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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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d George S. Thomas NYN- 88028 March 1, 1988 MWdh6 New Hampshire Yankee Division United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk
References:
(a) Facility Operating License No. NPF-56. Docket No. 50-443 (b) PSNH Letter (SBN-1211) dated October 9, 1986, '10CFR 50.59 Evaluations
- G. S. Thomas to V. S. Noonan
Subject:
10 CFR 50.59 Quarterly Report Gentlemen Enclosed please find the Quarterly Report of 10 CFR 50.59 Safety Evaluations for Seabrook Station. This report covers the period of October 1, 1987, to December 31, 1987, and is being submitted pursuant to the reporting requirements outlined in Reference (b).
Should you require further information regarding this matter, please contact Mr. Warren J. Hall at (603) 474-9574, extension 4046.
Very truly yours, hi /I 977W., f George S. Thomas Enclosure cci Mr. Victor Nerses, Project Manager Project Directorate I-3 Division of Reactor Projects United States Nuclear Regulatory Commission Washington, DC 20555 Mr. William T. Russell Regional Administrator United States Nuclear Regulatory Commission Region 1 425 Allendale Road King of Prussia, PA 19406 Mr. Antone C. Cerne NRC Senior Resident Inspector Seabrook Station Seabrook, NH 03874 8803000084 880301 PDR ADOCK 05000443
[h R DCD ,
P.O. Box 300. Seabrook. NH 03874 . Telephone (603) 474 9574
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. ENCLOSURE TO NYN- 88028 SEABROOK STATION 10 CFR 50.59 SAFETY EVALUATIONS
. QUARTERLY REPORT OCTOBER 1, 1987. TO DECEMBER 51, 1987
- 1. Desian Channes The below listed design changes have been made at Seabrook Station and safety evaluations have been performed pursuant to the requirements of 10 CFR 50.59.
Design Coordination Report: Number 87-124
Title:
Startup Feed Pump Control Circuit Modifications
Description:
In response to an engineering analysis conducted to address concerns outlined in IE Information Notice No. 86-70, a problem with the automatic start logic for the Startup Feed Pump (FW-P-115) was identified. The Startup Feed Pump can be powered from either of two busses. Normally the Startup Feed Pump is powered from Bus 4, a non-1E bus. However, if Bus 4 is lost and certain emergency conditions exist, the pump can be powered from the emergency Bus'E5, a 1E bus.
Design Coordination Report 87-124 was initiated to add an interlock to the Emergency Power Sequencer circuitry to prevent the Startup Feed Pump from being automatically loaded onto the Emergency Diesel Generator when a loss of off-site power occurs when the pump is aligned to Bus E5.
The diesel generator reliability is improved by providing better control of the loading sequence.
Conclusion:
A 10 CFR 50.59 safety evaluation was performed for this design change and it has been determined that this change will not create any unreviewed safety concerns. Changes to the Final Safety Analysis Report will be incorporated by means of a future amendment.
Design Coordination Report: Number 87-134 Title Vent Gas Sample Points
Description:
This Design Coordination Report was initiated to incorporate modifications to the Waste Gas and Vent Gas Systems, identified in Engineering Report 87-008. The purpose of the .
modifications are to improve operability and personnel safety when manual sampling is required. The modifications include the following:
- 1. Addition of a semple tubing connection at the top of the Safety Valve Surge Tank (VG-TK-108) to improve the sampling capabilities.
- 2. Addition of two new sample valves, one on each side of a normally closed vent valve in the hydrogenated vent header to provide a better means of post-criticality purging. The new valve upstream of the vent valve will also provide the ability to sample the system high point associated with the normally closed vent valve.
- 3. Addition of a high point vent / sample connection at the top of each Primary Drain Tank (BRS-TK-66A & B) to improve sampling capabilities.
- 4. Addition of a manual bypass valve around the pressure control valve that regulates nitrogen parge supply to the Waste Gas System. The bypass valve will allow reverse flow nitrogen purge from the hydrogen surge tank back through the carbon delay beds. This flow path allows flow from the bottom to the top of each vessel.
The four modifications outlined above are on non-safety related portions of the systems however, modifications 1 and 2 are in areas that are seismically supported and the appropriate seismic requirements have been met.
Conclusion:
A 10 CFR 50.59 safety evaluation was performed for this design change and it has been determined that this change will not create any unreviewed safety concerns. Changes to the Final Safety Analysis Report will be incorporated by means of a future amendment.
. Design Coordination Report: Number 87-214
Title:
Seismic Monitoring Response Spectrum Recorder Annunciation
Description:
The Seismic Monitoring Response Spectrum Recorder (1-SM-XR-6705) is mounted on the containment foundation and provides Main Control Room indication when 70Z and 1002 of the Operating Basis Earthquake (CBE) level has been reached.
Seabrook Station is committed to Regulatory Guide 1.12 (Rev.
1), that in turn endorses ANSI /ANS 2.2 (1978), that requires Main Control Room annunciation when the OBE level has been exceeded as sensed by the response spectrum recorder.
During normal review of the Seabrook Station Seismic Monitoring System, it was identified that the Main Control Room annunciation for 1002 OBE was in fact set at 70Z OBE.
The as-found 702 OBE level is actually a more conservative clarm level than the required 1002 OBE level. To comply with the requirements as outlined in ANSI /ANS 2.2, this Design Coordination Report was initiated to increase the 70!
OBE Main Control Room annunciation level to 1002 OBE.
Conclusion:
A 10 CFR 50.59 safety evaluation was performed for this design change and it has been determined that this change will not create any unreviewed safety concerns. Changes to the Final Safety Analysis Report will be incorporated by means of a future amendment.
Design Coordination Report: Number 87-223
Title:
Primary Component Cooling Water Heat Exchanger Tube Inlet Erosion
Description:
During recent eddy-current testing and visual inspection of the Primary Component Cooling Water (PCCW) Heat Exchanger (1-CC-E-17A), it was identified that there was uniform tube inlet degradation. An engineering evaluation has concluded that the degradation is a result of velocity induced erosion-corrosion of the 90/10 copper-nickel (CuNi) tube inlet ends, i This Design Coordination Report was initiated to facilitate
- modifications of the tube ends by using a 70/30 CuNi tube
! insert (sleeve) to preclude further degradation. The 70/30 CuNi sleeve is less sensitive to velocity induced erosion-corrosion and will provide better protection of the tube end and seal weld. The 70/30 CuNi sleeve material is compatible with the existing material for the PCCW Heat Exchanger.
Conclusion A 10 CFR 50.59 safety evaluation was performed for this design change and it has been determined that this change will not create any unreviewed safety concerns.
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Design Coordination Report Number 87-258
Title:
Freeze Protection of Steam Generator Blowdown System
Description:
This Design Coordination Report was initiated to add heat tracing to two lines in th9 Steam Generator Blowdown System. These lines are exposed to the elements and have previously experienced problems with freezing, requiring extensive maintenance to thaw them out.
A review of the additional electrical loads added to panels HT-CP-432 and HT-CP-433 has indicated that they will not exceed the panel capacity limited by the 15 KVA transformer feeding each of the panels. The Steam Generator Blowdown System is a non-safety related system.
Conclusion:
A 10 CFR 50.59 safety evaluation was performed for this design change and it has been determined that this change will not create any unreviewed safety concerns. Changes to the Final Safety Analysis Report will be incorporated by means of a future amendment.
Design Coordination Report Number 87-319
Title:
Procedure TP-14 Update
Description:
A review of the valve stroke times for motor operated valves listed in Procedure TP-14. FSAR Table 6.2.83 (Containment Isolation System Design Information), and FSAR Table 16.3-4 (Technical Requirement 6 for Containment Isolation Valves) reverled inconsistencies between the three documents. When an inconsistency was identified, the associated valve was reviewed to identify the correct stroke time and the appropriate document (s) revised as required for consistency.
In addition to the updating of the three documents, the motor overload heaters for eight Emergency Feedwater Flow Control Valves were identified as requiring an upgrade to a larger size because of an increase in the stroke times.
Procedure TP-14 originally stated that the eight valves would have a stroke time of 14-18 seconds, non-critical, but actual stroke time was 18.3 to 18.4 seconds. When TP-14 was changed to reflect a new stroke time of 14 20 seconds, non.
critical, the motor overload heaters were increased accordingly.
Qonclusion: A 10 CFR 50.59 safety evaluation was performed for this
. design change and it has been determined that this change will not create any unreviewed safety concerns. Changes to the Final Satfety Analysis Report will be incorporated by means of a future amendment.
Design Coordinator Report: Number 87-344
Title:
Post Accident Shaple dystem Panel Argon Gas Isolation Valves
Description:
This Desigr. Coordination Report was initiated to replace two valves on the Post Accident Sample System (PASS) panel with different style valves. A previously identified 10 CFR 50.59 design change redesignated the function of two metering valves as shutoff valves for the argon gas supply. The metering valves were not designed to operate as shutoff valves and have started to leak. The valves were replaced with soft seat valves that are designed for repeated shutoff service. The PASS panel has been seismically qualified and each component mounted on the panel is considered seismically mounted. The replacement valves size and weight are similar to the metering valves and did not requite a change in the mounting for the new valves. This design change will improve the PASS panel operation by providing positive shutoff for the argon gas supply.
Conclusion:
A 10 CFR 50.59 safety evaluation was performed for this design change and it has been determined that this change will not create any unreviewed safety concerns. Changes to the Final Safetr Analysis Report will be incorporated by means of a future amendment.
Design Coordination Report: Number 87-348
Title:
Motor Control Center Feeder Breaker Change for Lighting Panel EL31
Description:
Lighting Panel EL31 ED-HH-1700 is powered from safety-related motor control center HCC-E513, utilizing a 40-amp circuit breaker. Additional loa.is had been added to Panel EL31 resulting in the 40 amp breaker being undersized for the new loads.
. This Design Coordination Report was initiated to replace the 40 amp breaker with a 60-amp breaker. The (0-amp breaker is sized to carry the new loads added to EL31. The MCC loading, diesel generator loading, and voltage regulation have been evaluated and no adverse effects were identified as a result of this design change.
Conclusion:
A 10 CFR 50.59 safety evaluation was performed for this design change and it has been determined that this change will not create any unreviewed safety concerns. Changes to the Final Safety Analysis Report will be incorporated by means of a future amendment.
Design Coordination Report: Number 87-349
Title:
Residual Heat Removal Mini-Flow Line Vibration
Description:
This Design Coordination Report was initiated to remove the four instrument root valves associated with the pressure breakdown orifices in the Residual Heat Removal (RHR) mini-flow lines and cap the connections. Excessive vibration on the RHR mini-flow line had caused socket welds on the orifice flange pressure taps for FE-2474 to fail. The flow elements, FE-2473 and FE-2474, were used for flow balancing during pre-operational testing. No further flow measure-ments will be taken through the use of these valves.
Removal of the one-half inch root valves will reduce stresses in the pressure tap line. An Engineering evaluation was performed on the mini-flow line and vibration readings were taken during three basic flow conditions of the mini-flow line. The results of the evaluation and the data from the vibration readings show the vibration to be within acceptable limits as established by the Seabrook Station Preoperational Test Program.
Conclusion:
A 10 CFR 50.59 safety evaluation was performed for this design change and it has been determined that this change will not create any unreviewed safety concerns. Changes to the Final Safety Analysis Report will be incorporated by
> means of a future amendment.
Design Coordination Report Number 87-377 Title Verification of Motor Load List with Circuit Protection Calculation
Description:
During the performance of a routine surveillance procedure, the as-found breaker trip setting for motor operated valve ,
1-SI-V-77 (SI-P-6B to Hot Leg Discharge Isolation Valve) was found to be inconsistent with the setting specified in the Motor Load List. An engineering evaluation was performed to identify the correct trip setting. This Design Coordination Report was initiated to incorporate the new higher trip coil rating.
An increase in the trip coil rating will not degrade the function of the valve 1-SI-V-77, rather it will prevent temperature tripping and prolong the availability of the valve.
Conclusion:
A 10 CFR 50.59 safety evaluation was performed for this design change and it has been determined that this change will not create any unreviewed safety concerns. Changes to tb) Final Safety Analysis Report will be incorporated by means of a future amendment.
- 2. Temporary Modifications The below listed Temporary Modifications have been made at Seabrook Station and evaluations have been performed pursuant to the requirements of 10 CFR 50.59.
Temporary Modification Rsquest: Number 87-062
Title:
Temporary Power to Security System Lighting Panel ED-MM-212B >
Description:
The Security Guardhouse Essential Lighting Panel ED-MM-212B is normally powered from Motor Control Center MCC-523. Due to a scheduled outage of MCC-523, it was necessary to provide temporary power to Lighting Panel ED-MM-212B from MCC-211. This temporary modification involved replacing the normal power feed to the Guardhouse Essential Lighting Panel. ED-MM-212B, from EDE-HCC-523 with temporary power cables from a spare circuit breaker in ED-MOC-211. The power cables were not electrically connected in any way to HCC-523 bus work and the supply breaker to MCC-523 was tagged open during the period the change was installed. The additional load on MCC-211 was evaluated and there was no significant effect on load distribution features such as circuit breaker coordination.
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During this temporary modification, Diesel Generator backup
. to ED-MM-2123 was not'be available. Compensatory measures were incorporated in the unlikely event that a loss of off site. power should occur during the performance of the scheduled outage. This temporary modification has been removed and the system has been restored to its normal configuration.
Conclusion A 10 CFR 50.59 Saf6ty Evaluation was performed and it has been determined that installation of this temporary.
modification will not create any unreviewed safety concerns.
Temporary Modification Request: Number 87-071
Title:
Service Water to Diesel Generator 1B Water Jacket Heat Exchanger Flow Instrumentation Modification
Description:
Flow transmitters 1-SV-FT-1681 and 1 SV-FT-1691 have experienced faulty indications due to air pockets forming at high points in the instrument process lines. To eliminate this problem. Temporary Modification 37 071 was initiated to revise the location of the Annubar flow elemert taps and instrument lines from the top of the service water line flanged connections to the bottom flanged connections.
The original Annubar sensing lines were ASME Section III Class 3. Seismic Category I. The temporary tubing and tubing supports are not seismically supported and are not fully designed to ASKE Section III Class 3 requirements.
The temporary modification was only installed for use during Cold Shutdown (Mode 5) and prior to initial criticality.
The temporary modification will be incorpora.ted into an approved design change prior to entry into Hode 4.
Conclusion:
A 10 CFR 50.59 Safety Evaluation was performed and it has been determined that installation of this temporary -
modification will not create any unreviewed safety conceras.
Temporary Modification Request Nember 87-072
Title:
Temporary Cooling Water Supply to Instrument Air Dryer 1A-B-1098
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. Descriptions ;The three-way emergency supply isolation valves (1-SCC-V-318 j and 1-SCC-V-319) that isolate the Fire Protection System and the Secondary Component: Cooling Water system (SCC) have been -
leaking and causing contamination of the SCC system from Fire Protection _ System. This temporary modification ;
provides a temporary cooling water supply from the !
Domineralised Water System (EN) to the Instrument Air Dryer' IA-E-1095 mounted on skid IA-SKD-188. The temporary connections assures that the required 7-1/2 spa (max.)
cooling water supply will be available during-the maintenance of 1-SCC-V-318 and 1-SCC-V-319.
Conclusjon A 10 CFR 50.59 Safety Evaluation was per'tormed -and lLt has been determined that installation of this temporary modification will not create any unreviewed safety conc)rns.
- 3. Technical Recuirements Manual i The below listed changes have been made to the Seabrook Station Technical Requirements Manual and-evaluations have been performed pursuant to the requirements of 10 CFR 50.59.
Technical Requirements Manual Change Request Number 87-002
Title:
Technical Requirements Number 6 - Table 16.3-4 and Number 14 - Table 16.3-9
Description:
Changes to Seabrook Station's Technical Requirement 6. Table 16.3-4 ' Containment Isolation Valves
- and Technical Requirement 14. Table 16.3-9 'Notor Operated Valves with Thermal Overload Protection Devices Operable at All Times' have been made to ircorporate information identified in DCR 87-319. As described in Section 2 of this report, a consistency review between three documents that identify the maximum isolation time for selected containmor'. isolation valves was performed and the correct value t Daes revised in l the documents. The change to Technical Requirement 6 is the result of that review.
l The second change. Technical Requirement 14, incorporates the information for the upgrade of the eight emergency
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feedwater valve motor overload heaters. This increase in
, the overload heater sizing was identified in Section 2. DCR 87-319.
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T Conclusion ( A JO M Rio.59 Safety Evaluation was performed for the 1 h change te thc Technical Requirements Manual and it has been
- 4 i dite:Wr.ed ythat this change will not create any unreviewed j ,sefety concerns. Changes to the Final Safety Analysis Beport sill be incorpcrated by means of a future amendment.
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f f ' Tu' itNya.: Requircr.ent:. Manual Change Request: Number 87-003 I
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~ . U Tit'p: Technical idh ement Nunber 6 - Table 16.3-4 s
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Description:
In SeaLJc5k Stction Safety Evaluation Report, Supplement 6
} A approva! was granted to eliminate the trending requirements
, of ASME Section XI for rapid acting solenoid operated valves
/ with the conditiot; that a maximum limiting stroke time of 2 seconds be assigned to certain ASME Section XI valves. This h i Technical Requirements Manual Change Request was issued to h incorporate the 2 second maximum stroke time change for
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nineteen containment isolation valves listed in Technical
\ Requirement 6. Table 16.3-4.
Conclusion:
' A 10 CFR 50.59 Ss.fety Evaluation was performed for the thande_to'>he Technical Requirements Manual and it has been determined thet this change will not create any unreviewed safety concerns. Changes to the Final Safety Analysis Report wi '1 be it.corporated by means of a future amendment.
7 Technical Rcquiremente Ment:31 Change Request: Number 87-005
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Title:
Technical Requirement Number 15 - Table 16.3-10
Description:
A cunge tr, Technical Requirement Number 15. Table 16.3-10, 4- "Protecciva Devices for Non Class 1E Circuits Connected to Class IF Sources" wam made to incorporate information identified in DCR 87-348. As described in Section 2 of this reaponse, ths supply breaker to EL31 ED-MM-170C was increased in size to a 60 amp breaker. The larger breaker h^
required that the test setpoint for the 'long time' trip i
setting of the breaker be increased from 120 amps to 180 e amps as identified in Table 16.3-10.
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Conclusion:
A 10 CFR 50.59 Safety Evaluation was performed for the change to the Technical Requirements Manual and it has been detera.ined that this change will not create any unreviewed
, satey concerns. Changes to the Final Safety Analysis N
Rcpoct will be incorporated by means of a future amendment.
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- 4. Final ~ Safety Analsyis Report No revisions have been submitted for the Final Safety Analysis Report during this reporting period.
- 5. Procedure Changes Procedure changes that require review and approval by the-Station Operation Review Committee (SORC) have been subjected to the requirements of 10 CFR 50.59. No procedure changes have been made at Seabrook Station during this reporting period that would require a change to the final Safety Analysis Report.
- 6. Test or Experiments There were no tests or experiments performed during this reporting period that require evaluations in accordance with 10 CFR 50.59.
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