bay File Being Placed in Pdr.Review of Addl Documents Continuing ML20138A7521985-10-0808 October 1985 Requests Listing of Customers Purchasing or Ordering Valve Operators Containing Magnesium Motor Rotors.Test Anomalies Have Raised Concern Re long-term Availability of Valve Operator Motors W/Magnesium Rotors ML20133B2801985-07-29029 July 1985 Approves 841219 & 21 Requests for Withholding CAW-84-117, Equipment Justification for Interim Operation - Wolf Creek Generating Station,Unit 1 & Callaway Station,Unit 1, from Public Disclosure,Per 10CFR2.790 ML20126C1121985-06-10010 June 1985 Approves Request That WCAP-10553, Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Byron Units 1 & 2 & Braidwood Units 1 & 2, Be Withheld (Ref 10CFR2.790) ML20128L5161985-05-22022 May 1985 Concludes That 1985 Financial Info,Per 850419 Submittal, Satisfies 10CFR140.21,requiring That Each Licensee Maintain Approved Guarantee of Payment of Deferred Premiums for Each Operating Reactor Over 100 Mw(E) ML20129B2161985-05-20020 May 1985 Approves 841018 & 830926 Requests for Withholding WCAP-10690 & WCAP-10691, Technical Bases for Eliminating Large Primary Loop Pipe Rupture..., from Public Disclosure Per 10CFR2.790 ML20137G9831983-12-0909 December 1983 Notifies of 840111 Meeting in Shiller Park,Il to Discuss Scheduling Problems Re Exam Process & Examiner Stds, (NUREG-1021).Attendee Names & Addl Discussion Subjs Should Be Submitted by 831219.Preliminary Agenda Encl ML20137G9721983-07-22022 July 1983 Advises That Region III Telephone Number Will Be Changed Effective 830822.New Number Listed.Notice of Change Will Appear in Fr Prior to 830822 ML20055A4331982-06-16016 June 1982 Discusses Alternative Methods for NRC to Conduct Confirmatory Analyses of Westinghouse NSSS Designed NSSS W/O Involvement of OL Applicants.Transient & Accident Evaluation Performed on Generic Basis Generally Acceptable ML20054E8951982-06-0707 June 1982 Approves Request for Withholding Info Per 10CFR2.790 Re Improved Thermal Design Procedures (CAW-82-15) ML20137G8881981-08-28028 August 1981 Forwards IE Info Notice 81-26, Compilation of Health Physics Related Info Items. Five Items of Info That Generally Have Impact on Areas Normally Under Responsibility of Health Physics Group Listed ML20137G5071981-07-31031 July 1981 Forwards IE Info Notice 81-22, Section 235 & 236 Amends to Atomic Energy Act of 1954, Which Should Be Brought to Attention of Employees & Others Involved in NRC-licensed Activities.No Response Required IR 05000264/19790031979-12-0505 December 1979 Forwards Insp Rept 50-264/79-03 on 791022-24 & Notice of Violation ML20137H0401979-11-0909 November 1979 Forwards IE Info Notice 79-12A, Attempted Damage to New Fuel Assemblies. No Response Requested ML20137H0341979-10-17017 October 1979 Submits New Telephone Number for Region Iii,Effective 791022 ML20137H0031978-08-11011 August 1978 Ack Receipt of 780727 Response to Notice of Violation ML20137H0221978-06-12012 June 1978 Forwards IE Bulletin 78-08, Radiation Levels from Fuel Element Transfer Tubes ML20137H1121978-02-0606 February 1978 Confirms 780202 Telcon Re Meeting Between NRC & Dow Chemical Co on 780207 at Facility to Discuss Results of Physical Security Insp on 780110-12 ML20137H3941977-11-21021 November 1977 Forwards Amend 3 Renewing License R-108 & Incorporating Security Plan as License Condition.Safety Evaluation,Eia Notice of Issuance & Negative Declaration Also Encl.Security Plan Withheld (Ref 10CFR2.790) ML20137G9311977-08-18018 August 1977 Forwards Insp Rept 50-264/77-02 on 770719-22,26 & 27.No Noncompliance Noted ML20137H1161977-07-22022 July 1977 Ack Receipt of Informing of Recovery of 200-mCi Cs-137 Sealed Source from Brine Well on 770621 ML20137H2171977-07-18018 July 1977 Forwards IE Circular 77-10, Vacuum Conditions Resulting in Damage to Liquid Process Tanks ML20140F5801977-06-0606 June 1977 Advises That GE 770303 Conclusions That Leaking Safety/Relief Valves Would Result in Lower Loads on Structures than First Actuation W/O Leakage Unjustified,For Listed Reasons ML20137H3901977-04-15015 April 1977 Requests That Encl Notice Re Direct Accessibility of IE to Employees Concerned About Quality of Work,Radiological Safety or Safeguards at Facility Be Posted ML20137H3511976-12-17017 December 1976 Forwards IE Circular 76-03, Radiation Exposures in Reactor Cavities. Prompt Reply Requested.Original Submittal Forwarded on 760913 Not Received as Noted on 761214 ML20137H4101976-09-0101 September 1976 Requests That Encl Form Be Completed & Submitted by 760915 & Facility Emergency Plan & Implementing Procedures by 761007 in Order for NRC to Prepare Info Packets for Use in Responding to Incidents or Emergencies IA-85-256, Requests That Encl Form Be Completed & Submitted by 760915 & Facility Emergency Plan & Implementing Procedures by 761007 in Order for NRC to Prepare Info Packets for Use in Responding to Incidents or Emergencies1976-09-0101 September 1976 Requests That Encl Form Be Completed & Submitted by 760915 & Facility Emergency Plan & Implementing Procedures by 761007 in Order for NRC to Prepare Info Packets for Use in Responding to Incidents or Emergencies ML20234E7981976-07-0808 July 1976 Forwards List of Info Required to Complete Review of LWR ECCS Performance to Verify Conformance to 10CFR50.46.Info Must Be Filed on GESSAR-238 & GESSAR-251 Dockets as Part of Std SAR & Be Reviewed Prior to Preliminary Design Approval ML20235E5831976-07-0707 July 1976 Forwards Description of NRC Position on Safety Relief Valve Discharge Piping as Result of NRC Continuing Review of Quencher Safety Relief Valve Discharge Device for Facility. Commitment to Implement NRC Position Requested by 760716 ML20235C5631976-02-20020 February 1976 Informs That NRC Currently Reviewing Fuel Channel Hydrodynamic,Reactor Core Reactivity & Total Reactor Sys Stability Margins for Certain GE Bwrs.Addl Info Needed Re BWR Stability Margins Identified in Encl 1989-08-18 Category:OUTGOING CORRESPONDENCE MONTHYEARML20217L7971999-10-20020 October 1999
[Table view]Submits Results of Review of 990521 & 0709 Ltrs Which Provided Core Shroud Insp Results & Tie Rod Stabilizer Assemblies ML20217L7681999-10-19019 October 1999 Forwards Insp Rept 50-458/99-12 on 990822-1002.Four Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217G1291999-10-15015 October 1999 Forwards Errata to Safety Evaluation for Amend 168 Issued to FOL DPR-63 on 990921.Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20217J3751999-10-15015 October 1999 Informs That Applicable Portions of NEDC-32778P, Safety Analysis Rept for River Bend 5% Power Uprate, Marked as Proprietary Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) ML20212K8601999-10-0606 October 1999 Responds to Concern in 990405 Petition Re Residual Heat Removal Alternate Shutdown Cooling Modes of Operation at Nine Mile Point Nuclear Station,Unit 2 IR 05000458/19990071999-10-0505 October 1999 Refers to Util Ltr Re Apparent Violations Described in Insp Rept 50-458/99-07 Issued on 990804 & Forwards Nov.Insp Described Two Apparent Violations Related to River Bend Station Division I EDG ML20212K8641999-09-30030 September 1999 Informs That During 990927 Telcon Between J Williams & J Bobka,Arrangements Were Made for Administration of Exams at Plant During Wk of Feb 14,2000.Preliminary RO & SRO License Applications Should Be Submitted 30 Days Prior Exam ML20212J8831999-09-30030 September 1999 Informs That Util 980810 & 990630 Responses to GL 98-01 & Suppl 1, Y2K Readiness of Computer Sys at NPPs Acceptable. NRC Considers Subj GL to Be Closed for Plant ML20212J4651999-09-30030 September 1999 Informs of Completion of mid-cyle PPR of Nine Mile Point Nuclear Station on 990916.Determined That Problems in Areas of Human Performance & Work Control Required Continued Mgt Attention.Historical Listing of Plant Issues Encl ML20212D8901999-09-16016 September 1999 Discusses 6 Month Review of Plant Midcycle Ppr.Advises of Plans for Future Insp Activities.Forwards Historical Listing of Plant Issues,Referred to as PIM ML20216F7881999-09-15015 September 1999 Forwards Insp Rept 50-458/99-10 on 990830-990903.No Violations Noted.Insp Covered Licensed Operators Requalification Training Program & Observation of Requalification Activities ML20212B2821999-09-14014 September 1999 Responds to 990712 Correspondence Which Responded to NRC Ltr Re High Failure Rate for Generic Fundamentals Exam of 990407 for Nine Mile Point.Considers Corrective Actions Taken to Be Acceptable ML20211Q7721999-09-0909 September 1999 Expresses Appreciation for ,In Response to NRC 990702 Re Denial of Notice of Violation Cited in Concerning Insp Rept 50-458/98-16.Reply Found to Be Responsive to Concerns Raised in NOV ML20211Q3921999-09-0808 September 1999 Forwards Insp Rept 50-458/99-08 on 990711-0821.One Violation Being Treated as Noncited Violation ML20211Q5541999-09-0808 September 1999 Discusses Meeting Conducted on 990830 in St Francisville,La Re Overall Performance Issues During 990403-0703 Refueling/ Maintenance Outage.Due to Proprietary Nature of Some Subject Matters,Meeting Closed to Public.Attendance List Encl ML20211K5031999-08-30030 August 1999 Responds to Ltr Addressed to Chairman Dicus, Expressing Concerns Involving 990624 Automatic Reactor Shutdown.Insp Findings & Conclusions Will Be Documented in Insp Repts 50-220/99-06 & 50-410/99-06 by mid-Sept 1999 ML20211P5161999-08-26026 August 1999 Discusses Submitted on Behalf of Niagara Mohawk Power Corp Written Comments Addressing 10CFR2.206 Petition & Request That Ltr & Attached Response Be Withheld from Public Disclosure.Request Denied ML20211G4921999-08-26026 August 1999 Advises That Info Re Comments Addressing 10CFR2.206,dtd 990405 Will Be Withheld from Public Disclosure,In Response to ML20211E2071999-08-23023 August 1999 Discusses Insp Rept 50-458/99-07 in Which 2 Violations Were Identified & Being Considered for Escalated Enforcement Action.Response Should Be Submitted Under Oath or Affirmation ML20211A9291999-08-17017 August 1999 Forwards Insp Rept 50-458/99-11 on 990719-23.Areas Examined Included Portions of Licensee Physical Security Program. No Violations Noted ML20210T8881999-08-16016 August 1999 Forwards Replacement Pages 9-18 for Insp Rept 50-458/99-09, Issued on 990730 IR 05000458/19980101999-08-13013 August 1999 Forwards Summary of 990805 Mgt Meeting with Licensee in Arlington,Tx Re Radiological Control Problems Noted in Insp Repts 50-458/98-10 & 50-458/99-04.With Attendance List & Licensee Presentation ML20210U3751999-08-12012 August 1999 Informs That Info Contained in Presentation, River Bend Station Fuel Recovery Project,Dtd 990622, Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210Q7691999-08-11011 August 1999 Forwards Request for Addl Info Re Licensee River Bend Individual Plant Exam External Events,Under GL 88-20,suppl 4,dtd 910628 ML20210Q0031999-08-11011 August 1999 Informs That Due to Printing Malfunction,Some Copies of Author Ltr Dtd 990726,may Not Have Included Second Page of Encl 2 of Ltr ML20210R4591999-08-10010 August 1999 Ack Receipt of Which Transmitted Plant Emergency Plan,Rev 20 Under Provisions of 10CFR50,App E,Section V.Nrc Approval Not Required,Based on Determination That Changes Does Not Decrease Effectiveness of EP ML20210L5321999-08-0606 August 1999 Forwards List of Subjects Discussed During 990714 Telcon with Representatives of Niagara Mohawk Power Corp on Unit 1 Re USI A-46 Issue ML20210N1641999-08-0404 August 1999 Forwards Insp Rept 50-458/99-07 on 990530-0710.One Violation of NRC Requirements Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20210K4641999-08-0303 August 1999 Forwards SE Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Power-Operated Gate Valves, Issued on 950817 ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210J9691999-07-30030 July 1999 Discusses 990719 Meeting with Util in Arlington,Tx Re Region IV Staff Findings of Root Cause Investigation Into Fuel Cladding Failures That Occurred During Recent Cycle 8 Operation.List of Attendees & Organization Chart Encl ML20210K1351999-07-30030 July 1999 Forwards Insp Rept 50-458/99-09 on 990510-28 with in-office Insp Until 990701.Three Violations Being Treated as Noncited Violations ML20216E1491999-07-26026 July 1999 Forwards Two Ltrs Received from NMPC Re Nine Mile Point Unit 1 Core Shroud Related to 10CFR2.206 ML20210E9001999-07-23023 July 1999 Informs That as Result of Staff Review of Licensee Responses to GL 92-01,rev 1,Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 ML20210E9151999-07-23023 July 1999 Discusses Evaluation of Recirculation Line Weld 32-WD-050 Indication Found During 1997 Refueling Outage (RFO14) at NMPNS Unit 1.Requests Notification of Decision to Retain Category F Classification Until Listed Conditions Satisfied ML20196L0501999-07-0606 July 1999 Informs That NRC Insp Rept 50-458/99-03 Issued on 990519 with Errors in Tracking Numbers Assigned to Seven Noncited Violations & Error Re Actual Location of SRO During Refueling Activities.Revised Pages 2 & 4 Encl ML20196K6851999-06-30030 June 1999 Ack Receipt of & Denial of NOV in Response to Transmitting NOV & Insp Rept 50-458/98-16.Listed Info Documents Results of Review of Response to Violation Re fire-induced Circuit Faults ML20196K0671999-06-30030 June 1999 Forwards Insp Rept 50-458/99-04 on 990412-16 & 28-29.Five Violations of NRC Requirements Occurred & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy.Meeting Scheduled for 990726 ML20196J6421999-06-30030 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Issued on 960110 ML20196K6461999-06-29029 June 1999 Discusses Ofc of Investigations Rept 1-98-33 Re Unqualified Senior Reactor Operator Assuming Position of Assistant Station Shift Supervisor at Unit 1 on 980616.One Violation Being Cited as Described in Encl NOV ML20212J4431999-06-25025 June 1999 Discusses Responses to RAI Re GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20196E0601999-06-18018 June 1999 Forwards Insp Rept 50-458/99-05 on 990418-29.Four Violations Identified & Being Treated as Noncited Violations ML20195F9971999-06-11011 June 1999 Discusses 990513 Fax Which Forwarded Copy of an Open Ltr to Central New York on Nine Mile One Nuclear Reactor, & Petition to NRC Re Nine Mile Point One Core Shroud Insp, Signed by 187 People ML20195G9661999-06-11011 June 1999 Ack Receipt of Petition Requesting Action Under 10CFR2.206 Sent to W Travers on 990524.Petition Requested That NRC Suspend Operating License Issued to NMP for Nine Mile Point Unit 1.Staff Reviewing Issues & Concerns Raised in Petition ML20207H1021999-06-10010 June 1999 Advises That Info Re Theoretical Basis for Shear & Torsional Spring Constants in Holtec Sf Rack, Submitted in & Affidavit ,marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20207G5281999-06-0909 June 1999 Ack Receipt of Expressing Concern for Reactor Core Shroud for Plant,Unit 1.NRC Staff Requested to Conduct Insp of Reactor Shroud,Including Areas Outside Core Shroud Welds & Publicly Disclose Results 1 Wk Before Plant Restart ML20195G3671999-06-0909 June 1999 Ack Receipt of Ltr Dtd 981016,which Transmitted River Bend Station Emergency Plan,Rev 18 Under Provision of 10CFR50, App E,Section V.No Violations of 10CFR50.54(q) Identified During Review ML20195G3121999-06-0909 June 1999 Ack Receipt of Re Changes to River Bend Station Emergency Plan,Rev 19.No Violations of 10CFR50.47(b) Were Identified ML20137S9381999-06-0909 June 1999 Ack Receipt of Petition Requesting Action Under 10CFR2.206 Sent to W Travers on 990405.Petition Requested That NRC Take EA Against Util & Senior Nuclear & Corporate Mgt 1999-09-09 |
Text
,
OCT 8195 7*
Mr. Frank Denham Executive Vice President Limitorque Corporation 5114 Woodal Road P.O. Box 11318 Lynchburg, Virginia 24506
Dear Mr. Denham,
Subject:
Environmental Qualification Failure of Reliance Class RH AC Motors as used with Limitorque SB-3-150(AC) Motor Actuators General Electric has rccently informed the NRC that they have experienced test anomalies of the Reliance Class RH AC motors during the environmental qualifi-cation testing at Wyle Labs of the Limitorque fast acting SB-3-150 valve motor operator for their River Bend (CSU) and Nine Mile Point 2 (Niagara Mohawk) customers. The test anomalies, in particular what appears to be a failure of the magnesium rotors to withstand the test LOCA profile, have raised concern with the long term availability of valve operator motors with magnesium rotors.
General Electric has evaluated their plant applications and has issued a service information letter with their recommended actions.
It is our understanding that Limitorque was not a participant in the planning or conduct of the testing. It is also our understanding that your company has been appraised of the results and have had an opportunity to review them.
Since several non-GE plants have LOCA profiles approaching that of the General Electric /Wyle test and your valve operators may have been qualified for Nuclear use by other companies or utilities without your participation, we request a listing of those customers which have purchased or ordered valve operators that contain magnesium motor rotors. This information will allow us to compare the test failure data, the plant specific accident profiles, the plant specific applications and other EQ tests involving magnesium rotors. We will then determine the need, if any, for action by the NRC. We appreciate your coopera-tion in this matter.
Sincerely, ovintnv131me de Robert L. Baer, Chief Engineering and Generic Communications Branch y'_ '
N s Division of Emergency Preparedness
/ ,
') and Engineering Response I f ,i 3
('
'~ '
Office of Inspection and Enforcement cc: M Daniel S. Warsing, Limitorque DISTRIBUTION JMTaylor RHVollmer ELJordan SASchwartz JGPartlow BKGrimes JAxelrad RLBaer AWDromerick JCStewart CERossi GGZech EBaker HGarg GHubbard J6R DCS DEPER R/F EGCB R/F JCStewart R/F
- See previous concurrences
- DEPER:IE *DEPER:IE
/fv6 DEPER:IE JCStewart AWDromerick RLBaer 10/ /85 10/ /85 10///85
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