Letter Sequence Approval |
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Results
Other: ML19210C119, ML19247B236, ML19250A524, ML19250A528, ML19257B027, ML19260C126, ML19260C878, ML19309A657, ML19309B061, ML19309B071, ML19317G911, ML19317G973, ML19317G984, ML19330B670, ML19332A733, ML19337A632, ML19345F375, ML20148E958
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MONTHYEARML19319E1821976-08-12012 August 1976 Requests Info Re Facility Vulnerability to Plant Operation & Equipment Failures During Degraded Grid Voltage Conditions Similar to Millstone 2 Jul 1976 Occurrence.Description of Millstone 2 Event & Request for Addl Info Encl Project stage: RAI ML19309B0611976-09-17017 September 1976 Responds to NRC 760812 Info Request Re Grid Voltage Degradation Effects on Class IE Electrical Distribution Sys. Defines Facility Operating Limits Established by Grid Stability Analysis & Discusses Electrical Sys Capabilities Project stage: Other ML19317G8981977-06-0303 June 1977 Forwards NRC Safety Evaluation & Model Tech Specs Re Emergency Power Sys.Util Requested to Submit OL Amend Application Incorporating Tech Specs Comparable to Model Tech Specs Project stage: Approval ML19317G9111977-06-0303 June 1977 Model Tech Spec Tables 3.3,3.3-4 & 4.3-2 Re Engineered Safety Feature Actuation Sys Instrumentation & Section 4.8.1 Concerning Surveillance Requirements of Electrical Power Sys Project stage: Other ML19317G9021977-06-0303 June 1977 Safety Evaluation & Statement of NRC Positions Re Emergency Power Sys for Operating Reactors Project stage: Approval ML19317G9731977-07-19019 July 1977 Responds to NRC 770603 Info Request.Discusses Facility Second Level Voltage Protection,Undervoltage Scheme Mods, Emergency Bus Load Shedding Features & Tech Spec Test Requirement Demonstrating Onsite Power Source Operability Project stage: Other ML19317G9841977-10-10010 October 1977 Responds to NRC 771005 Telcon.Submits Util Schedule for Emergency Power Sys Redesign Work,Tech Spec Mod & Mod Completion Project stage: Other ML19309B0711978-01-0909 January 1978 Discusses Commitment to Installation During Aug-Sept 1978 Refueling Outage of Second Level Voltage Protection Sys for Nuclear Svc Buses W/Coincident Logic Per NRC Project stage: Other ML19309A6571978-06-20020 June 1978 Proposed Amend 51 to License DPR-54.Includes Tech Specs 4.1 Re Instrument Surveillance Requirements Project stage: Other ML19309A6551978-06-20020 June 1978 Forwards Proposed Amend 51 to License DPR-54.Tech Specs 4.1 Re Instrument Surveillance Requirements Drafted in Response to NRC 770603 Request for Review of Onsite Emergency Power Sys Project stage: Draft Request ML20148E9581978-10-31031 October 1978 Notifies That Util Cannot Obtain NRC Approval,Perform Calculations & Purchase New Equipment for Installation of Second Level of Voltage Protection by 1978 Refueling Outage. Proposes Mod Completion by End of 1979-80 Refueling Outage Project stage: Other ML19257B0271979-04-12012 April 1979 Forwards Background Info on 780916 AO at Facility & Sample Generic Ltr to Licensees Re Adequacy of Station Electric Distribution Sys Voltages Project stage: Other ML19242A4121979-06-26026 June 1979 Transcript of 790626 Meeting in Washington,Dc.Pp 1-55 Project stage: Request ML19274F9791979-07-18018 July 1979 Forwards Request for Addl Info Re Degraded Grid Voltage, to Be Sent to Licensee in Order to Complete Review of 771010 Submittal.Response Required within 45 Days Project stage: RAI ML19208C3621979-07-23023 July 1979 Submits Contention in Support of Request for Hearing.Plant Endangers Health & Safety of Population.Sufficient Mods Have Not Been Made Re TMI.Long-term Mods Must Be Implemented Per NRC 790507 Order.Certificate of Svc Encl Project stage: Request ML19247B2361979-07-23023 July 1979 Requests Addl Info Re Degraded Grid Voltages.Requests Response within 45 Days Project stage: Other ML19250A5281979-10-15015 October 1979 Requests Extension to 791018 for Response to . Delay Caused by Need to Modify Min Expected Voltage Assumptions & Perform re-analysis Project stage: Other ML19250A5241979-10-15015 October 1979 Notifies of Invalidity of 770603 & 760917 Submittals Re Degraded Voltage Susceptability.Fire Protection & TMI-related Mods to 230 Kv Transmission Sys Necessitate Redesign of Safety Grade Onsite Distribution Sys Project stage: Other ML19254D6491979-10-16016 October 1979 Responds to 790921 Request for Review of Unnecessary Challenges to Reactor Trip & Safeguard Sys.Forwards to NRC Re Review Project stage: Request ML19253B8121979-10-17017 October 1979 Forwards Response to NRC 790808 Request for Verification of Adequacy of Offsite Power Sys & Onsite Electrical Distribution Sys.Existing Sys Will Be Adequate W/Normal Plant Lineup After Implementation of Mods Project stage: Request IR 05000312/19790211979-10-17017 October 1979 IE Insp Rept 50-312/79-21 on 790904-28.Noncompliance Noted: Physical Security Project stage: Request ML19210C1191979-11-0202 November 1979 RO 79-13:on 790808,reanalysis of Switchyard Voltage Indicated That Present Setpoint for Bus Unloading Is Insufficient to Prevent Nuclear Svcs Busses from Decreasing Below 75% Rated Voltage.Undervoltage Relay Changed Project stage: Other ML19210E3901979-11-26026 November 1979 Submits Followup Request for Extension from 791105 to 791117 for Completion of Mods Re Degraded Voltage Conditions Project stage: Request ML19260C1261979-12-0606 December 1979 Corrects Util Re Max Experience Switchyard Voltage.District Changed Setpoint of Existing Overvoltage to 241 Kv During 791117 Outage.Operation at 241 Kv Acceptable Project stage: Other ML19260C8781980-01-24024 January 1980 Submits Clarification of Util Status on Degraded Voltage Mods.Will Submit Second Level Coincident Logic Design W/ Required Supporting Analysis & Documentation for Review, Comment & Approval by 800303 Project stage: Other ML19305D7101980-04-0808 April 1980 Responds to NRC Request for Info to Suppl 791017 Response to NRC Re Grid Voltage Degradation.Info Will Be Submitted by 800425 Project stage: Request ML19330B6701980-08-0101 August 1980 Forwards Revised Response to Inquiry on Adequacy of Facility Safety Grade Electrical Distribution Sys Voltage Since Condition Discovered at Millstone Unit 2.Util Is Planning to Implement Mod to Sys During 810601 Refueling Outage Project stage: Other ML19332A7331980-09-0303 September 1980 Requests Addl Info Re Adequacy of Station Electrical Distribution Sys Voltage Project stage: Other ML19337A6271980-09-22022 September 1980 Forwards Response to NRC 800903 Request for Info Re Adequacy of Station Electrical Distribution Sys Voltage Project stage: Request ML19337A6321980-09-22022 September 1980 Safety Evaluation & Statement of Staff Positions Relative to Emergency Power Sys for Operating Reactors Project stage: Other ML19305F2481980-12-0404 December 1980 Safety Evaluation Re Degraded Grid Voltage Protection for Class IE Power Sys at Facility.Proposed Design Mods & Changes to Tech Specs Are Acceptable Project stage: Approval ML19345F3691981-02-0202 February 1981 Application for Proposed Amend 51,Revision 1,to Ol.Forwards Proposed Tech Spec Changes.Changes Include All Items Submitted in Proposed Amend 51 Submitted on 780620 & Revisions Agreed to by Project stage: Request ML19345F3751981-02-0202 February 1981 Tech Spec Pages 4-34,4-34a,4-7b,3-41,3-42,3-43,3-44,3-41a & 3-41b Re Emergency Power Sys Periodic Testing & Auxiliary Electrical Sys Project stage: Other ML20086J9051984-01-0404 January 1984 Temporary Loss of All Ac Power Due to Relay Failures in Diesel Generator Load Shedding Circuitry (LER 83-18) Project stage: Other NRC 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 ML20126J8901985-06-0404 June 1985 Safety Evaluation Supporting Amend 68 to License DPR-54 Project stage: Approval 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 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 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 ML20135E8721985-09-0909 September 1985 Safety Evaluation Supporting Amend 74 to License DPR-54 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 ML20234D6151986-12-31031 December 1986 Pipe Vibration Survey Emergency Diesel Generator a Rancho Seco Nuclear Power Plant Project stage: Other ML20234D5241986-12-31031 December 1986 Baseline 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 1979-07-23
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June 3, 1977 DISTRIBUTION:
Docket File HRC PDR L PDR E
Docket No.:
50-312 ORB #4 Rdg
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RReid a g.;;
RIngram Sacranento Funicipal titflity District L01shan ATTN: Mr. J. J. flattinore DJaffe Assistant General !!anager Attorney, OELD and Chir.f Engineer 01&E (3) n 6201 S Street DEisenhut
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P. O. Box 15830 TBAbernathy F
Sacra 7 ento, California 95813 JRBuchanan ACRS (16)
Gentlenen:
Gray File RE: RA!: CEC SECO NUCLEAR GENERATING STATION We are currently revicuing the onsite energency power systens of all
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operating nuclear power facilities to assess the susceptibility of their rafety related electrical equipment with regard to (1) sustained degradec voltage conditions at the offsite power sources and (2) inter-action tetween tne offsite and onsite energency power systems.
We have completed our review of licensee responses to our previous eeneric recuest for infentation relative to the electrical power aistribution systens.
ilased on this initial review, wo have prepared the Safety Evaluation and Statcaent of Staff Positions contained in.
We recuest that you conpare the current cesign of the energency power systens at your facility (ies) with the Staff Positicns stated in the enclosure and:
(1) pronese plant nodifications as necessary to reet the Staff Positions, or (P) provice c cctailed cruslysis which shows your. facility design has equivalent capanilities and protective featurcs.
Additionally, sie recuire that certain technical' specifications de incorporated into all facility operating licenses.
tiodel technical specifications, consistent with the Staff Positicr.s containec in Encinsure 1, ero provided in Enclosure 2.
Accordingly, we reo,uest that you apply, within forty-five nays of the receipt of. this letter, for an anenG ent to your facility cocrating f,lp-f, license!s) to incorocrcte enrocra: ale technical snecifications ta_ those presented in the encitsure.
Addittanally, you should provide a coscription Md a schedule for the ce"piction of any picn'. sssociated J
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Sacramento Municipal Utility District If you have any questions on this matter, pleasc contact us.
Sincerely, p.
Robert W. Reid, Chief Operating Reactors Branch #4 i's Division of Operating Reactors
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Enclosures:
1.
Staff Positions
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2.
!iodel Technical Specifications cc: See neat page 9
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cc: David;S. Kaplan, Secretary and General Counsel
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E 6201 S Street Post Of fice Box-15830 -
Sacramento, California - 95813
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' Business and Municipal Departnent-Sacramento City-County Library 828 I Street Sacramento, California 95814 i.
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