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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
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2 LJ George S. Thomas Vice President-Nuclear Production June 4, 1986 New Hampshire Yankee Division SBN- 1088 T.F. B7.1.2 United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. Vincent S. Noonan, Project Director PWR Project Directorate No. 5
References:
(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) PSNH Letter (SBN-887), dated October 31, 1985,
" Control of Heavy Loads: NUREG-0612 (Revised Report)", J. DeVincentis to G. W. Knighton Su'oj e ct : Control of Heavy Loads: NUREG-0612
Dear Sir:
Enclosed please find, as Attachment 1, a revision to the heavy loads report submitted in Reference (b). The description of the changes and associated justifications are provided in Attachment 2.
We request that the acceptability of the enclosed change to our' heavy loads report be reflected in the next supplement to Seabrook's SER. .
Very truly yours, IA C %
Geor S. Thomas l
\
l Enclosures I
cc: Atomic Safety and Licensing Board Service List 8606060100 860604 PDR ADOCK 00000443 A PDR 3
Cf ' (
I P.O. Box 300 Seabrock,NH03874 Telephone (603)474-9521
_ ~ .__
l Dien3 Curran. Esquire Calvia A. Cann:g Harmon & Weiss City Manager 2001 S. Street. 5.W. City Hall i Suite 430 126 Daniel Stredt Washington D.C. 20009 -
Portsmouth. NN 03801 Sherwin B. Turk. Esq. Stephen E. Merrill. Esquire g Office of the Executive Legal Director Attorney General i U.S. Nuclear Regulatory Cossalssion George Dana 81sbee. Esquire Tenth Floor Assistant Attorney General Washington, DC 20555 Offlee of the Attorney Ceneral 25 Capitol Street Robert A. Backus. Esquire Concord. EN 03301-4397 116 Lowell Street P.O. Box 516 Mr. J. P. Nadeau Manchester. NH 03105 Selectmen's office 10 Central Road Philip Ahrens. Esquire Rye. NN 03870 Assistant Attorney General Department of The Attomey General Mr. Angle Nachiros statehouse Station M Chairsan of the Board of Selectmen hugusta. ME 04333 Town of Newbury Newbury. MA 01950 Nrs. Sandra Cavutis chairman Board of Selectmen Mr. William 8. Lord RFD 1 - Box 1154 Board of Selectmen Kannsington, NN 03827 Town Hall - Friend Street ,
Amesbury. MA 01913 l Carol S. Sneider. Esquire i Assistant Attorney Geners! Senator Cordon J. Humphrey Department of the Attorney General 1 Pillsbury Street One Ashburton Place 19th Floor Concord. EN 03301 Boston. MA 02108 (ATTN: Herb Boynton)
Senator Cordon J. Humphrey M. Joseph Flynn. Esquire U.S. Senate Office of General Counsel ,
Washington, DC 20510 Pederal Energency Management Agency g ;
(ATTW: Tom Burack) 500 C Street SW i Washington, DC 20472 Richard A. Hampe. Esq.
Hampe and McNicholas Paul McRachem. Esquire 35 Pleasant Street Matthew T. Brock. Esquire Concord. NH 03301 Shatnes & NcEachern 25 Naplewood Avenue Donald E. Chick P.O. Box 360 Town Manager Portsmouth. WH 03801 Town of Exeter 10 Pront Street Gary W. Holmes. Esq.
Exeter. EN 03833 Holmes & Ells 47 Winnacunnet Road Brentwood Board of Selectmen Hampton, NH 03841 RFD Dalton Road' Brentwood. BH 03t33 Mr. Ed Thomas PENA Region I Peter J. Nathews. Mayor 442 John W. McCormack PO & Courthouse City Hall Boston, MA 02109 Newburyport. MA 01950 Stenley W. Knowles Chairman Board of Selectmen P.O. Box 710 North Hampton, NH 03862
SBN- 1088 ATTACHMENT 1 Revised Excerpts Seabrook Station Heavy Loads Report 9
(report pgs. 1, 7, 10, 11, 12, 13, 37, 65; Table 2.1.3(c)-1, sht. I of 5 and 5 of 5, Table 2.4. 2-1, s ht . 10 of 11, Drawing No.
9763-F-805279) 4 I
I
a v
) .
l 1. INTRODUCTION
(
This report is in response to the NRC generic request for a review of I the control of heavy loads at nuclear power plants, as contained in '
f their letter dated December 22, 1980, and included herein (less enclosures) in Section 2 for reference. The report documents the results of a comprehensive review of the load handling operations at Seabrook Station
'{
and specifically addresses Enclosure 3 of the above letter, " Request for Additional Information on Control of Heavy Loads." The informational ()
content of the report is presented in a request / response format which )
follows the same general format of Enclosure 3. >
i t
(
The original issue of this report, dated September 1982, was forwarded
(
to the NRC for review by PSNH on September 24, 1982 under letter SBN-331. I
(
i Revision 1 to this report, dated May 1983, was an update prepared in response to the NRC's draft technical evaluation of the original report, date November 23, 1982, and supplemented by the NRC's letter to PSNH, dated December 28, 1982. i t
[?
The present Revision 2 to this report, dated October 1985, responds to the letters submitted by the NRC, dated August 31, 1983 and October 14, 1983, respectively, as well as provides additional design changes and t supplementary information which has been incorporated since Revision 1.
f Note that for the purposes of this evaluation, a heavy load is defined l<
z ,
in accordance with NUREC-0612, as a load whose weight is greater than f l the combined weight of a single spent fuel assembly and its handling tool,i , e ? ~M g ua :e a d._. 21^^ p-4. Fo r- all b ut +ka Mawlevla.b [p i e. loa 4 :p yder h 2 t w poun A,. In W /
Crawe % A Heik,%d,b c ase o I +%. Ma w p\o .
- Cvwe M a a, W O , w b b d oli W e4
- 3 dMered kwilq deEL. ,& i to. A paker b %So fo""d' ,
(c) Filter cask monorail.
(d) CVCS heat exchanger service monorail.
(e) Polar gantry crane.
l 9
i (f) Boric acid batching monorail. t
/-
The spent fuel bridge and hoist, the manipulator crane and manipulator l crane auxiliary hoist and the service water strainer monorail hoist have been derated to 2100 pounds capacity to preclude inadvertent use '
of these load handling systems with heavy loads. Si*sI""II1****W" c.vinwe
" Iw he&<hdn f,.- h% been clew fed -}e Er,Sofev*dtCMacih* l 8'"
f orti44c=%., of r.too/2 c.So Po ud c*yacih-).
The lifting devices for the spent fuel cask and the removable panels of -'
the pressurizer enclosure wall have not yet been designed. The design '
of these devices will be in compliance with the intent of NUREG-0612 requirements.
l t
Some exceptions have been taken to the requirements of NUREG-0612 and Enclosure 3 to the NRC letter; however, these exceptions do not reduce the reliability of the load handling operations. Alternatives in lieu of literal compliance with these requirements are discussed to ,
demonstrate their equivalency and/or adequacy.
In conclusion, load handling operations at Seabrook Station meet the intent of NUREG-0612 in regard to assuring safe handling of heavy loads identified in this report.
s
,\ .
\
l
- ?
MAXIMUM \
- HANDLING DESIGN CRITICAL TAG NO. /
SYSTEM CAPACITY- LOAD (MCL) LOCATION i
] CS-CR-14A, Charging Pump 2.5/2.5/ -
2.5/2.5/ Primary
-14B,-14C Service Monorail 6.0 Tons 6.0 Tons Auxiliary )
- Hoist Building 7 7
CC-CR-15A, Component Cooling 5 Tons 2.7 Tons Primary
?
CC-CR-15B Water Pump Auxiliary b
] Service Monorail Building f/
J Hoist ,
CBS-CR-18A, Radioactive Pipe 1.65 Tons 1.65 Tons Radioactive
( l'
] CBS-CR-18B Tunnel Service Pipe Tunnel )
Monorail Hoist '
] MS-CR-25A, Main Steam and 7.5 Tons 7.5 Tons MS and FW MS-CR-25B Feedwater Pipe Pipe Chase Chase Crane i
(
a FW-CR-27 Emergency Feed 5 Tons 2.5 Tons Emergency Pump Monorail Feedwater i
~
Hoist Pump i
~ Building [ 7
, DC-CR-28A, Diesel Generator 8 Tons 8 Tons Diesel l DC-CR-28B Service Crane Generator
1 9 SI-CR-40A, f./ '
,, SI-CR-40B Safety Injection Pump Service 3[.1 Tons // Tons Equipment Vault (PAB) d Monorail Hoist )
u J
a E i 1
W l
me l
= ,
l
] REQUEST 2.1-2 I i
a
" Justify the exclusion of any overhead ha ling system from the above category by verifying that there is sufficient physical separation from any l m load-impact point and any safety related component to permit a determination l}
J by inspection that no heavy load drop can result in damage to any system or component required for plant shutdown or decay heat removal." i T ,
o RESPONSE TO 2.1-2 o
.l The following load handling systems have been excludef from the above category because no safety related systems or components required for plant shutdown a j' or decay heat removal are located in the areas served by these overhead 1
. handling systems:
TAG NO. HANDLING SYSTEM CAPACITY 1
LOCATION 3 MM-CR-1 Turbine Building Crane 210 Ton Main Turbine
. 30 Ton Auxiliary Building MM-CR-2 Heater Bay Crane 100 Ten Main Turbine 15 Ton Auxiliary Building ES-CR-26 Cenerator Breaker Crane 5.5 Tons
> Turbine Building ,
CO-CR-29A To f. o 7045 i 29X Condenser Water Box Monorail Hoist W ns Turbine . U l
l Building 3
] ]
CW-CR-22 Circulating Water Stop Tons Service and Log. Monorail Hoist CW Pump House -
CW-CR-23 Pump House Trash Removal 1 Ton Service and Basket Monorail Hoist CW Pump House i
l PAH-CR-17 C.7$ Yen Ventilation Service A Primary Auxi-i Monorail Hoist
- liary Building EH-CR-39 Equipment Hatch Monorail 5 Tons Primary Auxi-Hoist liary Building
%s.
l
g.~. - - - - - .
m_,.,,-
. ~., m , u-g- ::,2. - _ 7gg::gis - _ - I 9
}
(
TAG NO. HANDLING SYSTEM CAPACITY LOCATION WS-CR-7 Waste Process General
> 4 tons Waste Service 80 Monorail Processing Hoist Building
> WS-CR-8 Waste Process General 4 tons Waste Service 40 Monorail Processing Hoist Building RS-CR-12 Resin Sluice Service 2 tons Waste Monorail Hoist Processing Building WS-CR-4 Solid Waste Handling 30 tons Waste Crane Processing Building AAH-CR-20 Decontamination Service 5 tons Administration Monorail Hoist and Service Building MM-CR-30 RCA Shop Crane 5 tons Administration and Service Building MM-CR-31 Training Center Annex 5 tons Training Crane 4 Center Annex id In addition, the following systems are excluded from further consideration since they do not handle heavy loads. A " heavy load" is defined in accordance with Section 1.1 of NUREG-0612, i.e., a load wnose weight is greater than the combined weight of a single spent fuel assembly and its
. handling for usa 3e tool (a load of 2too /z(.S0greater than 2100 p_.i}./ZGSO peo,idt -See " r>r% Auchokf pound icad)
TAG NO. _ HANDLING SYSTEM CAPACITY LOCATION FH-CR-33 Jib Crane 0.75 tons Containment FH-RE-5 Manipulator Crane main t4oi@ 2 5 tons Containment II
(;;ge ;g), g 2(o50 l A bs .
Manipulator Crane 1.5 tons Auxiliary Hoist containment ,$
(2100 lbs)* E
shown in parentheses are the derated capacities [M See "hhoducbo'E for gut M ica.h &n of 2100 /26.50 A(3. c9me ttiM .
L.4 d
7 i TAG NO. HANDLING SYSTEM CAPACITY LOCATION
, FH-RE-2 Spent Fuel Pool Bridge 2 tons Fuel Storage and Hoist (2100 lbs)* h Building g RH-CR-32 RHR, CS, SI Equipment 0.75 tons Equipment
)
Vault Monorail Hoist Vault (P.A.B.)
12 80 goond s SW-CR-16 Service Water Strainer 1. 7 ten., -
Outside Primary q
> Monorail Hoist (2100 15:}' Auxiliary L Building fet The manipulator crane auxiliary hoist, although rated at 1.5 ton, does not carry heavy loads. -The loads handled by this hoist such as control rod drive shaft, drive shaft unlatching tool, shaft handling tool, guide tube cover and cover handling tool, thimble plug and the associated handling tool etc. weigh much less than 2100 poundsj Similarly,
the spent fuel pool bridge and hoist handle only light loads, such as fuel l }
assemblies with or without control elements and their associated handling tools, burnable poison rod assembly and its handling tool etc, whkb weif t, IM Waw 2.100 p on d s.
Furthermore, during plant operation phase, the manipulator crane auxiliary hoist and the spent fuel pool bridge and hoist will be derated by posting a 2100 pounds capacity rating on the unit to caution the operators against
[
usingthesehoiststoliftheavierloads.dHowever,ifoverthelifeofthe l plant a situation arises requiring use of the hoists with loads greater than 12650 rect.tt&tI4 .
2100fpoundsg it would be thoroughly reviewed by the Station Operating Review Committee.
t v" vs< a.v, ( pv c.vu ne m ai h b oia dt4touh mM ah 2,S by Q not ca y heavy te=L. Tite 1e.A3 k% Ata (,y %,s heid co,,,rs-t q o f Ee\ AMem bliek wik er wikovt conbel elevue.d s weip 1% 44,e g 2(060 pounks.
% manipulab cvuwe hdi will be -
S to at 2(oSO m -% -
OCapacities shown in parenthesis are theb.derated capacities.
a..
p I
0 REQUEST 2.3-2
" Justify the exclusion of any cranes in this area from the above category by verifying that they are incapable of carrying heavy loads, or are permanently prevented from the movement of any load either directly over the reactor vessel or to such a location where in the event of any load-handling system failure, the load may land in or on the reactor vessel."
)
RFSPONSE TO 2.3-2 The following load handling systems are not listed above in Response 2.3-1.
The justification for their exclusion is provided below:
EQUIPMENT NO. CRANE TYPE CAPACITY FH-CR-33 Jib Crane Jib 0.75 tons FH-RE-5 Manipulator Crane Traveling Bridge v 2.5 tons ;
ThM Ro U f- and Hoist (2:00 15 )* '
Manipulator Crane 2Ce 5 0 1 61 }
Auxiliary Hoist 1.5 tons j (2100 lbs)* l, The jib crane is not capable of carrying heavy loads. It is used primarily to handle studs, and tools required to unbolt and remove the reactor vessel head during refueling operations.
The manipulator crane and manipulator crane auxiliary hoists handles only light loads such as fuel assemblies, control rod drive shaft, drive shaft ;
unlatching tool, shaft handling tool, guide tube cover and cover handling (
tool,& % thimble plug and its associated handling tool etc. Also, manipulator cMtMe I m3@? S: auxiliary hoists will be derated tog 245(V ri$d.tactWely b 100 pounds capacity4to preclude
[
inadvertent use of this hoist with heavier loads. The new (lower) rated 2 capacity will be marked on the hoist units. k 0 Capacities shown in parenthesis are the derated capacities (See "Inf>.doch "
h }$Ncdbn e{ 2.100 /2(o60 464. cg acih M .
l l
~
M~ all motors was conducted. The necessary documen-E~
tation concerning these tests is available in QA files at the plant.
E __ 8.2 Static and Dynamic Load Tests Requirement:
A static load test at 125% of the maximum critical load (MCL) should be performed. Full performance test with 100% of the MCL including verification of the proper
~
functioning of all limiting and safety control devices should be conducted. -
~
Actual: "e.
LLL3P C3 (Ba 3 M M "! m .d t.; y;rD =*y-haiar; = e = e i r-I 4ead retr .it- 173% Uf7he NCL and a pefformance-test-at j
oc-abeve-it 0% of the MCMill be performed as per abirve-I wequient r-Proper--functioning of_ all Limit Jsvit_ghes g -4nd-ot hem a f etpontro l- d evi ce s -vi l l- be- ve r i f i ed .-__
I 8.3 Two-Block Test E-~ Requirement: 1. When equipped with an energy-controlling device between the load block and the head block, the complete hoisting machinery should be hilowed to two-block. The test should be conducted at slow speed without load.
- 2. Crane should be tested for load hangup.
Actual: 1. Appendix C to NUREC-0612, allows the crane to be furnished with two independent travel limit switches in lieu of a design to withstand a two-
~~
blocking incident. This alternative is selected I
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TABLE 2.1.3(c)-1 (Sheet 1 of 5)
SEABROOK JTATION - UNITS 1&2 TABULATION OF HEAVY LOADS LOAD HANDLING WEIGHT IDAD FATH PROCEDURE REFERENCE CRANE / MONORAIL - HOIST LOAD IDENTIFICATION (1bs) LIFTING DEVICE ,pRAWINC SPECIFIC /CENERAL DRAWING CONTAIMENT Foler Centry Crane M-CR-3 423 Too Main 50 Ton Auxiliary Neutron Shield Fanel (8) 10,000 each Main / Aux. Hook & 805284 Whiting Corporation Ceneral F.F. d815542 Slings (See Note 2)
Reactor Cavity Seal Ring 18,625 Main / Aux. Hook & 805273 Specific F.F. #805556 d e
Slings Reactor Missile Shield 40,000 Main Hook and (See Note 1) f ?
805282 Specific F.F. 9101933 '
and Support (plus CRDM (with spreader Spreader Assembly /
'7 cooling fans) assembly) d 7
Reactor vessel Head 336,218 (with Main Hook, RV Head 805275 and Attachments Specific F.F. f50234 lifting rig) Lifting Rig, Load F.F. #50246 Cell, and Linkage Assemb;y Internale Lifting Rig 18,350 Main Book, Load cell 805272 Specific F.F. #53998 and Linkage Assembly Upper Internals 152,000 (with Main Hook, Internale 805272 Specific F.F. #50209 lifting rig) Lif ting Rig, lead Cell and Linkage Aeoembly Lower Internals 340,000 (with Main Hook, Internale Not Required Specific /Ceneral -
lifting rig) Lifting Rig, Load I
- Cell and Linkage Assembly Jib Craceb --'- -2 Auxiliary Hook and 805272
^
y2"_ __ , - ( ,f Ceneral F.F. #54824 glinge
.-- o.,. ,5r Stud Tensioners 2,500 Aum. Rook & Slinge 805283 Ceneral F.F. f50215 i Mclud s't p k 01 b Nty %
(8
M i _i LJ LL--J E- J M U N1 U --J LL-4 lb- A U '
U .a M U- U - U-' G3 U
(Sheet 5 of 5) 3 SEABROOK STATION - UNITS 1 & 2 TABULATION OF HEAVY LOADS LOAD HAND!.!NC WEIGHT LOAD PATH PROCEDURE REFERENCE CRANE / MONORAIL - HOIST LOAD IDENTIFICATION (Ibs) LIFTING DEVICE DRAWINC SPECIFIC /C'NE g DRAWINC I
RADIOACTIVE PIPE TUNNEL 1 Radioactive Pipe Smap Isolation valve Less than Slings See Note 3. Ceneral F.P. #90911 >
Tunnel Service Topworks (16" CBS- 2,500 lbs. g' >
Monorail Hoist V8 and V14) /
CBS-CR-18A & 188 N q 2 Ton capacity each ,
EQUIPMENT VAULT (P.A.B.)
2.80 '
Safety Injection Stings i Pump 3eb.
See Note 3. Ceneral F.P. #52936 ,
Pump Service Monorail Pump Motor 2,750 " " " " '
t Hoist '
SI-CR-40A & 405 d g.l /Toa Capacity each i p
NOTES:
- 1. Specific Procedure A specific procedure governs critical load handling operations requiring unique procedures, and provides detailed instructions for the movement and handling of such loads, or performance of complex tasks requiring greater detail to ensure safe handling of loads.
- 2. General Procedures A general procedure governs all crane and load handling operations not requiring a specific procedure, and may serve as a reference document for specific procedures. ,;
( .7
- 3. Load path is confined to the monorail track within a compartment that is separated by concrete walls from the adjoining compartment /s containing redundant equipment and associated monorails. '
'h
- 4. Load path is the entire area of crane travel within the two rails. The load is handled only when the plant is in cold shutdown with g the residual heat removal system in operation.
i
_. - -- -. _ , _ . . .- - -.~ _ _ ~
TABLE 2.4.2-1 (Sheet 10 of 11)
CONTROL OF LOAD / IMPACT AREA MATRIX . 4 HEAVY LOADS $
~
NUREG 0612 SEABROOK STATION UNITS 1 & 2 f
CRANE: SAFETY INJECTION PUMP SERVICE MONORAIL HOIST Ton capacit (SI-CR-40A & -40B) cf
~
LOCATION BUILDING : EQUIPMENT VAULT (PAB)
IMPACT Zone: Column 1-D
-- AREA l i
,' J Hazard c Safety Related Elimination LOADS Elevation Equipment Category
- Pump (-) 50'-0" Safety Injection B Pumps j 1
Pump Motor (-) 50'-0" Safety Injection B j Pumps t
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SBN- 1088 ATTACHMENT 2 DESCRIPTION AND JUSTIFICATION Revision to Table 2.1.3(c)-1, Sht. 1 of 5 One of the loads identified for the Polar Gantry Crane, in the above referenced table, is the " Jib Crane (including hoist and trolley)".
The weight shown is the heaviest of two lif ts. The second lift, the pedestal weighing 2500 pounds, was not specifically listed in the table.
As a result of a review of the use of this cranc during refueling operation and the number of times the crane would be disassembled and assembled (at least six times) we have decided to make a single lift of 5500 pounds. A single lift in lieu of a two lift process would, of course, require some changes to the crane.
The change described does not involve an issue of safety signif-icance. The lif ting devices used to remove and install the Jib Crane haie a maximum critical load capscity of at least 25 tons which equates to a safety factor of approximately 9 for the single lif t load of 5500 pounds.
Revision to pages 1, 7, 12, 13, 37 A heavy load is defined, in accordance with NUREG-0612, as a load whose weight is greater than the combined weight of a single spent fuel assembly and its handling tool. In determining this weight, we considered ,
the load on the Spent Fuel Bridge and Holst (FH-RE-2), the Manipulator Crane Auxiliary Holst, and the Manipulator Crane Main Hoist (Refueling Machine). For the Spent Fuel Bridge and Hoist and the Manipulator Crane Auxiliary Holst, we determined that the load would be 2071 pounds. The load determined for the Manipulator Crane Main Hoist was 1616 pounds.
As a result, we selected a value of 2100 pounds for our site specific heavy load threshold weight.
4 Since this earlier determination, while performing a review of the internal structure of the Manipulator Crane Main Holst, we found that the gripper mast was not structurally integral with the crane bridge and that the mast's weight (980 pounds) was directly imposed on the lif ting cable. This increased the load on the Manipulator Crane Main Hoist from 1616 pounds to 2596 pounds.
As the 2100 pounds weight is obviously the mos: conservative for determining if a load should be categorized as a heavy load, we intend to maintain this value as the threshold weight limit for all areas and cranes except the Manipulator Crane Main Holst (Refueling Machine) which will have a specific threshold weight limit of 2650 pounds. As a result of this change, we would also derate the Main Hoist from 2.5 tons (5000 pounds) to 1.325 tons (2650 pounds).
SBN- 1088 ATTACRMENT 2 DESCRIPTION AND JUSTIFICATION (Continued)
Revision to pages 10, 11, 13, Table 2.1.3(c)-1, sht. 5 of 5, Table 2.4.2-1, sht. 10 of 11 The following are being updated based on the latest inf o rmat ion.
- 1. The capacities of the following cranes / hoists were updated:
o SI-CR-40 A, B 4.0 tons to 3.1 tons (p. 10)
, o CO-CR-92A to 92X; 4.125 tons to 4.0 tons (p. 11) o CW-CR-22; 10 tons to 13 tons (p.11) o PAH-CR-17; I ton to 0.75 tons (p. 11) o SW-CR-16; 1.7 tons (2100 lbs.) to 1210 lbs. (p. 13)
- 2. Table 2.1.3(c)-1, sht. 5 of 5; Updated weight specified for pump for hoists SI-CR-40A, B, and the hoist capacity.
- 3. Table 2.4.2-1, sht. 10 of 11; Updated capacity specified for hoists and deleted double asterisked note (**).
Revision to page 65 Item 8.2 ' Static and Dynamic Load Testo" is being revised to be consistent with the Heavy Loads Report revision submitted previously via PSNH Letter, dated March 31, 1986 (SBN-977).
Revision to Drawing No. 9763-F-805279 The safe load paths for "new fuel assembly (([))" and "new fuel shipping container (l 2 l)" are to be revised as follows:
o New fuel shipping containers: load path: will be moved up to the South wall and into the cask lift rig area.
o New fuel assembly load path will be eliminated.
The new fuel shipping container load path is being changed as a result of the receipt of fuel at Seabrook. Briefly stated, we found it necessary to expand the load path area to facilitate the receipt of fuel. This change will not reduce the reliability of load handling operations in the fuel handling building.
The new fuel assembly load path is being eliminated to reduce confusion since a new fuel assembly does not constitute a heavy load. This change also will not reduce the reliability of load handling operations in the fuel handling building'.
1
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