Letter Sequence Other |
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Results
Other: 05000267/LER-1986-022, :on 860715,failure Point in 480-volt Ac Essential Bus 1 & 2 Undervoltage Relay Logic Identified. Caused by Misunderstanding of Basic Design Requirements. Designer & Independent Reviewer Reprimanded, ML20134A365, ML20135H559, ML20135H563, ML20137B356, ML20137K999, ML20137S363, ML20140H110, ML20206T734, ML20207R947, ML20212G867
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MONTHYEARML20074A7561983-04-27027 April 1983
Clarifies Proposed Changes in Undervoltage Protection & Reiterates Schedule for Implementation of Design Changes & Mods.Existing non-Class IE Undervoltage Relays Will Be Retained as Protection for 4,160-volt Buses
Project stage: Request
ML20212N6621985-08-31031 August 1985
Technical Evaluation Rept for Proposed Change to Operation of Ginna Fuel Pool Charcoal Filter Sys, Informal Rept
Project stage: Request
ML20135H5631985-08-31031 August 1985
Truth-Analysis/Action-Reaction Review of 480-Volt Essential Bus Tie Breaker Control Scheme, Final Rept
Project stage: Other
ML20135H5591985-09-13013 September 1985
Forwards Truth-Analysis/Action-Reaction Review of 480-Volt Essential Bus Tie Breaker Control Scheme, Final Rept & Provides Evaluation of Control Logic Design
Project stage: Other
IR 05000267/19850171985-09-13013 September 1985
Insp Rept 50-267/85-17 on 850617-0816.Violation Noted: Failure to Rept Nine Circulator Trips in 1984 & Seven Trips in 1985 & No Differential Helium Pressure Maintained When Pcrv Pressure Above 100 Psia
Project stage: Request
ML20137S3631985-09-13013 September 1985
Corrected Page 1 to Responding to 850614 Commitment to Perform Evaluation of Emergency Diesel Generator Control Logic Circuitry.Ltr Number Changed
Project stage: Other
ML20134A3651985-10-23023 October 1985
Amends Correction Portion of Item 2 (286G1A & 286G1B) in Util Re Results of Proto-Power Corp Analysis Concerning Emergency Electrical Power Sys Independence
Project stage: Other
ML20137B3561986-01-0303 January 1986
Informs That Design Changes Involving Emergency Diesel Generator (EDG) Control Logic Circuitry Implemented.No Single Failure Will Interfere W/Proper Operation of Redundant EDG
Project stage: Other
ML20137K9991986-01-14014 January 1986
Notifies That Design Changes in Emergency Diesel Generator Control Logic Circuitry Implemented,Per 850913 Commitment. Changes Assure That Failure Will Not Interfere W/Operation of Redundant Generator.Ltr Supersedes
Project stage: Other
ML20140H1101986-03-31031 March 1986
Submits Info Re Startup Check List for Automatic Operation of Emergency Diesel Generators,Sys Operating Procedure 92-04,in Response to NRC .Numbers Will Be Assigned to All Valves in Emergency Diesel Generator Rooms
Project stage: Other
ML17251A7911986-03-31031 March 1986
Reactor Containment Bldg Integrated Leakage Rate Test
Project stage: Request
ML20206T7341986-07-0101 July 1986
Submits Summary & Schedule of Mods to Be Performed on Emergency Diesel Generator Control Circuitry in Response to 860515 & 21 Telcons.Mods Will Be Completed Prior to Startup from Current Equipment Qualification Outage
Project stage: Other
ML20213G5811986-08-0707 August 1986
Draft Review of Fort St Vrain Onsite AC Standby Power Sys W/Regards to Compliance to Single Failure Criterion & Ser
Project stage: Draft Other
05000267/LER-1986-022, :on 860715,failure Point in 480-volt Ac Essential Bus 1 & 2 Undervoltage Relay Logic Identified. Caused by Misunderstanding of Basic Design Requirements. Designer & Independent Reviewer Reprimanded1986-08-14014 August 1986
- on 860715,failure Point in 480-volt Ac Essential Bus 1 & 2 Undervoltage Relay Logic Identified. Caused by Misunderstanding of Basic Design Requirements. Designer & Independent Reviewer Reprimanded
Project stage: Other
ML20213G5641986-11-12012 November 1986
Forwards Onsite Class 1E Power Sys Design Features Review Status Rept Based on FSAR & NRC 860814 Meeting W/Licensee & Inel Draft Review of Fort St Vrain Onsite AC Standby Power.... Resolution to Problems Requested Before Restart
ML20212D8641986-12-24024 December 1986
Summary of 861209 Meeting W/Util Re Plant Emergency Electrical Power Sys.Fsar Commitment Re Emergency Diesel Generators revised.Marked-up Draft Rept Re Ac Standby Power Sys Encl
ML20212G8671987-01-0909 January 1987
Forwards Rev a to EE-92-0008, Engineering Evaluation of Load Shedding,Load Auto Start Prohibit,Load Sequencing,Bus Tie Breaker Alignment & Generator Breaker Closing Portions of Emergency Diesel Generator Control Circuitry
Project stage: Other
ML20207R9471987-03-0606 March 1987
Rev 1 to Review of Fort St Vrain Onsite AC `Standby Power Sys Re Compliance to Single Failure Criterion & Ser
Project stage: Other
ML20207R9381987-03-0606 March 1987
Forwards Rev 1 to EGG-NTA-7456, Review of Fort St Vrain Onsite AC `Standby Power Sys Re Compliance to Single Failure Criterion & Ser
Project stage: Approval
ML20207S6271987-03-12012 March 1987
Summary of 870210 Meeting W/Util Re Emergency Diesel Generator Electrical Independence.List of Attendees Encl
Project stage: Meeting
1986-12-24
[Table View] |
Text
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Public Service ~
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2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 January 14, 1986 Fort St. Vrain Unit No. 1 P-86015 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission Washington, DC 20555 Attn: Mr. H.N. Berkow, Project Director Standardization and Special Projects Directorate Docket No. 50-267
SUBJECT:
Emergency Electrical Power System Independence
REFERENCES:
- 1) PSC Letter Warembourg to Jchnson dated June 14, 1985 (P-85208)
- 2) NRC Letter Johnson to Lee dated July 10, 1985 (G-85268)
- 3) PSC Letter Warembourg to Hunter dated September 13, 1985 (P-85313)
- 4) PSC Letter Warembourg to Berkow dated December 17, 1985 (P-85475)
Dear Mr. Berkow:
Please void from your files the Public Service Company letter Warembourg to Berkow dated January 3, 1985 our number P-86003.
This letter shall supersede the orignal letter which was inadvertently dated 1985.
In a letter dated September 13, 1985 (Reference 3), Public Service Company (PSC) committed to the implementation of design changes
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involving the Emergency Diesel Generator (EDG) control logic
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circuitry.
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The aforementioned design changes have been implemented and will
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assure that no single failure will interfere with the proper operation of a redundant EDG.
1 Should you have any questions regarding this matter, please contact Mr. M. H. Holmes at (303) 480-6960.
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Very truly yours, b
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D.W. Warembourg, ger Nuclear Engineering Division DWW/BS:pa I
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