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
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2420 W. 26t Avenue, Suite 100D, Denver, Colorado 80211 company of colorado July 1, 1986 Fort St. Vrain Unit No. 1 P-86441 Director of Nuclear Reactor Regula' tion U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attn: Mr. H.N. Berkow, Director Standardization and Special Projects Directorate Docket No. 50-267
SUBJECT:
Emergency Diesel Generator Control Circuitry Modifications
Dear Mr. Berkow:
Public Service Company of Colorado (PSC) hereby submits a summary and schedule of modifications to be performed on Fort St. Vrain (FSV) emergency diesel generator (EDG) control circuitry.
These modifications are in. response to telephone conversations on May 15, 1986 and May 21, 1986 with your office relative to your review of the FSV EDGs.
The specific concerns brought to the attention of PSC during the subject telecons was the effect of failure of DEV-86 RT and 86 GT1 on EDG operation.
The subsequent discussion concluded with the agreement that the contacts associated with these two devices which are presently part of the EDG control scheme would be removed.
This modification will be completed prior to FSV start-up at the end of the current EQ outage.
In addition, a review of the FSAR has been made and the results indicate that there are several instances where the action resulting from the actuation of these delays is described.
Because of the timing requirements and constraints on the present FSAR update, these references will be deleted in the next update (Revision 5).
8607080215 860701 pk PDR ADOCK 05000267 P
PDR
P-86441 Page 2 July 1, 1986 Should you have any questions on this matter, please contact Mr. M.H. Holmes at (303) 480-6960.
Very truly yours, D. W. Warembourg, Manager Nuclear Engineering Division DWW/MP:pa I
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