ML20205P688
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Other: 0CAN048804, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Informs That No Instances of Circuit Breakers Being Installed in safety-related Applications Identified at Plant, 3F0288-18, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breaker Models DS-206,DSL-206,DS-416,DSL-416 & DS-420, A07039, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Pole Shafts for All Four Breakers Replaced During Recently Completed Refueling Outage, BECO-88-050, Notifies That Westinghouse Circuit Breakers Not in Use or Planned to Be Used in safety-related Applications at Util, in Response to NRC Bulletin 88-001, ML20147F998, ML20147G854, ML20148A890, ML20148B666, ML20148K225, ML20148Q724, ML20149M198, ML20150A899, ML20150B182, ML20150B526, ML20150C407, ML20150D397, ML20151A945, ML20151B202, ML20151E018, ML20151E419, ML20151E868, ML20151G115, ML20151G791, ML20151H779, ML20151H965, ML20151Q920, ML20154D233, ML20154E154, ML20155A456, ML20155E392, ML20196H353, ML20205P688, ML20235J165, ML20235J168, ML20236A614, ML20236A849, ML20236D105, ML20236F547, ML20236S018, ML20247K075, NRC-88-0072, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Subj Circuit Breakers, RBG-27645, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Any Circuit Breakers Subj to Bulletin in Class 1E Svc at Plant, W3P88-0051, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Util Does Not Use Westinghouse Series Ds Circuit Breakers & Not Subj to Insps Requested in Bulletin | |
MONTHYEARML20235S2971987-10-0202 October 1987
[Table View]Summary of 870923 Meeting W/Westinghouse Re Technical Basis for Westinghouse Recommended Actions,Criteria & Conclusions in to Utils That Use Models DS-416,DSL-416, DS-420,DS-206 & DSL-206 Switchgear in Class 1E Svc Project stage: Meeting ML20236A6141987-10-16016 October 1987 Advises That Util Insp of Reactor Trip Breakers Revealed Catawba Pole Shaft Which Had Welds W/Indications of Cracking.Forwards Informal Technical Communication from Franklin Research Ctr Re Initial Observation Project stage: Other ML20236A8491987-10-16016 October 1987 Forwards I.6177-5-1, Interim Rept on McGuire Reactor Trip Breaker 2B Failure Evaluation & Rcommended Corrective Actions from Westingtonhouse. Rept Explains Mechanical Binding Which Kept Breaker from Opening on 870702 Project stage: Other ML20236D1051987-10-21021 October 1987 Provides Record of 871020 Telcon Between D Hood,D Sellers & V Hodge of NRC & J Mcvicker & Cowne of Bg&E Re Unit 1 480 Volt Circuit Breaker W/Broken Weldment Connecting Ctr Pole Lever to Pole Shaft.Util Exam Results in 860918 Memo Project stage: Other ML20236F5471987-10-23023 October 1987 Documents 871020 Telcon W/Util Re Unit 2 Circuit Breaker Pole Shaft Weld Failure Project stage: Other ML20236F9651987-10-27027 October 1987 Notification of 871103 Meeting W/Util & Westinghouse in Philadelphia,Pa to Discuss Results of Franklin Research Ctr Exam of Cracks in Pole Shaft Welds of Reactor Trip Breaker Project stage: Meeting ML20236S0181987-11-18018 November 1987 Summarizes 871020 Telcon Between NRC & Util Re Two Broken Fillet Welds on Pole Shaft Assembly of Circuit Breaker That Energizes Emergency Fire Protection Pumps for Facility. Photographs Attached to 870710 Memo to NRC Encl Project stage: Other ML20149M1981988-02-16016 February 1988 Advises That Since Util No Longer Operating Reactor Licensee Due to 870430 Shutdown & 870804 Amend,Modifying License DPR-45 to Possess But Not Operate Status,Generic Ltr 88-01 Determined Inapplicable to Facility Project stage: Other 3F0288-18, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breaker Models DS-206,DSL-206,DS-416,DSL-416 & DS-4201988-02-23023 February 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breaker Models DS-206,DSL-206,DS-416,DSL-416 & DS-420 Project stage: Other ML20196H3531988-02-25025 February 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Westinghouse Ds Series Circuit Breakers Installed at Facility Project stage: Other ML20147G8541988-03-0101 March 1988 Responds to NRC Bulletin 88-001 Re Westinghouse Ds Series Circuit Breakers Used in safety-related Applications.Plant Does Not Have Any Westinghouse Ds Series Circuit Breakers Project stage: Other ML20147F9981988-03-0404 March 1988 Submits Response to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Author Does Not Utilize Any Westinghouse Circuit Breakers,As Identified in Subj Bulletin,In Class 1E Applications at Facility Project stage: Other ML20150B1821988-03-0707 March 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breakers in Class 1E Applications So Bulletin 88-001 Does Not Apply to Plant Project stage: Other ML20148A8901988-03-0707 March 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Unit 1 Has No Westinghouse Ds Circuit Breakers Used in Class 1E Application.Unit 2 Reactor Trip & Bypass Breakers Insp Initiated Per Info Notice 87-035 Project stage: Other ML20150A8991988-03-0909 March 1988 Provides Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Determined That Westinghouse Series Ds Circuit Breakers Not Employed at Plant.Insp Required by Bulletin Not Applicable to Plant Project stage: Other ML20150C4071988-03-11011 March 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Determined That Westinghouse Type Ds Circuit Breakers Not Used at Plant Project stage: Other BECO-88-050, Notifies That Westinghouse Circuit Breakers Not in Use or Planned to Be Used in safety-related Applications at Util, in Response to NRC Bulletin 88-0011988-03-15015 March 1988 Notifies That Westinghouse Circuit Breakers Not in Use or Planned to Be Used in safety-related Applications at Util, in Response to NRC Bulletin 88-001 Project stage: Other ML20148B6661988-03-16016 March 1988 Responds to 880205 NRC Compliance Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Westinghouse Ds Series Circuit Breakers Not Used in Class IE Svc at Plant Project stage: Other NRC-88-0072, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Subj Circuit Breakers1988-03-24024 March 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Subj Circuit Breakers Project stage: Other ML20148K2251988-03-25025 March 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Two Reactor Trip Breakers & Two Reactor Trip Bypass Breakers Subj to Bulletin Used at Millstone Unit 3.Main Pole Shaft Weld Insps Completed by 880225 Project stage: Other ML20151G7911988-03-28028 March 1988 Confirms That Westinghouse Ds Breakers Not Used at Facility, Per IE Bulletin 88-001, Defects in Westinghouse Circuit Breakers Project stage: Other W3P88-0051, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Util Does Not Use Westinghouse Series Ds Circuit Breakers & Not Subj to Insps Requested in Bulletin1988-03-29029 March 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Util Does Not Use Westinghouse Series Ds Circuit Breakers & Not Subj to Insps Requested in Bulletin Project stage: Other ML20151A9451988-03-30030 March 1988 Responds to IE Bulletin 88-001 Re Westinghouse Ds/Dsl Circuit Breakers.Ref Components Not Utilized at Facility Project stage: Other 0CAN048804, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Informs That No Instances of Circuit Breakers Being Installed in safety-related Applications Identified at Plant1988-04-0101 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Informs That No Instances of Circuit Breakers Being Installed in safety-related Applications Identified at Plant Project stage: Other ML20151B2021988-04-0404 April 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Insp of All Westinghouse DS-415 Reactor Trip & Bypass Breakers Completed on 880308 & Results Encl Project stage: Other RBG-27645, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Any Circuit Breakers Subj to Bulletin in Class 1E Svc at Plant1988-04-0404 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Any Circuit Breakers Subj to Bulletin in Class 1E Svc at Plant Project stage: Other ML20148Q7241988-04-0707 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Westinghouse Models DS-206,DSL-206, DS-416,DSL-416 or DS-420 Breakers in Class 1E Circuits at Hatch Project stage: Other ML20151H7791988-04-0707 April 1988 Informs That Westinghouse Ds Circuit Breakers Not Utilized in Any 1E Application at Plant But Used in non-1E Applications & Will Be Included in Util Preventive Maint Program Project stage: Other ML20151E4191988-04-0808 April 1988 Responds to 880205 NRC Bulletin 88-01 Re Defects in Westinghouse Circuit Breakers for Facilities.Westinghouse Ds Series Circuit Breakers Not Used at Plants.Other Provisions of Bulletin Do Not Apply to Plants Project stage: Other ML20151E8681988-04-11011 April 1988 Forwards Response to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers in Class 1E Svc.All Required long-term & short-term Insps Completed Project stage: Other ML20151H9651988-04-13013 April 1988 Responds to NRC Bulletin 88-001, Deficiencies in Westinghouse Circuit Breakers. Bulletin Addresses Deficiencies Exclusive to Westinghouse Ds/Dsl Type Circuit Breakers & Outlines Specific Insps to Be Performed Project stage: Other ML20151G1151988-04-13013 April 1988 Ack Receipt of in Response to NRC Bulletin 88-001 Re Westinghouse Circuit Breakers.Plant Does Not Use or Plan Use of Circuit Breakers,Therefore Matter Closed Project stage: Other ML20205P6881988-04-20020 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Circuit Breakers Subj to Bulletin Installed in Plant Project stage: Other ML20155E3921988-06-0909 June 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit breakers.Sixty-six of sixty-seven Breakers Required New Pole Shafts Due to Failure of Welds to Meet Bulletin Requirements Resulting from Insp Project stage: Other ML20150B5261988-06-30030 June 1988 Informs That All Class 1E DS-416 Breakers Now in Use Comply W/Nrc Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers Project stage: Other ML20150D3971988-07-0505 July 1988 Advises That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20151E0181988-07-14014 July 1988 Advises That Util 880407 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20151Q9201988-08-0202 August 1988 Informs That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20154D2331988-09-0909 September 1988 Informs That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory & No Further Reply Necessary Project stage: Other ML20154E1541988-09-0909 September 1988 Advises That 880408 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20155A4561988-09-29029 September 1988 Requests Addl Info Re Util 880908 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Response Requested within 70 Days of Ltr Date Project stage: Other ML20235J1681989-02-17017 February 1989 Advises That 880314 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers Satisfactory. Westinghouse Ds Series Circuit Breakers Not Used in safety-related Applications at Plant Project stage: Other ML20235J1651989-02-17017 February 1989 Provides Final Response to NRC Bulletin 88-001, Defects in Westinhouse Circuit Breakers. Alignment Check Specified in 871201 Submittal Satisfactorily Performed During Installation of Replacement Pole Shaft in Breakers Project stage: Other ML20247C7191989-05-15015 May 1989 Forwards Supplemental Response to NRC Bulletin 88-001 Re Westinghouse Series Ds Circuit Breakers.Insp Info Corrected Project stage: Supplement ML20247K0751989-05-24024 May 1989 Responds to NRC Bulletin 88-001 Re Defects of Westinghouse Circuit Breakers.All forty-seven Westinghouse Type Ds Breakers Inspected Were Found to Have Acceptable Breaker Mechanism Alignment Project stage: Other A07039, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Pole Shafts for All Four Breakers Replaced During Recently Completed Refueling Outage1989-07-24024 July 1989 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Pole Shafts for All Four Breakers Replaced During Recently Completed Refueling Outage Project stage: Other 1988-03-07 |
| ML20205P688 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 04/20/1988 |
| From: | Randazza J Maine Yankee |
| To: | Russell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-88-001, IEB-88-1, MN-88-46, TAC-65955, TAC-65956, NUDOCS 8811080262 | |
| Download: ML20205P688 (1) | |
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[Table view]Forwards Summary of Changes Made to Maine Yankee Defueled Security Plan,Iaw 10CFR50.54(p)(2).Without Encl ML20217J0241999-10-13013 October 1999 Documents 991005 Telcon Between NRC & Util to Address All of Areas Identified in Reg Guide 1.179 & NUREG-1700 Re Final Survey Plan Except for One Area ML20212M2431999-09-22022 September 1999 Expresses Concern Re NRC Consideration of Adoption of Policy Based on Requests from Licensees,To Allow as Part of Decommissioning of Nuclear Power Plants & Demolition of Onsite Structures at Reactor Plant Sites ML20212B7011999-09-14014 September 1999 Submits Comments & Raises Questions Re Generation of White Paper for Commission to Decide Merits of Rubberization ML20212E4841999-08-27027 August 1999 Informs That at 990429 Meeting of Myap Community Advisory Panel,R Shadis,Asked If Given Lack of Resident Inspectors & Limited NRC-license Review Correspondence,If Shadis Could Take Part in Weekly NRC Conference Calls with Licensee ML20216F1891999-08-26026 August 1999 Forwards Copies of Maine Yankee & Yankee Rowe Refs Listed, Supporting Industry Position That Branch Technical Position Asb 9-2 Methodology over-estimates Spent Fuel Decay Heat ML20211C0591999-08-19019 August 1999 Forwards Addl Justification for Proprietary Request Re 990809 Submittal Info on Maine Yankee License Termination Plan ML20212A5981999-08-16016 August 1999 Expresses Appreciation for with Respect to e-mail Message Re Site Release Criteria Standards Can Never Be Verified Using Existing Database ML20210Q7201999-08-0909 August 1999 Forwards non-proprietary & Proprietary Draft Documents Re Info on Myap License Termination Plan & Diskette.Proprietary Info & Diskette Withheld ML20211D7041999-08-0909 August 1999 Forwards Rev 17 of Maine Yankee Defueled Safety Analysis Rept (Dsar), Per 10CFR50.71 & 10CFR50.4 ML20212B2271999-08-0606 August 1999 Discusses Concerns Re Recent Incindent Involving Transport of Nuclear Matl from Maine Yankee ML20210M8171999-08-0505 August 1999 Forwards Draft License Termination Plan/Amend Plan for Maine Yankee Atomic Power Co, to Enhance Dialogue Between Various Stakeholders & Provide Springboard for Clarifying Mutual Expectations.With Three Oversize Drawings ML20210L2211999-08-0202 August 1999 Forwards Two Copies of Objectives & Sequence of Events for Maine Yankee Emergency Preparedness Exercise for 990922. Without Encl ML20217M6571999-07-19019 July 1999 Expresses Concern Re Verification of Cleanup Stds at Maine Yankee Atomic Power Co Power Station ML20216D4311999-07-19019 July 1999 Informs That Util Intends to Construct ISFSI Located on Owner Controlled Property Currently Part of Maine Yankee Reactor Site ML20210C6271999-07-15015 July 1999 Forwards Draft Site Characterization Summary in Support of 10CFR50 License Termination & Copy of Latest Decommissioning Schedule with Milestones Identified.Info Submitted Per License Termination Plan ML20210G3981999-06-30030 June 1999 Discusses Review of Ltr Re Maine Yankee Backfit Appeal with Respect to Emergency Plan Exemptions for Decommissioning Plants ML20209C7731999-06-30030 June 1999 Responds to EDO Backfit Appeal Determination Re Emergency Plan Exemptions for Decommissioning Plants ML20209B4611999-06-29029 June 1999 Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Plant Is Y2K Ready.Contingency Plans Developed to Mitigate Potential Impact of non-plant Y2K-induced Events ML20195H1741999-06-15015 June 1999 Forwards Original & Copy of Request for Approval of Certain Indirect & Direct Transfer of License & Ownership Interests of Montaup Electric Co (Montaup) with Respect to Nuclear Facilities Described as Listed ML20195G9411999-06-10010 June 1999 Informs That Maine Yankee Considers Backfit Claim & Appeal Request of 980716 & 990316,to Be Acceptably Resolved Based on Staff 990518 Response ML20195F7531999-06-0707 June 1999 Forwards Copy of Insurance Endorsement Dtd 990429,reflecting Change in Nuclear Energy Liability Insurance,Iaw Requirements of 10CFR140.15(e) ML20206J2801999-04-30030 April 1999 Forwards 1998 Annual Financial Repts for CT Light & Power Co,Western Ma Electric Co,Public Svc Co of Nh,North Atlantic Energy Corp,Northeast Nuclear Energy Co & North Atlantic Energy Svc Corp,License Holders ML20206D7191999-04-29029 April 1999 Forwards Listed Radiological Repts for 1998 Submitted IAW Relevant Portions of License DPR-36 & ODCM ML20206E2911999-04-28028 April 1999 Requests NRC Review of ISFSI Licensing Submittals,As Scheduled & ISFSI Approval for Operation by Dec 2000.Util Will Support Any NRC RAI on Expedited Basis.Licensing Milestone Schedule,Encl ML20206E3101999-04-28028 April 1999 Forwards Data Diskette Containing 1998 Individual Monitoring NRC Form 5 Rept,Per 10CFR20.2206(b).Without Diskette ML20205K6541999-04-0707 April 1999 Submits Nuclear Property Insurance Coverage Presently in Force to Protect Maine Yankee at Wiscasset,Me ML20206H2401999-03-30030 March 1999 Informs That Myap Recently Revealed That Approx 20% of Fuel Assemblies Now in SFP Are non-std & Require Special Handling & Dry Cask Packaging.Info Confirms Growing Evidence of Periodic Loss of Radiological Control ML20206A6951999-03-29029 March 1999 Request Confirmation That No NRC Action or Approval,Required Relative to Proposed Change in Upstream Economic Ownership of New England Power Co,Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee ML20205C3331999-03-24024 March 1999 Submits Rept on Status of Decommissioning Funding for Year Ending 981231.Requested Info Provided in Attachment ML20205B7321999-03-24024 March 1999 Documents Withdrawal of Previously Submitted Request for Exemption from Requirements of 10CFR70.24 Re Criticality Accident Requirements, ML20204E5671999-03-18018 March 1999 Forwards Rev 1 to Maine Yankee Atomic Power Station Security Plan & Description of Changes & Summary of 10CFR50.54(p) Effectiveness Evaluation.Without Encl ML20206K6811999-03-16016 March 1999 Forwards Background & Details Re Backfits Claimed in Util Re Permanently Shutdown Reactor Security Plan ML20205G9841999-01-0505 January 1999 Discusses 1997 Maff - Sepa Radioactivity in Food & Environ ML20197J9001998-12-0707 December 1998 Submits Appeal of DD Re Myap Claim of Backfit Re Beyond Design Basis Accidents in Spent Fuel Pools.Discussion of Licensee Reasons,Provided ML20198J4061998-11-0909 November 1998 Ack Receipt of Roe Response to & Copy of Chairman 981014 address,S-98-25.Informs That Root of NRC Problems Lies in Inability to Create multi-dimensional Vision,Mission or Picture of Future NRC in 2003,2008 or Any Time Frame ML20195E8961998-11-0909 November 1998 Provides Response to Nov, Re NRC Insp Repts 50-309/96-09,50-309/96-10,50-309/96-11,50-309/96-16 & 50-309/97-01.Corrective Actions:Util in Compliance with TS 5.5,which Is Current Ref to Cited TS 5.8.2.a ML20155J0871998-11-0505 November 1998 Forwards Supplemental Info for NRC Review Re TS Change 208 Request on Sf Pool Cooling Sys ML20155H9461998-11-0303 November 1998 Informs That All Future Correspondence Being Sent to Myap Should Be Sent to Listed Address ML20155G9451998-11-0303 November 1998 Forwards Rev 1 to M01-1258-002, Decommissioning Cost Analysis for Myaps, Detailing Study of Decommissioning Costs.Rev 1 to Post-Shutdown Decommissioning Rept, Encl. Info Is Submitted as Required by 10CFR50.82(a)(8)(iii) ML20155D6461998-10-29029 October 1998 Forwards Corrected, Occupational Radiation Exposure Rept for 1997, Including Work & Job Function Categories That Were in Effect in 1997 Under Former TS 5.9.1.3.A.Earlier Submittal Contained Incorrect Info ML20155D7971998-10-28028 October 1998 Forwards Response to NRC 981002 RAI Re Modeling Spent Fuel Pool Heatup.Info Is Needed for NRC to Address Future Exemption Requests from Permanently Shutdown Plants in More Generic & Timely Manner ML20155B7221998-10-26026 October 1998 Informs That Util Has Been Unsuccessful in Determining Status &/Or Estimated Completion Date of NRC Evaluation of Licensee Backfit Claim.Assistance in Resolving Matter, Requested ML20154L4821998-10-15015 October 1998 Forwards Maine Yankee Defueled Emergency Plan. Change to Maine Yankee Emergency Plan Has Been Made in Accordance with 10CFR50.54(q) ML20203H2231998-10-14014 October 1998 FOIA Request for Documents Re EAs 96-299,96-320,96-375, 96-397,97-034,97-147 & 97-559 for Myaps.Requested Documents Include OI Repts & Internal Ltrs,Memos & e-mail Messages to & from OE ML20206N7601998-10-13013 October 1998 Discusses Concerns Re Regulatory Failures at Maine Yankee & Requests NRC Convene Public Meeting Between NRC Staff & Maine Yankee Stakeholders to Discuss Events of Past Two Years ML20203A8291998-09-29029 September 1998 Submits follow-up to Last Week Telcon Request That NRC Meet with Maine Advisory Committee on Radiation on Evening of 991104,to Provide Info & Answer Questions to Committee on Recent Exemptions Granted to Maine Yankee on Emergency Plan ML20153E7541998-09-22022 September 1998 Expresses Disappointment in Quality & Approach of Staff SER, to Provide Comments on Some of Bases Considered in Issuance of Exemption to Allow Util to Discontinue Offsite Emergency Planning Activities.Factual Discrepancies Noted ML20153B2971998-09-17017 September 1998 Withdraws Exemption Request from Certain Insurance Coverage & Financial Protection Requirement Limits of 10CFR50.54(w) & 10CFR140.11.If NRC Disagrees W/Conclusion Contained in Ltr, NRC Should Continue to Process 10CFR140.11 Request ML20155D8331998-08-31031 August 1998 Forwards Public Version of, Maine Yankee Emergency Preparedness Exercise, for Exercise Scheduled for 981028. Rept Demonstrates Major on-site Emergency Response Elements for Defueled & Permanently Defueled Shutdown Plant 1999-09-22 Category:UTILITY TO NRC MONTHYEARML20059H1791990-09-0707 September 1990
[Table view]Forwards Addl Info Re Control Element Assembly Failure at Facility ML20059F2861990-08-23023 August 1990 Responds to NRC Re Violations Noted in Insp Rept 50-309/90-10 Re RCS Inventory.Corrective Actions:Root Cause Evaluation Initiated & RCS Stabilized by Increasing Water Inventory & Venting ML20059E9341990-08-22022 August 1990 Responds to Violations Noted in Insp Rept 50-309/90-11. Corrective Actions:Work Planning Meeting Held Weekly & Radiological Controls Supervision Utilizing Plan of Wk to Assign Radiological Controls Technicians to Specific Jobs ML20056B3561990-08-20020 August 1990 Forwards fitness-for-duty Program Performance Data for Jan- June 1990 ML20059A8111990-08-10010 August 1990 Responds to Emergency Preparedness Exercise & Routine Insp Repts 50-309/88-09 & 90-14,respectively.Corrective Actions: Remedial Training Will Be Given to Available Emergency Coordinators in Use of Procedures for Developing PARs ML20058P3741990-08-0909 August 1990 Forwards Monthly Operating Rept for Jul 1990 for Maine Yankee Atomic Power Station & Revised Rept for June 1990 ML20055G6881990-07-19019 July 1990 Submits Results of Analysis of Component Cooling Heat Balance to Support Operation at 2,700 Mwt.Prior Administrative Controls Overly Conservative & No Longer Required ML20055E0641990-07-0303 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Outstanding Procurement Actions for Rosemount Pressure & Differential Pressure Transmitters Modified to Specify Mfg After 890711 ML20055E0501990-07-0202 July 1990 Responds to Info Notice 88-085 & NRC Bulletin 89-002 Re Two Anchor/Darling Swing Check Valves.Neither Valve Found to Have Any Svc Induced Cracking of Bolting.Existing Bolting Replaced W/Type 17-4PH Matl (Specification A564-630-1100) ML20055D4611990-06-25025 June 1990 Responds to NRC Re Violations Noted in Insp Rept 50-309/89-82.Corrective Actions:Testing Program Developed & Implemented for Testing of Molded Case Circuit Breakers & Procedure Modified to Address Revised Dedication Process ML20248J1941989-10-0404 October 1989 Discusses Review & Improvement of Inservice Testing Program, as Required by Generic Ltr 89-04.Addl Work Required to Assure Full Compliance W/Proposed Schedule Which Would Provide Goals for Enhancing Program ML20246F4871989-08-23023 August 1989 Advises That 4,160-volt Breakers for Charging/Hpsi Pumps, Equipped w/anti-pumping Feature Might Inhibit auto-start of Standby Pump Under Certain Accident Conditions.Redesign of Breaker Control Circuitry Will Be Completed by 890915 ML20246C1781989-08-17017 August 1989 Forwards Corrected Pages to 890807 Rev 1 to Security Plan. Errata Withheld ML20248C8101989-08-0707 August 1989 Forwards Rev 1 to Security Plan.Rev Withheld ML20245G8731989-08-0404 August 1989 Provides Final Response to NRC Bulletin 88-010, Non-Conforming Molded-Case Circuit Breakers. Review of Purchasing & Audit Records for Eight Remaining Circuit Breakers Verified Traceability to Original Mfg ML20245G8771989-08-0101 August 1989 Forwards Operator Licensing Exam Info Requested in Generic Ltr 89-12,consisting of Number of Reactor Operator & Senior Reactor Operator Exams Scheduled in FY90 to FY93 ML20247R1261989-07-31031 July 1989 Advises That No Compensation Terms or Conditions of Employment Restrictive of Employee Ability to Contact NRC Re Potential Safety Concerns Identified,Based on Review of Existing Contractual Agreements & Personnel Policies ML20247P6751989-07-28028 July 1989 Responds to NRC Re Violations Noted in Insp Rept 50-309/88-200.Corrective Action:Developed Guidelines & Representative Critical Characteristics to Be Retroactively Used for Acceptance of Approx 500 Commercial Grade Purchase ML20247P5611989-07-27027 July 1989 Confirms Implementation of long-term Monitoring Program, Assuring That Procedures or Administrative Controls in Place to Guard Against erosion/corrosion-induced Pipe Wall Thinning in high-energy Carbon Steel Sys ML20247H6511989-07-21021 July 1989 Responds to NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification. No Evidence of Permanent Deformation or Distress to Either Surge Line or Spring Hangers Found ML20247A2571989-07-19019 July 1989 Forwards Rev 7 to FSAR for Maine Yankee Atomic Power Station ML20246L8441989-07-11011 July 1989 Forwards Response to Generic Ltr 89-06 Requesting Certification That SPDS Meets Requirements of Suppl 1 to NUREG-0737 Per Info Provided in NUREG-1342 ML20246Q0011989-07-0606 July 1989 Requests Addl Time to Respond to Violation Noted in Insp Rept 50-309/88-20.Response Provided by 890721 05000309/LER-1989-002, Forwards LER 89-002-01.Suppl Documents Addl Info & That Evaluation of Reported Conditions Completed Per 10CFR211989-06-28028 June 1989 Forwards LER 89-002-01.Suppl Documents Addl Info & That Evaluation of Reported Conditions Completed Per 10CFR21 ML20245H5321989-06-19019 June 1989 Advises of Reclassification of Nine Circuit Breakers Previously Deemed Traceable Re NRC Bulletin 88-010 ML20245H1931989-06-14014 June 1989 Provides Amended Response to NRC Re Violations Noted in Insp Rept 50-309/88-23 on 1988 Shipment Records ML20245J2671989-06-13013 June 1989 Responds to NRC Re Violations Noted in Insp Rept 50-309/89-30.Corrective Actions:Svc Water HX Valves Will Be Relabeled & Setpoint Basis Document Will Be Developed to Control Setpoint Revs ML20244E1791989-06-13013 June 1989 Responds to NRC Bulletin 89-001 Re Failure of Westinghouse Steam Generator Tube Mechanical Plugs.No Plugs Installed or Ordered from Westinghouse ML20247D7331989-06-12012 June 1989 Requests That NRC Replace Pages 14,15 & 16 of Attachment to W/Attached Sheets,Per IE Bulletin 85-03 ML20247M0761989-05-30030 May 1989 Forwards Maine Yankee Atomic Power Station Safeguards Contingency Plan, Maine Yankee Atomic Power Station Security Force Training ..., & Description of Changes for Each Plan,Per 10CFR50.54(p).Encl Withheld Per 10CFR73.21 ML20247G6241989-05-30030 May 1989 Provides Addl Info Re Util Component Cooling Water Heat Balance to Support Operation at 2,700 Mwt.Util Conducted Conservative Analyses Which Justify Operation at 2,700 Mwt ML20246A3491989-05-25025 May 1989 Responds to NRC Re Violations Noted in Insp Rept 50-309/89-07.Corrective Actions Withheld ML20247K2541989-05-23023 May 1989 Notifies That Tj Carmody Temporarily Relieved of Duties Due to Complications from Previous Medical Condition ML20246K9801989-05-10010 May 1989 Forwards Monthly Operating Rept for Apr 1989 for Maine Yankee Atomic Power Station & Revised Operating Data Rept for Mar 1989.Unit Forced Outage Rate yr-to-date & Cumulative Values Changed ML20244D0191989-04-14014 April 1989 Forwards Sec Form 10K Re Annual Rept for FY88 ML20246N7121989-04-14014 April 1989 Submits Results of Evaluation of Plant Against Requirements of Station Blackout Rule.Proposed Station Blackout Duration, Procedure Description & Proposed Mods & Schedule Discussed. Diagram Re Alternate Power Supply Encl ML20244B3681989-04-12012 April 1989 Forwards Maine Yankee Inservice Insp Summary Rept. Results of Steam Generator Tube Inservice Insp Also Encl ML20245F9591989-04-0303 April 1989 Discusses Invoice for Part 55 Svcs for 870621-1219. Reaffirms That Accrued Interest Bill,Dtd 890309,should Be Disregarded ML20247N8201989-04-0303 April 1989 Forwards Revised Security Plan & Description of Changes.Rev Withheld (Ref 10CFR73.21) ML20248G6561989-03-31031 March 1989 Responds to NRC Bulletin 88-010, Non-Conforming Molded-Case Circuit Breakers. Util Plans to Conduct Audits of Intermediate Suppliers Records by 890530 ML20244B7711989-03-31031 March 1989 Forwards 115-kV Capacitor Bank Design Rept. Util Position Re Enhancements to Plant Offsite Power Sys Clarified. Capacitor Bank Fully Operational ML20236A9861989-03-15015 March 1989 Responds to NRC 890213 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $75,000.Util Has Undergone Comprehensive & Aggressive Program to Upgrade Security Program.Physical Security Plan Info Withheld ML20236D0521989-03-13013 March 1989 Repts Nuclear Property Insurance in Force to Protect Plant ML20236B5841989-03-0909 March 1989 Forwards Monthly Statistical Rept for Maine Yankee Atomic Power Station for Feb 1989.Revised Shutdown Power Reduction Sheet for Jan 1989 Also Encl ML20236A4531989-03-0606 March 1989 Forwards Response to NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification. No Evidence of Permanent Deformation or Distress to Either Surge Line or Associated Spring Hangers Noted ML20235V2061989-02-24024 February 1989 Responds to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Sys at Plant Operated,Maintained & Periodically Tested to Provide Assurance of Performance as Expected W/Design Basis Events ML20235U7291989-02-23023 February 1989 Responds to NRC Re Violations Noted in Insp Rept 50-309/88-23.Corrective Actions:Use of Radman Software for Performing Manifest Calculations Implemented to Reduce Errors & Procedure 9.1.29 Revised on 890130 ML20235V7711989-02-21021 February 1989 Responds to NRC Re Violations Noted in Insp Rept 50-309/88-21.Corrective Actions:Conduit Removed from Support & re-analysis Determined Support Not Required to Properly Support Conduit.Tubing Support Reinstalled & Retorqued ML20245H8321989-02-21021 February 1989 Responds to NRC Re Violations Noted in Insp Rept 50-309/88-80.Corrective Actions:Individual Entering Radiation Control Area Disciplined for Not Picking Up Required Dosimetry & Procedure 0.1.1 Revised ML20235W8021989-02-15015 February 1989 Requests Enforcement Discretion to Remain in Hot Shutdown Until 890217 to Complete Repairs to Electrical Penetrations Associated W/Six Open Containment Isolation Sys Valves. Repairs Expected to Take from 3 to 7 Days 1990-09-07 |
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a
~ . MaineYankee REUA8tE ELECTACTY FOA MArNE SINCE 1972 EDISON DRIVE . AUGUSTA, MAINE 04330. (207) 622 4868 April 20, 1988 HN-88-46 Region I '
United States Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 -
Attention: Mr. Hilliam T. Russell, Regional Administrator
References:
(a) License No. OPR-36 (Docket No. 50-309)
(b) USNRC Letter to HYA No dated February 5, 1988 (TACS 65955/65956)
Subject:
Response to NRC Bulletin 88-01: Defects in Westinghouse Circuit Breakers Gentlemen:
Maine Yankee has reviewed the use of Westinghouse DS type circuit breakers for Class 1E applications as required by NRC Bulletin 88-01. Reference (b).
He have deternined that there are no circuit breakers subject to this Bulletin insta!1ed in the Maine Yankee plant.
He trust that this response it, sufficient. However, if you should have any further questions, we will be pleased to answer them.
Very truly yours, NAINE YANKEE 8811080262 080420 PDR G
ADOCK 05000309 PNU Qgg vJohn 8. Randazza ,
President JBR/bjp cc: Mr. Richard H. Nessman .
Hr. H1111am T. Russell Mr. Cornelius F. Holden Mr. Patrick H. Sears -
! Mr. Clough Toppan l
STATE OF MAINE !
I Then personally appeared b6 fore me, John B. Randazza, who being duly sworn did state that he is President of Haine Yankee Atomic Power Company, that he is duly authorized to execute and file the foregoing request in the name and i on behalf of Haine Yankee Atomic Power Company, and that the statements therein are true to the best of his knowledge and belief. ;
haA may h 9
, .- ,m,#= h. . !
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