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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L7971999-10-20020 October 1999 Submits Results of Review of 990521 & 0709 Ltrs Which Provided Core Shroud Insp Results & Tie Rod Stabilizer Assemblies ML20217G1291999-10-15015 October 1999 Forwards Errata to Safety Evaluation for Amend 168 Issued to FOL DPR-63 on 990921.Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20217K2831999-10-14014 October 1999 Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001 ML20217H3211999-10-0808 October 1999 Forwards Changed Pages for Issue 5,rev 1 of Nine Mile Point Station Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p).Without Encls ML20212K8601999-10-0606 October 1999 Responds to Concern in 990405 Petition Re Residual Heat Removal Alternate Shutdown Cooling Modes of Operation at Nine Mile Point Nuclear Station,Unit 2 ML20216J9311999-09-30030 September 1999 Forwards Response to NRC 981119 Suppl RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20212J4651999-09-30030 September 1999 Informs of Completion of mid-cyle PPR of Nine Mile Point Nuclear Station on 990916.Determined That Problems in Areas of Human Performance & Work Control Required Continued Mgt Attention.Historical Listing of Plant Issues Encl ML18040A3701999-09-30030 September 1999 Provides Changes to Application for Amend Re Volumes 1-11 of 981016 Submittal & Discard & Insertion Instructions Re Integration of Proposed Changes,In Response to NRC RAIs ML20212K8641999-09-30030 September 1999 Informs That During 990927 Telcon Between J Williams & J Bobka,Arrangements Were Made for Administration of Exams at Plant During Wk of Feb 14,2000.Preliminary RO & SRO License Applications Should Be Submitted 30 Days Prior Exam ML20212J8831999-09-30030 September 1999 Informs That Util 980810 & 990630 Responses to GL 98-01 & Suppl 1, Y2K Readiness of Computer Sys at NPPs Acceptable. NRC Considers Subj GL to Be Closed for Plant ML20212E9801999-09-23023 September 1999 Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03 ML20216F7101999-09-17017 September 1999 Forwards Response to NRC 990806 RAI Re USI A-46,verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.Nrc Is Informed That Actions Required for Resolution of USI A-46 Have Been Completed ML20212B2821999-09-14014 September 1999 Responds to 990712 Correspondence Which Responded to NRC Ltr Re High Failure Rate for Generic Fundamentals Exam of 990407 for Nine Mile Point.Considers Corrective Actions Taken to Be Acceptable ML20212D8981999-09-14014 September 1999 Forwards ISI Summary Rept for Refueling Outage 15 & Flaw Indication Repts.Supporting Info Repts & Calculations, Encl ML20212B2581999-09-10010 September 1999 Requests That Name of Bm Bordenick Be Removed from Nine Mile Point,Units 1 & 2 Service List ML20211P5771999-09-10010 September 1999 Forwards Application for Amends to Licenses DPR-63 & NPF-69, to Transfer Licenses to Amergen Energy Co,Llc.Ts Pages & Proprietary Addendum,Included.Proprietary Encl Withheld ML20212A1341999-09-0707 September 1999 Forwards Summary Rept Secondary Containment Leakage Testing, Dtd June 1999 for Nine Mile Point,Unit 1,IAW TS 6.9.3.f ML20211K8141999-09-0101 September 1999 Forwards Reactor Containment Bldg Ilrt,Iaw Plant TS 6.9.3.e.Testing Confirmed That TS 3.3.3/4.3.3 & 6.16 Primary Containment Leakage Requirements Were Satisfactorily Met ML20211L9221999-09-0101 September 1999 Confirms That Licensee Will Retain Weld 32-WD-050 as IGSCC Category F Until Completion of Reinspection Program,In Response to NRC ML20211J6461999-08-30030 August 1999 Forwards Response to NRC 990625 RAI Re NMPC Responses to GL 92-01,rev 1,supplement 1, Reactor Vessel Structural Integrity ML20211K3001999-08-30030 August 1999 Forwards Semi-Annual Radioactive Effluent Release Rept for 990101-990630 & Revised ODCM, for Nine Mile Point,Unit 1. Format Used for Effluent Data Is Outlined in App B of Regulatory Guide 1.21,rev 1 ML20211K5031999-08-30030 August 1999 Responds to Ltr Addressed to Chairman Dicus, Expressing Concerns Involving 990624 Automatic Reactor Shutdown.Insp Findings & Conclusions Will Be Documented in Insp Repts 50-220/99-06 & 50-410/99-06 by mid-Sept 1999 ML20211H1921999-08-26026 August 1999 Forwards Application for Amend to License DPR-63,supporting Implementation of Noble Metal Chemical Addition by Raising Reactor Water Conductivity Limits in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b ML20211P5161999-08-26026 August 1999 Discusses Submitted on Behalf of Niagara Mohawk Power Corp Written Comments Addressing 10CFR2.206 Petition & Request That Ltr & Attached Response Be Withheld from Public Disclosure.Request Denied ML20211G4921999-08-26026 August 1999 Advises That Info Re Comments Addressing 10CFR2.206,dtd 990405 Will Be Withheld from Public Disclosure,In Response to ML20211D7731999-08-20020 August 1999 Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630 ML20211B9371999-08-18018 August 1999 Provides Addl Info Re Application of Method a at Nmp,Unit 1 as Described in Generic Implementation Procedure,Rev 2 (GIP-2),NRC Supplemental SER 2 & Documents Ref in GIP-2 Upon Which GIP-2 Is Based ML18040A3691999-08-16016 August 1999 Forwards Response to NRC 990510 RAI Pertaining to NMP Application for Amend Re Conversion of NMPNS Unit 2 Current TS to Its.Nrc Requested Info Re Several Sections,Including Section 3.6, Containment Sys. ML20210Q0031999-08-11011 August 1999 Informs That Due to Printing Malfunction,Some Copies of Author Ltr Dtd 990726,may Not Have Included Second Page of Encl 2 of Ltr ML20210R6661999-08-10010 August 1999 Confirms Conversation on 990721 Re Concerns of Syracuse Anti-Nuclear Effort on Status of 2.206 Petition (Filed 990524) & Upcoming NRC Performance Review Meeting on Nine Mile Point Units 1 & 2 ML20210R8101999-08-10010 August 1999 Forwards 1998 Annual Repts for NMP & co-tenants,including Rg&E,Energy East Corp/Nyse&G,Chg&E & Long Island Power Authority,Per 10CFR50.71(b) ML20210L5321999-08-0606 August 1999 Forwards List of Subjects Discussed During 990714 Telcon with Representatives of Niagara Mohawk Power Corp on Unit 1 Re USI A-46 Issue ML18041A0711999-07-30030 July 1999 Forwards Rev 1 to NMP2-ISI-006, Second Ten Year Interval ISI Program Plan for Nine Mile Point Nuclear Power Station Unit 2. Significant Changes from Rev 0 Listed ML20210J9351999-07-29029 July 1999 Informs That NMP Is Changing Completion Date for Replacement of Valves Having O Rings with Installed Life Greater than Eight Years.Replacement to Be Completed by 991031, During Hydrogen Monitoring Sys Maintenance Outage ML20216E1491999-07-26026 July 1999 Forwards Two Ltrs Received from NMPC Re Nine Mile Point Unit 1 Core Shroud Related to 10CFR2.206 ML20210E9151999-07-23023 July 1999 Discusses Evaluation of Recirculation Line Weld 32-WD-050 Indication Found During 1997 Refueling Outage (RFO14) at NMPNS Unit 1.Requests Notification of Decision to Retain Category F Classification Until Listed Conditions Satisfied ML20209G7911999-07-12012 July 1999 Provides Info Requested in NRC Re 990407 Generic Fundamentals Exam Failure Causes & Corrective Actions ML20209G3711999-07-12012 July 1999 Provides Final Root Cause Evaluation Re GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 1 ML20209G2001999-07-0909 July 1999 Forwards RFO-15 Core Shroud Insp Summary Rept, as Required by GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs & BWRVIP Rept BWR Core Shroud Insp & Flaw Evaluation Guideline (BWRVIP-01) ML20209F8561999-07-0606 July 1999 Forwards Rev 1 to Nmp,Unit 1 COLR for Cycle 14. Rept Is Being Submitted to Commission in Compliance with TS 6.9.1.f.4 ML20211K5071999-07-0606 July 1999 Submits Concerns Re 990624 Event Involving Automatic Reactor Shutdown.More than 5 Failures Were Identified in Event Number 35857 ML20196J6421999-06-30030 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Issued on 960110 ML20209B7071999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Facilities,As Contained in GL 98-01,Supp 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure,Encl ML20211P5271999-06-29029 June 1999 Submits Written Comments Addressing Petition Dtd 990405, Submitted by R Norway as It Relates to Expressed Concerns That Involve NMPC Activities.None of Relief Requested in Petition Warranted ML20196K6461999-06-29029 June 1999 Discusses Ofc of Investigations Rept 1-98-33 Re Unqualified Senior Reactor Operator Assuming Position of Assistant Station Shift Supervisor at Unit 1 on 980616.One Violation Being Cited as Described in Encl NOV ML20209B3501999-06-25025 June 1999 Submits Torus Shell & Coupon Corrosion Rate Determination for Nmpns,Unit 1.Torus Meets ASME Code Requirements,Iaw NRC 920825 & 940811 SERs ML20212J4431999-06-25025 June 1999 Discusses Responses to RAI Re GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20209B3531999-06-25025 June 1999 Informs NRC That All Actions Associated with NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs, Has Been Completed.Summary of Actions Completed & Other Pertinent Info Is Provided in Attachment ML20196F5721999-06-23023 June 1999 Forwards Rev 3 to NMP1-IST-003, Third Ten Year Inservice Testing Program Plan, Which Will Begin on 991226.Program Plan Conforms to Requirements of 1989 Edition of ASME Boiler & Pressure Vessel Code.Three Relief Requests,Encl ML20196G1461999-06-23023 June 1999 Informs That Actions Requested in GL 96-01, Testing of Safety-Related Logic Circuits Completed 1999-09-07
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217K2831999-10-14014 October 1999 Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001 ML20217H3211999-10-0808 October 1999 Forwards Changed Pages for Issue 5,rev 1 of Nine Mile Point Station Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p).Without Encls ML18040A3701999-09-30030 September 1999 Provides Changes to Application for Amend Re Volumes 1-11 of 981016 Submittal & Discard & Insertion Instructions Re Integration of Proposed Changes,In Response to NRC RAIs ML20216J9311999-09-30030 September 1999 Forwards Response to NRC 981119 Suppl RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20212E9801999-09-23023 September 1999 Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03 ML20216F7101999-09-17017 September 1999 Forwards Response to NRC 990806 RAI Re USI A-46,verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.Nrc Is Informed That Actions Required for Resolution of USI A-46 Have Been Completed ML20212D8981999-09-14014 September 1999 Forwards ISI Summary Rept for Refueling Outage 15 & Flaw Indication Repts.Supporting Info Repts & Calculations, Encl ML20212B2581999-09-10010 September 1999 Requests That Name of Bm Bordenick Be Removed from Nine Mile Point,Units 1 & 2 Service List ML20211P5771999-09-10010 September 1999 Forwards Application for Amends to Licenses DPR-63 & NPF-69, to Transfer Licenses to Amergen Energy Co,Llc.Ts Pages & Proprietary Addendum,Included.Proprietary Encl Withheld ML20212A1341999-09-0707 September 1999 Forwards Summary Rept Secondary Containment Leakage Testing, Dtd June 1999 for Nine Mile Point,Unit 1,IAW TS 6.9.3.f ML20211K8141999-09-0101 September 1999 Forwards Reactor Containment Bldg Ilrt,Iaw Plant TS 6.9.3.e.Testing Confirmed That TS 3.3.3/4.3.3 & 6.16 Primary Containment Leakage Requirements Were Satisfactorily Met ML20211L9221999-09-0101 September 1999 Confirms That Licensee Will Retain Weld 32-WD-050 as IGSCC Category F Until Completion of Reinspection Program,In Response to NRC ML20211K3001999-08-30030 August 1999 Forwards Semi-Annual Radioactive Effluent Release Rept for 990101-990630 & Revised ODCM, for Nine Mile Point,Unit 1. Format Used for Effluent Data Is Outlined in App B of Regulatory Guide 1.21,rev 1 ML20211J6461999-08-30030 August 1999 Forwards Response to NRC 990625 RAI Re NMPC Responses to GL 92-01,rev 1,supplement 1, Reactor Vessel Structural Integrity ML20211H1921999-08-26026 August 1999 Forwards Application for Amend to License DPR-63,supporting Implementation of Noble Metal Chemical Addition by Raising Reactor Water Conductivity Limits in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b ML20211D7731999-08-20020 August 1999 Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630 ML20211B9371999-08-18018 August 1999 Provides Addl Info Re Application of Method a at Nmp,Unit 1 as Described in Generic Implementation Procedure,Rev 2 (GIP-2),NRC Supplemental SER 2 & Documents Ref in GIP-2 Upon Which GIP-2 Is Based ML18040A3691999-08-16016 August 1999 Forwards Response to NRC 990510 RAI Pertaining to NMP Application for Amend Re Conversion of NMPNS Unit 2 Current TS to Its.Nrc Requested Info Re Several Sections,Including Section 3.6, Containment Sys. ML20210R6661999-08-10010 August 1999 Confirms Conversation on 990721 Re Concerns of Syracuse Anti-Nuclear Effort on Status of 2.206 Petition (Filed 990524) & Upcoming NRC Performance Review Meeting on Nine Mile Point Units 1 & 2 ML20210R8101999-08-10010 August 1999 Forwards 1998 Annual Repts for NMP & co-tenants,including Rg&E,Energy East Corp/Nyse&G,Chg&E & Long Island Power Authority,Per 10CFR50.71(b) ML18041A0711999-07-30030 July 1999 Forwards Rev 1 to NMP2-ISI-006, Second Ten Year Interval ISI Program Plan for Nine Mile Point Nuclear Power Station Unit 2. Significant Changes from Rev 0 Listed ML20210J9351999-07-29029 July 1999 Informs That NMP Is Changing Completion Date for Replacement of Valves Having O Rings with Installed Life Greater than Eight Years.Replacement to Be Completed by 991031, During Hydrogen Monitoring Sys Maintenance Outage ML20209G3711999-07-12012 July 1999 Provides Final Root Cause Evaluation Re GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 1 ML20209G7911999-07-12012 July 1999 Provides Info Requested in NRC Re 990407 Generic Fundamentals Exam Failure Causes & Corrective Actions ML20209G2001999-07-0909 July 1999 Forwards RFO-15 Core Shroud Insp Summary Rept, as Required by GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs & BWRVIP Rept BWR Core Shroud Insp & Flaw Evaluation Guideline (BWRVIP-01) ML20209F8561999-07-0606 July 1999 Forwards Rev 1 to Nmp,Unit 1 COLR for Cycle 14. Rept Is Being Submitted to Commission in Compliance with TS 6.9.1.f.4 ML20211K5071999-07-0606 July 1999 Submits Concerns Re 990624 Event Involving Automatic Reactor Shutdown.More than 5 Failures Were Identified in Event Number 35857 ML20209B7071999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Facilities,As Contained in GL 98-01,Supp 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure,Encl ML20211P5271999-06-29029 June 1999 Submits Written Comments Addressing Petition Dtd 990405, Submitted by R Norway as It Relates to Expressed Concerns That Involve NMPC Activities.None of Relief Requested in Petition Warranted ML20209B3501999-06-25025 June 1999 Submits Torus Shell & Coupon Corrosion Rate Determination for Nmpns,Unit 1.Torus Meets ASME Code Requirements,Iaw NRC 920825 & 940811 SERs ML20209B3531999-06-25025 June 1999 Informs NRC That All Actions Associated with NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs, Has Been Completed.Summary of Actions Completed & Other Pertinent Info Is Provided in Attachment ML20196G1461999-06-23023 June 1999 Informs That Actions Requested in GL 96-01, Testing of Safety-Related Logic Circuits Completed ML20196F5721999-06-23023 June 1999 Forwards Rev 3 to NMP1-IST-003, Third Ten Year Inservice Testing Program Plan, Which Will Begin on 991226.Program Plan Conforms to Requirements of 1989 Edition of ASME Boiler & Pressure Vessel Code.Three Relief Requests,Encl ML20209B2951999-06-22022 June 1999 Informs That Training Re Pressure Relief Panels Was Completed for Remainder of Target Population on 990226 ML20196E9231999-06-21021 June 1999 Forwards Response to NRC 990510 RAI Re NMP 981116 Application Proposing Changes to TSs to Provide Reasonable Assurance That Coupled neutronic/thermal-hydraulic Instabilities Were Detected & Suppressed in NMPN-1 Reactor ML18040A3651999-06-0707 June 1999 Forwards for Filing Original Application of Central Hudson & Gas & Electric Corp Seeking Extension of Expiration Date of Order,Dtd 980719,issued by Commission ML18040A3661999-06-0404 June 1999 Informs That Entire Attachment to Ltr NMP2L 1862 Dtd 990421, Should Be Replaced with Entire Attachment Being Sent with Present Ltr ML20195C9751999-06-0101 June 1999 Informs That Weld 32-WD-050 Will Be Reclassified Back to GL 88-01 Category a Weld & ASME Code Section XI Insps Will Be Conducted in Next Three Insp Periods ML20195C9601999-05-28028 May 1999 Provides Final Extent of Condition Evaluation Re Failed Cap Screw Beyond Upper Spring.Nmpc Continues to Conclude as Stated in That No Addl Mods Are Needed Other than Those Indicated in Ltr ML20207F1811999-05-24024 May 1999 Petitions NRC to Suspend Operating License of NMP for NMPNS Unit 1 Until Such Time as NMPC Releases Most Recent Insp Data on Plant Core Shroud & Adequate Public Review of Plant Safety Accomplished Because of Listed Concerns ML20195B1861999-05-21021 May 1999 Requests Staff Approval of Proposed Mod to Each of Four Tie Rods Per 10CFR50.55a(a)(3)(i).Summary of Tie Rod Insp Findings,Summary of Root Cause Evaluation of Failure of Cap Screw,Calculation B-13-01739-23 & Summary of Se,Encl ML20207D1541999-05-21021 May 1999 Forwards Issue 5,rev 0 of Physical Security & Safeguards Contingency Plan for Nmpns.Summary of Changes Included to Facilitate Review.Encls Withheld ML20207D5331999-05-21021 May 1999 Forwards Issue 3,Rev 1 of NMP Nuclear Security Training & Qualification Plan.Summary of Changes Is Included with Plan to Provide Basis for Individual Changes & to Facilitate NRC Review.Plan Withheld Per 10CFR2.790 ML20206S2621999-05-16016 May 1999 Expresses Concerns About Safety of Nmp,Unit 1 Nuclear Reactor.Nrc Should Conduct Insp of Reactor Including Area Besides Core Shroud Welds & Publicly Disclose Results at Least Wk Before Restart Date ML20195D5911999-05-13013 May 1999 Submits Final Copy of Open Ltr to Central Ny,With Proposals Re Nine Mile One Core Shroud Insp During Refueling Outage Which Began on 990411 ML20206P1981999-05-11011 May 1999 Forwards Response to NRC RAI Re NMP Previous Responses to GL 96-05, Periodic Verification of Design-Basis of SR Movs, for NMP Units 1 & 2 ML20206R6941999-05-10010 May 1999 Responds to 990413 & 0430 Ltrs Re Apparent Violation Noted in Investigation Rept 1-98-033.Util Agrees with Violation, But Disagrees with Characterization That Violation Was Willful or Deliberate ML20206N0291999-05-0707 May 1999 Forwards Rev 39 to NMP Site Emergency Plan & Revised Epips,Including Rev 1 to EPMP-EPP-03,rev 5 to EPIP-EPP-25 & Rev 5 to EPIP-EPP-28 ML20206G8121999-04-30030 April 1999 Forwards Comments on Draft Reg Guide DG-1083, Content of UFSAR IAW 10CFR50.71(e), Dtd Mar 1999.Util Generally Supports DG-1083 ML20206F7731999-04-22022 April 1999 Forwards Renewal Application for SPDES Permit Number NY-000-1015 for Nmpns,Units 1 & 2 1999-09-07
[Table view] Category:UTILITY TO NRC
MONTHYEARML17056A9771990-08-30030 August 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Revs 4 & 5 to Odcm. ML18038A3231990-08-30030 August 1990 Forwards Semiannual Radioactive Effluent Release Rept Jan- June 1990 & Revs 6-8 to Odcm. Radioactive Effluent Release Rept Includes Summary of Liquid,Gaseous & Solid Effluents & Justification for Revs to ODCM ML18038A3221990-08-24024 August 1990 Forwards NRC Form 474, Simulation Facility Certification & Supporting Documentation ML18038A3201990-08-21021 August 1990 Discusses Status of Completion of Generic Safety Issue 75, Item 2.2.2 Re Vendor Interface for safety-related Components ML18038A3251990-08-20020 August 1990 Forwards Rev 3 to Nine Mile Point Requalification Program Action Plan, Certifying That All short-term Corrective Actions Completed ML20058Q1151990-08-15015 August 1990 Forwards Response to Regulatory Effectiveness Review on 900604-08.Response Withheld (Ref 10CFR73.21) ML20055G5261990-07-18018 July 1990 Forwards Decommissioning Rept Indicating Reasonable Assurance That Funds Available to Decommission Facility. Financial Assurance of Cotenants Also Encl ML17058A5841990-06-27027 June 1990 Forwards Rev 8 to Updated FSAR for Nine Mile Point Unit 1. Changes Re Findings Noted in Insp Rept 50-220/88-201 Included in Rev.Rev Does Not Reflect Changes Re Reg Guide 1.97,Rev 2 ML18038A3051990-06-26026 June 1990 Responds to Generic Ltr 90-04 Re Status of Implementation of Generic Safety Issue Requirements.Tabulated Info Re Generic Safety Issue Title,Applicability,Status & Remarks Encl ML20042E3741990-04-11011 April 1990 Lists Info Re Unit Containment Vent & Purge Valves,Per NRC 900315 Request ML20012F6131990-03-30030 March 1990 Forwards Changes to Security Training & Qualification Plan. Plan Rewritten & Revised to Incorporate performance-oriented Training Program.Plan Withheld (Ref 10CFR2.790(d)) ML17056A6721990-03-0202 March 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 & Rev 3 to Administrative Procedure AP-3.7.1, Unit 2 Radwaste Process Control Program. ML18038A7071990-02-0505 February 1990 Forwards Rev 5 to NMPC-QATR-1, QA Topical Rept for Nine Mile Point Nuclear Station Operations. ML18038A7061990-01-10010 January 1990 Forwards Rev 21 to Emergency Plan,Revised Emergency Action Procedures,Including Rev 7 to S-EAP-1,Rev 11 to S-EAP-2,Rev 8 to S-EAP-3 & Epips,Including Rev 13 to S-EPP-4 & Rev 13 to S-EPP-20 ML20042D1981989-12-28028 December 1989 Informs of Delay in Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance, Until BWR Owner Group Generic Program Completed & NRC Appraisal of Program Reviewed by Util ML18038A7021989-11-28028 November 1989 Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Usi A-5,A-6 & A-7 Inapplicable to Facility ML18038A7711989-11-28028 November 1989 Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Requirements for NUREG-0612 Re Control of Heavy Loads Near Spent Fuel Completed.Usi A-40 Re Seismic Design Criteria Being Resolved as Part of USI A-46 ML18038A7701989-10-25025 October 1989 Forwards Rev 1 to Updated SAR for Nine Mile Point Unit 2. All Errata Items Identified in Attachment 1 to Previous Updated SAR Transmittal Ltr of 890428 Resolved.Programs to Resolve Setpoint Issues Will Be Established by 891130 ML18038A7611989-09-29029 September 1989 Forwards Addl Info Re Simulator Certification for Facility, Per 890803 Request.Schedule Extension Verbally Granted Until 890930 ML18038A6641989-09-0808 September 1989 Forwards Restart Readiness Rept. Rept Submitted in Fulfillment of Util Third Action Required by Confirmatory Action Ltr CAL-88-17,dtd 880724 ML17056A2701989-08-30030 August 1989 Forwards Nine Mile Point Nuclear Station - Unit 2 Semiannual Radioactive Effluent Release Rept Jan-June 1989 & Rev 1 to Administrative Procedure AP-3.7.1 Process Control Program. ML20245E8451989-08-0707 August 1989 Forwards Rev 6 to Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21 & 10CFR2.790(d)) ML20247M2771989-07-25025 July 1989 Forwards Issue 2,Rev 0 to Physical Security Plan.Specific Changes Set Forth in Attachment A.Supporting Info Set Forth in Attachment B.Master Acronym & Abbreviation List Also Encl.Encls Withheld (Ref 10CFR73.21) ML20246N9041989-07-13013 July 1989 Forwards Vital Area Evaluation for Plant Screenhouse.Encl Withheld (Ref 10CFR73.21(b)) ML18038A6611989-07-11011 July 1989 Provides Response to Generic Ltr 89-06, Task Action Plan Item I.D.2 - Spds. Certification Stating Plant Unit 1 SPDS Sys Meets Requirements of NUREG-0737,Suppl 1 & Plant Unit 2 SPDS Sys Will Be Modified to Meet NUREG-0737,Suppl 1 Encl ML18038A6591989-06-23023 June 1989 Forwards Util Response to 890522 Salp.Util Agrees W/Need to Improve Surveillance Testing Data & Upgrading Design Basis for Core Spray & HPCI Sys ML20244E3631989-06-15015 June 1989 Forwards Revised Application for Amend to License DPR-63, Incorporating Request to Limit Reactor Power Level at Which Blocking Valve in Feedwater May Be Closed ML18038A4731989-05-31031 May 1989 Forwards Emergency Preparedness Exercise/Drill Scenario 12 1989 Annual Exercise, Vols 1 & 2 ML18038A4581989-04-28028 April 1989 Forwards Rev 0 to Updated SAR for Nine Mile Point Unit 2. Emergency Plan,Formerly Included in Fsar,Not Included in Updated Sar.Portions of Util Responses to NRC FSAR Questions Incorporated Into Body of Initial Updated SAR ML20246Q0071989-04-28028 April 1989 Forwards Proprietary Section 6A of Updated FSAR for Nine Mile Point Unit 2.Section 6A Withheld (Ref 10CFR2.790) ML20246B5451989-04-28028 April 1989 Advises That Util Will Submit Rev to Restart Action Plan After Receipt of Repts from NRC Special Team Insp & INPO Reassessment of Facility ML18038A4561989-03-23023 March 1989 Forwards Addl Info Supporting Application to Use Alternative to 10CFR50.55a Requirements.W/Two Oversize Drawings ML18038A4551989-03-21021 March 1989 Provides Util Plans for Future Exam & Evaluation of Four Feedwater Nozzles Per NUREG-0619.Indications Conservatively Evaluated as Cracks Not Scratch Marks.During 1993 Refueling Outage,Sparger from Nozzle a Will Be Removed 05000410/LER-1989-003, Forwards Corrected Copy of LER 89-003-00 Submitted on 890320.Typo Identified on Page 5 of 7 Corrected1989-03-21021 March 1989 Forwards Corrected Copy of LER 89-003-00 Submitted on 890320.Typo Identified on Page 5 of 7 Corrected ML18038A4521989-03-0202 March 1989 Forwards Responses to NRC Questions Re Licensee Restart Action Plan & Nuclear Improvement Program.Replacement Pages for Action Plan Encl ML20245J5521989-03-0202 March 1989 Forwards Rept of Physical Security Event,Reported Via Emergency Notification Sys on 890203 ML18038A4511989-02-22022 February 1989 Forwards Rev 4 to NMPC-QATR-1, QA Program Topical Rept for Nine Mile Point Nuclear Station Operations. Revs Include Corporate Reporting & Responsibility Changes as Well as Descriptions for Organizations Not Previously Identified ML18038A4501989-02-14014 February 1989 Forwards Rev 1 to TR-6801-2, Mark I Torus Shell & Vent Sys Thickness Requirements Nine Mile Point Unit 1 Nuclear Station. Requests Approval to Use Certified Matl Test Repts for Most of Torus Matls ML18038A4341989-01-18018 January 1989 Forwards Revised,Second 10-yr Interval Inservice Testing Program Plan for Plant & Supporting Documentation,Per 881220 Commitment.Interim Approval of Program as Submitted to Spent Fuel Loading Scheduled for Apr 1989 Requested ML18038A4201988-09-29029 September 1988 Advises That No Unresolved Safety Issues Re Flow Fluctuations & Neutron Flux Noise Exist,Per NRC 880527 Ltr Requesting Summary of Plans to Mitigate Oscillations in APRM Signals & Total Core Flow ML20154C4221988-09-0909 September 1988 Informs That Contracted Vendor to Present Courses Will Not Be Able to Commence Training Until Later in Month of Oct or Early Nov 1988.Schedule Revised to Have Instrumentation & Control Initial Training Implemented by Nov 1988 ML20154B4301988-09-0808 September 1988 Forwards Security & Safeguards Contingency Plan.Definition of Security Force Member Discussed.Plan Withheld ML17055E2471988-08-30030 August 1988 Forwards Semiannual Radioactive Effluent Release Rept, Jan-Jun 1988, & Revs 4 & 6 to Offsite Dose Calculation Manual. ML18038A4121988-07-28028 July 1988 Forwards Info Re Implementation of NUREG-0131,Rev 2, Technical Rept on Matl Selection & Process Guidelines for BWR Coolant Pressure Boundary Piping. ML18038A4101988-07-28028 July 1988 Forwards Comments,Clarifications & Agreements Re Implementation Re 880506 SER Concerning 10CFR50,App J.Info Submitted Per Commitment Resulting from 880609 Meeting W/ NRC.W/15 Oversize Drawings ML18038A4111988-07-28028 July 1988 Forwards Licensee Response to Generic Ltr 88-01 Re Austenitic Stainless Steel Piping at Facility.Application for Amend to Incorporate Requirements of Generic Ltr Will Be Submitted Later ML20151A2971988-07-15015 July 1988 Forwards Changes to Physical Security Plan.Supporting Info Also Encl.Encls Withheld (Ref 10CFR73.21) ML20151A2751988-07-15015 July 1988 Forwards Changes to Security Training & Qualification Plan. Changes Withheld (Ref 10CFR2.790) ML18038A4081988-07-0707 July 1988 Submits Listed Changes to Util 880609 Comments on SALP, Including Advisal That Review of Nonradiological Chemistry Program Revised to More Accurately Describe How Review Performed ML18038A4061988-07-0606 July 1988 Responds to Request for Addl Info on ATWS Review Re Alternate Rod Injection & Recirculation Pump Trip Sys.W/ Seven Oversize Drawings 1990-08-30
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Text
EW 1 f REGULA'i RY INFORt~fl ION DISTRIBUTION SYSTEN (R IDS)
ACCESSION NBR: 8604220122 DOC. DATE: 86/04/15 NOTARIZED: YES DOCKET FACIL: 50-410 Nine Nile Point Nuclear Station> Unit 2> Niagara Noha 05000410 AUTH. NANE AUTHOR AFFILlATION NANQAN> C. V. Niagara Nohamk Power Corp.
REC lP. NANE RECIPIENT AFFILIATION ADENSAN> E. Q. BNR Prospect Directorate 3 P+f Ptv'o6
'UB JECT: Forulard s results o+ testing oF Kaman i solation devi ces utilized at plant> in response to Guesti ons 6421. 13 4 8420. Ol (ConFirmatorg item 20). Testing should resolve concerns re SPDS. Affidavit encl. Encl s withheld (ref 10CFR2. 790).
DISTRIBUTION CODE: PB01D COPlES RECEIVED: LTR ENCL SIZE:
TITLE: Proprietary Review Distribution Pre OL NOTES:
RECIPIENT COP IES RECIPIENT COP lES ID CODE/NANE ID CODE/NAYiE LTTR ENCL BNR PD3 LA HAUQHEY, N 01 1,0 LTTR ENCL BWR PD3 F'D 1 0 INTERNAL: AC 06 10 10 ELD/HDS3 0 EQ F RN/DDANI/NIB 02 1
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d RQN1 EXTERNAL: 24X 1 0 LPDR NRC PDR 1 0 TOTAL NUi'ABER OF COPIES REQUIRED: LTTR 20 ENCL 13
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NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST. SYRACUSE. N.Y. 13202/TELEPHONE (315) 474.1511 Apri 1 15, 1986 (NMP2L 0688)
Ms. Elinor G. Adensam, Director BWR Project Directorate No. 3 U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Washington, DC 20555
Dear Ms. Adensam:
Re: Nine Mile Point Unit 2 Docket No. 50-410 Enclosed are the results of the testing of the Kaman isolation devices utilized at Nine Mile Point Unit 2. This testing was performed in response to Questions Q421.13 and Q420.01 (Confirmatory Item 20).
This testing should also resolve the concerns stated in your letter dated January 29, 1986 (from yourself to B. G. Hooten) in regard to the isolation devices utilized in the Nine Mile Point Unit 2 Safety Parameter Display System (Open Item 18).
The information contained in the enclosed test report contains confidential commercial information of Niagara Mohawk Power Corporation. In accordance with Section 2.790 of the Commission's regulations, Niagara Mohawk Power Corporation hereby makes application for the withholding report from public disclosure. An affidavit in support of this application of this test for withholding is attached.
Very truly yours, C. V. Manga Senior Vice President TRL:ja 1486G Enclosure xc: R. A. Gramm, NRC Resident Inspector Project File (2) 4.f 5 eb0@00gg0 g22 eb0422o0CV. 050oo9R 98 A9 P
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4 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of )
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Niagara Mohawk Power Corporation ) Docket No. 50-410
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(Nine Mile Point Unit 2) )
AFFIDAVIT I, C. V. Mangan, being duly sworn depose and state as follows:
- l. I am Senior Vice President of Niagara Mohawk Power Corporation and am authorized on the part of said Corporation to make application for withholding from public disclosure of the document discussed in this affidavit.
- 2. This affidavit is made in support of an application for withholding from public disclosure the report entitled "Maximum Credible Fault Test Report for Kaman Instrumentation KESIM 8 KEAIM Isolation Devices" which contains information considered by Niagara Mohawk Power Corporation to be confidential commercial information consisting of analyses/results which should be withheld from public disclosure.
- 3. In support of its averment that the above-mentioned information is confidential commercial information exempt from public disclosure under the provision of Section 2.790 of the Commission's regulations, Niagara Mohawk provides the following reasons:
- a. This information is held and will continue to be held in confidence by its owner, Niagara Mohawk Power Corporation.
- b. This information is of the type customarily held in confidence by the owner, Niagara Mohawk Power Corporation. Release of this information would cause financial harm to Niagara Mohawk Power Corporation.
- c. This information is being transmitted to the Commission in confidence.
- d. This information is not available in any public sources.
4 Page 2 The information in this report was obtained through substantial expense by Niagara Mohawk Power Corporation incurred in the performance of an extensive testing program of the isolation devices, The -accumulated costs of the testing program include the purchase of spare isolation devices, spare control room indication components and electronic testing equipment. Additionally, a large number of man-hours (engineers, technicians, clerical and consultants) and the resultant overhead costs were expended in the preparation of the test, performance of the test and the analysis of the results. The information which resulted from this test is a valuable commercial commodity of interest to other commercial entities. Public release of this information would place Niagara Mohawk in a financially disadvantageous position with regard to the resale of this information and would prevent Niagara Mohawk from recouping a portion of these substantial expenses.
Subscribed and swor to be ore me, a Notary Public in for. the State of New York and County of , this L5~ day of 1986.
ot ry Public in and for County, New York My Com aQS>.mII.:
Notary Public ln tho Stato of New YorR Qualified In Onondaga County No. 478455I My Commission Expires March 30'9@~
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TABLE'OF CONTENTS SECTION TITLE PAGE 1.0. Purpose and Description 1 2.0 Applicable Documents 1 3.0 Record of Test Personnel 1 4.0 Test Equipment 2 5.0 Deviations from Test Erocedure 3 6.0 Discussion on Test Approach 8 7.0 Conclusion 10 8.0 Test Description 10 9.0 Qualification 10 10.0 Clarification ll Attachment 1 Test Equipment Calibration List 2 Kaman Equipment List (used in test) 3 SIMs Test Photographs 4 AlMs Test Photographs 5 Test Procedure 12177-SK-955, Rev. 2 8604220122
1.0 PURPOSE AND DESCRIPTION The pur'pose of this .test was to ensure that the two isolators supplied by Kaman for use with the Digital Radiation Monitoring System (DRMS) for Nine Mile Point Nuclear Station Unit 2 provides the electrical isolation between Class lE and non 1E circuits following the maximum credible faul't (MCF).
The Kaman supplied Analog Isolation Modul'es (KEAIM'r AIM) and the Safety Isolation Modules (KESIM or SIM) are to be used as a portion of the Safety Parameter Display System (SPDS) for providing DRMS information to the operator. As noted at the USNRC SPDS Audit at NMP2 on July 17 and 18, 1985, a detailed assessment by the NRC on type test data for the Kaman isolators wqs requi'red and reflected in FSAR 'Que's tion F420.'01.
The MCF test was performed to, demonstrate that the AIM's and SIM's qualify as acceptable isolation devices as defined in the require-ments of IEEE 384, 1977, IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits.
2.0 APPLICABLE DOCUMENTS
- 1. CPN Z855, Rev. 2 Maximum'redible Fault Test Procedur'e
- 2. IEEE 384, 1977 Criteria for Separation of Class 1E Equipment and Circuits
- 3. IEEE 323, 1974 Qualifying Class 1E Equipment for Nuclear Generating Stations
- 4. Regulatory Guide Physical Independence of Electrical Systems
. 5. 10CFR50 Appendix B, Title 10, Code of Federal Regulations, Part 50, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Processing Plants", USNRC 10CFR21 Title 10, Code of Federal Regulations, Part 21, "Reporting of Defects and Non Compliance.
3.0 RECORD OF TEST PERSONNEL
- 1. SIM~s Test 3/24/86 A. C. Dunham NMPC I&C Technician B. D. Burdick NMPC I&C Technician C. J. Connor I&C Technician D.'. Ganoung NMPC NMPC I&C Technician E. A. Sassani NMPC Engineering F'. F., Jensen Joint Startup' Test Group'WEC G. B'. Newman Engineering H. R. Connors SWEC Engineering (Test Coordinator)
- 2. AIM's Test A. C. Dunham NMPC I&C Technician B. D. Burdick NMPC I&C Technician C. J. Connor NMPC I&C Technician D. S. Ganoung NMPC I&C Technician E. A. Sassani NMPC Engineering F. R. Traber Joint Startup & Test Group G. L. Kassakatis Joint Startup & Test Group H. F. Jensen Joint Startup & Test Group" I. Connors SWEC Engineering (Test Coordinator) 4.0 TEST EQUIPMENT All measurement and test equipment (M&TE) used in performing these tests were calibrated as applicable in accordance with Niagara Mohawk Power Corporation's Instrum'entation & Control QA procedur'es for NMP2. All M&TE is traceable to NBS.
Additionally, traceability to this test is available on the Record of Test card located on the M&TE.
2
5.0 DEVIATIONS FROM TEST PROCEDURE Due to availability of test equipment, Figure 2 of the Test Procedure was modified to reflect that as shown in Figure 2A which is functionally equal to the earlier version.
PBl was replaced with Sl and the scope was set up to monitor full current fault pulse and scaled down voltage reading (120VAC = 24VAC) thru use of a transformer.
- 2. Test equipment used to perform the tpst was as shown in Attachments 1 & 2 and was equal to that as outlined in the test procedure.
Referring to Sections 5.1.1.1 of SIM's and AIM's test respectively.
The pass/fail criteria of the ICU remaining constant +1 least significant digit was determined prior to the start of the test to be too severe a criteria. A digital pulse gen-erator was used to simulate a gamma type detector for both tests and its output was held constant. The display on the ICU which was being updated at approximately 1 second intervals was observed to fluctuate with the input to the microcomputer held constant at various time periods to a maximum of plus 5 least significant digits and minus 0 digits before decaying to the normal test setpoint. There was no external interference such as toggling test equipment, turning on motors or lights which could have caused those fluctuations.
The acceptance criteria of +5/-0 least significant digits was adopted as reasonable.
JUSTIFICATION:.
A review of Kaman Instrumentation's Microcomputer Software Design Description, Functional Test for Multichannel Area Monitor (MCAM) with Ion Chamber Detector (KNP 18-72), and Functional Test Procedure MCAM with GM tube detector (KNP 18-86) indicates that the units displayed are engineering units, the result of calculations inherent to Kaman's software, not in counts per minutes (CPM).
A discussion of detector signal acquisition and radiation signal filtering method is as follows:
Every radiation monitor contains one or more detectors for measuring the level of radiation at the location of the monitor, or in the process of effluent stream being sampled. The type
of radiation detector used depends on the media being monitored, but all detectors measur'e the radiation from decay processes in terms of the number of events occurring in a certain time interval.
These events,"coun'ts from GM or scintillation detectors or current levels in the case of ion chamber detectors, are processed through various signal conditioning and interface electronics, and are presented to an event counter at the microcomputer. Each GM or scintillation detector, or channel, has a separate dedicated counter at the microcomputer that is continuo'usly running, counting pulses from the detector. The coun'ters used in the KEM-A and Kem-P microcomputers have a capacity. of more than 65 thous'and counts (16 bits) before they "roll over". These counters are read by the logic of the microcomputer, without interrup'ting the counting process approximately every 20 to 100 milliseconds. The maximum count rate for the counters is therefore more than 20 million counts per minut'e. This is beyond the capability of the detectors and other interface electronics, however, and the practical maximum'oun't rate is on the order of one to ten million counts per minute, depending on the detector type.
For ion chamber detectors, the low-level current signals of the detectors are amplified and conditioned, and the level of the sample activity is determined by passing this signal through an analog to digital converter and other scaling and auto-ranging electronics.
Since radioactive decay is a statistical process, the number of counts measured by the detectors per unit time varies. The radiation rates calculated by the microcomputer are averages over various'ime periods. In general, radioactive decays follow a "normal" statistical distribut'ion with time, so that at very low coun't rates (typical backgroun'd levels, for example) the average radiation rate measured over a short time interval may vary considerably. At high levels of activity, the variation (measured as a fraction of the long term average rate) is much smaller. In order to prevent large,oscillations in the displ'ay of current rates at low activity levels, where the statistical flue'tuations are large, and yet to give rapid and accurate readings at high radiation rates, Kaman us'es a continuously variable time constant filtering technique in the radiation rate calculations performed by the microcomput'er, as described in the next section.
RADIATION SIGNAL FILTERING METHOD The counts (or current'or ion chamber detectors) accumulated within one second by the microcomputer are converted to engineering
units of activity concentration (microcuries per cubic centi-meter, for example), displayed in digital form at both local and remote panels, and checked against the radiation alarm setpoints to determine if an alarm condition exists.
The "raw" or gross counts in a one-second period (Gs) are con-verted to gross counts.per minut'e (Cgm) by multiplying by 60.
This value's then converted to a gross activity concentration in engineering units by multiplying by the detector "linear conversion factor", e, which represents the activity concen-tration per cpm (or per ampere of current for ion chambers) as determined by detector calibration experiments using known source strengths. If. the detector's efficiency factor is not entirely linear over its range of operation (due to "dead time" errors in GM tubes, for example), a second multiplicative factor is then applied to the count rate. This unitless "non-linear correction factor", Cf, is determined by a table lookup procedure. Using this method, any non-linear response charac-teristics of the detectors are easily accounted for by the software of the microcomputer. the calculations performed in the software of the microcomputer to obtain the effective gross activity concentration, Ag, can be summarixed as:
Cgm = Cgs
Ag Csm
- Cf A smoothing or filtering technique is then applied to the gross activity 'concentration. This technique is the digital equiva-lent of a simple single pole RC filter.
First, a time constant is comput'ed based on the current count rate, Ag. this time constant is obtained by an interpolation procedure us'ing graphical data and takes on values from one second at count rates above 3000 cpm, to 26 seconds (13 seconds for area detectors) at count rates less than 120 'counts per minute (less than 230 cpm for area detectors). Within the range from 120 'to 3000 cpm, the time constant continuously decreases with the detector coun't rate. The time constant foun'd in this manner, Tc, is us'ed to determine the filtered activity con-centration by the following equa'tion:
RFc = RFp + (RUc RFp) * (1 exp[-Ts/Tc])
where:
RFc is the resultant filtered activity concentration, in engineering units such as microcuries per cubic centimeter for the current one second time interval, RF, is the filtered activity concentration in engin-eering units for the previous'ne second time interval; RUc is the gross unfiltered activity for the current one second time interval ( ~ Ag in this discussion);
Ts is the sampling time interval (always 1 second);
Tc is the time constant (in seconds) for the coun't rate of the current one second time interval.
The effect of this filtering technique is to give a "smoothing" effect at low coun't rates where large statistical variations are expected, but to give a more rapid response to changes in the radiation level at high count rates.
At a count rate of 120 cpm (or below), for example, the filtered radiation rate for a process channel is equal to .96 of the previous filtered rate plus only .04 of the new unfiltered rate. Above 3000 cpm, the filtered rate is equal to .37 of the previous filtered rate plus'63 of the current unfiltered rate.
This filtering method has proven to be.a reliable means of processing the raw count rates and preventing unwanted "nuisance" alarms from occurring at'ow count rates, while allowing fast response to real increases in the rates. The method has been found to be preferable to other means such as testing the number of times the raw count rate exceeds some preset value.
The net activity concentration, An, is then determined by sub'tracting the background activity concentration, Ab, from the filtered gross activity concentration, RFc. That is:
An = RFc = - Ab This backgroun'd activity may be specified to the microcomputer via the DCS or the control panel (KELIC or KERIC). In some units where aut'omatic backgroun'd determination is done by the microcomputer, the backgroun'd activity is calculated based on the activity during a purge operation. For area channels, which measur'e only backgioun'd activity, this subtraction is not done.
It is this net filtered radiation rate, An, that is then used to update the local and remote radiation rate displays. This filtered rate, or activity concentration, is tested against alarm setpoints to determine if an alarm condition exists.
The pulse generator used on these tests was set to yield below 200 HZ.
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6.0 DISCUSSION ON TEST APPROACH 81 The purpose of MCF testin g is to assure that in the event of non lE MCF conditions, the fault is not propagated through to the Class lE side. Although the MCF condition of 120VAC at 30amps is very unlikely due to both the structural design, wire routing features, and the limiting impedance os the devices,,the test was set up to accomo-date such.
Revision 2 to MCF Test Procedure 12177-SK-955 was issued on 3/19/86, prior to the start of the test. This revision specifically deleted the testing of the "From Transmit" port on the SIM's and of the two voltage output's (0-10 volt and 0-5 volts) on the AIM's as demon-stration on a single isolator circuit represents adequate testing while performing a second or third destructive type test on an, isolator damaged as a result of initial MCF could not be conclusive. Justifi-cation for selection of the circuit which was to be tested on the SIM's is covered in Section 6.1 while circuit selection for the AIM's is addressed in Section 6.2.
6.1 SIMs The approach for testing. the isolator was to ensure that MCF for the device was achieved. Only those faults which could occur outside of the SIM's were considered as the device is a sealed box and all wiring interface is through two 50 pin Amphenol connectors.
A review of the Kaman schematic drawing for the SIMs isolator board Pr430202 indicated two possible paths for MCF testing:
and send channels; each containing a Hewlett Packard 'eceive HCPL-2630 optocoupler as the isolation device.
t From the non 1E side of the device looking towards the lE side, the final'non 1E item is the LED on the optocoupler for the send channels. For the receive channels, it diode with an amplifier circuit on the optocoupler.
is the photo-As we wanted to verify the electrical isolation property of the SIMs, only the receive channel was selected for testing because the optocoupler in both the. send and receive channels is iden-tical. Also, for the receive channel, the amplifier circuit output, considered as an internal power source, coupled with the maximum credible fault~ provides a greater current drawing capability, thus creating heat and possible arcin'g on the board.
Further justification for not testing the send channel where signals originate on the non lE side is that the circuitry is
~ t designed to turn the LED in the optocoupler on and off in a current sink mode, acting as a switch rather than as a power source. With a regulated 5 volt power supply constantly
available to drive the LED, the Advanced Micro Devices AM26LS32DC Quad Differential Line Receiver (QDLR) grounds or opens pin 2 of the HCPL-2630 to switch the LED.
Test data indicates a minimum input impedance of 6000 ohms for the QDLR. The possible breakdown path is through this chip not including the HCPL-2630 via pins 8 and 12 to ground and pins 4 and 16 through the 5 volt supply.
As the HCPL-2630 LEDs are low voltage devices, any surge voltage out of tolerance will result in the destruction of the LED in an open circuit.. The impedance of the electrical isolation barrier in the HCPL-2630 will preclude any MCF transfer.
The class 1E device interprets the flash of the LED as informa-tion. The DRMS system has been extensively tested at the Inte-grated System Test (IST) prior to shipment from the vendor to verify that illegal commands or requests which could effect 1E equipment were inhibited.
Requests for information and time checks are performed via a Kaman protocol using RS422 interface. Due to physical data formatting (for security) with constraints such as headers, checksums, deadbands, body, and end of text, an instantaneous surge flash on the transmitting LED cannot be interpretted by the class 1E monitor to represent a high level logic string.
6.2 AIMS The approach for testing the isolator was to ensure that MCF for the device was achieved. Only those faults which could occur outside of the AIMs were considered as the device is a sealed box and all wiring interface is through two 20 pin Amphenol connectors.
A review of the Kaman schematic drawing for the AIMs isolator board 8430402-001 indicates three possible paths for MCF testing; 0-10 volt dc, 0-5 volt dc, and 4-20 mode. The isolation device for providing the non 1E to class"1E separation is an Intronics IA184 isolation amplifier; one for each channel of information.
Open circuit testing on the AIMs was achieved throughout factory testing of the DRMS and into the startup and test phases at KP2, as no loads were connected to the device and no shorting resistor was required on the current output nor provided.
The typical application of the AIMs at NMP2 is to provide Post Accident Monitoring (PAM) to the Emergency Response Facility (ERF) computer.
0 It was determined that this 4-20 mode signal be tested as it represents a greater source of current and heat in the device which would make the isolator more susceptible to failure as all components are mounted on the same printed circuit board.
Although the 0-10vdc output is also being used from the AIMs, this output is in series with the current output supply and is considered a part of the test channel after application of the MCF.
Testing of the 0-Svdc output represents a lesser risk for MCF testing as this circuit contains redundant operational and current amplifiers connected in series before connection to the isolation transformer.
7.0 CONCLUSION
7.1 SIH's Co~nication Device The Class lE circuit of the Safety Isolation Module (SIM) is not affected by faults occuring on the non lE portion of the module; these faults are open circuit, short circuit, line-to-ground and max'imum credible fault of 120VAC fused at 30amp transverse mode hot short.
7.2 AIH's Device The Class 1E circuit of the Analog Isolation Module (AIH) is not affected by faults occurring on the non 1E portion of the module.
The current output circuit on the AIHs was subjected to open and maxi~ credible fault of 120VAC fused at 30amp transverse mode hot short;-
8.0 TEST DESCRIPTION Refer to Test Procedure under CPN Z855, SWEC procedure //12177-SK-955, Rev. 2 dated 3-19-86 for details (Attachment 5)
NOTE: The test results shown in Attachment 5, Revision 2, HCF Test Procedure were transcribed directly from those, notes taken by Connors on 3-24-86 and 3-26-86 on a Revision 1 procedure
'ith appropriate Revision 2 items deleted. This copy is available for verification.
9.0 QUALIFICATION IEEE environ'ental and seismic qualification for the SIHs and ABfs has been completed by the vendor (Kaman) prior to the start of the MCF test.
This information is available in Kaman's NMP2 Qualification Summary Report f/K-84-103u(r) available at NHP2.
10
- 10. 0 CLARIFICATION
- 1. Section 5.7.1.1 of the SIkfs test (attachment 5)
Test set up functioned normally after completion of this step until the power was turned off to disconnect the test equipment.
- 2. Section 6.0 of the SL~fs test (attachment 5)
- a. 1st paragraph Hot short is the MCF.
- b. 2nd paragraph "Unit" referred to is the HCPL-2630 optocoupler. Although this device is rated for 3000vdc isolation, Kaman is claiming 1500vdc isolation in their specification sheet on the SIMs which is reasonable as all isolation is performed on one board in this mocule.
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- I P FIGURE 1 Test 5.7.1.1 SIM'S 3/24/86 C. Dunham Vertical = 5mV. x 100 = 5v./Div. AC volts Vertical = 200mV ~ 4A/Div. AC current (amps)
Hor. 5m Sec/Div.
ATTACHMENT 3 CPN Z855 Page 3 of 5
~ rr FIGURE 2 2RMS-Rul18 Microcomputer (Kem-A)
Location: Radwaste Sample Room Turbine Bldg. EL. 261-
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FIGURE 3 2RMS-RAW118 Remote Indication & Alarm (KE IA) with portable Indicator & Controller (KE IC)
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FIGURE 4 SRMS Interface Module with SIM'S Isolator NOTE: Post test photograph light on SIM's is off after unit failed.
FIGURE 5 Test equipment (pulse generator & scope) 4
ATTACHMENT 3 CPN Z855 Page 5 of 5 1 %41 FIGURE 6 Internal view of 2RMS-Rull8 FIGURE 7 Nicolet scope peak to peak reading 4
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~@~w~4:e- A FIGURF. 1 Test 5.3.1 - AIM's 3/24/86 C. Dunham Vertical ~ 5 volts/Div.
Vertical ~ 4 amps/Div.
Horizontal ~ 5mSec/Div.
ATTACHMENT 4 CPN Z855 Page 3 of 5
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P FIGURE 2 AIM's test scope setup (prior to test)
FIGURE 3 2SWP*CAB23A (KML) Location:. Electrical tunnel north el. 215'
ATTACHMENT 4 CPN Z855 Page 4 of 5
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Figure 6 Local Indicator & Controller (KELIC) for 2SWP*CAB23A Figure 7 Aim's test setup KERIC and scope