Letter Sequence Meeting |
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MONTHYEARML20207G7281986-12-22022 December 1986 Proposed Tech Specs,Changing Expiration Date of OL from 101211 to 150731 Project stage: Other ML20207G6911986-12-22022 December 1986 Application for Amend to License DPR-65,changing Expiration Date of OL from 101211 to 150731 Project stage: Request B12368, Forwards Application for Amend to License DPR-65,extending Duration of License to 40 Yrs from Date of Issuance of Ol. Fee Paid1986-12-22022 December 1986 Forwards Application for Amend to License DPR-65,extending Duration of License to 40 Yrs from Date of Issuance of Ol. Fee Paid Project stage: Request ML20206A4141987-04-0101 April 1987 Forwards Request for Addl Info Re 861222 Application for Extension of Expiration Date for License DPR-65.Response Requested within 60 Days of Ltr Receipt Project stage: RAI B12451, Submits Addl Info Re Transportation of Nuclear Fuel & Radioactive Waste to & from Facility,Per NRC 870220 Request, Including Initial U-235 Fuel Assembly Enrichment1987-04-0303 April 1987 Submits Addl Info Re Transportation of Nuclear Fuel & Radioactive Waste to & from Facility,Per NRC 870220 Request, Including Initial U-235 Fuel Assembly Enrichment Project stage: Other ML20209H0341987-04-24024 April 1987 Forwards Request for Addl Info in Order to Continue Review of 861222 Application Re Expiration of Facility OL & 860123 Submittal Re Pressurized Thermal Shock Project stage: RAI ML20214T7491987-05-28028 May 1987 Forwards Addl Info Re Nonradiological Impacts Associated w/861222 Request to Extend Duration of License to 40 Yrs from Date of Issuance of OL Project stage: Other ML20234B4001987-06-30030 June 1987 Forwards Request for Addl Info Re 861222 Application for Extension of Expiration Date for License DPR-65.Response Requested within 60 Days of Ltr Receipt Project stage: RAI A06657, Forwards Addl Info Re 861222 Application for Amend to License DPR-65,extending Duration of License to 40 Yrs from Date of Issuance of License,Per NRC 870630 Request1987-08-0404 August 1987 Forwards Addl Info Re 861222 Application for Amend to License DPR-65,extending Duration of License to 40 Yrs from Date of Issuance of License,Per NRC 870630 Request Project stage: Request A06470, Forwards Addl Info,Clarifying Info Submitted in Author Re OL Extension Amend,Per NRC 870401 Request1987-10-0505 October 1987 Forwards Addl Info,Clarifying Info Submitted in Author Re OL Extension Amend,Per NRC 870401 Request Project stage: Other ML20236V6801987-12-0202 December 1987 Notification of 871210 Meeting W/Util in Bethesda,Md to Discuss Encl Questions Re Worker Radiation Exposure Project stage: Meeting B12777, Forwards Addl Info for 861222 Amend Request for 40-yr Ol,Per NRC 871210 Request.Extent & Effectiveness of Util ALARA Programs at Other Plants Evident When Reviewing Encl Chronology Program & Achievements to Date1987-12-18018 December 1987 Forwards Addl Info for 861222 Amend Request for 40-yr Ol,Per NRC 871210 Request.Extent & Effectiveness of Util ALARA Programs at Other Plants Evident When Reviewing Encl Chronology Program & Achievements to Date Project stage: Request ML20147C3461988-01-0606 January 1988 Summary of 871210 Meeting W/Util in Bethesda,Md Re Full 40-yr OL & Status of Worker ALARA Programs at Plants.List of Attendees & Viewgraphs Encl Project stage: Meeting 1987-04-24
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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217P5261999-10-20020 October 1999 Forwards Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217E9841999-10-14014 October 1999 Forwards Petition for Leave to Intervene Submitted on 991006 by Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone ML20217D6741999-10-13013 October 1999 Responds to Tia, Re Requirements of 10CFR70.51 for Physical Inventories of Special Nuclear Matl in Spent Fuel Pool at Plant ML20216F5061999-09-16016 September 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petitions as of 990831.During August,Director'S Decision (DD-99-10) on Seabrook Issued & Petition Closed.Six Petitions Open,Five in NRR & One in Nmss.Attachment 2 Withheld ML20216F3591999-09-15015 September 1999 Informs That Encl SRM on COMSECY-99-016 Being Released to Public,Effective 990915.Encl Documents Including 990406 SRM in Response to Millstone Independent Review Team 990312 Rept & 990713 Memo from G Caputo Previously Released ML20211P7751999-09-10010 September 1999 Notification of 990923 Meeting with Util in Rockville,Md to Discuss License Termination Plan Being Prepared for Haddam Neck Plant by Cy & Contractors & Releasing Portion of Property for Unrestricted Use Before License Termination ML20211K1431999-09-0202 September 1999 Notification of 990920 Meeting with Util in Rockville,Md to Discuss Recent Developments in New England Re Industry Deregulation & Restructuring Affecting Nu Use of Performance Indicators as Operating Plant ML20210U1461999-08-13013 August 1999 Notification of 990827 Meeting with NNECO in King of Prussia,Pennsylvania to Discuss Engineering Initiatives & Backlog Management ML20210E9311999-07-26026 July 1999 Notification of 990825 Public Meeting in Waterford,Ct Re PSDAR for Plant Unit 1 ML20210K1421999-07-22022 July 1999 Informs That Recipient Designated Chairman of Millstone Assessment Panel & E Adensam,Designated Co-Chairman.Panel Established to Assist Region I & NRR in Coordination of NRC Resources for Performance Monitoring & Inspecting Millstone ML20210E0291999-07-19019 July 1999 Notification of Significant Licensee Meeting 99-42 with Util on 990811 to Discuss Licensee Turnover of Decommissioning Activities to Bechtel,Decommissioning Operations Contractor & Plans for SG Removal & Support Bldg Demolition ML20210C1631999-07-19019 July 1999 Forwards Monthly Rept Which Gives Status of 10CFR2.206 Petitions as of 990630.Six Open NRR,1 OE & 2 NMSS Petitions Available.Attachment 2 Withheld ML20209G0541999-07-13013 July 1999 Submits Director'S Guidance 99-001,effective Immediately,As Result of SRM in Response to Recommendations in Plant Independent Review Team Rept, ML20212J5161999-07-0101 July 1999 Documents,For Public Record,Interaction Between NNECO & NRC Staff Re Licensee Proposed Licensing Action Now Being Reviewed by NRC Staff ML20209D7621999-06-29029 June 1999 Notification of Meeting 99-40 on 990715 with Nuclear Energy Advisory Council in Waterford,Ct to Discuss Millstone Safety Conscious Work Environ/Employee Concerns Program ML20209D7721999-06-29029 June 1999 Notification of 990715 Meeting 99-39 with Util in Waterford, CT Re Corrective Action & Safety Conscious Work Environ/ Employee Concerns Program Team Exit Meeting ML20196F0711999-06-24024 June 1999 Notification of 990714 Meeting with Util in Rockville,Md to Discuss Results of Evaluation of Natural Gas Blast Hazards at Facility ML20212H9471999-06-22022 June 1999 Informs That No Addl Work Required on TACs M91735 & M95118 & Closes TACs Administratively ML20196F0581999-06-21021 June 1999 Discusses Update of Status of Petition,Dtd 961125,as Amended by Ltr,Dtd 961223,by Petitioners Re Millstone,Units 1,2 & 3 & Haddam Neck Nuclear Facilities ML20207F0951999-06-0404 June 1999 Forwards Figure 1 to Millstone Combined Insp Repts 50-245/99-05,50-336/99-05 & 50-423/99-05.Rept e-mailed on 990604 ML20206Q6001999-05-17017 May 1999 Notification of 990602 Meeting with Util & Bechtel in Rockville,Md to Discuss Licensing Requirements for Installation of Natural Gas Powered Electric Generating Facility at Plant Site IR 05000336/19990041999-05-10010 May 1999 Forwards Database Used by Licensee to Track Questions Asked During Osti,Insp Rept 50-336/99-04.Summary of Licensee Responses Also Provided ML20206A6041999-04-23023 April 1999 Notification of 990506 Meeting with Util in Rockville,Md to Provide Northest Nuclear Energy with Opportunity to Discuss Status of Development of post-shutdown Decommissioning Activities Rept for Unit 1 ML20206A1791999-04-22022 April 1999 Forwards Supplemental Info Related to Questions Re 50 Mile Ingestion Pathway Associated with Millstone Nuclear Facility That Were Raised During 990414 Commission Meeting on Remaining Issues Re Proposed Restart of Unit 2 ML20205R1051999-04-21021 April 1999 Discusses Closeout of TAC MA3456,which Was Taken Out to Follow Developments Re Reactor Vessel Shipment from Haddam Neck Plant DD-99-05, Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action1999-04-20020 April 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action ML20206B2371999-04-19019 April 1999 Forwards Questions & Answers Addressing Long Island Emergency Planning Issue Raised at Commission Meeting ML20205N1641999-04-0606 April 1999 Notification of Significant Licensee Meeting 99-18 with Util on 990420 in King of Prussia,Pa to Discuss Plant Unit 3 Outage Plans ML20205J1961999-03-31031 March 1999 Discusses Clarification of Enforcement Discussion in 990319 Millstone Independent Review Team Rept ML20205C3041999-03-23023 March 1999 Notification of Significant Meeting 99-15 on 990407 with NNECO in Waterford,Ct,To Discuss Operational Safety Team Insp Exit Meeting for Millstone,Unit 2 ML20207M7641999-03-16016 March 1999 Forwards Monthly Rept of Status of 10CFR2.206 Petitions as of 990228.During Feb Director'S Decision DD-99-01,DD-99-02, DD-99-03 & DD-99-04,became Final Agency Actions & Closed. Attachment 3 Filed in Central Files ML20205J2011999-03-15015 March 1999 Forwards Annotated Draft Info Notice 99-XX Re Inadvertent Discharge of Carbon Dioxide Fire Suppression Sys in Cable Spreading Room,Reflecting Util Changes ML20207H4601999-03-0404 March 1999 Notification of 990318 Meeting with Northeast Nuclear Energy Co in Waterford,Connecticut to Discuss Exit Meeting Results of Millstone Unit 2 Independent C/A Program C/A Insp Performed by NRR ML20207K4011999-03-0404 March 1999 Rev 1 to Notification of Significant Meeting 99-12 with Util on 990318 in Waterford,Ct to Discuss Recovery of Millstone, Unit 2.Location of Meeting Has Been Changed ML20207K4071999-03-0404 March 1999 Notification of Significant Licensee Meeting 99-11 with Util on 990318 in Waterford,Ct to Discuss Plans,Schedules & Progress Toward Recovery of Plant,Unit 2 ML20206U3581999-02-0303 February 1999 Notification of Significant Licensee Meeting 99-08 with Util on 990217 Re 40500 Corrective Action Team Exit Meeting ML20202H7171999-02-0202 February 1999 Forwards Draft RAI Re Reg Guide 1.97 Deviation Request Involving Containment Area Radiation ML20202H7791999-02-0202 February 1999 Forwards Draft Request for Addl Info Re Loss of Main Feedwater Transient Analysis ML20206U3621999-02-0202 February 1999 Notification of Significant Licensee Meeting 99-07 with Util on 990308 to Discuss Apparent Violation of 10CFR50.5 as Noted in NRC Correspondence to Individual , Which Referenced Office of Investigation Rept 1-97-008 ML20202H7591999-02-0101 February 1999 Forwards Draft Request for Addl Info Re Radiological Consequences of Steam Generator Tube Rupture ML20202E4391999-01-28028 January 1999 Forwards Draft RAI Transmitted by Facsimile on 990127 to R Joshi of Licensee Staff Re post-LOCA Long Term Cooling. Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20202E4511999-01-27027 January 1999 Requests Arrangements for Conference Call with Licensee to Discuss Listed Items Re Facility Electrical Mods ML20204J6171999-01-27027 January 1999 Responds to 990107 Memo Re OI General Event Inquiry Case 99-01S,NRC Handling of Harassment & Intimidation Complaints at Millstone.Listed C/As Have Been or Will Be Taken ML20202E4081999-01-27027 January 1999 Forwards Draft RAI Re Loss of Normal Feedwater Flow.Memo & Encl Do Not Convey Formal Request for Info or Represent NRC Position ML20202E3941999-01-27027 January 1999 Forwards Draft RAI Re RG 1.97, Deviation Condensate Storage Tank Level. Memo & Encl Does Not Convey Formal Request for Info or Represent NRC Position ML20202E1461999-01-27027 January 1999 Forwards Draft RAI Re Application of Leak Before Break for Surge Line Sent 990125.Memo & Encl Does Not Convey Formal RAI or Represent NRC Position ML20202E4361999-01-27027 January 1999 Forwards Draft RAI Transmitted by Facsimile on 990127 to R Joshi of Licensee Staff Re post-LOCA Long Term Cooling. Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20202E4201999-01-25025 January 1999 Requests Responses to Listed RAIs So Review Can Be Completed ML20199K4641999-01-12012 January 1999 Notification of Significant Licensee Meeting 98-04 with Util on 990201 to Discuss Apparent Violation of 10CFR50.5 as Noted in NRC Correspondence to Individual ,which Referenced OI Rept 1-97-031 ML20199A4251999-01-11011 January 1999 Informs That Time within Which Commission May Act to Review Decision of ASLB (LBP-98-28) Dismissing Proceeding in Docket Has Expired.Commission Declined Any Review.Decision Became Final Agency Act on 981229.With Certificate of Svc 1999-09-02
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217J8951999-10-21021 October 1999 Staff Requirements Memo Re Affirmation Session on 991021, Rockville,Md (Open to Public Attendance) ML20217P5261999-10-20020 October 1999 Forwards Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217E9841999-10-14014 October 1999 Forwards Petition for Leave to Intervene Submitted on 991006 by Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone ML20217D3601999-10-13013 October 1999 Staff Requirements Memo on SECY-99-223 Re Millstone Independent Review Team 990312 Rept on Allegations of Discrimination in NRC Ofc of Investigation Cases Nda: 1-96-002,1-96-007 & 1-97-007 & Associated Recommendation 6 ML20217D6741999-10-13013 October 1999 Responds to Tia, Re Requirements of 10CFR70.51 for Physical Inventories of Special Nuclear Matl in Spent Fuel Pool at Plant ML20216F5061999-09-16016 September 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petitions as of 990831.During August,Director'S Decision (DD-99-10) on Seabrook Issued & Petition Closed.Six Petitions Open,Five in NRR & One in Nmss.Attachment 2 Withheld ML20216F3591999-09-15015 September 1999 Informs That Encl SRM on COMSECY-99-016 Being Released to Public,Effective 990915.Encl Documents Including 990406 SRM in Response to Millstone Independent Review Team 990312 Rept & 990713 Memo from G Caputo Previously Released ML20211P7751999-09-10010 September 1999 Notification of 990923 Meeting with Util in Rockville,Md to Discuss License Termination Plan Being Prepared for Haddam Neck Plant by Cy & Contractors & Releasing Portion of Property for Unrestricted Use Before License Termination ML20211K1431999-09-0202 September 1999 Notification of 990920 Meeting with Util in Rockville,Md to Discuss Recent Developments in New England Re Industry Deregulation & Restructuring Affecting Nu Use of Performance Indicators as Operating Plant ML20210U1461999-08-13013 August 1999 Notification of 990827 Meeting with NNECO in King of Prussia,Pennsylvania to Discuss Engineering Initiatives & Backlog Management ML20210E9311999-07-26026 July 1999 Notification of 990825 Public Meeting in Waterford,Ct Re PSDAR for Plant Unit 1 ML20210K1421999-07-22022 July 1999 Informs That Recipient Designated Chairman of Millstone Assessment Panel & E Adensam,Designated Co-Chairman.Panel Established to Assist Region I & NRR in Coordination of NRC Resources for Performance Monitoring & Inspecting Millstone ML20210C1631999-07-19019 July 1999 Forwards Monthly Rept Which Gives Status of 10CFR2.206 Petitions as of 990630.Six Open NRR,1 OE & 2 NMSS Petitions Available.Attachment 2 Withheld ML20210E0291999-07-19019 July 1999 Notification of Significant Licensee Meeting 99-42 with Util on 990811 to Discuss Licensee Turnover of Decommissioning Activities to Bechtel,Decommissioning Operations Contractor & Plans for SG Removal & Support Bldg Demolition ML20209G0541999-07-13013 July 1999 Submits Director'S Guidance 99-001,effective Immediately,As Result of SRM in Response to Recommendations in Plant Independent Review Team Rept, ML20216F3651999-07-0707 July 1999 Staff Requirements Memo Re COMSECY-99-016, Recommendations 2 & 3 of Mirt,Re Witness Credibility & OI Conclusions,Staff Requirements Memo ML20212J5161999-07-0101 July 1999 Documents,For Public Record,Interaction Between NNECO & NRC Staff Re Licensee Proposed Licensing Action Now Being Reviewed by NRC Staff ML20209D7721999-06-29029 June 1999 Notification of 990715 Meeting 99-39 with Util in Waterford, CT Re Corrective Action & Safety Conscious Work Environ/ Employee Concerns Program Team Exit Meeting ML20209D7621999-06-29029 June 1999 Notification of Meeting 99-40 on 990715 with Nuclear Energy Advisory Council in Waterford,Ct to Discuss Millstone Safety Conscious Work Environ/Employee Concerns Program ML20196F0711999-06-24024 June 1999 Notification of 990714 Meeting with Util in Rockville,Md to Discuss Results of Evaluation of Natural Gas Blast Hazards at Facility ML20212H9471999-06-22022 June 1999 Informs That No Addl Work Required on TACs M91735 & M95118 & Closes TACs Administratively ML20196F0581999-06-21021 June 1999 Discusses Update of Status of Petition,Dtd 961125,as Amended by Ltr,Dtd 961223,by Petitioners Re Millstone,Units 1,2 & 3 & Haddam Neck Nuclear Facilities ML20207F0951999-06-0404 June 1999 Forwards Figure 1 to Millstone Combined Insp Repts 50-245/99-05,50-336/99-05 & 50-423/99-05.Rept e-mailed on 990604 ML20212A8181999-05-25025 May 1999 Staff Requirements Memo Re SECY-99-010, Closure of Order Requiring Third-Party Oversight of Northeast Nuclear Energy Implementation of Resolution of Millstone Station Employee Safety Concerns ML20206Q6001999-05-17017 May 1999 Notification of 990602 Meeting with Util & Bechtel in Rockville,Md to Discuss Licensing Requirements for Installation of Natural Gas Powered Electric Generating Facility at Plant Site IR 05000336/19990041999-05-10010 May 1999 Forwards Database Used by Licensee to Track Questions Asked During Osti,Insp Rept 50-336/99-04.Summary of Licensee Responses Also Provided ML20206B2261999-04-28028 April 1999 Staff Requirements Memo Re Briefing on Remaining Issues Related to Proposed Restart of Millstone Unit 2 (SECY-99-109) on 990414 in Rockville,Md.Briefing Open to Public Attendance ML20206B2501999-04-28028 April 1999 Staff Requirements Memo Re SECY-99-109,recovery of Millstone Nuclear Power Station,Unit 2.Commission Agreed with Staff Conclusions That Nene Satisfied 960814,independent Corrective Action Verification Program Order ML20206B9511999-04-28028 April 1999 Staff Requirements Memo Re Briefing on Remaining Issues Concerning Proposed Restart of Millstone Unit 2 (SECY-99-109) on 990414 in Rockville,Md (Open to Public) ML20206A6041999-04-23023 April 1999 Notification of 990506 Meeting with Util in Rockville,Md to Provide Northest Nuclear Energy with Opportunity to Discuss Status of Development of post-shutdown Decommissioning Activities Rept for Unit 1 ML20206A1791999-04-22022 April 1999 Forwards Supplemental Info Related to Questions Re 50 Mile Ingestion Pathway Associated with Millstone Nuclear Facility That Were Raised During 990414 Commission Meeting on Remaining Issues Re Proposed Restart of Unit 2 ML20205R1051999-04-21021 April 1999 Discusses Closeout of TAC MA3456,which Was Taken Out to Follow Developments Re Reactor Vessel Shipment from Haddam Neck Plant DD-99-05, Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action1999-04-20020 April 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action ML20206B2371999-04-19019 April 1999 Forwards Questions & Answers Addressing Long Island Emergency Planning Issue Raised at Commission Meeting ML20205H7291999-04-0606 April 1999 Staff Requirements Memo in Response to Millstone Independent Review Team 990312 Rept on Allegations of Discrimination in NRC Office of Investigations Cases 1-96-002,1-96-007, 1-97-007 & Associated Lessons Learned ML20205H7501999-04-0606 April 1999 Staff Requirements Memo in Response to EDO Memo Re OIG Inquiry,Case 99-01S & Remaining Issues from SECY-98-292.Commission Approved C/As Described in EDO Memo ML20205N1641999-04-0606 April 1999 Notification of Significant Licensee Meeting 99-18 with Util on 990420 in King of Prussia,Pa to Discuss Plant Unit 3 Outage Plans ML20205J1961999-03-31031 March 1999 Discusses Clarification of Enforcement Discussion in 990319 Millstone Independent Review Team Rept ML20205C3041999-03-23023 March 1999 Notification of Significant Meeting 99-15 on 990407 with NNECO in Waterford,Ct,To Discuss Operational Safety Team Insp Exit Meeting for Millstone,Unit 2 ML20207M7641999-03-16016 March 1999 Forwards Monthly Rept of Status of 10CFR2.206 Petitions as of 990228.During Feb Director'S Decision DD-99-01,DD-99-02, DD-99-03 & DD-99-04,became Final Agency Actions & Closed. Attachment 3 Filed in Central Files ML20205J2011999-03-15015 March 1999 Forwards Annotated Draft Info Notice 99-XX Re Inadvertent Discharge of Carbon Dioxide Fire Suppression Sys in Cable Spreading Room,Reflecting Util Changes ML20207G0521999-03-0909 March 1999 Staff Requirements Memo on SECY-99-010 Re Closure of Order Requiring independent,third-party Oversight of Northeast Nuclear Energy Co Implementation of Resolution of Millstone Station Employees Safety Concerns ML20207K4011999-03-0404 March 1999 Rev 1 to Notification of Significant Meeting 99-12 with Util on 990318 in Waterford,Ct to Discuss Recovery of Millstone, Unit 2.Location of Meeting Has Been Changed ML20207K4071999-03-0404 March 1999 Notification of Significant Licensee Meeting 99-11 with Util on 990318 in Waterford,Ct to Discuss Plans,Schedules & Progress Toward Recovery of Plant,Unit 2 ML20207H4601999-03-0404 March 1999 Notification of 990318 Meeting with Northeast Nuclear Energy Co in Waterford,Connecticut to Discuss Exit Meeting Results of Millstone Unit 2 Independent C/A Program C/A Insp Performed by NRR ML20203H1441999-02-19019 February 1999 Staff Requirements Memo Re Briefing on Status of Third Party of Oversight of Millstone Station Employee Concerns Program & Safety Conscious Work Environment on 990119 in Rockville,Md ML20206U3581999-02-0303 February 1999 Notification of Significant Licensee Meeting 99-08 with Util on 990217 Re 40500 Corrective Action Team Exit Meeting ML20202H7171999-02-0202 February 1999 Forwards Draft RAI Re Reg Guide 1.97 Deviation Request Involving Containment Area Radiation ML20202H7791999-02-0202 February 1999 Forwards Draft Request for Addl Info Re Loss of Main Feedwater Transient Analysis ML20206U3621999-02-0202 February 1999 Notification of Significant Licensee Meeting 99-07 with Util on 990308 to Discuss Apparent Violation of 10CFR50.5 as Noted in NRC Correspondence to Individual , Which Referenced Office of Investigation Rept 1-97-008 1999-09-02
[Table view] |
Text
1 MG021987 l Docket flo..- 50-213/336:
MEMORAfiDUM FOR: John F. Stolz, Director Project Directorate I-4 Division of Reactor Projects -.I/,II
- FR0ti: David !!. Jaffe, Project ffanager Project' Directorate I-4 Division of Reactor Projects'- I/II
SUBJECT:
FORTHCTING f1EETlhG WITH NORTHEAST UTILITIES (NU) ON'
. FORTY-iEAR OPERATING LICENSES
.DATE & TJhE: Thursday, December 10, 1087 8:30 a.m.
LOCATION: Room 6507 flaryland National Bank. Building Bethesda, MD ,
PURPOSE: To discuss the enclosed. questions.related to' worker- i radiation exposure ;i.
l PARTICIPANTS: NRC NU .i C Congel C Sear )
J. Stolz R.-Harris D. Jaffe R. Kacich
- 0. Lynch l
E. Branagan i C. Hinson i A. Mang j F. Akstulewicz
/
M( 8!'KO F !
l
. David H. Jaffe, Projec.t fianager- Il Project Directorate I Division of Reactor Projects I/II l
Enclosure:
As stated ;
cc: See next page St:eetings between f?RC technical staff and applicants or licensees are open for-interested men,bers of the public, petittorers, interveners, or other parties to attend as observers pursuant to "Open Veeting Statement.of I;RC Staff ;
Felicy," 43 Federal Register 28058, 6/28/78.
DJak e:1m -J 12/i/87 12/)/87 12/j/87 2
- a. ;
n 8712040478 871202 j
PDR ADOCK 05000213 i P PDR y;
..__.______._..___._____i.__'_
~
Mr. Edward J. Mroczka Millstone Nuclear Power Station Northeast Nuclear Energy Company Unit No. 2 cc: .
Gerald Garfield, Esq. Mr. Stephen E. Scace Day, Berry & Howard Superintendent Counselors at Law Millstone Nuclear Power Station City Place P. O. Box 128 .
Hartford, Connecticut 06103-3499 Waterford, Connecticut 06385 Regional Administrator, Region I Mr. Wayne D. Romberg U.S. Nuclear Regulatory Commission Vice President, Nuclear Operations Office of Executive Director for Northeast Nuclear Energy Company Operations P. O. Box 270 631 Park Avenue Hartford, Connecticut 06141-0270 King of Prussia, Pennsylvania 19406 Mr. Charles Brinkman, Manager Washington Nuclear Operations C-E Power Systems Combustion Engineering, Inc.
7910 Woodmont Avenue
- Bethesda, Maryland 20814 Mr. Lawrence Bettencourt, First Selectman Town of Waterford Hall of Records - 200 Boston Post Road Waterford, Connecticut 06385 Northeast Utilities Service Company ATTN: Mr. Richard M. Kacich, Manager Generation Facilities Licensing Post Office Box 270 Hartford, Connecticut 06141-0270 Kevin McCarthy, Director Radiation Control Unit ,
Department of Environmental
, Protection State Office Building Hartford, Connecticut 06106 Mr. Theodore Rebelowski U.S. NRC P. O. Box 615
Office of Policy & Management l
ATTH: Under Secretary Energy l Division
, 80 Washington Street l Hartford, Connecticut 06106
l .
! Mr. Edward J. Mroczka Millstone Nuclear Power Station Northeast Nuclear Energy Company Unit No. 2 ,
cc:
Gerald Garfield, Esq. Mr. Wayne D. Romberg ;
l Day, Berry & Howard Superintendent l Counselors at Law Millstone Nuclear Power Station j City Place P. O. Box 128 '
Hartford, Connecticut 06103-3499 Waterford, Connecticut 06385 i
Regional Administrator, Region I '
U.S. Nuclear Regulatory Comission Office of Executive Director for 1 Operations l l 631 Park Avenue
! King of Prussia, Pennsylvania 19406 l
Mr. Charles Brinkman, Manager 1 Washington Nuclear Operations j C-E Power Systems i Combustion Engineering, Inc.
7910 Woodmont Avenue i Bethesda, Maryland 20814 l 1' Mr. Lawrence Bettencourt, First Selectman l Town of Waterford Hall of Records - 200 Boston Post Road Waterford, Connecticut 06385 Northeast Utilities Service Company ATTN: Mr. Richard R. Laudenat, Manager ;
Generation Facildties Licensing -
rest Office Box 270 Hartford, Connecticu' 06141-0270 Kevin McCarthy, D' ector ,
Radiation Contre' Unit )
Department of 0,vironmental l Protection State Offier Building Hartford, ' nnecticut 06106 l
Mr. Ther 'are Rebelowski U.S. Nr-P. O. 4ox 615 Wateord, Connecticut 06385-0615 Of' .ce of Policy & Management l F 7N: Under Secretary Energy Division
'O Washington Street dartford, Connecticut 06106 i i
1
- - - - - - - _ - - - - - - _ - _ - - - - - - - _ _---_a
. t i
e MILLSTONE UNIT-2 LICENSE EXTENSION:
l
- 1. In Ref.1, p.1, Northeast Nuclear Energy Company. (NNECO) very briefly described the plant activities which have contributed to high annual doses '
at Millstone Unit 2 for six of the last nine years. The staff notes, however, that Millstone Unit 2 has one of the highest cumulative average exposures of any operating pressurized water reactor (PWR) in the United States. In addition, the average exposure for the three most recent years (i.e., 1984 - 1986) has remained relatively high. Given the magnitude and !
persistency of these exposures, the staff requests that NNECO provide a l more detailed breakdown of the annual occupational exposures for Millstone l Unit 2 for every year from 1978 to the present. As part of this break- i down, NNECO should identify and describe, to the extent feasible, every 1 l job performed during this period in which more than 10 person-rems were l l expended (similar to Table 8 of Reference 2). NNECO should provide its definition of "special maintenance" work and, for each job listed, should state whether this work was classified as being a special maintenance job.
- 2. For those jobs described above that are of a repetitious nature,
- a. Provide a table listing each of these jobs along with the correspond- 1 ing exposures expended for each of the years from 1978 to present !
(similar in format to the table on page 5 of the 1986 Refueling and Maintenance Outage ALARA Report).
- b. Describe the measures that NNEC0 has taken to eliminate or reduce the i frequency of perfoming these jobs, or parts of these jobs;
- c. Describe the measures that NNECO has taken to reduce exposures re-ceived from performing these jobs. For those jobs listed where the yearly exposures have increased or remained the same over the last several years, describe why efforts have been unsuccessful in reducing exposures related to these jobs.
- d. If these jobs are being performed on the same or similar equi i components, identify the components, the nature of the work (pment repair,or maintenance, or replacement), and what is being done to avoid 2 repetition. !
- 3. In Ref. 1, p. 1, NNECO stated that: "In all the aforementioned years
[1978,1980,1982,1983,1985,and1986],except1980,steamgenerator l inspection and repair projects were the primary contributor to exposure above PWR averages." It appears that steam generator related work has been a recurrent problem at Millstone Unit 2. Describe the steps that NNEC0 has taken over the preceding years to prevent these relatively high exposures from steam generator inspections and repair projects. Specifi-cally, provide the following information: l 1
- a. Identif sures (y and describe the steps that NNECO has taken to reduce expo-e.g., use inspection and repair projects. Note the time periods in which these l
1
_ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ __ _ _ _ . _ .a
f steps were taken and describe their degree of success in reducing exposures. Describe what further steps NNEC0 plans to take to reduce steam generator work related exposures,
- b. Identify and describe NNEC0's efforts to lower dose rates (e.g., f through decontamination and/or shielding) in and around steam genera-tors prior to maintenance. Describe the success of these efforts in reducing area dose rates.
I
- c. In the 1986 Annual Exposure Report, NNEC0 states that since the 1981-82 refueling outage, approximately 65% of the refueling outage exposures has been due to steam generator work. In 1986, steam generator work accounted for only 40.8% of the outage exposure. By eliminating or minimizing the amount of steam generator related work 1 performed during cutages. NNECO will have made a big step in realizing i their outage year exposure goal of 500 person-rems. Assuming that Millstone Unit 2 does not replace its current steam generators during the next five year period, provide an estimate of what percentage of I the annual exposure will be due to steam generator related work at 1 Millstone Unit 2 over each of the next five years. Identify and describe the steps that NNECD has taken to minimize the need for steam generator repairs. For example, describe any changes in water chemis-try control made io minimize steam generator tube corrosion. Have i condenser tube leaks contributed to degradation of the steam generator tubes, and, if so, what has been done to alleviate this problem? ,
- d. Describe NNECO's plans and time schedule to replace the steam genera -
tors at Millstone Unit 2. Describe what steps will be taken to ensure that NNEC0 will not have the same' recurring problems with the new steam generators. ;
'i
- e. State what jobs other than steam generator related work are large contributors to the annual dose at Millstone Unit 2 on a repetitive basis. What efforts have been made to minimize the exposures related ,
to these jobs. .
- 4. In Ref. 1, p. 2, NNEC0 stated that: "Our exposure goal of less than 500 man-rem per year includes steam generator work." However, a time frame was not given for attaining this goal. Provide NNECO's time frame ,
for meeting this goal, and describe the specific steps that NNECO will take to reduce exposures at Millstone Unit 2 to 500 person-rems per year, ,
or less. Assuming that this annual goal of 500 person-rems is for an outage year, state what the non-outage year annual exposure goal is.
Describe how you plan to implement these exposure goals by assigning individual exposure goals to the various departments at Millstone Unit 2. .
Describe how you plan to enforce these exposure goals and what steps you {
plan to take when these goals are exceeded. !
- 5. In Ref. 1, p. 3, NNECO stated that: "NNECO is taking an aggressive stand for the ALARA philosophy," and that the " Exposure Reduction Initia-tive Program is a major effort on the part of NNEC0" to reduce person-rems. Although the " Exposure Reduction initiatives" are listed on
- p. 4 of Ref. 1. these initiatives are not described in enough detail for
i the staff to reach a favorable conclusion. Describe each of the initia-tives in more detail. In particular, describe the scope, expected results
. (e.g., expected person-rem savings), schedules, costs, level of effort, '
and how these initiatives are expected to contribute towards the exposure ,
goal (s) for Millstone Unit 2 (i.e., NNECO's response to, Question #4 of Ref. 1).
- 6. Describe NNECO's criteria for performing ALARA reviews over the time period 1978 through the present. In particular, state NNECO's cutoff exposure above which an ALARA review must be performed. Provide, to the extent feasible, the percentage of jobs receiving ALARA reviews for each of the years 1978 through present. An integral part of any ALARA review is the post-job review. This review consists of comparing any differences between estimated and actual job exposures,' and recommending better ways to perform the task in the future (e.g., use of mockups and testing for operability of equipment prior to initiating the job, use of different equipment, use of shielding, changes to job procedures, erection of permanent staging and/or platforms, use of experienced workers) that would result in even lower overall exposures. Describe NNECO's procedures for evaluating and implementing post-job review ALARA recommendations which may result in lower future exposures for performing repetitive jobs. :
- 7. Provide any additional information that NNECO thinks is relevant for the staff to reach a favorable conclusion regarding the license extension at this time, rather than deferring consideration of NNEC0's request to allow NNECO additicnal time to identify root causes of, correct, and reduce i
occupational exposures at Millstone Unit 2.
References
- 1. Letter from E. J. Mroczka, NNECO, to USNRC, dated August 4,1987.
- 2. Letter from E. J. Mroczka and C. F. Sears, NNECO, to USNRC, dated December 22, 1986.
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MEETING NO,TICE DISTRIBUTION
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