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Results
Other: AECM-84-0107, Requests Addl Delay in Submittal of Inservice Insp Program Until 840801.Justification Provided, AECM-84-0257, Forwards Sample Plan for Selection of Pipe Supports to Be Subj to 10-yr Inservice Insp Plan,Per ASME Boiler & Pressure Vessel Code,Section Xi.Plan Does Not Encompass Snubbers. Review by 840601 Requested, AECM-84-0335, Forwards Requests for Relief from ASME Section XI Code Requirements for Inservice Insp of 11 Items.Requests Submitted in Accordance W/Requirements of 10CFR50.55a(g)(5)(IV), AECM-84-0371, Forwards 10-yr Inservice Insp Plan for Piping,Welds & Supports,Vols I-III, AECM-87-0068, Documents Conversations Re Postulated Complete through-wall Circumferential Fracture of CRD Housing & Normal Makeup Capacity Available at or Near Cold Shutdown.Crd Pump Can Supply Normal Makeup Inventory Due to Failure.Fee Paid, ML20202J455, ML20203J811
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MONTHYEARAECM-84-0107, Requests Addl Delay in Submittal of Inservice Insp Program Until 840801.Justification Provided1984-03-16016 March 1984 Requests Addl Delay in Submittal of Inservice Insp Program Until 840801.Justification Provided Project stage: Other AECM-84-0257, Forwards Sample Plan for Selection of Pipe Supports to Be Subj to 10-yr Inservice Insp Plan,Per ASME Boiler & Pressure Vessel Code,Section Xi.Plan Does Not Encompass Snubbers. Review by 840601 Requested1984-05-11011 May 1984 Forwards Sample Plan for Selection of Pipe Supports to Be Subj to 10-yr Inservice Insp Plan,Per ASME Boiler & Pressure Vessel Code,Section Xi.Plan Does Not Encompass Snubbers. Review by 840601 Requested Project stage: Other AECM-84-0335, Forwards Requests for Relief from ASME Section XI Code Requirements for Inservice Insp of 11 Items.Requests Submitted in Accordance W/Requirements of 10CFR50.55a(g)(5)(IV)1984-06-29029 June 1984 Forwards Requests for Relief from ASME Section XI Code Requirements for Inservice Insp of 11 Items.Requests Submitted in Accordance W/Requirements of 10CFR50.55a(g)(5)(IV) Project stage: Other AECM-84-0371, Forwards 10-yr Inservice Insp Plan for Piping,Welds & Supports,Vols I-III1984-07-25025 July 1984 Forwards 10-yr Inservice Insp Plan for Piping,Welds & Supports,Vols I-III Project stage: Other AECM-84-0470, Forwards Request for Relief from ASME Section XI Code Requirements for Inservice & Preservice Insp of Pressure Retaining Piping Weld.Expeditious Review Requested1984-09-20020 September 1984 Forwards Request for Relief from ASME Section XI Code Requirements for Inservice & Preservice Insp of Pressure Retaining Piping Weld.Expeditious Review Requested Project stage: Request ML20134K4911985-08-22022 August 1985 Forwards Request for Addl Info Re Proposed Inservice Insp Program & Requests for Relief from Requirements in Section XI of ASME Code Submitted on 840920.Info Needed by 850930 Project stage: RAI AECM-85-0349, Forwards Response to 850822 Request for Addl Info Re 840725 10-yr Inservice Insp Program & 840920 Request for Exemption from Certain ASME Code Section XI Requirements.Program Approval Requested by 8603021985-10-31031 October 1985 Forwards Response to 850822 Request for Addl Info Re 840725 10-yr Inservice Insp Program & 840920 Request for Exemption from Certain ASME Code Section XI Requirements.Program Approval Requested by 860302 Project stage: Request ML20202J4551986-03-28028 March 1986 First Interval Inservice Insp Program,Grand Gulf Nuclear Station, Technical Evaluation Rept Project stage: Other AECM-86-0186, Requests Response to Encl Rev to Justification for Relief Request I-00008 Re ASME Section XI Code Requirements for Inservice Insp of CRD & in-core Housing Welds & Flange Bolting,Per ,By 8608011986-07-14014 July 1986 Requests Response to Encl Rev to Justification for Relief Request I-00008 Re ASME Section XI Code Requirements for Inservice Insp of CRD & in-core Housing Welds & Flange Bolting,Per ,By 860801 Project stage: Request ML20203G4251986-07-22022 July 1986 Forwards Safety Evaluation Re Inservice Insp Program & Requests for Relief from Certain Inservice Insp Requirements & SAIC-86/1626, First Interval Inservice Insp Program, Technical Evaluation Rept.Plan & Requests Acceptable Project stage: Approval ML20203G4361986-07-22022 July 1986 Safety Evaluation Re Inservice Insp Program & Requests for Relief from Certain Inservice Insp Requirements.Inservice Insp Plan Acceptable for Implementation Project stage: Approval AECM-86-0224, Requests NRC Approval of Proposed Change to Inservice Insp Program to Allow Use of Figure Iwb 2500-7(b) from 1983 Edition,Summer 1983 Addenda of ASME Code,Section XI Re Exam Category B-D Weldments.Fee Paid1986-07-23023 July 1986 Requests NRC Approval of Proposed Change to Inservice Insp Program to Allow Use of Figure Iwb 2500-7(b) from 1983 Edition,Summer 1983 Addenda of ASME Code,Section XI Re Exam Category B-D Weldments.Fee Paid Project stage: Request ML20203J8111986-07-30030 July 1986 Notifies That 860723 Request to Use Portion of 1983 ASME Boiler & Pressure Vessel Code,Section XI in Plant Inservice Insp Program Should Be Resubmitted,As Request for Relief from 1977 Edition of Code,By 860816 Project stage: Other AECM-86-0248, Forwards Relief Request I-00013 Seeking NRC Approval for Use of Summer 1983 Addenda of ASME Section Xi,Based on Interpretation of 10CFR50.55(a)(g)(4)(iv), Re Inservice Insp Requirements for Reactor Pressure Vessel Nozzles1986-08-15015 August 1986 Forwards Relief Request I-00013 Seeking NRC Approval for Use of Summer 1983 Addenda of ASME Section Xi,Based on Interpretation of 10CFR50.55(a)(g)(4)(iv), Re Inservice Insp Requirements for Reactor Pressure Vessel Nozzles Project stage: Request AECM-86-0252, Forwards Fee for 860714 Application Revising Relief Request I-00008,per NRC 860804 Request1986-08-20020 August 1986 Forwards Fee for 860714 Application Revising Relief Request I-00008,per NRC 860804 Request Project stage: Request ML20215E7631986-10-0606 October 1986 Forwards Safety Evaluation Supporting Inservice Insp Relief Requests I-00008 & I-00013 Which Request Relief from ASME Code Section XI Requirements for Inservice Control Rod Drive Insp & Approval of 1983 ASME Code Re Inservice Insp Program Project stage: Approval ML20215E7771986-10-0606 October 1986 Safety Evaluation Re Inservice Insp Program & Requests for Relief from Certain Inservice Insp Requirements Project stage: Approval AECM-87-0068, Documents Conversations Re Postulated Complete through-wall Circumferential Fracture of CRD Housing & Normal Makeup Capacity Available at or Near Cold Shutdown.Crd Pump Can Supply Normal Makeup Inventory Due to Failure.Fee Paid1987-07-23023 July 1987 Documents Conversations Re Postulated Complete through-wall Circumferential Fracture of CRD Housing & Normal Makeup Capacity Available at or Near Cold Shutdown.Crd Pump Can Supply Normal Makeup Inventory Due to Failure.Fee Paid Project stage: Other 1986-10-06
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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
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MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi P. O. B O X 164 0, J AC K S O N, MIS SIS SIP PI 3 9 2 0 5 May 11, 1984 NUCLEAR PRODUCTION DEPARTMENT 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 Units I and 2 Docket Nos. 50-416 and 50-417 License No. NPF-13 File 0260/L-860.0/L-952.0/M-189.0 Inservice Inspection to ASME Section XI AECM-84/0257 This letter transmits the sample plan for the selection of Grand Gulf Nuclear Station (GGNS) Unit 1 pipe supports that shall be subject to the ten year inservice inspection plan to comply with the ASME Boiler and Pressure Vessel Code,Section XI, 1977 Edition with Addenda through and including Summer of 1979.
The attachment delineates the criteria which shall be used for the selection of ASME Section III Class 1, 2 and 3 pipe supports requiring inservice inspection.
This sample plan, however, does not encompass snubbers since the safety related snubbers on ASME Class 1, 2 and 3 piping shall be subject to examination and operability testing in accordance with surveillance requirements described in GGNS Unit 1 Technical Specifications, Section 3/4.7.4.
Please review the attached information by June 1,1984, so that the ten-year inservice inspection plan can be submitted to you by August 1, 1984.
If you have any questions or require further information, please contact this office.
Yours truly,
\( -)
8405150003 840511 PDR ADOCK 05000 go (
Manager of Nuclear Services ,
GS/JGC:1m
Attachment:
Sample Plan for Pipe Supports cc: (See Next Page)
FS1 Member Middle South Utilities System
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AECM-84/0257 MISSISSI'PPI POWER C1 Ll*2HT CCMPANY Page 2 cc: Mr. J. B. Richard (w/a)
Mr. R. B.' McGehee (w/o)
Mr. G. B. Taylor (w/o)
Mr. Nicholas S. Reynolds, Esq. (w/o)
Bishop, Liberman, Cook, Purcell & Reynolds 1200. Seventeenth Street, N.W., Suite 700 Washington, D.C. 20036 Mr. J. P. O'Reilly, Regional Administrator (w/a) -
U.S. Nuclear Regulatory Commission Region II 101 Marietta St., N.W., Suite 2900 Atlanta, Georgia 30303 Mr. J. F. Cook (w/a)
EG&G Idaho Co., Inc.
Willow Creek Building Idaho Falls, Idaho 83401 Mr. Martin Hum (w/a)
Materials Engineering Branch U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 Mr. D. R. Bivins (w/a)
Lead A/I Kemper Insurance Company 1
FS2
i ;
x !
amo aaI, Nucrm erIcu ;
PAGE 1 f UNIT 1 SAMPLE PIAN POR PIPE SUPPORPS l f
1.0 SCOPE [
his doctanent describes the sanple plan that shall be used in selecting pipe supports that shall be subject to ISI. l f
his sanple plan is limited to pipe supports as defined in the Subsection l IWF of the ASME Boiler and Pressure Vessel Code Section XI, 1977 Edition through and including 1979 Summer Addenda. This sanple plan does not i cover snubbers, as all safety related snubbers on ASME Class 1, Class 2, and Class 3 piping are subject to examination and operability testing as per surveillance procedures described in omis Unit 1 Operating License Manual Section 3/4.7.4.
2.0 EXEMPTION CRITERIA
%e sample plan for pipe supports shall exclude following supports:
2.1 Pipe supports on ASME Section III Class 1 piping 1" nps and smaller.
Also, pipe supports on piping 2" nps and smaller inaccessible due to a control red drive penetrations.
I 2.2 Pipe supports on AEME Section III Class 2 and 3 piping 2" nps and smaller.
! 2.3 Pipe supports buried or encased in w ete or within guard pipes.
3.0 PEREDIOSNCE CRITERIA POR ' HIE SAMPLE PIAN The performance criteria for the sampling plan is that it shall provide 95 percent confidence that a support population which contains 10 percent or
- more defective supports will be rejected (i.e. 95/90). This criteria will
- be satisfied over the ten-year interval of this plan
- 4.0 SUPPORT CATEODRIES i
me pipe supports to be inspected as per this sanple plan shall be grouped by the support types such as spring, anchor or rigid. Where a support is constructed from more than one support type, each type shall be listed sith its respective category. Rigid supports shall be further divided into
, standard couponents and frane type supports, based on their assembly details. Further, all groups shall be subdivided into Class 1, and Class 2 or 3, based on the piping mde class. W e supports on pipe Class 2 and 3 i shall be placed into the same category since their design, fabrication and installation requirements are similar.
5.0 SAMPLING PIAN A single stage sanpling plan shall be selected. The size of the sanple for such a plan depends upon the population size and the maxistuu nunber of rejects permitted in the sanple. The sanple size is based on ic population distribution. For large populations, the sanple
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GRAtt GULF NUCLEAR STATION .
(251T 1 PAGE 2 SAMPLE PIAN POR PIPE SUPPORTS t f
permit 1 or more defective supports, while for small population (less than !
wwdmately 50) a zero defective support shall be allowed within the !
sample selected. A typcial example of such a sanpling plan is shown in Attachment #1.
i 6.0 SE[ ACTION OF SUPPORF SAMPIES
'Ihe selection of supports for each sanple shall be head on a rande [
basis. 'Ihe population in each support category shall be assigned randam indices. Frm each population category, the required nuptier of samples shall be drawn randtsnly. 'Ihis sanple selection shall be perforned using a r subroutine from the International Mathematical and Statistical Ilbrary, j which generates the specified nunber of sanple indices (equal to the sanple ;
size) fra a given population size. 'these sanple indices shall be then i matched with the indices in the C;-- ding population to arrive at the l supports to be inspec.:wi. -
[
Attachnent #2 is an example of the selection of rande sanple indices and sanple supports.
7.0 EKAMINATION [
f The pipe support sanples selected shall be examined once during the ten :
year interval. 'Ibe sample size in each support category shall be !
scheduled over three inspection periods, in accordance with ASPE Section XI J Tables IND-2412-1 and INC-2412-1. 'the results of the examination shall be }
evaluated in accordance with A!BE Section XI. (
i 8.0 ADDITI(21hL EXAMINRfrIONS ,
8.1 In the event that the ramber of unacceptable supports exceeds the i permissible reject Invel, additional examinations shall be made. 'Ihe additional examinations shall be conducted in accordance with a sanpling appropriate for the population size of the original sanple.
8.2 For small populations (less than approximately 100), when the nunber !
of cumtlative defectives avn==da the acceptance rumber, the entire i population shall be examined. !
, j 8.3 For large populations, upon gletion of the inspection of the !
initial sanple and their evaluation, additional sanples shall be t generated for 181. 'the size of these additional samples will be l
l determined haamd on the evaluation of the defects recorded in the {
sanples examined. If the nature and origin of the defect can be ;
~
i established, all pipe a with similar possible defects shall be f examined. For the case such trend cannot be established, the additional aseples will be determined by the initial acceptance mmber (
! and the total rumber of defective supports recorded in the sangles -
examined. 'the equation that shall be used to generate the additional aanpie sine in provided in Attachnent #3. '!he use of the equation j i witi a typical exanple is also explained. [
i :
I
! l t
GRAND GULF NUCLEMt STATION LNIT 1 PAGE 3 SAMPLE PIAN FOR PIPE SUPPORTS 9.0 ATTACH 4ENIS 9.1 Attachnent il - Supling Plan for Pipe Supports Subject to ISI
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9.2 Attachment #2 - Selection Process for Pipe Supports 9.3 Attachment #3'- Equations for Additional Suples t
4
A II N GLP NUCLEAR STAMm UNIT I SAMPLE PINI EOR PIPE SUPPORTS TABLE #1 SAMPLING PLAN FOR PIPE SUPPOlYIS SURTECT 'IO ISI Support Population Sanple No of Defects No. Category Size Size Accept Reject ASME Class 1 1 Spring 69 40 0 or 1 2 2 Rigid (Std. Ccmp) 40 21 0 1 3 Rigid (Free) 85 40 0 or 1 2 A!NE Class 2 & 3 4 Spring 74 40 0 or 1 2 5 Anchor 66 40 0 or 1 2 -
6 Rigid (Std. Canp) 712 100 5 or less 6 7 Rigid (Frame) 638 100 5 or less 6
- h. _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ . _ _ . _ . _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _
ATTACHMENT #2 PAGE 1 of 4 I. O*
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C ALctsL ATIcrwn. NC=u1111=84013 REY. D CALCuLaTIQu my SHTAM KuMAR========= VERIFIED BY ===*==============
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. GR AND GULF NUCLE AR ST47 ION =UMIT7
) .
POPULATION DF PAPE SUPPORTS FOR IS!
, iagtr. ga iPRIM M UPPURT31 PIPE =CI;453 !J
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8Mda WAMuun 373 -~HL 0*G.MO. ----- PIPE SUPPORT NO PIPE SIZE PIPE CLASS LIhE NO. STRESS PSUR NEMARES Q IhDICES - INCH--^~ -
~-
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)H U 1 45 B21 G002=769E453 01021C006H101A 28 ==4 A N4 MAIN STM=RE FURN.
L 2 55 B21 h002=769E453 U1521G006H1018 28 ==4 R NX M air 57misRE F11RN.
3L 3 19 B21 G002=769E453 01b21G006H102n 28 ==4 R M4 MAIN STu=mE FHRN.
L 4 35 621 G002=769E453 G1521G006H101C 28 ==A R N4 MAIN STM RE FHRN.
O - 5 34 eg1 '-- G002-769E453 Glo21G006H102C 24 ==4 -C N4 HAIM STM=RE FHRN.
}W 6 57 b21 G002-769E453 01821G006H1010 28 ==A n M4 n41N S7m nE FilNN.
J 7 1 821 1328J/6 Q1B21G026H04 12 DB4 17 75 8 54721 4328J/6 s1821G026H02 12 084 4r 74
). 9 32 821 1328J/6 01521G026H03 18 084 13 75
- s. 10 7 321 1328J/6 Q1821G026Wo1 18 084 13 74 7 11 - 60 821 1077 A=323=C/3-91021G153C02 2 084 19 e nBT COMB M /DIRI V 5HU4
} t ,t 12 38 b21 10774=023=C/3 Q1821A153C03 2 DBA 21 2681 y 68 COMB. W/9NHR.
13 ~u21 1077A=022=C/2 Q1821G152w01 2 nba 19 2n81
% to 69 821 a328J/6 G1921CO26CO2 c4 uS4 13 n CUMB V/SNU4 ij 15 17 e21 1328J/6 Q1521G026C01 24 / OSA 13 74 COMB. N/4NHa
)Q 16 21 833 G002 768E317 Q1833G006H351A 16 ==A A Na HECTReamE FURN.
!;f- - 17 6 - 833 G002-764E317 Q1833G006H352A 16 ==4 ~ ~
4 N4 RECTRC=RE'FHRN. ,,
3 lJ 18 39 633 G002=768E317 Gl#33G006H353A 16 *=4 A N4 RECTReanE FURN.
- g Q 19 26 833 G002-768E317 20 3 & 833 - 6002 768E317 G1833G006H354A 91#33G006M3515 16 ==4
8 N4 RECTRCseE FHRN. [
t,_
a6 na nECTRC=RE Ftw .
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)L 21 22 64 033 G002=768E317 Q1833G006H352R 16 ==4 8 NA RECTRC=9E FitRN, a g
L 3 B33 G002=768E317 Q1833G006H353R 16 ==4 8 N4 RECTRC=4E FilRN. [
t,J 23 833 -G002=768E 317 918333006H3548 16 **4 R NA R EC TRC=RE Ft'W". i 3p 24 50 033 G002-768E317 Q1833G006H3014 24 25 2 633 G002-768E317
==4
==A A N4 RECTRC=CE FHRN. "
g l 01033G006H302A 24 A NA RECTRC=cE FHWN, [
t 26 53 n33 M 002=768E317 ste33G006H303A 24 ==4 A NA RECTRC=CE FURM.
3(g 27 20 833 G002*768E317 uta33G006H304A 24 ==4 A N4 RECTRC=RE Fi!RN.
- g 28 16 833 G002-768E317 Q1533G006H3054 24 ==4 A NA RECTRC=RE FHRN.
y-29 5 -h33 -G002 768E317 S1533c006H3064 24 ==4 A ~ ~-
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re t NFCTRC=RE FHRM. ,,
30 47 833 G002-768E317 Q1b33G006H3554 24 ==4 A 3 i,j Q
ti 31 32 13 24 -t:33 - 6002=769E31s 833 G002=768E317 Q1D33G006H3564 J18330006M3018 24 24
==4
==4 A
8 N4 N4 M4 NECTRC=CE FHRH.
RFCTRC=RE FHHN. [g
- FCTRC=CE~F8tRM. -
$' ] 33 33 033 G002 768E317 U1833GQ06H302B 24 ==A B N4 RECTRC=4E FURN. =g b 34 4 B33 G002=768E317 Q1533G006H303R 24 ==4 8 N4 RECTRC=4E FilRH.
rT - ~35 56- 0 3 3 -6002-7 68 E 317 918338006H3049 24 ==A 8 M4 RECTRC=cE Ft'RM. ,
36 48 b33 E002-768E317 Q1833G006H305R 24 ==A B N4 RFCTRC=RE FHRN. a g 3 ]) ;,, 37 36 66 833 G002 768E317 W1533G006H306M 24 ==4 8 p. A RECTRC=CE FHHN.
65 - 333 - S002=768E317 s1833000eH355n - 24 ==4 8 na NEC7RC=mE Fttaw. o 39 23 G002 768E317 3 833 Q1833G006H356B 24 ==4 5 N4 RECTRC=GE FijpN. =
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) ' ATTACHMENT #2 PAGE 2 of 4 'j C ALCutCTierNG. nCus1111=84013 RECO [ '
3
, CALCULATION SY 8HTAM uuMAR=========vgeIFIED BY ================== ' ,
b- GR AMD-CULF fJUCLE AR 3T ATION= UNIT 1 y ,
PuPULATION OF PIPE SUPP0 HTS FOR ISI
, IASLE a4 SF#INC 30PPORT3-tP!PE*CUA33 %
, Smu, RAhDOM SYS. HL DMG.NO.
- - 1NDICt3- PIPE SUPPORT NO PIPE SIZE PIPE CLASS LINE NU. STRE95 PROR RFNARKS INCH
', CO 36 1533 10784*028C/l 01533G128C01 2 nsA 40 v34 O! 8 533 t078 A*005C/e: slu33G105 tun c0Ha! W/SNH8AtR C2 z uCA za 134 y, 18 833 10784*088C/4 Q1833G108C01 2 DCA 24 139 COMB N /9NUBAER g C3 28 633 1078A*029=C/1 01u33G129C01 CoMs. W/MNHB9ER 2 CBA 41 139 Cnns W/spRINGeRTGTD g- C4 14 833 13424 01633G024H01 4 DCA 1 13R
) l,, C5 31 C41 1082 013C C6 G1C41G113H01 1.5 DCA 3 2'l48 L 59 C41 1082-019C Q1C41G119H02 1.5 nCA 3 2647 E. C7 T E12 a3487/s w1E12G016H01 C8 49 12 DBA 38 67 E12 1348F/15
)('. C, C9 50 -
37 E12 41 -- E12 1348F/15 Q1E128015H12 Q1E12G015H04 14 14 DBA DBA 28 29 102 101 1348 A/17 91E12G012H1T 20 DBA 54
)L 51 to E12 1348E/20 123 Q1E12G014H01 6 084 32 165 L 52 62 E21 13508/7 Q1E21G002H04 r 53 14 08A 1 56 61 E21 a3505/i sit 218002HO! as DBA
) (, 54 27 E22 13498/7 G1E22G003H04 4 084 1 55 55 5 60
,, 42 E22 13498/7 Q1E22G003H03 4/ OsA ;g; 55 5 61
,, 63 - E51 1347A/10 01E51G004H07 to DBA 24 ,,
229
) ,, 57 53 58 46 E51 1346A/12 Q1E51G001H09 6 DBA 30 14 J
. E51 1346A/12 Q1E51G001H08 6 DBA 30 78 $
t,, SG 51 - E5g 1346A/12 stE51G001M07 6 OSA 20 7R
) 1,, CO 44 E51 13444/12 Q1E51G001H05
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ATTACHMENT #2
) m PAGE 4 of 4 O f.
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tIST CP-3CPPORT3-70 BE~EXAMINCD
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ATTACINENr #3 GRAND GUIF NUCLEAR SrATION
- UNIT 1
- SAMPLE PIAN MR PIPE SUPPORTS CAICUIATION mR ADDITIONAL SAMPLES SIZES i
'Ihe following equation will be used to detemine the size of the additional '
su ple sizes. i N=S 2 2 (a - c) c+1 where, S = Initial saple size c = Allowable nutber of defective supports a = Total nutber of defective supports in the total saple 5
For c = 5 and S = 100, the first re-se ple size will be
, Ny = 11.11 (a , c)
Further additional sa ple sizes will be determined by the following equation ,
2 2 N2 = (b) (S) c+1 where, b = No of defective supports in the previous re-seple >
N2 = 11.11 (b) l' The process will continue until no additional defective supports are found.
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