Letter Sequence Other |
---|
|
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement
Results
Other: A11745, Evaluation of DSR-48 Emergency Diesel Generator Crankshafts at Rancho Seco Nuclear Generating Station, ML20126J866, ML20126J973, ML20135E867, ML20149D631, ML20149F003, ML20196E677, ML20196E697, ML20206H162, ML20212B420, ML20214K863, ML20215G661, ML20234C529, ML20234C558, ML20234D524, ML20234D615, ML20234D649, ML20235M565, ML20235Q511, ML20236L543, ML20236N639, ML20236N713, ML20236S088, ML20237B265, ML20237B279
|
MONTHYEARNRC Generic Letter 1985-061985-04-16016 April 1985 NRC Generic Letter 1985-006: Quality Assurance Guidance for ATWS Equipment That Is Not Safety-Related Project stage: Request ML20126J9731985-06-0404 June 1985 Notice of Denial of Amend to License DPR-54 & Opportunity for Hearing Re Proposed Tech Spec Establishing Operability Requirements for Essential HVAC Sys Project stage: Other ML20126J8901985-06-0404 June 1985 Safety Evaluation Supporting Amend 68 to License DPR-54 Project stage: Approval ML20126J8661985-06-0404 June 1985 Amend 68 to License DPR-54,defining Operability & Surveillance Requirements for Plant Essential Electrical Sys & Operability Requirements for Components of Fire Protection Sys Project stage: Other ML20135E8721985-09-0909 September 1985 Safety Evaluation Supporting Amend 74 to License DPR-54 Project stage: Approval ML20135E8671985-09-0909 September 1985 Amend 74 to License DPR-54,revising Tech Specs to Define Testing Requirements for Pressurizer Heaters Powered from Class 1E Power Sources Project stage: Other ML20135E8571985-09-0909 September 1985 Forwards Amend 74 to License DPR-54 & Safety Evaluation. Amend Revises Tech Specs to Define Testing Requirements for Pressurizer Heaters Powered from Class 1E Power Sources Project stage: Approval ML20215C9951986-10-0202 October 1986 Forwards Replacement Pages Inadvertently Omitted from 860723 Amend 4 to Updated FSAR Re Reactor Vessel & Steam Generator Design Data Project stage: Request ML20212B3781986-12-19019 December 1986 Application for Amend to License DPR-54,consisting of Rev 1 to Proposed Amend 147,changing Electrical Distribution Sys. Design Basis Repts,Response to NRC Question from 861125 Telcon & Summary of Changes Encl Project stage: Request ML20212B4201986-12-19019 December 1986 Proposed Tech Specs Reflecting Changes to Electrical Distribution Sys & Mods to Inverter Power Supply Sys & Undervoltage/Overvoltage Protection Sys.W/Five Oversize Diagrams Project stage: Other ML20234D5241986-12-31031 December 1986 Baseline Vibration Survey Emergency Diesel Generator a Rancho Seco Nuclear Power Plant Project stage: Other ML20234D6151986-12-31031 December 1986 Pipe Vibration Survey Emergency Diesel Generator a Rancho Seco Nuclear Power Plant Project stage: Other ML20234D6491987-01-31031 January 1987 Crankshaft Torsional Vibration Measurements Emergency Diesel Generator a Rancho Seco Nuclear Power Plant Project stage: Other A11745, Evaluation of DSR-48 Emergency Diesel Generator Crankshafts at Rancho Seco Nuclear Generating Station1987-02-28028 February 1987 Evaluation of DSR-48 Emergency Diesel Generator Crankshafts at Rancho Seco Nuclear Generating Station Project stage: Other ML20206H1281987-04-0101 April 1987 Application for Amend to License DPR-54,revising &/Or Adding Addl Sections to Tech Specs & Addressing Safety Impact of Bringing Tdi Diesel Generators Into Svc. Description of Proposed Changes Encl Project stage: Request IR 05000312/19870081987-04-0101 April 1987 Insp Rept 50-312/87-08 on 870209-0306.No Violations Noted. Major Areas Inspected:Licensee Program for Environ Qualified Electrical splices,follow-up of Insp Open Items,Ie Bulletins & Info Notices,Unresolved Items & LERs Project stage: Request ML20206E0561987-04-0101 April 1987 Commits to Broadening Scope of 870226 Upgrade of Meteorological Sys to Include Installation of fixed-width Guyed Tower Approx 120 Yards Southwest of Existing Tower,Per 870211 Meeting.Schedule Will Be Submitted within 30 Days Project stage: Meeting ML20206H1621987-04-0101 April 1987 Proposed Tech Specs Re Safety Impact of Bringing Tdi Diesel Generators on Line Project stage: Other ML20215G6611987-04-13013 April 1987 Informs That Seismic Qualification of Either of Listed Options Re Resolution of Issue of Class 1 Indication of Tdi Diesel Generator Status in Control Room Will Be Based on Generic Ltr 87-02,per 870401 Commitment Project stage: Other ML20214K8631987-05-18018 May 1987 Informs That Validations Re Tdi Diesel Generator Insps Completed & Phase I Rept Progressing Well.Some Difficulties Prevented Completion of Test Program & Rept to Support 870515 Submittal Date.Interim Rept Expected by 870630 Project stage: Other ML20234C5581987-06-10010 June 1987 Rev 0 to Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75 Project stage: Other ML20234C5291987-06-26026 June 1987 Forwards Rev 0 to ERPT-E0220, Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75, Per Discussions on 870602 & 03 Re Rev 2 to Proposed Amend 147 to License Project stage: Other ML20235M5651987-07-0808 July 1987 Forwards Design Review/Quality Revalidation (Dr/Qr) Program for Rancho Seco Tdi Diesel Generators, Final Engineering Summary Rept.Preliminary Turbocharger Final Rept Will Be Submitted by 871001 Project stage: Other ML20236N7131987-08-0505 August 1987 Part 21 Rept Re Potential Problem W/Vibration in Lube Oil & Jacket Water Sys.At Rancho Seco Site,Fatigue Cracks Found in Welds of Support Members in Lubricating Oil Sys.Cracks Due to Vibration in Lube Oil Sys.Addl Preventive Action Taken Project stage: Other ML20235F5251987-09-22022 September 1987 Forwards Supplemental Info Re Previous Submittal of Proposed Amend 147,Rev 2 Re Electrical Sys Tech Specs.Info Reflects More Restrictive Limiting Condition of Operation for Diesel Generators to Be out-of-svc Project stage: Supplement ML20235F5301987-09-22022 September 1987 Proposed Tech Specs Consisting of Supplemental Info to Proposed Amend 147,Rev 2 Re Diesel Generator Outages Project stage: Supplement ML20235Q4781987-10-0101 October 1987 Application for Proposed Amend 164 to License DPR-54, Consisting of Enhancements to Tech Specs to Resolve Certain Comments Resulting from NRC Region V Feb & Mar 1987 Contracted Comparison of Plant Tech Specs to Sts.Fee Paid Project stage: Request ML20235Q5111987-10-0101 October 1987 Proposed Tech Specs Re Comparison of Plant Tech Specs to STS Project stage: Other NL-87-1295, Forwards Supplemental Emergency Diesel Generator Info,Per NRC Request.W/One Oversize Drawing Change Notice1987-10-0808 October 1987 Forwards Supplemental Emergency Diesel Generator Info,Per NRC Request.W/One Oversize Drawing Change Notice Project stage: Supplement ML20236E9361987-10-26026 October 1987 Forwards Response to 871008 Request for Clarification & Info Re Emergency Diesel Generator Review Project stage: Request ML20236L5431987-10-30030 October 1987 Forwards Requested Addl Info Re Proposed Amend 147 to License DPR-54 & Plant Electrical Distribution Sys.Single Failure at Switch 52-4B202 Has No Safety Impact Project stage: Other ML20236N3211987-11-0909 November 1987 Forwards Three Pages Inadvertently Omitted from Util 871030 Response to NRC Request for Addl Info Re Proposed Amend 147 to License DPR-54 Project stage: Request ML20236N6391987-11-0909 November 1987 Confirms That 15% Damping Value Used During Design of Cable Tray Supports in Tdi Diesel Generator Bldg,In Response to Request Project stage: Other ML20236Q2381987-11-10010 November 1987 Forwards Safety Evaluation Supporting Plant Electrical Distribution Sys Design (Ref Tdi Diesel Generators).Approval of Design Required Before Performance of Loss of Offsite Power Test Project stage: Approval ML20236Q2461987-11-10010 November 1987 Safety Evaluation Supporting Util & Related Submittals Re Design Mods to Emergency Electrical Distribution Sys (Ref Tdi Diesel Generators) Project stage: Approval ML20236S0821987-11-17017 November 1987 Supplemental Application for Amend to License DPR-54, Consisting of Suppl 2 to Rev 2 to Proposed Amend 147, Concerning Diesel Generators Project stage: Supplement ML20236S0881987-11-17017 November 1987 Proposed Tech Specs,Consisting of Suppl 2 to Rev 2 to Proposed Amend 147,concerning Diesel Generators Project stage: Other ML20237B2791987-12-0101 December 1987 Rev 2 to Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75 Project stage: Other ML20237B2651987-12-0808 December 1987 Forwards Rev 2 to ERPT-E0220, Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Electrical Installation to Reg Guide 1.75, Per Class 1 & 2 Cable Trays & Raceways Described in NUREG-1286,Section 4.7.3.2 a 1 & 2 Project stage: Other ML20234D5061987-12-29029 December 1987 Forwards Listed S&W & Failure Analysis Assoc Repts Re Vibration on Tdi Emergency Diesel Engines,In Response to M Hartzman 871215 Request for Addl Info Project stage: Request ML20149D6311988-01-0404 January 1988 Forwards Engineering Summary Repts for 16 Tdi Phase I Diesel Generator Components,Containing Detailed Info on Design Review/Quality Revalidation Program.Vibration Problems W/Turbocharger Support Bracket Resolved Project stage: Other ML20149F0031988-02-0101 February 1988 Informs of Intent to Submit Formal Rept Re Vibration Surveillance Program for Tdi Diesel Generators.Actions to Be Taken in Future to Monitor Diesels for Vibration Listed Project stage: Other ML20196E6971988-02-0505 February 1988 Rev 3 to Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75 Project stage: Other ML20149L2391988-02-0909 February 1988 Forwards Amend 94 to License DPR-54 & Safety Evaluation. Amend Changes Tech Specs to Reflect Addition of Two Diesel Generators & Associated Mods to Facility Emergency Electrical Distribution Sys Project stage: Approval ML20196E6771988-02-22022 February 1988 Forwards Rev 3 to ERPT-E0220, Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75, Presenting Clarification for Actual Configuration at Facility Project stage: Other 1987-12-29
[Table View] |
|
---|
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 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 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 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 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) 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 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 IR 05000312/19980021998-07-15015 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 ML20217G6661998-03-18018 March 1998 Forwards Discharge Self Monitoring Rept for Feb 1998, Which Makes Note of One Wastewater Discharge Permit Violation 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 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 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 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 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 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 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 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 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) 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 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 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 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 ML20029E4601994-05-12012 May 1994 Forwards Response to NRC Bulletin 94-001, Potential Fuel Pool Drain-Down Caused by Inadequate Maint Practices at Dresden Unit 1. Util Plans to Move Spent Fuel Into Proposed Rancho Seco ISFSI by 1998 ML20149E3971994-05-10010 May 1994 Forwards Re Updated Decommissioning Cost Estimate for Rancho Seco & Attached Rept by Tlg Engineering,Inc. W/Svc List NL-94-008, Forwards Endorsement 118 to Nelia Policy NF-0212 & Endorsement 106 to Maelu Policy MF-00751994-04-28028 April 1994 Forwards Endorsement 118 to Nelia Policy NF-0212 & Endorsement 106 to Maelu Policy MF-0075 ML20029D3531994-04-28028 April 1994 Forwards Documents S11-25-003, Update of 1991 Decommissioning for Rancho Seco Nuclear Generating Station 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 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 ML20059J9161990-09-13013 September 1990 Notification of Change in Operator/Senior Operator Status for R Groehler,Effective 900907 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 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 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 ML20055J0331990-07-25025 July 1990 Notifies of Change in Operator/Senior Operator Status. Operators Terminating Employment & No Longer Require License ML20055J0311990-07-25025 July 1990 Forwards fitness-for-duty Performance Data for Facility from 900103-0630 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 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 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 ML20043G9521990-06-12012 June 1990 Notifies of Organizational Changes.Svc List Should Be Revised as Listed ML20043G5701990-06-12012 June 1990 Forwards NSHC for long-term Defueled Condition of Plant for Security Plan,Per Util .As Discussed W/Nrc During Telcon,Determination Made That NSHC Needed to Be Processed in Support of Security Plan ML20043E8191990-06-0606 June 1990 Requests Withdrawal of 900510 Request for Exemption from GDC 17, Electric Power Sys. Util Understands That Formal Exemption Not Required,Based on Discussions W/Nrc.Info on Plans Re Diesel Generator Operation Also Provided ML20043E1691990-05-25025 May 1990 Forwards Refinement List of Tech Specs Applicable in Defueled Condition,Per .Unless NRC Differs W/ Approach,Conduct of Activities in Defueled Condition Will Proceed Until Amend 182,Rev 1 Approved ML20042G9821990-05-10010 May 1990 Requests Temporary Exemption from General Design Criteria 17, Electrical Power Sys as Applicable to Use of Diesel Generator Sets as Peaking Power Supplies.Request Based on Special Circumstances in 10CFR50.12(a)(2)(ii) & (iv)-(vi) 05000312/LER-1990-001, Forwards Errata to LER 90-001-00,re Inoperable Radioactive Gaseous Effluent Monitoring Instrumentation Not Reported in Semiannual Radioactive Effluent Release Rept Due to Procedural Deficiencies,To Include Rept Date1990-05-0202 May 1990 Forwards Errata to LER 90-001-00,re Inoperable Radioactive Gaseous Effluent Monitoring Instrumentation Not Reported in Semiannual Radioactive Effluent Release Rept Due to Procedural Deficiencies,To Include Rept Date ML20042F3421990-04-26026 April 1990 Forwards Long Term Defueled Condition Security Plan.Plan Withheld (Ref 10CFR2.790) ML20042F6121990-04-26026 April 1990 Forwards Rancho Seco Emergency Plan Change 4 Long-Term Defueled Condition. New Plan Includes Provisions Necessary for Protection of Onsite Personnel & for Protection of Public Via Communication W/Offsite Agencies ML20034C4081990-04-24024 April 1990 Forwards Rev 5 to Sections 1 & 8 of Plant Emergency Plan,Per NRC Requesting Two Changes ML20034A9721990-04-19019 April 1990 Requests Extension of Date of Submission of 1989 Annual Radiological Environ Operating Rept to 900615.Extension Necessary Due to Legal Dispute Over Payment W/Contractor for Analysis of Environ Monitoring Samples NL-90-143, Responds to Generic Ltr 89-13 Re Svc Water Problems Affecting safety-related Equipment.Routine Sys Walkdowns Performed by Operations Personnel to Ensure Sys Parameters within Required Range1990-04-17017 April 1990 Responds to Generic Ltr 89-13 Re Svc Water Problems Affecting safety-related Equipment.Routine Sys Walkdowns Performed by Operations Personnel to Ensure Sys Parameters within Required Range ML20034B6701990-04-13013 April 1990 Forwards Quarterly Update of Emergency Response Telephone Directory.Directory Withheld ML20042E0941990-04-10010 April 1990 Advises That Util Intends to Submit EIS Associated W/Plant Decommissioning After Submittal of Decommissioning Plan ML20033G5981990-03-30030 March 1990 Forwards Mods to Plant Operator Training Program Submitted on 891228,in Response to Requesting Addl Info ML20012D7711990-03-28028 March 1990 Responds to NRC 900205 Comments on Util Discussing Tech Specs Applicable to Defueled Condition.Util Intends to Keep Area Radiation Monitor R15028 Functional at All Times.Spent Fuel Pool Bulk Temp Maintained at 80 F ML20033F8891990-03-27027 March 1990 Forwards Effluent & Water Mgt Project Action Plan to Address Current Effluent & Water Mgt Concerns.Util Closing Out Effluents & Water Mgt Project Action Plan ML20012E2211990-03-23023 March 1990 Forwards Amend 18 to Physical Security Plan.Encl Withheld (Ref 10CFR73.21) ML20012D6011990-03-16016 March 1990 Forwards Suppl 1 to Proposed Amend 180 Re Removal of Fire Protection Requirements from Tech Specs,Per Generic Ltr 88-12 in Response to Telcon Request ML20012B8731990-03-0909 March 1990 Provides Status of Inservice Insp & Inservice Testing Programs.Util Does Not Intend to Continue Normal Test Schedule for Pumps & Valves in Sys Not Required by Tech Specs to Be Operable NL-90-030, Forwards Endorsements 94,95 & 96 to Nelia Policy NF-212, Endorsements 82,83 & 84 to Maelu Policy MF-75,Endorsements 10 & 11 to Nelia Certificate N-49 & Maelu Certificate M-49, Respectively & Endorsements 5,6,14 & 15 to Master Policy 11990-02-21021 February 1990 Forwards Endorsements 94,95 & 96 to Nelia Policy NF-212, Endorsements 82,83 & 84 to Maelu Policy MF-75,Endorsements 10 & 11 to Nelia Certificate N-49 & Maelu Certificate M-49, Respectively & Endorsements 5,6,14 & 15 to Master Policy 1 ML20012A1401990-02-21021 February 1990 Forwards Updated Listings Re Deferral & Rescheduling of Commitments.Listed Items Will Be Reviewed Prior to Moving Fuel from Spent Fuel Pool Back Into Reactor Bldg ML20033F1661990-02-14014 February 1990 Forwards Revised Pages to Sections 1-8 of Rev 4 to Emergency Plan,Per NRC 900206 Telcon Request.Summary of Changes Listed,Including Deletion of Ref to Accidents Not Exceeding Alert Classification 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 ML20006F1451990-02-13013 February 1990 Revises 891212 Exemption Request Re Requirements for Simulation Facility Training & Testing.Requested Exemptions Commensurate W/Nuclear Safety Requirements W/Plant in Defueled Condition ML20033E3471990-02-12012 February 1990 Advises of Change in Operator/Senior Operator Status for H Coomes,Effective 900205 ML20006D6771990-02-0808 February 1990 Requests Limited Scope Exemption from Requirements of 10CFR26 Fitness for Duty Programs.Util Currently Implementing Program in Accordance W/Enforcement Discretion Granted in Commission NL-90-023, Forwards Endorsements 95 & 83 to Nelia Policy NF-212 & Maelu Policy MF-75,respectively,Endorsements 10 & 11 to Certificates N-49 & M-49 & Endorsements 5,6,14 & 15 to Maelu Policy 11990-02-0707 February 1990 Forwards Endorsements 95 & 83 to Nelia Policy NF-212 & Maelu Policy MF-75,respectively,Endorsements 10 & 11 to Certificates N-49 & M-49 & Endorsements 5,6,14 & 15 to Maelu Policy 1 ML20006D0201990-02-0202 February 1990 Requests Exemption from Simulator Training & Testing Requirements of 10CFR55.11 While Plant in Defueled Mode.In Present Defueled Condition,Use of Simulator to Ensure Skills & Abilities Re Plant Operations Irrelevant ML20011E1711990-01-30030 January 1990 Forwards Rev 0 to NDP-039, Sys Required to Support Defueled Mode, & Rev 1 to TSAP-4124, Sys Layup Program. Sys Categories at Facility Include,Operable,Available,Prudent to Operate & Layup 1990-09-06
[Table view] |
Text
{{#Wiki_filter:,
1
(
(
$~)SMUD SACRAMENTO MUNICIPAL' UTILITY DISTRICT C P. O. Box 15830, Sacramento CA 95852 1830,1916) 452-3211
,f AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA OCT 3 0 N
.AGM/NPP 87-348 U. S. Nuclear Regulatory Commission Attn: Frank J. Miraglia, Jr.
Ass'ociate. Director for Projects Philips Bldg.
7920 Norfolk Avenue Bethesda, MD 20014 DOCKET 50-312 RANCHO SEC0 NUCLEAR GENERATING STATION j
LICENSE N0. DPR-54 REQUEST FOR ADDITIONAL INFORMATION, PROPOSED AMENDMENT NO.147
Dear Mr. Miraglia:
As a. result of. discussions with the staff on Proposed Amendment No.147 and the Rancho Seco electrical distribution system, additional information was requested. Attached is the requested information. This includes questions, as we understood them, and the District response.
i Please contact me if you have any questions. Members of your staff with questions requiring additional information or clarification may contact Robert Roehler at extension 4918.
Sincerel,
ose F. Firlit Assistant. General Manager, Nuclear Power Production Attachment i
l cc:
J. B. Martin, NRC, Walnut Creek
(.
G. Kalman, NRC, Bethesda w/atch l-A. D' Angelo, NRC, Rancho Seco w/atch I
(jlljDDCKo396 07103o 05000312 P
PDR RANCHO sECO NUCLEAR GENERATING STATION O 14440 Twin Cities Road, Herald, CA 95638 9799;(209) 333-2935
s 1'
{
l RESPONSE TO NRC QUESTION QUESTION (VERBAL)':
I With reference to drawing E-207, Sht. 3B, Rev. O, analyze the effect of switch 52-4A202 being closed, diesel generator GEA2 paralleled to the of.fsite power, and a single failure at switch 52-48202.
RESPONSE
As these two switches have a single key, which is held captive in the closed position, a ' single failure of all contacts on switch 52-4B202 would be physically possible. Therefore, a single failure at switch 52-4B202 would be l
limited to a single short across terminals, i
For.this discussion see attached switch identification points for the i
following analysis:
Short between any 4 and any 7 terminals would blow the fuses to switch 52-4A202 from bus 4A2.-
If diesel generator GEA2 is not paralleled this will prevent paralleling.
If diesel generator GEA2 is paralleled there I
would be' no impact.
In either case, there would be'no safety impact.
j Short between any 3 and any G terminals would blow the fuses to switch 52-4B202 from bus 482.
This would prevent paralleling of diesel generator 1
GEB2, which has no safety impact.
1 Short between terminals 7A and 8A, 78 and 8B, 7A and 8B, 7B and 8A, 3A and l
4A, 3B and 48, 3A and 4B, or 3B and 4A, would not complete any circuit
)
and, therefore, would have no impact other than on the capability to parallel' diesel generator GEB2, which has has no safety impact.
Short betweer 3D and 4D terminals does not complete a circuit by itself, f
Therefore, this short has no safety impact.
i The conclusion is that a single failure at switch 52-48202 has no safety j
impact. Also, even in the event of a double failure (i.e., short) as follows there is no safety impact:
A double direct short (i.e., no resistance in short; a resistance short j
would blow the fuses to the switches) between 7A and 8A, and 7B and 88 l
would cause the 460 voltage balance relay to alarm as indicated on drawing i
E-104, Sht. 8, Rev. O.
Thereby, operator would take action and this would l
result in no safety impact.
A double direct short between 3A and 4A, and 3B and 48 would be evident on voltmeter at cubicle S4B200 and would have no safety impact.
1 i
Page ) of 19 l
C _ __
[
' ". ge_.
j7 r
,E i
RESPONSE T0 NRC. QUESTION-(Cont.).
j i
}
Even a complete failure of switch 52-48202.(i.e., both switches 52-4A202 5
and 52-48202 closed simultaneously, which as previously noted is f
physically impossible) would still Lnot cause GEB2 to be closed to GEA2 or 3
result in any detrimental effects.
Diesel generator GEA2 can only be l
paralleled to Startup Transformer No.1 and diesel generator GEB2 is 1
interlocked to prevent paralleling with Startup Transformer No.1.
l l
.The previous analysis is equivalent' for GEB2, Startup Transformer No. 2 l
and GEA2.
. The above analyses were based on paralleling'the diesel generator to the 4160V bus and thereby to the offsite power. The equivalent analysis would 3
apply if the paralleling to the offsite power were to take place across bus supply breakers 52-4A203, 52-4A207, 52-4B203 or 52-48207.
Therefore, due to the interlocking that prevents GEA2-from being paralleled to Startup Transformer No. 2 and GEB2 from being paralleled to Startup Transformer No.1, even a complete failure of any switch 52-4A202, 4A203, 4A207, 4B202, 4B203 or 4B207 will not result in paralleling of GEA2 and-GEB2; or result in any detrimental effects.
1
]
t
.s -
Page 2 of 19 w___-__
RESPONSE TO NRC QUESTION QUESTION:
(2) Page 8 (n)..- Reg. Guide 1.9, Position 7, recommends retaining other protective trips, beside overspeed and differential, only with coincident logic. Low lube oil' pressure trip should have a coincident logic.
1
(
' RESPONSE:
I The TDI' diesel generators have coincident logic, 2 out of 3, for tripping on
~
low labe oil.
i
.I l
l 0
1 l1 Page 3 of 19 l -.
mv jc
.m
,1
]
b\\
- t
'a
.\\
L 3
.(
,5
'p
'S
,g J
1, 1 #
3 p
j 1
, l h h'g
\\
'\\
A
. \\)
]d
'%8 1,
p
.,}_
a, f(
i' fpSDONSE T0 I!E' QUESTION 1
j j
+^
y3 p
8
.c 9
Od,,jUdd:
,\\
l')
l' ~,,
l 3
\\
n il.
-l-ECN't-374S,-3Elt%-](i
. t
>)
i 1
sN 1
s
)(t (i!1 Page.8 l: ) - Pgsf tf n 7 of Reg. Gu ne l'9 requires Eypass circuitry to t
meet IEEE!279 c/71 rdgerements at the system level and should include ~ the
.T three listeQi. Jabi?ities.
Confirm Rancho Seco compliance.
')'
a,3
, 7;t l
s
RESPONSE
6
,/
s
.t i
The TCfy.f etW1 generator installation complies with R. G.1.9, Section C.7, l
bypass"circijtry compliance with indicated IEEE 2T9-1971 capabilities as follows:
.s r -
- 41) 'The operabiWty of the bypassing circuit is tested at each refueling j
.f
- outage, j
,(s si g
s
.(
(2);. Any bypasse j ' trip is alarmed in the Control Room upon activation.
1
- b..,
(3) The reset of shq. hj?ns initiating' signal,(ESFAS) must be manually
.y reset.
. h "t
.I w/< z i
g
-{
n\\
,ge 4 of F.1, t)
?
\\
i
! k y
\\
t t
)
(..
- 4
?{ C ).,,
h i.m'{.-
e.
t r
, w w @3
,1
,N.
t, 1
1, i
4 s
1
- m wy x
.z,,,
1 m,<>
8.
4 c.
j.. ki, pp, ;
v.
o:-.
, ;i i
j g
D; '{g
-u '
w>
RESPONSE T0.'NRC. QUESTIONS:
g: p
~ [, f( V.
?
J:.
@.s a.
xQUESTION:.
\\
s:
v.
3
,}
'ECN:A-3748,lREY. 5;
'9' o
3 q
o
+m :(4). Page19.l(T) -l'DG.' Inoperative": alarm is-- provided-in the, main control ! room E
F.
'.: computer. : Verbala commitment made in past;to: design this" alarm as Class IE.
- Confirm.this': commitment. -.
x,
~ \\.i =
.:\\
4y h
RESPONSE
?
H s
M JThi;commitmentito/the NRC's Mr.1Ed;Tomlinson was ifor aD eismiclClassil.
- l
~
S a
y,b,, ? indication':of, seven -indicated..TDI: Diesel. Generator-trouble' alarms in.the.
J
^
control room.. : The, traditional "DG Inoperative" alarms will ; continue to report.
1
- on.IDADS. The: term Class:1E is:not applicable' to mild environments at' Rancho i
'Seco, only.Clessil meaning seismically qualified..
( wf:
n 3.-
1 s
s; e,
3 s y
!!.'k I
s I
(-
jn l
f l
1 s
!(
(
i
.1 T
t
(.'
9
,4, a
Page 5 of 19 i@
- .1 ?
?
i,.
v;;Q4
~
- ' ~ ~ - - ~ ~ - -
~- -- --
v
+
L.1; g., n - -
g(s u
1-u n.,
4, r.
RESPONSE TO NRC QUESTION,
,'l.
- QUESTION
- -
1 ECN A-3748, REV.LS:
. (5)?- Confirm that the. EDG' qualification' meets. thearequirement 'of ' Reg. : Guide -
4
- 1.89. and'1'.9.-and ; test capabilities will-be in' accordance
- with ' Reg.. Guide 1 108 and. GDC 11,8.
y 1
n,c
' RESPONSE:.
N
"~
', ;The TDI. diesel generator' installation meets IEEE'323-1974' for. mild.
.c.
environment. ? As. Reg.L Guide 1.89-primarily;; deals with harsh environment', it~
f
'r twas. not invoked. This installation meets the qualification. requirements'of.
Reg.--Guide-l'.9; specifically. Reg. Guide.l.100.'.. This; installation: also meets :
the, testing requirements of. Reg. Guide 1'.108. and'GDC 18; j
d 4
-j l
i *r i
a j
t
'1 g'
i s
-j a
s I
Page 6 of 19
.i N_. '
- m. -
y.
1; ;
^
RESP.0NSE TO NRC QUESTION:
QUESTION:
ENCLOSURE 5 -' DESCRIPTION OF THE DISTRIBUTION SYSTEM
,1 1
<(2) Table'1 (auto sequence starting) Note l'.-
Does the. sequencer operate.on
- loss of offsite power.'(LOOP) only ~and ~ sequences:the shutdown load. ' For a: LOOP:
on-one, bus,.the associated EDG starts 'and connects to the bus. Do the shutdown load starts-or sequencing 'is blocked.. If sequencing is blocked Land.
an SI signalcomes, how unblocking is accompl_ished and.how safety loads are started. - Explain the scenario.
RESPONSE
. -) :
r
/ All. loads l required for a' safe shutdown'are' automatically loaded on' to;their diesel generator in the event _ of-a < loss of power to. the. diesel generator.'s
. 4160V bus.
In 'all modes of ' operation tho sequencer provides the sequenceds l permissive tolthe connected loads.. For loads only required in the event of an
- ESFAS, the completion of the closing, circuit is 'accomp1.ished by an ESFAS contact closure.-
I r
.I a
i Page 7 of 19 L
- -ff
.p w
1
- j f,
RESPONSE TO NRC-QUESTION
?
" QUESTION: L l
ENCLOSURE:5 - DESCRIPTION OF THE: TABLE.3'AND ECN R-0955.
4 (3) - Thh four:25kva; deleted inverters were supplied from 125VDC buses SOA,-.
S0B, SOC and S0D and were respectively supplying 120Y AC buses S1 A, S18, S1C.
i
~ nd S10. Theinew 25kva inverters are each supplying an additional bus as per-a
' Fign2-and 3 of
Enclosure:
5 and the. sketch'with ECN R-0955..:Is the inverter >
l' sufficient'.for both buses. loads. They should be' qualified as Class 1E as
~
- the.ir-associated inverters.-
l 1 RESPONSE:'
The maximum combined load of; the respective.120V AC buses on each NSEB'-
inverter < is-14.2kva, which _is.well. below the inverter's rating of. 25kva. ' The
inverter.-. static' transfer switch and maintenance bypass switch.are qualified.-
1 1
- l I
l r.-:
l.
[,;
i L
i j.
Page 8 of 19 i<
___._._______________.___.._____________________a
V l
p ;r
}..
RESPONSE TO NRC QUESTIONS l
l QUESTION:
ECN A-3660'- APPENDIX D i
-(1) Page D-3, Item 5.
Transformer NSST is shown to be capable of. overload l
(109.3%) for a period of more than 4 hours without any degradation. GDC 17 requires both capacity and capability of the offsite power to perform its i
safety function. Cumulative effect of overloading is not identified in this
.i ECN. Also the capability-of this power with references to the consequential i
voltages on safety buses and the equipuent are not furnished. SMUD response j
to NRC question _12 is already considered.
i i
RESPONSE-GDC 17 states that the system should be capable to perform it's function under
. anticipated operational occurrences. - The indicated theoretical overload is not an anti _cipated operational occurrence. To reach this theoretical overloaded condition-the following would 'all have to happen:
- Loss of Startup Transformer No. 2 offsite power, source.
- Loss of both diesel generators, DGB and DGB2.
- Operate three (3) 100% capacity HPI/ Makeup Pumps. -
- A design basis accident.
Furthermore, even if this could happen it would obviously be a one time occurrence in the life of Rancho Seco and, therefore, would not represent any cumulative effect on the life of the Nuclear Station Service Transformer.
Pa8e 9 of 19 a.
. m. _.
r a,.;
m.
r e.,
- ,p -
+
,. v.
I=
h' a.
.,..g l~.I'k- }
' -~
+
n o.,
u 4
9: 3..
h RESPONSE TO NRC QUESTION 1
1
'1
-QUESTION:
H, i ECN A-3660 - APPENDIX D ~
l
^
- l
.I
- (2) Page.D-4,.: Item' 9.=
Non-op'erative ' alarm forl.;the battery charger 'should' be :
like the DG.inoperativ.e". alarm as in Question 4 on ECN A-3748.'.
n q
RESP 0 NEE:
l
~
.j There has been no previous-l discussion on extending the. commitment made to the-j
. NRC's' Mr.1Ed Tomlinson for selected DG trouble seismically qualified-alarms to -
-:other systems.. Nor. do Lwe'see any need or. requirement to-de so.
i i
-l i
c I
l I
l l
Page 10 of 19
r 4
RESPONSE TO NRC QUESTION I
QUESTION:
ECH R-1045 The operator transfers load to EDG when bus voltage is 4500 or 237.5kv grid vol tage. Confirm that EDG can be synchronized at 4500 volts and no detrimental effect will be caused.
RESPONSE
i
)
As stated in the Amendment 147 Technical Specification, Safety Analysis for i
items in Section 'III, the operator will start taking action at 4500Y and j
complete transferring loads to the diesel generators before the bus. voltage
~
reaches 4626V.
The diesel generators have been tested up to 4700V and no-detrimental effect was caused. Also, upon opening the normal bus supply breaker, after paralleling is complete, the diesel generator operating mode will automatically change from DROOP to ISOCHRONOUS.
Once this occurs the generator _ voltage will automatically be returned to it's preset point (nominally 4160V).
I I
1 l
l
)
l i
l Page 11 of 19
I' f
TECH SPEC REQUESTS FROM NRC (IQBAL AHMED)
I October 21, 1987 i
NRC Concern:
ECN R-1045 has the operators paralleling the diesel-with offsite power when the 4kV bus voltage increased through 4500Y and procedures to reduce this voltage have not stopped the increase.
The concern is that the onsite emergency power sources are connected to an abnormal' offsite source. This exposuro would occur for each 4kV Class 1 bus as it is reconfigure to the diesel and this is considered a potential common mode failure (Reference GDC 17 and Branch Technical Position ISCP-8).
District Response:
The District commits to not parallel the emergency diesels f
except for testing. The offsite supply breakers to the Class 1 buses will be tripped before the buses are exposed to 4626 volts.
NRC Request:
In the District's October 2,1986 submittal of Proposed Technical Specification Amendment 147 under SRP 8.3.1 Requirements, Section 4 Standby Power Supplies, paragraph concerning reliability and operation item "d" - preventative i
maintenance program; the response states that applicable.
l 1
recommendations of the TDI Owners Group will be incorporated into the TDI diesel generator preventative maintenance program.
Add a statement that all the SRP requirements will be adequately i
addressed.
District Response:
{
The HRC and the TDI Owners Group have agreed upon the J
preventative maintenance required for the TDI diesel generators
)
and published these in NUREG 1216 ( August 1986). Technical i
Specification 4.6.3.C.1 a) and b) both reference the recommendations made by the TDI Owners Group. The District comniitted to implement the maintenance and preventive maintenance requirements of NUREG 1216 in our February 20, 1987 l
(JEW 87-232) submittal.
1 1
Page 12 of 19
s:
t
- {s/OMUD CALCULATION: SHEET SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201SStreet.P.O. Box 15830.SacrarnentoCA958521830(916) 452 3211
-o
' ORIGINATOR DATE.
CALC.NO.
!4*L' 64 /"ZD'A b/A Y 8'J -
CHECKED SUBJECT-'
l' A & 4 (W-
,l0.- $b2'i%/ 01 lt. 2"V13 *5 'E 05'1k 0V A, SHEET OF'
.. p i
.i 2
b 4
i 6
7 s
i L 613O PEC Pr4' ! ; 72 Yth'
~
l
. IN VER T.:R
~
n i Aux. bum l N 5.ES
(;< V A )
12
> lA C
'0l A 5lA L -l
'N
.4,$ 0 7 f5 -
1
.'s
^i
- sl:*
~ 515:.! -
Si n ~
/5,1<'
3 j (!SC 8.-79 it
)
S/C SIC:-/
18
,$ / C2 5, 4 C.
C,6 0
[ 6 10 S/O
\\ S!:L t i 4 / ~^ '
S,85
! b,do
.' 4 46 i
22 23 24 ts t
26
}
27 29 se 3'
I 2:
33 34
.... - - ' ~. - -...
35 36 SMuo 1420s 10-84 Page 13 of 19 w-____--_
October 27,.1987
}
Selected pages from. Calc Z-EDS-E0104, Rev.1, per request of -
' October 21, 1987.
i I
f I
i i
i
.]
]
'l
-1 I
l l
l i
i 1
l l
1 l
l s
Page 14 of 19 b:
CALCULATION COVER SHEET SMD SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201SStreet.P.O.Dox15830.SocrementoCA9585218301916) 452-3211 calc. wo.
svaxci Un bErt \\)0 L7 AGE / UV ) d Ovs?? V6L.7 AGE (MJ
\\
RELAV E s,'TlblG E.,L E.[C.SMiTCHC6 ):l':
S~
$"h/N
&~ 17 0 /
ovauty cGis i
/
C0tmNUO ON M 1 A-
,,,,, 3
"" " "' /
l N
RECORD OF ORIGINAL ISSUE AND REV1310NS SMUD ORIGINATED CALCS CEPT WJ-
' 870VW or se navisioN ossCaienoN 04T onio.
Cxn.
Q O(h GI N A L.
}[ftJE 9-20-8 4 Cet Vf7AaliC st{ES T I
G u lbt r\\L fE Wr/oA/
ll-14-8h Go, W W/gk r
l 1
J l
RESULTS OF CHECKER REVIEW l
I 9E%l$10N NC.
litM OtSCRIPnON I
E l
S
~~~
~~
0","C!WN#CJan'n80'N! cts'sM' " '
iMn=
M p3 gg si FICANT NEC $sARY OHRE T N ARE MADE.
IMTIAL AYTAr*W$
CHECK MADE BY ATTACH (O ALTERNATE INITIAL f4.:0 7 C ALCUL ATIONS.
SHEETS DATE ecg.o ee rsir cate_. we-usuiss cat.c. z-soc-sootf (A.Ce f.2,9C.,)
1 l
I l
l l
A QE e V ek:#$ u-1.s-rg
, %TAL. No of CHT't 6 esEEam B A. Schm'itier f@MTmats E5
///iy/5 omanaron C. K VoHre 4
(
M%6 -
()
( (p C
9-z6-RG, r
CHECKER
$ g, ggQ
\\ [c,k.[s.M-(A,,,,,_,
Q {. g F,,.,"
gf /g, /g g f.[ggM/
b
'l[M SUPVY, REvtEW h
d PPINTE6 NAME StGNATURE 7
'INffiAL OISCIPtlNE DATE swuo.ists cas
)
Page 15 of 19
]
O O
CALCULATION CHEET z.-GE8N't CALC. NO. A.s.02.2 r73 s
- [L 2-28-83 DATE '2"2 b 3 SIGN ATUR E A
DATE CSiECKED PROJECT - 'EANCHO YECO JOB NO.
INN SU6 JECT UNDP RVOLTACG A CVERVOLTAGE RELAY syggy 7
op SHEETS me r rtyc1 PnR cs e s waa..
2,4-6 d? v/ UAL. SAIf V 0 & r.4 6 s c 5
d.
3
,l _
gg n
7 s
e l4a
- v..~
7T m}.S 4g N
3sva Ao J.uan wm se b.a,n$o a.s t
. b.
Y.
o y
a 5.
s a
e m
'2 m
B; 3
y q
a b
2
$s.>g 9
a i4 q
Tw S
MS-w g
),,., t g
b e
\\p l
>d 3
s 5
4m b
b
'Y $
O O
is d
J N
V.
V 7
19 l
g hC T
~
k sm C$td
/m d" I
4
- o x se ut e 5
?oY s
2 o
Oo a, s R=$c..e.
mf@1 2'
4 a
c-m dQl
{
?
NSq% 'ws g',k $ 8
\\
3 E
E
.].
%1:
s y
R m
v 7.e 2
l w~ 9
- j n
t u
~
<8 uf 1; ~S $.14 8 e
sa
=
n w
cc# us 89, 2
R W# SW!V#l H.Aeg),
D. i. ed "
BM \\55*/
A b
f
~~~
d__.M.S'
.ad L
g1 v
k4@g$,
1
['
f-g"?
c l
GG6@
=
,.u
- 0 3$_,
1
=
u m_m.___
)f W
$V ')
JOB NO. Jg 13 sf CALC. NO. Ma,.8 e.. /2 E.,
PROJECT SHEET NO. /6 4 2 ' S ' * #
! V A 0lV ll*..L A '/ f g r Y p ](*; &~ f y -Q' N Y Ff SUBJECT REV ORIGIN ATOR DATE CHECKER
,DATE REV ORIGIN ATOR OATE CHECKER DATE G
Yit/{
.,, ldlff /s sh f.
'N f*
f
/\\
/\\
10 u !f$g/jn lb: itM I
(Mo/g{35 0'ET' 'U! 'in is ' "r e
=+<<4
! _. j,, _,,, _.,L 9
f,7
-u Oe
W 2.: " U s e t m :'. p~ > ' -
~
k
'a 3MW.gili nj! ! iill f'._.._.:.. :.
g _'.. '
T a
i 7
_2.: =.
7.
r =....
.m:;.
,4: :
}.-
l
.,}:. :
1..
6 u_..
_.p
...._ I.. u 1-
......y,y.-, n m y p.i eer"y", - y
- y.. T
- o n
6' m 2
L1Lvnet' LAY.iTRIp. 5ETTIN,G
< +.
y b).
- f? :}*
' AM O QV/UV ALARIK
..t., :
i a.~
4:
3
"#(-)4,C. )(1%y l~~
- A NY [$
A A (A0 )
y
~' }.f~ 4800 56Y l;.
M M)
'2 g.
.g /(0 6 k.-
7h.L 3
g y
c
- ,h;
-d 2.s 4#Aw dvs shun !
lvbt Yf.Oll2PV l
4 Md. _.
42 _ h.i. ;.,i....: ;
1.s d
..At E l
- M.. %MI $. A@
i
.Sg g
.p.
27 (l1~6 27 D) b
' 4ggoy 4 }'
39:
ifLMM AT 4:2oV{3740).
'~
~
f k 9L...._.._...........'
'I
,421 Fh A '.011-SI)2
.. ~.
pj l
I i
% 8,. 427 AA5/~ 4tUI
L E
t\\
-.L 6
l$/
~ L"# * *)
(r rs 2 j
" f7 7h-h\\,
'l
~
)'~~
n" n,;.
u c
s ; s u,.< w.2.7^ \\
m scr. n%.nw w,D4.
.4
. O
- 4 V. : ii F
l
/
v.
e q
e >.
f i
- 8
.... E.E ii.
S 'l \\1L5BD)
- 3. -
a, 421-iAf3dfa fEAn !......= I fY.f -
Y l..
9
- eN
- .j'.L '
N, 3(._M1-It@) p,M' W...
hl*V 'Q '.gy 3,, -
gs (JTr 47 r
it.
- j nw rAf3.
{.
f V'. -. &.. _
u.
s, 2.
Q; l
C STEAtfL51AiE.yoLJ'AkE. % 2.1.S.
g D*
2h A
i 2
!I -
1/MC7N'3
'lLL..
Ji
( REP- )l) 1.
5Td!GG#F 35 dig Ei:
!Mi% Val.FME Di#A7:-
- 12 la 3
.-cwVn,,,
my p# f yf. N_tb lL7
......': d3 9
p.
l
.1.
-(WMrr u 5 0v1 10 2.d
' '. : 1.... : E" J. 67. #. Ea
! r/ //c.
..i... m.pr;spmC96)
__L__.____
3 y [a#j' lj 7
9 9 i
2
?5 3 4
5 6
15 20 25
'O p
7 y 7 i
i ?
O e;.'
e aea
- 3. '3 5 3 3 3 e votre x 4 e EQUIV. volts oM 4160V BUS,
L Page 17 of 19
I9 O
.O
' r
%)cs CALCULATI'dN CHEET' 2'-e~Df-M....
calc.No A* M '2.I21 Nt b IM SIGNATURE
. (fL DATE CHECKED DATE PROJECT 7AO'M $E(o MN JOB NO.
' SUBJECT UONW3M F'dMP\\/07/V#
WN SHEET OF
'2 1 SHEETS serrm6s nw ese s u.)a A, 3, 4 S Q Ut VA c dAJ 7',Vo c.rA G 68 G)<
eM G4 4
a "kk i
Y~*'9;'
3
~
y Jt 9 P.
y 45& %,: o m 3
s
~
E m, 15m m 4, b
. A t/ L&* /.'S/ W
'A HW E 00 0 h
4s, V'
a N
2
@>)
09 9
m w
b v
Fw W
G h.
S_
xs Q
's is g
14 Th
,f
)
is J
s O
L
'Q a
a 3
'G is
. :s i
T
~
n
)9 T
U 5A h
h D
l bgl
.6 Q
g o
L
% i, \\T
{
re, is h+ll
-w ga* m >I is a
-s.
y awj
}
d,,
r*
gi f> m "Ej zo i
y
>ij@f W g-
'[
$w h-I
~ ma
{
tk b j
/'
e.
3 2
h w,
Tu x,g
$uRi Y
h h
? -
@Ikkstifh!'
e' s ei e3 c _ _ y. s e
u e9 i
a e
-~
..- n
, 2,.
r
~ m
< m l
s "k/
28 u o,8 n 'Nt s
^mo? I ; on.
[)
'. c:J g
u o
l b
l N
9 t
Oc 6%
W (a.5g' O"
Es-o 5
dW6$
u
~%z sy d
b 6@@@
~
9 o$
as s
e4
~
1 l'
'41ur' 1
1 ya e ci
!APh W W0 JOB NO. ]21.$N CALC. NO. M A '
s a-L:!& E/N)
CUBJECT h l Oll W Y AMf5 N b. $ 0 'G A S EET NO. W W 2 7, \\,
~
REV. ORIGIN ATOR DATE CHECKER DATE REV OMiGIN ATOR DATE CHECKER j DATE F
(~'.
M).
< M HPA > 1h/ft y.ety,
ujule /\\
$oti eo b
i f
10.
i
....-....itEi-.dhEkhttiiiE@M! it' @ hh !$f II._.d._. _...!!!!
3 Ifl?\\!-
d!...d.:
l i
i!!'
I!! U-Wi
- fih!
Y 9
i" *!* " * **d * * * *
b"-l t c i.}
.F
~
iiiF M W ' TUi"q;
- nF i"Fjiify:ilig pp
. an e ip; i.. ;.-l"- - - l -
- .tr.:: -
m: :~.::::.. a:t "
.tn r.:....
t::5..'(*-
p:
S: ::'.:
i; 1
., P -
.1 10 lp: ' e"-',i idi
.n. :s i H i+ :i m m
y, i a 'D t+
I. ' a Q
6.
+ - - -
. :} ;r m. mpgc';Mg' ;.i y' m
+
i i.
1 W
W k
V W*D]M9ELAY TRIP SETT/UL
^
s.
- ' L s %m m:.# :#?.juu,0ggm w mi n c hu..
m.oggjy !Az.yus t '4
..e in.. : IN.i.4: ! ' f I r! 3 i j H "
4.
...' !.. i. h. h. "."ri. li:" ' " S..p. ".E. i. it.!,J. j f.l.!.i.f.u..' i: !.$.i.i...",4 i
i
, aggg. g.gg
.q j q' I-
.,, i f,
-l-
.,,,, 4g.. 2.d...D..<//2 W:"'.. a p't.-g....gg
.u M.
N
'.g. gg' g g2, (g g' m
i
- ggr, o
W
.M........jhN
.. W;d...
b G XfMd
..'..r.-
. Il i
,...p e3
,.m...
. t~t t
.N f%... p.
.. :. t
.(
7.e.
p u.
7
+
.5 F,
a
- B]U.S -3
'h.
f./t.y/,l'
.E"
^
t M,... :OV
.. i
- l T(N2J:
2
- g.
- ~. -..-.---_. - -,..
h-
.): M r-
)
M42@@4 i
- (MJ t..n
- 42'l 1.5 t Au e------@
i N. N $
J. H.4.*
bLhP.M
~
,f, dgy
.....,.e...
. I.. ',
le
.l. j.,],i...
i i.
i o
I, I
a i
10
% Eii!!#!?.~$: iiH Nil
~ T';
'!N id Mi l
3 6
i3 L-7 3*f,.(jfE_27h___V '[ __.. _1_ __1.
._. L _I
_;f d?J Mj6h@fd.gff G)
$N Mi! E~
I Wp
'.. n l
Jti
- Miii E!!b li:.
~
/.
i_.42L:..gSN,..::iitqE:
X '...
i.
..q _._
g G" ~ :-
U"i:"I"9: d!E.0" O E 27Nh..
m.:.'N f;.
- 'f...p*A A.(jfq,,, g 7g),g_._..h p.g "1
"+"
6 g[
f__11. _tf Q %
c:.3,
. :.i,
.w q..
q...1D4 g g.
l p..; j 9 !
h! M 1N70 DM8' M
--.u 73 F.. -'
1:rg s': IqiF. [,A 3 gg3...
. iv :Fi;i,n.
a i
,---Mi..--
.o-
-- -} -- r-u 3
?
i
$ $ h.th5 "' '
b
-- ~
t 4
?"*
~~di - M.:AT s0 4@-"'"~'l F ~'~~l-F',j i"
..l.*"mE..... ::
u; q)l. -..: ".). g U::.tn.:-~'"
rw j
4 n
- lu...:y'::--,g y:
up j-i
- a..., ;.; m. y
- 2. n. a.a.:._
q.
9 n
~
.p
!. l 4l fe
.[.
" b.t...r.:1 :f r~
.a i j
j
. y..
a g-
'_i.
1 t"
]
-o.
, y 3
IM. ' II 1 btdi.
- l I'. i' -
I-b.N M ijih..d
'.i ;.
1;-
I I
r-J l
l
. I I
$.a 2.s.,_ M 3 M M Q
.!!.w-
- PG:8.
t J:-
g=.?
n.:
.- q a
t v::
S J5t!pE.%i M.Nd:!$5NII 4!!
.m : c,..
u i
i i.
m m
. c.. g
=
d; 1 "i..
i I i I
%!!!M :- ! !E?!!iI '" "
' ; MY sredMd L%E.LMl3M_i.4 ' L mi2
+
=
.h.l i
(REO \\s) '
. tTs3M3 :" ?.M M!FiDM"" E~N'9 "D"M"Au
?
. t..M. R..
S i
...n..d..b.,.:..t
..n i
. r.7 a
.....,. 2.. :... ut h@k-M. HP NM e n d m )1,h:
1.s WN
- i..
n: n:n r9;....: tm d.W t:sinYow l 1
-- m r: t;
.r.;;;-m g
- g:r, g....
y... 7 j
f grWuwiemu
..g ei...,. ;;.4;....".a:(wy]s.T6. 4...pr.9.a f
- r n,.
..v.p
- g rp
.-H @ir#m.0 in'N W4W)WW @ rr -;'
'45: '
.i' I
.,,.. 1 o.
3 9 -@h 'te i s
,1
,3 2:5 s 4
4 i
is 7oso*1(
1.s 2o 2.s ao
.to so no m
.s m
'c-P 8
8
]n
$a
& Po 8
8 l
o n.M m
,o u
w
- n w
m u.
w w w w w w s.,
s.,
s VOL*TS. X 4M t
_E.QUlV. VOLTS ON Al60 V BU.S Page 19 of 19
)
-___}}