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MONTHYEARAECM-84-0473, Forwards Response to Generic Ltr 84-15 Re Proposed Actions to Improve & Maintain Diesel Generator Reliability.Comments & Recommendation Encl1984-09-28028 September 1984 Forwards Response to Generic Ltr 84-15 Re Proposed Actions to Improve & Maintain Diesel Generator Reliability.Comments & Recommendation Encl Project stage: Other ML20195C9181986-05-22022 May 1986 Proposed Tech Specs,Changing Ac Electrical Power Sources Project stage: Other AECM-86-0157, Application for Proposed Amend PCOL-86/10 to License NPF-29, Changing Tech Specs Re Ac Electrical Sources in Response to Generic Ltr 84-15.Fee Paid1986-05-22022 May 1986 Application for Proposed Amend PCOL-86/10 to License NPF-29, Changing Tech Specs Re Ac Electrical Sources in Response to Generic Ltr 84-15.Fee Paid Project stage: Request ML20197B5151986-10-23023 October 1986 Safety Evaluation Accepting,In Part & Denying,In Part,Util 860522 Request for Tech Spec Changes Re Diesel Generator Testing,Per Generic Ltr 84-15 Project stage: Approval ML20197B4861986-10-23023 October 1986 Forwards Safety Evaluation of Util 860522 Request for Changes to Tech Specs Re Emergency Diesel Generator,Per Generic Ltr 84-15.Util Should Resubmit Request for License Amend to Address Unacceptable Changes Project stage: Approval ML20215C5221986-12-0909 December 1986 Proposed Tech Specs for Diesel Generator Testing,Allowed out-of-svc Time & Surveillance Requirements for Offsite & Onsite Ac Electrical Sources Project stage: Other AECM-86-0394, Forwards Application for Amend to License NPF-29,revising Tech Specs for Diesel Generator Testing,Allowed out-of-svc Time & Surveillance Requirements for Offsite & Onsite Ac Electrical Sources.Fee Paid1986-12-0909 December 1986 Forwards Application for Amend to License NPF-29,revising Tech Specs for Diesel Generator Testing,Allowed out-of-svc Time & Surveillance Requirements for Offsite & Onsite Ac Electrical Sources.Fee Paid Project stage: Request ML20209H1041987-01-29029 January 1987 Proposed Tech Spec Change to Table 4.8.1.1.2-1 Re Diesel Generator Test Schedule Project stage: Other AECM-87-0024, Amended Application for Amend to License NPF-29,originally Submitted on 860522 & 1209.Wording of Footnote to Tech Spec Table 4.8.1.1.2-1 Changed to Reflect Discussion W/Nrc1987-01-29029 January 1987 Amended Application for Amend to License NPF-29,originally Submitted on 860522 & 1209.Wording of Footnote to Tech Spec Table 4.8.1.1.2-1 Changed to Reflect Discussion W/Nrc Project stage: Request 1986-12-09
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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
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c- _~4 MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi P. O. B OX 164 0, J A C K S O N, MIS SIS SIP PI 3 9 2 05 September 28, 1984 b o.*EU[IS ., . r. ve m .
U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C. 20555 Attention: Mr. Harold R. Denton, Director
Dear Mr. Denton:
SUBJECT:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-13 File: 0290/L-800.0 Response to Generic Letter 84-15 AECM-84/0473 This letter provides the Mississippi Power & Light Company (MP&L) response to Generic Letter (GL) 84-15, dated July 2, 1984, pertaining to proposed staff actions to improve and maintain diesel generator (D/G) reliability. Attached to this letter is MP&L's response to each of the items addressed in GL-84-15, with respect to Grand Gulf Nuclear Station (GGNS)
Unit 1.
MP&L recognizes the significant safety benefit of maintaining high reliability of diesel generators at operating nuclear plants to mitigate the consequences of a loss of offsite power event. To realize this benefit, MP&L has developed a long term D/G maintenance testing program (attached) to maintain the high reliability experienced to date.
Also, included in the attached response are MP&L's comments /
recommendations on the proposed staff actions of GL-84-15.
Please contact this office if questions arise concerning this submittal.
Yours tr ,
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JBR:rg Attachments cc: See next page O ( g P i Member Middle South Utilities System
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AECM-84/0473 MISSISSIPPI POWER & LI2HT COMPANY #E' '
.cc: Mr. J. B.. Richard (w/a)
'Mr.'R. B. McGehee (w/o)
Mr. N. S. Reynolds -(w/o)
--Mr.'G.-B. Taylor (w/o)
Mr. Richard.C. DeYoung, Director (w/a)
Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington,.D. C. 20555 Mr. J. P. O'.Reilly, Regional Administrator (w/a)
U.S. Nuclear Regulatory Commission Region Il 101 Marietta St., N.W., Suite 2900 Atlanta, Georgia 30323
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BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE NO. NPF-13 DOCKET NO. 50-416 IN THE MATTER OF MISSISSIPPI POWER & LIGHT COMPANY
- and.
MIDDLE SOUTH ENERGY, INC.
and SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION AFFIRMATION I, J. B. Richard, being duly sworn, stated that I am. Senior Vice-President,. Nuclear of Mississippi Power & Light Company; that on behalf of Mississippi' Power & Light Company, Middle South Energy, Inc., and South Mississippi Electric Power Association I am authorized by. Mississippi Power &
_ Light' Company to sign and file with the Nuclear Regulatory Commission, this
. response to Generic Letter 84-15 for the Grtad~ Gulf Nuclear Station in
.accordance with 10CFR50.54(f); that I signed this submittal as Senior Vice
~
President, Nuclear of Mississippi Power & Light Company; and.that the statements made and the matters set forth'therein are true and ect to the best of my knowledge,-information and belief.
\
J. . Rithard p _ . STATE OF MISSISSIPPI COUNTY.0F HINDS SUBSCRIBED AND SWORN TO before me, a Notary Public, in and for the County and State above named, this - 2Pf4 day of .Nf,/%/f r" , 1984.
(SEAL) c'. ,
Notarypb1N My commission expires:
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Attachment to AECM-84/0473
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MP&L RESPONSE TO GENERIC LETTER 84-15 V
i1. .NRC1 REQUEST No.i1: ,
' Reduction in Number of Cold Fast Start Surveillance Tests for Diesel Generators This item -is directed towards reducing the number of cold fast start
+
, surveillance tests for diesel-generators which the staff has determined e .results-in' premature diesel engine degradation. Tne details relating to
~7 this subject'are provided in Enclosure 1. Licensees are requested-to rdescribe.their current programs:to avoid cold fast start surveillance
. testing or their-intended actions to reduce cold fast start surveillance-testing for diesel generators.
'MP&L RESPONSE:
- MP&L'has in place procedures which serve to reduce the number of cold fast
' starts experienced by the diesel generators (D/Gs) at the Grand Gulf
. Nuclear Station (GGNS). These procedures were developed based on recommendations by the-diesel manufacturers and include the fo11 swing
. practices:
(1). The engines are maintained in a warm condition with heated lube oil and jacket water circulating. . This keeps some of the -internal components lubricated and warm reducing-friction and thermal stresses during startup.
.(2) Prior.to each ' planned surveillance, the Division I and II. diesel
~
engines are air rolled to inspect for water accumulation in the
~
- cylinders. Drip systems have also been added to the lubrication systems of the turbochargers on Division I and 11 to maintain- the
' thrust bearings in a lubricated condition while the engines are'in-
. standby. . The Division I, II, and III diesel engines and turbochargers are prelubed prior to planned ' starts for surveillance-Etesting to ensure that'c itical' engine components are well lubricated.
J(3)~ The Division'III-diesel is also hand rolled and prelubed on a weekly-
' basis to' ensure that critical components are lubricated if an unplanned automatic start occurs and the independent air start nystems are tested'on a rotating basis to assure operability of each'
~
system.-
- MP&L considers that the current GCNS D/G design and maintenance practices.
, : described abovefreduces the number-of cold starts more than the proposed changes incorporated in the attachment to-Enclosure 1 of Generic Letter
.; 84-15.
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'AECM-84/0473
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MP&L- Comments / Recommendations on NRC Proposed D/C Technical Specifications -
3
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Cold _' starts (without prelubing the diesel engine an'd'in some instances.
>turbochargers) arp not reccamended. To avoid unnecessary demands, wear and stress;on.the diesel-generator. system, all preplanned starts should be ~
~
Jpreceded by appropriate prelubes, with the exception.that a' cold fast-(non prelubed). start:should be. demonstrated at'least once each-18 months. The
' ability 2of<the engine, generator,and support systems to operate properly
- is fadequately,. demonstrated with' the 31 day and 18 moath surveillance
' tests.
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-;MP&L'recommen'ds'that.the footnote requiring cold fast (non-prelubed) totartsfonce each six months be deleted and the above recommendation for a 18 month surveillance period be adopted. This action will further serve to avoid unnecessary cold fast start surveillances.
In addition, ' the :" continuous rating" ' referenced in Section 4.8.1.1.2.a.5 ~
3'
. should:be based on the maximum expected loao following a loss of coolant eaccident (LOCA)=or loss ofLoffsite power (LOSP) and not on the maximum rating of the diesel generator.
- Note that loading to the continuous. rating'within 60 seconds (as' required .
by the GGNS Technical Specification) produces high stress levels on the diesels. : MP&L1 recommends'thatzfast' starts and loading to." continuous
. rating" within 60 seconds should be performed on a six month schedule-as
- part:of.rection 4.8.1.1.2.a.5.instead of on the frequency as specified in
- Table 4.8-1 E(once every.31 days).: Thirty-one day surveillances should 'be
~
. performed during " fast' starts and slow loading". By loading the diesel
. generators over a 10 to 15 minute time frame the stress levels would be great 1 y reduced'and;the ability of'the dieself to carry the required LOCA/
LOSP:. loads would be adequately demonstrated. MP&L's recommendations are
~- . ' summarized in Table 1 attached.
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SUMMARY
OF MP&L RECOMMENDATIONS.ON NRC PROPOSED D/G TECH SPECS ITEM- NRC PROPOSED MP&L RECOMMENDATIONS JUST1FICATION Failures Frequency.
- 1. 31 Day Surveillances :E l 31 uays $1 31 days The.NRC proposal requires testing at four times the.
Ref: _T.S. 4.8.1.1.2.a 2: 2 7 days 2 14 days. frequency if,more than 1 (Test Frequency) failure occurs. -Doubling the Table ~4.8.1 2: 3 7 days frequency of testing for.
subsequent failures adequately tests:the diesels and will-reduce the testing demands-on the D/G system.-
- 2. Ambient Starts Ref: T.S. 4.8.1.1.2.a.4 and asterisk subnote (e) Prelubed Starts (a) Perform " ambient" (a) Same (a) No change proposed prelubed starts every 31 days minimum (b) Non-prelubed Starts (b) Perform " ambient" (b) Perform " ambient" (b) There is no justification non-prelubed starts non-prelubed starts for subjecting D/Gs once each 184 days at least once each repeatedly to non-minimum- 18 months prelubed starts. This should be performed on a less frequent basis than the NRC proposal because-of the added wear and stresses on critical D/G components. Unplanned LOSP/LOCA starts and 18 month test adequately demonstrate ability to start the diesel " dry".
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SUMMARY
OF MP&L RECOMMENDATIONS ON NRC. PROPOSED D/G TECH SPECS ITEM NRC PROPOSED MP&L RECOMMENDATIONS- JUSTIFICATION.
- 3. Cenerator Synchronization
.Ref: T.S. 4.8.1.1.2.a.5 (a) Continuous ~ Rating (a) Verify generator- (a) " Continuous rating" (a) There is no justification synchronization bys should be defined as for loading diesels.to-loading to maximum expected 100% of their engine or
" continuous rating" site LOSP/LOCA Load- generator loading rating (not engine rating). after pre-operational and shop-testing has demon-strated their capability.
Tests performed during surveillance only need to demonstrate load carrying capacity to maximum expected er.orgency loads.
(b) Time to Load (b) Verify loading to (b) Current CCNS T.S. '(b) One of the most severe
" continuous rating requires 160 transients on diesel in ( ) seconds" seconds. All generator equipment is planned starts fast. loading to full should verify fast rated power. Once the start (510 seconds capability of the-D/G to to. volts / frequency) perform this function has and slow loading to been demonstrated, it is above continuous not necessary to reverify rating in 515 this capability each 31 minutes. days.- Slow loading is preferred which reduces l thermal transients and stresses. Fast loading la $60 seconds should only be demonstrated at least once each 18
. months.
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Attcchment to AECM-84/0473
- 2. NRC REQUEST No. 2:
Diesel Generator Reliability Date
'This item requests licensees to furnish the current reliability of each diesel generator at their plant (s), based on surveillance test data.
Licensees are requested to provide thn information requested in Enclosure 2.
MP&L RESPONSE:
The GGNS procedures include a detailed set of instructions on the start and run history of the Division I, II, and III diesel generators. All starts and attempted starts are logged and run time / loads are recorded. A diesel' generator valid start / failure determination sheet based on the criteria in Regulatory Guide 1.108 position C.2.e is completed for all failures. At least each 18 months the cumulative operating data and any trends are reviewed and documented. Repeat failure mechanisms, repeat human errors, or common mode failures are described in the documentation process.
The reliability data for the GGNS Division I, II and III diesel generators through September 20, 1984 is provided in Table 2. The combined relia-bility of the diesel generators at GGNS is 98% over the last 100 valid tests, which demonstrates that the current GGNS program is effective in maintaining high diesel generator reliability.
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TABLE 2 -
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CGNS DIESEL CENERATOR' RELIABILITY
, , t DIVISION VALID FAILURES ' TIME PERIOD ' TOTAL VALID TESTS TOTAL VALID FAILURES RELIABILITY' BASED ON TOTAL IN LAST 20. -0F 20 VALID FROM DATE OF % N DAH OF %3 TO' ' WD USTS m VALID FARMS 3
VALID TESTS TESTS' .TO 9/20/84 9/20/84 I 2 '1/28/84 93 3 97%~
- to .
9/20/84' II. 0 2/3/84 69 0 100% ,
to-9/20/84.
III O .1/26/84- .78 .2 97%
to
-9/20/84-Data as of. September 20, 1984.-
Valid tests and valid failures based on' criteria in Regul'atory Guide 1.108.
Operating License received 6/i6/82.
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Attachmont to m E: - AECM-84/0473' y -
'i3. ~ NRC REQUEST No. 3:
Diesel Generator Reliability-
. Licensees'are~ requested:to describe their program, if any, for attaining
=and maintaining a reliability-goal for their diesel generaters. An example ~of~a performance Technical Specification to support a desired diesel reliability. goal has been provided by the staff in Enclosure 3.
Licensees are requested to comment on, and compare their existing program or:any proposed program with the example performance specification.
~
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- MP&L' RESPONSE:
- The GGNS program for_ improving the reliability of the diesel generators is ibased on a planned schedule of inspections and tests developed to provide a high degree of' reliability while maintaining the diesels available for tuse if needed. The reliability goal of the program is to maintain the
- diesel generator reliability as high as possible. This program meets or
- exceeds the intent of Regulatory Guide 1.108 and is based on s '
manufacturers' recommendations and past operating experience. Frequent sampling of lube oil and' cooling water is performed _to provide early warning of potential problems. Table 3 provides the long term GGNS D/G
-Maintenance Testing Program for the two standby; diesel engines and Table 4
.the program for the Division III diesel engines. The effectiveness of this program has been empirically _shown by the high reliability.
experienced to date as presented in Table 2 of this submittal.
The~ recommendations of NUREG/CR-06f0, " Enhancement of Onsite Emergency Diesel Generator Reliability,' February 1979" were considered in the development:of the diesel generator reliability program.' Each of the
{, ; recommendations is addressed in Chapter 9 of the GGNS FSAR.
J
,Section 3.8.1.1 of the propcsed Technical Specifications would allow a
- delay up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> under certain conditions before demonstrating diesel
- generator operability, given that one offsite a.c. source or'one diesel generator.is inoperable. This additional delay provides greater opportunity for a. determination to be made of the cause of inoperability, if unknown, without placing undue demands on the operable diesel'
.. generator (s). The recently amended Full Power GGNS Technical
! Specifications allow only a 2 hcur. delay. The proposed change to the L Action statement ~also' indicates that only one start is required within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while 'in the '72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Limiting Condition for _ Operation (LCO). GGNS
~
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Technical ~ Specifications require a start within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and then once
,every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter while in the LCO. Thus, this proposed Technical L
Specification change is expected to significantly reduce the number of-starts experienced.
p MP&L comments on Section 4.8.1.1.2 of.the proposed Technical Specification
[
are discussed in response to NRC Request No. 1. Table 4.8.1, however, does~ require some clarification. It should be explicitly stated that in the event that a diesel generator has two or mote valid failures in the L last: twenty valid demands, only that diesel generator is tested on a more
<- .' frequent basis. If the other diesel generators at c given unit have not i , : experienced a higher failure frequency there is no need for more frequent ftesting of those' diesels.
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Atttch snt to AECM-84/0473 R
- A comparison.of the proposed test frequencies with the current GGNS t'est frequenciesHis given in Table 5.
!The GCNSiTechnical-Fnecifications contain specific reporting requirements
~
in the event of a valid _or non-valid diesel generator failure. The.
~ > information listed.inLSection 6.3.b of Regulatory Guide 1.108 is required
- to be sent to;the-NRC.. This information'is similar to that being
- proposed.- In addition, a statement on the' basis for continued operation is required as well.as the length'of time that th'e diesel generator was
,unavailableh;0nly the' evaluation of the~ recommendations of NUREG/CR-0660 t
l is not included. Because the reporting requirements currently embodied in
- the GCNS Technical Specifications exceed the' proposed requirements, no
[ changes are deemed necessary;to keep the NRC abreast of any diesel 1
' f* generator problems.
The proposed requalification of a diesel generator as described in Attachment 2 to Tab?a'4.8-2 provides a reasonable means for obtaining-evidence that the diesel generator in qttestion is again reliable.and able
'to perform its intended function. Currently no standard'requalification
- scheme is contained in' the GGNS Technical Specifications, although MP&L'is
- participating in the Transamerica Delaval Incorporated, Diesel Generator Owners' Group diesel.requalification/ revalidation effort.
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' TABLE 3: - '
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.,(CONTINUED) , , ,
-Maintenance Action Frequency.
1~ month'
~
Check. lubricating oilifor fuel dilution with a viscosimeter.
!' Send lubricating' oil. sample to: laboratory fortanalysis.- '
-1 month.
i l- Drain. lubricating' oil system. Clean sump.and strainers,' refill'with ~
.18Jmonths (1)'
l new oil..
l Check pH factor of ja'cket water. -1 month L
l Remove alternate left side doors and examine inside of engine'for any 18 months-
! abnormal conditions.
Check hydraulic valve,lif ters .for operation and proper adjustment. 18 months Remove fuel injector nozzles. clean, reset, and reinstall. 18 months Check connecting rods and link rod bearing clearance. -18' months (2)
Check and record crankshaft deflections. 18 months-
~
~
Visually inspect? foundation for. breaks.in bond.between sole plates'and 18 months (3) grout, ,
Check foundation bolts..for correct torque. Retorque as necessary then 18 months recheck crankshaft' deflections.
l Check lubricating oil jets at gears for plugged or broken lines. 18 months.
Remove can covers and cylinder head covers. Inspect cams, tappets, ~18 months rollers, rocker arms., push rods, springs,'and. valve guides.
Drain governor oil, clean, flush refill with new oil. If necessary, 18 months replace governor drive coupling.
NOTE 1: .This item performed only.if deemed necessary'as a result of lube oil analysis.
NOTE 2: Bearing wear is determined by. analysis of metal concentration in lube oil analysis.
NOTE 3: -This inspection is performed during. foundation bolt torque check and crankshaft deflection check.
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TABLE 3 . i
~
(CONTINUED)
Maintenance Action Frequency .
Remove turbocharger (s).: Disassemble and clean.- .S years
-18 months Check cold compression pressures, maximum firing' pressures.-
If indicated, remove . cylinder heads, grind valves. ' Check valves and~ liners. ,
Inspect gears for general condition. . Check backlash and replace worn- 18 months gears exceeding maximum clearance.
Remove fuel injection pumps. . Disassemble, clean, repair, and adjust. 18 months as necessary..
Remove end plates from heat exchangers and intercoolers. Examine and '18 months'~
clean as necessary.
Check main bearings. 18 months Inspect intake' air f11ter oil distribution plate. Change oil in 18 months-(4).
-filter.
-f a
- NOTE 4: Oil in the air filter is sampled and changed only when deemed necessary by oil analysis results.
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- Attachment to AECM-84/0473 TABLE 4 GGNS D/G MAINTENANCE TESTING PROGRAM
^
DIVISION III' DIESELS
' Check jacket water coolant level Every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Check starting' air pressure Every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Drain low point water collector, "Y" strainers once/24 hr.
.and air receiver-tanks in starting air system Check pH and alkalinity of, jacket. cooling water 1 month
- Inspect starting air compressor 3 months Clean andlinspect' starting air' lubricator 6 months
- Clean and inspect "Y" strainers in starting air system 6 months
(( < Take oil'~ sample 11n. air intake filter reservoir. 6 months Clean and change oil in air intake filter 6 months Sample crankcase lube oil 1 month Inspect, clean,'and calibrate lube oil relief valves 3. years
- Remove condensate from fuel oil storage tanks 3 months
.Take-oil sample from starting air compressor 3 months-
-Inspect lube oil separator 1 year Adjust valves on starting air compressor' 1 year
. Inspect.pnd lubricate Woodard governor 18 months Inspect and clean fuel oil-and auxiliary fuel oil strainers 18 months
. Replace fuel and auxiliary fuel filters 18 months Replace turbocharger lube oil filter element 18 months Clean lube oil strainers 18 months Test fuel injectors 18 months
- Inspect and adjust fuel injector linkage 18 months P
Inspect turbochargers 5 years X38rg6 s
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Attachmsnt to
- - AECM-84/0473 e , TABLE 5 DIESEL CENERATOR TEST SCHEDULE
-CENERIC LETTER- CURRENT GCNS TECH. SPEC.
84-15 p.
No.lof Failures in ' Test 'No. of' Failures in Test'
!Last 20 Valid Tests' Frequency Last 100 Valid Tests Frequency ik ~ 1 once/31 days 61 once/31 days Jt'2 once/7 days 2 once/14 days 3 once/7 days 2: 4 ' once/3 days k s' f
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