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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20216J6721999-09-22022 September 1999 Forwards Copy of Memorandum ,received from La Robertson,Fema Region Iv,Re Summary of Disaster Initiated Review,Hurricane Floyd for Bnpp,Offsite Preparedness.Memo Accurately Reflects Issues Discussed During 990918 Telcon ML20211L3541999-09-0303 September 1999 Notification of 990914 Meeting with Util in Southport,Nc to Discuss Brunswick Practices Re Protection of Threatened & Endangered Species of Sea Turtles Near Plant ML20204E2851999-03-17017 March 1999 Requests Entry of Attached Draft Info Provided by CP&L on 990315,into Brunswick Steam Electric Plant Docket Files & Pdr.Info Pertains to Pending Request to Extend Electrical Bus Allowed Outage Time Submitted to NRC on 961101 ML20203C2491999-02-0909 February 1999 Notification of 990309 Meeting with Util in Rockville,Md to Discuss NRC Staff Questions Re Application to Amend Brunswick Steam Electric Plant TSs to Extend Allowable Outage Time for Specific Electrical Buses ML20207L6971999-02-0909 February 1999 Notification of 990309 Meeting with Util in Rockville,Md to Discuss NRC Staff Questions Re Application to Amend BSEP TSs to Extend AOT for Specific Electrical Buses.Meeting Has Been Cancelled ML20155E0811998-10-30030 October 1998 Notification of 981117 Meeting with CP&L in Rockville MD to Discuss NRC Staff Questions Re Application to Amend TSs to Extend Allowable Outage Time for Specific Electrical Buses ML20198P7281998-05-0808 May 1998 Discusses OI Rept 2-97-015 Re Brunwsick Alleged Discrimination Against Employee for Raising Concerns Re Environmental Qualification Program to Nrc.Oi Did Not Substantiate Allegation ML20216B0961998-03-0404 March 1998 Forwards SER Accepting 971117 Request for Approval of Alternative to Insp of RPV Circumferential Welds in Plant, Unit 1 Pursuant to 10CFR50.55a(a)(3)(i) & 10CFR50.55a(g)(6)(ii)(A)(5) for Next Two Operating Cycles ML20198R4051998-01-16016 January 1998 Notification of 980128 Meeting W/Carolina Power & Light Co in Rockville,Md to Discuss NRC Staff Questions Re Brunswick Steam Electric Plant Conversion to Improved TSs ML20197K1151997-12-15015 December 1997 Notification of Meeting W/Cp&L on 980108 in Rockville,Md to Discuss Staff Questions Re Plant Conversions to Improved TSs ML20199J6951997-11-20020 November 1997 Notification of 971202 Meeting W/Util to Discuss NRC Staff Questions Re Licensee TS Amend Request to Support Hardware Upgrades to Control Building Ventilation Sys ML20199J7191997-11-20020 November 1997 Notification of 971205 Meeting W/Util to Discuss NRC Staff Questions Re Licensee Conversion to Improved TS ML20236N3921997-09-10010 September 1997 Discusses Closure of TIA 97-006 Re Vessel Disassembly W/O Secondary Containment Integrity Established for Brunswick Steam Electric Plant,Unit 1 ML20217K8211997-08-13013 August 1997 Notification of 970904 Meeting W/Util in Rockville,Md to Discuss Staff Questions Re Units 1 & 2 Conversion to Improved TSs ML20217H8481997-08-0707 August 1997 Notification of 970811 Meeting W/Util in Southport,Nc to Discuss Consultation Procedures Associated W/Endangered Species Act ML20198G1181997-08-0707 August 1997 Notification of 970820 Meeting W/Cp&L in Rockville,Md to Discuss Staff Questions Re Plant Conversion to Improved TSs ML20198G1121997-08-0707 August 1997 Notification of 970908 Meeting W/Cp&L in Rockville,Md to Discuss Staff Questions Re Plant Conversion to Improved TSs ML20217H8341997-08-0707 August 1997 Notification of 970814 Meeting W/Util in Rockville,Md to Discuss NRC Staff Questions Re Plant,Units 1 & 2 Conversion to Improved TSs ML20149L5411997-08-0101 August 1997 Notification of 970806 Meeting W/Util in Rockville,Md to Discuss Status & Review Schedule for BSEP Conversion to Improved TSs ML20149K8921997-07-25025 July 1997 Notification of 970801 Meeting W/Cp&L in Rockville,Maryland to Discuss Status & Review Schedule for Various CP&L Licensing Actions Under NRC Review ML20198P7121997-07-0909 July 1997 Discusses OI Rept 2-96-036 Re Brunswick Steam Electric Plant Discrimination Against Engineer for Raising Technical Concerns About Equipment Qualification Practices.Also Encl, Viewgraphs Re Cpl EQ Program Reconstitution Effort ML20198P6641997-02-12012 February 1997 Submits Brunswick Responses to Recipient EQ Questions ML20198P6191997-02-0505 February 1997 Informs That Author Passed Along Brunswick Licensee Engineering Evaluation on Flexible Conduit & Conduit Seal Configuration to F Ashe of Eelb NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20134B5061994-04-13013 April 1994 Submits Plants Which Will Be Discussed in Categories Indicated Re Results of Screening Meetings for June 1994. Partially Deleted ML20217D3401994-01-28028 January 1994 Provides Brunswick Restart Assessment Panel Recommendation to Proceed W/Restart of Brunswick,Unit 1.Summary of 930112 Plant Performance Review,Restart Review Plan,Unit 1 Specific Restart Issues & Status of Restart Issues Encl ML20212E5101994-01-26026 January 1994 Discusses Status of Restart Issues Assigned to NRR for Resolution at Facility.Restart Review Plan Encl ML20059K3721994-01-12012 January 1994 Notification of 940119 Significant Meeting W/Util at Brunswick Media Center to Discuss Restart,Readiness & Power Ascension Plans ML20059J1451994-01-12012 January 1994 Notification of Significant Meeting W/Util in Atlanta,Ga to Discuss Scope of Upcoming Brunswick Unit 2 Refueling Outage ML20217D3621994-01-12012 January 1994 Discusses Status of Restart Issues Assigned to NRR for Plant,Unit 1 ML20059L0871993-12-21021 December 1993 Forwards Rept of Technical Review Team:Potential Shroud Cracking in 1984 ML20217D3551993-12-16016 December 1993 Informs Staff of Intent of CP&L to Restart Brunswick Unit 1 in Near Future & Identifies Issues That May Be Adverse to Recommendation Which Have Not Been Identified ML20058A6421993-11-18018 November 1993 Notifies of 931130 Meeting W/Util in Rockville,Md to Discuss Evaluation of Core Shroud Cracks & Safety Analysis for Design of Repair Mod ML20058J7081993-11-10010 November 1993 Notification of Significant Licensee Meeting W/Util on 931216 in Southport,Nc to Discuss Plant SALP ML20058J7221993-11-0505 November 1993 Notification of Significant Licensee Meeting W/Util on 931215 to Discuss Facility Restart Readiness ML20058J5441993-11-0505 November 1993 Notification of Significant Licensee Meeting W/Util on 931118 to Discuss SALP Board Meeting Re Peformance of Facility During Period 921101-931106 ML20057F9191993-10-15015 October 1993 Notification of 931022 Meeting W/Util in Rockville,Md to Discuss Core Shroud Cracks,Evaluation Methodology & Analysis & Design of Repair Option ML20059A0301993-10-13013 October 1993 Forwards Written SALP Feeder Inputs on Performance of Plant During Period 921101-931106.Informs of Assigned Responsibility by Functional Area for Presentation to SALP Board on 931118.Encl Filed in Central Files ML20057E7281993-10-0505 October 1993 Notification of Significant Licensee Meeting W/Util on 931025 to Discuss Restart Readiness ML20057E7621993-10-0505 October 1993 Notification of 931020 Meeting W/Util in Atlanta,Ga to Discuss Nuclear Assessment dept-related Issues ML20057E4901993-09-23023 September 1993 Notification of Significant Meeting W/Util on 931012 to Discuss Nuclear Engineering Dept-Related Issues ML20057B9281993-09-22022 September 1993 Notification of 930923 Meeting W/Util in Rockville,Md to Discuss Inspection Activities Associated W/Facility Core Shroud ML20217D4971993-08-24024 August 1993 Forwards Evaluation of Qa,Engineering & Operations Re, Charter for Brunswick 1 Readiness Insp ML20056E0321993-08-13013 August 1993 Notification of 930829 Meeting W/Util in Rockville,Md to Discuss Technical Issues Re Unit 1 Restart Readiness. Meeting Recheduled ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20056E0611993-08-0202 August 1993 Notification of 930817 Meeting W/Util in Rockville,Md to Discuss Technical Issues on Restart Readiness ML20211M3491993-04-0808 April 1993 Informs Commission of Present Status of Staff Review of Activities of Licensee in Preparation for Restart of Plant, Units 1 & 2 ML20128F9861993-02-0909 February 1993 Notification of 930217 Meeting W/Util in Rockville,Md to Discuss Implementation of motor-operated Valve Test Program at CP&L Facilities ML20128C3421993-01-29029 January 1993 Notification of 930202 Meeting W/Util in Rockville,Md to Discuss Revision of Amend Request Proposing Termination of Confirmatory Order on Brunswick Improvement Plan ML20128A8001993-01-21021 January 1993 Notification of Significant Meeting W/Util on 930204 to Discuss Startup Related Issues 1999-09-03
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20216J6721999-09-22022 September 1999 Forwards Copy of Memorandum ,received from La Robertson,Fema Region Iv,Re Summary of Disaster Initiated Review,Hurricane Floyd for Bnpp,Offsite Preparedness.Memo Accurately Reflects Issues Discussed During 990918 Telcon ML20211L3541999-09-0303 September 1999 Notification of 990914 Meeting with Util in Southport,Nc to Discuss Brunswick Practices Re Protection of Threatened & Endangered Species of Sea Turtles Near Plant ML20204E2851999-03-17017 March 1999 Requests Entry of Attached Draft Info Provided by CP&L on 990315,into Brunswick Steam Electric Plant Docket Files & Pdr.Info Pertains to Pending Request to Extend Electrical Bus Allowed Outage Time Submitted to NRC on 961101 ML20203C2491999-02-0909 February 1999 Notification of 990309 Meeting with Util in Rockville,Md to Discuss NRC Staff Questions Re Application to Amend Brunswick Steam Electric Plant TSs to Extend Allowable Outage Time for Specific Electrical Buses ML20207L6971999-02-0909 February 1999 Notification of 990309 Meeting with Util in Rockville,Md to Discuss NRC Staff Questions Re Application to Amend BSEP TSs to Extend AOT for Specific Electrical Buses.Meeting Has Been Cancelled ML20155E0811998-10-30030 October 1998 Notification of 981117 Meeting with CP&L in Rockville MD to Discuss NRC Staff Questions Re Application to Amend TSs to Extend Allowable Outage Time for Specific Electrical Buses ML20198P7281998-05-0808 May 1998 Discusses OI Rept 2-97-015 Re Brunwsick Alleged Discrimination Against Employee for Raising Concerns Re Environmental Qualification Program to Nrc.Oi Did Not Substantiate Allegation ML20216B0961998-03-0404 March 1998 Forwards SER Accepting 971117 Request for Approval of Alternative to Insp of RPV Circumferential Welds in Plant, Unit 1 Pursuant to 10CFR50.55a(a)(3)(i) & 10CFR50.55a(g)(6)(ii)(A)(5) for Next Two Operating Cycles ML20198R4051998-01-16016 January 1998 Notification of 980128 Meeting W/Carolina Power & Light Co in Rockville,Md to Discuss NRC Staff Questions Re Brunswick Steam Electric Plant Conversion to Improved TSs ML20197K1151997-12-15015 December 1997 Notification of Meeting W/Cp&L on 980108 in Rockville,Md to Discuss Staff Questions Re Plant Conversions to Improved TSs ML20199J6951997-11-20020 November 1997 Notification of 971202 Meeting W/Util to Discuss NRC Staff Questions Re Licensee TS Amend Request to Support Hardware Upgrades to Control Building Ventilation Sys ML20199J7191997-11-20020 November 1997 Notification of 971205 Meeting W/Util to Discuss NRC Staff Questions Re Licensee Conversion to Improved TS ML20236N3921997-09-10010 September 1997 Discusses Closure of TIA 97-006 Re Vessel Disassembly W/O Secondary Containment Integrity Established for Brunswick Steam Electric Plant,Unit 1 ML20217K8211997-08-13013 August 1997 Notification of 970904 Meeting W/Util in Rockville,Md to Discuss Staff Questions Re Units 1 & 2 Conversion to Improved TSs ML20198G1181997-08-0707 August 1997 Notification of 970820 Meeting W/Cp&L in Rockville,Md to Discuss Staff Questions Re Plant Conversion to Improved TSs ML20198G1121997-08-0707 August 1997 Notification of 970908 Meeting W/Cp&L in Rockville,Md to Discuss Staff Questions Re Plant Conversion to Improved TSs ML20217H8481997-08-0707 August 1997 Notification of 970811 Meeting W/Util in Southport,Nc to Discuss Consultation Procedures Associated W/Endangered Species Act ML20217H8341997-08-0707 August 1997 Notification of 970814 Meeting W/Util in Rockville,Md to Discuss NRC Staff Questions Re Plant,Units 1 & 2 Conversion to Improved TSs ML20149L5411997-08-0101 August 1997 Notification of 970806 Meeting W/Util in Rockville,Md to Discuss Status & Review Schedule for BSEP Conversion to Improved TSs ML20149K8921997-07-25025 July 1997 Notification of 970801 Meeting W/Cp&L in Rockville,Maryland to Discuss Status & Review Schedule for Various CP&L Licensing Actions Under NRC Review ML20198P7121997-07-0909 July 1997 Discusses OI Rept 2-96-036 Re Brunswick Steam Electric Plant Discrimination Against Engineer for Raising Technical Concerns About Equipment Qualification Practices.Also Encl, Viewgraphs Re Cpl EQ Program Reconstitution Effort ML20198P6641997-02-12012 February 1997 Submits Brunswick Responses to Recipient EQ Questions ML20198P6191997-02-0505 February 1997 Informs That Author Passed Along Brunswick Licensee Engineering Evaluation on Flexible Conduit & Conduit Seal Configuration to F Ashe of Eelb NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20134B5061994-04-13013 April 1994 Submits Plants Which Will Be Discussed in Categories Indicated Re Results of Screening Meetings for June 1994. Partially Deleted ML20217D3401994-01-28028 January 1994 Provides Brunswick Restart Assessment Panel Recommendation to Proceed W/Restart of Brunswick,Unit 1.Summary of 930112 Plant Performance Review,Restart Review Plan,Unit 1 Specific Restart Issues & Status of Restart Issues Encl ML20212E5101994-01-26026 January 1994 Discusses Status of Restart Issues Assigned to NRR for Resolution at Facility.Restart Review Plan Encl ML20059K3721994-01-12012 January 1994 Notification of 940119 Significant Meeting W/Util at Brunswick Media Center to Discuss Restart,Readiness & Power Ascension Plans ML20059J1451994-01-12012 January 1994 Notification of Significant Meeting W/Util in Atlanta,Ga to Discuss Scope of Upcoming Brunswick Unit 2 Refueling Outage ML20217D3621994-01-12012 January 1994 Discusses Status of Restart Issues Assigned to NRR for Plant,Unit 1 ML20059L0871993-12-21021 December 1993 Forwards Rept of Technical Review Team:Potential Shroud Cracking in 1984 ML20217D3551993-12-16016 December 1993 Informs Staff of Intent of CP&L to Restart Brunswick Unit 1 in Near Future & Identifies Issues That May Be Adverse to Recommendation Which Have Not Been Identified ML20058A6421993-11-18018 November 1993 Notifies of 931130 Meeting W/Util in Rockville,Md to Discuss Evaluation of Core Shroud Cracks & Safety Analysis for Design of Repair Mod ML20058J7081993-11-10010 November 1993 Notification of Significant Licensee Meeting W/Util on 931216 in Southport,Nc to Discuss Plant SALP ML20058J5441993-11-0505 November 1993 Notification of Significant Licensee Meeting W/Util on 931118 to Discuss SALP Board Meeting Re Peformance of Facility During Period 921101-931106 ML20058J7221993-11-0505 November 1993 Notification of Significant Licensee Meeting W/Util on 931215 to Discuss Facility Restart Readiness ML20057F9191993-10-15015 October 1993 Notification of 931022 Meeting W/Util in Rockville,Md to Discuss Core Shroud Cracks,Evaluation Methodology & Analysis & Design of Repair Option ML20059A0301993-10-13013 October 1993 Forwards Written SALP Feeder Inputs on Performance of Plant During Period 921101-931106.Informs of Assigned Responsibility by Functional Area for Presentation to SALP Board on 931118.Encl Filed in Central Files ML20057E7281993-10-0505 October 1993 Notification of Significant Licensee Meeting W/Util on 931025 to Discuss Restart Readiness ML20057E7621993-10-0505 October 1993 Notification of 931020 Meeting W/Util in Atlanta,Ga to Discuss Nuclear Assessment dept-related Issues ML20057E4901993-09-23023 September 1993 Notification of Significant Meeting W/Util on 931012 to Discuss Nuclear Engineering Dept-Related Issues ML20057B9281993-09-22022 September 1993 Notification of 930923 Meeting W/Util in Rockville,Md to Discuss Inspection Activities Associated W/Facility Core Shroud ML20217D4971993-08-24024 August 1993 Forwards Evaluation of Qa,Engineering & Operations Re, Charter for Brunswick 1 Readiness Insp ML20056E0321993-08-13013 August 1993 Notification of 930829 Meeting W/Util in Rockville,Md to Discuss Technical Issues Re Unit 1 Restart Readiness. Meeting Recheduled ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20056E0611993-08-0202 August 1993 Notification of 930817 Meeting W/Util in Rockville,Md to Discuss Technical Issues on Restart Readiness ML20211M3491993-04-0808 April 1993 Informs Commission of Present Status of Staff Review of Activities of Licensee in Preparation for Restart of Plant, Units 1 & 2 ML20128F9861993-02-0909 February 1993 Notification of 930217 Meeting W/Util in Rockville,Md to Discuss Implementation of motor-operated Valve Test Program at CP&L Facilities ML20128C3421993-01-29029 January 1993 Notification of 930202 Meeting W/Util in Rockville,Md to Discuss Revision of Amend Request Proposing Termination of Confirmatory Order on Brunswick Improvement Plan ML20128A8001993-01-21021 January 1993 Notification of Significant Meeting W/Util on 930204 to Discuss Startup Related Issues 1999-09-03
[Table view] |
Text
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n UNITED STATES 3#
i NUCLEAR REGULATORY COMMISSION l WASHINoTON. O C. 20146 o%,o l November 10, 1992
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HEMORANDUM FOR: Elinor G. Adensam, Director I Project Directorate 11-1 Division of Reactor Projects i
FROM: Scott F. Newberry, Chief Instrumentation and Controls Branch Division of Reactor Controls and Human Factors
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION STEAM LEAK DETECTION INSTRUMENTATION NUMAC UPGRADE - BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 On September 14, 1992, the licensee submitted for NRC staff review a
~
proposed revision to the Technical Specifications for the Brunswick Steam Electric Plant, Units 1 and 2. The staff determined that several' topics j addressing hardware and software implementathn have not been addressed adequately in this submittal, and therefore it is equested that the licensee '
provide the additional informatio.. as listed in the enclosure in preparation :
for review of this Technical Specification amendment. Please provide a response and related documentation to these questions within C0 days.
(1,k .
Scott F. Newberry, Chie Instrumentation and Controls Branch Division of Reactor Controls and Human factors
Enclosure:
-As stated cc:
R. Lo i pf'aDMb ed*
e
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4 ENCLOSURE General Backaround Information
- 1. Provide design information of the GE microprocessor based NUMAC system. Include the descriptions of the devices used in the microprocessor, the programming language, compiler, type of microprocessor, etc.
- 2. Provide drawings and descriptions of the physical location of the replacement system in the plant. ,
- 3. Discuss the temperature and humidity qualifications of the NUMAC system and how these qualifications meet normal plant '
and worst case accident conditions.
Software Verification and Validation
- 1. Provide references / guidelines used for the NUMAC system.
- 2. Discuss any differences with IEEE 7.4.3.2.
- 3. Describe the plans for performing the verification and validation (V&V) of the NUMAC system logic. If the V&V has been performed, provide the documentation of the V&V plan.
If the V&V has not been performad, describe the process which CP&L will ensure the adequacy of the software used in the NUMAC system for 1E applications.
- 4. Provide the acceptance critoria for hardware and software, and also discuss traceability of products at different development stages to their specifications.
- 5. Provide the acceptance criteria and procedures for, and results of the hardware / software integration testing.
- 6. Provide the procedures and results for the startup testing..
- 7. Previde a listing of all software errors and_their ensuring corrections.
Operations /Surveillances
- 1. Describe site acceptance / pre-operatiunal testing;-
specifically ad. tress loss and restoration of power to the NUMAC system during standby and power operation. Also describe the memory-retention capability of the NUMAC system. *
- 2. Discuss coordination of self check and continuous monitoring modes with normal NUMAC system operations.
Page 1 of 4 i
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- 3. Describe the steps required to recover the NUMAC s ' tem if a loss of system function is detected.
- 4. Describe all provisions for "back-up" provision to the NUMAC system.
- 5. Does the system provide alarms for the loss of the NUMAC system's self-diagnostic features?
- 6. Discuss the potential failures for which the NUMAC system is not capable of detecting during channel functional testing.
- 7. Discuss the NUMAC system stability.
EMI/RFI
- 1. Provide the NUMAC electromagnetic compatibility (EMC) specifications and justify the margin between the EMC specifications and expected electromagnetic interference.
- 2. Discuss the process by which CP&L will verify that the electromagnetic environment at the plant is enveloped by the NUMAC EMC test parameterst
- a. Provide a list of the test equipment used in the onsite EMI/RFI testing and their technical specifications.
- b. Provide the methodology and the results of the onsite electromagnetic interference survey.
- c. Provide the evaluations of the vendor's EMI/RFI testing methodology and the results of the factory testing for radiated and conducted susceptibility.
- d. Provide the results of the licensee's comparison between the onsite and f actory EMI/RFI testing.
- 3. List the EMI/RFI testing frequencies and provide justifications for any frequencies not tested.
- 4. Durin., the pre-operational test, are there any transient monitors installed? If any, what are the parameters being-monitored?
- 5. Provide the surge transient susceptibility testing apecifications for the NUMAC system and justify the margin between the specifications and expected surges.
Man Machine Interface
- 1. Discuss the_ interface that the man machine interface (MMI) has with the NUMAC system.
Page 2 of 4
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e
- 2. Discuss tha process of altering setpoints through MMI or other means, i.e., password protection, administrative control, etc. ,
IE and Non-1E Isolation
- 1. Provide a detailed description of the devices used to '
accomplish electrical isolation between the 1E and non-1E systems and describe the specific testing performed to demonstrate that the devices are acceptable for this application.
- 2. Provide data to verify that the maximum credible faults applied during the tests discussed in the above question were the maximum voltage / current to which the device could be exposed, and explain how the maximum voltage / current was determined.
- 3. Verify that other faults were considered (i.e., open and short circuits)
- 4. Define the acceptance criteria for each type isolati.on device.
- 5. Provide the electrical wiring diagrams which show the non-1E connections to the NUMAC system.
C_onfiouration Control Describe the process for future modification to the software and hardware of the NUMAC system.
Commercial Grade Item Dedication
- 1. Provide the procurement documentation for the NUMAC system.
- 2. Provide the mean-time-to-failure (MTTF) and the mean-time-to-repair (MTTR) information for the NUMAC system.
- 3. Describe the audit and audit results of the vendor's QA program and procedures fcr commercial grade dedication of the NUMAC system.
- 4. What are the vendor's recommendation and bases for the shelf life of the_NUMAC_ spare parts?
- 5. Provide the standards and procedures used to dedicate the GE commercial grade NUMAC system.
- 6. Describe the criteria governing the successful completion of the GE commercial grade NUMAC system.
Page 3 of 4
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- 7. Identify the methods and acceptance criteria for verifying the critica). characteristics.
Deslan basis consideration Provide the assessment and documentation on the development of the design modification with respect to the design basis.
Egwer Sunoly
- 1. Were the power supplies independently surge withstand tested?
- 2. Provide the power requirements for the NUMAC system.
3 Are switching power supplies used and what provisions are made to control harmonic distortions in the replacement system.
Failure Mode Discuss the failure mode of a loss of detector signal.
Eail Safe i Describe operation and design of any other NUMAC component uued to place the system in its fail safe condition.
Groundina
- 1. Are the analog and digital grounds isolated?
- 2. During RFI testing, was the signal on the ground line monitore Discuss the effects of the signal measured on the grounu line in relation to RFI testing.
- 3. Discuss the effects of lightning strike on the ground line and provisions for system protection.
EgipJ;tipt Calculations Discuss the methodology of calculating the analytical limit and allowable limit for the differential flow of the reactor water cleanup system isolation function..
Page 4 of 4
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