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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 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 ML20216J7101999-09-26026 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator License Examinations 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 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 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 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 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 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 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 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 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 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 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, 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 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 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 ML20196J5811999-06-30030 June 1999 Advises That Version of Info Submitted in 990504 Application & Affidavit Re Engineering Rept ME-98-001-00,marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 as Amended 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 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 ML20216J7101999-09-26026 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator License Examinations 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) 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 ML20211K6061999-08-31031 August 1999 Informs That Plant Has No Candidates to Take 991006 Generic Fundamentals Exam 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 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 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 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 ML20207A9901999-02-24024 February 1999 Informs That Util Has No Candidates from GGNS to Nominate for Participation in Planned Gfes,Scheduled for 990407 ML20207A8161999-02-24024 February 1999 Forwards 1998 Annual Operating Rept for Ggns,Unit 1. Listed Attachments Are Encl 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:VENDOR/MANUFACTURER TO NRC
MONTHYEARML20155F4441988-05-0404 May 1988 Responds to NRC & Request at 880504 Meeting Describing GE Program to Reconfirm Design Adequacy of Associated Circuits in GE Bwrs.Upon Completion of Phases 1 & 2 of Evaluation of Bwrs,Ge Will Submit Summary by 881104 ML20215B1231987-06-0909 June 1987 Confirms That Methodologies in XN-NF-79-71,Rev 2,Nov 1981 & Util to NRC Acceptable for Application for Facility Cycle 3 Transients.Nrc Acceptance Will Be Assumed If No NRC Exceptions Received by 870710 ML20214P1911986-11-19019 November 1986 Forwards Proprietary NEDC-31336, GE Instrument Setpoint Methodology, Per Lrg Instrument Setpoint Methodology Group .Rept Applicable to Listed Plants & Withheld (Ref 10CFR2.790) ML20100G0611985-03-14014 March 1985 Corrects 850312 Part 21 Rept Re Potential Problem W/Check Valve.Mississippi Power & Light Did Not Perform Low Pressure Injection Insp of Valve Disk.Valves Supplied by Cloy Corps & William Gauge Co ML20203A0751984-11-19019 November 1984 Forwards Notification Ltr Re Problem W/Model C Deluge Valve Which May Affect Fire Protection Sprinkler Sys to Be Mailed to Utils W/Permits to Build & Licenses to Operate Nuclear Power Plants ML20091L7911984-06-0404 June 1984 Responds to IE Info Notice 84-16, Failure of Automatic Sprinkler Sys Valves to Operate. No Design or Mfg Faults Exist in Model C Deluge Valves.Maint Procedure Revised Requiring Smoother Surfaces on New & Existing Valves ML20070C7631982-12-10010 December 1982 Part 21 Rept Re Problem W/Brown Boveri Electric,Inc Low Voltage Circuit Breakers W/Solid State Trip Devices.Units from San Onofre 2 & 3 Failed Due to long-term Degradation of Filter Capacitor C205.Suspect Trip Units Should Be Tested ML20052G5671982-05-13013 May 1982 Part 21 Rept Re Potential Defect in Component of Dsrv or Dsr Standby Diesel Generator.Potential Problem Exists in Starting Air Valve Assembly Which Could Result in Engine Nonavailability.All Cognizant Parties Notified ML20040D6481982-01-15015 January 1982 Forwards Affidavit Requesting Withholding of Proprietary Version of OPS-37A35, Verification of CLASIX-3 Computer Program ML20040H5161981-12-22022 December 1981 Confirms 811202 Telcon Re Teflon Coating on Shell Id of Aftercooler.Aftercooler Used to Lower Gas Discharge Temp of Drywell Purge Compressor Supplied by Atlas Copco Turbonetics,Inc for Installation of Bechtel Piping Sys ML20037D7251981-08-21021 August 1981 Forwards Response to NRC Request for Addl Info Re Postulated Calculations for low-low Set Relief Logic Failure Modes. Details for Reliability Analysis & Comparable Evaluation for Facility Relay Logic Provided ML19312E7201980-04-0404 April 1980 Informs NRC of Possible Defective Matl Shipment to Power Plant.Notification Was Received Per Encl Vendor 800402 Ltr ML19310A3771980-04-0303 April 1980 Notifies NRC of Defective Comsip,Inc Containment Gas Analysis Sys.During Testing,Pump K Deadheaded for Approx 20-s & Pressure at Pump Outlet Exceeded 150 Psig.Pump Discharge Bypass Line to Be Fitted ML19257B2721980-01-0707 January 1980 Forwards Chart Listing Revised Natural Frequency for Valves Supplied to Util.Frequencies Not Yet Available Will Be Evaluated by 800121.Advises of Evaluation of Corrective Action & Lists Valve Evaluation Procedure ML19262A6861979-11-30030 November 1979 Forwards Initial Questions Re FSAR in Response to 791115 Discussion.Requests NRC Assistance in Obtaining Answers to All Questions ML19210C4671979-11-0707 November 1979 Forwards Questions Re Electric Power,Developed During Initial Review of Section 8.1 of FSAR ML19270H0681979-05-11011 May 1979 Responds to IE Bulletins 78-12,12A & 12B Re Reactor Pressure Vessel Welds.No Discrepancies Noted ML20054E2321977-11-17017 November 1977 Forwards Prototype Qualification Test Program for NRC Review.Tests Simulating Typical HPCS Sys Configuration Scheduled for Second Quarter 1978 1988-05-04
[Table view] |
Text
P'Ev'Mai 00 3DNT E. I. ou PONT DE NEMOURS 6 COMPANY m.
ATOMIC ENERGY DIVISION SAVANNAH RIVER PLANT AIKEN. SOUTH CAROLIN A 29801
,,m.................
November 30, 1979 Mr. Faust Rosa, Chief Power Systems Branch Mail Stop 832B Phillips Building U.S. Nuclear Regulatory Commission Bethesda, MD 21609
Dear Mr. Rosa:
Attached are initial questions relating to Grand Gulf Nuclear Station which we discussed with A. Bennett and yourself on November 15, 1979.
In addition to these questions, the applicant has not replied to your questions numbered 040.26, 040.37 and 040.38.
Your assistance is requested in obtaining responses to all questions.
Yours very truly, W. M. Taylor Superintendent E & I Department WMT:ssr 1522 096 79121003/o
Q040. - Section 8.1.4.1.b of the FSAR says that there ce three (8.1)
GG (3) physically independent circuits from the 500KV switch-1 yard to the onsite electrical distribution system.
Figure 8.2-3 indicates that there are only two (2) circuits from the 500KV switchyard.
Clarify.
Q040. - Standard Review Plan Section 8.3.1, III, 4 requires onsite (8.1)
(8.3) fuel storage capacity for seven (7) days.
The following GG 2
questions pertain to this capacity:
a) - In FSAR Section 8.1.4.2.3.e, it is stated that the fuel capacity for the standby power soirce has " time sufficient to put the plant in a safe condition".
How much time is
" sufficient"?
b) - Provide the fuel consumption rate of the HPCS and standby diesel generators while they are supplying maximum post-LOCA load demands.
c) - How much of the diesel storage tank is useable?
(i.e. How much fuel oil can the transfer pump be expected to supply to the day tank?)
Provide drawing of stcrage tank, trans-fer pump, and transfer pump suction line.
Provide dimensions of storage tank, depth of suction line into storage tank and show where level of fuel oil is maintained during normal standby operation.
1522 097
Q040. - In the first paragraph of FSAR Section 8.1.4.3 a " spare (8.1)
GG set of BOP transformers" are mentioned.
Are these in 3
addition to those shown in Figure 8.1-1 or do you mean
~
that these are included in the four BOP transformers shown (such as BOP XFMRS #12A and 12B) ?
Q040. - In FSAR Section 8.1.4.2.3.f it is stated that " provision (8.1)
GG is made for control (of the HPCS power system) from the 4
control room and another location external to the control room".
Where is the other location?
Q040. - ; RP Section 8.1, III, 5, Revision 1, requires that cri-(8.0)
GG teri;t applicable to the design should be identified and 5
the degree of conformance defined.
SRP Table 8-1 lists applicability of criteria to each FSAR section.
Each section of your FSAR Chapter 8 should mention conformance (or exception) to all of the criteria of SRP Table 8-1.
This may be done by a single comprehensive table in FSAR Section 8.1 which would be referenced by the subsequent sections.
Where exceptions, relative to the electrical power systems, are taken, these should be specifically noted and referenced to a detailed explanation.
Q040. - FSAR Section 8.1.4.4.1 states that the design is in (8.1)
GG accordance with Regulatory Guide 1.93, among others.
6 However, in the table of contents of Appendix 3A, RG 1.93 is noted as "not addressed in FSAR........".
1522 098
The statement in Appendix 3A is not correct since the recommendation of Regulatory Guide 1.93 will be incor-porated in the Technical Specifications, FSAR Section 16.
Correct Appendix 3A.
Q040. - In FSAR Appendix 3A, page 3A-4, Regulatory Guide 1.32 is (Appx. 3A)
GG noted as N/A.
However, compliance with RG 1.32 is stated 7
in FSAR on page 3A/1.32-1.
Correct this discrepancy.
Q040. - SRP Section 8.1, III, 1 states that FSAR grid "....descrip-(8.2)
GG tions should state whether facilities are existing or 8
planned; if planned, the respective completion dates should be provided."
Which of the 500KV and ll5KV overhead lines are completed and ready for service at this time?
For those that are not completed, list scheduled or projected date of
~
completion.
Q040. - Regulatory Guide 1.70, Revision 3, Section 8.2.2 specifies (8.2)
GG that the applicant should " provide information and a 9
discussion of grid availability, including the frequency, duration and cause of outages".
For the outage statistica given in FSAR Table 8.2-1, furnish the following information:
a) cause of each outage b) duration of each outage c) update the table to the present time Q040. - In FSAR Section 8.2.1.2 and Section 8.2.1.4 the acronym (8.2)
GG "NAPSIC" is used.
Explain the meaning and the function 10 of NAPSIC.
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Q040. - Explain how you comply with Regulatory Guide 1.9, (8.3)
GG revision 1, paragraph C.9 with respect to first out 11 alarm indication.
Q040. - In the FSAR paragraph 8.3.1.1.4.2.10 it indicates that (8.3)
GG generator differential current and engine overspeed are 12 the only emergency protective devices for the HPCS diesel.
Figure 8.3-8 of the FSAR shows that lube oil pressure low (2 of 3 logic) and case pressure high (2 of 3 logic) also operate protective interlocks during an emergency for division I and II.
If this logic diagram also applies to the HPCS diesel explain the discrepancy or provide the logic diagram for the HPCS diesel.
Q040. - FSAR Section 8.3.1.1.5.1 in describing the RPS power (8.3)
GG supply states that ".....the power feeds to indepen-13 dent divisions are physically separated and feed four redundant buses."
FSAR Figure 8.3-11 shows only two
- buses, "A" and "B".
Correct the contradiction.
Q040. - SRP Section 8.2, I, 2 states that " evaluation (of the (8.2)
GG offsite power sou 'Q will include a review of the 14 electrical protective relaying and breaker control circuits and power supplies to assure that lass of one preferred system circuit will not cause or result in loss of the redundant counterpart, nor any standby power system sources".
FSAR Section 8.2.1.2 states that 1522 100
"a fault of any section of 500KV bus will be cleared....
and not inter upt operation of any of the remaining parts of the 500KV switchyard bus".
Provide details describing how this selectivity of breakers is accomplished.
Q040. - In FSAR Table 8.2-3 " Load Flow Studies" and Table 8.2-4 (8.2)
GG
" Stability Studies", the results of analysis of contin-15 gencies and faults are stated as "no problem" and " stable".
Define:these terms more explicity so as to provide greater assurance of the results of the analysis.
Provide minimum or maximum voltage, transient durations, and other quanti-tative values to substantiate the conclusions drawn in Tables 8.2-3 and 8.2-4.
Q040. - Clarify the description in FSAR Section 8.2.1.2, regarding (8.2)
GG alarms for the various problems that could occur involving 16 the switchyard auxiliary systems.
Identify the alarm indication and its location.
Q040. - In FSAR Section 8.2.1.1 page 8.2-3, you state that "there (8.2)
GG has only been an average loss of two towers per year....".
17 Provide further detail of these tower failures and show how this compares to the experience of other utilities and the effect on grid stability at Grand Gulf.
Q040. - In Section 8.2.1.1 on page 8.2-2, it is stated that "The (8.2)
GG ll5KV line does not cross over or under any of the 500KV 18 offsite power supply lines....".
However, from Figure 8.2-2, it appears that the 500KV line from Franklin to 1522 101
Grand Gulf does cross over the 115KV line between Natchez S.E.S. and Port Gibson.
Confirm that it does or does not cross.
Provide further information on grid stability at Grand Gulf if the above mentioned 500KV line fell on top of the ll5KV line.
Q040. - In FSAR Section 8.3.1.2.1.a.4, page 8.3-26 provide a more (8.3)
GG substantive basis to support the statement concerning 19 large motors reaching rated speed in 5 seconds or less.
Relate this information to each of the large motors involved.
Q040. - FSAR Section 8.3.1.1.4.1 page 8.3-11 provides information (8.3)
GG on controls for diesel generators.
Clarify statement con-20 cerning how many and where the local control stations are for each diesel generator.
Q040. - Describe how you assure that a diesel generator is capable (8.3)
GG of responding automatically to a LOCA - loss of preferred 21 power condition after completion of and during a periodic test.
Address the following:
o Governor control settings o
Monitoring of Diesel Generator Sync-Speed setting Q040. - FSAR Section 8. 3.1. 2.1.b.14. (e) page 8. 3-37, s tates that (8.3)
GG the "HPCS generator is operated in the isochronous mode 22 only".
HPCS Power Supply Topical Deport NEDO-10905, page 1522 102
7-11 states that IEEE 387 - Section 5.6.1.4 is "not applicable since the governor is operated in droop mode only".
Clarify this discrepancy and explain the pro-visions for placing the engine governor controls in an acceptable mode of operation when the diesel-generator unit is required to operate automatically.
(See also Topical Report NEDO-10905 paragraph 5.2.10)
Q040. - In FSAR Section 8.3.1.2.3.b page 8.3-39, you state that (8.3)
GG
" circuits of different safety divisions are not routed 23 through hostile areas....".
Define and identify (provide list) all hostile areas.
Q040. - In FSAR Section 8.3.1.1.4.1 page 8.3-7, you state that (8.3)
GG folloging an automatic start, diesel generator sats 11 24 and 12 (21 and 22) are automatically connected to their associated 4.16KV ESF buses.
Clarify the statement with regard to the availability of offsite power as discussed in FSAR Section 8.3.1.1.3.b.
Q040. - In FSAR Section 8.3.1.1.2.1 page 8.3-2, you state that (8.3)
GG any one offsite power source is capable of supplying 25 AC power to start the ESF loads of one unit required due to a LOCA and to run the ESF loads of the other unit required for safe shutdown.
IEEE Standard 308 uses the terminology of " start and operate the ESF loads of the other unit required for safe shutdown."
Define the 1522 103
capability of the offsite power source more explicitly in this regard.
Q040. - In FSAR Section 8.3.1.1.4.1.1.a.2 page 8.3-12, it appears (8.3)
GG that the resistive load was omitted from the tabulated 26 data in test 2; clarify.
Also, provide the analytical method for obtaining the cumulative loads.
Q040. - The load shedding and sequencing reset operation is (8.3)
GG mentioned in Section 8.3.1.1.3 page 8.3-5.
Regarding 27 restoring of motors and valve operations following loss of offsite power, clarify and expand the description since you state that, " reset is not a function of the presence or absence of bus voltage".
Q040. - In Table 8.3-5 of FSAR, it is stated that the diesel (8.3)
GG generator start signal is given at time 3 seconds following 28 LOCA.
In Table 6.3-1 the diesel generator start signal is given at time 0 seconds.
Correct this discrepancy.
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