Letter Sequence Other |
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Results
Other: ML20195C233, ML20209G130, ML20209G166, ML20209G183, ML20209G226, ML20209G235, ML20212H039, ML20236G894, ML20236G900, ML20236G904, ML20236N590
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MONTHYEARML20137L9151986-01-20020 January 1986
Comments on 851028 Commission Policy Statement on Engineering Expertise on Shift,Per NUREG-0737,Item I.A.1.1 Re Shift Technical Advisor.Util Pleased W/Incorporation of Technical Advisor Position in Operating Staff
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
ML20198K8801986-05-30030 May 1986
Forwards Smud Action Plan for Performance Improvement at Rancho Seco Nuclear Generating Station. Plan Provides Preliminary Results of Util Mgt Review of Implications of 851226 Overcooling Incident.Formal Plan Expected by 860703
Project stage: Other
ML20198K8991986-06-0202 June 1986
Smud Action Plan for Performance Improvement at Rancho Seco Nuclear Generating Station
Project stage: Other
ML20206H3941986-06-20020 June 1986
Summarizes NRC Concerns Expressed at 860610 Meeting Re Preliminary Version of Action Plan for Performance Improvement at Plant.Formal Plan Scheduled for Submittal on or About 860701 Should Resolve Listed Concerns
Project stage: Meeting
ML20203E9221986-06-30030 June 1986
Forwards Rev 4 to Updated FSAR for Prairie Island Nuclear Generating Plant.Two New Vols Provided for Reprinting of Apps of Original FSAR
Project stage: Other
ML20206T8691986-07-0303 July 1986
Forwards Action Plan for Performance Improvement. Plan Addresses 851226 Event & Includes Prioritization Process Which Identifies Actions That Will Be Completed Before Restart.Review Requested
Project stage: Other
ML20202G0431986-07-0303 July 1986
Discusses Systematic Assessment Program Portion of Performance Improvement Program,Per 860617 & 18 Discussions. Little Progress Made to Define & Implement Meaningful Sys Review & Test Program.Review of Program Suggested
Project stage: Approval
ML20204E5811986-07-17017 July 1986
Rev 1 to Instruction QCI-12, Plant Performance & Mgt Improvement Program
Project stage: Other
ML20204E5741986-07-21021 July 1986
Forwards Rev 1 to Instruction QCI-12, Plant Performance & Mgt Improvement Program, Per 860717 Meeting Request
Project stage: Meeting
ML20204C4931986-07-23023 July 1986
Responds to Retrospective Part of Issue 2a Re Completeness of Staff & Licensee Actions Associated W/Control Sys,Per Stello 860313 Memo to Denton in Response to Investigation of 851226 Incident.Issue 2a Closed
Project stage: Other
05000312/LER-1986-011, :on 860424,during Visual Insps of Internal Wiring Terminations,Seven Internal Compression Terminations Failed.Caused by Loose Conductor/Lug Assemblies in Bailey Cabinets.Maint Stds & Insp Plan Developed1986-07-23023 July 1986
- on 860424,during Visual Insps of Internal Wiring Terminations,Seven Internal Compression Terminations Failed.Caused by Loose Conductor/Lug Assemblies in Bailey Cabinets.Maint Stds & Insp Plan Developed
Project stage: Other
ML20212E9511986-07-29029 July 1986
Forwards General Comments on Util 860703 Action Plan for Performance Improvement.Prior to Scheduled 860814 Working Meeting W/Util,Staff Will Provide Addl Comments to Be Addressed in Meeting Agenda
Project stage: Meeting
ML20214N8311986-09-0505 September 1986
Forwards Request for Addl Info Re Util Action Plan for Performance Improvement & Preliminary List of Issues to Be Resolved in Electrical,Instrumentation & Control Portion of Proposed SER
Project stage: RAI
ML20210K8421986-09-12012 September 1986
Rev 1 to Design Basis Rept
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
ML20210G0031986-09-15015 September 1986
Forwards Amend 1 to Action Plan for Performance Improvement. Util Determined Installation of Emergency Feedwater Initiation & Control Sys Prior to Restart Feasible
Project stage: Other
NL-86-672, Forwards Rev 1 to A-5415, Design Basis Rept, as Requested. Review of Current Emergency Feedwater Initiation & Control Sys Design Should Address Inconsistencies w/1983 SER Not Technical Adequacy1986-09-26026 September 1986
Forwards Rev 1 to A-5415, Design Basis Rept, as Requested. Review of Current Emergency Feedwater Initiation & Control Sys Design Should Address Inconsistencies w/1983 SER Not Technical Adequacy
Project stage: Other
ML20215K6031986-10-16016 October 1986
Submits Results of Survey on Engineering Expertise on Shift. Findings of Survey Include That Plants Utilize Shift Technical Advisors That Are on-call & That Differences from Commission Policy Statement Handled on case-specific Basis
Project stage: Other
ML20213F6951986-11-0606 November 1986
Forwards non-nuclear Instrumentation & Instrumentation & Control Sys Schematics & Piping & Instrument Drawings,In Response to NRC 860530 Request
Project stage: Other
ML20213F0381986-11-0707 November 1986
Advises of Revised Schedule for Completion of NUREG-0737, Item III.D.3.4 Re Control Room Habitability.Provisions to Complete Item III.D.3.4 Will Be Implemented Prior to Startup from Current Outage Anticipated in Early May 1987
Project stage: Other
ML20211M4641986-12-0303 December 1986
Advises of Actions Taken in Response to Recent Burnout of Pressurizer Heater Bundle.Sessions Scheduled at Lynchburg Simulator During Feb 1987 to Polish Operator Skills & Awareness,Per Performance Improvement Action Plan
Project stage: Other
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
ML20211P5981986-12-15015 December 1986
Forwards Amend 2 to Action Plan for Performance Improvement. Amend Identifies Specific Actions Required for Accomplishment Prior to or During Restart
Project stage: Other
ML20209G2351986-12-30030 December 1986
Preliminary Results of Central Control Unit Isolation Devices Test,Rancho Seco Plant
Project stage: Other
ML20209G1831986-12-31031 December 1986
Rev 1 to Availability Evaluation for SPDS at Rancho Seco Plant
Project stage: Other
ML20211P6121986-12-31031 December 1986
Amend 2 to Action Plan for Performance Improvement
Project stage: Other
ML20209G1661986-12-31031 December 1986
SPDS Safety Analysis for Rancho Seco Nuclear Generating Station Unit 1
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
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
ML20212N3381987-01-14014 January 1987
Forwards Audit Plan for 870210-12 Safety Evaluation of SPDS in Lynchburg,Va
Project stage: Approval
ML20207Q6041987-01-20020 January 1987
Advises of Future Plans to Take Reactor Out of Cold Shutdown & Proceed Through Heatup to Hot Shutdown Conditions,Based on Interpretation of 851226 Confirmatory Action Ltrs for pre-start Activities
Project stage: Other
ML20210F5391987-02-0303 February 1987
Confirms Telcon Re Arrangements for Evaluation of Requalification Program.Evaluation Visit Scheduled for Wk of 870504.Ref Matl Requirements for Program Evaluation & Requirements for Administration of Written Exams Encl
Project stage: Other
ML20213G4141987-02-26026 February 1987
Advises That All Steps Necessary to Ensure That Reorganizational Efforts Do Not Adversely Impact Restart Schedule Taken,Per 870205 Request
Project stage: Other
ML20207R0691987-03-0303 March 1987
Advises That Plans to Proceed W/Sys Testing Program & Precriticality Startup Program,Including Hot Shutdown, Consistent W/Confirmatory Action Ltrs for Prestartup Activities.W/O Rept
Project stage: Other
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
ML20214L0191987-05-13013 May 1987
Forwards Request for Addl Info on Section 3.2.4 of Facility Restart Rept Re Steam Generator Overfill & Flooding of Main Steam Headers to Complete Review
Project stage: RAI
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
NUREG-1286, Forwards SER Re Restart Following 851226 Event (NUREG-1286). Requests Response to 870814 Request for Addl Info to Resolve Restart Issues1987-10-0707 October 1987
Forwards SER Re Restart Following 851226 Event (NUREG-1286). Requests Response to 870814 Request for Addl Info to Resolve Restart Issues
Project stage: Approval
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
ML20055C2051988-02-12012 February 1988
Forwards Safety Evaluation Supporting Util 871223 & 880211 Submittals Re Proposed Amends to Tech Specs (PA 155,Rev 2) for Plant.Salp Input Also Encl
Project stage: Approval
1986-07-29
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'esuun SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S Street, P.O. Box 15830. Sacramento CA 95852 1830,1916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA JEW 86-1103 Ja nua ry 12, 1987 Director of Nuclear Reactor Regulation Attention: Fra nk J. Mi ra glia, J r.
Division of PWR Licensing-B U S Nuclear Regulatory Commission Washington D C 20555 Docket 50-312 Rancho Seco Nuclear Generating Station Unit #1 NRC REQUEST FOR INFORMATION ON SPDS AND MFW INDICATION
Dear Mr. Miraglia:
In a telephone conversation on 12/16/86, Mr. Syd Miner and Mr. Leo Beltracchi of your staff requested specific information concerning the Rancho Seco Safety Parameter Display Systen and Main Feedwater (MFW) indication in the Control Roan. The following documents the District's responses to those questions as discussed during the telecon:
What is the District's schedule to meet with the NRC staff at the B&W Lynchburg office to review two selected SPDS instrument strings fran sensor to display?
The District has arranged the meeting for February 10 to 12,1987 at B&W, Odd Fellows Road, Lynchburg Virginia. The District will also be prepared to discuss any questions the NRC staff may have concerning ti,
'listrict's previous sutnittal of Novenber 20, 1986 and anticipated subnittal of January 7,1987. Prior to the meeting in Lynchburg, the District understands Mr. Beltracchi will forward an Audit Plan to the District.
Can the District advance its schedule to perfonn a R. G.1.152 review of the Rancho Seco SPDS, and 'f so when?
The District will canplete its R. G.
52 review of the Rancho Seco SPDS in time for the District /NI eeti ng in Lynchburg.
How does the District indicate / label lure of MFW irdication in the Control Roam?
Annunciators in the Control Roan identify ICS power failure.
The MFW flw recorders have a purple label, located under the recoMers, identifying that the recorders are pwered by ICS.
8701210266 870112 I
dg PDR ADCCK 05000312
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P PDR
1 F. Mi raglia, Jr.
, Ja nua ry 12, 1987 JEW 86-1103 These recorders fail mid-scale on a loss of ICS. Redundant MFW flow indicators are located on the same console (H1R1) as the MFW flod recorders. These indicators are powered by NNI (orange label) ard will not be failed on loss of ICS power. However, they will fail on loss of NNI poder.
Emergency Operating Procedures (E0Ps) direct the operators upon a loss of NNI power to use the irdication independent of NNI power such as the SPDS and EFIC panel.
However, it is important to note, upon a loss of NNI ac or de power (x, y or z), the ICS de power is tripped which causes both MFW punps to be tripped, EFIC to actuate, and AFW to feed the OTSG's.
Therefore, MFW flow indication is not needed.
The ATOG Post Trip display on the SPDS provides the operator with infonnation reganling primary to secondary heat transfer, OTSG 1evel, ard pressurizer level.
This SPDS display provides a good overview of primary / secondary plant response to a transient.
Post Telecon:
In addition, the District reviewed Action Plan, Anendnent 1, Section 4B.19, and detennined that the section erroneously irdicated that MFW' punps runback to minimum speed on loss of ICS poder. The MFW punps are tripped on a loss of ICS ac or de power. As irdicated above, on loss of NNI ac or dc poder (x, y or z), the ICS de poder is tripped causing the MFW pumps to trip, EFIC/AFW to actuate and control 0TSG 1evel. This infonnation is correctly stated in the Restart Report submitted by the District to the NRC on 12/15/86.
The District will revise the Action Plan Section 4B.19 in Anen&nent 3 scheduled for issue on 2/28/87.
If you have any questions, contact Jerry Delezenski of my staff.
Sincer y,
-y o
. Wa rd eputy General Manager, Nuclear cc:
Syd Miner, NRC - Bethesda T. D' Angelo, NRC - Ra ncho Seco l
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