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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: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 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 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] |
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s b GENERAL OFFICES C0RPORATION OF AMERICA POST OFFICE BOX 180 June 4, 1984 1000 EAST EDGERTON ROAD CLEVELAND,0HIO 44147 PHONE: 216428-9900 Mr. Richard C. DeYoung 8"~""
Director, Office of Inspection
& Enforcement US Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Nuclear Regulatory Commission Infomation Notice 84-16,
" Failure of Automatic Sprinkler System Valves to Operate"
Dear Mr. DeYoung:
The following information is provided in response to the Nuclear Regulatory Commission Information Notice 84-16 concerning operational failures of our Model C deluge valve at Grand Gulf Unit No.1 of the Mississippi Power and Light Company.
To obtain an indication of whether this problem existed at other installations, we tested a total of seventeen (17) 2-1/2"' Model C deluge valves at eight (8) different locations and eight (8) 6" Model C deluge valves at three (3) different locations, using a special test procedure (130.002SP), and found no operational failures. Two (2) additional six inch (6") Model C deluge valves were tested at a fourth location without failure using the standard test procedure.
The special test procedure required the weight onIeach valve to be dropped only one-half the normal distance so that only one-half the energy is generated to unlatch the valve under this special test condition. A tabulation of the 2-1/2" and 6" valves tested is given on Table I.
The results of our field tests do not indicatt. a problem with our valve design or manufacture.
We performed a number of tests in our laboratory on a 6" Model C deluge valve and found we could duplicate the type of operational failure experienced at the Grand Gulf facility if the latch and clapper nose mating surfaces were rough (approximately a 500 microinch finish or rougher).
We reviewed our drawings to determine if any changes were made which could have caused the problem observed at the Grand Gulf facility. A drawing change was made in September '
I of 1973 which changed the finish requirement on the clapper and latch mating surfaces from a 63 microinch to a 125 microinch finish.
Valves with serial numbers higher than 4586 for 2-1/2" valves and 6821 for 6" valves were manufactured after the September 1977 drawing change and, since the Grand Gulf Unit No. 1 valve serial numbers were higher than those identifying the 1973 finish change, we I required that the valves tested in the field to our special test procedure have serial I numbers which indicate that they were produced after the surface finish change. As pre- l viously stated, no operational failures were found on the valves tested which were 1 produced after the surface finish change.
Although we did not find the Grand Gulf mode of failure at any other installation, we made two changes to increase the probability of successful valve operation. The surface 8406000210 840604 PDR ADOCK 05000416 men t.caroRAflON OF AMERICA. A FIGGIE INT ( AN ATIONAL COMPANY W G PDR
2.
~
finish drawing requirement of tto clapper nose and latch mating surfaces was changed from a 125 microinch finish to a 16 microinch finish on November 1983, and our data pages G8a and G22a (copies enclosed) were changed to require refinishing of the clapper nose and latch mating surfaces at each routine, periodic instection.
With respect to the conditions noted in Infonnation Notice No. 84-16 regarding bowing of the guide rod and the undersize I.D. of the upper guide rod collar, the following information is offered.
The guide rod we install in our valves i:: purchased under ASTM B16, material C36000.
The ASTM B16 (Table 15) straightness requirement is 1/32" maximum curvature (depth of arc) in any 2 ft long portion. The bowing observed (0.005 inch) in the 20 inch long guide rod used in our 6" Model C deluge valve easily meets the ASTM requirement.
The upper guide collar was stated to have an I.D. of 0.637 inch and our minimum I.D.
dimension was stated to be 0.647 inch. Our actual drawing minimum dimension for this I.D. is 0.640 so the collar was measured by the Grand Gulf people to be undersize by 0.003 inches. However, the ASTM B16 requirement for the guic's rod is 0.625 *0.002".
The minimum clearance for the guide rod in this undersize hole is 0.637-0.627 or 0.010 inches which is adequate to allow the weight to slide freely on the guide rod even if the guide collar I.D. was undersize as claimed.
It is our conclusion that no design or manufacturing fault exists in our Model C deluge valves; however, we revised the maintenance procedure and require smoother surfaces in manufacturing to increase the probability of successful operation of both new and existing Model C deluge valves.
I We further conclude the operational failures at Grand Gulf Unit #1 are peculiar to that facility.;
Very truly yours, c r S f5. __
w Charles B. Barnett, Manager Research and Development CBB/mn Attachment cc: W. H. Miller, Resident Inspector E. L. Jordan, Director of Engr. & 0.A.
J. P. O'Reilly, Regional Administrator
TABLE I 6" MODEL C DELUGE VALVE Serial No. Trip Test Pressure (psi 9tatic Water ) Satisfactory Location 8429 150 Yes Perth Amboy, NJ 8153 110 Omaha, NE 8106 93 Mankato, MN 8102 90 " "
8077 175 "
Atlanta, GA 8082 " "
8078 " "
8094 " "
8095 " " "
8096 " "
Total 10 valves at four (4) different locations.
2-1/2" MODEL C DELUGE VALVE 8200 130 Yes Carson City CA 8183 132 " " "
8604 130 " " "
4878 125 " " "
8148 "
120 Baytown TX 8149 120 " " "
8293 150 "
Perth Amboy, NJ 8294 150 " "
8291 " " "
150 8277 150 " " "
5113 "
200 Nebraska City, NE
$8204 77 "
Oakland, CA S8199 80 " " "
8276 115 "
McKeesport, PA 8190 100 "
Greensburg, PA 8188 110 " " "
S8215 "
100 Des Moines, IA Total 17 valves at eight (8) different locations, c' ,
N .. Automatic.. Sprinkler '. Corporation ca SUPROTEX-DELUGE of Amen.
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" Automatic" Model C Deluge Valves
" Automatic" Model C Suprotex-Deluge Valves MAINTENANCE The " Automatic" Model C Deluge and Supervisory Air Supply. Strainers and reg-Suprotex Deluge Valvr and their related equip- ulators should be checked and cleaned as required.
ment should be exami..ed periodically to ensure Air reservoirs and drum drips should be drained as proper operation and trouble-free service. Several often as required to remove any water that has areas to be routinely inspected are: accumulated.
Clapper / Clapper Latch. The mating surfaces The air dryer should be checked and replaced of the clapper nose and the clapper latch must be when the blue granules become pink or white.
kept clean and smooth. As required, sand each Air Compressor. The air compressor should be surface with No. 220 grit sandpaper until smooth, lubricated as recommended by the manufacturer, then finish the surface with crocus cloth. The motor unit should be kept free of dirt. Filters Clapper Facing. The rubber clapper facing and strainers should be cleaned as required.
should be checked for wear or damage, and to Air Pressure. Air or nitrogen pressure must be determ,ine that it is free of dirt and other fore,ign maintained on the detection system as recom-substances. If found to be worn or damaged (e.g.,
, mended in the operational instructions. Low-air-foreign matter imbedded in the surface), the facing pressure alarms should be tested and switches should be replaced. If it is dirty, it should be should be checked to see that they are properly p' cleaned, but compounds which could damage the rubber facing must never be used.
set to operate at the required pressure level.
5 O Detection System. The detection system and Seat Ring. The seat ring should be cleaned related components are to ba tested and checked thoroughly and checked for possible damage. If as recommended in the opuational instructions.
it is found to be severely damaged, the complete deluge valve assembly should be replaced or returned to " Automatic" for possible recon-ditioning.
Alarm Line Strainer. The strainer in the alarm line should be checked and cleaned thoroughly.
Alarm Test Valve & Main Drain Valve. All con-trolling valves normally closed when the deluge valve is in the set position should be checked to be sure that they are fully closed and not leaking.
System Control Valve, Alarm Control Valve
& Air (or Nitrogen) Supply Control Valve. All controlling valves normally open when the deNge valve is in the set position should be checked to oe sure that they are in the fully open position and sealed, where required.
Deluge Valve & Trim. The overall setup should be checked for visible leaks and possible physical damage to the valve and connections (e.g., broken fres).
(] Valve Enclosure. The temperature in the
() enclosure around the deluge valve should be main-tained at a temperature above 40* F (4 C). r 12/83
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sn,,,,,,, e,,,,,,:.. . ..,, SUPROTEX/ PRE-ACTION
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" Automatic" Model C Pre-Action Valves
" Automatic" Model C Suprotex Valves MAINTENANCE The " Automatic" Model C Pre-Action and Supervisory Air Supplies. Strainers and reg-Suprotex (supervised Pre-Action) Valves and their ulators should be checked and cleaned as required.
related equipment should be examined periodically Air reservoirs and drum drips should be drained as to ensure proper operation and trouble-free service, often as required to remove any water that has Several areas to be routinely inspected are: accumulated.
Clapper / Clapper Latch. The mating surfaces The air dryer should be checked and replaced of the clapper nose and the clapper latch must be when the blue granules become pink or white.
kept clean and smooth. As required, sand each Air Compressors. The air compressors should surface with No. 220 grit sandpaper until cmooth, then finish the surface with crocus cloth, be lubricated as recommended by the manufact-urer. The motor units should be kept free of dirt.
Clapper Facing. The rubber clapper facing Filters and strainers should be cleaned as required.
should be checked for wear or damage, and t Air Pressure. Air or nitrogen pressure must be determ,ne i that it is free of dirt and other foreign maintained on the sprinkler and detection system substances. If found to be worn or damaged (e.g., as recommended in the operational instructions.
fore,ign matter imbedded in the surface), the facing Low-air-pressure alarms should be tested and should be replaced. If it ,si dirty, it should be switches should be checked to see that they are D cleaned, but compounds which could damage the properly set to operate at the required pressure (V rubber facing must never be used.
level.
Seat Ring. The seat ring should be cleaned Detection System. The detection system and thoroughly and checked for possible damage. if related components are to be tested and checked it is found to be severely damaged, the complete as recommended in the operational instructions, pre-act,oni valve assembly should be replaced or returned to " Automatic" for possible recon-ditioning.
Alarm Line Strainer. The strainer in the alarm line should be checked and cleaned thoroughly.
Alarm Test Valve & Main Drain Valve. All con-trolling valves normally closed when the pr?-action valve is in the set position should be checked to be sure that they are fully closed and not l'aking.
System Control Valve, Alarm Control Valve
& Air (or Nitrogen) Supply Control Valve. All controlling valves normally open when the pre-action valve is in the set position should be checked to be sure that they are in the fully open position and sealed, where required.
Pre-Action Valve & Trim. The overall setup should be checked for visible leaks and possible physical damage to the valve and connections (e.g.,
broken gages).
( Valve Enclosure. The temperature iri ine
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enclosure around the pre-action valve should be maintained at a temperature above 40 F (4 C).
12/83