A07039, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Pole Shafts for All Four Breakers Replaced During Recently Completed Refueling Outage
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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 |
| ML20247N728 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/24/1989 |
| From: | Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | Russell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| A07039, A7039, IEB-88-001, IEB-88-1, TAC-65955, TAC-65956, NUDOCS 8908030133 | |
| Download: ML20247N728 (2) | |
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Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal1999-09-16016 September 1999 Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal B17876, Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant1999-09-16016 September 1999 Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant B17882, Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6) B17881, Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6) B17859, Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 9801281999-09-15015 September 1999 Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 980128 B17880, Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6) B17872, Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 11999-09-14014 September 1999 Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 1 ML20212A9011999-09-10010 September 1999 Forwards Environ Assessment & Finding of No Significant Impact Re Application for Exemption,Dtd 990803.Proposed Exemption Would Provide Relief from Requirement of 10CFR50 ML20212A3171999-09-10010 September 1999 Discusses Investigation Rept 1-1998-045 Conducted on 981112 to Determine If Former Senior Health Physics Technician Being Denied Employment at Millstone in Retaliation for Having Raised Safety Concerns in Past.Synopsis Encl B17838, Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls1999-09-10010 September 1999 Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls ML20212A7501999-09-10010 September 1999 Forwards Staff Requirements Memo Response,Dtd 990525,which Provides Actions NRC Plans for Continued Oversight of safety-conscious Work Environ & Employee Concerns Program ML20211J9291999-09-0303 September 1999 Forwards mark-ups & Retypes of Proposed Conforming License Changes Required in Connection with Transfers Being Sought in 990615 Application of Montaup Electric Co & New England Power Co for Transfer of Licenses & Ownership Interests ML20211K5171999-09-0202 September 1999 Expresses Appreciation for Support Provided for NRC Public Meeting on 990825 05000336/LER-1999-010, Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 11999-09-0202 September 1999 Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 1 ML20216H0591999-09-0202 September 1999 Responds to Re Issues Submitted by Cullen on Behalf of Several Petitioners Concerning Offsite Emergency Prepardeness for Millstone Nuclear Power Station ML20211N9241999-09-0101 September 1999 Forwards Document Classification Form for Insertion Into Emergency Planning Services Department Procedures ML20211H0741999-08-30030 August 1999 Discusses GL 92-01,Rev 1, Rv Structural Integrity, Issued by NRC on 950519 & NNECO Responses for Millstone Unit 2 & 980715.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 Based on Response Review 1999-09-30 Category:INCOMING CORRESPONDENCE MONTHYEARML20217N8261999-10-25025 October 1999
[Table view]Discusses Errata Re 991021 Filing of Northeast Nuclear Energy Co Answer to Request for Hearing & Petition to Intervene B17886, Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 21999-10-18018 October 1999 Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 2 B17901, Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6)1999-10-18018 October 1999 Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6) 05000336/LER-1999-012, Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl B17900, Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 11999-10-14014 October 1999 Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 1 ML20217P1201999-10-0606 October 1999 Informs NRC of Proposed Acquisition of Parent Holding Company of Central Maine & Requests NRC Concurrence,Based on Threshold Review,That Proposed Acquisition Does Not,In Fact, Constitute Transfer Subject to 10CFR50.80 ML20217F0031999-10-0606 October 1999 Forwards Original Petition to Intervene Being Filed on Behalf of Clients,Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone,Iaw Provisions of 10CFR2.714 B17892, Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC1999-10-0505 October 1999 Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC B17887, Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer1999-09-28028 September 1999 Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer B17883, Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-62301999-09-27027 September 1999 Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-6230 B17890, Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-09-27027 September 1999 Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal B17884, Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-031999-09-24024 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-03 B17888, Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 9909151999-09-24024 September 1999 Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 990915 05000336/LER-1999-001, Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl B17867, Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports1999-09-17017 September 1999 Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports B17876, Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant1999-09-16016 September 1999 Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant B17865, Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal1999-09-16016 September 1999 Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal B17881, Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6) B17880, Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6) B17859, Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 9801281999-09-15015 September 1999 Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 980128 B17882, Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6) B17872, Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 11999-09-14014 September 1999 Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 1 B17838, Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls1999-09-10010 September 1999 Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls ML20211J9291999-09-0303 September 1999 Forwards mark-ups & Retypes of Proposed Conforming License Changes Required in Connection with Transfers Being Sought in 990615 Application of Montaup Electric Co & New England Power Co for Transfer of Licenses & Ownership Interests 05000336/LER-1999-010, Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 11999-09-0202 September 1999 Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 1 ML20216H0591999-09-0202 September 1999 Responds to Re Issues Submitted by Cullen on Behalf of Several Petitioners Concerning Offsite Emergency Prepardeness for Millstone Nuclear Power Station ML20211N9241999-09-0101 September 1999 Forwards Document Classification Form for Insertion Into Emergency Planning Services Department Procedures B17851, Forwards Semiannual fitness-for-duty Program Performance Data for 990101-990630 for Millstone Nuclear Power Station, Units 1,2 & 3,IAW 10CFR26.71(d)1999-08-27027 August 1999 Forwards Semiannual fitness-for-duty Program Performance Data for 990101-990630 for Millstone Nuclear Power Station, Units 1,2 & 3,IAW 10CFR26.71(d) B17855, Forwards NRC Forms 398 & 396 in Support of License Renewal for SRO TE Grilley,SOP-4053-04.Encl Withheld,Per 10CFR2.7901999-08-17017 August 1999 Forwards NRC Forms 398 & 396 in Support of License Renewal for SRO TE Grilley,SOP-4053-04.Encl Withheld,Per 10CFR2.790 B17849, Forwards Second Quarter Backlog Performance Rept for 1999, Which Represents Fourth Rept on Mnps Performance Since Restart of Unit 3 & First Status Update for Unit 2.No Regulatory Commitments Are Contained in Ltr1999-08-16016 August 1999 Forwards Second Quarter Backlog Performance Rept for 1999, Which Represents Fourth Rept on Mnps Performance Since Restart of Unit 3 & First Status Update for Unit 2.No Regulatory Commitments Are Contained in Ltr B17854, Forwards Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2,per TS 6.9.1.7.Revised Repts for May & June Also Encl Which Reflect Correct Faulty Printometer Readings1999-08-14014 August 1999 Forwards Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2,per TS 6.9.1.7.Revised Repts for May & June Also Encl Which Reflect Correct Faulty Printometer Readings B17850, Forwards First Lhc Quarterly Assessment Rept for Assessment Performed 990621 to 990701.NNECO Taking Appropriate Actions to Address Observations in Rept1999-08-11011 August 1999 Forwards First Lhc Quarterly Assessment Rept for Assessment Performed 990621 to 990701.NNECO Taking Appropriate Actions to Address Observations in Rept B17837, Forwards COLR for Cycle 7, for Millstone Unit 3,IAW TS 6.9.1.6.Explanation of Changes to COLR Also Encl1999-08-0707 August 1999 Forwards COLR for Cycle 7, for Millstone Unit 3,IAW TS 6.9.1.6.Explanation of Changes to COLR Also Encl B17657, Requests Schedular Exemption from Emergency Plan Exercise Requirements of 10CFR50,App E,Part Iv,Section F,Paragraph 2.c.Requests That Nrc/Fema Evaluated Exercise Be Conducted in Mar 2000 Rather than Sept 19991999-08-0303 August 1999 Requests Schedular Exemption from Emergency Plan Exercise Requirements of 10CFR50,App E,Part Iv,Section F,Paragraph 2.c.Requests That Nrc/Fema Evaluated Exercise Be Conducted in Mar 2000 Rather than Sept 1999 B17845, Forwards Revised Commitment for Surveillance Scheduling & Tracking.Options for Surveillance Scheduling & Tracking Methodologies to Be Incorporated in Standardized Station Surveillance Program Are Currently Being Reconsidered1999-08-0202 August 1999 Forwards Revised Commitment for Surveillance Scheduling & Tracking.Options for Surveillance Scheduling & Tracking Methodologies to Be Incorporated in Standardized Station Surveillance Program Are Currently Being Reconsidered B17831, Informs NRC Staff That Change 3 to Rev 25 of Mnps Emergency Plan Was Implemented on 990715.Change Removes Facility Organizational Charts from Emergency Plan & Identifies Relocation to Nuqap1999-07-26026 July 1999 Informs NRC Staff That Change 3 to Rev 25 of Mnps Emergency Plan Was Implemented on 990715.Change Removes Facility Organizational Charts from Emergency Plan & Identifies Relocation to Nuqap B17834, Forwards Proprietary Revised NRC Form 398,which Certifies That SL Doboe Has Completed Eligibility Requirements for Sro,Per 10CFR55.31.Proprietary Info Withheld1999-07-20020 July 1999 Forwards Proprietary Revised NRC Form 398,which Certifies That SL Doboe Has Completed Eligibility Requirements for Sro,Per 10CFR55.31.Proprietary Info Withheld B17836, Forwards Revised NRC Form 396 & Supporting Physician Rept for Licensed Operator Restricted from Licensed Duties, Effective 990628,due to Medical Condition.Without Encl1999-07-20020 July 1999 Forwards Revised NRC Form 396 & Supporting Physician Rept for Licensed Operator Restricted from Licensed Duties, Effective 990628,due to Medical Condition.Without Encl B17811, Submits Response to NRC AL 99-02,requesting That Licensees Provide Numerical Estimates of Licensing Actions to Be Expected to Be Submitted in Fy 2000 & 20011999-07-20020 July 1999 Submits Response to NRC AL 99-02,requesting That Licensees Provide Numerical Estimates of Licensing Actions to Be Expected to Be Submitted in Fy 2000 & 2001 ML20210S9911999-07-18018 July 1999 Requests NRC Intervene for All Shareholders of New England Electric System & to Help with Merger with National Grid Group & That NRC Petition Security & Exchange Commission to Investigate Matter Relative to No Shareholder Options B17835, Forwards Rev 33 to Millstone Station Physical Security Plan, Per 10CFR50.54(p)(2).Licensee Determined That Changes Do Not Decrease Effectiveness of Plan.Rev Withheld from Public Disclosure,Per 10CFR2.790(d)(1)1999-07-16016 July 1999 Forwards Rev 33 to Millstone Station Physical Security Plan, Per 10CFR50.54(p)(2).Licensee Determined That Changes Do Not Decrease Effectiveness of Plan.Rev Withheld from Public Disclosure,Per 10CFR2.790(d)(1) B17818, Provides NRC Staff with Change to TS Bases Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only.Change Was Reviewed & Approved by Unit 3 Plant Operations Review Committee IAW Provisions of 10CFR50.591999-07-16016 July 1999 Provides NRC Staff with Change to TS Bases Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only.Change Was Reviewed & Approved by Unit 3 Plant Operations Review Committee IAW Provisions of 10CFR50.59 B17824, Forwards Monthly Oeprating Rept for June 1999 & Revised Monthly Operating Rept for May 1999 for Millstone Unit 21999-07-13013 July 1999 Forwards Monthly Oeprating Rept for June 1999 & Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20212K1701999-07-13013 July 1999 Submits Concerns Re Millstone & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Should Provide Adequate Emergency Planning in Case of Radiological Accident B17816, Provides Certification That M Lettrich,Has Completed Eligibility Requirements,Per 10CFR55.31 for Operator License.Util Requests That Licensing Action Be Taken for Named Individual1999-07-0101 July 1999 Provides Certification That M Lettrich,Has Completed Eligibility Requirements,Per 10CFR55.31 for Operator License.Util Requests That Licensing Action Be Taken for Named Individual B17801, Forwards 10CFR50.59 Annual Rept for Period Jan-Dec 1998. Various Changes That Were Initiated in Previous Yrs & Completed in 1998,also Incorporated Into Annual Rept1999-06-30030 June 1999 Forwards 10CFR50.59 Annual Rept for Period Jan-Dec 1998. Various Changes That Were Initiated in Previous Yrs & Completed in 1998,also Incorporated Into Annual Rept B17819, Forwards Rev 17 to FSAR & Addendum 6 to Annual Rept.Nneco Recently Completed Review of Unit 2 Design & Licensing Bases Which Resulted in Changes to FSAR Provided in Encl 1.Encl 2 Includes Info Covering Changes Not Included in1999-06-30030 June 1999 Forwards Rev 17 to FSAR & Addendum 6 to Annual Rept.Nneco Recently Completed Review of Unit 2 Design & Licensing Bases Which Resulted in Changes to FSAR Provided in Encl 1.Encl 2 Includes Info Covering Changes Not Included in B17780, Forwards Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) TR, IAW 10CFR50.54(a)(3).Changes to TR Are Shown as Text in Bold Italics1999-06-30030 June 1999 Forwards Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) TR, IAW 10CFR50.54(a)(3).Changes to TR Are Shown as Text in Bold Italics B17723, Responds to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for Units 2 & 3 Encl.Without Encl1999-06-29029 June 1999 Responds to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for Units 2 & 3 Encl.Without Encl B17767, Forwards Rev 12 to FSAR & Addendum 3 to Annual Rept, for Millstone Unit 3,per 10CFR50.71(e) & 10CFR50.4(b)(6). No New Regulatory Commitments Contained in Ltr1999-06-29029 June 1999 Forwards Rev 12 to FSAR & Addendum 3 to Annual Rept, for Millstone Unit 3,per 10CFR50.71(e) & 10CFR50.4(b)(6). No New Regulatory Commitments Contained in Ltr 1999-09-03 Category:UTILITY TO NRC MONTHYEARML20064A8071990-09-11011 September 1990
[Table view]Forwards Core Operating Limits Rept for Four & Three Loop Operation,Per Tech Spec 6.9.1.6.d A08900, Responds to Expressing NRC Views on Access to Util Internal or third-party Assessment Repts.Believes Internal Analysis to Support Amend of One of Util NRC OLs to Authorize Higher Power Level Is within NRC Purview & Access1990-09-11011 September 1990 Responds to Expressing NRC Views on Access to Util Internal or third-party Assessment Repts.Believes Internal Analysis to Support Amend of One of Util NRC OLs to Authorize Higher Power Level Is within NRC Purview & Access B13628, Forwards Correction to Error Discovered in Util 900727 Response to Notice of Violation from Insp Rept 50-336/90-09. Statement Corrected to Read That Contract Personnel That Have long-term Assignments,Certified as Testing Personnel1990-09-0707 September 1990 Forwards Correction to Error Discovered in Util 900727 Response to Notice of Violation from Insp Rept 50-336/90-09. Statement Corrected to Read That Contract Personnel That Have long-term Assignments,Certified as Testing Personnel B13624, Forwards Addl Info Re Relief Request from ASME Code Section XI Requirements for Temporary Repair to Piping Adjacent to Valve 2-SW-97A,per 900817 Telcon1990-09-0505 September 1990 Forwards Addl Info Re Relief Request from ASME Code Section XI Requirements for Temporary Repair to Piping Adjacent to Valve 2-SW-97A,per 900817 Telcon A08977, Advises of Commitment to Install Hardened Wetwell Vent at Facility,In Response to NRC .Util Will Be Proceeding W/Initial Design & Engineering of Hardened Vent, to Support Installation During 1993 Refueling Outage1990-09-0404 September 1990 Advises of Commitment to Install Hardened Wetwell Vent at Facility,In Response to NRC .Util Will Be Proceeding W/Initial Design & Engineering of Hardened Vent, to Support Installation During 1993 Refueling Outage B13626, Informs That Info Provided in Re safety-related Equipment Classification Programs Also Applicable for Unit 3 of Facility1990-08-31031 August 1990 Informs That Info Provided in Re safety-related Equipment Classification Programs Also Applicable for Unit 3 of Facility B13596, Forwards Millstone Unit 3 Individual Plant Exam for Severe Accident Vulnerabilities, Per Generic Ltr 88-20.Rept Identified That No Major Severe Accident Vulnerabilities Requiring Corrective Action Needed1990-08-31031 August 1990 Forwards Millstone Unit 3 Individual Plant Exam for Severe Accident Vulnerabilities, Per Generic Ltr 88-20.Rept Identified That No Major Severe Accident Vulnerabilities Requiring Corrective Action Needed B13618, Forwards Addl Info on Util 900815 Relief Request from ASME Code Section XI Requirements,Per 10CFR50.55a(g)(6)(i),for Repairs to Pipe 3SWP-006-050-031990-08-24024 August 1990 Forwards Addl Info on Util 900815 Relief Request from ASME Code Section XI Requirements,Per 10CFR50.55a(g)(6)(i),for Repairs to Pipe 3SWP-006-050-03 ML20059C2061990-08-23023 August 1990 Forwards Vols 1 & 2 to Semiannual Radioactive Effluents Release Rept Jan-June 1990, Per 10CFR50.36a.Rept Includes Summary of Quantities of Solid Radwaste & Liquid & Gaseous Effluents A08918, Responds to Notice of Violation & Proposed Imposition of Civil Penalty Re Insp Rept 50-245/90-08.Mitigation of Civil Penalty Requested.Corrective Action:List of Procedural Changes Provided1990-08-22022 August 1990 Responds to Notice of Violation & Proposed Imposition of Civil Penalty Re Insp Rept 50-245/90-08.Mitigation of Civil Penalty Requested.Corrective Action:List of Procedural Changes Provided B13610, Requests Relief from ASME Boiler & Pressure Vessel Code Section XI Requirements Re Mods to Pipe 3SWP-006-050-03. Results of Insps & Required Repairs Will Determine Schedule for Future Insps1990-08-15015 August 1990 Requests Relief from ASME Boiler & Pressure Vessel Code Section XI Requirements Re Mods to Pipe 3SWP-006-050-03. Results of Insps & Required Repairs Will Determine Schedule for Future Insps B13595, Notifies NRC That Utils Volunteer to Participate in Emergency Response Data Sys Project for All Four Nuclear Units,Per Generic Ltr 89-15 & NUREG-13941990-08-14014 August 1990 Notifies NRC That Utils Volunteer to Participate in Emergency Response Data Sys Project for All Four Nuclear Units,Per Generic Ltr 89-15 & NUREG-1394 B13607, Requests Relief from ASME Code Section XI to Reflect Mod to Piping Adjacent to Valve 2-SW-97A,in Response to Generic Ltr 90-051990-08-10010 August 1990 Requests Relief from ASME Code Section XI to Reflect Mod to Piping Adjacent to Valve 2-SW-97A,in Response to Generic Ltr 90-05 A08845, Responds to NRC Backfit Analyses of Hardened Wetwell Vent, Contained in .Benefit of Installing Hardened Wetwell Vent to Satisfy Basic Design Objective of Preventing core-melt Event Not Sufficient for Immediate Decision1990-08-0808 August 1990 Responds to NRC Backfit Analyses of Hardened Wetwell Vent, Contained in .Benefit of Installing Hardened Wetwell Vent to Satisfy Basic Design Objective of Preventing core-melt Event Not Sufficient for Immediate Decision ML20058N2181990-08-0707 August 1990 Notification of Change in Senior Operator Status.Util Determined That Need to Maintain Senior OL of LS Allen No Longer Exists.Determination Effective 900719 ML20058M8321990-08-0707 August 1990 Discusses Spent Fuel Racks Poison Surveillance Coupon Boraflex Degradation.Visual Exam of Remaining Surveillance Coupons Revealed Similar Situation Existed in All Coupon Samples B13590, Responds to NRC 900718 Request for Addl Info Re Util 900418 Request for Schedular Exemption from 10CFR50,App E,Section IV.F.3 to Allow Dec 1990 Full Participation Exercise to Be Exchanged W/Oct 1991 Partial Participation Exercise1990-08-0101 August 1990 Responds to NRC 900718 Request for Addl Info Re Util 900418 Request for Schedular Exemption from 10CFR50,App E,Section IV.F.3 to Allow Dec 1990 Full Participation Exercise to Be Exchanged W/Oct 1991 Partial Participation Exercise A08881, Responds to NRC Re Violations Noted in Insp Rept 50-423/90-08.Corrective Action:Operators Directly Involved W/Event Removed from Licensed Duties & Counseled by Operations Manager on Causes of Event1990-07-31031 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-423/90-08.Corrective Action:Operators Directly Involved W/Event Removed from Licensed Duties & Counseled by Operations Manager on Causes of Event B13594, Forwards Rev 13 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21(b) & 2.790(a))1990-07-30030 July 1990 Forwards Rev 13 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21(b) & 2.790(a)) ML20055J4621990-07-27027 July 1990 Advises That Need to Maintain OL or Senior OL for Listed Individuals No Longer Exists,Effective 900701 A08565, Responds to NRC 900302 Request for Addl Info Re LPCI Swing Bus Transfer Design & Single Failure Vulnerabilities1990-07-26026 July 1990 Responds to NRC 900302 Request for Addl Info Re LPCI Swing Bus Transfer Design & Single Failure Vulnerabilities B13585, Provides Supplemental Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of Unresolved Safety Issue A-47.Plant Procedures Modified to Provide Operability Verification of Steam Generator Protection Sys1990-07-26026 July 1990 Provides Supplemental Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of Unresolved Safety Issue A-47.Plant Procedures Modified to Provide Operability Verification of Steam Generator Protection Sys B13592, Requests Extension to Respond to NRC Backfit Analyses of Hardened Wetwell Vent1990-07-24024 July 1990 Requests Extension to Respond to NRC Backfit Analyses of Hardened Wetwell Vent ML20063P9791990-07-23023 July 1990 Notification of Change in SL Jackson Status Effective 900701,due to Permanent Reassignment within Util B13566, Advises That Util Has Reasonable Assurance That Safety Relief Valves Operable & Will Perform as Expected Until Next Outage1990-07-20020 July 1990 Advises That Util Has Reasonable Assurance That Safety Relief Valves Operable & Will Perform as Expected Until Next Outage B13563, Discusses Util Comprehensive Review of Options Re Degraded Grid Undervoltage Protection.Confirms Previous Conclusion That Splitting Loss of Normal Power Logic Would Have Overall Adverse Impact on Plant Safety1990-07-20020 July 1990 Discusses Util Comprehensive Review of Options Re Degraded Grid Undervoltage Protection.Confirms Previous Conclusion That Splitting Loss of Normal Power Logic Would Have Overall Adverse Impact on Plant Safety ML20055G5331990-07-18018 July 1990 Forwards Decommissioning Financial Assurance Certification Rept A08822, Submits Addl Info Requested Re Util Response to Generic Ltr 88-11, Radiation Embrittlement of Reactor Vessel Matls. Charpy Impact Use Values for Welds Provided in Evaluation of Irradiated Capsule W-971990-07-18018 July 1990 Submits Addl Info Requested Re Util Response to Generic Ltr 88-11, Radiation Embrittlement of Reactor Vessel Matls. Charpy Impact Use Values for Welds Provided in Evaluation of Irradiated Capsule W-97 B13588, Corrects 900703 Submittal of Results of Second in-cycle Insp of Steam Generators.All Tubes W/Cracks Stacked & Plugged1990-07-18018 July 1990 Corrects 900703 Submittal of Results of Second in-cycle Insp of Steam Generators.All Tubes W/Cracks Stacked & Plugged B13587, Requests Temporary Waiver of Compliance from Tech Spec 3.5.F.2 Re Emergency Diesel Generator (EDG) Limiting Condition for Operation.Waiver Would Extend Available Time to Repair Damaged Electrical Components1990-07-16016 July 1990 Requests Temporary Waiver of Compliance from Tech Spec 3.5.F.2 Re Emergency Diesel Generator (EDG) Limiting Condition for Operation.Waiver Would Extend Available Time to Repair Damaged Electrical Components ML20055D3461990-07-0303 July 1990 Responds to NRC Bulletin 90-001 Re Loss of Fill Oil Transmitters Mfg by Rosemount.Operability Determinations Performed & Documented for All Rosemount 1153 & 1154 Transmitters at Facility ML20055D3481990-06-29029 June 1990 Forwards Addl Info Re Facility Crdr & Isap,Including Justification for Human Engineering Discrepancies Dispositioned for No Corrective Action ML20055D7191990-06-29029 June 1990 Amends 900604 Rev 13 to QA Program B13545, Forwards Rev 3 to Updated FSAR for Millstone Unit 31990-06-29029 June 1990 Forwards Rev 3 to Updated FSAR for Millstone Unit 3 B13550, Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl1990-06-27027 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl B13499, Forwards Corrected Tech Specs Page 3/4 9-1 for Incorporation Into Proposed Amend 36 to License DPR-21 Re Auxiliary Electrical Sys1990-06-26026 June 1990 Forwards Corrected Tech Specs Page 3/4 9-1 for Incorporation Into Proposed Amend 36 to License DPR-21 Re Auxiliary Electrical Sys ML20043F8721990-06-11011 June 1990 Corrects Name of Vendor Supplying Replacement Plug Valves, Per Util 900511 Ltr.Replacement Bolts,Not Valves,Purchased from Cardinal Industrial Products Corp ML20043H0161990-06-0808 June 1990 Requests Exemption from App J to 10CFR50 for 12 Valves in Reactor Bldg Closed Cooling Water Sys.Valves Not within Definition of Containment Isolation Valves in App J & Not Required to Be Tested ML20043E8831990-06-0505 June 1990 Requests NRC Authorization to Use Plugs Fabricated of nickel-chromium-iron Uns N-06690 Matl Alloy 690 to Plug Tubes in Steam Generators of Plant ML20043D0451990-05-30030 May 1990 Discusses Proposed Rev to Tech Specs Re Facility ESF Actuation Sys Instrumentation Trip Setpoint,Per 900330 Ltr ML20042H0311990-05-0909 May 1990 Discusses Steam Generator Safety Assessment.Concludes That Continued Operation Through Remainder of Current Cycle 10 Fully Justified ML20042F0941990-04-30030 April 1990 Provides Addl Info Re Environ Impact of 900226 Application for Amend to License NPF-49,revising Tech Specs to Allow Containment Pressure to Increase to 14 Psia During Modes 1-4,per NRC Request ML20042F0661990-04-30030 April 1990 Responds to NRC 900404 Ltr Re Violations Noted in Safety Insp Rept 50-336/90-01 on 900120-0305.Corrective Action:Ler 90-004 Submitted on 900430 to Document Condition Prohibited by Plant Tech Specs ML20042E8331990-04-27027 April 1990 Forwards Annual Environ Protection Plan Operating Rept for 1989, & Monitoring Marine Environ of Long Island Sound at Millstone Nuclear Power Station Annual Rept 1989. ML20012E2681990-03-23023 March 1990 Responds to NRC 900226 Ltr Re Violations Noted in Insp Rept 50-423/89-23.Corrective Actions:Requirement to Review All Changes on Safety Sys for Potential Operating Procedure Changes Stressed to Operations & Engineering Personnel ML20012C3141990-03-13013 March 1990 Forwards Info Re Insp of Facility Emergency Operating Procedures,Per 900119 Ltr ML20012B4111990-03-0202 March 1990 Provides Addl Info Requested to Clarify Changes Proposed to Tech Spec Action Statements for Inoperable Accumulator B13453, Advises That Mods to Steam Generator Blowdown Sample Sys Completed,Per Violations Noted in Insp Rept 50-423/89-14 & Salp.Sys Will Be Evaluated for Next 2 Wks to Ensure Blowdown Radiation Monitor Operating Reliably1990-02-26026 February 1990 Advises That Mods to Steam Generator Blowdown Sample Sys Completed,Per Violations Noted in Insp Rept 50-423/89-14 & Salp.Sys Will Be Evaluated for Next 2 Wks to Ensure Blowdown Radiation Monitor Operating Reliably ML20011F7541990-02-26026 February 1990 Notifies That Jh Parillo Reassigned & No Longer in Need of License SOP-10263-2 as of 900219 ML20006G1581990-02-21021 February 1990 Forwards Response to & Comments on Initial SALP Rept 50-423/88-99 for Period 880601 - 891015.Procedures Revised to Permit Operators to Adjust Area Monitors to Reduce Nuisance Alarms 1990-09-07 |
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July 24, 1989 Docket No. 50-423 A07039 Re: NRC Bulletin 88-01 TACS 65955/65956 Mr. William T. Russell, Regional Administrator Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
References:
(1) NRC Bulletin No. 88-01: Defects in Westinghouse Circuit Breakers, dated February 5, 1988.
(2) E. J. Mroczka letter to V. T. Russell, " Response to NRC Bulletin No. 88-01", dated March 25, 1988.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 3 NRC Bulletin No. 88-01 Defects in Westinghouse Circuit Breakers Roterence (1) requires licensees using certain Westinghouse circuit breakers to perform inspections of those breakers. Reference (2) provided Northeast Nuclear Energy Company's (NNECO) initial response to Reference (1). As described in Reference (2), the two reactor trip breakers and two bypass breakers did not meet all of the Reference (1) short term inspection acceptance criteria. Therefore, the pole shafts for all four breakers were replaced during the recently completed refueling outage. All actions required by this Bulletin are now complete.
If there are any questions, please do not hesitate to contact my staff.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY
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E. K fr6dzka~ f/
Senid Vice Prefident 8908030133 890724 PDR g ADOCK 05000423 PDC
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Then personally appeared before me, E. J. Mroczka, who being duly sworn, did state that he is Senior Vice President of Northeast Nuclear Energy Company, Licensee herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Licensee herein, and that the statements contained in said information are true and correct to the best of his knowledge and belief.
11&L 1F Notary Pub MyCommission Expires March 31,1993 cc: U. S. Nuclear Regulatory Commission Document Control Desk Vashington, DC 20555 D. H. Jaffe, NRC Project Manager, Millstone Unit No. 3 V. J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2, and 3 l
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