Letter Sequence Other |
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Results
Other: ML20195C233, ML20209G130, ML20209G166, ML20209G183, ML20209G226, ML20209G235, ML20212H039, ML20236G894, ML20236G900, ML20236G904, ML20236N590
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MONTHYEARML20132E6891985-07-16016 July 1985
Requests Addl Info Re SPDS Display Format,Operator Tasks to Acquire Display Format,Display Sys for Each Critical Safety Function,All Variables for Function Selected & Control Room Diagram Locating Display Sys within 45 Days
Project stage: Other
ML20134M2461985-08-30030 August 1985
Responds to 850716 Request for Addl Info Re Spds.Explanation of Layout of Control Room & Relative Locations of SPDS Crts, SPDS Controls,Digital Radiation Monitoring Sys & Further Definition of Display Format Encl
Project stage: Request
ML20141J1741986-04-0707 April 1986
SER Re Spds.Sys Insufficiently Human Factored to Allow User to Rapidly & Reliably Evaluate All Critical Safety Functions Required by NRC
Project stage: Other
ML20141J1691986-04-0707 April 1986
Forwards SER Re Spds.Sys Does Not Incorporate Human Factors Considerations Into Design & Does Not Permit User to Rapidly & Reliably Evaluate Critical Safety Function.Schedule for Response to Concerns Requested
Project stage: Other
ML20195C2331986-05-21021 May 1986
Informs That Revised SPDS Design Will Be Submitted by 861231,per 860407 Ser.Design Currently Under Review to Remove Human Engineering Discrepancies within Sys & Change Displays
Project stage: Other
ML20210G2431986-09-15015 September 1986
Forwards Audit Plan for Safety Evaluation of Facility Action Plan for Performance Improvement of Control Room Design & Spds.Audit Should Be Conducted in Early Oct to Preclude Impact on Proposed Restart Date
Project stage: Approval
ML20209G2261986-12-0505 December 1986
Rev 1 to Final Rept,Qualification Test of Isolation Device for SPDS Multiplexers Rancho Seco Nuclear Generating Station
Project stage: Other
ML20209G2351986-12-30030 December 1986
Preliminary Results of Central Control Unit Isolation Devices Test,Rancho Seco Plant
Project stage: Other
ML20209G1661986-12-31031 December 1986
SPDS Safety Analysis for Rancho Seco Nuclear Generating Station Unit 1
Project stage: Other
ML20209G1831986-12-31031 December 1986
Rev 1 to Availability Evaluation for SPDS at Rancho Seco Plant
Project stage: Other
ML20209G1301987-01-12012 January 1987
Forwards Listed Documentation,Including 47-1139815-01, SPDS Safety Analysis for Rancho Seco Nuclear Generating Station Unit 1 & Rev 1 to BAW-1753, Availability Evaluation for Spds..., Per NRC Request Re
Project stage: Other
ML20212H0391987-01-12012 January 1987
Responds to Questions Discussed During 861216 Telcon Re SPDS & Main Feedwater (MFW) Indication in Control Room.Util Will Revise Action Plan,Section 4B.19 Re MFW Pump Trips
Project stage: Other
ML20212N3381987-01-14014 January 1987
Forwards Audit Plan for 870210-12 Safety Evaluation of SPDS in Lynchburg,Va
Project stage: Approval
ML20206S2681987-04-17017 April 1987
Forwards Description of SPDS Isolation Methodology Based on Discussion at 870407 Meeting.Method Will Provide Isolation When Exposed to Max Credible Fault.One Oversize Drawing Encl
Project stage: Meeting
ML20236G9041987-07-24024 July 1987
Rev 0 to Test of Ccu/Csu Interface Devices for Data Acquisition Sys (Anatec)
Project stage: Other
ML20236G9001987-07-24024 July 1987
Rev 0 to Test of Isolation Devices for Data Acquisition Sys (Anatec)
Project stage: Other
ML20236G8941987-07-24024 July 1987
Forwards Evaluations of Preliminary Test Results of SPDS Isolation Devices,Including Isolators 4,5,8,9 & 10
Project stage: Other
ML20236N5901987-11-0909 November 1987
Discusses SPDS Safety Evaluation Issues Re Fire Protection, Software Validation & Verification & Electrical Isolation. Listing of Status of Each Issue & Comparison of Nonlinear Data Points in Final Acceptance Test Encl
Project stage: Other
1986-05-21
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i SACRAMENTO MUNICIPAL UTILITY DISTR'CT C P. O. Box 15830 Sacramento CA 95852-1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA JEW 86-022 May 21,1986 DIRECTOR OF NUCLEAR REACTOR REGULATION ATTENTION FRANK J MIRAGLIA JR DIRECTOR PWR-B DIVISION U S NUCLEAR REGULATORY COMMISSION WASHINGTON DC 20555 DOCKET 50-312 RANCHO SECO NUCLEAR GENERATING STATION UNIT NO. 1 SAFETY PARAMETER DISPLAY SYSTEM
Reference:
John F. Stolz (NRC) to R. J. Rodriguez (SMUD) dated 4/7/86 The above reference contained an NRC Safety Evaluation Report (SER) on the Rancho Seco Safety Parameter Display System (SPDS).
The NRC developed the SER af ter a visit to Rancho Seco during June 19 - 21, 1985 by members of the Control Systems Branch.
The findings discussed in the SER include the need to improve the human factors engineering of the Rancho Seco SPDS. The improvement is aimed at allowing a "... user to rapidly and reliably evaluate all of the critical safety functions required by the NRC."
In order to accomplish the above, the District is currently reviewing the Rancho Seco SPDS design to remove human engineering discrepancies within the system. This review has already resulted in a rearrangement of the alphanumeric displays to present a more " structured" and useable display.
The District, in light of the NRC comments, is re-examining the displays and will make appropriate changes as necessary.
In addition to the alphanumeric review, the District is analyzing which radioactivity signals it will add to the SPDS displays.
The District, af ter completing the above reviews by July 31, 1986, will submit a revised SPDS design to the NRC by December 31, 1986. The District will then schedule the implementation of the modification in accordance with its Living Schedule process.
8605300178 860521 yDR ADOCK 05000312 PDR h
i go DISTRICT HEADQUARTERS O 6201 S Street. Sacramento CA 95817-1899
W Frank J Miraglia May 21,1986 If you have any questions, please contact Jerry Delezenski of my staff at (916) 452-3211, extension 4909.
.h J. E. WARD ASSISTANT GENERAL MANAGER, NUCLEAR