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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M8851999-10-0808 October 1999 Informs of Staff Determination That Listed Calculations Should Be Withheld from Public Disclosure,Per 10CFR2.790, as Requested in 990909 Affidavit ML20211J7731999-08-31031 August 1999 Forwards Insp Rept 50-312/99-03 on 990802-06.No Violations Noted.Insp Included Decommissioning & Dismantlement Activities,Verification of Compliance with Selected TS & Review of Completed SEs ML20211H7481999-08-13013 August 1999 Forwards Amend 126 to License DPR-54 & Safety Evaluation. Amend Changes Permanently Defueled Technical Specification (PDTS) D3/4.1, Spent Fuel Pool Level, to Replace Specific Reference to SFP Level Alarm Switches with Generic Ref 3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held ML20210H9541999-07-0707 July 1999 Informs NRC of Change to Rancho Seco Decommissioning Schedule,As Described in Licensee Post Shutdown Decommissioning Activities Rept ML20209D2501999-06-24024 June 1999 Informs That Util Has Revised All Sections of Rancho Seco Emergency Plan (Rsep),Change 4,effective 990624 ML20196G0431999-06-22022 June 1999 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Smud Rancho Seco Nuclear Generating Station ML20195D1851999-05-27027 May 1999 Forwards Rancho Seco Annual Rept, IAW Plant Permanently Defueled TS D6.9.4 & D6.9.6b.Rept Contains Shutdown Statistics,Narrative Summary of Shutdown Experience,Er Info & Tabulation of Facility Changes,Tests & Experiments ML20195B8511999-05-27027 May 1999 Forwards Change 4 to Rancho Seco Emergency Plan, Incorporating Commitments Made to NRC as Outlined in NRC .Emergency Plan Includes Two Listed Supporting Documents ML20207E9181999-05-27027 May 1999 Informs That Effective 990328,NRR Underwent Reorganization. within Framework of Reorganization,Div of Licensing Project Mgt Created.Reorganization Chart Encl ML20206U7411999-05-18018 May 1999 Provides Summary of 990217-18 Visit to Rancho Seco Facility to Become Familar with Facility,Including Onsite ISFSI & Meeting with Representatives of Smud to Discuss Issues Re Revised Rancho Seco Ep,Submitted to NRC on 960429 ML20206M1611999-05-10010 May 1999 Forwards Listed Proprietary Calculations to Support Review of Rancho Seco ISFSI Sar.Proprietary Encls Withheld ML20206E8591999-04-12012 April 1999 Provides Info Re High Total Coliform Result in Plant Domestic Sewage Effluent Prior to Confluence with Combined Effluent.Cause of High Total Coliform Result Was Broken Flow Rate Instrument.Instrument Was Repaired on 990318 ML20204H6751999-03-19019 March 1999 Forwards Insp Rept 50-312/99-02 on 990309-11.No Violations Noted.Portions of Physical Security & Access Authorization Programs Were Inspected ML20204E4031999-03-16016 March 1999 Submits Rept of Status of Decommissioning Funding for Rancho Seco,As Required by 10CFR50.75(f)(1).Plant Is Currently in Safstor, with Operating License Scheduled to Expire in Oct 2008 ML20204E6661999-03-11011 March 1999 Forwards Rancho Seco Exposure Rept for Individuals That Received Greater than 100 Mrem During 1998,IAW TS D6.9.2.2 & NRC Regulatory Guide 1.16 ML20204E6441999-03-11011 March 1999 Forwards Individual Monitoring Repts for Personnel That Required Radiation Exposure Monitoring During 1998 ML20207L1711999-03-10010 March 1999 Informs of Staff Determination That Supporting Calculations & Drawings Contained in Rev 2 of Sar, Should Be Withheld from Public Disclosure,Per 10CFR2.790 NL-99-002, Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3)1999-03-10010 March 1999 Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20207D4431999-03-0101 March 1999 Forwards Annual Radioactive Effluent Release Rept, for Rancho Seco Nuclear Generating Station for 1998 ML20207H6181999-02-18018 February 1999 Provides Attached Metrix & Two Copies of Rancho Seco ISFSI Sar,Rev 2 on Compact Disc,As Requested in 990209 Meeting. First Rounds of RAIs Dealt Primarily with Use of Cask as Storage Cask.Without Compact Disc ML20203D0761999-02-10010 February 1999 Ltr Contract:Task Order 37 Entitled, Technical Assistance in Review of New Safety Analysis Rept for Rancho Seco Spent Fuel Storage Facility, Under Contract NRC-02-95-003 ML20155D4431998-10-27027 October 1998 Forwards Amend 3 to Rancho Seco Dsar,Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode.With Instructions & List of Effective Pages NL-98-032, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1998-09-30030 September 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util ML20237A6031998-08-0707 August 1998 Forwards Insp Rept 50-312/98-03 on 980706-09.No Violations Noted ML20237A9481998-08-0303 August 1998 Forwards Smud 1997 Annual Rept, IAW 10CFR50.71(b),which Includes Certified Financial Statements ML20236Q9461998-07-15015 July 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-02 ML20236J6331998-06-30030 June 1998 Forwards Response to Violations Noted in Insp Rept 50-312/98-02.Corrective Actions:Util Revised RSAP-1003 to Clarify District Security Staff Responsibilities Re Handling & Review of Criminal History Info ML20236E8211998-06-0303 June 1998 Forwards Insp Rept 50-312/98-02 on 980519-21 & NOV Re Failure to Review & Consider All Info Obtained During Background Investigation.Areas Examined During Insp Also Included Portions of Physical Security Program ML20217G8391998-04-20020 April 1998 Forwards Copy of Rancho Seco Monthly Discharger Self-Monitoring Rept for Mar 1998 IR 05000312/19980011998-03-25025 March 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-01 on 980205 ML20217F1891998-03-18018 March 1998 Forwards Signed Original & Amend 7 to Rancho Seco Long Term Defueled Condition Physical Security Plan & Rev 4 to Long Term Defueled Condition Training & Qualification Plan.Encls Withheld,Per 10CFR2.790 ML20217G6661998-03-18018 March 1998 Forwards Discharge Self Monitoring Rept for Feb 1998, Which Makes Note of One Wastewater Discharge Permit Violation ML20217H0451998-03-18018 March 1998 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1997,per TS D6.9.2.2 & Guidance Contained in Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1997 ML20216K1091998-03-11011 March 1998 Forwards NRC Form 5 Individual Monitoring Repts for Personnel Who Required Radiation Exposure Monitoring,Per 10CFR20.1502 During 1997.W/o Encl ML20217N9531998-03-0505 March 1998 Responds to Violations Noted in Insp Rept 50-312/98-01. Corrective Actions:Radiation Protection Group Wrote Potential Deviation from Quality (Pdq) 97-0082 & Assigned Radiation Protection Action to Determine Cause & CAs ML20203H7001998-02-25025 February 1998 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1997, IAW 10CFR50.36a(a)(2) & TS D6.9.3.Revs to Radiological Environ Monitoring Manual & off-site Dose Calculation Manual,Encl ML20202G0131998-02-12012 February 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements & Master Worker Policy Certificate of Insurace for Facility NL-98-006, Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3)1998-02-12012 February 1998 Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3) ML20202C4641998-02-0505 February 1998 Forwards Insp Rept 50-312/98-01 on 980105-08 & Notice of Violation.Insp Included Decommissioning & Dismantlement Work Underway,Verification of Compliance W/Selected TS & Main & Surveillance Activities Associated W/Sfp ML20199A5881997-11-10010 November 1997 Responds to NRC Re Violations Noted in Insp Rept 50-312/97-01.Corrective Actions:Reviewed SFP Water Temp & Instrument Calibr Records,Generated Otr 97-001 to Document out-of-tolerance Instrument & Generated Pdq 97-0064 ML20198R9501997-11-0505 November 1997 Requests Interpretation of or Rev to NUREG-1536, Std Review Plan for Dry Cask Storage Sys, Re Compliance W/ 10CFR72.236(e) & 10CFR72.122(h)(4) for Dry Fuel Storage Casks ML20198K5391997-10-21021 October 1997 Forwards Insp Rept 50-312/97-04 on 970922-25 & Notice of Violation.Response Required & Will Be Used to Determine If Further Action Will Be Necessary ML20217D3101997-09-25025 September 1997 Forwards Update of 1995 Decommissioning Evaluation, for Rancho Seco Nuclear Generation Station & Annual Review of Nuclear Decommissioning Trust Fund for Adequacy Re Assumptions for Inflation & Rate of Return ML20211F0991997-09-23023 September 1997 Forwards One Certified Copy of Mutual Atomic Energy Liability Underwriters Nuclear Energy Liability Insurance Endorsement 120 for Policy MF-0075 for Smud Rancho Seco Nuclear Facility ML20198G8141997-08-22022 August 1997 Forwards Amend 125 to License DPR-54 & Safety Evaluation. Amend Permits Smud to Change TS to Incorporate Revised 10CFR20.Amend Also Revises References from NRC Region V to NRC Region IV ML20151L0281997-07-29029 July 1997 Provides Response to NRC Request for Addl Info Re TS Change,Relocating Administrative Controls Related to QA to Ufsar,Per NUREG-0737 ML20149E5031997-07-10010 July 1997 Second Partial Response to FOIA Request for Documents. Forwards Records Listed in App C Being Made Available in Pdr.Records in App D Already Available in PDR ML20148P5161997-06-30030 June 1997 Second Partial Response to FOIA Request for Documents.App B Records Being Made Available in PDR ML20141A1721997-06-17017 June 1997 Forwards Insp Rept 50-312/97-03 on 970603-05.No Violations Noted.Areas Examined During Insp Included Portions of Physical Security Program 1999-08-31
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEAR3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held ML20210H9541999-07-0707 July 1999 Informs NRC of Change to Rancho Seco Decommissioning Schedule,As Described in Licensee Post Shutdown Decommissioning Activities Rept ML20209D2501999-06-24024 June 1999 Informs That Util Has Revised All Sections of Rancho Seco Emergency Plan (Rsep),Change 4,effective 990624 ML20196G0431999-06-22022 June 1999 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Smud Rancho Seco Nuclear Generating Station ML20195B8511999-05-27027 May 1999 Forwards Change 4 to Rancho Seco Emergency Plan, Incorporating Commitments Made to NRC as Outlined in NRC .Emergency Plan Includes Two Listed Supporting Documents ML20195D1851999-05-27027 May 1999 Forwards Rancho Seco Annual Rept, IAW Plant Permanently Defueled TS D6.9.4 & D6.9.6b.Rept Contains Shutdown Statistics,Narrative Summary of Shutdown Experience,Er Info & Tabulation of Facility Changes,Tests & Experiments ML20206M1611999-05-10010 May 1999 Forwards Listed Proprietary Calculations to Support Review of Rancho Seco ISFSI Sar.Proprietary Encls Withheld ML20206E8591999-04-12012 April 1999 Provides Info Re High Total Coliform Result in Plant Domestic Sewage Effluent Prior to Confluence with Combined Effluent.Cause of High Total Coliform Result Was Broken Flow Rate Instrument.Instrument Was Repaired on 990318 ML20204E4031999-03-16016 March 1999 Submits Rept of Status of Decommissioning Funding for Rancho Seco,As Required by 10CFR50.75(f)(1).Plant Is Currently in Safstor, with Operating License Scheduled to Expire in Oct 2008 ML20204E6441999-03-11011 March 1999 Forwards Individual Monitoring Repts for Personnel That Required Radiation Exposure Monitoring During 1998 ML20204E6661999-03-11011 March 1999 Forwards Rancho Seco Exposure Rept for Individuals That Received Greater than 100 Mrem During 1998,IAW TS D6.9.2.2 & NRC Regulatory Guide 1.16 NL-99-002, Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3)1999-03-10010 March 1999 Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20207D4431999-03-0101 March 1999 Forwards Annual Radioactive Effluent Release Rept, for Rancho Seco Nuclear Generating Station for 1998 ML20207H6181999-02-18018 February 1999 Provides Attached Metrix & Two Copies of Rancho Seco ISFSI Sar,Rev 2 on Compact Disc,As Requested in 990209 Meeting. First Rounds of RAIs Dealt Primarily with Use of Cask as Storage Cask.Without Compact Disc ML20155D4431998-10-27027 October 1998 Forwards Amend 3 to Rancho Seco Dsar,Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode.With Instructions & List of Effective Pages NL-98-032, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1998-09-30030 September 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util ML20237A9481998-08-0303 August 1998 Forwards Smud 1997 Annual Rept, IAW 10CFR50.71(b),which Includes Certified Financial Statements ML20236J6331998-06-30030 June 1998 Forwards Response to Violations Noted in Insp Rept 50-312/98-02.Corrective Actions:Util Revised RSAP-1003 to Clarify District Security Staff Responsibilities Re Handling & Review of Criminal History Info ML20217G8391998-04-20020 April 1998 Forwards Copy of Rancho Seco Monthly Discharger Self-Monitoring Rept for Mar 1998 ML20217H0451998-03-18018 March 1998 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1997,per TS D6.9.2.2 & Guidance Contained in Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1997 ML20217F1891998-03-18018 March 1998 Forwards Signed Original & Amend 7 to Rancho Seco Long Term Defueled Condition Physical Security Plan & Rev 4 to Long Term Defueled Condition Training & Qualification Plan.Encls Withheld,Per 10CFR2.790 ML20217G6661998-03-18018 March 1998 Forwards Discharge Self Monitoring Rept for Feb 1998, Which Makes Note of One Wastewater Discharge Permit Violation ML20216K1091998-03-11011 March 1998 Forwards NRC Form 5 Individual Monitoring Repts for Personnel Who Required Radiation Exposure Monitoring,Per 10CFR20.1502 During 1997.W/o Encl ML20217N9531998-03-0505 March 1998 Responds to Violations Noted in Insp Rept 50-312/98-01. Corrective Actions:Radiation Protection Group Wrote Potential Deviation from Quality (Pdq) 97-0082 & Assigned Radiation Protection Action to Determine Cause & CAs ML20203H7001998-02-25025 February 1998 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1997, IAW 10CFR50.36a(a)(2) & TS D6.9.3.Revs to Radiological Environ Monitoring Manual & off-site Dose Calculation Manual,Encl NL-98-006, Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3)1998-02-12012 February 1998 Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3) ML20202G0131998-02-12012 February 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements & Master Worker Policy Certificate of Insurace for Facility ML20199A5881997-11-10010 November 1997 Responds to NRC Re Violations Noted in Insp Rept 50-312/97-01.Corrective Actions:Reviewed SFP Water Temp & Instrument Calibr Records,Generated Otr 97-001 to Document out-of-tolerance Instrument & Generated Pdq 97-0064 ML20198R9501997-11-0505 November 1997 Requests Interpretation of or Rev to NUREG-1536, Std Review Plan for Dry Cask Storage Sys, Re Compliance W/ 10CFR72.236(e) & 10CFR72.122(h)(4) for Dry Fuel Storage Casks ML20217D3101997-09-25025 September 1997 Forwards Update of 1995 Decommissioning Evaluation, for Rancho Seco Nuclear Generation Station & Annual Review of Nuclear Decommissioning Trust Fund for Adequacy Re Assumptions for Inflation & Rate of Return ML20211F0991997-09-23023 September 1997 Forwards One Certified Copy of Mutual Atomic Energy Liability Underwriters Nuclear Energy Liability Insurance Endorsement 120 for Policy MF-0075 for Smud Rancho Seco Nuclear Facility ML20151L0281997-07-29029 July 1997 Provides Response to NRC Request for Addl Info Re TS Change,Relocating Administrative Controls Related to QA to Ufsar,Per NUREG-0737 NL-97-030, Forwards Endorsement 132 to Nelia Policy NF-0212 & Endorsement 118 to Maelu Policy MF-0075 for Smuds Rsngs1997-05-13013 May 1997 Forwards Endorsement 132 to Nelia Policy NF-0212 & Endorsement 118 to Maelu Policy MF-0075 for Smuds Rsngs ML20138F5321997-04-28028 April 1997 Forwards Response to RAI Re License Amend 192,updating Cask Drop Design Basis Analysis,Per NRC 960510 Request for Addl Info on 960318 Application NL-97-027, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility1997-04-17017 April 1997 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility ML20137W8091997-03-20020 March 1997 Forwards Biennial Update to Rancho Seco Post-Shutdown Decommissioning Activities Rept ML20137S3571997-03-19019 March 1997 Provides Notification of Use of Revised Quality Manual for Activities Re Rancho Seco ISFSI ML20137D0981997-03-18018 March 1997 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1996.Provided IAW TS D6.9.2.2 & Guidance Contained in NRC Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1996 ML20137D1221997-03-18018 March 1997 Submits,Iaw 10CFR20.2206 & TS D6.9.2.1,1996 NRC Form 5 Individual Monitoring Repts for Personnel Requiring Radiation Exposure Monitoring Per 10CFR20.1502 During 1996. W/O Encl NL-97-012, Submits Rept of Listed Current Levels of Property Insurance for Plant,Iaw 10CFR50.54(w)(3)1997-02-11011 February 1997 Submits Rept of Listed Current Levels of Property Insurance for Plant,Iaw 10CFR50.54(w)(3) ML20138L1091997-01-29029 January 1997 Informs of Schedule Change Re Decommissioning of Rancho Seco.Incremental Decommissioning Action Plan,Encl NL-97-005, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility1997-01-22022 January 1997 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility NL-96-056, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1996-12-16016 December 1996 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util ML20134E0041996-10-23023 October 1996 Forwards Response to NRC GL 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks ML18102B6871996-08-0606 August 1996 Informs That Util Will Revise Loading & Unloading Procedures & Operator Training as Necessary ML20149E4491994-05-16016 May 1994 Forwards 1993 Annual Rept of Sacramento Municipal Utility District,For Info ML20149E3971994-05-10010 May 1994 Forwards Re Updated Decommissioning Cost Estimate for Rancho Seco & Attached Rept by Tlg Engineering,Inc. W/Svc List ML20059H6731994-01-20020 January 1994 Forwards Revised Rancho Seco Quality Manual, Reflecting Current Rancho Seco Pol Phase Nuclear Organization Changes ML20059E1221994-01-0303 January 1994 Forwards Amend 7 to Long Term Defueled Condition Physical Security Plan.Encl Withheld (Ref 10CFR73) ML20059C1681993-12-22022 December 1993 Forwards Suppl Info to Support Review & Approval of 930514 Proposed License Amend 186 Re Nuclear Organization Changes, Per NRC Request 1999-07-07
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L5431990-09-20020 September 1990 Requests Exemptions from Certain Requirements of 10CFR50.47(b) & 50,App E & Proposes New Emergency Plan That Specifically Applies to Long Term Defueled Condition ML20059J9161990-09-13013 September 1990 Notification of Change in Operator/Senior Operator Status for R Groehler,Effective 900907 ML20059J9221990-09-13013 September 1990 Responds to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2,Part 2, 'Vendor Interface for Safety-Related Components.' No Vendor Interface Exists for Spent Fuel Pool Liner NL-90-442, Forwards Endorsements 13 to Nelia Certificate N-49 & Maelu Certificate M-49,Endorsements 91 & 92 to Maelu Policy MF-75 & Endorsements 103 & 104 to Nelia Policy NF-2121990-09-12012 September 1990 Forwards Endorsements 13 to Nelia Certificate N-49 & Maelu Certificate M-49,Endorsements 91 & 92 to Maelu Policy MF-75 & Endorsements 103 & 104 to Nelia Policy NF-212 ML20059G0791990-09-0606 September 1990 Forwards Supplemental Fitness for Duty Performance Data, Omitted from 900725 Rept Re Random Drug Testing Results ML20059E0031990-08-30030 August 1990 Forwards Semiannual Radioactive Effluent Release Rept,Jan- June 1990, Corrected Repts & Revs to ODCM ML20059C2491990-08-27027 August 1990 Advises That M Foster & B Rausch Leaving Util Effective on 900810 & 17,respectively & Will No Longer Require Active Operator Licenses ML20056B2591990-08-20020 August 1990 Forwards Long-Term Defueled Condition Security Training & Qualification Plan. Encl Withheld (Ref 10CFR2.790) ML20056B2961990-08-10010 August 1990 Discusses 900731 Meeting Re Future of Util & Closure & Decommissioning of Facility.Request for Possession Only License Pending Before Commission ML20058Q2811990-08-0909 August 1990 Forwards Updated Listing of Commitments & long-range Scope List Items Deferred or Closed by Commitment Mgt Review Group Since Last Update ML20058N0911990-08-0707 August 1990 Notifies of Minor Change in List of Tech Specs Applicable in Plant Defueled Condition.Determined That Surveillance Requirements Table 4.1-1,Item 63 Not Required to Be Included in List of Tech Specs Applicable in Defueled Condition ML20056A2041990-07-30030 July 1990 Provides Response to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. Pressure & Differential Pressure Transmitters 1153 & 1154 Do Not Perform Any safety-related Function in Current Plant Mode ML20056A1131990-07-30030 July 1990 Apprises of Status of Plans to Use 3 of 4 Emergency Diesel Generators as Peaking Power Supplies & Responds to Questions in .Util Obtained Authorization for Operation of Diesel Generators for No More than 90 Days Per Yr ML20055J0311990-07-25025 July 1990 Forwards fitness-for-duty Performance Data for Facility from 900103-0630 ML20055J0331990-07-25025 July 1990 Notifies of Change in Operator/Senior Operator Status. Operators Terminating Employment & No Longer Require License ML20055H7561990-07-24024 July 1990 Requests Exemption from Performing Annual Exercise of Emergency Plan,Activation of Alert & Notification Sys & Distribution of Public Info Brochures,Per 10CFR50.12 Requirements ML20055H8081990-07-24024 July 1990 Forwards Decommissioning Financial Plan for Plant,Per 10CFR50.33(k)(2) & Requests Interim Exemption Re Requirement to Have Full Decommissioning Funding at Time of Termination of Operation,Per 10CFR50.12 ML20055F8421990-07-13013 July 1990 Forwards Application for Proposed Decommissioning of Plant. Util Needs Relief from Equipment Maint,Surveillance,Staffing & Other Requirements Not Necessary to Protect Public Health & Safety During Defueled Condition ML20055G9821990-07-12012 July 1990 Advises That Environ Exposure Controls Action Plan Will Be Provided by Sept 1990,per Insp Rept 50-312/90-02 ML20055E5111990-07-0606 July 1990 Notifies of Change in Operator/Senior Operator Status for D Rosenbaum & M Cooper,Effective 900622 & 29,respectively ML20055C3511990-02-14014 February 1990 Forwards Addl Info Re 900306 Response to NRC Bulletin 88-003, Inadequate Latch Engagement in Hfa Type Latching Relays Mfg by Ge. Util Will Replace Only Relays Found Not to Meet Insp Criteria ML20055C3541990-02-14014 February 1990 Forwards Updated Response to Insp Rept 50-312/88-30. Calculations for Liquid Effluent Monitors Completed & in Use & Rev to Reg Guide 4.15 in Procedure RSAP-1702 Scheduled to Be Completed & Implemented by Apr 1990 ML20248H2391989-10-0606 October 1989 Requests Exemption from Requirements of 10CFR26 Re Fitness for Duty Programs Based on Present & Future Operational Configuration ML20248H2571989-10-0606 October 1989 Responds to NRC Re Addendum to Safety Evaluation Supporting Amend 92 to License DPR-54 Re Reactor Vessel Vent Valve Testing.No Testing of Reactor Vessel Vent Valves Will Be Performed ML20248A8271989-09-25025 September 1989 Requests Permission to Submit Next Amend to Updated FSAR W/Decommissioning Plan Submittal.Extension Will Allow District to Incorporate Plant Closure Status in SAR Update to Reflect Plant Conditions Accurately ML20248D4611989-09-13013 September 1989 Responds to 890906 Request for Assessment of Util Compliance W/Ol & Associated Programs & Commitments,Per 10CFR50.54(f). Staffing Requirements for Emergency Preparedness Will Not Be Violated & Future Shortfalls Will Be Remedied ML20247G1991989-09-11011 September 1989 Requests Extension for Time Period Equivalent to That of Current Shutdown.Extension Would Result in Revised Final Expiration Date of Not Earlier than 900318.Plant Would Not Be Brought Above Cold Shutdown W/O NRC Prior Concurrence ML20247H3551989-09-0707 September 1989 Informs That Util Stands by Commitments of 890621 & 0829 Re Implementation of Closure Plan in Safe & Deliberate Manner in Compliance W/License & W/All Applicable Laws & Regulations ML20247H5541989-09-0101 September 1989 Responds to Violations Noted in Insp Rept 50-312/89-14. Corrective Actions:Stop Order on Fuel Movement Issued & Action Plan Generated on 890908 to Address Broader Issues 05000312/LER-1988-010, Forwards Rev 1 to LER 88-010,due to Change in Commitment Date for re-evaluating Fire Zones.Date Changed to 901001. Zones re-evaluated in Conjunction W/Mods to Fire Detection Annunciator Sys1989-08-23023 August 1989 Forwards Rev 1 to LER 88-010,due to Change in Commitment Date for re-evaluating Fire Zones.Date Changed to 901001. Zones re-evaluated in Conjunction W/Mods to Fire Detection Annunciator Sys ML20246A4011989-08-16016 August 1989 Forwards Rev 5 to Inservice Testing Program Plan. Changes Identified Consistent W/Guidance Provided by Generic Ltr 89-04 NL-89-593, Forwards Plant Closure Organizational Charts & Administrative Procedure RSAP-0101,per 890802 Request1989-08-15015 August 1989 Forwards Plant Closure Organizational Charts & Administrative Procedure RSAP-0101,per 890802 Request ML20245H4781989-08-10010 August 1989 Requests Exemption from Generic Ltr 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs Because on 890607,util Board of Directors Ordered That Plant Cease Operation ML20245H1781989-08-0909 August 1989 Notifies of Change in Operator/Senior Operator Status. J Dailey & J Reynolds Terminated Employment on 890721 & 890802,respectively ML20245L1831989-08-0808 August 1989 Informs That Official Correspondence Must Be Directed to Listed Individuals Due to Reorganization of Util Following 890606 Election ML20247L9221989-07-26026 July 1989 Provides Revised Response to NRC Re Violations Noted in Insp Rept 50-312/88-33.Corrective Action:Portable Shield Walls Inspected Every 6 Months to Ensure All Safety Factors Met & Area Surveys Conducted on Weekly Basis ML20247M4121989-07-24024 July 1989 Requests Exemption from 10CFR50,App E,Section IV.F.2 to Allow Util Not to Perform Annual Emergency Plan Exercise for 1989.Request Results from Transitional Mode of Plant from Operating Plant to Plant Preparing for Decommissioning NL-89-541, Requests That Completion Date for Addl Training of Personnel Involved in Performing Work on Environ Qualified Equipment Be Extended from 890616 to 8912151989-07-14014 July 1989 Requests That Completion Date for Addl Training of Personnel Involved in Performing Work on Environ Qualified Equipment Be Extended from 890616 to 891215 ML20246P4011989-07-14014 July 1989 Informs That Evaluation of Contracts & Agreements Identified No Restrictions on Employee Ability to Provide Info About Potential Safety Issues to NRC NL-89-547, Forwards Amend 110 to License DPR-54,issued on 890609, Identifying Discrepancy in Tech Spec Page X (Table of Contents) Which Does Not Reflect Changes Approved in Amend 1061989-07-0606 July 1989 Forwards Amend 110 to License DPR-54,issued on 890609, Identifying Discrepancy in Tech Spec Page X (Table of Contents) Which Does Not Reflect Changes Approved in Amend 106 ML20246A9751989-06-30030 June 1989 Advises That Concerns Addressed in Generic Ltr 89-08 Inapplicable,Since Util Intends to Defuel Reactor.Generic Ltr Will Be Reviewed Prior to Placing Facility in heatup-cooldown Operational Mode for Return to Power ML20246A5171989-06-30030 June 1989 Forwards Rancho Seco Closure Plan, Per 890621 Request for Addl Info Re Plan CEO-89-289, Notifies of Change in Operator/Senior Operator Status.Listed Operator/Senior Operator Terminated Employment on Listed Effective Date1989-06-27027 June 1989 Notifies of Change in Operator/Senior Operator Status.Listed Operator/Senior Operator Terminated Employment on Listed Effective Date NL-89-526, Lists Discrepancies Noted in Amend 109 to License DPR-54,per 890615 Discussion W/S Reynolds.Tech Specs Encl1989-06-22022 June 1989 Lists Discrepancies Noted in Amend 109 to License DPR-54,per 890615 Discussion W/S Reynolds.Tech Specs Encl ML20245H4181989-06-21021 June 1989 Discusses Util Plans Re Overall Closure of Plant,Per 890615 Meeting W/Nrc.Util Will Request Appropriate Changes to Tech Specs to Reflect Defueled Mode & Will Evaluate & Request Changes to Emergency Plan ML20245D9281989-06-21021 June 1989 Discusses Activities Underway Re Plan for Closure of Plant Discussed During 890615 Meeting W/Region V.Util Intends to Continue Use of Essential Programs,Such as Preventive Maint Program,For Sys within Scope of Closure Process ML20245A0981989-06-16016 June 1989 Responds to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs. No Westinghouse Plugs Used at Plant ML20248B5751989-06-0202 June 1989 Advises That Util Anticipates That Final Analysis of Thermal Striping Will Conservatively Support Surge Line Lifetime Significantly Longer than June 1994 Date,Per NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification 1990-09-06
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SACRAMENTO MUNICIPAL UTILITY OtSTRICT G P. O. Box 15830, Sacramento CA 95852-1830 (9161 452 3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA JEW 86-667 November 5, 1986 U. S. Nuclear Regulatory Commission Region V Office of Inspection and Enforcement 1450 Maria Lane, suite 210 Walnut Creek, CA 94596 Docket 50-312 Rancho Seco Nuclear Generating Station Unit il PROGRAM STATUS
SUMMARY
, RESPONSE TO IE BULLETIN NO. 85-03; MOTOR OPERATED VALVE COMMON MODE FAILURES DURING PLANT TRANSIENTS DUE TO IMPROPER SWITCH SETTINGS
References:
Letter JEW 86-023, J. E. Ward (SMUD) to J. B. Martin (USNRC);
Response to IE Bulletin No. 85-03; Motor Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings, Dated May 16, 1986.
l
Dear Mr. Martin:
The above referenced letter provided a description of the District's program to address IE Bulletin No. 85-03 action items, in accordance with the l requirements of Item e of the subject bulletin. In order to provide further assurance of the proper operability of other station motor operated valvea (MOVs), the District expanded the scope under the MOV Refurbishment Program to include (1) all safety related MOVs and (2) all other MOVs on-site.
Additionally, the program has been enhanced through the use of MOVATS, INC.
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response signature analysis equipment and computer based baseline comparison / analysis techniques, to cite two examples. All MOV Refurbishment Program work on the thirty IEB 85-03 MOVs and all other safety related MOVs will be completed prior to restart.
In order to keep you apprised of our progress, attached is a status summary of the District's MOV Refurbishment Program to comply with IEB 85-03. As you will note, the program summary is structured consistent with the specific action items required by the bulletin. For each element of the program, the
" Current Program in Progress" description includes the elements of the District's May 16, 1986 response and subsequent enhancements which result in a more comprehensive program, consistent with the District's commitment to excellence.,
Based on the scope and depth of the program that is being implemented, the District is confident that its actions will address the immediate issues regarding MOV operator switch settings. We feel that the MOV maintenance, configuration control and procedural revision / upgrade actions being taken as a result of this program, will ensure the minimization of future MOV related problems.
8611180235 861105 PDR ADOCK 05000312 G PDR DISTRICT HEADQUARTERS O 6201 S Street, Sacramento CA 95817-1899 -
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Status Update Summary November 5, 1986 Through the transmittal of this letter, the District requests that the NRC conduct a priority review of the attached program. Additionally, we request that approval of, and/or comments on, the program in progress be provided.
If you have any questions, please contact Jerry Delezenski of my staff at (209) 333-2935, extension 3909.
Sincerely,
/ /
Jo n . Ward uty General Manager, Nuclear Attachment cc: Sydney Miner, NRC, Bethesda Tony D'Angelo, NRC, Rancho Seco 1
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- MOV REFURBISHMENT PROGRAM STATUS
SUMMARY
A. DESIGN BASIS REQUIRED BY IEB 85-03:
Review and document the design basis for the operation of each valve.
This documentation should include the maximum differential pressure expected during both opening and closing the valve for both normal and abnormal events to the extent that these valve operations and events are included in the existing, approved design basis, (i.e., the design basis documented in pertinent licensee submittals such as FSAR analyses and fully-approved operating and emergency procedures, etc.). When determining the maximum differential pressure, those single equipment failures and inadvertent equipment operations (such as inadvertent valve closures or openings) that are within the plant design basis should be assumed.
REPORTED BY J. E. WARD LTR TO NRC, MAY 16, 86:
The District conducted a study (ERPT-E0181) on each of the Rancho Seco Updated Safety Analysis Report (USAR) Chapter 14 accidents to identify the motor-operated valves which are required to function in order to mitigate each event. The valves (30 applicable to IEB 85-03 criteria) and the maximum differential pressure associated with each valve have been identified and included in the Refurbishment Program.
CURRENT PROGRAM IN PROGRESS:
In addition to the thirty IEB 85-03 valves, the scope of the Refurbishment Program has been increased to include (1) all safety related Motor Operated Valves (MOVs) and (2) other MOV assemblies on site.
The maximum differential pressure (delta P) for each valve has been determined and recorded. These values are currently being verified and used in analytical thrust / torque calculations which will result in the determination of torque switch settings after the MOV refurbishment.
Calculations are being performed for each MOV to determine the minimum operator torque / thrust necessary to open and/or close the valve under maximum delta P conditions.
The maximum allowable load for each valve and each operator is being determined using the following process:
- 1. The valve manufacturer is contacted to obtain seat port information and other valve specific information.
- 2. Limitorque furnishes operator data to identify the "as shipped" operator gear ratio and confirm the aizing information furnished by the valve manufacturer.
- 3. Preliminary loads (normal and maximum), valve stem diameter,
- stem thread pitch, stem thread lead, motor RPM and unit gett i
r ratio are developed, based on vendor information. The
' calculated thrust loads are a conservative summation of the valve stem thrust, the packing load and the stem load. The calculations assume minimum voltage and maximum delta P.
- 4. The following field information is confirmed prior to using the analytically determined preliminary loads:
- a. Valve Stem Diameter
- b. Stem Thread Pitch
- c. Stem Thread Lead
- d. Motor RPM and HP/ Torque
- e. Operator Unit Gear Ratio
- f. Verification of Spring Pack Number (if available)
- g. Operator Serial Number
- 5. For final loads (normal and maximum), the valve vendors will furnish the following:
- a. On safety related valves and other plant valves frequently required to operate, where valve serial numbers are available, the valve serial number will be identified and the valve vendor's specific information for operator sizing will be obtained (stem diameter, stem thread pitch, stem thread lead, seat port diameter, valve thrust, and required torque / thrust for the design maximum differential pressure).
- b. On the remaining valves and where serial numbers are not available, the valve vendor will furnish seat port areas for the globe and gate valves from general design information. For the ball and butterfly valves, the supplier will furnish stem diameter and disc weight from general design information.
- 6. The valve and operator information is compared, any conflicts are resolved and the torque / thrust values for the MOV assemblies ;
are provided.
- 7. MOVATS, INC. calculates design pressure stem thrust requirements for flow and pressure only, using MOVATS verified equations.
The calculated torque / thrust values are provided to the District.
The torque / thrust inputs are compared, discrepancies are resolved, and the data is entered into the on-site document control system for implementation.
B. SWITCH SETTINGS / DOCUMENTATION REQUIRED BY IEB 85-03:
Using the results from item a above, establish the correct switch settings. This shall include a program to review and revise, as
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necessary, the methods for selecting and setting all switches (i.e.,
torque, torque bypass, position limit, overload) for each valve operation (opening and closing).
If the licensee determines that a valve is inoperable, the licensee shall also make an appropriate justification for continued operation in accordance with the applicable technical specification.
PROPOSED BY J. E. WARD LTR TO NRC, MAY 16, 86:
Obtain current switch settings by manually moving the valve using the handwheel.
Record the torque switch setting and torque load on the handwheel.
Collect nameplate data from valve and operator.
Using the data collected, calculate and document the analytic load required to be placed on the stem for the most adverse operating conditions.
The most adverse analytic load will be compared to the current condition and compared with the allowable condition for the valve, with the allowable thrust and torque for the operator, and with the allowable motor usage torque to determine if the operator is properly sized.
The switch settings will be documented on controlled Engineering Drawings maintained under the configuration control system for the Rancho Seco Nuclear Generating Station.
Analytical determination of torque and thrust, using values supplied by valve vendors and motor-operator vendors, will be accomplished.
Use of the analytical methodology will establish a load and corresponding handwheel torque required to achieve the load.
Limit switch settings will be established as a standard percent open for the open torque switch bypass setting.
, Open limit switch settings will be adjusted to ensure that the valves are not backseated.
4 CURRENT PROGRAM IN PROGRESS:
! The "as-found" data on each IEB 85-03 MOV assembly is being recorded in
! the IED 85-03 Data Summary and on the on-site controlled documents. For each MOV within the Refurbishment Program, the Motor Operated Valve Data controlled site document (E-1012) is being revised to include data on the i
valve, the operator, the motor, the reference drawings / documents, and the l MOV dynamic responses (see attachment). Each of the electrical drawings i and mechanical drawings is being verified for as-built accuracy as each assembly is refurbished and tested.
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Specific mechanical maintenance procedures have been written and are in use in the refurbishment of the motor operators. Any known deficiencies on the valves or operators are being corrected prior to reassembly.
Internal challenges to assembly operability are being summarized in the IEB 85-03 Data Summary. The refurbishment includes examination of all components for continued service, replacement of all consumable items and initial setting of switches. Final settings are being performed during the electrical maintenance signature analysis baseline testing.
A review of the policy and existing procedures for switch setting has resulted in an electrical procedure rewrite and a clarification of logic for MOVs. The acquisition of dynamic testing equipment (MOVATS) and software allows precision switch setting, functional confirmation, and the establishment of a baseline data base.
On a case-by-case basis, the following items were reviewed:
- a. Open/Close Torque Switch Bypass Limit Switches (IEN 186-29)
- b. Open/Close Limit Switches (IEN 986-71)
- c. Open/Close Torque Gwitches (IEN #84-10 and IEC #77-01)
- d. Switch Control for Butterfly and Three-Way Valves
- e. Overload Devices
- f. Interlocks with Other Equipment (IEN 886-29) 9 Position Indications (IEN 886-29)
- h. Operator Heaters (IEN 886-71 and IEB #79-01B)
- 1. Termination Splicing (IEN 886-53)
- j. Environmental Qualification (EQ) (IEN 086-03)
- k. Lubricant (IEN 979-03)
- 1. Pinion Gear Installation (IEN 085-22)
- m. Gearhead Worm Gear Orientation (IEN #83-02)
- n. Stem Nut Lock Nut Staking (IEC #79-04)
- o. Hammering Effect from Non-Locking Gear Set (IEN 985-20)
Each item was addressed, abnormalities resolved, and specific direction given in procedures and recorded in controlled documents.
C. TESTING / RECORDING / ANALYSIS REQUIRED BY IEB 85-03:
Individual valve settings shall be changed, as appropriate, to those established in item b, above. Whether the valve setting is changed or not, the valve will be demonstrated to be operable by testing the valve at the maximum differential pressure determined in item a above with the exception that testing motor-operated valves under conditions simulating a break in the line containing the valve is not required. Otherwise, justification should be provided for any cases where testing with the maximum differential pressure cannot practicably be performed. This justification should include the alternative to maximum differential I
pressure testing which will be used to verify the correct settings.
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Note: This bulletin is not intended to establish a requirement for valve testing for the condition simulating a break in the line containing the valve. However, to the extent that such valve operation is relied upon in the design basis, a break in the line containing the valve should be considered in the analyses prescribed in items a and b above. The resulting switch settings for pipe break conditions should be verified, to the extent practical, by the same methods that would be used to verify other settings (if any) that are not tested at the maximum differential pressure.
Each valve shall be stroke tested, to the extent practical, to verify that the settings defined in item b above have been properly implemented even if testing with differential pressure can not be performed.
PROPOSED BY J. E. WARD LTR TO NRC, MAY 16, 86:
Each operator will be mechanically and electrically refurbished to ensure proper working condition.
Following refurbishment, the torque and limit switch settings will be made on the operator. The torque switch settings will be input through the actuator handwheel and set to a specific value of handwheel torque.
The open torque switch bypass switch will be set to a fixed percentage of disc motion.
The open limit switch will be set to ensure valves are not backseated.
Three way valves will be set to torque out in each direction.
The handwheel torque values and corresponding torque switch settings will be recorded along with the limit switch settings.
Once the operators have been refurbished and new switches set, the valves will receive a delta P test.
Analytical justification will be provided for those that do not receive a delta P test.
The test program will record as appropriate, valve stroke time, confirmation of switch operation, inlet and outlet pressures, flow and system alignment.
CURRENT PROGRAM IN PROGRESS:
Each of the MOV assemblies is being mechanically and electrically refurbished and deficiencies are being recorded and corrected. Specific mechanical procedures direct the work activities from removal, inspection, and reassembly through coarse limit switch setting by turn-of-the handwheel methods. A specific electrical procedure directs the fine tuning of the switch settings, baseline dynamic response signature gathering and motor-load threshold acquisition. The correct dynamic response is being ensured with MOVATS Series 2150 systems. A MOVATS field representative is consulting with District EM personnel who have been
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formally trained in the use of the system and in response signature analysis. Valve work and baseline data gathering are done with the system dry and de-pressurized. The "as-left" response data will be added to the controlled documents by a revision for future reference.
In conjunction with the system testing, each IEB 85-03 MOV assembly will be tested, where practical, consistent with the IEB 85-03 Item c requirements. Selected valves will be tested to demonstrate that the MOV assembly is operable at the maximum differential pressure with minimum supply voltage. The MOVATS signatures at identified differential pressures will first be recorded onto bubble memory storage, then transferred to the specific MOV computer diskette for analysis and comparison to (1) the MOV's unpressurized dynamic response signatures and (2) the industry full or partial pressure test data available from MOVATS, INC. The test results will allow the completion of the IEB 85-03 Data Summary and a detailed record of MOV assembly response to worst case conditions. Those MOV assemblies which fail to function properly during system testing will be declared inoperable and the replacement units will be subject to the above mentioned MOV program requirements. This will ensure that full operability is demonstrated for all MOVs onsite.
The hard copy controlled documents and the computer stored response signature records will provide the baseline for future comparisons of dynamic MOV assembly response. In accordance with procedural work planning, each future work activity affecting the response of the MOV assembly will include a MOVATS measurement and comparison requirement (threshold value or complete signature acquisition).
D. PROGRAMMATIC SOLUTIONS REQUIRED BY IEB 85-03:
Prepare or revise procedures to ensure that correct switch settings are determined and maintained throughout the life of the plant. Ensure that applicable industry recommendations are considered in the preparation of these procedures.
PROPOSED BY J. E. WARD LTR TO NRC, MAY 16, 86:
Generic compliance with action required by IEB 85-03.
CURRENT PROGRAM IN PROGRESS:
Correct switch settings will be maintained for all MOV assemblies on-site by the continued use of several new procedures. New mechanical maintenance procedures have been issued and are in use for refurbishing the motor operators. These procedures direct the detailed examination of all components for continued service, replacement of consumable items and initial setting of switches.
A new electrical maintenance procedure has been issued and is in use for detailing the testing of MOVs using MOVATS dynamic response systems. This procedure specifically directs the setting of switches to those values
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recorded on the controlled documents, thus ensuring continued performance within the design basis. Also included within this procedure are the directions for the following signature acquisitions:
- a. Motor Load Threshold
- b. Thrust Measuring Device (TMD) and Control Switch
- c. Motor Current
- d. Motor Load These response signatures are transferred to computer diskettes for storage and future use in comparisons and analyses.
Preventative maintenance (PM) tasks are being written for each MOV assembly on site. Environmental Qualification (EQ) considerations establish a task interval on most MOV assemblies with individual assessments establishing the interval on the remaining units. Once detailed and entered into the existing PM Program, the tasks will be scheduled for work and the results included in the machinery history for each assembly. The minimum confirmation of operability will be the comparison to the MOVATS baseline motor load threshold value. Any discrepancies identified during the PM task could lead to additional MOVATS signatures and analyses for resolution. Each PM task includes all the items proposed in the MOVATS, INC. Performance and Monitoring Program presented to the NRC in September 1986.
E. SCHEDULE The following is an updated status of the MOV Refurbishment Program tasks:
- 1. Determination of Differential Pressures Completed
- 2. Submittal of Projected Program Completed
- 3. Training of Personnel Completed
- 4. Preparation of Procedures Completed
- a. EM.ll7A
- b. M.115
- c. M.ll6
- 5. Calculation Data Collection
- a. Valve manufacturer input Commenced 8/4/86
- b. Operator manufacturer input Commenced 8/4/86
- 6. Analytical Calculation Commenced 9/15/86
- 7. Refurbish Operators and valves Commenced 9/2/86
- 8. Field Data Confirmation Commenced 9/2/86
- 9. Torqua/ Thrust Values Determined Commenced 9/15/86
- 10. MOVATS, INC. Provides Torque / Thrust Values Commenced 10/1/86
- 11. Preparation of On-Site Documents Commenced 10/14/86
- 12. Switch Settings Commencing 10/26/86
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A I B I C .,
VALVE INFORMATION OPER ATOR INFORMATION MOTOR INFORMATION g VALVE EOuiPMENT L D. OPERATOR MANUFACTURER - MOTOR MANUFACTURER ,
sERveCE TYPE S size sERi Ai NUMBER 2
MANUFACTURER VENDOR SMOP ORCER NO. PO5LN' 5'u'PPLY ( AC/DC VOLTS) 3 4 TYPE S SIZE SERIAL NUM8ER M AX DESIGN RUNNING CURRENT
$ AN51 RATING UNIT PULL 0uf EFFICIENCY NPM (NAMEPt ATE) 6 PURCHAst ORMR MAN 0*MEEL GEAR RATIO MOTOR APPLICATION FAC M UNIT GEAR Raft 0 DUTY HATING -
SERIAL NUMBER 7 des GN SPEED OF OPER ATION $EC INSUL AflON CL ASS g $ TEM TYPE Liuti SwlTCH TYPE (2 0R 4 ROTOR 1REv0LVING / MON REVOLVING) AND MATERIALI 9 DRECTaON OF Flow MIN. REO'D. SETTING THRUST gg MOTOR DESIGN TOROUE FT-L85 (OVER / UNDER $E AT) ($EE NOTE 63 MOTOR MANIMdM TOROUE FT-L S$
STEM DIAMETER ,,- WIN. REO'O. SETTING TOROUE 10 AT PACniNG tsEE NOTE &l FT-LDS STEM DIAMETER MAJOR iN. DE5iGN TMRUST AT AP M NOR L85 REFERENCE DWGS. / DOCUMENTS AT THRE ADS iN .
g THRE AD PITCH
- MAKIMUM THRUST - OESIGN - t 195 P S ID (LO-ORDIN ATE $1 4TALLED THRUST- LBS '~
g3 THREAD LE AD DEstGN TOROUE AT AP F M 85 SPECIFiCATsON g4
- STRos(L LENGTH MECMANICAL M A XIMUM TOROUE - DE SIGN- FI* L RS , VENDdR DRAwlNGS ST ALLED TOROUE- FT-Les e STROKE TIME (MAMMER BLOW AT O-C SEC M AX. TOROut AVAIL. AT MIN SUPPLY T eos FT-Les ' ELECT'MICAL L AYOUT OR AwlNG STEM NUT TO MOTOR DE-ENERGlZEG C-O SEC VOLTAGE (UNDERVOLTAGE CONDiTeON D V mle h 16 e sTROut TIME- f O-C sEC MAN 0 WHEEL TORouE ELECIRICAL EL E M E NTARY CONTACTOR l C-O SEC (NECESSARY TO TRIP TORout Swl DI AGN AM 37 SE AT PORT ARE A mt M AX MANOwMEEL TOROUE- DESIGN pg ggg EL EMCAL BREAMER DATA
$ MEET &_ 8 MEANER I.O.
gg STEM TOROUE FACTOR TOROUE $wlTCH f SERI AL NO. PHYSICAL LOCATION (FROM MEL)
SPRNG 1 $ PACER NO.
gg VALVE FACTOR TOROUE SwlTCM SETTING LIMITER APPLICallL E $P'S PL ATE REOulRED (YES / NO3 ~
A PRES $uRE / OPE NING) PSI 9 OCSiGN /MAE ALLOwASLE TOROUE OPEN MINIMtlM SUPPLY 20 (Ma x iMuM) \CLO$ 1NG) P$4 SWITCH SETTING CLOSEO v0LT AGE VALUE SOURCE PRESSURE tMAX.)- PSI *AS INST ALLE0* TOROUE SWITCH OPEN REOulHED STROME 2: SYSTEM TEMPERATURE (Max .1- .r sETTNG CLoSto y source y M AX. THRUST VALVE CAN wlTM. OPEN LB$ LIMIT SwtTCH ROTOR I NOTLS:
stand IN NOTED OIRECTION CLOSED LOS SETTING .%OF , ROTOR 2 s. vnavat IEnusmaTED 23 CAN wiTH- O*EN FT-Les oisc MOVEMENT- ROTOR 3 O ga,ogQoa-M5o M8 uAx.
STANDTOROut IN NOTEDv&LvE.RECTICN O CLOSED FT-L85 DESIGN ROTOR 4 2. masrient cara stoaast apretss_
NOMIN AL PACMING $1ZE LIMIT SWITCH '
ROTOR I 3 E=vinunut efat maLIFication asstuety_lvEsimot ttvEL _tM.u.mt -
24 SETTsNG- % OF ,
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twausT.
015C MOVEMENT- ROTOR 3 3 umiemeu neomato Servi =G YamusTr vcRout rounts cesica TamusTs 25 ACiuAt ROTOR A "' 5* 58"'*o ea=o snALL et miniuuu vaux +cs.-os.
- 6. u'"n"i r"is u"u"itto av noi m a actro tes 26 GREASE TYPE f GE AR 80X 1 LIMIT SwlTCMES
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