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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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George S. Thomas Vice President Nuclear Produchon N'.N 88007 Pubuc Service of New Hampshire January 22, 1988 Ncw Hamr snire Yankee Division United States Nuclear Regulatory Comission Washington, DC 20555 Attention: Document Control Desk References (a) Facility Operating License NPF-56, Docket No. 50-443 (b) USNRC Letter, Dated February 3, 1987, ' Inspection Report No. 50-443/86-54', E. C. Wenzinger to R. J. Harrison (c) PSNH Letter (NYN-87013), Dated February 9, 1987, ' Request for Additional Information", G. S. Thomas to the USNRC (d) PSNH Letter (NYN 87024), Dated March 2, 1987, ' Response to Inspection Report No. 50-443/86-54', G. S. Thomas to the USNRC
Subject:
Proposed Modification to Control Building HVAC (CBA) System Gentlemen:
In Reference (d), New Hampshire Yankee (NHY) comitted to provide the details of modifications to the Control Building HVAC (CBA) System for NRC review prior to implementation. In accordance with that commitment, Enclosure 1 provides a description of the proposed design modifications to the CBA System.
i Also, the post-LOCA radiological doses to Control Room personnel have been l reanalyzed by modeling the CBA System in the proposed configuration. The l results of this analysis are provided as Enclosure 2. Based upon the present l implementation schedule, it is requested that the NRC Staff provide comments l and/or concurrence regarding the proposed modifications by February 29, 1988.
l l Should you have any questions concerning this submittal, please contact l Mr. Warren J. Hall at (603) 474-9574, extension 4046.
l Very truly yours, p Q G rge . Thomas Enclosure cc: Mr. William T. Russell Mr. A. C. Cerne Regional Administrator NRC Senior Resident Inspector Region 1 Seabrook Station U.S. Nuclear Regulatory Commission Seabrook, NH 03874 631 Park Avenue King of Prussia, PA 19406 Mr. Victor Nerses, Project Manager go03 8802020261 860122 Project Directorate I-3 PDR ADOCK 05000443 1 l
l Division of Reactor Projects P PDR j U.S. Nuclear Regulatory Commission Washington, DC 20555 P.O. Box 300 . Seabrook, NH 03874 . Telephone (603) 474-9574
., ENCLOSURE 1 TO NYN-88007
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CONTROL R00M ilABITABiLITY'SISTEM'DESCRIPTiO REFERENCES
- 1. 10CFR50, Appendix A. General Design Criterion 19
- 2. NUREG-0800, Standard Review Plan (a). Section 6.4-(b) Section 6.5.1
- 3. PSNH Letter (NYN-87013)
- 4. PSNH Letter (NYN-87024)
- 5. PSNH Letter (NYN-87051)
INTRODUCTION One of the specific f unctions of the Control Building HVAC (CBA) System is to maintain the radiological exposure to Station operators within allowable limits :or a 30-day mitigation period following a Design Basis Accident (DBA). 'fhese limits are specified in References 1 and 2(a).
The subsystems of the CBA System which limit radiation exposure will collectively be referred to herein as the Control Room Habitability System. References 3 and 5 provided a description of those subsystems, as currently designed, which perform this function. Figure 1 shows the existing system configuration.
Modifications to the CBA System are proposed to be implemented prior to i operation above 5% of rsted power (References 3 & 4). The configuration of the modified Control Room Habitability System is shown in Figure 2 and consists of the following subsystems:
o Control Room Normal Makeup Air Subsystem o Control Room Emergency Makeup Air and Filtration Subsystem o Control Room Exhaust and Static Pressure Control Subsystem These subsystems function to maintain post-accident Control Room doses within allowable limits.
DESIGN BASES The control Room Habitability System is designed to provide filtered air for continuous occupancy of the Control Room complex by Station personnel during postulated emergency conditions.
The subsystems discussed above are specifically designed to satisfy the following design bases:
o Maintain a pressure of at least (+) 1/8" W.G. in the Control Room complex with respect to adjacent areas at all times to preclude the infiltration of hazardous contaminants.
- ENCLOSURE 1 TO NYN-88007 l (Co'ntinued)
CONTRdL ROOM'RABITABILITY SYSTEM DESCRIPTION o Provide for adequate air changeout to preclude excessive buildup of carbon dioxide and other noxious odors within the Control Room complex.
o ' Filter all Control Room makeup air and a portion of recirculated air during emergency / radiological conditions to prevent the buildup of airborne particulates and radioactive iodines within the Control Room complex.
o Satisfy the post-accident Control Room dose and habitability criteria specified in References 1 and 2(a).
SYSTEM DESIGN Durirg normal plant operation, the Control Room Normal Makeup Air Sub-system is aligned to deliver approximately 1000 cfm of outside air from remotely located intakes (500 cfm per intake). With or. : normal makeup air f an (CBA-FN-27A or 27B) operating, valves 1-CBA-V9 and 2-CBA-V9 will be positioned to allow equal amounts of air to be drawn from the east and west intakes. The makeup air discharges into a plenum immediately upstream of the CBA-F-38 filter components. This plenum is integral to the housing of CBA-F-38 and is made common to CBA-F-8038 by connecting ductwork. Approximately 500 cfm flows through the prefilter and electric heater for CBA-F-38, and discharges into the Control Room HVAC Equipment Room, bypassing the remainder of the filtra-tion system. The remaining air (approximately 500 cfm) flows through the filter crosstie to CBA-F-8038 where it flows through a prefilter and elec-tric heater and discharges into the Control Room HVAC Equipment Room, by-passing the remainder of the filtration system. Psnual isolation dampers are provided immediately downstream of the prefilter for CBA-F-38 and on the crosstie duct to CBA-F-8038. The dampers allow for train isolation.
The air heater in each filter operates continuously to maintain the relative humidity within the carbon adsorber section equal to or less than 70%. The Control Room Exhaust and Static Pressure Control Subsystem functions with exhaust f an (CBA-FN-15) operating and its discharge control damper (CBA-DP-28) modulating to maintain the Control Room complex at a pressure of at least (+) 1/8" W.G. with respect to adjacent areas. The redundant exhaust isolation damper (CBA-DP-1058) remains fully open during normal plant operation.
During emergency plant conditions, when high radiation is detected in either remote intake or upon generation of a safety injection ("S") '
signal, the Control Room Normal Makeup Air Subsystem (CBA-FN-27A and 27B, CBA-DP-53A and 53B) and the Control Room Exhaust and Static Pres-sure Control Subsystem (CBA-FN-15, CBA-DP-28, and CBA-DP-1058) are auto-matically isolated. In addition, both redundant Control Room Emergency Makeup Air and Filtration Subsystem fans (CBA-FN-16A and 16B) and dis-charge dampers (CBA-DP-27A and 27B) are automatically actuated.
, ENCLOSURE 1 TO NYN-88007 (Continued)
CO,NTROL ROOM HABITABILITY SYSTEM DESCRIPTION Either filter unit (CBA-F-38 or CBA-F-8038) and its associated f an are designed to draw a total of 600 cfm makeup air f rom both remote in-takes (300 cfm per intake) and 500 cfm recirculation air from the control Room HVAC Equipment Room, resulting in a flow rate of 1100 cfm per filter.
The system air flow rates specified above are for single train operation (i.e. , one emergency makeup air f an operating and its associated discharge damper fully open). The emergency makeup air fans and associated system configuration have been designed to ensure fan stability during dual train operation. The increased air flow rates for dual train operation will not impact the system's ability to satisfy its intended design bases. Conservatively high system flow rates projected for dual train operation have been assumed in calculating post-LOCA Control Room radio-logical doses (Reference Enclosure 2 to this submittal).
The emergency makeup air is drawn f rom the intakes via piping and back-draft dampers (CBA-DP-1061A, 1061B) which bypass the normal makeup air f ans and discharge dampers. This makeup air enters a suction plenum immediately upstream of CBA-F-38 which is made common to CBA-F-8038 by connecting ductwork. The makeup air is drawn through either or both filter units. Each unit is designed with a prefilter, an electric heater for humidity control, and a HEPA-carbon-HEPA filter configura-tion. Each filter housing is also designed with an orifice, immediately downstream of the heater, for recirculation airflow. The mixture of makeup air and recirculation air is drawn through the HEPA-carbon-HEPA configuration and discharged into the Control Room HVAC Equipment Room.
The filtered air is then distributed throughout the Control Room complex via the Control Room Air Conditioning System.
The 600 cfm makeup air flow rate and one filter unit are more than adequate to maintain the Control Room complex pressurized and provide required air changeout. The Control Room complex outleakage with the Control Room Exhaust and Static Pressure Control Subsystem fully iso-lated is calculated to be 165 cfm at a pressure of (+) 1/8" W.G. Pre-operational testing has determined this postulated leakage value to be conservatively high. The minimum required ventilation rate for occu-pancy/ breathing purposes is 175 cfm.
The total flow rate of 1100 cfm per filter train provides an average air flow velocity of 22 fpm for the CBA-F-38 carbon adsorber and 53 fpm for the CBA-F-8038 carbon adsorber. These velocities satisfy Regulatory Guide 1.52 minimum carbon residence time criterion of 0.25 seconds for the respective filter units.
A 4-inch diameter pipe with a manual isolation valve is provided to cross-connect the two filter units at a point downstream of the car-bon adsorber sections. The isolation valve will be throttled to a pre-set normally open position. During single train operation, this align-ment will provide approximately 50 cfm of air flow through the carbon A
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. ENCLOSURE 1 TO NYN-88007 (Continued)
CONTROL ROOM HABITABILITY SYSTEM DESCRIPTION adsorber section of the inactive train. This air flow will remove decay heat satisfying fire protection concerns. The isolation valve will be closed for train isolation in the event a fire is detected in one of the filter units.
INSTRUMENTATION AND CONTROL The Control Room Normal Makeup Air Subsystem f ans and discharge dampers are controlled f rom the Main Control Board (MCB). Opening of a discharge damper (CBA-DP-53A or 53B) satisfies a permissive to start its corres-ponding f an (CBA-FN-27A or 27B). During normal plant operation, one damper is open and its associated f an is running. Detection of high radiation at either remote intake will automatically close the damper and shut down the fan. The control scheme of the normal makeup air f ans and dampers is "cross-trained" to ensure isolation regardless of any single active failure. That is, detection of high radiation by either Train A monitor (RM-6507A for west intake or RM-6506A for east intake) will close CBA-DP-53B and trip CBA-FN-2 7A. Detection of radiation by either Train B monitor (RM-6507B for west intake or RM-6506B for east intake) will close CBA-DP-53A and t rip CBA-FN-27B. Failure of a vital bus will also isolate the system.
Redundant radiation monitoring instruments are provided for each remote intake. Details of the radiation monitoring instrumentation are provided in Section 12.3.4 of the FSAR. Status lights are provided on the MCB for the normal makeup air f ans and dampers. Status indication is also provided on the MCB for the intake isolation valves (1-CBA-V9 and 2-CBA-V9). Isolation of the Control Room Normal Makeup Air Subsystem generates an alarm at the MCB. Smoke detection alarms are provided for each intake.
The Control Room Emergency Makeup Air and Filtration Subsystem f ans and discharge dampers are also controlled from the MCB. In the auto mode, CBA-DP-27A and 27B will open upon receipt of a high radiation signal or a saf ety injection ("S") signal. Opening of these dampers will automat-ically start associated fan CBA-FN-16A or 16B. A high radiation signal or starting f ans 16A and 16B will trip CBA-FN-27A and 27B and isolate dampers CBA-DP-53A, 53B, 28, and 1058. Each filter air heater operates continuously. High and high-high temperature heater trips are provided.
The high-high temperature trip requires local / manual reset. Status lights are provided on the MCB for the fans and discharge dampers.
Status lamps are also provided for the fans in the Accident Monitoring Instrumentation arrays.
Differential pressure indication across each filter component is pro-vided locally. High dif ferential pressure across each filter unit generates an alarm at the MCB. The temperature for each filter unit is indicated locally. High temperature generates an alarm at the MCB.
ENCLOSURE 1 TO NYN-88007 (Continued)
CONTROL ROOM HABITABILITY SYSTEM DESCRIPTION Relative humidity for each filter unit is monitored by the Main Plant Computer, with high relative humidity generating an alarm at the MCB.
Air flow for each filter train is monitored by the Main Plant Computer.
Two carbon monoxide detectors per filter unit (one each at the inlet and outlet of the carbon adsorber banks) provide for early fire detection.
These devices monitor the filtration systems and generate an alarm in the Control Room.
The Control Room Exhaust and Static Pressure Control Subsystem f an (CBA-FN-15) and discharge control damper (CBA-DP-28) are controlled from the MCB. During normal plant operation, the f an is running and J
the discharge damper modulates to maintain Control Room pressure at
> (+) 1/8" W.G. This modulating feature is controlled by a differential pressure control loop. This control loop senses pressure in the Control Room HVAC Equipment Room, Cable Spreading Room, and the outside atmosphere.
The damper is modulated automatically to maintain the Control Room HVAC Equipment Room at > 1/8" W.G. positive pressure with respect to atmosphere and the Cable Spreading Room. The redundant exhaust isolation damper (CBA-DP-1058) is fully open during normal plant operation. Loss of normal makeup air and/or loss of Control Room pressurization will close CBA-DP-28 and trip CBA-FN-15. Interlocks are provided so that isolation dampers .
CBA-DP-28, 1058 and exhaust f an CBA-FN-15 are isolated whenever a high i radiatica signal is present or f an 16A or 16B is running. Status indica-tion for CBA-FN-15, CBA-DP-28 and 1058 is provided on the MCB. Indication of differential pressure between the Control Room HVAC Equipment Room and outside atmosphere is provided in the HVAC Room. This differencial pres-sure, as well as the differential pressure between the Cable Spreading Room and the HVAC Room, is monitored by the station computer.
SAFETY EVALUATION The Control Room Habitability System is being modified to ensure compli-ance with 10CFR50, Appendix A, GDC 19, and Section 6.4 of the Standard Review Plan.
All active components in the Control Room Normal Makeup Air Subsystem, Control Room Emergency Makeup Air and Filtration Subsystem, and Control Room Exhaust and Static Pressure Control Subsystem, except exhaust fan CBA-FN-lS, are designed to meet ANS Safety Class 3 and Seismic Categorv I requirements. The exhaust f an is designed NNS.
Filtration systems CBA-F-38 and 8038, including associated f ans and dampers, are designed as Engineered Safety Features (ESP) in accordance with Regulatory Guide 1.52 and Section 6.5.1 of the Standard Review Plan.
The filter trains are fully redundant.
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, _ - ._.~ _ _ __ ._ _ ._ ..- - -
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ENCLOSURE 1 TO NYN-86007 (Continued)
CONTROL ROOM HABITABILITY SYSTEM DESCRIPTION All redundant active components :>re powered by separate and independent trains of emergency power f rom the diesel generators. Pneumatically actuated system dampers are designed to f ail in the safe position as follows:
CBA-DP-53A Fail Closed CBA-DP-53B Fail Closed CBA-DP-28 Fail Closed CBA-DP-1058 Fail Closed CBA-DP-27A Fail Open CBA-DP-27B Fail Open in addition, the piping which bypasses the normal makeup air f ans and dampers is provided with redundant parallel backdrait dampers (CBA-DP-1061A and 1061B). This design ensures that an emergency makeup air flow path is available in the event one of the backdraf t dampers f ails to open with flow initiated upon actuation of CBA-FN-16A or 16B.
The redundant and f ail-safe damper design ensures that the system will perform its safety-related function regardless of any single active failure.
The motors for CBA-FN-16A and 16B, CBA-FN-27A and 27B are designed Class IE. The electric air heaters associated with each filter are also Class lE. All electrical, instrumentation and control systems which perform vital control functions are designed Class IE in accordance with IEEE S tanda rd 279-1971, and otherwise satisfy existing commitments in Chapters 7 and 8 of the FS AR.
The makeup air duct upstream of CBA-F-38 and 8038 and external to the Control Room complex envelope is heavy-wall carbon steel pipe designed to remain intact and functional following a seismic event. The filter housings, discharge ductwork, and all other passive system components are also designed to remain intact and functional following a seismic event. All portions of the makeup air system external to the Control Room complex envelope are designed to minimize inleakage.
All active and passive components of the system are contained in missile-protected buildings or are underground. No internally-generated missiles which could impair the system's ability to perform its safety-related functions are credible.
The proposed modifications do not increase the probability of occurrence or consequences of an accident or malfunction of equipment important to safety nor create the possibility for an accident or malfunction of a type other than currently evaluated in the FSAR. The proposed modifi-cations do not reduce the mardin of safety ao currently defined in the bases for any Technical Specifications.
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ENCLOSURE 2 TO NYN-88007 CONTROL ROOM POST-LOCA RADIOLOGICAL DOSES The Control Room doses for the DBA-LOCA have been reanalyzed modeling the Control Room Habitability System in accordance with the proposed modifications. The analysis is based on the following assumptions or inputs.
o Source Term: Radiological releases based on current DBA-LOCA assumptions specified in FS AR Section 15.6.5 as follows.
- Containment Leakage (La) = 0.15% Containment Mass / Day Secondary Containment Bypass Leakage = 0.60 La Secondary Containment Evacuation Time = 8 Minutes o Control Room Complex Volume: 246,000 ft 3 as specified in FSAR Section 6.4.
o Control Room Emergency Filters: Redundant systems are located within the Control Room complex boundary filtering all outside makeup air and a percentage of recirculation air with the following efficiencies:
95% Elemental Iodine 95% Organic Iodine 99% Particulate Iodine o Control Room Emergency Makeup Air and Filtration Subsystem Flow Rates: A total subsystem flow rate of 2000 cfm is the projected maximum for dual train operation. 1200 cfm make up air and 800 efm recirculation air is assumed. The higher than projected makeup air to recirculation air flow rate proportion is conservative as doses increase with increasing makeup air. Na credit is taken for manual isolation of a contaminated remote intake (i.e., both intakes remain open for the 30-day release period).
o Unfiltered Infiltration: 1200 cfm is assumed for two seconds during automatic system alignment (i.e., switchover from Control Room Normal Makeup Air Subsystem to Control Room Emergency Makeup Air and Filtration Subsystem). The actual normal makeup air flow rate is approximately 1000 cfm. This assumption is therefore conservative. Following the system realignment, unfiltered in-filtration is assumed to be 0 cfm for the primary ingress / egress boundary (double door configuration) and I cfm for the single door emergency fire exit (based on low anticipated usage).
ENCLOSURE 2 TO NYN - 88007 (Continued)
CONTROL ROOM POST-LOCA RADIOLOGICAL DOSES o Atmospheric Dispersion Factors X/Q (Sec/M3 )
Time Period (hr) Control Room West Intake East Intake 0-1 4.08E-03 1.13 E-0 3 1.4 2E-03 1-2 3.18E-03 7.06E-04 1.14 E-0 3 2-8 2.04E-03 3.55E-04 6.95E-04 8-24 1.44E-03 1.45E-04 4.67E-04 24-96 9.78E-04 8.58E-05 3.05E-04 96-720 7.51E-04 5.71E-05 2.00E-04 Dose results are based on X/Q values for worst intake (east) divided by two for dilution since equal amounts of makeup air will be drawn f rom each intake for the 30-day release duration.
The resultant 30-day Control Room doses for the DBA-LOCA are as follows:
Thyroid Dose 25.0 rem Whole Body Gamma Dose 4.1 rem Skin Dose 6.5 rem
-