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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20137N1591997-03-31031 March 1997 Informs That Licensee Facility Scheduled to Administer NRC GFE on 970409.Sonalsts,Inc Authorized Under Contract to Support NRC Administration of GFE Activities ML20058M0361993-04-12012 April 1993 Partial Response to FOIA Request for Documents.Forwards Records in App L Which Are Being Withheld Partially for Listed Reasons,(Ref FOIA Exemptions 5) ML20248D6521989-07-20020 July 1989 Forwards Response to Util Re Bills D0184 & D0185 for Plant OL Application Review Costs by Various Program Ofcs Through June 1984 ML20245D9621989-04-28028 April 1989 Forwards Addl Info Re Bunker Ramo Instrumentation Penetration Modules,Per 890131 Request.Util Believes That Modules Environmentally Qualified in Accordance w/10CFR50.49 & NUREG-0588,Category II ML20205C3521988-09-23023 September 1988 Final Response to FOIA Request for Documents Re Plant. Forwards App D Documents.App D Documents Also Available in PDR ML20155A7001988-06-0202 June 1988 Informs That Const on Conversion of Plant to gas-fired Facility Began on 880404 ML20155A7401988-05-18018 May 1988 FOIA Request for Documents on 850731 & 870312 Meetings Re Plant.Document Re 840314 Meeting Previously Obtained & Therefore Excluded from Request ML20237B4361987-12-14014 December 1987 Final Response to FOIA Request for Documents.App B Document, Board Notification 84-024,encl & Also Available in PDR ML20236X6141987-12-0808 December 1987 Final Response to FOIA Request All Documents.No Addl Records Subj to Request Located ML20236U2571987-11-0505 November 1987 FOIA Request for Documents Re Ball Type Main Steam Isolation Valves Used at Facilities ML20235B3081987-09-21021 September 1987 Responds to FOIA Request for Documents,Including AEC to ACRS Forwarding Safety Evaluation Re Zimmer.App a Documents Cannot Be Located.App B Documents in Pdr.App C & D Documents Withheld (Ref 10CFR2.790) ML20235M4251987-07-13013 July 1987 Partial Response to FOIA Request for Documents Re Acrs. Forwards Documents for Categories One & Three of FOIA Request.Review of 21 Addl ACRS Documents Continuing ML20235K1731987-07-0909 July 1987 Partial Response to FOIA Request for Info Re Certain Contracts Awarded by NRC for Reporting Svcs.Forwards App a & B Documents.Documents Also Available in PDR ML20234F0911987-06-26026 June 1987 Responds to Appeal Re Denial of FOIA Request for Documents. Forwards Document 5 in App F.Portions of Document 5 Withheld (Ref FOIA Exemptions 6 & 7).Other Requested Documents Withheld (Ref FOIA Exemption 6) ML20215K1981987-06-19019 June 1987 Final Response to FOIA Request for Documents Re Allegations Concerning Plant.Forwards App G & H Documents.Documents Also Available in Pdr.App H Documents Partially Withheld (Ref FOIA Exemption 6) ML20213F9351987-05-0808 May 1987 Partial Response to FOIA Request.Forwards App F Document & Weld Allegations.App G Documents Partially Withheld (Ref FOIA Exemption 6) ML20206H4951987-04-13013 April 1987 Partial Response to FOIA Request for Documents Re Bechtel Employment Discrimination.Forwards App E Documents.App D Documents Withheld (Ref FOIA Exemption 6) ML20235G2321987-04-0101 April 1987 FOIA Request for Documents Re Forged NDE Inspectors Certification Supplied by Barclay Intl for Use at Quad Cities Nuclear Station & Stated Investigations at Plants ML20211A9531987-02-13013 February 1987 Advises That Financial Info Submitted for 1987 in Util Satisfies Requirements of 10CFR140.21 That Each Licensee Maintain Guarantee of Payment of Deferred Premiums for Operating Reactors Over 100 Mwe ML20212M7651987-01-16016 January 1987 Informs That Due to Demands on Staff,Nrc Will Respond by 870430 to 850607 Request for Review of Invoices D0184 & D0185 Re OL Application Review Costs Through 840623 ML20207C0151986-12-19019 December 1986 Forwards Notice of Withdrawal of Application for OLs & Termination of Proceeding,Per Util 860711 Request & ASLB 861217 Memorandum & Order Granting Motion ML20207C1191986-12-18018 December 1986 Forwards Order Terminating CPPR-81 & CPPR-82 Based on Fact That Const of Facility Ceased,Units Inoperable & Site Environmentally Stable,Per Util 860701 Request to Withdraw Application to Amend CPs ML20215B9641986-12-0505 December 1986 Notifies Util of 870204-05 Early Emergency Responders Workshop in Chicago,Il to Discuss Lessons Learned & Current Problems in Coordination & Integration of Emergency Response Efforts.Meeting Agenda & Preregistration Form Encl ML20214Q0911986-11-24024 November 1986 Partial Response to FOIA Request for Documents Re Ofc of Inspector & Auditor Investigations.Forwards App B Documents. Documents Also Available in PDR ML20214A0761986-11-14014 November 1986 Forwards Insp & Evaluation of Plant for Adequacy of Stabilization Plan,Documenting 861015-16 Site Insp & Review & Insp of Site Stabilization Rept.Environ Stabilization Satisfactory ML20215N0241986-10-28028 October 1986 Forwards Order from DOE Economic Regulatory Admininstration Granting Exemption from Prohibitions of Power Plant & Industrial Fuel Act of 1978 & Puc of Mi Opinion & Order Granting Relief from Commission 850329 Rate Order ML20215M8851986-10-28028 October 1986 Forwards Insp Repts 50-329/86-01 & 50-330/86-01 on 861015-16.No Violations Identified ML20211B5401986-10-0909 October 1986 Further Response to FOIA Request for Eight Categories of Documents Re Ee Kent Allegations Concerning Facilities. Forwards Documents Listed in App K ML20210S9971986-10-0202 October 1986 Requests Change in Facility Svc List Address to Ref Address. Related Correspondence ML20210S4131986-09-26026 September 1986 Further Response to FOIA Request for 16 Categories of Records Re Facilities.Forwards App D & E Documents.Documents Also Available in PDR ML20214T7431986-09-24024 September 1986 Forwards Form 8-K Filed W/Securities & Exchange Commission. Util Believes Info Presented Bears No Issues Currently Before Aslb.Related Correspondence ML20214N4541986-09-0808 September 1986 Provides List of Activities Re Remedial Soils Work Being Modified Pending Final Disposition of Issues Described in Util 860701 & Counsel s Withdrawing Request for CP Extension.W/Svc List.Related Correspondence ML20209E6621986-09-0505 September 1986 Responds to FOIA Request for Documents Re Util Response to NRC 840112 Confirmatory Order.Documents Listed on App Available in PDR IA-86-235, Responds to FOIA Request for Documents Re Util Response to NRC 840112 Confirmatory Order.Documents Listed on App Available in PDR1986-09-0505 September 1986 Responds to FOIA Request for Documents Re Util Response to NRC 840112 Confirmatory Order.Documents Listed on App Available in PDR ML20212K9061986-08-21021 August 1986 Forwards Request for Addl Info Re Environ Review of Util 860711 Request to Withdraw Applications for OL by 860828 ML20206M8311986-08-15015 August 1986 Forwards Util Response to ASLB 860716 Order.W/O Encl.Related Correspondence ML20212J1391986-07-25025 July 1986 Forwards ALAB-106 Monthly Rept for June 1986.Listed Nonconformance Repts & Addl Documents Closed During June Encl ML20207D7261986-07-11011 July 1986 Forwards Motion for Authorization to Withdraw OL Application & for Dismissal of OL & Order of Mod Proceedings & Motion for Termination of Aslab Jurisdiction.W/O Encl.Related Correspondence ML20202F9581986-07-11011 July 1986 Forwards Util Motion for Authorization to Withdraw OL Application & for Dismissal of OL & Order of Mod Proceedings & Motion for Termination of Appeal Board Jurisdiction,For Filing.W/O Encl ML20203B2351986-07-10010 July 1986 Informs That Review of 820622 Application to Receive Unirradiated Nuclear Fuel Assemblies Terminated,Per .Fission Chambers Should Be Disposed of & Licenses SNM-1904 & SNM-1905 Terminated,Per 10CFR70.38(b) ML20206T2401986-07-0101 July 1986 Advises That Since Facility Formally Abandoned as Nuclear Facility,Util Will Not Reply to Generic Ltr 86-05 Re TMI Action Item II.K.3.5 ML20202B1091986-07-0101 July 1986 Forwards Evaluation of 13 Specific Recommendations Contained in BNL Rept of Review of Surveillance & Maint Program,In Response to CE Norelius 860506 Request ML20206T4321986-07-0101 July 1986 Withdraws Application for Ols.Facility Will Be Converted to combined-cycle gas-fired Plant.Abandonment Actions & Equipment Sales Will Provide Assurance That Plant Cannot Be Used as Nuclear Facility ML20199J9181986-06-30030 June 1986 Submits ALAB-106 Quarterly Rept 51.No New Individuals Assigned quality-related Duties.Const Shut Down Since 840716 & No Const Activities Projected for Jul-Sept 1986 ML20211L0361986-06-25025 June 1986 Forwards Bechtel & B&W Nonconformance Repts for May 1986,per Memorandum & Order ALAB-106 ML20198E9051986-05-25025 May 1986 Forwards ALAB-106 Monthly Rept for Apr 1986,including Nonconformance Repts,Quality Action Requests,Equality Audit Finding,B&W Repts of Nonconformance & Audit Finding Repts. Only Nonconformance Repts Encl ML20205P9331986-05-23023 May 1986 Responds to Generic Ltr 86-10, Implementation of Fire Protection Requirements. Project in Surveillance & Maint Mode.Generic Ltr & FSAR Update Will Be Reviewed When Project Restarted ML20203Q2891986-05-0606 May 1986 Forwards BNL Technical Rept, Surveillance & Maint..., Based on NRC 851014-18 Insp.No Violations Noted.Items Identified Could Have Impact on Later Project Restart. Evaluation of Rept Recommendations Requested within 60 Days ML20203N3901986-05-0101 May 1986 Forwards Rev 2 to Tdi Owners Group App Ii:Generic Maint Matrix & Justifications. Rev Approved by Tdi Owners Group & Tdi ML20205N5861986-04-29029 April 1986 Forwards Corrected Page 1 to JW Cook to H Berkow Re Pipe Whip Restraint Design.Last Line Inadvertently Eliminated When Ltr Originally Issued 1997-03-31
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20245D9621989-04-28028 April 1989 Forwards Addl Info Re Bunker Ramo Instrumentation Penetration Modules,Per 890131 Request.Util Believes That Modules Environmentally Qualified in Accordance w/10CFR50.49 & NUREG-0588,Category II ML20155A7001988-06-0202 June 1988 Informs That Const on Conversion of Plant to gas-fired Facility Began on 880404 ML20155A7401988-05-18018 May 1988 FOIA Request for Documents on 850731 & 870312 Meetings Re Plant.Document Re 840314 Meeting Previously Obtained & Therefore Excluded from Request ML20236U2571987-11-0505 November 1987 FOIA Request for Documents Re Ball Type Main Steam Isolation Valves Used at Facilities ML20216E4721987-05-28028 May 1987 Part 21 Rept 140 Re Potential Defect in Air Pressure Regulators Mfg by Bellofram.Dripwell Gasket May Fail Due to Mismachining of Gasket Seating Surface Causing Loss of Control Air & Starting Air Pressure ML20235G2321987-04-0101 April 1987 FOIA Request for Documents Re Forged NDE Inspectors Certification Supplied by Barclay Intl for Use at Quad Cities Nuclear Station & Stated Investigations at Plants ML20215N0241986-10-28028 October 1986 Forwards Order from DOE Economic Regulatory Admininstration Granting Exemption from Prohibitions of Power Plant & Industrial Fuel Act of 1978 & Puc of Mi Opinion & Order Granting Relief from Commission 850329 Rate Order ML20210S9971986-10-0202 October 1986 Requests Change in Facility Svc List Address to Ref Address. Related Correspondence ML20214T7431986-09-24024 September 1986 Forwards Form 8-K Filed W/Securities & Exchange Commission. Util Believes Info Presented Bears No Issues Currently Before Aslb.Related Correspondence ML20214N4541986-09-0808 September 1986 Provides List of Activities Re Remedial Soils Work Being Modified Pending Final Disposition of Issues Described in Util 860701 & Counsel s Withdrawing Request for CP Extension.W/Svc List.Related Correspondence ML20206M8311986-08-15015 August 1986 Forwards Util Response to ASLB 860716 Order.W/O Encl.Related Correspondence ML20212J1391986-07-25025 July 1986 Forwards ALAB-106 Monthly Rept for June 1986.Listed Nonconformance Repts & Addl Documents Closed During June Encl ML20207D7261986-07-11011 July 1986 Forwards Motion for Authorization to Withdraw OL Application & for Dismissal of OL & Order of Mod Proceedings & Motion for Termination of Aslab Jurisdiction.W/O Encl.Related Correspondence ML20202F9581986-07-11011 July 1986 Forwards Util Motion for Authorization to Withdraw OL Application & for Dismissal of OL & Order of Mod Proceedings & Motion for Termination of Appeal Board Jurisdiction,For Filing.W/O Encl ML20206T4321986-07-0101 July 1986 Withdraws Application for Ols.Facility Will Be Converted to combined-cycle gas-fired Plant.Abandonment Actions & Equipment Sales Will Provide Assurance That Plant Cannot Be Used as Nuclear Facility ML20202B1091986-07-0101 July 1986 Forwards Evaluation of 13 Specific Recommendations Contained in BNL Rept of Review of Surveillance & Maint Program,In Response to CE Norelius 860506 Request ML20206T2401986-07-0101 July 1986 Advises That Since Facility Formally Abandoned as Nuclear Facility,Util Will Not Reply to Generic Ltr 86-05 Re TMI Action Item II.K.3.5 ML20199J9181986-06-30030 June 1986 Submits ALAB-106 Quarterly Rept 51.No New Individuals Assigned quality-related Duties.Const Shut Down Since 840716 & No Const Activities Projected for Jul-Sept 1986 ML20211L0361986-06-25025 June 1986 Forwards Bechtel & B&W Nonconformance Repts for May 1986,per Memorandum & Order ALAB-106 ML20198E9051986-05-25025 May 1986 Forwards ALAB-106 Monthly Rept for Apr 1986,including Nonconformance Repts,Quality Action Requests,Equality Audit Finding,B&W Repts of Nonconformance & Audit Finding Repts. Only Nonconformance Repts Encl ML20205P9331986-05-23023 May 1986 Responds to Generic Ltr 86-10, Implementation of Fire Protection Requirements. Project in Surveillance & Maint Mode.Generic Ltr & FSAR Update Will Be Reviewed When Project Restarted ML20203N3901986-05-0101 May 1986 Forwards Rev 2 to Tdi Owners Group App Ii:Generic Maint Matrix & Justifications. Rev Approved by Tdi Owners Group & Tdi ML20205N5861986-04-29029 April 1986 Forwards Corrected Page 1 to JW Cook to H Berkow Re Pipe Whip Restraint Design.Last Line Inadvertently Eliminated When Ltr Originally Issued ML20197F8331986-04-28028 April 1986 Advises That Response to Generic Ltr 86-04 Re Engineering Expertise on Shift Inapproriate at Present Because Midland Not Currently Under Const.Commitment to Provide Info Will Be Added to Commitment Tracking Sys ML20210L2351986-04-25025 April 1986 Forwards ALAB-106 Monthly Rept for Mar 1986,including Nonconformance Repts,Quality Action Requests,Mgt Corrective Action Repts & Quality Audit Findings ML20203K8531986-04-23023 April 1986 Responds to NRC Re Allegation Concerning Adequacy of Pipe Whip Restraint Design.Project Records Placed in Storage & Personnel Performing Work Dispersed.Specific Design Approach Would Require Check of Records at Bechtel ML20203P1661986-04-21021 April 1986 Discusses 860407 Study Considering Options for Facility. Options Range from Abandonment of Facility to Completion as Nuclear Plant.Conversion of Plant to Combined Cycle gas-fired Plant Chosen as Most Favorable Option ML20209E6531986-03-28028 March 1986 FOIA Request for Documents Re Util Response to NRC 840112 Confirmatory Order ML20140F8781986-03-25025 March 1986 Forwards ALAB-106 Monthly Rept for Feb 1986,including Nonconformance Repts,Quality Action Requests,Mgt Corrective Action Repts & Quality Audit Findings ML20154H9651986-02-25025 February 1986 Forwards Nonconformance Repts Written or Closed During Jan 1986,per Memorandum & Order ALAB-106 ML20154D3581986-02-24024 February 1986 Confirms Items Agreed Upon in 860219 Telcon Re soil-related Issues.Util Will Discontinue Monitoring Dike Groundwater Wells During Shutdown & Site Maint.Authorization Given to Seal Weeping Wall Crack ML20198H2401986-01-24024 January 1986 Forwards ALAB-106 Monthly Rept for Dec 1985,including Bechtel Nonconformance Repts,Quality Action Requests,Mgt Corrective Action Repts & Quality Audit Findings ML20136F4771985-12-31031 December 1985 Forwards PNL-5718, Review of Tdi Diesel Generator Owners Group Engine Requalification Program,Final Rept, Technical Evaluation Rept ML20138Q5531985-12-31031 December 1985 Submits ALAB-106 Quarterly Rept 50.No New Individuals Assigned quality-related Duties Since 850930 Rept & No Const Activities Projected for Jan-Mar 1986 ML20136C5711985-12-20020 December 1985 Forwards Monthly Rept for Nov 1985,including Bechtel Nonconformance Repts,Quality Action Requests,Mgt Corrective Action Repts,Quality Audit Findings,B&W Repts of Nonconformity & Util Nonconformance Repts,Per ALAB-106 ML20138Q3871985-12-13013 December 1985 Ack Receipt of 851115 IE Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings. Valve Operability Program & Rept Scheduled to Be Completed Prior to OL Issuance ML20137Z1481985-11-27027 November 1985 Advises That Response to 851029 IE Bulletin 85-001, Steam Binding of Auxiliary Feedwater Pumps, Inappropriate at Present Since Plant in Surveillance & Maint Status.Schedule for Response Will Be Provided When Status Changes ML20137F2541985-11-25025 November 1985 Forwards ALAB-106 Monthly Rept for Oct 1985,including Bechtel Nonconformance Repts,Quality Action Requests,Mgt Corrective Action Repts & Quality Audit Findings,Per 730323 Order ALAB-106 & Amend 1 to Cp.Svc List Encl ML20138J4431985-10-25025 October 1985 Forwards Monthly Rept for Sept 1985,per Memorandum & Order ALAB-106 & Amend 1 to Cp,Including Bechtel Nonconformance Rept,Quality Action Requests,Mgt Corrective Action Repts, Quality Audit Findings & B&W Repts of Nonconformity ML20138D0031985-10-14014 October 1985 Informs That Util Will Submit Schedule for Meeting Requirements of 10CFR50.62(d) Per Generic Ltr 85-06 Re QA Guidance for ATWS nonsafety-related Equipment When & If Project Reactivated ML20133F7581985-10-0808 October 1985 Informs of Plans to Physically Disable Equipment Installed in & About Evaporator Bldg to Serve Process Steam to Dow Chemical Co,Per 850925 Resolution.Equipment & Structures Abandoned Are non-Q.Related Correspondence ML20137Y7921985-09-30030 September 1985 Submits Quarterly Rept 49,per ALAB-106.No New Individuals Assigned to quality-related Duties.Const at Plant Shut Down on 840716.No Const Projected for Fourth Quarter 1985.Next Quarterly Rept Will Be Submitted by End of Dec 1985 ML20133A3141985-09-27027 September 1985 Forwards Review of Section 4.7 of Technical Evaluation Rept PNL-5600, Review of Resolution of Known Problems in Engine Components for Tdi Emergency Diesel Generators, Reflecting Views Re Crankshafts for 16-cylinder Engines ML20133H1261985-09-25025 September 1985 Forwards Bechtel Nonconformance Repts,Quality Action Requests,Mgt Corrective Action Repts & Quality Audit Findings Written or Closed During Aug 1985,per Condition of Memorandum & Order ALAB-106 ML20138S0731985-09-17017 September 1985 Advises That Addl Excavation Between Tank Farm & Auxiliary Bldg Will Be Conducted Per NRC 850826 Authorization. Excavation Needed to Provide Supplemental Cathodic Protection.Svc List Encl.Related Correspondence ML20133H8841985-09-16016 September 1985 Discusses Ee Kent Allegations Re Plant,Per Encl . Decision Reflected in NRC Should Be Reconsidered. B Garde & T Devine of Gap Unwilling to Testify for Kent.Kent & Counsel Unable to Produce Expert Witnesses ML20140G8331985-08-23023 August 1985 FOIA Request for ACRS Documents Re Facility ML20137F7061985-08-12012 August 1985 Forwards Listed Documents Written or Closed During Jul 1985, in Accordance w/730323 Memorandum & Order ALAB-106 & Amend 1 to Cp.Only Nonconformance Repts Encl ML20133L8331985-08-0909 August 1985 Forwards Attachment 1 to Revised Exhibit D of Revised Compliance Filing & Application for Authorization to Issue Securities.Plan Is Requirement of Agreements W/Banks to Restructure Outstanding Debt.Related Correspondence ML20132B1841985-07-19019 July 1985 Forwards Monthly Repts for May & June 1985 Per Condition of 730323 Memorandum & Order ALAB-106 & Amend 1 to Cp.Related Correspondence 1989-04-28
[Table view] Category:UTILITY TO NRC
MONTHYEARML20245D9621989-04-28028 April 1989 Forwards Addl Info Re Bunker Ramo Instrumentation Penetration Modules,Per 890131 Request.Util Believes That Modules Environmentally Qualified in Accordance w/10CFR50.49 & NUREG-0588,Category II ML20155A7001988-06-0202 June 1988 Informs That Const on Conversion of Plant to gas-fired Facility Began on 880404 ML20155A7401988-05-18018 May 1988 FOIA Request for Documents on 850731 & 870312 Meetings Re Plant.Document Re 840314 Meeting Previously Obtained & Therefore Excluded from Request ML20215N0241986-10-28028 October 1986 Forwards Order from DOE Economic Regulatory Admininstration Granting Exemption from Prohibitions of Power Plant & Industrial Fuel Act of 1978 & Puc of Mi Opinion & Order Granting Relief from Commission 850329 Rate Order ML20214N4541986-09-0808 September 1986 Provides List of Activities Re Remedial Soils Work Being Modified Pending Final Disposition of Issues Described in Util 860701 & Counsel s Withdrawing Request for CP Extension.W/Svc List.Related Correspondence ML20212J1391986-07-25025 July 1986 Forwards ALAB-106 Monthly Rept for June 1986.Listed Nonconformance Repts & Addl Documents Closed During June Encl ML20206T2401986-07-0101 July 1986 Advises That Since Facility Formally Abandoned as Nuclear Facility,Util Will Not Reply to Generic Ltr 86-05 Re TMI Action Item II.K.3.5 ML20202B1091986-07-0101 July 1986 Forwards Evaluation of 13 Specific Recommendations Contained in BNL Rept of Review of Surveillance & Maint Program,In Response to CE Norelius 860506 Request ML20206T4321986-07-0101 July 1986 Withdraws Application for Ols.Facility Will Be Converted to combined-cycle gas-fired Plant.Abandonment Actions & Equipment Sales Will Provide Assurance That Plant Cannot Be Used as Nuclear Facility ML20199J9181986-06-30030 June 1986 Submits ALAB-106 Quarterly Rept 51.No New Individuals Assigned quality-related Duties.Const Shut Down Since 840716 & No Const Activities Projected for Jul-Sept 1986 ML20211L0361986-06-25025 June 1986 Forwards Bechtel & B&W Nonconformance Repts for May 1986,per Memorandum & Order ALAB-106 ML20198E9051986-05-25025 May 1986 Forwards ALAB-106 Monthly Rept for Apr 1986,including Nonconformance Repts,Quality Action Requests,Equality Audit Finding,B&W Repts of Nonconformance & Audit Finding Repts. Only Nonconformance Repts Encl ML20205P9331986-05-23023 May 1986 Responds to Generic Ltr 86-10, Implementation of Fire Protection Requirements. Project in Surveillance & Maint Mode.Generic Ltr & FSAR Update Will Be Reviewed When Project Restarted ML20203N3901986-05-0101 May 1986 Forwards Rev 2 to Tdi Owners Group App Ii:Generic Maint Matrix & Justifications. Rev Approved by Tdi Owners Group & Tdi ML20205N5861986-04-29029 April 1986 Forwards Corrected Page 1 to JW Cook to H Berkow Re Pipe Whip Restraint Design.Last Line Inadvertently Eliminated When Ltr Originally Issued ML20197F8331986-04-28028 April 1986 Advises That Response to Generic Ltr 86-04 Re Engineering Expertise on Shift Inapproriate at Present Because Midland Not Currently Under Const.Commitment to Provide Info Will Be Added to Commitment Tracking Sys ML20210L2351986-04-25025 April 1986 Forwards ALAB-106 Monthly Rept for Mar 1986,including Nonconformance Repts,Quality Action Requests,Mgt Corrective Action Repts & Quality Audit Findings ML20203K8531986-04-23023 April 1986 Responds to NRC Re Allegation Concerning Adequacy of Pipe Whip Restraint Design.Project Records Placed in Storage & Personnel Performing Work Dispersed.Specific Design Approach Would Require Check of Records at Bechtel ML20203P1661986-04-21021 April 1986 Discusses 860407 Study Considering Options for Facility. Options Range from Abandonment of Facility to Completion as Nuclear Plant.Conversion of Plant to Combined Cycle gas-fired Plant Chosen as Most Favorable Option ML20140F8781986-03-25025 March 1986 Forwards ALAB-106 Monthly Rept for Feb 1986,including Nonconformance Repts,Quality Action Requests,Mgt Corrective Action Repts & Quality Audit Findings ML20154H9651986-02-25025 February 1986 Forwards Nonconformance Repts Written or Closed During Jan 1986,per Memorandum & Order ALAB-106 ML20154D3581986-02-24024 February 1986 Confirms Items Agreed Upon in 860219 Telcon Re soil-related Issues.Util Will Discontinue Monitoring Dike Groundwater Wells During Shutdown & Site Maint.Authorization Given to Seal Weeping Wall Crack ML20198H2401986-01-24024 January 1986 Forwards ALAB-106 Monthly Rept for Dec 1985,including Bechtel Nonconformance Repts,Quality Action Requests,Mgt Corrective Action Repts & Quality Audit Findings ML20138Q5531985-12-31031 December 1985 Submits ALAB-106 Quarterly Rept 50.No New Individuals Assigned quality-related Duties Since 850930 Rept & No Const Activities Projected for Jan-Mar 1986 ML20136C5711985-12-20020 December 1985 Forwards Monthly Rept for Nov 1985,including Bechtel Nonconformance Repts,Quality Action Requests,Mgt Corrective Action Repts,Quality Audit Findings,B&W Repts of Nonconformity & Util Nonconformance Repts,Per ALAB-106 ML20138Q3871985-12-13013 December 1985 Ack Receipt of 851115 IE Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings. Valve Operability Program & Rept Scheduled to Be Completed Prior to OL Issuance ML20137Z1481985-11-27027 November 1985 Advises That Response to 851029 IE Bulletin 85-001, Steam Binding of Auxiliary Feedwater Pumps, Inappropriate at Present Since Plant in Surveillance & Maint Status.Schedule for Response Will Be Provided When Status Changes ML20137F2541985-11-25025 November 1985 Forwards ALAB-106 Monthly Rept for Oct 1985,including Bechtel Nonconformance Repts,Quality Action Requests,Mgt Corrective Action Repts & Quality Audit Findings,Per 730323 Order ALAB-106 & Amend 1 to Cp.Svc List Encl ML20138J4431985-10-25025 October 1985 Forwards Monthly Rept for Sept 1985,per Memorandum & Order ALAB-106 & Amend 1 to Cp,Including Bechtel Nonconformance Rept,Quality Action Requests,Mgt Corrective Action Repts, Quality Audit Findings & B&W Repts of Nonconformity ML20138D0031985-10-14014 October 1985 Informs That Util Will Submit Schedule for Meeting Requirements of 10CFR50.62(d) Per Generic Ltr 85-06 Re QA Guidance for ATWS nonsafety-related Equipment When & If Project Reactivated ML20137Y7921985-09-30030 September 1985 Submits Quarterly Rept 49,per ALAB-106.No New Individuals Assigned to quality-related Duties.Const at Plant Shut Down on 840716.No Const Projected for Fourth Quarter 1985.Next Quarterly Rept Will Be Submitted by End of Dec 1985 ML20133H1261985-09-25025 September 1985 Forwards Bechtel Nonconformance Repts,Quality Action Requests,Mgt Corrective Action Repts & Quality Audit Findings Written or Closed During Aug 1985,per Condition of Memorandum & Order ALAB-106 ML20138S0731985-09-17017 September 1985 Advises That Addl Excavation Between Tank Farm & Auxiliary Bldg Will Be Conducted Per NRC 850826 Authorization. Excavation Needed to Provide Supplemental Cathodic Protection.Svc List Encl.Related Correspondence ML20140G8331985-08-23023 August 1985 FOIA Request for ACRS Documents Re Facility ML20137F7061985-08-12012 August 1985 Forwards Listed Documents Written or Closed During Jul 1985, in Accordance w/730323 Memorandum & Order ALAB-106 & Amend 1 to Cp.Only Nonconformance Repts Encl ML20132B1841985-07-19019 July 1985 Forwards Monthly Repts for May & June 1985 Per Condition of 730323 Memorandum & Order ALAB-106 & Amend 1 to Cp.Related Correspondence ML20128M1471985-07-19019 July 1985 Forwards Nonconformance Repts for May & June 1985,per 730323 Memorandum & Order ALAB-106 & Amend 1 to Facility CP ML20140G3691985-06-28028 June 1985 Responds to Generic Ltr 85-07,dtd 850502,re Implementation of Integrated Schedules for Plant Mods.Util Will Initiate Participation in Integrated Living Schedule If Project Reactivated.Survey Form Encl ML20127P1951985-06-28028 June 1985 Submits Quarterly Rept 48 Per ALAB-106.Const Shut Down Since 840716.No Const Activities Projected for Jul-Oct 1985.Next Rept Will Be Sent by End of Sept 1985 ML20128B8131985-06-20020 June 1985 Confirms 850610 Telcon W/D Hood Re Detailed Schedule for Shunt Trip Mods & Tech Spec Rev Established Per Generic Ltr 83-28,Items 4.3 & 4.4 (Generic Ltr 85-10).Schedule Commitment Entered Into Commitment Tracking Sys ML20127A9901985-06-17017 June 1985 Responds to Generic Ltr 85-02 Re Recommended Actions to Assure Steam Generator Tube Integrity & Rupture Mitigation. Facility Steam Generators in long-term Dry Layup Since Project Shut Down in Jul 1984 ML20126K2871985-06-0707 June 1985 Requests Extension of Due Date for Payment of Bill to Facilitate Resolution of Contested Fees.Conference to Discuss Billing Procedures Also Requested.Review of Info Re Bills Do 184 & Do 185 Encl ML20129B7261985-05-25025 May 1985 Forwards Bechtel Nonconformance Repts,Quality Audit Findings,B&W Repts of Nonconformity,Util Nonconformance Repts,Audit Finding Repts & Quality Action Requests for Apr 1985,per ALAB-106 ML20133C3771985-05-24024 May 1985 Responds to Request for Info on Item 13 in BNL Rept Re Exposure Time of Low Hydrogen Electrodes to Environ After Removal from Hermetically Sealed Containers or Drying/ Storage Ovens.Related Correspondence ML20133D9421985-05-0707 May 1985 Confirms 850426 Telcon Re Backfilling Number of Excavations of Site.Excavations Left Open Due to Removal of Temporary Freezewall Apparatus Last Fall.M Sinclair Response to Aslab 850423 Order & Svc List Encl ML20117J6761985-05-0707 May 1985 Submits ALAB-106 Quarterly Rept 47.No New Individuals Assigned quality-related Duties Since Last Rept.No Const Activities Projected for Apr-June 1985.Next Rept Will Be Sent in June 1985 ML20117G0641985-04-29029 April 1985 Responds to 850425 Request for Addl Info Re Recent Organizational Changes,Per 850425 Telcon.Announcement Involves Resolution of Legal Proceeding Surrounding Project & Possible Sale of Facilities ML20116E8611985-04-25025 April 1985 Forwards Bechtel & Util Nonconformance Repts,Quality Action Requests,Mgt Corrective Action Repts,Quality Audit Findings & B&W Repts of Nonconformity for Jan & Feb 1985,per Memorandum & Order ALAB-106 ML20117G0831985-04-22022 April 1985 Informs of Reorganization Changes to Increase Efficiency of Energy Supply & Assimilate Certain Portions of Projects, Engineering & Const Organization ML20116D3371985-04-19019 April 1985 Ack Receipt of Jan 1985 BNL Rept Re Welding Allegations Encl w/850322 Ltr.Portion of Issues Closed.Remaining Open Issues Impracticable to Close Due to Lack of Resources. Investigation May Resume in Event of Restart 1989-04-28
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Director of Nuclear Reaction Regulation '
[ 1 Attn: Mr. Roger Boyd, Acting Director
@[T OgI A I Division of Reactor Licensing /- ' /*
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U.S. Nuclear Regulatory Co= mission e~ fI Vashington, D.C. 20555 D - /g8s[ O' ,d '
\'n MIDLAND PROJECT DOCKET NUMBERS 50-329, 50-330
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,(N N.'c.','q 7g e REGULATORY GUIDE ESTINGS FILE: 0505 SERIAL: 1856 We are attaching herewith 10 copies of the Consumers Power Ccmpany positions on implementation of Regulatory Guides 1.20, 1.26, 1.29, 1.46, 1.48, 1.67 and 1.72.
These Regulatory Guides are on the agendc for discussion in the Mechinical l Engineering Regulatory Guide meeting which has been scheduled for November 18, 1975 by your staff. )
Also attached are 10 copies of the Consuner's position on implementation of Regulatory Guide 1.40. This Regulatory Guide has been removed from the agenda for the Mechanical meeting and placed on the agenda for the Electrical / Control Systems meeting scheduled for November 13, 1975 by your staff. It should be added to the set of positions transmitted with our letter of July 21, 1975.
THIS DOCUMENT CONTAINS P00R QUAUTY PAGES l R. C. Bauman Project Engineer ~~'
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REGULATORY GUIDE 1.20 VIBRATION MEASUREMENTS ON REACTOR INTERNALS (December 29, 1971)
- For equipment within the B&W scope of supply, the degree of compliance with this Regulatory Guide is as follows:
The preoperational vibration monitoring program for these units will be in compliance.with parts d.1 and 2 of this guide. The prototype unit for these internals is the Oconee Unit 1. This test program is described in B&W topical reports BAW-10038, " Prototype Vibration Measurement Program for Reactor Internals," Rev. 1, November 1972, and BAW-10039,
" Prototype Vibration Measurement Results for B&W's 177-Fuel Assembly 2 Loop Plant," April 1973.
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a REGULATORY GUIDE 1.26 QUALITY GROUP CLASSIFICATION AND STANDARDS (June 1975)
RESPONSE TO RI:GULATORY POSITION Quality group classifications and code requirements for components of plant prccess systems meet the intent of Regulatory Guide 1.26. Certain clarifications and specific exceptions to the guide are discussed below.
(1) Paragraphs A and B There is a different usage of the term "important to safety" than that used elsewhere in the regulations and regulatory guides. The guide includes components which fall into quality group D under the definition of "important to safety," which implies that a quality assurance program in accordance with 10 CFR Part 50, Appendix B, should be applied. Quality assurance require-ments are not applied to quality group D components.
The definition of the term "important to safety," insofar as quality assurance is concerned, is considered to be that which appears in the introduction of Regulatory Guide 1.29.
(2) Midland quality group classifications are reflect.ed in PSAR Figure 4.1-1 submitted to the NRC by Amendment No. 26. We are aware of the following open items as discussed in the November 1, 1974 letter from A. schwencer (NRC) to S. H. Howell (CPCo) :
- a. The feedwater ring header is ANS'I B31.1.0 vs ASME III-2. This is due to the fact that this component was purchased in 1968.
- b. Portions of the reactor coolant pump seal injection system are ASME III-3 vs ASME III-2. These lines were designated ASME III-3 because they fall under the requirements of Regulatory Guide Position C-2.b.
- c. Except for ASME Section III Class 3 piping to the first isolation valve of the RCP seal cooler /
motor cooler, the CCW supply pipe is B31.1 to the RCP coal cooler / motor coolcr, the letdown cooler and the seal return cooler. As indicated in PSAR section 4.2.2.4, loss of CCW to the RCP seals does not preclude cooling of the seals since seal
' injection water is available. Also, as discussed in 4.2.2.4, loss of CCW to the seal return coolers does not affect operation of the RCPs.
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G REGULATORY GUIDE'l.26 (cont'd)
The letdown line is not necessary following a LOCA,-and is isolated through the use of an ECCAS signal. The letdown coolers are not sized to handle any significant cooling (16 x 10 6 Btu /hr with a log mean temperature difference (LMTD) of 124 0F.) Follow-ing a LOCA, the RC temperature would drop rapidly which decreases the temperature difference and the heat transferred by this cooler. The decay heat coolers are sized to handle 30 x 106 Btu /hr at an LMTD of 15.
Even for the case where the RC pressure stays up follow-ing a LOCA,,the decay heat pumps would be used as booster pumps for the makeup pumps with the decay heat coolers handling the recirculation flow adequately, even assuming a single failure. At the present time our system controls do not allow the H.P. pumps to take suction from the makeup tank following a LOCA.
Thus, it would be difficult to use the letdown coolers as a backup for the decay heat coolers.
- d. In addition we'wish to clarify one area of possible misinterpretation on Figure 4.1-1. The piping in the.
chemical addition system from the tanks to the pumps and from the pumps to the makeup and purification
' system is designed to ANSI B31.1.0. This is not clearly indicated on' Figure 4.1-1. This classification is made since this system does not serve a safety function.
The quality group B seismic Class 1 BWSTs provide the
. boric acid required to bring the reactor to a cold shutdown condition.
(3) Position Col.d The words "or remote manual" are considered to be inserted after the word " automatic" in the seventh line of the paragraph. This option is included to avoid an unnecessary complication (leading to decreased plant reliability) in lines which would not normally be provided with automatic closing valves.
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REGULATORY GUIDE 1.26 (cont ' d)
(4) Position C.2.c -
Systems connected to the reactor coolant pressure boundary are quality group D beyond the second isolation valve that is either normally closed or capable of automatic or remote manual closure.
(5) Position-C.2.d and e Radioactive waste systems and other systems "that contain or may contain radioactive material," are divided between quality groups C and D based on an offsite dose resulting from failure of components in the systems. The dividing line value of 0.5 rem, which appears to be based on,the normal annual release limits of 10 CFR Part 20, is inappropriate for the types of failures which the guide is addressing. Quality group D is applied to such systems unless their failure would result in offsite doses approaching the guideline values of 10 CFR Part 100.
(6) Amendment 30 to the Midland PSAR discusses the use of concrete pipe in a portion of the ultimate heat sink. -
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REGULATORY GUIDE 1.29 SEISMIC DESIGN CLASSIFICATION (August 1973)
RESPONSE TO REGULATORY POSITION Seismic design classification for plant structures, systems, and components meets the intent of Regulatory Guide 1.29.
In order to meet the intent of the Regulatory Guide, certain clarifications.of the guide are necessary. The following items describe these clarifications and specific exceptions to the guide.
(1) As indicated in the introduction section of.the guide all plant items important to safety should be designed for a safe shutdown earthquake. (SSE) .* All plant items which are necessary to cope with a loss of coolant accident '(LOCA) or to shut the plant down saf31y following an SSE in the absence of.a LOCA are designed for the SSE. There are,
'however, some plant items not required following an SSE but which are required to cope with other natural phenomena.
For example, a plant item which is required to function only during or following a tornado in order to achieve a safe plant shutdown must be considered important to safety.but design of the item for,an SSE is unnecessary.
Further, there are plant items which serve to mitigate the consequence of certain in-plant occurrences (other than LOCA) which are not considered to occur simultaneously with an SSE. Examples of the latter are fuel handling or spent fuel cask accidents and loss of control room habitability. This point.does not conflict with the regulatory position of the guide, but is noted here to clarify the. fact that certain items not listed in Regulatory Guide 1.29 are considered important to safety and therefore subject to quality assurance coverage in accordance with 10 CFR Part 50, Appendix B.
(2) Position C.l.d Systems required for reactor' shutdown or residual heat removal must be designed for the SSE. This is interpreted to' include only those minimum systems which must function in the performance of an orderly shutdown and in mainten-ance of the plant in'the shutdown condition. For the reasons
-stated in the response to Regulatory Guide 1.26 the cooling water to the letdown coolers is not designed to seismic Class 1 standards. The chemical addition system is not designed to r nn . - -
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REGULATORY GUIDE 1.29 (cont'd) seismic Class 1 requirements since the BWSTs can provide sufficient boric acid for reactor shutdown /cooldown after a seismic event. The water / boric a.cid in the nWST is used to complete an orderly feed without bleed shutdown /cooldown
.of the reactor plant in the event that the letdown system and chemical' addition systems are unavailable.
(3) Position C.l.f The words "or remote manual" are considered to be inserted after the word " automatic" in the eighth line of the paragraph. This option is included to avoid an unnecessary complication (leading to decreased plant reliability) in main steam branch lines which would not normally be provided with autcmatic closing valves.
(4) Position C.l.h Since the reactor coolant pumps do not perform any safety function, and since failure of the reactor coolant pumps due to cooling water system failure does not have safety implications (see PSAR Section 4.2.2.4) the cooling water
- system for the reactor coolant pumps is not designed to withstand an SSE.
(5) Position C.l.p and q These paragraphs cover radioactive waste systems and other systems "that contain or may contain radicactive material," and set a dividing line between seismic Category I and non-seismic Category I based on an offsite dose resulting from failure of components in the systems.
The dividing line value of 0.5 rem, which may be based on the normal annual release limits of 10 CFR Part 20, conflicts directly with the third paragraph of the introduction to the guide. Such systems are not designed for the SSE unless their failure would result in offsite doses approach-ing the guideline values of 10 CPP.Part 100.
(6) Position C.2 Portions of structures, systems, or components not designed as seismic Class 1 whose failure could reduce the function-ing of any safety related component to an unacceptable level will be analyred to insure that such failure will not occur under seismic loading.
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REGULATORY GUIDE 1.29 (cont'd)
(7) Position C.4 Quality assurance requirements of 10CFR50 Appendix B are not applied to components discussed in Position C.2 above.
(8) To clarify a point discussed in A. Schwencer's letter to S. Howell dated November 1, 1974, we point out that all ASME III Class 3 components designed and/or purchased to date are seismic Class 1.
" Design Basis Earthquake," is equivalent to " Safe Shutdown Earthquake."
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4 REGULATORY GUIDE 1.46 PROTECTION AGAINST PIPE WHIP INSIDE CONTAINMENT (May 1973)
RESPONSE TO REGULATORY POSITION The-requirements of the Regulatory Guide are met. The following clarifications are required to describe our analysis:
Paragraph B High energy fluid systems are defined as in APCSB 3-1 and MEB 3-1.
C.1 The B&W piping systems were designed in accordance with the ANSI B-31.7 Code. Break locations will be chosen utilizing the Regulatory Position for ASME Section III Code Class 1 piping.
C.l.b ASME Section III Code Class 1 piping breaks will be postulated to occur at any intermediate locations where th3 primary plus secondary stress intensities derived on in clastically calculated basis under the loadings associated with specified seismic events and normal plant conditions (plant operating conditions during reactor startup, operation at power, hot standby, or reactor cooldows to cold shutdown condition) exceed 2 Sm for ferritic steel and 2.4 Sm for austenitic steel.
. C.l.d Intermediate break locations for ASME Section III Code Class 1 piping, in addition to those determined by lb and 1c, will be selected on the basis of maxi- -
mum stress intensity or changes in the coordinate plane of the line. As a minimum, there will be two intermediate locations for each piping run or branch run.
C.2.c No fatigue analysis of ASME Section III Code Class 2 or 3 piping will be done.
C.2.d Intermediate break locations for ASME Section III Code Class 2 and 3 piping, in addition to those determined by 2b and 2c, will be selected on the basis of maximum stress intensity or changes in the coordinate plane of the line. As a minimum, there will be two intermediate locations for each piping run or branch run.
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REGULATORY GUIDE 1.46 (cont'd)
Footnote 10 - Break area for longitudinal breaks is assumed to be equal to the effective cross-
. sectional flow area upstream of the break only.
C.3 For that portion of the decay heat system which is high energy for only short operational periods, we will postulate critical cracks
- in lieu of cir-cumfere.ntial or longitudinal breaks.
- Critical cracks are assumed to be 1/2 the pipe diameter in length and 1/2 the pipe wall thickness in width.
On the topic of high energy line breaks we wish to obtain clarification of the Commission's statements 3 and 4 of A. Schwencer's October 18, 1974 letter to CPCo, a copy of which is attached.
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REGULATO,RY GUIDE 1.67 INSTALLATION OF OVERPRESSURE ,
PROTECTION DEVICES (October 1973)
RESPONSE TO REGULATORY POSITION Compliance with ASME Code Case 1569, " Design of Piping for Pressure Relief Valve Station," as supplemented by Regulatory Guide 1.67, is subject to the folicwing:
(1) The specifications are applicable to open discharge, simple configurations of stack, non-water seal and non-slug flow, relief or safety valves.
(2) Regulatory Position C.1 of Regulatory Guide 1.67 requires that the magnitude of the reaction force, the anticipated transient behavior, and the basis for theirspecification design determinationforshould be included in the the valve. Since all of the above are characteristic to each valve manu-facturer, it is not current practice to stipulate these data. Rather, the manufacturer supplies that information after selection of the valve, orifice size, inlet and outlet O.D., etc., to accommodate the flow rates required by the Design Specification.
This manufacturer supplied infcrmation is then used in the design of the relief / safety valve station.
(3) Response to Regulatory Position C.2 RV connections are spaced on the header so that there is no local interaction. The total forces and moments on the header resulting from simul-taneous discharge of all RVs are included in the stress analysis of the header and its supporting restraint system.
(4) Response to Regulatory Position C.3 The design of relief valve (RV) stations includes the considerations of both local stresses at the header-to-RV inlet piping junction and the stresses in the RV inlet piping and header.
(5) Response to Regulatory Position C.4 Forces and moments on the piping resulting from thrust developed by full opening of the RV are considered in the stress analysis. Dynamic Ampli-
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Response to Regulatory Position C.4 co'.?
c t fication factors are considered in the design.
The dynamic amplification factor is defined as '
the ratio of the actual deflection of the relief valve to the static deflection. The actual deflec-tion is calculated by modeling the valve header assembly as a single degree of freedom equiva? ant spring-mass system; the response due to the forced vibration is then calculated.
In lieu of the above procedure, some history-dynamic calculation may be uced.
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1 REGULATORY GUIDE 1.72 SPRAY POND PLASTIC PIPING .
RESPONSE TO REGULATORY POSITION
, Regulatory Guide 1.72 does not apply to the Midland facility since spray ponds are not used.
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. REGULATORY GUIDE 1.40 QUALIFICATION TEST OF CONTINUO *JS-DUTY MOTORS INSTALLED INSIDE Tile CONTAINMENT .
OF k'ATER-COOLED NUCLEAR P0k'ER PLANTS RESPONSE TO REGULATORY POSITION ,
The requirements of Regulatory Guide 1.40 are met as follows:
- 1. The reactor building cooler' motors are the only applicable motors in the Midland Plant.
- 2. To the extent practicable, auxiliary equipment that will be part of the installed motor assembly will also be qualified in accordance with IEEE Standard 334-1971.
- 3. The qualification will simulate as closely as practical all design l basis events which affect operation of the motor's auxiliary equipment.
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