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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:NRC TO UTILITY
MONTHYEARML20062E4151990-11-16016 November 1990 Forwards H Myers 901019 Request for Info Re Plant Welds for Appropriate Action ML20217A2531990-11-15015 November 1990 Requests Info Re Surety Bond & Status of Eua Power Interest in Surety Bond ML20058E6871990-10-29029 October 1990 Ack Receipt of in Response to NRC Announcing Intent to Perform Team Insp of Maint Program on 901203-14.Subj Insp Date Changed to 910128-0208 Due to Various Complications ML20058D6061990-10-24024 October 1990 Forwards Safety Insp Rept 50-443/90-17 on 900905-1014. Actions Taken on Previous Insp Findings Found to Be Adequate ML20058A3461990-10-17017 October 1990 Informs That Util Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-08,Item 2.2 'Vendor Interface for Safety-Related Components,' Acceptable IR 05000443/19900181990-10-17017 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-443/90-18 ML20058B8081990-10-12012 October 1990 Informs That SW Kessinger Scheduled to Participate in NRC 901022 Requalification Exam IR 05000443/19900151990-10-0202 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-443/90-15 ML20059N8241990-10-0101 October 1990 Informs of 901203-14 Maint Program Team Insp & Forwards NRC Temporary Instruction 2515/97,Rev 1 ML20059L8831990-09-21021 September 1990 Forwards Safety Insp Rept 50-443/90-16 on 900730-0904.No Violations Noted ML20059H0601990-09-0707 September 1990 Discusses Unescorted Access to Licensee Facilities & fitness-for-duty Program,Per .Nrc Regulations Do Not Prohibit Licensee from Accepting Access Authorization Program of Another Licensee,Contractor or Vendor ML20058P7851990-08-16016 August 1990 Forwards Safety Insp Rept 50-443/90-15 on 900625-0729 & Notice of violation.Self-assessment Team Rept on Power Ascension Testing Demonstrated Ability to Be self-critical & Results Corresponded Well W/Nrc Assessments of Performance ML20058N1121990-08-10010 August 1990 Provides Comments on Util 900102 Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. NRC Does Not Take Any Position on Acceptability of Util Station Gauge Methodology ML20058M6181990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Licensee Has Undertaken Positive Initiatives in Engineering Area, Including Design Basis Document Updates,Safety Sys Functional Insps & Other Engineering Program Improvements ML20055G7591990-07-16016 July 1990 Forwards Safety Insp Rept 50-443/90-13 on 900521-25.No Violations Noted.Weaknesses Noted ML20055G1481990-07-12012 July 1990 Forwards Safety Insp Rept 50-443/90-12 on 900514-0624 ML20055G1771990-07-11011 July 1990 Requests Util Provide Ref Matls Listed in Encl for Requalification Program Evaluation Scheduled for 901015-26. Facility Mgt Responsible for Providing Adequate Space & Accomodations to Properly Develop & Conduct Exams ML20055G0471990-07-0505 July 1990 Forwards Safeguards Insp Rept 50-443/90-14 on 900618-22.No Violations Observed.One Potential Weakness Identified Which Requires Attention to Maintain Effectiveness of Security Program ML20055F5391990-07-0202 July 1990 Forwards Special Power Ascension Team Insp Rept 50-443/90-81 on 900316-0502.Power Ascension Test Program Acceptable ML20055D0941990-06-28028 June 1990 Forwards Transcript of 900619 Public Meeting to Discuss Assessment of Power Ascension Test Program Performance Up to 50% Power Level ML20055D0761990-06-26026 June 1990 Advises of Completion of Review of Proposed Changes to Emergency Action Levels for Plant & Found Rev to Emergency Plan Acceptable W/Listed Understandings ML20055C9991990-06-25025 June 1990 Formalizes Requests Made in Conversation Between J Grillo & Ph Bissett on 900619 Re Planned Insp of Facility EOPs ML20059M9361990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248G1381989-09-26026 September 1989 Forwards SALP Rept 50-443/87-99 for Aug 1987 - June 1989 ML20247N7101989-09-15015 September 1989 Requests Encl Listed Ref Matl for 891211 Evaluation of All Shift Operating Crews on Simulator Using NRC-developed Scenarios ML20247K9511989-09-13013 September 1989 Forwards Safety Inspt Rept 50-443/89-08 on 890701-0817.No Violations Noted ML20246P6341989-09-0606 September 1989 Forwards SER Re Generic Ltr 83-28,Item 4.5.3, Reactor Trip Sys Reliability for All Domestic Operating Reactors. Existing Intervals for on-line Functional Testing at Plant Consistent W/Achieving High Reactor Trip Sys Availability ML20246N8211989-08-29029 August 1989 Advises That Reactor & Senior Reactor Operator Exams Scheduled for Wk of 891114,per Telcon.Licensee Responsible for Providing Encl Ref Matl by 890901 ML20246F3181989-08-21021 August 1989 Forwards Safety Insp Rept 50-443/89-07 on 890619-23.No Violations Noted.Concerns Re Steam Leakage Problems Through Auxiliary Feed Pump Turbine Control Valves & Leakage Through Certain RCS Pressure Isolation Valves,Expressed ML20246J3601989-08-18018 August 1989 Clarifies NRC Position Re Definition of Extremity for Purpose of Setting Occupational Exposure Limits.Procedures Should Incorporate Applicable Dose Limits of 10CFR20 IR 05000443/19890821989-08-17017 August 1989 Forwards Augmented Team Insp Rept 50-443/89-82 on 890628-30, Enforcement Conference Issues & Related Regulatory Requirements.W/O Insp Rept ML20246A9201989-08-11011 August 1989 Forwards Team Safety Insp Rept 50-443/89-81 on 890612-23.No Violations or Unresolved Items Noted ML20247Q7431989-07-28028 July 1989 Forwards Safety Insp Rept 50-443/89-06 on 890527-0630. Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-443/89-03 ML20247N5731989-07-28028 July 1989 Forwards Safety Evaluation Updating Status of Onsite & Offsite Emergency Preparedness for Plant.Onsite Emergency Preparedness Acceptable & Adequate for Full Power Operation. Offsite Emergency Preparedness Will Be Acceptable ML20247L9611989-07-18018 July 1989 Advises That Proposed Objectives for 1989 Annual Exercise of Radiological Emergency Plan Acceptable for Intended Purpose IA-89-326, Advises That Proposed Objectives for 1989 Annual Exercise of Radiological Emergency Plan Acceptable for Intended Purpose1989-07-18018 July 1989 Advises That Proposed Objectives for 1989 Annual Exercise of Radiological Emergency Plan Acceptable for Intended Purpose ML20247A9801989-07-14014 July 1989 Forwards Readiness Assessment Team Insp Rept 50-443/89-80 on 890527-0601.No Violations Noted ML20245J2101989-06-23023 June 1989 Confirmation of Action Ltr 89-11,confirming 890623 Telcon. Understands That Listed Actions Will Be Completed Prior to Startup in Response to 890622 Reactor Manual Trip Which Occurred During Natural Circulation Startup Test ML20245F0891989-06-21021 June 1989 Forwards Insp Rept 50-443/89-05 on 890424-0527.Violation Noted Re Storage Location for Svc Water Cooling Water Pump ML20245A9051989-06-15015 June 1989 Forwards SER Re Proposed Implementation of ATWS Rule (10CFR50.62) Requirements.Pending Final Resolution of Tech Spec Issue,Atws Design Proposed by Util in Compliance W/Rule.Design Mods Should Be Completed by Sept 1990 NUREG-0896, Forwards Sser 8 (NUREG-0896),addressing Issues Re 5% Low Power License.W/O Encl1989-06-0909 June 1989 Forwards Sser 8 (NUREG-0896),addressing Issues Re 5% Low Power License.W/O Encl ML20244D0951989-05-26026 May 1989 Forwards License NPF-67,authorizing Operation of Facility to Power Levels Not Exceeding 5% of Rated Power & Limited to No More than 0.75 Effective Full Power Hours ML20247R5731989-05-25025 May 1989 Forwards Insp Rept 50-443/89-03 on 890228-0424 & Notice of Violation.Ack Util Intention to Initiate Appropriate Corrective Action as Described in .Notice of Violation Re Welding Program Deficiencies Not Issued ML20247G3331989-05-21021 May 1989 Forwards Summary of NRC Understanding of How Restrictions on Low Power Physics Testing Will Be Met.Approach Satisfactory ML20247L7401989-05-18018 May 1989 Forwards Safety Insp Rept 50-443/89-04 on 890327-31.No Violations Noted ML20247L9411989-05-0505 May 1989 Provides Guidelines for Review of Emergency Exercise Objectives & Scenario Packages Prior to Plant Partial Participation Emergency Exercise Scheduled for Wk of 890925, Including Schedule CLI-88-10, Forwards Safety Evaluation Accepting Licensee Decommissioning Funding Assurance Plan.Plan Provides Necessary Assurance & Satisfies Requirements in Decision CLI-88-101989-05-0303 May 1989 Forwards Safety Evaluation Accepting Licensee Decommissioning Funding Assurance Plan.Plan Provides Necessary Assurance & Satisfies Requirements in Decision CLI-88-10 ML20247B0911989-05-0303 May 1989 Extends Invitation to Attend Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Agenda Encl ML20246F3911989-05-0202 May 1989 Requests Explanation Re Effect of Paragraph M.5 of Section 6.01 of Supplementary Decommissioning Trust Agreement Re Funds (Strips) to Be Provided for Supplementary Trusts ML20245F5861989-04-25025 April 1989 Comments on Supplemental Decommissioning Funding Financial Assurance Arrangements Presented at 890420 Meeting in Rockville,Md.Listed Info Should Be Included in Formal Response to Comments 1990-09-07
[Table view] Category:OUTGOING CORRESPONDENCE
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 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 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 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 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 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 ML20212J0301999-09-24024 September 1999 Forwards Insp Rept 50-443/99-10 on 990726-30 & 0809-13.No Violations Noted.Insp Discussed 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 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 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 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 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 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 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 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 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 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 ML20210J8421999-08-0303 August 1999 Forwards Order,Conforming Amend & SER in Response to Application Transmitted by Util Under Cover Ltr , & Suppl by Ltrs & 0407 Requesting Approval of Transfer of License NPF-86 ML20210K4911999-07-28028 July 1999 Responds to to Chairman Jackson Requesting Info on Concerns Raised by Constitutent a Menninger,Re Seabrook Nuclear Power Station Y2K Readiness IR 05000443/19990041999-07-26026 July 1999 Forwards Insp Rept 50-443/99-04 on 990510-0620.No Violations Noted.Emergency Preparedness Program Reviewed & Found to Be Acceptable ML20209G4711999-07-14014 July 1999 Informs That Unredacted Version of Supplemental Commercial & Financial Data for Baycorp Holdings,Ltd,Submitted in 990407 Application & Affidavit,Marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20196J7011999-06-30030 June 1999 Forwards Second Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20209A6701999-06-25025 June 1999 Informs That NRC Ofc of NRR Reorganized Effective 990528.As Part of Organization,Div of Licensing Project Mgt Was Created.Organization Chart Encl IR 05000443/19990021999-06-21021 June 1999 Forwards Insp Rept 50-443/99-02 on 990321-0509.Violation Re Failure to Ensure That Critical Relay Calibr Characteristics Were Met Prior to Installation Was Identified ML20196G8421999-06-21021 June 1999 Forwards Copy of Notice of Consideration of Approval of Application Re Proposed Corporate Merger & Opportunity for Hearing Re 990315 Application Filed by Nepco ML20196J4451999-06-18018 June 1999 Ack Receipt of ,Following Up on .In Ltr of April 5,EJ Markey Highlighted Issue of EDG Reliability in Light of Recent Discovery of Defective AR Relays at Seabrook NPP in New Hampshire ML20212J2651999-06-17017 June 1999 Informs That Unredacted Version of Updated Financial Data for Baycorp Holdings,Ltd Will Be Withheld from Public Disclosure & Marked as Confidential Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act ML20212H6661999-06-15015 June 1999 Forwards RAI Re 990315 Application Request for Approval of Proposed Indirect Transfer of Seabrook Station,Unit 1 License & Proposed Indirect Transfer of Millstone,Unit 3 License to Extent Held by Nepco ML20207B2221999-05-20020 May 1999 Forwards Insp Rept 50-443/99-03 on 990308-0408.Violations Identified & Being Treated as non-cited Violations ML20206K1811999-05-0707 May 1999 Responds to Re Event Notification from North Atlantic Energy Service Co Indicating That One of Seabrook Two EDG May Have Been Inoperable Since June 1997. NRC Insp of Problem Not Yet Completed ML20206N6811999-04-23023 April 1999 Ack Receipt of ,Re Potential Inoperability of Two Emergency Diesel Generators Since June 1997 at Seabrook Nuclear Power Station.Issue Under Ongoing Insp & Review by NRC ML20205R1171999-04-20020 April 1999 Ack Receipt of Ltr Requesting Action Under 10CFR2.206 Re Enforcement Action Against Individuals Alleged to Have Unlawfully Discriminated Against Contract Electrician. Request to Attend Enforcement Conference Denied.Frn Encl ML20206B3451999-04-20020 April 1999 Forwards Insp Rept 50-443/99-01 on 990207-0321.Violations Identified Involving Failure to Properly Test Primary Auxiliary Building for Test Failures & Inadequate C/A to Prevent Recurrence of Repeated Pab for Test Failures ML20205P1871999-04-0909 April 1999 Discusses 990225 PPR & Forwards Plant Issues Matrix & Insp Plan.Advises of Planned Insp Effort Resulting from Plant PPR Review ML20205N4991999-04-0808 April 1999 Responds to Requesting Copy of OI Rept 1-1998-005,or in Alternative Summary of Investigation Rept. Request for Copy of Investigation Rept,Denied at This Time, Because NRC Did Not Make Final Enforcement Decision ML20205C1891999-03-24024 March 1999 Refers to Naesco 981030 Request for Approval of Alternative Inservice Exam to That Specified by ASME BPV Code,Section XI,1983 edition/1983 Summer Addenda.Forwards SE Supporting Proposed Relief Request IR-8,Rev 1 ML20204E4191999-03-16016 March 1999 Informs of Results of Investigation Conducted at Seabrook Nuclear Generating Station by NRC OI & Requests Participation at Predecisional Enforcement Conference in King of Prussia,Pa Relative to Investigation 1-98-005 ML20204F3101999-03-16016 March 1999 Discusses Investigation Conducted at Plant by OI Field Ofc, Region 1.Purpose of Investigation to Determine Whether Certain Activities Conducted Per NRC Requirements.Synopsis of IO Investigation Rept 1-98-005 Encl ML20210U2281999-03-16016 March 1999 Refers to Apparent Violation of NRC Requirements Prohibiting Deliberate Misconduct by Individuals & Discrimination by Employers Against Employees Who Engage in Protected Activities,Investigation Rept 1-98-005 ML20207C2991999-02-26026 February 1999 Forwards Insp Rept 50-443/98-11 on 981228-990207.No Violations Noted.Inspectors Identified Several C/A Program Deficiencies Involving Timeliness of Reviews & Effectiveness of Previous C/As ML20203A2811999-01-28028 January 1999 Forwards Insp Rept 50-443/98-10 on 981115-1227.No Violations Noted.Operators Performed Well During Two Reactor start-ups & Response to Plant Trip on December 22.Radioactive Waste Mgt Program Properly Implemented ML20198Q7391998-12-21021 December 1998 Informs That Review of Licensee Response to GL 97-05, SG Tube Insp Techniques, Did Not Identify Any Concerns with SG Insp Techniques Employed at Seabrook That Would Indicate That Naesco Not in Compliance with Licensing Basis ML20198S1661998-12-17017 December 1998 Final Response to FOIA Request for Documents.Records Encl & Identified in App C & D.App E Records Withheld in Part & App F Records Withheld in Entirety (Ref FOIA Exemption 5) & App G Records Withheld in Entirety (Ref FOIA Exemptions 4 & 5) ML20198D1341998-12-16016 December 1998 Forwrds Ltr from J Bean Transmitting Final Exercise Rept for 981020,MS-1,out of Sequence Drill for Elliot Hosp in Manchester,Nh.Assistance Being Requested to Offsite Officials to Address & Resolve Identified Arca Timely ML20198C1131998-12-11011 December 1998 Forwards Insp Rept 50-443/98-09 on 981004-1114 & Notice of Violation.Nrc Identified That Safety Equipment Removed from Service at Beginning of Forced Outage Without Appropriate Monitoring of Status of Equipment as Required ML20197K1931998-12-0909 December 1998 Forwards RAI Re Utilities Participation in WOG Response to GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations. Response Requested within 90 Days of Submittal Date 1999-09-30
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>> MS g i5 g NUCLEAR REGULATORY COMMISSION-g WASHINGTON. D. C. 20555 May 21, 1989 Docket No. 50-443 Mr. Edward ' A. Brown President 8' Chief Executive Officer New Hampshire Yankee Division Public Service Company of New Hampshire Post Office Box 300 Seabrook, New Hampshire 03874
Dear Mr. Brown:
SUBJECT:
SEABROOK LOW POWER PHYSICS TESTS U
I In accordance with the Commission Order, CLI-88-10 dated December 21, 1989, for any low power testing license that may be issued for Seabrook Unit 1, the license will be conditioned to allow operation at pcwer levels not in excess of five percent and shall permit no more than 0.75 effective full power hours (EFPH) of operation.
In consideration that such a license may be issued, we have reviewed the manner in which your staff intends to perform low power physics tests and remain
} within the license restriction of 0.75 EFPH and 5% maximum power' level. The enclosure presents a summary of our understanding of how the two restrictions are expected to be met. We find the approach to be- satisfactory.
p Sincerely, s_- ., . 8 M c. G Victor Nerses, Project Manager Project Directorate I-3 Division of Reactor Projects I/II L
Enclosure:
i As stated cc w/o enclosure:
See next page f
Public Service Company of New Hampshire q Cc:.
l Thomas Dignan, Esq. E. Tupper Kinder, Esq.
'o John A. Ritscher, Esq. G. Dana Bisbee, Esq.
Ropes and Gray Assistant Attorney General-
'225 Franklin Street Office of Attorney General Boston, Massachusetts 02110 208 State House Annex Concord,-New Hampshire 03301 Mr. Bruce B. Beckley, Project Manager Public. Service' Company of New Hampshire Resident Inspector Post Office' Box 330 US Nuclear Regulatory'Comission Manchester, New Hampshire 03105 Post Office Box 1149 Seabrook, New Hampshire 03874 Dr. Mauray Tye, President Sun Valley Association Mr. A. M. Ebner, Project Manager-
'209 Summer Street United Engineers & Constructors Haverhill, Massachusetts 01830 Post Off ke Box 8223 Philadetph?a, Pennsylvania 19101 Robert Backus, Esq.
Backus, Meyer and Solomon Steven Oleskey, Esq.
116 Lowell Street Office of the Attorney General Manchester, New Hampshire 03106 One Ashburton Place P.O. Box 330 Diane Curran, Esq. Boston, Massachusetts 02108 Harmon and Weiss
, 2001 S Street, NW Carol S. Sneider, Esq.
Suite 430. Office of the Assistant Attorney General Washington, D.C. 20009 One Ashburton Place P.O. Box 330 Philip Ahren, Esq. Boston, Massachusetts 02108-Assistant Attorney General State House, Station #6 D.- Pierre G. Cameron, Jr., Esq.
Augusta, Maine 04333 General Counsel Public Service Company of New Hampshire Mr. Edward A. Brown, President Manchester, New Hampshire 03105 and Chief Executive Officer New Hamp hire Yankee Division Mr. Jac s 1 Pesc!ki Public Service Company of Public Service Company of New Hamsphire New Hampshire P.O. Box 300 Post' Office Box 300 Seabrook, New Hampshire 03874 Seabrook, New Hampshire 03874 Seacoast Anti-Pollution League Regional Administrator, Region I 5 Market Street U.S. Nuclear. Regulatory Comission Portsmouth, New Hampshire 03801 475 Allendale Road 25 Maplewood Ave.
King of Prussia, Pennsylvania 19406 Ms. Diana P. Randall Ashod N. Amirian, Esq.
70 Collins Street Town Counsel for Merrimac Seabrook, New Hampshire 03874 376 Main Street Mr. T. Feigenbaum Public Service Company of New Hamsphire Post Office Box 330 Seabrook, New Hampshire 03874
- m. ,
l Edward A. Brown, Public Seabrook Nuclear Power Station Service Company of New Hampshire CC*
Mr. Calvin A. Canney, City Manager Mr. Alfred Y. Sargent, City Hall Chairman 126 Daniel Street Board of Selectmen Portsmouth,.New Hampshire 03801 Town of Salisbury, MA 01950 Board of Selectmen Senator Gordon J. Humphrey RFD Dalten Road ATTN: Tom Burack Brentwood, New Hampshire 03833 531 Hart Senate Office Building U.S. Senate Ms. Suzanne Breiseth, Washington, D.C. 20510 Board of Selectmen Town of Hampton Falls Drinkwater Road Mr. Owen B. Durgin, Chairman Hampton Falls, New Hampshire 03844 Durham Board of Selectmen Town of Durham Mr. Guy Chichester, Chairman Durham, New Hampshire 03824 Rye Nuclear Intervention Committee Jane Spector c/o Rye Town Hall Federal Energy Regulatory 10 Central Road Commission Rye, New Hampshire 03870 825 North Capital Street, N.E.
Room 8105 Chairman, Board of Selectmen Washington D. C. 20426 RFD 2 South Hampton, New Hampshire 03827 Mr. R. Sweeney R. Scott Hill - Whilton Three Metro Center Lagoulis, Clark, Hill-Whilton suite 610
& McGuire Bethesda, Maryland 20814 l 79 State Street Newburyport, Ma. 01950 Mr. Richard Strome, Dire.ctor '
1 . iL Cashman, Chairman New Hanipshire. Office ci t merge 6cy Board of Selectmen Management Town of Amesbury State Office Park South Town Hall 107 Pleasant Street Amesbury, Massachusetts 01913 Concord, New Hampshire 03301 Adjudicatory file (2)
Honorable Peter J. Matthews Atomic Safety ae.d Licensing Board Mayor, City of Newburyport Panel Docket City Hall U.S. Nuclear Regulatory Commission Newburyport, Massachusetts 01950 Washington, D.C. 20555 Mr. Donald E. Chick, Town Manager Congressman Nicholas Mavroules Town of Exeter 70 Washington Street 10 Front Street Salem, Massachusetts 01970 Exeter, New Hampshire 03823 Mr. G. Thomas Mr. John C. Duffett Public Service Company of President and Chief Executive Officer New Hampshire Public Service Company of New Hampshire Post Office Box 330 1000 Elm St., P.O. Box 330 Seabrook, New Hampshire 03874 Manchester, New Hampshire 03105
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Seabrook 55/0.75 EFPH Operation GENERAL INFORMATION 3 0.75 effective full power hours (EFPH) operation for Seabrook is equiva-lent to 0.75 x 3411MW x 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> = 2558 MW -br. At5% power (or170.6MW)' t t t Seabrook could operate continuously for 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />. The tests to be conducted are primarily_ low power physics tests and a natural circulation test. The majority of the low power physics tests are conducted in the zero power test range (approximately .01% power). Low power flux mapping will be conducted at approximately 1% power and the natural circulation test'will be conducted at approximately 3% power.
The process that will be used to determine core exposure during the low power test program will be identical to that used to determine core exposure during normal plant operation. However, instead of using a secondary calorimetric to calibrate (normalize) the power range nuclear instruments the core AT power will be used to calibrate'(normalize) theintermediaterange(IR)nuclearinstruments. This calibration will-be based on the full power core temperature risc (core A T). One of the first evolutions to be performed in the low power test program till be to increase reactor power to 3% (based on core AT) and record the IR detector currents. From the data obtained by this evolution, the normal-irction enrs.txt , frr each intermediate range detector (amps /% power) n will be determined.
A process computer program has been written to record the IR detector currents and the time between program executions. The program then utilizes this data along with the IR detector normalization constants to
. calculate core exposure. The EFPH will be the sum of the test power levels times the test time and this sum will be maintained below 2558 Mw -hr.
t
4 2-SPECIFIC INFORMATION Reactor power will be measured using the core temperature rise normalized to the full power core temperature rise (comonly referred to as AT power). The IR detector outputs will then be normalized to the measured core 4 T power. It will be necessary to calibrate (normalize) the IR detectors to trace core exposure because most of the low power testing is conducted in the zero power test range where core AT is O'T but the IR detectors are producing a current equivalent to approximately .01% power.
The uncertainties associated with the measurement of core 4T are about the same magnitude as the measurement itself. To offset this, a full power core 6T of 57.0'F.is used to determine the IR detector normalization constants. A full power core AT of 57.0*F is conservative with respect to the expected full power value of 59.4*F. The process of normalizing l
L the IR detector output to match coreoT power also normalizes out any uncertainties associated with the IR detector outputs. Thus, the IR detector outputs simply inherit the error associated with the core oT measurements which has already been accounted for.
All instruments necessary to monitor core exposure are calibrated with the exception of the IR detector output normalization. IR detector normalization will be performed during normai plant startup regardless of any core exposere .mitations.
There is no specific plan or schedule for expending the .75 EFPH. The only plan that exists is the low power test sequence which, if goes as planned and without any unforeseen test or equipment difficulties, should be completed within the allotted exposure limit. The tests are expected to be completed in about ten days.
A special computer program has been written for the main plant computer to calculate and track core exposure. An administrative procedure will be written to ensure that the exposure limit will not be exceeded and to document core exposure'. The administrative procedure that tracks and documents core exposure will contain a section on manual tracking of core exposure if the plant computer is unavailable.
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!.0 INTRODUCTION When the low power license for Seabrock is issued, it is expected to contain an accumulated core exposure limitation of 45 effective full power minutes (EFPM). To verify compliance with any EFPM limitations
.and to simplify will be used. the core exposure tracking, an NPCS computer program This functional description specifies the requirements and basis for the calculations that will be ured by the program to track accumulated core exposure.
2.0 DEFINITION OF TERMS EFPM, Effective Full Power Minute LPPT. Low Power Physics Testing MCB. Main Control Board HPCS, Main Plant Computer System RE. Reactor Engineering 3.0 ASSUMPTIONS 3.1 The power Invel existing at the time of program execution has existed since the last program execution.
3.2 The response of intermediate range instrumentation versus power level is linear.
4.0 DESCRIPTION
A program for tracking core curnup currently exists on the MPCS; however, it lacks the capability to accurately track core exposure at low power levels.
during icwA power separate program is required to track core exposure (in EFPM) physics testing. The new program will operate as follows:
4.1 The program will be ectivated by the periodic scheduler on a 5 minute basis. Since the program is temporary in nature, it will M a ',tand alone program and will not be incorporated in thu existirig
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RE 5 minute task (RE5 MIN}.
4.2 Due to the temporary need for the program, no DA1 disc storage will be used. All tracking will be dene with 6 calculated points which are described below!
- Calculated Point 1: This point is the cumulative amp-minutes calculated using intermediate range chanse) 35 indication. This C point will be updatcc every program execution.
- Calculated Point 2: This point is the camulative amp-minutes calculated using intertrediate range channel 36 indication. This C point will be updated every program execution.
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- Calculated Point 3: This point is the channel conversion con-stant used to convert intermediate range channel 35 amp-minutes
-into an ETPM value. Thts C point will be updated by RE. as required, using the Analog Management-Function at the HCB. This point will not be RELIAB cnecked since use of a subftttute value causes an unreliable flag to be set.
- Calculated Point 4: This point is the channel conversion Con- i stant used to convert intermediate range channel 36 amp-minutes into an EFPM value.- This C point will be updated by RE. as required using the Analog Management Function at the MCB. This point will not be RELIAS checked since use-of a substitute value causes an' unreliable flag to be set.
- Calculated Point 5: This point is the current core exposure as of the last program execution. This C peint will be updated every program execution.
- Calculated Point 6: This point is the sean nutr.ber corresponding to the previous progran execution. This C point will be updated every program execution. ;
4.3 Every time the' program is executed, it will perform the following items:
4.3.1 Obtain the analog values for intermediate range channels 35 and 36, and convert to units of aftps. If one.value is
- unreliable, the alternate value will be substituted for the unreliable value. If both values are unreliable, a value of zero amps wl!1 be assigned to beth channels.
4.3.2 The difference in scan number since last program execution will be calculated and converted te minutes.
4.3.3 The Step 4.3.1 values will be multiplied by the Step 4.3.2-delta time to obtain the change in amp-minutes for each intermediate range channel.
4.3.4 The change in amp-minutes from Step 4.3.3 will be adced to the applicable calculatec points te obtain new values of cumulative arrp-minutes.fer each intermediate range ctannel.
j Calculated points, 1 and 2 will be updatec with the new values.
4.3.5 The cumulative trrp-minutes from Step 4.3.a will be multiplied by the applicable channel conversion constant (calculated points 3 and 4 input into the program anc not RELIAB checked) to obtain an EFPM value for each intermediate range channel.
4.3.6 The current core burnup in EFPM will be obtained by averaging the two EFPM values of Step 4.3.5. The result will be usec to update calculated point 5.
4.3.7 Calculated point 6 will te udpated with the s'can number of the current program execution.
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5.0 DETAILS OF CALCULATIONS S.1 Conversion of MPCS intermediate range analog values to amps.
The analog units of MCAMPS. values for intermediate range.c.hannels 35 and 36 are in To obta must be multiplied by 10 jn the required urlits of amps, the MCAMPS 5.2 Calculating to minutes. the time since last program execution and converting Delta Current Scan number Time (Minutes)
= [ ( scan ) - ( of previous ) ) x ( (5 secondy) x g 1 minute number. program execution scan 60 seconds) )
Note that if.the delta scan time is less than zero (indicating a new day has started), a value of 17,280 will be addeo to the current scan titre in order to obtain the delta scan time.
5.3 Converting amp-minutes to EFPM using channel conversion constants.
The value of cumulative emp-minutes for intermediate range channel 35 and 36 is converted to ETPM using channel conversion constants. The initial value of the channel conversion constant is determined as ex-plained below; however, the values should De updated when a more accurate value has been cbtained from LPPT data. -
Revision 2. of the Precat,tions. Limitations and Setpoints for Nuclear Steam Supply Systems states that the initial setting for intermediate range channels is such that the full power current for 100% is 10-4 amps.
is: Therefore the initial value for the channel conversion constants 100% 1 EFFH
[ 10-4 amps 3 3 = 10
- 4 EFPM/ amp-minute (100%) (2 min)
During LPPT overlap data consisting of intermediate range currents and core delta temperatures (in units of % power) will become availatle.
This data should be eval.lsted for possible Channe' conversion constart update as described below:
5.3.1 Verify the data represents stable conditions (constant power level and constant RCS temperatures).
5.3.2 Average the % power values to obtain a core average % power.
1 1
hp To f ' l V .-
S.3.3 f Correct the-core average % power by multiplying by (51'F/57'F) where: j
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- 1) 51'F.is'the conservative value initially used by delta I
temperature instrumentation to convert delta temperature !
to % power.
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- 2) 57'F'is an estimate of actual full power delta temperature.
.(Note that an alternate value specified by the RE Department Supervisor can also be used).
5.3.4 Calculate new channel conversion constants as follows:
Calculated Point 3 "E % power (from Step 5.3.3) 3
~3
!R 35 indication (amps) (100%) (1 min)
Calculated 1 EFPM Point 4 "E % power (from Step 5.3.3) 3
- E 3 IR 36 indication (amps) (100%) (1 min) 5.3.5 If directed by the RE Department Supervisor, update calculated points 3 and 4 with the Step 5.3.4 values using the Analog Management Function at the NCB.
S.4 Calculation of current core exposure. -
Calculated point 5 for current core exposure in EFPM will be the aver-age of the EFPM calculated by both intermediate range channels as shewn below:
Calculated 5
C Calculated C C
=.C alculated3 Point 1 E Point 3 3 + b alculated Point 2 3 b alculate:-
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2
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