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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F8911999-10-13013 October 1999 Forwards Copy of FEMA Region IV Final Rept for 990623-24, Grand Gulf Nuclear Station Exercise.Rept Indicates No Deficiencies or Areas Requiring Corrective Action Identified During Exercise ML20216J8891999-10-0404 October 1999 Forwards Details of Existing Procedural Guidance & Planned Administrative Controls.Util Respectfully Requests NRC Review & Approval of Changes by 991020.Date Will Permit to Implement Changes & Realize Full Benefit During Refueling ML20217B0361999-10-0404 October 1999 Refers to Investigation Conducted by NRC OI Re Activities at Grand Gulf Nuclear Station.Investigation Conducted to deter- Mine Whether Security Supervisor Deliberately Falsified Unescorted Access Authorizations.Allegation Unsubstantiated ML20212J8151999-09-29029 September 1999 Forwards Insp Rept 50-416/99-12 on 990725-0904.One Violation Noted & Being Treated as Noncited Violation.Licensee Conduct of Activities at Grand Gulf Facility Characterized by Safety Conscious Operations,Sound Engineering & Maint Practices ML20216J6811999-09-28028 September 1999 Ack Receipt of ,Transmitting Rev 31 to Physical Security Plan for GGNS Under Provisions of 10CFR50.54(p). NRC Approval Not Required,Based on Determination That Changes Do Not Decrease Effectiveness & Limited Review ML20212J7361999-09-28028 September 1999 Forwards Insp Rept 50-416/99-11 on 990830-0903.No Violations Noted.Purpose of Insp to Review Solid Radioactive Waste Management & Radioactive Matl Transportation Programs ML20212J5321999-09-27027 September 1999 Forwards Insp Rept 50-416/99-14 on 990830-0903.No Violations Noted.Inspectors Determined That Radioactive Waste Effluent Releases Properly Controlled,Monitored & Quantified ML20216J7101999-09-26026 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator License Examinations ML20216J8141999-09-26026 September 1999 Forwards Proprietary Renewal Applications for Licensed Operators for Wk Gordon & SA Elliott at Grand Gulf Nuclear Station.Proprietary Info Withheld ML20212F5521999-09-23023 September 1999 Forwards SER Accepting Util Analytical Approach for Ampacity Derating Determinations at Grand Gulf Nuclear Station,Unit 1 & That No Outstanding Ampacity Derating Issues as Identified in GL 92-08 Noted ML20212D9211999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of GGNS on 990818 & Identified No Areas in Which Licensee Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through March 2000 Encl ML20212A9331999-09-13013 September 1999 Forwards Partially Withheld Insp Rept 50-416/99-15 on 990816-20 (Ref 10CFR73.21).One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20211P7631999-09-10010 September 1999 Discusses Staff Issuance of SECY-99-204, Kaowool & FP-60 Fire Barriers at Plant.Proposed Meeting to Discuss Subj Issues Will Take Place in Oct or Nov 1999 ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211Q3471999-09-0909 September 1999 Forwards Federal Emergency Mgt Agency Final Rept for 990623 Plant Emergency Preparedness Exercise.No Deficiencies Noted & One Area Requiring Corrective Action Identified ML20211Q3091999-09-0909 September 1999 Forwards Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20211Q4861999-09-0808 September 1999 Informs That Util Has Discovered Dose Calculation Utilized non-conservative Geometry Factor for Parameter.Calculation Error Being Evaluated in Accordance with Corrective Action Program ML20211Q0091999-09-0808 September 1999 Forwards Request for Addl Info Re Individual Plant Exam of External Events for Grand Gulf Nuclear Station,Unit 1. Response Requested by 000615 ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20211P4171999-09-0707 September 1999 Ack Receipt of ,Which Transmitted Addendum to Rev 30 to Physical Security Plan for Ggns,Per 10CFR50.54(p).NRC Approval Is Not Required,Since Util Determined That Changes Do Not Decrease Effectiveness of Plan ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211K6061999-08-31031 August 1999 Informs That Plant Has No Candidates to Take 991006 Generic Fundamentals Exam ML20211K5641999-08-31031 August 1999 Forwards Rev 39 to Grand Gulf Nuclear Station Emergency Plan Non-Safety Related, IAW 10CFR50,App E,Section V. Changes Do Not Decrease Effectiveness of Plan & Continues to Meets Stds of 10CFR50.47(b) & Requirements of App E ML20211J2321999-08-26026 August 1999 Advises That Info Contained in to Support NRC Review of GE Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Will Be Withheld from Public Disclosure ML20211J3761999-08-25025 August 1999 Corrected Ltr Informing That Info Provided (on Computer Disk & in Ltr to Ineel ) Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended.Corrected 990827 ML20211F4881999-08-25025 August 1999 Advises That Info Submitted by 990716 Application & Affidavit Containing Diskette & to Ineel Mareked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20211F7751999-08-24024 August 1999 Forwards Insp Rept 50-416/99-10 on 990809-13.No Violations Noted.Insp Covered Licensed Operator Requalification Program & Observations of Requalification Activities ML20211C4381999-08-20020 August 1999 Forwards Rev 31 to Physical Security Plan for Protection of Grand Gulf Nuclear Station,Iaw 10CFR50.54(p).Util Has Determined That Rev Does Not Decrease Effectiveness of Plan. Encl Withheld,Per 10CFR73.21 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20211B3761999-08-16016 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001, ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20211A9481999-08-12012 August 1999 Informs of Completion of Analysis of Heat Transfer in Cooler During Fan Coast Down & Concludes That Potential Exists for Steam Foundation,Under Conditions Where Dcw Sys Flow Is Lost Prior to Full Isolation Valve Closure ML20210P8411999-08-0909 August 1999 Forwards Insp Rept 50-416/99-09 on 990613-0724.No Violations Noted.Activities at Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20210N6401999-08-0303 August 1999 Informs That Eighteeen Identified Penetrations Will Be Restored to Conformance with Licensing Requirements Prior to Restart from RFO10,scheduled for Fall 1999,per GL 96-06. Example of Piping Analysis Being Performed,Encl ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210K1951999-07-30030 July 1999 Forwards Insp Rept 50-416/99-03 on 990405-08 & 0510-11.No Violations Identified ML20211K7491999-07-30030 July 1999 Forwards Ltr Rept Documenting Work Completed Under JCN-W6095,analyses Performed at Ineel to Calculate Minimum Time to Fuel Pin Failure in Boiling Water Reactors (BWR) ML20210K6661999-07-29029 July 1999 Forwards Fitness for Duty Program Performance six-month Rept for Period Covering Jan-June 1999,per 10CFR26.71 ML20210F3591999-07-26026 July 1999 Forwards Proprietary Version & Redacted Version of Wyle Test Rept M-J5.08-Q1-45161-0-8.0-1-0,re Pressure Locking & Thermal Binding Test Program.Proprietary Version Withheld ML20210E3251999-07-23023 July 1999 Forwards Insp Rept 50-416/99-07 on 990622-25.No Violations Noted.Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise Was Conducted ML20210D2401999-07-21021 July 1999 Informs of Resignation of Operator WE Griffith,License OP-20806-1,from Entergy Operations,Inc ML20209J0311999-07-16016 July 1999 Forwards Proprietary Info Supporting Review of Generic Alternate Source Term Request.Proprietary Info Withheld Per 10CFR2.790 ML20209G4791999-07-15015 July 1999 Forwards Proposed Emergency Plan Change as Addendum to Changes Previously Submitted Via GNRO-98/00028 & GNRO-99/00007,for NRC Review & Approval ML20210B1031999-07-15015 July 1999 Forwards Insp Rept 50-416/99-08 on 990502-0612.Determined That Three Severity Level IV Violations Occurred & Being Treated as Noncited Violations ML20210H3211999-07-14014 July 1999 Forwards Proprietary Info Supporting Review of 970506 Submittal of BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic Bwr. Proprietary Info Withheld Per 10CFR2.790 ML20209D7511999-07-0909 July 1999 Responds to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. as Result of NRC Review of Util Responses,Info Revised in Rvid & Rvid Version 2 Will Be Released ML20209D7671999-07-0101 July 1999 Submits Response to Violations Noted in Insp Rept 50-416/99-02 on 990222-26 & 0308-12.Corrective Actions: Contractor Performance Has Been re-evaluated in Regards to UFSAR Reviews ML20196K4901999-07-0101 July 1999 Discusses Relief Requests PRR-E12-01,PRR-E21-01,PRR-E22-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01 Submitted by EOI on 971126 & 990218.SE Accepting Alternatives Proposed by Util Encl ML20196J5711999-06-30030 June 1999 Advises That Versions of Submitted Info in 990506 Application & Affidavit, Re Proposed Amend to Revise Ts,Marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20216J8891999-10-0404 October 1999 Forwards Details of Existing Procedural Guidance & Planned Administrative Controls.Util Respectfully Requests NRC Review & Approval of Changes by 991020.Date Will Permit to Implement Changes & Realize Full Benefit During Refueling ML20216J7101999-09-26026 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator License Examinations ML20216J8141999-09-26026 September 1999 Forwards Proprietary Renewal Applications for Licensed Operators for Wk Gordon & SA Elliott at Grand Gulf Nuclear Station.Proprietary Info Withheld ML20211Q4861999-09-0808 September 1999 Informs That Util Has Discovered Dose Calculation Utilized non-conservative Geometry Factor for Parameter.Calculation Error Being Evaluated in Accordance with Corrective Action Program ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211K6061999-08-31031 August 1999 Informs That Plant Has No Candidates to Take 991006 Generic Fundamentals Exam ML20211K5641999-08-31031 August 1999 Forwards Rev 39 to Grand Gulf Nuclear Station Emergency Plan Non-Safety Related, IAW 10CFR50,App E,Section V. Changes Do Not Decrease Effectiveness of Plan & Continues to Meets Stds of 10CFR50.47(b) & Requirements of App E ML20211C4381999-08-20020 August 1999 Forwards Rev 31 to Physical Security Plan for Protection of Grand Gulf Nuclear Station,Iaw 10CFR50.54(p).Util Has Determined That Rev Does Not Decrease Effectiveness of Plan. Encl Withheld,Per 10CFR73.21 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20211B3761999-08-16016 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001, ML20211A9481999-08-12012 August 1999 Informs of Completion of Analysis of Heat Transfer in Cooler During Fan Coast Down & Concludes That Potential Exists for Steam Foundation,Under Conditions Where Dcw Sys Flow Is Lost Prior to Full Isolation Valve Closure ML20210N6401999-08-0303 August 1999 Informs That Eighteeen Identified Penetrations Will Be Restored to Conformance with Licensing Requirements Prior to Restart from RFO10,scheduled for Fall 1999,per GL 96-06. Example of Piping Analysis Being Performed,Encl ML20211K7491999-07-30030 July 1999 Forwards Ltr Rept Documenting Work Completed Under JCN-W6095,analyses Performed at Ineel to Calculate Minimum Time to Fuel Pin Failure in Boiling Water Reactors (BWR) ML20210K6661999-07-29029 July 1999 Forwards Fitness for Duty Program Performance six-month Rept for Period Covering Jan-June 1999,per 10CFR26.71 ML20210F3591999-07-26026 July 1999 Forwards Proprietary Version & Redacted Version of Wyle Test Rept M-J5.08-Q1-45161-0-8.0-1-0,re Pressure Locking & Thermal Binding Test Program.Proprietary Version Withheld ML20210D2401999-07-21021 July 1999 Informs of Resignation of Operator WE Griffith,License OP-20806-1,from Entergy Operations,Inc ML20209J0311999-07-16016 July 1999 Forwards Proprietary Info Supporting Review of Generic Alternate Source Term Request.Proprietary Info Withheld Per 10CFR2.790 ML20209G4791999-07-15015 July 1999 Forwards Proposed Emergency Plan Change as Addendum to Changes Previously Submitted Via GNRO-98/00028 & GNRO-99/00007,for NRC Review & Approval ML20210H3211999-07-14014 July 1999 Forwards Proprietary Info Supporting Review of 970506 Submittal of BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic Bwr. Proprietary Info Withheld Per 10CFR2.790 ML20209D7671999-07-0101 July 1999 Submits Response to Violations Noted in Insp Rept 50-416/99-02 on 990222-26 & 0308-12.Corrective Actions: Contractor Performance Has Been re-evaluated in Regards to UFSAR Reviews ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl ML20195J6351999-06-16016 June 1999 Forwards Addendum to Rev 30 of GGNS Physical Security Plan IAW 10CFR50.54(p).Addendum Is Submitted to Announce Relocation/Reconfiguration of Plant Central & Secondary Alarm Station Facilities.Rev Withheld,Per 10CFR73.21 ML20195G0281999-06-0909 June 1999 Submits Summary on Resolution of GL 96-06 Re Eighteen Penetrations Previously Identified as Being Potentially Susceptible to Overpressurization ML20207F5041999-06-0202 June 1999 Forwards Updated Medical Rept IAW License Condition 3 for DA Killingsworth License OP-20942-1.Without Encls ML20206P2981999-05-13013 May 1999 Forwards Responses to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, Cancelling 990402 Submittal ML20206N1921999-05-10010 May 1999 Provides Revised Attachment 2 for Alternative Request IWE-02,originally Submitted 990429 Re Bolt Torque or Tension Testing of Class Mc pressure-retaining Bolting as Specified in Item 8.20 of Article IWE-2500,Table IWE-2500-1 ML20206J0941999-05-0404 May 1999 Forwards Proprietary & Redacted ME-98-001-00,both Entitled, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators. Rept ME-98-002-00 Re Flexible Wedge Gate Valves,Encl.Proprietary Rept Withheld ML20206E7811999-04-29029 April 1999 Proposes Alternatives to Requirements of ASME B&PV Code Section XI,1992 Edition,1992 Addenda,As Listed.Approval of Alternative Request on or Before 990915,requested ML20206D8171999-04-29029 April 1999 Informs NRC of Results of Plant Improvement Considerations Identified in GGNS Ipe,As Requested in NRC . Licensee Found Efforts Have Minimized Extent of Radiological Release in Unlikely Event That Severe Accident Occurred ML20206D7281999-04-28028 April 1999 Forwards South Mississippi Electric Power Association 1998 Annual Rept, Per 10CFR50.71(b).Licensee Will Submit 1998 Annual Repts for System Energy Resources,Inc,Entergy Mississippi,Inc & EOI as Part of Entergy Corp Annual Rept ML20206C9551999-04-22022 April 1999 Forwards 1999 Biennial Emergency Preparedness Exercise Scenario. Without Encl ML20205M1311999-04-0202 April 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. Info Was Discussed During Conference Call with NRC on 990126.Wyle Position Paper Encl.Subj Paper Withheld ML20205H5861999-04-0101 April 1999 Requests Relief from ASME B&PV Code,Section XI for Period of Time That Temporary non-code Repair Was in Effect,Per 10CFR50.55a(g)(5)(iii) ML20205F1781999-03-31031 March 1999 Forwards Consolidated Entergy Submittal to Document Primary & Excess Property Damage Insurance Coverage for Nuclear Sites of Entergy Operations,Inc,Per 10CFR50.54(w)(3) ML20196K7101999-03-26026 March 1999 Submits Reporting & Recordkeeping for Decommissioning Planning,Per 10CFR50.75(f)(1) ML20205A6511999-03-25025 March 1999 Responds to NRC Re Violations Noted in Insp Rept 50-416/99-01 on 990201-05.Corrective Actions:Program Will Be Implemented to Ensure Accessible Areas with Radiation Levels Greater than 1000 Mrem/H ML20204E7391999-03-15015 March 1999 Forwards Objectives for June 1999 Emergency Preparedness Exercise for Plant.Without Encl ML20207H9291999-03-0404 March 1999 Submits Update to Original Certification of Grand Gulf Nuclear Station Simulation Facility IAW Requirements of 10CFR55.45(b)(5) ML20207E3081999-03-0303 March 1999 Informs That GGNS Severe Accident Mgt Implementation Was Completed on 981223.Effort Was Worthwhile & Station Ability to Respond & Mitigate Events That May Lead to Core Melt Has Been Enhanced ML20207E3221999-03-0303 March 1999 Notifies of Change in Status of Mj Ellis,License SOP-43846. Conditional License Requested to Accommodate Medical Condition.Revised NRC Form 396 with Supporting Medical Evidence Attached.Without Encls ML20207A8161999-02-24024 February 1999 Forwards 1998 Annual Operating Rept for Ggns,Unit 1. Listed Attachments Are Encl ML20207A9901999-02-24024 February 1999 Informs That Util Has No Candidates from GGNS to Nominate for Participation in Planned Gfes,Scheduled for 990407 ML20203A1551999-02-0101 February 1999 Forwards Grand Gulf Nuclear Station Fitness for Duty Program Performance six-month Rept for Reporting Period 980701-981231 ML20202G0791999-01-26026 January 1999 Informs That He Mcknight Has Been Permanently Reassigned from Position Requiring License to Perform Assigned Duties. License Is No Longer Needed,Effective 981231 ML20199K4151999-01-20020 January 1999 Forwards Proposed Addendum to Emergency Plan Changes Previously Submitted Via GNRO-98/00028 for NRC Review & Approval as Required by 10CFR50.54(q) & 50.4 ML20199K6771999-01-14014 January 1999 Provides Notification of Planned ERDS Software Change Scheduled to Take Place on 990215 ML20199D8811999-01-11011 January 1999 Submits Response to SE JOG Program on Periodic Verification of motor-operated Valves,In Response to GL 96-05 ML20199D9521999-01-0808 January 1999 Informs That CE Cresap,License SOP-4220-4,has Been Permanently Reassigned from Position Requiring License & No Longer Has Need for License,Per 10CFR50.74 ML20199A6081999-01-0606 January 1999 Submits List of Plant Info Brochures Disseminated Annually to Public & List of Updated State &/Or Local Emergency Plan Info,Per NRC Administrative Ltr 94-07, Distribution of Site-Specific & State Emergency Planning Info ML20202B7531998-12-21021 December 1998 Submits Ltr Confirming Discussion with J Tapia,Documenting Extension for Response to NOV 50-416/98-13.Util Response Will Be Submitted by 990212 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARAECM-90-0169, Forwards Operator Licensing Natl Exam Schedule for FY91 Through FY94,per Generic Ltr 90-071990-09-17017 September 1990 Forwards Operator Licensing Natl Exam Schedule for FY91 Through FY94,per Generic Ltr 90-07 AECM-90-0172, Forwards Endorsement 67 to Nelia Policy NF-257 & Endorsement 46 to Maelu Policy MF-1061990-09-17017 September 1990 Forwards Endorsement 67 to Nelia Policy NF-257 & Endorsement 46 to Maelu Policy MF-106 AECM-90-0174, Forwards List of Submittals Pending NRR Review Re Grand Gulf Licensing Activities1990-09-14014 September 1990 Forwards List of Submittals Pending NRR Review Re Grand Gulf Licensing Activities AECM-90-0165, Forwards Addl Info on NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount1990-09-12012 September 1990 Forwards Addl Info on NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount AECM-90-0158, Forwards Quarterly Status Rept for Reg Guide 1.97 Re Neutron Monitoring Sys for Period Ending 900630.Rept Includes Major Actions Completed to Date for Unit ex-core Sys.Estimated Milestone Schedule for Activities Also Encl1990-09-0808 September 1990 Forwards Quarterly Status Rept for Reg Guide 1.97 Re Neutron Monitoring Sys for Period Ending 900630.Rept Includes Major Actions Completed to Date for Unit ex-core Sys.Estimated Milestone Schedule for Activities Also Encl AECM-90-0163, Forwards Endorsement 61 to Nelia Policy NF-257,Endorsement 40 to Maelu Policy MF-106,Endorsement 62 to Nelia Policy NF-257,Endorsement 41 to Maelu Policy MF-106 & Endorsement 63 to Nelia Policy NF-2571990-09-0606 September 1990 Forwards Endorsement 61 to Nelia Policy NF-257,Endorsement 40 to Maelu Policy MF-106,Endorsement 62 to Nelia Policy NF-257,Endorsement 41 to Maelu Policy MF-106 & Endorsement 63 to Nelia Policy NF-257 AECM-90-0161, Forwards Quarterly Status Rept Re Degraded Core Accident Hydrogen Control Program, for Apr-June 19901990-08-30030 August 1990 Forwards Quarterly Status Rept Re Degraded Core Accident Hydrogen Control Program, for Apr-June 1990 AECM-90-0149, Forwards Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Rev 3 to Process Control Program1990-08-30030 August 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Rev 3 to Process Control Program AECM-90-0162, Forwards fitness-for-duty 6-month Rept for Period Ending June 1990,per 10CFR26.Success of Program Evident in Statistical Data Indicating Extremely Low Incident Rate1990-08-29029 August 1990 Forwards fitness-for-duty 6-month Rept for Period Ending June 1990,per 10CFR26.Success of Program Evident in Statistical Data Indicating Extremely Low Incident Rate ML20028G8591990-08-27027 August 1990 Forwards Updated Svc List to Be Used for Licensee Correspondence.Requests That Author Be Primary Addressee for All Correspondence Re Plant AECM-90-0144, Forwards Security Boundary Upgrade Bimonthly Status Rept for Period Ending 900731,per 900330 Commitment.Rept Covering Period 900801-0930 Will Be Submitted in Oct 19901990-08-22022 August 1990 Forwards Security Boundary Upgrade Bimonthly Status Rept for Period Ending 900731,per 900330 Commitment.Rept Covering Period 900801-0930 Will Be Submitted in Oct 1990 ML20056B3511990-08-20020 August 1990 Suppls Info Re 900806 Application for Amend to License NPF-29,changing Tech Specs on Alternate DHR Sys,Per NRC Comments.Proposed Tech Spec 3/4.5.2 Encl AECM-90-0147, Informs That Annual Emergency Preparedness Exercise for Facility Scheduled for Wk of 9108261990-08-14014 August 1990 Informs That Annual Emergency Preparedness Exercise for Facility Scheduled for Wk of 910826 AECM-90-0142, Forwards Supplemental Info Re 900705 Application for Amend to License NPF-29,revising Tech Specs Due to Addition of Alternate DHR Sys1990-08-0909 August 1990 Forwards Supplemental Info Re 900705 Application for Amend to License NPF-29,revising Tech Specs Due to Addition of Alternate DHR Sys AECM-90-0143, Notifies That Cd Bland No Longer Employed by Util,Effective 9007191990-08-0202 August 1990 Notifies That Cd Bland No Longer Employed by Util,Effective 900719 AECM-90-0139, Forwards Endorsement 68 to Nelia Policy NF-257,Endorsement 47 to Maelu Policy MF-106 & Revised Endorsement 35 to Maelu Policy MF-1061990-08-0202 August 1990 Forwards Endorsement 68 to Nelia Policy NF-257,Endorsement 47 to Maelu Policy MF-106 & Revised Endorsement 35 to Maelu Policy MF-106 ML20055J0551990-07-27027 July 1990 Forwards Summary of Environ Protection Program Re Const of Unit for 6-months Ending 900630,per Exhibit 2-A in Subsection 3.E.1 of CPPR-119 AECM-90-0136, Forwards Executed Amend 4 to Indemnity Agreement B-72,per NRC 891214 Request1990-07-27027 July 1990 Forwards Executed Amend 4 to Indemnity Agreement B-72,per NRC 891214 Request AECM-90-0130, Forwards Corrected Pages to Rev 17 to Physical Security Plan.Pages Withheld (Ref 10CFR73.21)1990-07-17017 July 1990 Forwards Corrected Pages to Rev 17 to Physical Security Plan.Pages Withheld (Ref 10CFR73.21) ML20044A9251990-07-0909 July 1990 Forwards Rev 1 to Relief Request I-00018 Correcting Valve Number & Description of One Component.Review & Approval Requested Prior to 901001 ML20044A7861990-06-29029 June 1990 Responds to NRC 900601 Ltr Re Violations Noted in Insp Rept 50-416/90-08.Corrective Actions:Operations Superintendent Counseled Individuals Re Inoperable Reactor Water Level Transmitter & Met W/All Shift Senior Reactor Operators AECM-90-0121, Withdraws 880831 & 890324 Proposed Amends,Deleting Certain Test,Vent & Drain Valves from Tech Spec Table 3.6.4-11990-06-27027 June 1990 Withdraws 880831 & 890324 Proposed Amends,Deleting Certain Test,Vent & Drain Valves from Tech Spec Table 3.6.4-1 AECM-90-0115, Forwards List of Followup Actions as Result of NRC Requalification Reexam of Three Licensed Operators on 900531.Lessons Learned Guideline Will Be Prepared Re Ability of Training Personnel to Evaluate Simulator Crew1990-06-26026 June 1990 Forwards List of Followup Actions as Result of NRC Requalification Reexam of Three Licensed Operators on 900531.Lessons Learned Guideline Will Be Prepared Re Ability of Training Personnel to Evaluate Simulator Crew ML20044A2931990-06-22022 June 1990 Responds to NRC Request for Addl Info Re Boraflex Gap Analysis.If Vibratory Ground Motion Exceeding OBE Occurs,Per 10CFR100,App a & as Previously Committed,Plant Will Be Shut Down.Listed Addl Surveillance Will Be Performed ML20043G6231990-06-14014 June 1990 Forwards Evidence That Cash Flow Would Be Available for Payment of Deferred Premium Obligation for Facility.Sys Energy Resources,Inc Responsible for Generating 90% of Required Cash Flow ML20043G3341990-06-11011 June 1990 Forwards Rev 9 to GGNS-TOP-1A, Operational QA Manual, for Evaluation ML20043G5861990-06-0808 June 1990 Forwards Bimonthly Status Repts Re Security Boundary Upgrade Project for Period Ending 900531 ML20043F5121990-06-0808 June 1990 Forwards List of Directors & Officers of Entergy Operations, Inc.Operation of All Plants Transferred to Entergy on 900606 ML20043E8011990-06-0707 June 1990 Forwards Nonproprietary ANF-90-060(NP), Criticality Safety Analysis for Grand Gulf Fuel Storage Racks W/ANF-1.4 Fuel Assemblies. ML20043E7831990-06-0707 June 1990 Forwards Updated Svc List to Be Used Re Plant Correspondence.Requests WT Cottle Be Primary Addressee for All Correspondence Concerning Plant ML20043E8161990-06-0606 June 1990 Informs That Sys Energy Resources,Inc Received Necessary Regulatory Approvals to Transfer Performance Activities for Facility to Entergy Operations & All Conditions in Amend 9 to CP CPPR-119 Implemented,Effective on 900606 ML20043F2061990-06-0606 June 1990 Forwards 1989 Annual Financial Repts for Sys Energy Resources,Inc & South Mississippi Electric Power Assoc ML20043E8111990-06-0606 June 1990 Informs That Sys Energy Resources,Inc Received Necessary Regulatory Approvals to Transfer Operating Responsibility for Facility to Entergy Operations & All Conditions in Amend 65 to License NPF-29 Implemented,Effective on 900606 ML20043C8611990-05-31031 May 1990 Forwards Preliminary Drafts of Plant Specific Tech Specs in Order to Facilitate NRC Validation of BWR Owners Group Improved Tech Specs,Per NRC Request.Understands That Util & NRC Will Meet During Wk of 900716 to Discuss NRC Review ML20043B6811990-05-24024 May 1990 Forwards Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Jan-Mar 1990 ML20043B6021990-05-23023 May 1990 Confirms NRC Understanding That Safety Evaluation Will Be Written for Use of New Tech Spec 3.0.4 Flexibility Regardless of Plant Condition at Time Flexibility Required ML20043B2471990-05-18018 May 1990 Forwards Final Response to Generic Ltr 89-04, Guidance on Developing Acceptable Inservice Testing Programs & Rev 4 to Pump & Valve Inservice Testing Program. ML20043A9651990-05-17017 May 1990 Forwards Draft Tech Specs for Power Distribution Limits,Rcs, ECCS & Plant Sys as Part of Util Involvement W/Bwr Owners Group as BWR-6 Lead Plant ML20042G6931990-05-0909 May 1990 Forwards Rev 4 to Fire Hazards Analysis. Design Changes Include Installation of Alternate DHR Sys & Access Hatch in Pipe Chase ML20042G8681990-05-0909 May 1990 Forwards Response to Recommendations Re Areas of Concern Noted in NRC SER Dtd 900316 & 900316 Request for Addl Info Re Design Criteria for Cable Tray Supports in Turbine Bldg ML20042G6731990-05-0909 May 1990 Notifies of Cancellation of Emergency Plan Procedure 10-S-01-13, Onsite Radiological Monitoring. Info Incorporated Into Procedure 10-S-01-14,Rev 13, Radiological Monitoring. ML20042F4891990-05-0404 May 1990 Requests Extension of 90 Days to Provide Addl Time for Securities & Exchange Commission Review Re Implementation of Amend 65 to License NPF-29 ML20042F4441990-05-0404 May 1990 Forwards Response to Generic Ltr 89-19 Re USI A-47, Safety Implications of Control Sys in LWR Nuclear Power Plants. Plant Has Adequate Automatic Reactor Vessel Overfill Protection,Procedures & Tech Specs ML20042F1791990-04-30030 April 1990 Responds to NRC 900402 Ltr Re Violations Noted in Insp Rept 50-416/90-03.Corrective Actions:Valves Closed,Effectively Isolating Flow of Contaminated Water Into Makeup Water Sys & Demineralized Water Sys Flushed & Cleaned of Contamination ML20042F1811990-04-30030 April 1990 Responds to Generic Ltr 89-15, Emergency Response Data Sys. Util Volunteers to Participate in Emergency Response Data Sys ML20042F3711990-04-30030 April 1990 Forwards Certificate of Insurance for Nuclear Property Insurance Submitted by Nuclear Mutual Ltd for Policy Period 900401-910401 & Certificate of Insurance Evidencing Increased Excess Property Insurance,Per 900330 Ltr ML20042F1751990-04-30030 April 1990 Advises That Util Will Not Be Able to Provide Complete Supplemental Summary Rept on Dcrdr by 900430,as Indicated in Util 891221 Ltr.Supplemental Rept Will Be Submitted by 900930 ML20012F3311990-04-0202 April 1990 Forwards GE Affidavit Requesting That All Drawings Presently Denoted as Proprietary in Rev 4 to Updated FSAR Re Offgas Sys Should Remain Proprietary (Ref 10CFR2.790) ML20012E2961990-03-26026 March 1990 Forwards Updated Svc List for NRC Correspondence to Util. Facility Fee Bills Sent to Wrong Primary Addressee ML20011F2171990-02-23023 February 1990 Responds to NRC 900131 Ltr Re Violations Noted in Insp Rept 50-416/89-30.Corrective Actions:Quality Deficiency Rept Initiated to Document & Resolve Incident & Incident Rept & Reportable Events Procedure Enhanced 1990-09-08
[Table view] |
Text
,
., l i y-% -c.O t.3 J, aarg MISSISSIPPI POWER & LIGHT COMPANY A A Helping Build Mississippi P. O. B O X 16 4 0, J A C K S O N MI S SIS S I P PI 39205
- $,*$rTTN,%f February 20, 1981 Office of Inspection & Enforcement U. S. Nuclea- Regulatory Cecmission Region II 101 Marietta Street, N.W.
Suite. 3100 Atlanta, Georgia 30303 Attention: Mr. J. P. O'Reilly, Director Dear Mr. O'
$ . Q. .
SUBJECT:
Grand Gulf Nuclear Station
.c '
gj Rm( f il(M
,\y/ Nc) g Units 1 and 2 Docket Nos. 50-416/417
_! u File 0260/15525/15526
-j ': 2 0 :21981 - b RII:DKW 50-416/79-15 and
50-417/79-15 cf u.s. '=".scuuren58
- IE Inspection Report of D
/Q.1 7/24-8/24/79
\
AECM-81/59 if; A l j n u
References:
- 1) MAEC-79/158, 10/18/80 (IE Inspection Report)
- 2) AECM-79/127, 11/12/79
- 3) AECM-80/20, 1/15/80
- 4) AECM-80/241, 9/30/80 Mississippi Power p.,,T,ight Company received a Notice of Viola-tion as Appendix A to your letter dated October 18, 1979 which transmitted IE Inspection Report 79-15. One item of noncompli-ance, nine unresolved items, and one inspector follow-up item were identified in the report.
Mississippi Power & Light has responded to the Notice of Vio-lation in Refere: ces 2, 3, & 4 listed above. Our final response is contained in Attachment A to this letter.
Although we have not previously submitted written responses to " unresolved items" or " inspector follow-up items", Attachment "B" provides responses to those items outlined in the subject inspec-tion report. We elect to provide this information due to its rele-vence to the Attachment A response to the Notice of Violation.
A draft response was discussed with your Mr. Tom Conlon on 30/7 February 5 and 10, 1981. At that time it was agreed to delay this .5 response until February 20, 1981.
//
8103030l87 .
M ember Middle South Utilities System .
O 1
- y. . . . _ _ _ _. _ _ _ _ . _
~
[ MISSISSIPPI POWER & LIGHT COMPANY Mr. J. P. O'Reilly AECM-81/59 NRC Page 2 4
Additional information may be found in our Final Report on our Potentially Reportable Deficiency (PRD)-79/04, letter number AECI-81/80, dated February 20, 1981.
Yours truly, i
p g J. P. McGaughy, Jr.
EWC:mt Attachment ,
cc: Mr. N. L. Stampley
-l Mr. R. B. McGehee Mr. T. B. Conner 1
Mr. Victor Stello, Director Division of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. G. B. Taylor
, South Miss. Electric Power Association P. O. Box 1589 Hattiesburg, MS 39401 re e k *
- . - - - - y , ._, , -.
9-
Attachment A to AECM-81/59 Page 1 of 2 RESPONSE TO VIOLATION NUMBER 416/79-15-09 AND 417/79-15-09 " FAILURE TO MEET MIL-SPEC REQUIREMENTS" I. Corrective Steps Taken And Results Achieved Mississippi Power & Light acknowledges that at the time of the inspection, July 24 through August 24, 1979, there were inade-quate tests available to confirm the adequacy of pull test values in use. The deficiency, of inadequate pin crimping in certain Power Generation Control Complex (PGCC) interconnecting cables, was originally discovered and reported as a Potentially Reportable Deficiency to your office February 23, 1979 A com-prehensiva inspection to determine extent and correct deficien-cies discovered was underway at the time of the NRC inspection.
As discussed in item 2.d., pages 9 and 10 of the inspection report, the acceptance values of 15 pounds for 16 AWG wire and 8 pounds for 20 AWG wire were utilized for the inspection in progress. Preliminary tests performed by the General Electric Co. had indicated, with a high cor.fidence level, the adequacy of the pull values utilized.
Meetings were conducted on November 16, 1979, with the Regula-tory Staff and on Fe$r~u'ary 14, 1980, with'the Region II staff.
As identified in those meetings, an addendum to the General Electric Co. NEDO 10466A was prepared to remove any ambiguities regarding connector requirements. In a letter dated January 10, 1980 from E. P. Stroupe of GE to 0. D. Parr of the NRC, Errata and Addenda sheets applicable to NEDO 10466A were submitted for NRC approval. If this " Errata and Addenda" is approved, MP&L will review our FSAR requirements to determine if incorporation is necessary.
In July, 1980, CE completed extensive tests to demonstrate the qualification of PGCC caole/ connectors and panel connectors to the full requirements of IEEE 323-1974 and 344-1975. The results of this qualification testing also clearly demonstrated the
j .
Attachmsnt A to AECM-81/59 .
- - Page 2 of 2 adequacy of the eight (8) and fifteen (15) pound pull force / '
-crimp strength values applied at the Grand Gulf jobsite for l pull testing of 20 AWG and 16 AWG wire size crimps respectively. .
t f
The combination of actions:
(1) the confirmation of eight and 15 pound pull force values by tests conducted by GE per 10CFR50, Appendix B
.j(2) the demonstration of qualification of PGCC cables / connectors
! to the full requirements of IEEE 323-1974 and IEEE 344-1975 should serve to close out the infraction. The Qualification Test records are available for examination at General Electric at San Jose, with a copy of the test report available at the I CGNS jobsite.
. II. ~ Corrective Steps Taken To Avoid Further Noncompliance Since GE has qualified their pull. test values, no additional 4
- actions are required.
j III. Date When Full Compliance Will Be Achieved Full compliance has been achieved.
1 t'
I p
hPM" 1
4 1
I m
i
.. - - _ . . . . - . - , . ._. .4_ . . _ _ - . _ _ . ,, .- . . ,, . , , . _ . , _ , , - , . , , , , _ , _ . . _ , . . , . . . - . _ . - -
Attachment B to AECM-81/59
- Page 1 of 11 ATTACHMENT 'T' UNRESOLVED ITEMS i
INTRODUCTION r j The NRC IE Inspection Report officially notified Mississippi Power &
J Light Company of eight (8) Unresolved Items and (3) one NRC Inspec-
! tor follow-up item as follows: I
- 1. Unresolved items 416/79-15-01 and 417/79-15-01, Aging effects on electrical properties of low force pin crimps. '
- 2. Unresolved items 416/79-15-02 and 417/79-15-02, Aging effects i
on conductor insulation.
- 3. Unresolved items 416/79-15-03 and 417/79-15-03, Aging effects on connector clamp strength.
- 4. Unresolved items 416/79-15-04 and 417/79-15-04, Shield wires not pull tested.
- 5. Unresolved items 416/79-15-05 and 417/79-15-05, Environmental effects on hipot test results.
- 6. Unresolved items 416/79-15-06 and 417/79-15-06, Broken wire strands inside pin barrel.
- 7. Unresolved items 416/79-15-07 and 417/79-15-07, Evaluation of cable outer jacket damage.
- 8. Unresolved items 416/79-15-08 and 417/79-15-08, Rework of cable failing continuity check.
- 9. Infractions 416/79-15-09 and 417/79-15-09, Failure to meet 4
Mil-spec requirements. (Covered in -Attachment A)
- 10. Inspection follow-up items 416/79-15-10 and 417/79-15-10, Failure to meet ANSI N45.2 requirements.
UNRESOLVED ITEMS 01 THROUGH 08 General Electric completed tests in July 1980, to demonstrate qualifi-cation or PGCC cables / connectors and panel connectors to full require-
! ments of IEEE 323-1974 and 344-1975.
The purpose of the qualification tests was to obtain data that pro-l vides reasonable assurance that the installed PGCC cable assemblies l will perform their safety related functions. The testing included PCCC cable assembly test samples which were fabricated to simulate observed and postulated pin crimping anomalies as well as normal manufactured product. The environmental parameters for testing (temperature, humidity and seismic) enveloped the environmental i
l
Attachm:nt B to AECM-81/59 Page 2 of 11 parameters specified for the BWR 4, 5, and 6 control room normal and abnormal environmental limits. The tests were conducted in the following sequence:
Assembly and Inspection Baseline Functional Testit.g-Accelerated Thermal Aging Post-Aging Functional Testing Seismic Vibration Aging and DBE ' Exposure Post-Seismic Functional Testing Environmental Functional Testing Destructive Testing Test Data Reduction and Analysis The Qualification Test records are available for examinatior. st General Electric.
The test results, as applicable to the Unresolved Items of the NRC IE Inspection Report, are included below.
- 1. UNRESOLVED ITEM 01, EFFECT OF AGING ON LOW MECHANICAL FORCE CRLaPS A low force crimp is defined by General Electric to be less than 15 pounds pull strength for 16 AWG wire and lest than 8 pounds for 20 AWG wire.
u.. -
To create low force crimps for testing, General Electric measured the relationship of crimp depth to crimp strength - a shallow or light crimp would yield a low strength crimp, a deep or heavy crimp would yield a high strength crimp. In the preparation of test samples, proper operation of calibrated crimping tooling yielded crimps normally above the 20 pound range for 20 AWG wire and above the 40 pound range for 16 AWG wire. By upsetting the
~
crimping process and tooling, it was possible to create crimps down to the 1-2 pound range, but not reproducibly with high yield.
In the Qualification Test Program, two of the objectives were: ;
- a. Dete ___._ _..._ .....w or accelerated thermal aging on low l
! force crimps.
l l
l 1
- - - - ~ . . .. . . -. -- - _ - -. . ._
~
Attachment B to AECM-81/59 '
Page 3 of 11 l b. Confirm the adequacy of 8 and 15 pound pull force values.
For these two objectives, twenty-four (24) connector assembly i test samples were produced - 16 with 16 AWG wire crimped to 16 AWG contact pins (300 pins total) and 8 with 20 AWG wire crimped to 16 AWG contact pins (300 pins total). The 24 test samples, designated N,-3, 12, 13, Nb -1 through 6, Nd+ c 1 through 6, -
- N -1, N +N -1 & 2, N -1 & 2, N -1&2 and N -1&2 were subjected e f c n. o p to accelerated thermal aging and then tested (each pin) for i
insulation resistance and hipot. Eleven (11) of the samples were then sequenced through seismic and environmental conditions of test, again with insulation resistance and hipot measurement I i
i
! on each pin after each set of qualification test conditions.
Finally, the 24 test samples were destructively tested. The de-structive crimp pull testing showed that 7% of the crimps were low force (600 pins total - 500 pull tested - 35 low force -
35/500 = 7%).
Test results show that, specifically, the low force crimped i
pins were not affected by any of the conditions of accelerated thermal aging, seismic and environmental testing. Analysis of 4 destructive crimp pull testing data also confirms the adequacy of the 8 and 15 pound.xalues for field testing.
4 2. UNRESOLVED ITEM 02, THE EFFECT OF AGING ON THE INSULATION PRO-PERTIES OF NICKED AND/OR CUT INSUIATION PGCC cable assembly test samples were altered to contain damaged insulation and cut wire strands within the crimped pin barrel.
The insulation of 182 conductors was damaged by cutcing through 50% of the insulation thickness of 50% (91 conductors) of the samples and 25% of the insulation thickness on the remaining 50%. The conductors were positioned so that the cuts faced ,
each other. . These test samples, designated Nd + N , were as-sembled in this manner for testing to determine the effect of
- aging on nicked, gouged or cut insulation.
i l
- .
- -c., ,g.. ., --- e. g. 7 ..-e --+e- ,
.- . - ~ _ - - . - - . . - -. . - _ . . - . - . - . - - . . .. - . . - - . _ . _ . - - - - _
I ' Attachment B to AECM-81/59 F
Page 4 of 11 i Insulation Conductors ,
- Sample Connector Mfr. Contacts Material No. AWG (
t N+
d c -1&2 Cannon Cannon Raychem 37 16
[
N N~
d e """ " """ " "'** '
i N+ -566 Amphenol Amphenol Tefzel 44 20 [
d c N +N -768 Amphenol Amphenol Vulkene 8 16 d c ;
$ Additional test samples were configured with damaged i sulation ,
only. These test samples, designated N -1 and 2, were altered x ,
i to contain damaged insulation similar to that described for [
samples N +N ' i d c Insulation Conductors Sample Connector Mfr. Contacts Material No. AWG N -1 Amphenol Amphenol Tefzel 8 16 x
Ng -2 Amphenol Amphenol Vulkene 8 16 f Each test sample was hipot tested to 2200 Vac prior to quali-i fication testing. Each sample was hipot tested at 1760 Vac before and after each test sequence following thermal aging.
1 All test samples were subjected to accelerated thermal aging, 1.
j seismic and abnormal environmental conditions. No failures
- l. occurred. Test sample Nd+N c 2,4,6 and 7 were subjected to thermal aging, seismic, and abnormal environmental conditions. No '
'" " ~ ~ '
failures occurred. ~
Test sample N -1 was subjected to a hipot test of 2200 Vac and thermally aged without failure of the insulation and no visual
] evidence of damage propagation. Test sample N -2 was subjected to the same tests as N -1 and additionally to seismic and ab-normal environmental conditions, without failure of the conductor
)
insulation and no visual evidence of damage propagation. .
I i
Two test samples, N -1 and 2, of PGCC cable assemblies were p .
l altered with insulation damage to expose bare wire and assembled i with the defects face to face. One pin of 10 per sample failed 1
hipot testing. This result could be expected with uninsulated conductors in close proximity.
e
-- y e r,., , - - + , . - , -%-.% , ,r--.y .-r-,.--. ..r-...r--,<w---we-,-m., m--w-c-.m.- ,n,ve,-
Attachmsnt B to AECM-81/59 Page 5 of 11 >
The revised General Electric PCCC inspection procedure accepts cable 2
insulation that is nicked, gouged or cut unless bare wire is exposed.
The PGCC cable qualification test results demonstrate, with reasonable assurance, that there is no effect of aging on nicked and/or cut in-sulation.
- 3. _UNPESOLVED ITEM 03, AGING EFFECTS ON CONNECTOR CLAMP STRENGTH The test data for low mechanical strength crimps indicate that a crimp atrength as low as approximately 2 pounds with the connector clamp tightened
? onto the cable will maintain electrical integrity over th'e qualified life of the cable. No crimp separation caused by either cable clamp loosening or crimp failure was observed. Normally, Power General Control Complex
- cabies are secured to support structures (wire grills or brackets) in the' panels and cabinets which provide further cable support and reduced strain on the cable that is in contact with the clamp. Therefore, the
- clamp does not normally support the entire cable weight. Seismic testing on aged cables, showed that the cable clamps performed their intended function, f 4. UNRESOLVED ITEM 04, SHIELD WIRES NOT PULL TESTED
! Shielding on cables is not critical except for sensitive neutron monitoring
- instruments where separate routing and conduits are required. In general, shielding is preventive rather than demonstrative 1y required.
~
Over the years, General Electric has found that plants have very different noise characteristics depending on the location and layout of equipment, f wiring and ground systems. Since there are " noisy" plants and " quiet"
~ '
e plants (and all gradationA in between) Gene'ral Electric has taken the 1
action to call for shielding and for the use of twisted pairs whenever low-level signals are involved. Should a shield not be connected, the twisting of the twisted pair will suffice in most cases. The twisting of the twisted, shielded pairs provide the majority of the protection from in-ductive pickup of noise, with the shields providing excess margin. Since I many PGCC cables are multiple, twisted shield pairs which are then twisted into a cable, loss of a shield connection on one or more f 3 he pairs would not cause function failures. In addition to the natural impedance, j the shielding effect of the adjacent pairs with their shields. grounded would aid in excluding noise. In the " noisy" plant, a disconnected shield f
! may result in unsatisfactory system performance. The condition will be i
readily apparent during pre-op and startup testing and can be easily l found and corrected, I
I
d 8, '
Attachm:nt B to AECM-81/59 Page 6 of 11 ,
There are two systems supplied by General Ilectric which must have shield integrity - the Neutron Monitoring System (NMS) and the Process Radiation Monitoring System (the Main Steamline Radiation Monitor). For both systems the connectors involved are not the multipin (MIL-C-5015 type) connectors which were of concern in the NRC Inspection (Infraction and Unresolved Items). For the Neutron Monitoring System a three-pin, connector is used and the shield carries the signal return so that an open shield results in a downscale reading and alarm. For the Process Radiation Monitoring System, the connector is coaxial type with completely different assembly methods from the crimp poke-home type.
The great majority of the shielding used by General Electric in PGCC (and non-PCCC) is preventive and called for as sound engineering practice rather than as a requirement for safety.
The pull testing of shield wires is not necessary to assure safe operation.
Since multi-conductor connectors have numerous shields, the loss of an individual shield is not apt to be detrimental to the performance of the circuitry. The cable which was of concern contained three shields that were off in a 48 pin con-
~
nector. The three shfeld wires which'd'e're off will not affect the function of the circuitry.
- 5. UNRESOLVED ITEM 05, ENVIRONMENTAL EFFECTS OF HIPOT TESTING Hipot tests for all assemblies at the factory and at site are performed in ambient temperature and humidity. These tests i are a quality search for workmanship problems (which could l
I cause electrical faults) which are not readily identifiable
by inspection or other means. Stray strands, wires scraped over sharp edges within assemblies, etc. can be (and are) un-covered by impressing a high voltage on otherwise floating-from-ground conductors. The voltage chosen is sufficiently higher i than the operating voltages to assure proper function of the
% -7
~ . . .
Attachmtnt B'to AECM-81/59
- Page 7 of.11 .
circuits, but low and brief enough so no damage is caused.
These tests are not tests of the materials or components but are for.Q.C. purposes only. The individual materials and com-ponents have all previously been tested and qualified for their application.
To date, there is no evidence that any hipot failure hAs been caused'by high or low humidity. In the operational condition, no. failures are expected from high or low humidity since the operating and accident environments are well within the limits of the wire, cable and connectors.
The concern for the effect of dense smoke environment on hipot test results can be satisfied for the following reasons:
- 1. The ability of the crimps to meet or not meet a destructive pull test will not be affected by smoke in the atmosphere.
Nor will there be any effect on hipot testing for nicks /
cuts in insulation. Smoke is not a significant conductor and the location of the nicks / cuts of concern are within the connector housing, away from the air currents that would transport the smoke.
w.s- . .
- 2. The function of the crimp, to provide electrical continuity, will not be adversely affected by smoke in the atmosphere.
The conductivity is determined by the contact area.
- 3. Any connector, with or without crimp problems or nicked / cut insulation, may have leakage paths generated by smoke depost-tion but the PGCC connectors will be least affected due to the protection afforded by the insert and connector shell.
- 4. Neither IEEE 323-1974 nor NUREG 0588 require consideration of smoke as an environmental agent. This is undoubtedly due to the major effort in the past few years on fire protection and separation. If there was such a requirement, other devices would be far more susceptible than covered connectors. The PCCC is in compliance with NRC fire prevention .
! and protection requirements.
4 Attachment B to AECM-81/59 Page 8 of 11
- 6. UNRESOLVED ITEM 06, WIll STRANDS BROKEN IN CONNECTOR BARREL ON ONE CONDUCTOR OF CABLE 5551/SZ51-006 Except for the thermocouple extension cables, all functional conductors are stranded with 7 or 19 strands. This is for flexibility and to assure that if some damage causes broken strands, other strands can continue to function. None of the 16 AWG or 20 AWG conductors carry anywhere near rated' current as evidenced by the lack of significant temperature rise in the cables. Loss of several strands at any point along the conductor causes an insignificant increase in resi tance (loss is proportional to resistance). Also, since the thermal con-ductivity of the copper on both sides of the broken strands is good, increased resistance from higher temperature is minimal (resistance, hence loss, is proportional to temperature).
Cable inspection experience for this defect indicates that wire strands are normally not cut through, as noted on the referenced cable. What sometimes happened was that the wire stripper nicks one or more outer wire strands during cable fabrication.
When the electrician examined the wire for this characteristic he would bend the pin back and forth. Nicked strands often break when this is done. There is no flexing at this point when the hemostat issused for the pull-test.
A spot check of 50 16-AWG and 50 20-AWG GGI cable data sheets (2752 conductors total) indicated six " nicked wires." There was no indication of any broken or missing strands.
In the General Electric PGCC Cable / Connector Qualification Test program, test samples N +
I d c were altered to simulate broken wire strands within a crimp connection. The test samples' vere altered by cutting away 10% of the conductor strands of 50% of the samples and 25% of the conductor strands in the remaining 50%. The cut strands were removed so that the crimp contained l approximately 90% of the normal volume of conductor strands of one sample and approximately 75% of the volume of the other sample. This condition automatically creates low mechanical
-- .m+, y
~
Attachment B to AECM-81/59 Page 9 of 11 i
strength crimps because a normal manufactured crimp was applied assuming a normal volume of conductor strands. All 182 conduc-tors, 91 with 10% cut-strands and 91 with 25% cut strands, were ,
- subjected to accelerated thermal aging, seismic and the abnormal .
environmental conditions, without alteration of the electrical properties and integrity of the low mechanical strength crimps.
M In summary, broken strands, even as many as 25%, cause no func-tional impairment in any control or insttumentation wire. At the worst, broken strands are a worksmanship fault.
- 7. UNRESOLVED ITEM 07, EVALUATION OF CABLE OUTER JACKET DAMAGE ON 4 CABLE 8347/SP-64/006 The purpose of the jacket is to provide protection to the pri-mary conductors and their insulation during the life and use of the cable and scrapes, cuts and tears in the jacket demon-I strate the jacket is functioning as designed. The decision to repair or not repair the damage or replace the cable can be made based on the seriousness of the damage, the environment and location of the damaged area on the installed cable, and the continued need for this additional protection for the primary conductor.
i r
With regard to cable 8347/SP64-006,
- u. . -
the, actual damage was a one-fourth inch circumferential jacket cut 2.5 feet from the .
cable end. This is within the scope of the cable reinspection plan. The cable was repaired with Insultape as required.
The five foot limitation in the cable inspection plan for a damaged outer jacket was established because that is a length I
that would normally be accessible during this inspection. Cables
, are 100% inspected full length for this characteristic after factory PGCC system test, immediately prior to shipment to the
- site. The check at the site of accessible portions of cables 4 was added to obtain an indication of installation damage. The I amount of such observed damage has been minimal.
s
.. . - ._ , _ _ , _ _. - _ . . - , _ , _ . - , _ . - _ . _ , _ _ - . _ . _ . ,..,,.__,.-r... - - , _ _ . . . . . . _
Attachment E to AECM-81/59 Page 10 of 11
- 8. UNRESOLVED ITEM 08, REWORK OF CABLE FAILING CONTINUITY CHECK Wire pairs 4 and 5 of cable 8248-SV41-001 were reported to have failed a continuity check and the cable was returned for rework. The pairs had been cut and taped back, and the pre-vious inspection sheets were not in the data folder. The cable was reported to have been QC inspected and accepted prior to its failure of the continuity check. This could not be con-firmed as the original inspection sheet was not found.
The cutting and taping of the conductors was an error by an electrician. Cutting and taping would have been an acceptable disposition to a nonconformance where unused conductors exist within a cable. In this case, there were no unused conductors.
The continuity check detected the error, as it should have, and a repair was indicated.
The first set of data sheets for this cable was misplaced or, for some reason, never turned in. Thus, it was necessary to initiate a new set of paper to cover rework and reinspection of the cable.
DiSPECTOR FOLLOWUP ITEM: FAILURE TO MEET ANSI N45.2 REOUIREMENTS Two deficiencies to ANSI 45.2 were not documented as of July 26, 1979: ... .
- 1. Flat head pins (identified on July 9, 1979)
- 2. Missing " spring" or " clip" on Amphenol connectors (identified July 18, 1979)
Flat head pins were identified cn a cable in July 1979. General Electric initiated FDDR JB1-768 on July 26, 1979 to establish cri-teria for flat head pins and institute 100% inspection and repair for the condition. Inspection of 21,340 pins resulted in finding 35 flat head pins. The low frequency of occurrence was judged to be sufficient positive evidence to halt further inspection for a condition which was not significant to the function of the component in the circuitry.
i Attachmene B to AECM-81/59 Page 11 of 11 Concerning missing "J" springs in Amphenol connectors, General
- Electric initiated FDDR JB1-768 on July 26, 1979, calling for 1007.
inspection and repair for the condition.
In response to the MP&L Corrective Action Report (CAR) No. 231, which identified and tracked this concern, appropriate cha;nges were made to the GE I&SE QA Manual to assure deficiencies are pro-perly identified and corrected.
SUMMARY
- General Electric has successfully completed qualification testing of PGCC cables / connectors and panel connectors, similar to the installed PGCC equipment at GGNS, to the full requirements of IEEE 323-1974 and 344-1975. In its testing, General Electric simulated
the workmanship. anomalies of concern in the NRC IE Inspection Report Nos. 50-416/79-15 and 50-417/79-15. It has been demonstrated that
- j. test samples which included such anomalies do withstand conditions of 'ccelerated a aging, seismic and environmental testing without degradation of functional integrity.
l General Electric has implemented prudent and timely inspection and repair actions on delivered PGCC equipment at GGNS to assure the functional integrity and high quality of that product.
And, General Electric has taken appropriate action to clarify the intent of NED0-10466A regarding PGCC connectors by submitting Addenda
- 1 to the NRC.
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