Letter Sequence Request |
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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
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
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
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
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
IR 05000312/19790211979-10-17017 October 1979
IE Insp Rept 50-312/79-21 on 790904-28.Noncompliance Noted: Physical Security
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
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
1979-11-26
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SACRAMENTO MUNICIPAL UTIL'TY DISTRICT O 6201 S Street, Box 15830, Sacrpmento. California 95813; (916) 452-3211 Octooer 16, 1979 Director of Nuclear Reactor Regulation ATTN: Darrell G. Eisenhut Acting Director for Operating Reactors Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555 RE: Docket No. 50-312 Rancho Seco Nuclear Generating Station, Unit No. 1 D. G. Eisenhut letter to All Pressurized Water Reactors dated September 21, 1979
Dear Mr. Eienhut:
Your letter dated September 21, 1979, requested a review of unnecessary challenges to the reactor trip and safeguards systems at our facility. This request was preceded by a letter from you concerning the same subject, dated June 26, 1979. The Sacramento Municipal Utility District responded to the first letter on September 28, 1979. A copy of that response is attact.ed.
If you have any questions regarding this matter, please contact Mr. Ron Colombo at the Rancho Seco Station.
Respectfully,
- 0. ! LGCa J. J. Mattimoe Assistant Gene ml Manager and Chief Engineer JJM:RJR:RWC:sik Attachment
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- ppAC4f 3 MUNICIPAL UTILITY DISTRICT O 6201 3 Street, bs 1M30, Sacra nento. Cahf:rnia 9M13. m() 452.:211 September 28, 1979 Director of Nuclear Reactor Regula: ion
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Acting Direc:er for Operating Reactors l
Division of Operating Reactors U. S. Nuclear Regula: cry Commission
'iashington, D. C.
20$35 Re: Docket No. 50-312 Rancho Seco Nuclear Generating Station Unit No. 1 D. C. Eisenhut letter to All Pressurized l
Water React 9rs dated June 26, 1979
Dear Sir:
Your letter dated June 26, 1979, requested a review of unnecessary challences to the reactor trio and safecuards syste=s at our facility.
The Sacramento Municipal Utility District is hereby submitting the requested respense.
A review of our plant operation history indicates that aute=atic safety injection system actuations have not been a cotron occurrence at our facility. With a few notable excepticas (reference LER 78-01 and LER-79-01)
'the majority of reactor trip cha]}enge-were not acco=panied by automatic safety injectien system challenges.
Inadvertent reactor trips were encountered core frequenti:. during the early phases of operatien. Approxicately 50T; of all reactor trips occurred during cur first la conths of operation (October,1974 through December, 1975).
Upgrading and.wdifying specific systems have aided in tininizing inadver:ent reactor trips.
The sane review indicated that there was no indication that a subst:ntial r.unber of the trips ere caused by surveillance testin;.
Some of the trips occurred during ini:ial syste= testing (T?'s) and seme la:er ones occurred during the performance of Special Test Procedures (ST7's).
- However, trips which occurred due to ecuipment talfunction er o:hcr operatienal events (naintenance activities, d? sign changes, etc.) constitute a gr2ater percentage of the total number of trips than these as a direct result of testing.
The District does not cencur that there is an apparen: sense of conplacency toward surveillance require ents which have tne,.ctential of causing inadvertent reactor SCRAMS at the Ranche Seco facility.
Follouing all reactor trips, plant personnel investigate and analyze the trip and prerare a repert. This report is then reviewed bv the Plan: ?.c'. lev Ce==i t t e e.
Major parancters at.d systen(s) respcases du.ing the transient are reviewed.
Rece ten-daticas crucerning petcntial design or precedure changes to prevent tecurrence are often discua8ed in these reperts.
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Hr. Darrell C. Eisenhut Page 2 September 2S, 1979 It is the District's contention that the facility's st5ff analysis of each reactor trip is sufficient to detect any procedural inadequacies which have the parential of i= posing unnecessary challenges to the reactor trip and safe-guards system.
To assure review by plant supervisors, a copy of your letter and this response vill be routed to the appropriate group supervisors at our facility.
Respectfully, J. J. Mattizoe Assistant General Manager' and Chief Engineer JJM:IIH:j i=
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