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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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'm 1671 Worcemw Rood Pub 5c Service of New Hampshire M"'***d "ON (617) - 872 - 8100 June 24, 1983 S BN- 524 T.F. B7.1.2 United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing Re fe re nc es : (a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) PSNil Letter, dated March 29, 1983, " Response to SER Outstanding Issue #1 (SER Section 2.3.1, Meteorological and Effluent Treatment Systems Branch)," J. DeVincentis to C. W. Knighton (c) PSNil Letter, dated April 20, 1983, " Supplemental Response to SER Outstanding Issue #1 (SER Section 2.3.1, Meteorological and Ef fluent Treatment Systems Branch),"
J. DeVincentis to G. W. Knighton
Subject:
Pevised Response to SER Outstanding Issue #1 (SER Section 2.3.1, Meteorological and Ef fluent Treatment Systems Branch)
Dear Sir:
We have enclosed a revised version of the response to SER Outstanding Issue #1 which was forwarded in Reference (b). The enclosed revised response re flects discussions with the Staf f reviewer (J. Fairobent) at a meeting conducted on May 18, 1983. Revisions are indicated by bars in the right margin.
The enclosed response will be incorporated in OL Application Amendment 49.
Ve ry truly yours, YANKEE ATOMIC ELECTRIC COMPANY B307060129 830624 PDR ADOCK 05000443 E PDR
- - Qh John DeVincentis Project Manager ALL/pf Enc losure \
cc: Atomic Safety and Licensing Board Service List 1000 Elm St.. P.O. Box 330, Manchester, NH 03105 Telephone (603) 669-4000 . TWX 7102207595 !
Rep. Beverly Hollingworth Ms. Olive L. Tash Coastal Chamber of Commerce Designated Representative of 209 Winnacunnet Road the Town of Brentwood Hampton, NH 03842 R.F.D. 1, Dalton Road Brentwood, NH 03833 William S. Jordan, III, Esquire Harmon & Weiss Edward F. Meany 1725 I Street, N.W. Designated Representative of Suite 506 the Town of Rye Washington, DC 20006 155 Washington Road Rye, NH 03870 Roy P. Lessy, Jr., Esquire Office of the Executive Legal Director Calvin A. Canney U.S. Nuclear Regulatory Commission City Manager Washington, DC 20555 City Hall 126 Daniel Street Robert A. Backus, Esquire Portsmouth, NH 03801 116 Lowell Street P.O. Box 516 Dana Bisbee, Esquire Manchester, NH 03105 Assistant Attorney General Office of the Attorney General Philip Ahrens, Esquire 208 State House Annex Assistant Attorney General Concord, NH 03842 Department of the Attorney General Augusta, ME 04333 Anne Verge, Chairperson Board of Selectmen Mr. John B. Tanzer Town Hall Designated Representative of South Hampton, NH 03842 3
the Town of Hampton 5 Morningside Drive Patrick J. McKeon Hampton, NH 03842 Selectmen's Office
, 10 Central Road Roberta C. Pevear Rye, NH 03870 Designated Representative of the Town of Hampton Falls Ruthanne G. Miller, Esquire Drinkwater Road Law Clerk to the Board Hampton Falls, NH 03844 Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Mrs. Sandra Cavutis Washington, D.C. 20555 Designated Representative of the Town of Kensington Dr. Maury Tye, President RFD 1 Sun Valley Association East Kingston, NH 03827 209 Summer Street Haverhill, MA 01830 Edward J. McDermott, Esquire Sanders and McDermott Mr. Angie Machiros Professional Association Chairman of the Board of Selectmen I
408 Lafayette Road Town of Newbury Hampton, NH 03842 Newbury, MA 01950 Jo Ann Shotwell, Esquire
- Assistant Attorney General
- . Environmental Protection Bureau Department of the Attorney General one.Ashburton Place, 19th Floor Boston, MA 02108 l
)
451.11 a. Identify meteorological conditions (including extreme temperatures, pressure, humidity, and windspeeds) considered in the design of auxiliary systems and components (e.g., the diesel generator combustion air intake and exhaust system discussed in Section 9.5.8).
'b. Provide the bases for the selected values (including the magnitude and duration).
- c. Compare the selected values with severe or extreme meteorological conditions. observed in the region through 1981 I (through January 1982 for extrece minimum temperatures).
- d. Compare the selected values with those presented in Section 2.3.1.2 for tornadoes and hurricanes, extreme winds (e.g.,
100 year recurrence), extreme temperatures (100 year recurrence; see NUREG/CR-1390, " Probability Estimates of Temperature Extremes for the Contiguous United States"), and other extreme conditions for atmospheric moisture and precipitation.
RESPONSE: a. Meteorological conditions considered in the design of auxiliary systems and components, exclusive of the diesel generator air intake and exhaust system, are summarized below; the environmental conditions for the diesel generator air intake and exhaust system are addressed in RAI 430.130.
4 Extreme Outdoor Temperatures Maximum 880F f- Minimum 0 F i Relative Outdoor Humidity Maximum 100%
Minimum 10%
The above temperature and humidity extremes were utilized in the design of the HVAC systems for all safety-related buildings. The HVAC systems.are intended to maintain temperature and humidity environments within the buildings as specified in FSAR Figure 3.11(B)-1 (Service Environment
, Chart) under the outdoor conditions specified above. j
- - 1 Seismic Category I structures and certain non-Seismic Category I structures, as listed in Subsection 3.8.4.1, were.
designed for. wind velocities as follows:
i Severe Environmental Load:
l A wind speed of 110 mph at 30 feet above ground for a 100-year: return.
to
d l'db Extreme Environmental Load:
A total maximum tornado wind velocity (translational plus rotational of 360 mph). .
Seismic Category I structures and certain non-Seismic Category I structures were designed for the following atmospheric pressure change accompanying the design basis tornado:
1 Total pressure change due to passage of tornado: 3 psi Rate of pressure change: 2 psi per second
{
- b. The bases for specification of temperature extremes are actual measured regional temperature distributions for Massachusetts presented in "ASHRAE Eandbook of -Fundamentals",
i Chapter 22. Table 1, page 380, 1967 Edition. The 2-1/2 % ,
values (Summer) and 97-1/2% values (Winter) of the distributions were used.
The bases for the selection of the humidity range is the assumption that relative humidities at or near 100% occur during fog, dev formation and precipitation which are frequently observed in this climate. Relative humidities less than 10% are not observed under the climatic conditions affecting this site.
The bases for the design wind velocities and atmospheric 1 pressures for Seismic Category I' structures and certain I
non-Seismic Category I structures (listed in Subsection 3.8.4.1) are discussed in Subsection 2.3.1.2.
c.- Extreme wind speed and ambient temperature conditions observed in the Seabrook Station eite region through December 1978 were reported in Seabrook FSAR Tables 2.3-4, 2.3-11 and 2.3-12. Seabrook FSAR Table 2.3-4 shows that the fastest mile wind speed recorded was 87 mph (Boston, September 1938);
SB FSAR Tables 2.3-11 and 2.3-12 show that the maximum and
, minimum ambient temperatures. observed were 1040F (Boston, July 1911) and -390F (Portland, February 1943),
, respectively. None of these extreme environmental conditions
.have been exceeded at their respective stations as of January 1982.
Extreme temperatures which are'more representative of the ,
site were determined through an analysis of the Pease AFB
, (Portsmouth, N.H') temperature data for the period April 1956
'through June 1982. The pertinent results of this analysis i- are contained in our response to part (d)'below.
A National Severe Storm Center list of tornado data for the ~
Seabrook. Station site region for.the~ period 1950-1981 (Reference 1) indicates that the closest initial tornado-touchdown point recorded was approximately 2' miles from the i site on July 1,~1968.- This tornado was rated 1 on the-
- (5 Fujita-Pearson scale estimate of force (73-112 mph winds).
The three strongest tornadoes recorded as having initially touched down within 50 miles of the site during this same 32 year period were rated 3 on the Fujita-Pearson scale estimate of force (158-206 mph winds). The estimated wind load of these three extreme tornadoes is well below the design extreme environmental tornado wind velocity of 360 mph.
NOAA Technical Report NWS 23 (Reference 2) provides a list of hurricanes with observed or estimated minimum central pressures less than 29.00 inches Hg which have occurred along the U.S. east coast during the 79 year period 1900-1978.
According to NWS 23, the minimum hurricane central pressure estimated to have occurred within 150 nautical miles of the U.S. east coast during this period was 27.44 inches Hg on September 10, 1919 off the Florida coast. Minimum hurricane central pressures along the New England coast have generally been higher due primarily to decreasing water temperatures toward the north. The lowest pressure ever recorded in the site region (e.g. , at either Boston, Concord or Portland NWS) was 28.40 inches Hg recorded in Portland on December 2,1942 (Reference 3). Thus, the diesel generator air intake and exhaust design hurricane and northeastern storm pressure of 26 inches Hg as discussed in SB FSAR Section 9.5.8 and in SB RAI 430.130 is conservative when compared to the minimum pressures which have been observed in the site region.
- d. The 100 year return period wind speed at 30 feet above ground is reported in FSAR Section 2.3.1.2 as 110 mph. This was the wind velocity used for the severe environmental wind load.
The design basis tornado wind velocities and atmospheric pressures are those outlined for Region I in Regulatory Guide 1.76 (Reference 4). The design basis hurricane or northeastern storm pressure of 26 inches Hg more conservative than the probable maximum hurricane central pressure of 26.80 reported for the New England coastline by NWS 23 (Reference 2).
According to NUREG/CR-1390 (Reference 5), the 100-year return period maximum and minimum temperatures for the Seabrook site are approximately 1060F and -320F, respectively. These extreme temperatures were obtained by the interpolation between isotherms shown on the maps of 100 year maximum and minimum temperatures contained in NUREG/CR-1390 The data base used to develop these maps does not include, however, temperature data from any reporting stations near the Seabrook site and also shows a strong influence of inland etations on the isotherm maps of 100 year maximum and minimum temperatures. Thus, NUREG/CR-1390 does not, in our opinion, adequately account for the modification of extreme temperatures due to the proximity of Seabrook to the Atlantic Ocean.
Our analysis (Reference 6) of extreme temperature data 4- collected at nearby weather stations (Portsmouth, NH (Pease AFB)), climatological stations (Rockport, MA, Sanford, ME, and Greenland, NH) and at the Seabrook site results in 100 year return period maximum and minimum hourly temperatures.for the Seabrook site of 1020F and -210F, respectively. (These values were computed following the methodology found in NUREG/CR-1390. ) '
Since the design of some equipment is more dependent on the maximum and minimum temperatures averaged over a period of greater than one-hour, extreme temperatures for 2, 4, 8, 12, and 24-hour averaging periods were also determined. The values are listed below:
100-Yea r Return Period Temperature (OF) i Averaging Period Maximum Minimum i
2-Hour 102 -21 4-Hour 101 -21 8-Hour 99 -20
- 12-Hour 96 - 19 24-Hour 92 -16 In addition to the above hypothetical 100 year return period temperature extremes, our analysis indicated that the highest hourly temperature recorded during the period 1957 through 1981 at Pease AFB (Portsmouth, N.H.) was 1010F on July 1, 1964 (hour 13). The hottest contiguous 24-hour period containing this temperature extended from June 30 (hour 15) through July 1 (hour 14). The hourly temperature progression for this period is provided in Table 451.11-1.
The five hottest and five coldest contiguous 24-hour hourly temperature periods recorded at Pease AFB for the data base of 1957 through 1981 are presented by Table 451.11-2.
- e. Calculations show that resulting maximum ambient temperatures r j experienced by equipment, located in ventilated compartments of concrete structures are functions not only of the temperature extremes, but also are functions of the diurnal i
. variations in the outside temperature and 'the thermal inertia i of the concrete structures. Concrete walls and slabs have thermal' capacitance associated with them, thus the heat
, transfer occurring between the structures and the ventilation air damp out the daily temperature fluctuations that would tend to occur within the' ventilated areas. The benefit that
- is gained by accounting for this thermal inertia can be determined by calculating the room temperature as_a function of time'of day.
From Table 451.11-2, which shows maximum temperatures of 1000F on August 3, 1975, the hottest 24-hour average external temperature was determined as'86.60F. Since our
. __ a ~ ._ , ~= u .. - u , - .- ,
f analysis of temperature extremes predicts a 100-year return maximum temperature of 1020F, the hourly temperature progression data for this day was thus adjusted upward by 2 F, in order to envelope the 100-year return conditions.
As a typical example of the ef fect that the thermal inertia of concrete structures can have, it was found that the anticipated maximum temperatures at the 21'-6" elevation of the Control Building in the Emergency Switchgear Rooms would be decreased from 1180F to 113.50F, and in the Battery Rooms from 1090F to 1030F, refer to Table 451.11-3 for details. In other words, by accounting for the diurnal variations and the thermal inertia associated with the concrete structures, the maximum temperatures that would occur in ventilated rooms would be lowered by approximately
-4.5 to 6.00F.
Based on our probabilistic evaluation of temperature extremes using the Pease AFB meteorological data (Reference 6), the outdoor temperature exceeding the extreme design temperature of 880F' occurs during a small fraction (0.25%) of the plant life. Moreover, it can be demonstrated that considering the thermal inertia of the building structures and the diurnal variation of temperature, the maximum temperature within a ventilated room will not exceed 1040F as long as the peak temperature of a hypothetical day does not exceed 910F.
- The temperature of the Control Room will not exceed 80 0F as long as the peak temperature of a hypothetical day does not exceed 910F. The fraction of the plant life when the
- temperature exceeds 910F is less-than 0.105%.
Elevated ambient temperatures may affect equipment life.
! However, to do so'the temperatures must be much higher than the design ambient temperature of the equipment and must be
- sustained for a long period of time.
Since internally generated heat is a function of the square of the current (P = 12 R) the loading of the equipment has a j great effect on the internal temperatures.
We have determined that there will be no significant.
- degradation of equipment within the buildings as a result of j the 100-year return maximum temperature for the following reasons
l o The maximum ambient temperature exceeds the design ambient by less than 100F,
-o The duration of these elevated temperatures as shown in response d is short and occurs infrequently throughout the life of the station.
f l o. The loading of our equipment is expected to be
.significantly lower than design maximum.
w $ - ,* - -ws- 7x- s up e e e e
All structures housing safety-related systems were examined for the effect of minimum temperature of -160F for a 24-hour period. All areas of all the buildings in question are capable of being maintained at a temperature of 500F, or greater, under those conditions, except the following:
An area of the Secondary Containment outside the personnel hatch Diesel Generator Building, Mechanical Equipment Rooms at Elevation 51'-6" --- -160F Cooling Tower The Secondary Containment Area in question contains no safety-related equipment and, therefore, the temperature extremes in this area will have no effect on the safe operation of the station.
The equipment in the Diesel Generator Mechanical Equipment Rooms will start and run satisfactorily under these extreme minimum conditions.
The following considerations were taken into account for the low temperature evaluation of the mechanical draf t cooling tower which serves as backup to the main circulating water tunnel for cooling of the primary components heat exchangers and diesel generator heat exchangers:
- 1. The tower is only intended to be used as a cooling means for the service water system if a seismic event has occurred which results in a blockage of over 95% of the flow area of the intake tunnel. As stated in FSAR Sections 9.2.1 and 9.2.2, the total flow required for the performance of the heat sink function by the tower in less than 5% of the circulating water flow rate provided during normal full power operation. The likelihood of such extreme blockage occurring in this hard ock tunnel is considered extremely remote.
- 2. The five year on-site and 25 year Pease AFB outdoor temperature data bases reveal that 00F was equalled or exceeded 0.356% of the time on-site and 0.394% of the time at Pease AFB. The probability of a major seismic event which could render the tunnel incapable of providing sufficient service water flow concurrent with temperatures below the design temperature of 00F is considered extremely low.
Based on the above considerations, the availability of sufficient service water is assured.
(b{
l Because of the thermal inertia associated with concrete
- k. structures and the relatively short duration of time that temperatures would be below -160F, we do not feel the temperatures of the buildings would fall significantly below the values stated above and, therefore, the equipment within the buildings would be unaffected by the 100-year return minimum temperatures.
Since the environmental conditions in the areas discussed above are acceptable from the personnel access and operating equipment standpoints, it is concluded that the extreme 100-year return temperatures would not be detrimental to l plant operation. I References
- 1. National Severe Storms Forecast Center, Tornado Data, " Tornadoes Within 125 Miles of Seabrook", 1950-1981 (unpublished).
- 2. NOAA Technical Report WWS 23, " Meteorological Criteria for Standard Project Hurricane and Probable Maximum Hurricane Windfields, Gulf and East Coasts of the United States", Washington, D.C. , September 1979.
- 3. Telecon with Ms. Ettinger, Partland NWS, April 21, 1982.
- 4. NRC Regulatory Guide 1.76, " Design Basis Tornado for Nuclear Power Plants", April 1974.
- 5. Nicodemus, M. L., and N. B. Guttman, " Probability Estimates of Temperature Extremes for the Contiguous United States", NUREG/CR-1390, National Climatic Center, Asheville, NC, May 1980.
- 6. United Engineers and Constructors, Inc. Report, " Probability Estimate of Temperature Extremes for Seabrook New Hampshire", January 1983.
g-I .
-~ ~ '
j TABLE 451.11-1 f l
l i
I e ENTEST CONTICUOUS 24 HOURS IN ASSOCIATION WITH t
THE HOTTEST ONE-MOUR TElfERATURE*
OBSERVED DURING 1957 TEROUGE 1981 AT PEASE AFB Mour Temperature (*F) g Date June 30 Er 15 89 1964 89 16 17 89 18 85 19 81 20 80 21 77 22 76 23 76 July 1 Br 00 74 1 76 2 75 3 75 4 74 5 73
7 80 8 88 9 92 10 93 96 11 1
' 12 98 13 101*
14 100 C926 - HOI 1W15 M0088W35 AW9 9tsti C8. St*sWW 888'd _ _ - __ _ , _ ..
., . *< > *, g
/ !
Five Coldest and Warmest j
- 14'tiour Periods at Seabrook Station _
i ytyg ui ===T 24 ==vu FEcons
- aw arar 34 m yesemme e6.ti, es.91 e4.42 e3.87 83.13 frys Amorees 1964 1974 1941
-4.94 -7.12 -S.30 -2.70 -3.30 Year 1973 1977 Avereen Forted Gada fag,J h L31 h Lil h L U, h L 1 Year 1M8 1957 1900 1M7 1981 rted tada 13,1 Jgt111e,s.l,f hk M
_Pe newt ne=r
'00 00 01 .
01
- 02 Ot 03 04 74 03 04 M . n .
-4 08 at M -t 85 06 -1 07
-5 4' 06 90 OF -7 92 us -4 03
-7 10 97 88 Og 0 -t
-7 11 99 to -7 1 -2 100 90 11 -4 2 1 12 93 91 4 -5* 13 100 93 11 -4 2 2- 100 M,
13 4 3 14 M 93
-4 -4 3 15 98 93 14 -4 3 3 97 M M 15 -4 3 2 16 92 91
-5 5
- 17 92 92 15 2 0 86 4 -5 18 87 8B SB 86 87 17 -7 0 0 M 87 87 14 -7 -1 -2 19 85 M 86 7
to 82 85 at
" 19 -4
-7 -1 -t 80 83 M st 30 -10 -5 21 M 32 80
-10 -7 -t 22 M st 42 to II
-4 -7 -3 -7 77 m 82 at -10 -4 -7 23 81 82 79
-7 4 00 79 23 -10
-4 -5 -6 -7 00 77 79 to e M 00 -10 -4 -5 01 79 79 77
-9 -10 -5 et 75 78 79 75 01
-11 -5 -7 -5 M n 79 02 -9 -4 5 03 N 79 74
-10 -13 -5 04. 77 M 75 03 -5 -8 4 77 77 04 -9 -14 -4 06 76 FS TF
-15 4 -4 77 as -10 -9 06 80 M 79 79
-10 -15 07
-12 -16 at 08 M 80 82
. 07 -7 37 M 82 10 -14 Og 90 85 as 08
-4 -12 -3 to 91 to 00 95 92 10 -7 4 11 M 89
-5 12 M 93 11 96 ,
-1 13 95 '
12 98 0 14 M '
13 98 14 1 15 94 0 le 93 l 15 14
-3 17 90
-4 18 .
17 4 19 18
-4 to 19 t 21 to -2 21 22 El 23 l 23
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E926 - NOI1W15 20088W35 AW9 tritt te. Ct'aww 600
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' TABLE 451.11-3 UIGH TEMPERATURE EXTREME IN l
. ColfrROL BUILDING AT 21' -6" i MAXIMUM TEMPERATURE (OF)_
!- CONFARTMENT Emergency Switchgear Rooms 113.0
- Train A or Train B
- 113.3 .
Rod Drive HG-Set Rooms 103.0 Battery Rooma "A," "B." "C" Kr "D" Remainder of Switchgear Area 113.5'F
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