Letter Sequence Request |
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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
[Table view] |
Text
O MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi RIB &EAMdlE P. O. B O X 16 4 0. J A g K.S O N , MI S S I S S I P PI 39215-1640 October 31, 1985 NUCLEAR OCENSING 8 SMETY DEPARTMENT U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C. 20555 Attention: Mr. liarold R. Denton, Director
Dear Mr. Denton:
SUBJECT:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 Additional Information on the 10 Year Inservice Inspection Program AECM-85/0349 Mississippi Power and Light (MP&L) submitted the 10 Year Inservice Inspection Program by AECM-84/0371 dated July 25, 1984. By letter AECM-84/0470 dated September 20, 1984, MP&L requested relief from certain requirements of Section XI of the ASME Code. This submittal is provided in response to a request from your staff for additional information dated August 22, 1985.
As discussed with the NRC during the review of the Grand Gulf Nuclear Station (GCNS) Pump and Valve Inservice Testing Program, inservice plans in general are periodically updated to reflect the latest "as-built" conditions.
After the NRC completes this review of the CGNS Inservice Inspection (ISI) program, future updates will be submitted to the NRC Region II to keep the inspection personnel current of the latest plant and program status. This is consistent with NRC direction given concerning the testing program.
MP&L's responses are provided in the attached. Where the response acknowledges a change to the 10-year program, copies of the changed page(s) are provided. These changes will be incorporated into the program by revision prior to MP&L's first refueling outage. This is consistent with MP&L's plans and schedule for an "as-built" of the 10-year program plan prior to refueling outages.
MP&L requests your review and approval of the ISI program be provided by March 2, 1986. This will enable MP&L to implement an accepted plan during the GGNS initial refueling outage, currently scheduled to begin in June, 1986.
0511040006 851031 gDR ADOCK 05000416 jd i PDR iLl kg J19AECM85102901 - 1 Member Middle South Utilities System
r
. AECM-85/0349 Page 2 If you have any questions or require further information, please contact t this office.
i Yours truly, L. F. Dale Director GCS/MLC/JGC: pus Attachment cc: Mr. J. B. Richard (w/a)
Mr. O. D. Kingsley, Jr. (w/a)
Mr. R. B. McGehee (w/a)
Mr. N. S. Reynolds (w/a)
Mr. H. L. Thomas (w/o)
Mr. R. C. Butcher (w/a)
Mr. James M. Taylor, Director (w/a)
Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Dr. J. Nelson Grace, Regional Administrator (w/a)
U. S. Nuclear Regulatory Commission Region II 101 Marietta St., N. W., Suite 2900 Atlanta, Georgia 30323 i
J19AECM85102901 - 2 L
.-.____w
MP&L'S RESPONSE TO NRC LETTER OF AUGUST 22, 1985
- 1) NRC COMMENT Section 1, Foreword, Page 2 Section i states "The Grand Gulf Nuclear Station Unit I has utilized a unique plan for the inservice inspection of pipe supports other than snubbers. This sampling plan was transmitted to NRC by letter AECM-84/0257 dated May 11, 1984." The proposed sampling plan for pipe supports is also described in Section 7 of the CGNS ISI plan. This plan is being reviewed by the staff as an alternative program to be used in lieu of the IWF Code requirements.
As presented in letter AECM-84/0257 and Section 7, the proposed GGNS sampling plan would provide inservice inspection of pipe supports (other than snubbers) based on a statistically selected subset of the supports. MP&L proposes that the sampling plan will provide 95 percent confidence that a support population which contains 10 per cent or more defective supports will be identified and evalt. ted. In addition, the Class 2 and Class 3 supports are combined in the proposed GGNS plan, and an inspection sample is selected from the combined group on the basis that the design criteria for the Class 2 and 3 supports are the same. While the ASME Code Committee is considering proposals for statistical sampling methods and the concept of combining Class 2 and 3 supports, these methods are not at present in Section XI. Statistical sampling has been used in technical specifications for the functional testing of snubbers.
The GGNS plan is based on ASME Section XI, 1977 Edition with Addenda through Summer 1979. Section IWF-2510 of this Addenda of the Code requires that:
(a) component supports selected for examination shall be the supports of those components that are required to be examined under IWB, IWC, and IWD during the first inspection interval; (b) for multiple components within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.
Pressure retaining piping is included as a component in accordance with IWA-1300. Exclusions for IWF are identified in the Code as "In the course of preparation." Those exclusions applicable to components under IWB, IWC, and IWD can be included in the selection of piping supports for examination.
NMELET PMI 368 ATT
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The staff cannot determine that the extent of examination and sample size proposed in the CGNS ISI plan is equivalent or superior to requirements of the applicable Addenda of the Code. The staff interprets the requirements of IWF to include the following:
(a) The exclusions contained in IWB-1220, IWC-1220, and IWD-1230 may be applied in the selection of component supports for examination (Reference IWF-2510(a)).
(b) For Class 1, 2, and 3 components, the supports in a " single loop" may be selected for examination. The supports of only one of multiple components, such as pumps and valves, within a system of similar design, function, and service are required to be examined (Reference IWF-2510(b)).
(c) Additional exclusions from examination will be considered on a
- case-by-case basis (Reference IWF-1230).
The staff recognized that the licensee has already addressed Item (a) but his interpretation of Items (b) and (c) is not clear. Therefore, the licensee should provide comparative information that will clearly establish the relationship between the requirements of the Code for Class 1, Class 2, and Class 3 piping supports and the initial sample size and expansion criteria proposed in his plan.
MP&L's RESPONSE Comparison of the Code Required Inspection Plan With GGNS Sampling Plan The GGNS sampling plan is based on a random statistical sampling over the total support population. The initial sample size and acceptance criteria is based on a performance criteria of 95/90 for the plan.
At completion of the total inspection there is a 95% confidence level that no more than 10% of the' supports are unacceptable in the entire population. On the other hand, the code requires an inspection of all supports in a single loop, and excludes supports in the remainder of multiple loops based on similarity. The code requirements provides a 100% confidence level that the loop examined has no unacceptable supports, but does not reflect conditions of supports in the remainder of multiple loops.
The inspection of random samples, when completed, will provide actual conditions of the total support population. Therefore, the GGNS pipe support sampling plan is superior to that required by the code. The comparisons between the code requirements and the GGNS sampling plan is presented below:
Class 1 Pipe Supports Table 1 (attached) shows a comparison of the GGNS sampling plan with code required inspections for Class 1 pipe supports. It should be noted that the initial sample size is smaller than required by code, but if the number of unacceptable supports exceeds that required by the 95/90 performance criteria, the total population (100%) of Class 1 supports will be examined during the inspection interval.
J14NMELET PMI 368 ATT
4 P ga 3 of 8 Class 2 and Class 3 Pipe Supports Table 2 (attached) shows a co$parison of the CGNS sampling plan with the code required inspectio~ns for" Class 2 and Class 3 pipe supports.
The total support population for GGNS includes supports on piping 2-1/2 l~ inch to 4-inch NPS (nominal pipe size). The code exempts supports on piping 4-inch NPS and under'.- It should be noted that the initial sample size used to_ meet the performance criteria of 95/90 is signi-ficantly less than that required by the code, but if the number of unacceptable supports exceed the acceptable criteria, an additional sample of similar size will be selected to meet the performance criteria of 95/90.
- 2) NRC COMMENT Section 1, Pages 4 and 7 As stated in Paragraph 2.2.3 of Section 1,10 CFR 50.55a(b)(2)(iv) requires that the Class 2; velds on RHR and ECCS systems be selected for examination per ASME Section XI 1974 Edition with Addenda. CGNS in Paragraph 2.2.3, proposes an alternate criterion for-selecting Class 2 welds on RHR and ECCS systems. A comparison of the sample size, obtained by using (1) the GGNS criteria and (2) the ASME Section XI 1974 Edition with Addenda through Summer 1975, is given in the answers to FSAR question 121.10, Reference 1. It indicates that the GGNS sample is larger by nearly>n factor of two in the number of welds to be examined per interval and in the total number of welds to be examined over the life of the plant. The methodology used to select the sample should be explained in the plan to demonstrate that the minimum requirements of the Code are met or exceeded, i.e., sample size alone does not meet the requirements of the Code. Specific types of welds must be included in the sample to meet the code requirements.
(. Please clarify the discrepancy in the number of Category C-F welds.
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J14NMELET PMI 368 ATT i
c Pigs 4 of 8 MP&L's RESPONSE As stated in the response to NRC Question 121.10 (AECM-81/334, dated September 1,1981), the Grand Gulf Nuclear Station weld selection criteria for the RHR and ECCS systems is a plant specific,' unique methodology. The weld selection criteria is a combination of the criteria contained in the 1974 Edition of ASME Section XI, 1977 Edition, Summer 1978 Addenda.
The earlier ASME Code criteria required examinations at physical configurations that could be categorized as structural discontinuities, i.e., circumferential weld joints with different base metal thickness, circumferential welds at or near anchor points, longitudinal welds in fittings, etc. The later ASME Code added stress limitations and dis-similar metal welds to the earlier Code's structural discontinuities, reduced the number of examinations for each system, and required that the initial welds selected be reexamined over the lifetime of the
' piping component. The 1977 Edition, Summer 1978 Addenda of the Code
'did not contain specific guidelines for RHR and ECCS.
The Grand Gulf Initial Ten Year Inservice Inspection (ISI) Program for the RHR and ECCS systems was based on the 1974 Edition, Summer 1975 Addenda identification of the physical piping system configurations that must be included in the overall population. From this population, a selection was made based on the selection criteria defined in Paragraph 2.2.3 of the Introduction to the ISI Program. These selection criteria are consistent with those identified in AECM-78/77. 11e ISI Program 'contains a cross-section of physical configurations as defined in Table IWC-2520 of the 1974 Edition, Summer 1975 Addenda of the Code, selected for the first ten year inter-val.
In addition to the requirements of the earlier Code, the GGNS program also applied the stress limitation and dissimilar metal weld criteria from the 1977 Edition, Summer 1978 Addenda of the Code to select the family of welds to be examined. Also included was the later Code's requirement for reexamination of the same weld.
By utilizing the previously stated criteria, the GGNS family of welds selected for inspection exceeds the quantity required by strict adherence to the 1974 Edition, Summer 1975 Addenda of the Code. The mix of the welds selected may differ slightly from the sampling guide-lines of the 1974 Edition, Summer 1975 Addenda, but the GGNS ISI plan includes those weld configurations which have been recognized in the piping industries as producing the highest stress points and are as such, more susceptible to failure.
Concerning the discrepancy in the number of Category CF welds, the ISI plan submitted for your review reflected the latest "As-Built" infor-
! mation where the earlier identified quantities were based on review of design and fabrication drawings. Also, the identification of welds, CF vs CG, is more consistent with the 1977 Edition, Summer 1978 Addenda designations, which provides better distinction between piping welds vs welds in pump casings or valve bodies.
NMELET PMI 368 ATT
Pags 5 of 8
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3)' NRC COMMENT General Several categories of the ASME Code require that all dissimilar metal welds and also those experiencing specified stress levels and loads be
. subjected to more extensive examination. The GGNS inservice inspection plan does not identify the welds that meet these criteria.
Please explain the methodology that was used to determine the extent of inspection and sample size for dissimilar metal welds and welds exceeding the stress levels specified in the Code.
MP&L's RESPONSE To identify those welds which should be included in the inspection sample due to stress levels, a review was performed on all the applicable ASME Section III stress analyses to identify any welds with calculated stress levels exceeding those specified in ASME Section XI, Tables IWB-and IWC-2500-1.
After applying the size' exemptions of Sections IWB and IWC and the pressure / temperature exemption of IWC-1220(b), the remaining population of dissimilar metal welds was established. The sample size was selected based on the requirements of Tables IWB-2500-1, Categories B-F and B-J, and IWC-2500-1, Category C-F.
For RHR and ECCS, the sample selection was based on the criteria identified in the response to Comment 2.
- 4) NRC COMMENT Appendixes Isometric Drawing RH-7-21 is apparently missing from the plan.
Please supply this drawing.
MP&L's RESPONSE Isometric Drawing RH-7-21 was inadvertently missed. The isometric is provided as an attachment to this response (see Figure 1).
- 5) RELIEF REQUEST
- 1. NRC COMMENT Relief Requests I-0003, I-00011, pages 4-8 and'4-38 ASME Section XI, Table IWC-2500-1, Examination Category C-F, Item C5.21 (I-00003) and CF.21 (I-00011) are referenced. Please clarify these references, since Category C-F is not part'of Table IWB-2500-1 and Item CF.21 is an incorrect designation.
NMELET PMI 368 ATT
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.4 MP&L's RESPONSE a). ' Relief Request I-00003,'Section 4, page 8:
. Paragraph III has been corrected to reference Table IWC-2500-1 (see Figure 2).
b)' Relie'f Request I-000ll, Section 4, page 38:
. Paragraph III has been corrected to reference Table IWC-2500-1 and' Item C5.21 (see Figure 3).
.2.
'NRC' COMMENT Relief Request I-00004, pages 4-9 through 4-11 Relief from volumetric examination of the lower one-half of the reactor pressure vessel lower head-to-shell weld (AA) is
- requested. The principal reason cited for requesting relief'is the unavailability of automated equipment to operate on the curved surface of the lower head. Please provide a dimensioned cross-sectional drawing of the lower head-to-shell weld that clearly shows changes in vessel wall thickness and vessel head curvature :b2 the region adjacent to the weld.
MP&L's RESPONSE-A'dimensioned cross-sectional drawing of the lower head-to-shell weld including wall-thickness and curvature is attached (see
. Figure 4).
3 .- NRC COMMENT Relief Requests I-00004, I-00005, I-00006, pages 4-9 through 4-20 Relief is requested from varying percentages of volumetric examination of three circumferential shell welds (AA, AB, and AC) of the' reactor pressure vessel. Please estimate the percentage of Code-required volume (CRV) that will be examined using planned
~
. volumetric methods.
Estimated personnel radiation exposures are cited in partial'
-support of these relief requests. -Have these estimated exposures
,been reviewed.with the MP&L group responsible for establishing and implementing ALARA exposure guidelines to determine that the benefit of performing manual examination is not consistent with ALARA?
Jl4NMELET PMI'368 ATT
,. P&gn 7 of 8 MP&L's RESPONSE Percentages of volumetric examination of shell welds AA, AB, and AC have been estimated. The following distinguishes portions performed by remote vs manual. ultrasonic techniques.
A. Seam "AA", Relief Request I-00004 Upper Portion - 100% UT by remote ultrasonics Lower Portion - 1.43% UT by manual ultrasonics due to presence of_three recordable indications.
(12"x12" area of recordable indications; shell cir. = 841.14", R = 133 15/16")
B. Seam "AB", Relief Request I-00005 Upper Portion - 100% UT by remote ultrasonics Lower Portion - 2.62% UT by manual ultrasonics due to presence of four recordable indications.
(13"x22" area of 4 recordable indications; shell cire. = 841.14", R = 133 15/16")
C. Seam "AC" 83% of total' seam performed by remote ultrasonics, as stated in relief request.
The Grand Gulf ALARA Committee has assessed the exposure levels discussed by the subject relief request and found them to be reasonable.
- 4. NRC COMMENT Relief Request 1-00010, pages 4-34 to 4-37 Relief is requested from volumetric examination of inaccessible Class 1 and Class 2 welds as detailed in Table 1 of the request.
The table includes three welds (Items 6, 7, and 8) designated on Isometrics FW-8-2, FW-8-4, and FW-11-7. Please confirm that-relief is requested for these welds in the feedwater system and that the system should be included in Paragraph I, component description.
MP&L's RESPONSE Relief Request I-00010, Section 4, page 34:
Paragraph I has been corrected to include the feedwater system as referenced in Table 1 o' Section 4, page 36 (see Figure 5).
NMELET PMI-368 ATT
4 .- Pagt 8 of 8
- 5. NRC COMMENT Relief Request I-00012 Relief is requested for volumetric examination of 25% of-the Class l' weld, Weld 592, located on.the reactor core isolation
- cooling system (RCIC,.E51). Table 1 in the relief request references Isometric Drawing R1-11-7, which is included in Volume III of.the proposed ISI program as Revision 0, dated 5/1/84.
Since this drawing does not indicate Weld 502, please provide a reference to the appropriate drawing which would illustrate the location and inaccessibility of the weld portion.
MP&L RESPONSE Relief Request I-00012 A partial revision of Isometric R1-11-7 is attached showing weld 502. This drawing is for reference only.and has not been issued as part'of Revision lyto the 10-year plan (see Figure 6).
NMELET PMI 368 ATT' -
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TABLE - 1 PIPE SUPPOKE SAWLING PIAN KR A9E Q. ASS 1 PIPING GCNS ISI MAN OGNS ISI CT E REQUIRED tl1' SUPPORT WrAL SIZE ITTILIZATING IN M E RESAMPLE WrE CAIE00RY POPULATI N MLTIPLE IDOP EXEMPTIN SAMEiE SIZE SIZE [2] [3]
SERING 69 45 40 29 69 RIGID (Std.Ca p.) 40 35 21 '19 40 RIGID (Frane) 85 74 40 45 85
'IUTAL 194 154 101 93 194
- 1. Code requires inapaction of all supports (100%) in a single loop and aclia supports on the remainder of the nultiple loops.
- 2. AMitimal inspection, if ramber of unauxptiule supports in the initial saple exceed the acceptance criteria.
- 3. All supports (100%) will be ==id within the inanacrim interval if the result of inspection of the initial saple is unacceptable.
lHEIEr IMI 368 ATI TABLE 1
,- a TABLE - 2 PIPE SUPIMI SAMPLING MAN RR ASME QASS 2 and QASS 3 PIPING
[1] 00DE REQUIIED [2]
SUPIMI CODE SIZE UIILIZATING TUTAL[3] INITIAL y CATE00RY IU H ATIW M]LTIPLE I E P ED W II m 1HRATIN SAMPIE SIZE SIZE TUTAI.
SPRING 67 42 79 40 39 79 ANOIR 42 30 66 40 26 66 RIGID (Std.Canp.) 489 350 712 100 100 200 RIGID (Frame) 322 238 638 100- 100 200 IUTAL 920 660 1495 280 265 545
- 1. Pipe supports on 4" NPS or under excluded.
- 2. Code requires inspection of all supratu (100%) in a single loop and =cliaa supports on the reneinder of the nultiple loops.
- 3. GWS ISI population incli*a supports on 2-1/2" to 4" NPS and does not exclude supports on similar loops.
- 4. Additional bu==ctim, if ranber of unacceptable supports in the initial sanple exceed the acceptance criteria. oms ney elect to use the equation shown in Table 3 to determine the size of additional sanples. g;.
MELEI PMI 368 ATI TABLE 2
TABLE - 3 FORMULA TO DETERMINE ADDITIONAL SAMPLE SIZE The following equation may be used to determine the size of the' additional:
samples.
N=Sj/ 2 T2 (a - c) where:. S = Initial Sample Size (c+1 e = Allowable number of defective supports a = Total number of defective supports in the total sample For c =.5 and S = 100, the first re-sample size will be N1 = 11.11 (a - 5).
Further sampling will continue according to the expression N2 = (b)(S) 2 2 where: b = No. of defective supports in the yc + l j
= (11.11) (b) previous re-sample.
This process will continue until no additional defective supports are found.
NMELET PMI 368 ATT TABLE 3
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FIGURE 2 INSERVICE INSPECTION REQUIREMENTS GENERALVI ELECTRIC SECTION 4 RELIEF REQUESTS PAGE 8 APPARATUS & ENGINEERING SERVICr.S GRAND GULF NUCLEAR STATION PAGE 1 of 1 UNIT 1 REQUEST FOR RELIEF NO. I-00003 INSERVICE INSPECTION OF-CIRCUMFERENTIAL DISSIMILAR METAL WELD I. Component: Circumferential dissimilar metal weld (FW-13) between reactor core isolation cooling (RCIC) line 20"-HBB-53 and 20"-HCB-29.
Line 20"-HCB-29 is the RCIC turbine exhaust sparger.
II. Code: The subject pressure retaining, circumferential, dissimilar metal weld is fabricated in accordance with ASME'Section III, Class 2 requirements. Inservice inspection is to be per-formed in accordance with ASME Section XI,1977 Edition through and including Sumer 1979 Addenda.
III. Code requirements: The pressure retaining, circumferential, dissimilar metal, Class 2 weld is regtdred to be surface (PT or MT) and volume-trically (ultrasonically) inspected once every ten-year interval in accordance with ASME Section XI, Table IWC-2500-1, Examination Category C-F, Item #C5.21, Note (1)(c).
IV. Information to The implementation of the code. requirement is impractical as .
support the deter . the subject weld is in constant contact with the water in the mination that the suppression pool. When the suppression pool is at its lowest code requirement level (Post-LOCA 111'-4 3/4"), the subject weld is submerged is impractical: under 6'-4 3/4" of water.
V. Specific relief Permission is requested to exempt RCIC turbine exhaust requested: sparger weld (FW-13) from inservice inspection, except as noted in alternative testing.
VI. Reasons why relief _ Request for exemption should be granted for the following should be granted: reasons:
- 1. The subject weld has been volumetrically examined by radiography and found acceptable in accordance with ASME Section III, Class 2 requirements.
- 2. The subject weld will only be exposed to design pressure and temperature a small percentage of the time the plant operates. The balance.of that time, it will see static conditions at near atmospheric pressure, along with relatively low temperatures.
- 3. The open area of the sparger hole is over 300% of the cross sectional area of the pipe itself. The steam will flow through the sparger relatively unimpeded, permitting only low pressure buildup in the pipe.
VII. Alternative No alternative testing is proposed at this time. However, if testing: the suppression pool is drained for other. reasons, inspection of the weld will be performed.
FIGURE 3 INSERVICE INSPECTION REQUIREMENTS G E N E R A L I[) E LECTRIC SECTION 4 PAGE 38 APPARATUS & ENGINEERING SERVICES RELIEF REQUESTS PAGE 1 of 5 GRAND GULF NUCLEAR STATION UNIT 1 REQUEST FOR RELIEF NO. I-00011 INSERVICE INSPECTION OF THERMAL TEE SLEEVE WELDS I. Component: Thermal tee sleeve welds D011-A-1 and D011-B-1 located on the residual heat removal (RHR). return from reactor water cleanup (RWCU) line (See attached sketch for location of the welds).
II. Code: Pressure retaining thermal tee sleeve welds 0011-A-1 &
00ll-B-1 were fabricated in accordance with ASME Section III, Class 2 requirements. Inservice inspections are to be performed in accordance with ASME Section XI,1977 Edition through and including Surmier 1979 Addenda.
III. Code requirements: Thermal tee sleeve welds are required to be surface (magnetic particle) and volumetrically (ultrasonic) inspected once every ten-year inservice inspection interval in accordance with ASME Section XI, Table IWC-2500-1, Exami-nation Category C-F, Item #C5.21.
IV. Information to Due to the dasign of the thermal tee sleeve, there is not support the deter- sufficient area to perform a meaningful ultrasonic exami-mination that the nation. Also, the position of the thermal sleeve, as well as code requirement lack of internal access, precludes the use .of radiography.
is impractical.
V. Reasons why relief Request for exemption from inservice volumetric (ultrasonics should be granted: and radiography) inspections of thermal tee welds 0011-A-1 and D011-B-1 on the RHR return to RWCU line, should be granted for the following reasons:
- 1. The thermal tee welds have been volumetrically examined by radiography and found acceptable in accordance with ASME Section III, Class 2 requirements.
- 2. The thermal tee welds have been surface examined by magnetic particle and found acceptable in accordance with ASME Section XI, Class 2 requirements.
- 3. The thermal tee welds will be subject to magnetic particle inspection every ten-year interval in accorda.cce with ASME Section XI, Class 2 requirements.
- 4. Thermal tee welds will be subject to a system pressure test in accordance with ASME Section XI, Class 2 requirements.
GRAND GULF UNIT ONE BOTTOM HEAD TO RING 4k I 7.6" - :
'SHELL RING # 1 l
l CL ADDING 6
4 '
RING # I TO BOTTOM HEAD 3 --
WELD ( AA)
E i BOTTOM HEAD 4
\[ -
5 6
7.25 SKIRT +
Y .
FIGURE 4
FIGURE 5 3 INSERVICE INSPECTION REQUIREMENTS G E N E R A L (v E LECTRIC SECTION 4 RELIEF REQUESTS PAGE 34 APPARATUS & ENGINEERING SERVICES PAGE 1 of 4 GRAND GULF NUCLEAR STATION UNIT 1 REQUEST FOR RELIEF N0. I-00010
_I__NSERVICE INSPECTION OF PRESSURE RETAINING WELDS I. Component: Inaccessible portions of Class I and Class II pressure retaining piping welds located on residual heat removal (RHR, E12),
reactor core isolation cooling (RCIC, E51), main steam (MS, B21) recirculation (Recirc., 833), reactor water cleanup (RWCU,G33),
and feedwater (FW, 821) systems. (See Table 1 for details)
II. Code: These portions of the pressure retaining piping welds were designed and fabricated to the ASME Section III, Class 1 and Class 2 requirements. Applicable inservice inspections are to be performed in accordance with the ASME Section XI,1977 Edition through and including Summer 1979 Addenda.
III. Code requirements: Class 1 and Class 2 pressure retaining piping welds are required to be volumetrically and surface examined, essentially 100% of the weld, once every ten-year interval in accordance with ASME Section XI, Table IWB-2500-1, Category.
B-J, Table IWC-2500-1, Category C-F.
IV. Information to Portions of welds that were preservice examined have physical support the deter- obstructions due to design, due to this limited accessibility, mination that the it is impractical to volumetrically examine 100% of the welds code requirements listed on Table 1.
are impractical:
V. Specific relief Permission is requested to exempt from volumetric examination requested: the inaccessible portions of the Class 1 and Class 2 welds listed on Table 1.
VI. Reasons why relief Request for an exemption should be granted for the following should be granted: reasons:
- 1. The inaccessible portions of listed welds were examined by radiography, passed in accordance with ASME Section III, Class 1 and Class 2 requirements.
- 2. The inaccessible portions of listed welds were surface examined (magnetic particle or liquid penetrant), passed in accordance with ASME III and/or XI, Class 1 and Class 2 requirements.
- 3. The inaccessible portions of listed piping welds.will be subject to a system leakage test after each refueling outage for Class 1, and each inspection period for Class 2 in accordance with ASME Section XI requirements.
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