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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M8771999-10-25025 October 1999 Requests That Industry Studies on long-term Spent Fuel Pool Cooling Be Provided to R Dudley at Listed Mail Stop ML20217M4331999-10-19019 October 1999 Submits Rept 17, Requal Tracking Rept from Operator Tracking Sys. Rept Was Used by NRC to Schedule Requalification Exams for Operators & Record Requal Pass Dates ML20217F5841999-10-13013 October 1999 Requests Revocation of License OP-11038-1 for GE Kingsley. Individual Has Been Reassigned to Position within Naesco ML20217F5811999-10-13013 October 1999 Forwards Insp Data & Naesco Evaluation of a EDG Exhaust Insp Conducted on 990407.Insp Ensured That Unacceptable Wall Thinning Will Not Occur During 40-year Design Lifetime of Sys ML20217C7321999-10-0808 October 1999 Forwards Copy of Seabrook Station Videotape Entitled, Completion of Seal Barrier Installation. Videotape Documents Process of Selecting,Designing & Installing Seal Deterrent Barrier to Preclude Entrapment of Seals ML20217B8621999-10-0505 October 1999 Forwards Rev 28,change 1 to EPIP Er 1.1, Classification & Emergencies, Per 10CFR50.54(q).Rev to Procedure Does Not Decrease Effectiveness of Seabrook Station Radiological Emergency Plan ML20217B7471999-10-0101 October 1999 Provides Notification of Change in PCT of More than 50 F,Per Requirements of 10CFR50.46(a)(3)(i),(ii).Tabulation of Large Break LOCA PCT Margin Utilization Applicable to Seabrook Station,Encl ML20212J8271999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Seabrook Station. Staff Conducted Reviews for All Operating NPPs to Integrate Performance Info & to Plan for Insp Activities at Facility Over Next Six Months.Plant Issues Matrix & Insp Plan Encl ML20216J2381999-09-30030 September 1999 Responds to Re Enforcement Discretion for Nuclear Plants During Y2K Transition.Nrc Expects All Licensees to Operate Nuclear Facilities Safety IAW NRC Regulations & Requirements ML20216J2421999-09-30030 September 1999 Responds to Card Received in Aug 1999,providing Comments on NRC Interim Enforcement Policy Re Enforcement Discretion for Nuclear Plants During Y2K Transition.Informs That Naesc Reported Seabrook as Y2K Ready Prior to 990701 ML20216J2471999-09-30030 September 1999 Responds to Which Provided Comments on NRC Interim Enforcement Policy Re Enforcement Discretion for Nuclear Plants During Y2K Transition.Informs That Naesc Reported Seabrook as Y2K Ready Prior to 990701 ML20212K7921999-09-30030 September 1999 Confirms 990922 Telcon with J D'Antonio & T Grew Re Arrangements Made for NRC to Inspect Licensed Operator Requalification Program at Seabrook Facility ML20212J0301999-09-24024 September 1999 Forwards Insp Rept 50-443/99-10 on 990726-30 & 0809-13.No Violations Noted.Insp Discussed ML20212G5071999-09-21021 September 1999 Submits Complaint to NRC Re NRC Failure to Cite Seabrook Station NPP Operators for Failing to Periodically Calibrate & Establish Adequate Measures to Insure That Relay Equipment Met All Required Calibration Settings Prior to Installation ML20212C1881999-09-20020 September 1999 Ack Receipt of Which Raised Concerns Re NRC Enforcement Actions at Plant & Issuance of NCVs ML20212D1401999-09-17017 September 1999 Forwards SE Accepting Request to Use Proposed Alternative to Certain Weld Repair Requirements in ASME Boiling & Pressure Vessel Code ML20212B9511999-09-17017 September 1999 Forwards NRC Form 396 for MG Sketchley,License SOP-10685, Along with Supporting Medical Exam Info.Nrc Form 396 Has Been Superceded by Revised Version Dtd 971222,which Was Previously Submitted to NRC on 990812.Encl Withheld ML20212C3621999-09-15015 September 1999 Forwards Rev 34 to Seabrook Station Radiological Emergency Plan & Rev 85 to Seabrook Station Emergency Response Manual, Per 10CFR50,App E & 10CFR50.4 ML20212B5021999-09-14014 September 1999 Forwards Licensee Responses to EPA Questions Re Plant Seal Deterrent Barrier.Util Completed Installation of Subject Barriers on All Three Station Offshore Intake Structures on 990818.Barriers Will Preclude Entrapment of Seals ML20211Q8521999-09-0808 September 1999 Informs That Rl Couture,License SOP-11027,terminated Employment at Naesco on 990907.Revocation of License Requested ML20211N8781999-09-0303 September 1999 Forwards Response to 990820 RFI Re NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams 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 ML20211M3221999-09-0202 September 1999 Responds to NRC Re Violations Noted in Insp of License NPF-86 & Proposed Imposition of Civil Penalty. Corrective Actions:Conducted Prompt Review of Layoff Decision to Determine Relevant Facts DD-99-10, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-10) Expired.Commission Declined Review & Decision Became Final on 990830.With Certificate of Svc.Served on 9909021999-09-0202 September 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-10) Expired.Commission Declined Review & Decision Became Final on 990830.With Certificate of Svc.Served on 990902 ML20211J8811999-09-0101 September 1999 Forwards Comments on Seabrook Station Review of Reactor Vessel Integrity Database (Rvid)(Version 2).Minor Discrepancies Were Noted.Proposed Changes Are Encl in Order to Correct Discrepancies ML20211J8411999-09-0101 September 1999 Forwards Updated NRC Form 396 for E Decosta,Nrc License OP-10655-1.Without Encl ML20211G9191999-08-27027 August 1999 Informs NRC That Name of New Company, Ref in Order Approving Application Re Corporate Merger Is Nstar Which Is Massachusetts Business Trust ML20211J0401999-08-26026 August 1999 Responds to 990819 Request,On Behalf of Gr Pageau & Williams Power Corp,For Addl Time in Which to Reply to Nov,Issued on 990803.Response Due to NRC by 991008 ML20211H0651999-08-25025 August 1999 Forwards Insp Rept 50-443/99-05 on 990621-0801.One Violation Re Failure to Include Multiple Components within Scope of ISI Test Program Was Identified & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20211G7761999-08-24024 August 1999 Expresses Great Concern Re Lack of Enforcement Actions Against Seabrook Station Despite Citations NRC Has Issued for Violations of Seabrook Operating License ML20211J2171999-08-23023 August 1999 Expresses Disappointment with Lack of Enforcement Action Against Seabrook Station Despite Repeated Safety Violations ML20211J4971999-08-21021 August 1999 Submits Comments Re Violations Cited in Early Mar & 990509 Insps ML20211H8361999-08-19019 August 1999 Submits Concerns Re Violations at Seabrook Station ML20211F2681999-08-19019 August 1999 Discusses Former Chairman Jackson & 990602 Predecisional Enforcement Conference Re Findings of Ofc of Investigations Involving Allegations Raised by Contract Electrician.Determined That Allegations Not Supported ML20211J3241999-08-15015 August 1999 Expresses Disappointment in Apparent Failure of NRC to Cite Seabrook Station NPP for Recent Violations of Safety Regulations Uncovered During Recent Insps in Mar & May ML20211J1831999-08-15015 August 1999 Submits Concerns Over Serious Deficiencies at Seabrook Station That NRC Has Declined to Take Enforcement Actions Against ML20210T1601999-08-13013 August 1999 Informs That as Result of Staff Review of Licensee Responses to GL 92-01,rev,supp1 1, Reactor Vessel Structural Integrity, NRC Revised Info in Reactor Vessel Integrity Database & Is Releasing It as Rvid Version 2 ML20211J2071999-08-13013 August 1999 Expresses Concerns Re Violations Occurring Recently at Seabrook Nuclear Power Station.Requests Effort to See That Measures Taken to Stop Flagrant,Continuing Violations That Hold Danger to Workers & Community ML20210S9611999-08-13013 August 1999 Informs That NRC Received Encl Ltr from Pb Johnston Expressing Concern About Certain Impacts on Shareholders of New England Electric Sys with Respect to Nees Proposed Merger with Natl Grid Group ML20210S9511999-08-13013 August 1999 Responds to to Collins Expressing Concerns with Certain Terms of Proposed Merger Between New England Electric Sys & National Grid Group.Nrc Has No Authority to Interject Itself in Nees Merger with National Grid Group ML20210S2001999-08-12012 August 1999 Forwards NRC Forms 398 & 396 in Support of Applications for Renewal of Operator Licenses for Individuals Listed Below. Without Encls ML20210R8401999-08-11011 August 1999 Forwards Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20210S7331999-08-11011 August 1999 Submits Third Suppl to 980423 Application to Renew NPDES Permit NH0020338 for Seabrook Station.Suppl Provides Addl Info on Input Streams & Requests Increased Permit Limit for Chemical Used in Makeup Water Treatment Sys ML20210R9581999-08-11011 August 1999 Forwards ISI Exam Rept of Seabrook Station, for RFO 6, Period 3,for Insps Conducted Prior to & During Sixth Refueling Outage Concluded on 990510 ML20210Q7441999-08-11011 August 1999 Forwards Order Approving Indirect Transfer of Control of Canal Interest in Seabrook Station Unit 1 as Requested in Application & SER ML20210R7931999-08-10010 August 1999 Forwards Cycle 7 Startup Rept for Seabrook Station, IAW Requirements of TS 6.8.1.1 ML20210N9421999-08-0505 August 1999 Informs That North Atlantic Suggests Listed Revisions to 990730 Draft Revisions to Committee Rept & Order.Further Revs Consistent with What North Atlantic Proposed at 990608 Hearing ML20210N5721999-08-0303 August 1999 Discusses Investigations Rept 1-98-005 Conducted by OI at Naesco,Seabrook Station & Forwards NOV & Proposed Imposition of Civil Penalty - $55,000.Violation Re Failure to Promptly Correct Incorrectly Terminated Cables of Control Bldg Air ML20210P3361999-08-0303 August 1999 Discusses Investigation Rept 1-98-005 Conducted by Region I OI at Naesco,Seabrook Station & Forwards Nov.Violations Re Electrical Wiring in Control Panel for Control Bldg Air Conditioning Sys ML20210P3161999-08-0303 August 1999 Discusses Investigation Rept 1-98-005,conducted Between 980129 & 0527 at Seabrook Station & Forwards Nov.Violation Re Discrimination of Williams Power Corp,Contractor of Naesco,Against Electrician for Raising Safety Issues 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217F5841999-10-13013 October 1999 Requests Revocation of License OP-11038-1 for GE Kingsley. Individual Has Been Reassigned to Position within Naesco ML20217F5811999-10-13013 October 1999 Forwards Insp Data & Naesco Evaluation of a EDG Exhaust Insp Conducted on 990407.Insp Ensured That Unacceptable Wall Thinning Will Not Occur During 40-year Design Lifetime of Sys ML20217B8621999-10-0505 October 1999 Forwards Rev 28,change 1 to EPIP Er 1.1, Classification & Emergencies, Per 10CFR50.54(q).Rev to Procedure Does Not Decrease Effectiveness of Seabrook Station Radiological Emergency Plan ML20217B7471999-10-0101 October 1999 Provides Notification of Change in PCT of More than 50 F,Per Requirements of 10CFR50.46(a)(3)(i),(ii).Tabulation of Large Break LOCA PCT Margin Utilization Applicable to Seabrook Station,Encl ML20212G5071999-09-21021 September 1999 Submits Complaint to NRC Re NRC Failure to Cite Seabrook Station NPP Operators for Failing to Periodically Calibrate & Establish Adequate Measures to Insure That Relay Equipment Met All Required Calibration Settings Prior to Installation ML20212B9511999-09-17017 September 1999 Forwards NRC Form 396 for MG Sketchley,License SOP-10685, Along with Supporting Medical Exam Info.Nrc Form 396 Has Been Superceded by Revised Version Dtd 971222,which Was Previously Submitted to NRC on 990812.Encl Withheld ML20212C3621999-09-15015 September 1999 Forwards Rev 34 to Seabrook Station Radiological Emergency Plan & Rev 85 to Seabrook Station Emergency Response Manual, Per 10CFR50,App E & 10CFR50.4 ML20211Q8521999-09-0808 September 1999 Informs That Rl Couture,License SOP-11027,terminated Employment at Naesco on 990907.Revocation of License Requested ML20211N8781999-09-0303 September 1999 Forwards Response to 990820 RFI Re NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams 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 ML20211M3221999-09-0202 September 1999 Responds to NRC Re Violations Noted in Insp of License NPF-86 & Proposed Imposition of Civil Penalty. Corrective Actions:Conducted Prompt Review of Layoff Decision to Determine Relevant Facts ML20211J8411999-09-0101 September 1999 Forwards Updated NRC Form 396 for E Decosta,Nrc License OP-10655-1.Without Encl ML20211J8811999-09-0101 September 1999 Forwards Comments on Seabrook Station Review of Reactor Vessel Integrity Database (Rvid)(Version 2).Minor Discrepancies Were Noted.Proposed Changes Are Encl in Order to Correct Discrepancies ML20211G9191999-08-27027 August 1999 Informs NRC That Name of New Company, Ref in Order Approving Application Re Corporate Merger Is Nstar Which Is Massachusetts Business Trust ML20211G7761999-08-24024 August 1999 Expresses Great Concern Re Lack of Enforcement Actions Against Seabrook Station Despite Citations NRC Has Issued for Violations of Seabrook Operating License ML20211J2171999-08-23023 August 1999 Expresses Disappointment with Lack of Enforcement Action Against Seabrook Station Despite Repeated Safety Violations ML20211J4971999-08-21021 August 1999 Submits Comments Re Violations Cited in Early Mar & 990509 Insps ML20211H8361999-08-19019 August 1999 Submits Concerns Re Violations at Seabrook Station ML20211J3241999-08-15015 August 1999 Expresses Disappointment in Apparent Failure of NRC to Cite Seabrook Station NPP for Recent Violations of Safety Regulations Uncovered During Recent Insps in Mar & May ML20211J1831999-08-15015 August 1999 Submits Concerns Over Serious Deficiencies at Seabrook Station That NRC Has Declined to Take Enforcement Actions Against ML20211J2071999-08-13013 August 1999 Expresses Concerns Re Violations Occurring Recently at Seabrook Nuclear Power Station.Requests Effort to See That Measures Taken to Stop Flagrant,Continuing Violations That Hold Danger to Workers & Community ML20210S2001999-08-12012 August 1999 Forwards NRC Forms 398 & 396 in Support of Applications for Renewal of Operator Licenses for Individuals Listed Below. Without Encls ML20210R8401999-08-11011 August 1999 Forwards Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20210R9581999-08-11011 August 1999 Forwards ISI Exam Rept of Seabrook Station, for RFO 6, Period 3,for Insps Conducted Prior to & During Sixth Refueling Outage Concluded on 990510 ML20210R7931999-08-10010 August 1999 Forwards Cycle 7 Startup Rept for Seabrook Station, IAW Requirements of TS 6.8.1.1 ML20210K3281999-07-30030 July 1999 Forwards Response to NRC RAI Re License Amend Request 98-17. North Atlantic Concurs with Staff That Bases Should State That Maintaining ECCS Piping Full of Water from RWST to Reactor Coolant Sys Ensures Sys Will Perform Properly ML20210H8991999-07-27027 July 1999 Forwards Tabulation of Current LBLOCA & SBLOCA Peak Clad Temp Margin Utilization Tables Applicable to Seabrook Station ML20210H0921999-07-27027 July 1999 Forwards Naesc Semi-Annual Fitness-for-Duty Rept,Jan-June 1999, Per 10CFR26.71(d).Rept Includes Data from 990101- 0610 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 ML20210A2521999-07-15015 July 1999 Forwards Rev 33 to Seabrook Station Radiological Emergency Plan & Rev 84 to Seabrook Station Emergency Response Manual ML20209J0601999-07-14014 July 1999 Forwards Rev 11 to Vols 1-10 of State of Nh Radiological Emergency Response Plan & Vols 11-50 to Town Radiological Emergency Response Plans,In Support of Vermont Yankee & Seabrook Station.Vols 17-19 of Were Not Included ML20209G1351999-07-0909 July 1999 Forwards Relief Request Re Repair Welding on SA-351 Matl to Be Installed in Seabrook Station SW Pumps & SW Cooling Tower Pumps ML20209D2871999-07-0606 July 1999 Submits Response to NRC AL 99-02,re Numerical Estimate of Licensing Actions Expected to Be Submitted in Fy 2000 & 2001.Schedule Does Not Include Activities Which Meet AL Definition of Complex Review ML20209C9021999-06-30030 June 1999 Provides Revised Distribution List for Seabrook Station Correspondence to Reflect Current Organization ML20196G2391999-06-23023 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant Encl ML20196G3381999-06-23023 June 1999 Forwards LAR 99-19 for License NPF-86,increasing AOT for Cracs from 30 Days to 60 Days on One Time Basis for Each Train to Facilitate on-line Implementation of Design Enhancements During Current Operating Cycle ML20195J0981999-06-17017 June 1999 Forwards Responses to Questions Posed in Re Application of New England Power Co for Transfer of Control of Licenses NPF-49 & NPF-86.Copy of 1998 Schedule 13G, Included,As Requested ML20196D0561999-06-16016 June 1999 Forwards Certified Copy of Endorsements 77 & 78 to Nelia to Policy NF-0296 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 ML20195J1221999-06-15015 June 1999 Forwards Addl Clarifying Info to Suppl Info Provided at 990602 Predecisional Enforcement Conference at Region I. Proprietary Declarations by Util Employees to Correct Inaccuracies Encl.Proprietary Info Withheld,Per 10CFR2.790 ML20210K4971999-06-15015 June 1999 Forwards Copy of Ltr from Concerned Constitutent AC Menninger from Franconia,Nh to Senator Smith Re Seabrook Nuclear Power Station Y2K Readiness ML20195E9731999-06-0707 June 1999 Forwards Rev 32 to Seabrook Station Radiological Emergency Plan & Rev 83 to Emergency Response Manual ML20206T4201999-05-20020 May 1999 Forwards Certified Copies of Resolution Adopted by Shareholders of National Grid Group Approving Acquisition of New England Electric Sys & Vote of New England Electric Sys Shareholders Approving Merger with National Grid Group ML20196L2001999-05-0707 May 1999 Forwards Rev 01-07-00 to RE-21, Cycle 7 COLR, Per TS 6.8.1.6.c ML20206K4301999-05-0707 May 1999 Forwards Copy of Corrective Order of Notice by State of Nh Nuclear Decommissioning Financing Committee ML20206J3321999-05-0505 May 1999 Forwards Tabulation of Number of Tubes Plugged in Each of Two SGs Inspected During Sixth Isi,Per Plant TS SR 4.4.5.5a. Sixth ISI Was Completed on 990420 ML20206J3341999-05-0505 May 1999 Informs That on 990501,ISO New England & New England Power Pool Implemented Restructured Wholesale Electricity Market. Summary of Util Action as Result of Implementation of Subject Market,Encl 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 ML20206G4371999-04-30030 April 1999 Forwards 1998 Annual Environ Operating Rept for Seabrook Station.Encl Rept Is Summary of Implementation of EPP for Period of Jan-Dec 1998 ML20206H4801999-04-30030 April 1999 Forwards 1998 Annual Radioactive Effluent Release Rept for Seabrook Station. Listed Info Provided in Encls 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059K5221990-09-14014 September 1990 Responds to NRC Re Violations Noted in Insp Rept 50-443/90-15.Corrective Actions:Procedure ON1090.04 Revised to Require That Whenever Containment Entry Made,Entry Logged in Action Statement Status Log ML20059K5951990-09-14014 September 1990 Forwards Endorsement 29 to Nelia Policy NF-296,Endorsement 22 to Maelu Policy MF-127,Endorsement 9 to Nelia Policy N-109 & Maelu Policy M-109 ML20059K1051990-09-13013 September 1990 Advises of 1990 Biennial Exercise Meeting Scheduled for 900928 at Facility to Discuss Comments Re objectives/extent- of-play Submittal & Present Operational & Radiological Details of Scenario.Suggested Agenda Encl ML20059D6971990-08-30030 August 1990 Forwards 10CFR50.59 Quarterly Rept for Apr-June 1990 ML20064A4001990-08-21021 August 1990 Forwards, New Hampshire Yankee Fitness-For-Duty Semiannual Rept,900103-0630 ML20059B0231990-08-21021 August 1990 Forwards Addl Info Re Topics Discussed on 900816 Concerning Licensees Response to Intervenors Emergency Motion to Reopen Record on Adequacy of Staffing of New Hampshire Radiological Emergency Response Plan & Immediate Shutdown ML17348B4921990-08-15015 August 1990 Forwards Revised Evacuation Time Estimates Incorporating Vehicles Hidden from Aerial Observation,Per ALAB-932 & ASLB Memorandum & Order LBP-90-20.Revised Estimates Will Be Incorporated Into Radiological Emergency Response Plan ML20059A3051990-08-14014 August 1990 Informs of Closing on United Illuminating Co Sale & Leaseback Transaction on 900809,per Amend 1 to License. Transaction Conforms to Description in Amend Application, ,as Supplemented by 900426 & 0606 Ltrs ML20058L9571990-08-0303 August 1990 Forwards Rev 1 to Inservice Testing Program for Pumps & Valves,Adding Cold Shutdown Justification ML20058M2211990-08-0303 August 1990 Notifies of Change in Listed Licensed Operator Position. MR Breault Will Continue to Maintain Senior Operator License in New Position Until 900917 ML20055J4751990-07-26026 July 1990 Confirms That Util Completed Installation & Testing of Facility ATWS Mitigation Sys,Per 890706 Commitment ML20055J0271990-07-24024 July 1990 Forwards Rev 5 to Facility Security Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21) ML20055H5831990-07-20020 July 1990 Forwards Rev 11 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20044B1861990-07-10010 July 1990 Forwards Rev 1.B to Spmc,App H,New Hampshire Yankee Offsite Response Communications Directory & Spmc,App M,New Hampshire Yankee Offsite Response Emergency Resource Manual. ML20044A6631990-06-25025 June 1990 Responds to NRC 900524 Ltr Re Violations Noted in Insp Rept 50-443/90-10.Corrective Actions:Maint Group Instruction Issued Describing Valve Verification When Valves Not Covered by Procedure & Procedures Written Re Monitoring Skids ML20044A3741990-06-22022 June 1990 Notifies That United Illuminating Co Received Approval of State of CT Dept of Public Util Control of Sale & Leaseback of Facility ML20043H1321990-06-18018 June 1990 Forwards New Hampshire Yankee Power Ascension Assessment Self-Assessment Team Phase 2 50% Power Plateau. ML20043G4761990-06-11011 June 1990 Lists Changes in Status of Licensed Operator Positions at Facility,Per 10CFR50.74 ML20043F5791990-06-0808 June 1990 Requests That Meeting W/Nrc & Westinghouse Be Held During Wk of 900624 to Further Discuss Intended Cycle 2 Fuel Design Features & Fuel Mgt Strategies ML20043E9811990-06-0606 June 1990 Forwards Info on Owner Participation & Owner Trustee in United Illuminating Co Sale/Leaseback Transaction, Consisting of Sec Form 10K & Citicorp 1989 Annual Rept. ML20043E5371990-06-0606 June 1990 Responds to NRC 900508 Ltr Re Violations Noted in Insp Rept 50-443/90-08.Corrective Actions:Signs Will Be Placed on Containment Hatches to Remind Personnel That Retest Required After Containment Hatch Use & to Notify Control Room ML20043C5251990-05-31031 May 1990 Responds to NRC Bulletin 88-010,Suppl 1, Nonconforming Molded Case Circuit Breakers. Util Verified That Certificates of Conformance Issued by Telemecanique for All 305 Telemecanique-supplied Molded Case Circuit Breakers ML20043B7291990-05-24024 May 1990 Forwards Employee Allegation Resolution Program Radio Communication Transcript Review. Transmissions Did Not Contain Issues of Detrimental Safety Significance to Public or Plant Personnel ML20043C1031990-05-23023 May 1990 Forwards Revs 53 & 54 to Production Emergency Response Manual. ML20043F7071990-05-18018 May 1990 Forwards Addl Info Re Status of Licensee Actions in Response to INPO Evaluation Repts of Facility for 1983-1989,including Update of Response to INPO Rept of 1983 Const Project Evaluation & Evaluation of Seabrook Station Const Project. ML20042G2511990-05-0808 May 1990 Forwards Estimates of Time Impact on Facility Personnel Re Topics Identified in Generic Ltr 90-01.Info Presented in Format of Completed Questionnaire Sheets ML20042G6501990-05-0808 May 1990 Forwards Rev 10 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20042F7471990-05-0404 May 1990 Informs of 900430 Election of Le Maglathlin to Replace Jc Duffett as President & Chief Executive Officer ML20042E8371990-04-30030 April 1990 Forwards Annual Environ Operating Rept 1989, Seabrook Environ Studies 1988,Characterization of Baseline Conditions in Hampton-Seabrook Area,1975-1988,Preoperational Study for Seabrook Station & Seabrook Environ Studies... Rept. ML20012E9991990-03-30030 March 1990 Suppls Info to 890417 Submittal on Station Blackout Rule (10CFR50.63).Instrumentation Required to Cope W/Station Blackout Is safety-related & Evaluated for Operability at Elevated Temps ML20012E9881990-03-30030 March 1990 Forwards marked-up FSAR Section 13.2 (Training) Descriptive Enhancements,Per 891113 Commitment.Rev Will Be Included in 900415 FSAR ML20042D8251990-03-30030 March 1990 Requests NRC Participation at 900405 Working Session to Discuss Objectives & Extent of Play for 1990 Biennial Emergency Preparedness Exercise on 901213.Encl Withheld ML20012F0341990-03-30030 March 1990 Forwards Suppl to, Semiannual Radioactive Release Rept Initial Plant Startup Through Fourth Quarter 1989, Consisting of Dose Calculations ML20012E8751990-03-29029 March 1990 Advises That Replacement of Rosemount Transmitter from High Failure Fraction Mfg Lot Completed on 900314,per 900312 Commitment ML20012D9181990-03-21021 March 1990 Forwards Executed Amend 4 to Indemnity Agreement B-106 & Opinion Ltr from Ropes & Gray Re Signature Authority of Util as Agent for Joint Owners of Plant ML20012D9681990-03-20020 March 1990 Discusses Steam Generator Overfill Protection,Per Generic Ltr 89-19 & USI A-47, Safety Implications of Control Sys in LWR Nuclear Power Plants. Steam Generator Overfill Protection at Plant Meets Recommendations of Generic Ltr ML19324G6791990-03-15015 March 1990 Provides Info in Response to late-filed Allegations,Per 900314 Telcon ML20012B8601990-03-14014 March 1990 Clarifies 900312 Supplemental Response to Proposed Draft NRC Bulletin on Loss of Fill Oil in Rosemount Transmitters. If More Frequent Calibr Required,Transmitter Will Be Time Response Tested to Operability Acceptance Criteria ML20012B8351990-03-13013 March 1990 Notifies That Senior Operator License No Longer Required for PD Mccabe & License Considered Expired ML20012B8371990-03-13013 March 1990 Clarifies Supplemental Response to Proposed Draft NRC Bulletin on Loss of Fill Oil in Rosemount Transmitters,Per 900313 Telcon.Operability Acceptance Test Will Be Performed ML20012B6191990-03-12012 March 1990 Advises That Licensee Intends to Submit FSAR Amend 63 by 900415 Instead of 900315 ML20012B4901990-03-0808 March 1990 Forwards Corrected Response Re Allegation by Employees Legal Project Concerning Reactor Coolant Pump Support Leg Anchor Bolts ML20012B1191990-03-0707 March 1990 Responds to NRC 900205 Ltr Re Violations Noted in Insp Rept 50-443/89-17.Corrective Actions:Conduit Seals Installed on Required Solenoids & Operability Completed on 900204 ML20012C2521990-03-0606 March 1990 Documents Info Provided in Telcon Re Relief & Safety Valve Testing ML20012B3631990-03-0202 March 1990 Forwards Secondary Chemistry Annual Rept, for 1989.Rept Summarizes & Evaluates 1989 Condensate,Feedwater & Steam Generator Water Chemistry Operating Experience & Repts Total Time Secondary Water Chemistry Parameters Out of Spec ML20012A1581990-03-0101 March 1990 Submits Annual Rept of Challenges to Pressurizer PORVs & Safety Valves for Initial Criticality Period Through 891231 ML20012A1861990-03-0101 March 1990 Forwards Seabrook Station 10CFR50.59 Safety Evaluation Quarterly Rept,Oct-Dec 1989. Power Supply Breakers for Containment Lighting Panel XL4 Replaced & Smoke Detector Insp Frequency Changed to at Least Semiannually ML20012A1011990-02-26026 February 1990 Responds to Info Notice 89-045, Metalclad Low-Voltage Power Circuit Breakers Refurbished W/Substandard Parts. One molded-case Circuit Breaker Purchased from Satin American in Nov 1989 for Use in Plant Simulator ML20006F5401990-02-23023 February 1990 Submits Addl Info Re Util Maint Program,Per NRC 900221 Telcon Request.Util Maint Program Includes Preventive, Predictive & Corrective Maint as Well as Implementation of Design Enhancements ML20006G1571990-02-21021 February 1990 Forwards Renewal Application for NPDES Permit NH0020338,per App B to License NPF-67.State of Nh EPA Determined That Requested Changes to Discharges 001,022,023 & 024 Will Not Jeopardize Environ When Full Power Operation Begins 1990-09-14
[Table view] |
Text
O D WMW companyof New HempeNro SFRR00K STATION Engineering office:
1671 Worcester Road Framingham, MA 01701 January 4, 1982 E A SBN-203 T.F. B7.1.7 ,
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b -9 U.S. Nuclear Regulatory Commission "g JAN 5 1ggg -
Washington, D.C. 20555 Sum *
% rpa p Attention: Mr. Louis Wheeler; Project Manager Licensing Branch 3
Reference:
(a) Constructiort Permits CPPR - 135 and CPPR - 136, Docket Nos. 50-443 and 50-444 (b) PSNH Letter dated November 27, 1981, " Response to Acceptance Review Requests for. Additional Information (RAIs)", J. DeVincentis to D. Eisenhut
Subject:
Submittal of Additional Information; Environmental Report RAI 240.25
Dear Mr. Wheeler:
PSNH responded to NRC Acceptance Review RAIs via Reference (b).
Environmental Report RAI 240.25 (Reference (b), Enclosure 2, page 32) committed to providing additional information. This information is attached.
Very truly yours, YAN EE ATOMIC ELECTRIC COMPANY h.
,pe John De en is Project Manager
'8201060346 820104 PDR ADOCK 05000443 s i{i C PDR
240.25 Environmental Effects of Accidents (7)
(ER) Calculate the radiological consequences of a liquid pathway release from a postulated core melt accident. .The analysis should assume, unless otherwise ' justified, that there has been a penetration of _the reactor basemat by the molten core mass, and that a substantial portion of radioactively contaminated sump water was released to the ground. Doses should be compared to those calculated in the _ Liquid Pathway Generic Study (NUREG-C640, 1978). Provide a summary of your analysis procedures and the values of parameters used .(such as permeabilities, gradients.
populations affected, water use). It is suggested that meetings with the staff of the Hydrologic Engineering Section be arranged so that we may share with you the body of information necessary to -
perform this analysis.
RESPONSE: The Liquid Pathway Generic Study (LPGS)(1) calculated the population doses from accidents involving liquid pathways for design basis events and for events greater than the de sign basis.
Dr.e of the conclusions reached by this study was that doses from design basis events were much lower (in the order of several hundred man-rem to the thyroid) than from events involving core melt. This analysis for Seabrook has therefore concentrated on core melt events in determining the relative risk of Seabrook from accidents involving liquid pathways.
This determination of relative risk was made by identifying those parameters used in the LPGS analysis to calculate population doses and comparing their values at the LPGS ocean site with that at the Seabrook Station site. The ratio of each parameter is the
" multiplier" relating population doses between the two sites (see ER-OLS Table 240.25-1). Multipliers were determined for the following parts of the liquid pathways:
A. Source term B. Groundwater transport
- 1. Travel time of groundwater
- 2. Source availability
- 3. Retardation by sorption C. Surface water transport D. Usage of the water bodies
- 1. Aquatic food
- 2. Shoreline usage The foundations of the Seabrook Station reactors are located in the bedrock of t.he site. A large portion of the site, including Unit 1, is four.ded on a gneissoid phase of the Newburyport quartz diorite intrusive; a hard, durable crystalline igneous rock consisting of medium-to-course-grained quartz diorite matrix intimately enclosing inclusions of dark gray, fine-grained
r diorite. A small portion of the site, including much of Unit 2, is founded on Merrimack Group metaquartzite and granulite which occurs as a large relict inclusion welded into the enclosing Newburyport igneous mass along a broad, transitional-intrusive contact zone. The physical, chemical and mechanical qualities of the rock in the Merrimack Group metamorphic ir.clusion are comparable to those of the Newburyport igneous rock.
Groundwater at the site generally occurs between 10 and 15 feet mean sea level (MSL). The basemats of the reactors, approximately
-70 feet MSL, are below the water table.
The groundwater gradient in the region is clearly toward the ocean. There are no wells between the site and the ocean, so no drinking water pathway could be affected by an accidental contamination of the groundwater. There is virtually no possibility of a reversal of the groundwater gradient due to heavy pumping inland, particularly because such a reversal would, at the same time, cause an unacceptable intrusion of saltwater into the aquifer. Therefore, liquid radioactivity released from a core melt accident could only cause contamination by being transported through the groundwater and subsequently released to the Atlantic Ocean.
A conservative estimate of the shortest groundwater path to the nearest down gradient water body, the Browns River, is estimated to be 1,000 feet through the bedrock followed by approximately 110 feet through marine and swamp deposits. A conservative estimate of the groundwater travel time would be 48 years, 10.3 years through the bedrock portion and 37.7 years through the soil portion. Groundwater travel time in the bedrock was estimated by applying Darcy's Law and checked using dewatering information from the major excavations on site. To estimate the groundwater travel time through the soil portion of the pathway, Darcy's Law was applied using the most conservative measured or estimated parameters.
Conservative values of the retardation factors, which reflect the effects of sorption on geologic materials, were estimated for the bedrock and soil, for the two radionuclides that were important contributors to the population dose in the LPGS, i.e. , Sr-90 and Cs-137. In the bedrock, retardation f actors of 8.6 for Sr-90 and 154 for Cs-137 were used for the fractured crystalline bedrock (3). In the soil underlying the marsh, the retardation factors were conservatively estimated to be 15 for Sr-90 and 141 for Cs-137. These retardation factors were estimated using Equation B-35 of the LPGS study. The equilibrium distribution coefficients for Sr and Cs were conservatively chosen as 2 and 20, respectively. The mean transport times from the Unit I reactor building to the Atlantic Ocean is, therefore, conservatively estimated to be about 650 years for Sr-90 and about 6,900 years for Cs-137. When these travel times are compared to 5.7 years for Sr-90 and 51 years for Cs-137 in the LPGS land-based ocean site case, virtually all of the Sr-90 and Cs-137 would have decayed before reaching the surface water. Parameters used to calculate
radionuclide travel times and relativo doses are listed in ER-OLS Table 240.25-2.
Contaminants released from the shoreline would disperse in the oceanic turbulence. The LPGS made no distinction between the turbulence that would be found in the east, Gulf, or west coasts of the United' States. The only assumption which can be made without site-specific data is that the mixing at the Seabrook Station and LPGS sites is similar.
The two major liquid exposure pathways for an ocean site without a drinking water pathway, are aquatic food consumption and direct shoreline exposure. The commercial and recreational finfish and shellfish harvest for a rectangular block 80 km alongshore and stretching 40 km offshore from Seabrook Station has been estimated to be about 24.0 x 106 kg. This estimate is based on information and data obtained from the National Marine Fisheries Service. For comparison, the same size block using the LPGS ocean site fish catch densities would yield about 5.8 x 106 kg of finfish.
Therefore, fish production from the ocean in the vicinity of the Seabrook Station has been estimated to be approximately four times the generic ocean site in the LPGS. Most of the dose from fish consumption resulted from the two radionuclides discussed above however, and, since these will effectively _ decay the dose from this pathway will be much lower for Seabrook than for the LPGS site.
The annual population beach usage factor within the 50-mile radius of Seabrook was estimated in two parts. For the O to 10-mile radius of beach, the summer (June-August) transient population in the NNE through south sectors, with respect to the site, were derived from the seasonal resident, hotel / motel, campground and daily transient population groups as given on Figures 2.1-10, 2.1-11, 2.1-12, 2.1-13, 2.1-15 and 2.1-19 of the SB-FSAR. In the case of daily transients associated with beach parking lots and on-street parking, the maximum capacity figures given on FSAR Figures 2.1-15 and 2.1-19 were multiplied by 0.79 to represent the maximum observed population associated with these two categories in three years of observation. This single day (Sunday) peak observed beach population was then adjusted by applying the average observed daily population loading factor as derived from Figure 2.1-17 of the SB-FSAR. For weekdays, this factor represented 46% of the single day peak observed values, while the Saturdays' loading factor was estimated to be 66% of the Sunday observed peak. These results were then added to the other seasonal transient groups noted above. These daily population beach area inventories were then multiplied by the number of weekdays (64) or weekend days (13 Saturdays,13 Sundays) assumed to represent the summer beach season. These values were then multiplied by a daily average beach population loading factor (0.27) which corrected the peak observed population values-that relate to the maximum number of people on the beach during the height of the beach day to an hourly average value over an entire
~
I 24-hour period. This hourly loading factor was derived from the time-of-day vehicle distribution data in SB-FSAR Figure 2.1.16.
Finally, a multiplier of 0.25 is used to estimate the f raction of time that beach users, while on' the beach, are in the active area of radioactivity deposition at the ocean-shoreline interface. The resulting multiplication of peak observed population, times daily usage factor, times hourly average loading factor, times shoreline exposure period gives an estimate of the number of person-hours / year of beach use. The total 0-10 mile population 6
occupancy factor is estimated to be 9.8 x 10 person-hours / year.
The second part of the estimate involves the beach usage between 10 and 50 miles from the site. For beaches north of the site, an estimate of beach capacity of 33,148 persons (FSAR-Section 2.1.3.3.f.1.a.) was multiplied by 90 days per year summer season, the 0.27 average hourly loading factor per day, plus the 0.25 shoreline exposure fraction. For beaches south of the site, no specific beach. capacity estimates were identified. Therefore for the 40 miles of beach area assumed to be south of the site, an average capacity loading of 1 person per 2 feet of beach was used to estimate the beach capacity, and this then corrected as noted above.
The beach usage factor for the 10-50 mile radius was estimated to be 2.0 x 107 person-hour per year. The total 0-50 mile radius beach usage population value is thus estimated to be 3.0 x 10 7 person-hours / year.
The shoreline usage factors discussed above show that the total man-hours may be slightly higher than was assumed in the LPGS.
Essentially, all of the shoreline and swimming exposure in the LPGS ocean site came from Cs-137. However, since decay will remove Cs-137 before it reaches the ocean at Seabrook, this pathway can be eliminated.
The LPGS determined that accidents involving liquid pathways did not contribute significantly to public risk. This analysis has shown that liquid pathway accidents involving the Seabrook Station would be of much lower consequence than was reported for the LPGS site. Therefore these types of accidents are not expected to significantly increase the risk from the- operation of Seabrook.
Mitigating actions which could be undertaken to decrease liquid pathway impacts following a core-melt accident include the following:
- 1. Injection or withdrawal of water;
- 2. Lowering of the watertable;
- 3. Installation of a grout curtain.
For Seabrook Station; the third method, installation of a grout curtain, would be the most reasonable approach to source interdiction. The first two methods would probably not be feasible due to the local topography, location of the melt debris, and proximity of the site to the ocean.
Injection of a chemical grout slurry curtain through holes slant-drilled to a depth below the core debris could be engineered to form an effective waterproof seal around the debris creating a permanent isolation barrier.
s REFERENCES TO 240.25
- 1. U.S.- Nuclear Regulatory Commission,1978, " Liquid Pathway Generic Study",
NUREG-0440, February 1978.
- 2. FSAR Seabrook Station, Units 1 and 2.
- 3. Draft Environmental Statement, V.C. Summer Station / Unit No. 1, NUREG-0534 Supplement, USNRC, November 1980.
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TABLE 240.25-1 Summary of Factors in Seabrook and LPGS Ocean Site Comparison Factor LPGS Seabrook Multiplier A. Source Term 3411 Mwth 3411 Mwth Equal to unity
- B. Groundwater Transport
- 1. Travel time 6.7 ft/ day 0.26 ft/ day Much less than of water in bedrock unity 0.008 ft/ day in soil
- 2. Source Ecurce directly Source directly. Equal .to unity availability immersed in -immersed in flowing flowing groundwater groundwa ter
- 3. Re ta rdation 9.2 for Sr 8.6 for Sr, Less than unity coefficients bedrock 83 for Cs 154 for Cs, bedrock 15 for Sr, soil 141 for Cs, soil C. Surface Water - -
Assumed equal to Transport unity D. Usage
- 1. Aquatic food 5.8 x 106 kg 24.0 x 106 kg Approximately finfish finfish and equal to 4 shellfish
- 2. Shoreline 1.1 x 107 3 x 107 Approximately usage man-hrs /yr man-brs/yr equal to 3 w _ _ _ _ _ - _ _ _ . - _ _ _ _ . .
FL
, . w TABLE 240.25-2 Parameters Used for Seabrook Station Parameter Value Permeabilities .Kbedrock = 2.1 gpd/ft 2 Ksoil = 0.6 gpd/ft 2 Groundwater gradients Ibedrock = 0.014 ft/ft Isoil = 0.02 ft/ft Distance from reactor to nearest- Lbedrock = 1,000 ft surface water leading to ocean
= 110 ft
~Lsoil Ltotal = 1,110 ft Retardation factors for ion exchange Sr - 8.6 bedrock,1S soil-in' soil Cs - 154 bedrock, 141. soil Porosity Bedrock = 0.015 Soil- = 0.2'
. Fish harvest statistics Commercial 0-3 miles '214 kg/ha/yr 3-12 miles 42 kg/ha/yr 12-200 miles 17.3 kg/ha/yr Recreational. 0-3 miles 87 kg/ha/yr 3-12 miles 26.5 kg/ha/yr 12-25 miles 7.6 kg/ha/yr Shoreline usage beach season duration weekdays 64 days Saturdays 13 days Sundays 13 days
[- beach population-(daily weekdays 59,216 persons peak values) (0-10 miles)
Saturdays. -78,601 persons (0-10 miles)
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-4 ..
D
- ,C I' A~
- b . TABLE 240.25-2 Parameters Used for: Seabrook Station -
(Continued)
Sundays .
93,799 persons-(0-10. miles)
All days 138,748 persons-
'(10-50 miles)
Shoreline usage
-average daily population .27 beach loading-factor-fraction of time persons .25-on beach are in active land-ocean interface zone I
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