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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20155D4801998-10-27027 October 1998 Amend 3 to Rancho Seco DSAR, Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode ML20217D3271997-07-30030 July 1997 Update of 1995 Decommissioning Evaluation for Rancho Seco Nuclear Generating Station ML20137W8151997-03-20020 March 1997 Amend 1 to Post Shutdown Decommissioning Activities Rept ML20217A5711990-08-28028 August 1990 Final Engineering Rept,Assessment of Spent Fuel Pool Liner Leakage ML20058B6521990-05-0404 May 1990 Rev 0 to ERPT-M0216, Property Loss Study for Rancho Seco Nuclear Generating Station in Long Term Defueled Mode ML20246F6301989-02-28028 February 1989 Auxiliary Feedwater Sys Overpressurization Event Engineering Evaluation Rept,Feb 1989 ML20154K8571988-08-24024 August 1988 Evaluation of Double Steam Line Break at Rancho Seco ML20151U4851988-07-31031 July 1988 Power Ascension Mid-Term Assessment of Plant Operations & Maint & Scheduling Activities ML20154M7381988-05-31031 May 1988 Assessment of Control Room Habitability Given Postulated Onsite Release of 20 Weight Percent Aqueous Ammonia ML20147E5361988-03-0707 March 1988 Control Room/Technical Support Ctr Habitability Study, Aqueous Ammonia Concentrations ML20147C3751988-03-0101 March 1988 Procurement Engineering Assessment Plan,Interim Rept ML20147E5201988-02-29029 February 1988 Control Room/Technical Support Ctr Habitability Study, Radiological Dose Assessment ML20147E4991988-02-29029 February 1988 Methodology for Revised Control Room X/Q Determination for Rancho Seco Nuclear Station ML20151U0241988-02-29029 February 1988 Rev 5 to Final Wire & Cable Program Rept for Rancho Seco Nuclear Generating Station ML20148C7641988-02-24024 February 1988 Rev 1 to Future Plant Capacity Factor Engineering Assessment ML20147G4881988-02-11011 February 1988 Preliminary Rept Rancho Seco Piping Vibration Tdi Diesels a & B ML20196E6971988-02-0505 February 1988 Rev 3 to Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75 ML20148G2861988-01-31031 January 1988 Radioactive Liquid Effluent Sys Evaluation Using Program Liquid Effluent Based Operating Guides Rev II ML20149D3981988-01-19019 January 1988 Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings, Final Rept ML20148T1551987-12-31031 December 1987 Rev 4 to Wire & Cable Program Rept ML20147D3401987-12-31031 December 1987 Proposed Alarm Sys Mods NFPA 72D Compliance ML20234D8161987-12-0404 December 1987 Rev 0 to Resolution of Audit Findings Pertaining to Fire Pumps ML20237B2791987-12-0101 December 1987 Rev 2 to Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75 ML20236U1321987-11-17017 November 1987 Review of Smud Emergency Operating Procedures ML20236B0101987-10-12012 October 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Nuclear Svcs Electrical Bldg Essential & Normal HVAC Sys ML20236B0051987-10-0707 October 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Component Cooling Water (CCW) & Turbine Plant Cooling Water (Tcw) Sys ML20236B0021987-10-0707 October 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Auxiliary Feedwater Sys ML20236A9981987-10-0707 October 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of 480-Volt AC Distribution Sys ML20236A9921987-10-0707 October 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Rcs ML20236A9891987-10-0707 October 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Safety Features Actuation Sys ML20235V7951987-09-30030 September 1987 Response to NRC Questions on Geologic & Seismologic Conditions. W/Five Oversize Drawings Encl ML20235Y8891987-09-28028 September 1987 Rev 0 to Rept on Response to NRC IE Circular 79-02, Engineering Rept ML20235Q7301987-09-15015 September 1987 Pressurizer Heater Incident,Task 852 ML20239A0301987-09-0303 September 1987 Twelve Sys Assessment of Expanded Augmented Sys Review & Test Program Rept ML20239A1071987-08-31031 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Radiation Monitoring Sys Sys ML20235Y6651987-08-31031 August 1987 Rereview of Plant Instrumentation & Control for IE Bulletin 79-27 ML20239A1041987-08-27027 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Seal Injection & Makeup Sys ML20239A0891987-08-27027 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Non-Nuclear Instrumentation Sys ML20239A0841987-08-27027 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Nuclear Svc Cooling Water Sys ML20239A0821987-08-27027 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of 120 Volt AC Vital Power Sys Sys ML20239A0751987-08-27027 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Main Feedwater Sys ML20239A0661987-08-18018 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Main Steam Sys ML20239A0531987-08-18018 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Nuclear Raw Water Sys ML20239A0461987-08-18018 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Emergency Diesel Generator Sys ML20239A0431987-08-18018 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Control Room/Technical Support Ctr Essential Hvac ML20239A0381987-08-18018 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of DHR Sys ML20239A0341987-08-18018 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Integrated Control Sys ML20237J4241987-08-0505 August 1987 Evaluation of Integrated Control Sys ML20237J3871987-08-0404 August 1987 Evaluation of DHR Sys ML20237J3841987-08-0404 August 1987 Evaluation of Control Room/Technical Support Ctr Essential HVAC Sys 1998-10-27
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20211H7921999-08-13013 August 1999 Safety Evaluation Supporting Amend 126 to License DPR-54 ML20195D1901999-05-0606 May 1999 Annual Rept ML20195H8571998-12-31031 December 1998 1998 Annual Rept for Smud. with ML20155D4801998-10-27027 October 1998 Amend 3 to Rancho Seco DSAR, Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode ML20248C4301998-05-0606 May 1998 Annual Rept, Covering Period 970507-980506 ML20249A7831997-12-31031 December 1997 1997 Smud Annual Rept ML20198G8271997-08-22022 August 1997 Safety Evaluation Supporting Amend 125 to License DPR-54 ML20217D3271997-07-30030 July 1997 Update of 1995 Decommissioning Evaluation for Rancho Seco Nuclear Generating Station ML20140A6371997-05-0606 May 1997 Annual Rept, Covering Period 960507-970506 ML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20137W8151997-03-20020 March 1997 Amend 1 to Post Shutdown Decommissioning Activities Rept ML20141J2711996-12-31031 December 1996 Smud 1996 Annual Rept ML20138L1231996-11-13013 November 1996 Smud Rancho Seco Incremental Decommissioning Action Plan, Rev 0,961113 ML20129E7151996-10-14014 October 1996 Defueled SAR for Rancho Seco ML20059H6821994-01-17017 January 1994 Revised Rancho Seco Quality Manual ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20059K1981993-05-0606 May 1993 Annual Rept, Covering Period from 920501- 930506,consisting of Shutdown Statistics,Narrative Summary of Shutdown Experience & Tabulations of Facility Changes, Tests & Experiments,Per 10CFR50.59(b) ML20128C9641993-02-0202 February 1993 Informs Commission of Status of Open Issues & Progress of Specified Facilities Toward Decommissioning ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20126E6771992-08-0303 August 1992 Rev 7 to Rancho Seco Quality Manual NL-90-451, Monthly Operating Rept for Oct 1990 for Rancho Seco Nuclear Generating Station1990-10-31031 October 1990 Monthly Operating Rept for Oct 1990 for Rancho Seco Nuclear Generating Station ML17348B5061990-10-0909 October 1990 Part 21 Rept Re Zener Diode VR2 on Power Supply Board 9 1682 00 106 Possibly Being Installed Backwards ML20059G9621990-09-10010 September 1990 Safety Evaluation Supporting Amend 115 to License DPR-54 NL-90-443, Monthly Operating Rept for Aug 1990 for Rancho Seco1990-08-31031 August 1990 Monthly Operating Rept for Aug 1990 for Rancho Seco ML20217A5711990-08-28028 August 1990 Final Engineering Rept,Assessment of Spent Fuel Pool Liner Leakage NL-90-439, Monthly Operating Rept for Jul 1990 for Rancho Seco Nuclear Generating Station1990-07-31031 July 1990 Monthly Operating Rept for Jul 1990 for Rancho Seco Nuclear Generating Station ML20055F8591990-07-16016 July 1990 Special Rept 90-11:on 900613,06,25,18,21 & 28,fire Barriers Breached More than 7 Days & Not Made Operable in 14 Days. Corrective Actions:Operability of Fire Detectors Verified on One Side of Breached Barriers NL-90-423, Monthly Operating Rept for June 1990 for Rancho Seco Nuclear Generating Station1990-06-30030 June 1990 Monthly Operating Rept for June 1990 for Rancho Seco Nuclear Generating Station ML20055C6301990-05-21021 May 1990 Special Rept 90-09:on 900424,25,30,31 & 0502,fire Barriers Inoperable for More than 7 Days,Per Tech Spec 3.14.6.2 Requirement.Hourly Fire Watches Established & Penetrations & Doors Returned to Operable Status ML20055C6291990-05-21021 May 1990 Special Rept 90-08:on 900419,fire Pump Batteries Inoperable When Surveillance Procedure SP.206 Not Performed by Due Date.Caused by Test Frequency Incorrectly Changed from Weekly to Monthly.Surveillance Schedule Revised ML20058B6521990-05-0404 May 1990 Rev 0 to ERPT-M0216, Property Loss Study for Rancho Seco Nuclear Generating Station in Long Term Defueled Mode ML20248E0121989-09-13013 September 1989 Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating NL-89-634, Monthly Operating Rept for Aug 1989 for Rancho Seco Nuclear Generating Station1989-08-31031 August 1989 Monthly Operating Rept for Aug 1989 for Rancho Seco Nuclear Generating Station NL-89-598, Monthly Operating Rept for Jul 1989 for Rancho Seco Nuclear Generating Station1989-07-31031 July 1989 Monthly Operating Rept for Jul 1989 for Rancho Seco Nuclear Generating Station ML20247B3611989-07-17017 July 1989 Safety Evaluation Supporting Amend 112 to License DPR-54 NL-89-556, Monthly Operating Rept for June 1989 for Rancho Seco Nuclear Station1989-06-30030 June 1989 Monthly Operating Rept for June 1989 for Rancho Seco Nuclear Station ML20245E1161989-06-20020 June 1989 Safety Evaluation Supporting Amend 111 to License DPR-54 ML20245B6651989-06-15015 June 1989 Part 21 Rept 150 Re Potential Defect in Component of Dsr Standby Diesel Generator.Cause of Failure Determined to Be Combination of Insufficient Lubrication to Bushings.Listed Course of Action Recommended at Next Scheduled Engine Maint ML20245A1991989-06-0909 June 1989 Safety Evaluation Supporting Amend 110 to License DPR-54 ML20248B9361989-06-0505 June 1989 Safety Evaluation Supporting Amend 107 to License DPR-54 ML20248B6321989-06-0505 June 1989 Safety Evaluation Supporting Amend 108 to License DPR-54 ML20248B9621989-06-0505 June 1989 Safety Evaluation Supporting Amend 109 to License DPR-54 NL-89-517, Monthly Operating Rept for May 1989 for Rancho Seco Nuclear Generating Station1989-05-31031 May 1989 Monthly Operating Rept for May 1989 for Rancho Seco Nuclear Generating Station ML20247P1761989-05-30030 May 1989 Safety Evaluation Accepting Generic Ltr 83-28,Item 4.5.2 Re on-line Testing of Reactor Trip Sys ML20247N7491989-05-30030 May 1989 Special Rept 89-13:on 890328-29,specific Activity of Primary Sys Exceeded Limits in Administrative Procedure & Chemistry Control Commitment.Possibly Caused by Power Reduction.Isotopic Analysis Continued ML20247K7261989-05-23023 May 1989 Safety Evaluation Supporting Amend 105 to License DPR-54 1999-08-13
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RANCHO SECO ACTION PLAN FOR RESTART' REPORT FOR THE MONTH OF NARCH, 1987 l
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Prepared By:
J. E. WARD DEPUTY GENERAL MANAGER, NUCl. EAR APRIL.20, 1987 8705070034 870424 PDR ADOCK 05000312 R PDR
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ACTION PLAN NONTHLY PROGRESS REPORT CONTENTS I. Highlights II. Introduction III. Action Plan Progress
.1 Changes and Revisions to the Action Plan
.2 New Issues Affecting Restart
.3 Closure of Issues
.4 Systematic Assessment Program
.5 Manacement, Operations, and Administration
.6 Plant Modifications and Maintenance Improvements
.7 Systems Review and Testing Program
.8 Non-Action Plan Related Activities
.9 Resource Commitments and Utilization
.10 Schedule l
i
f, :
i I. HIGHLIGHTS In March plans were drawn to evolve the Action plan from a Restart l list into a historical document. Managers and System Engineers began to prepare submissions reflecting completion of Specific Action Items. Amendment 4 will compile these and thus begin to indicate what was actually done for restart. The perspective is changing. i l
- The new TOI diesels passed their 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> run tests and began their "35 consecutive starts" test. This project is ahead of i
schedule, j
- Testing began on the Emergency Feedwater In*tiation and Control l system (EFIC). A portable simulator was connected to dynamically i test the various panels and cabincts. l
- A total of 31 new NRC "Open Items" (specific action items identified during NRC inspections) were added in March. Of the 433 identified items only 140 remained open on March 31.
- Efforts continued to resolve the entire cable raceway issue.
As-a conservative measure, 243 cables are being " walked down" to determine whether they are physically located as designed; 234 such inspections have been completed. Only 11 minor discrepancies were discovered so far. This issue is expected ,
to be resolved in April.
- A very significant milestone was reached as the Decay Heat "A" system outage was begun. This event culminated a sequence of .
prerequisites which in their aggregate indicate major progress in mechanical and electrical readiness to restart.
- The weld filler certification issue was investigated and resolved in March.
- A complete review is being conducted of all Restart calculations. This was 80% complete by the end of March
- Phase 2 of the Foothill Fault study was authorized and the contract was let to Bechtel. '
- Stone & Webster conducted their annual Emergency Preparedness audit in March. Their finding was "a tremendous improvement".
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I. HIGHLIGHT 3 (Continued) e Resource Commitment With the progress made on refining task scope and program details, a Restart Budget for 1987 was provided to the Board.
Approval was received in December. Site staffing levels have been dropped 10%. Staffing and expense trends are consistent with budget estimates. Efforts are being expanded to identify all permanent managers before April 30. The new AGMs and a temporary Licensing Manager have been named.
Schedule Restart of the reactor is planned. in July with power operation beginning in September. Physics testing will precede power operation. Some tests at power will be conducted in August.
SUMMARY
Restart efforts are progressing as detailed within the Action Plan.
Progress is being made and activity is apparent everywhere at Rancho Seco. The NRC, and other industry agencies, are working closely with us to insure that our commitments meet their needs and will support a safe and timely restart.
II. INTRODUCTION This report highlights the progress in implementing the " Action Plan for Performance Improvement" at the Rancho Seco Nuclear Generating Station. The Action Plan was submitted to the NRC on July 3,1986 Amendment 2 on December 15, 1986 and Amendment 3 on February 28, 1987. This report covers the month of March, 1987.
III. ACTION PLAN PROGRESS
- 1. Changes and Revision to the Action Plan The expanded System Review and Test Program (SRTP) is now functioning with assigned Systems Engineers for each system.
The SRTP consolidates the input from the Plant Performance and Management Improvement Program (PP&MIP) with the system revi.ews performed by the Systems Engineer and develops a systems testing program to demonstrate plant material readiness.
The Action Plan is being used as a source document or " Subset" of a comprehensive Restart List being assembled by Implementation. This document will be transmitted to NRC as requested.
l t
P III. ACTION PLAN PROGRESS (Continued)
- 2. New Issues Affecting Restart Weekly program reports are prepared by the DGM, Nuclear and submitted to a broad distribution including the District's General Manager. New issues which could impact the restart are identified in those reports and are summarized below.
The two Decay Heat systems are being shut down and repaired sequentially. The "B" system repair cannot start before "A" system is restored to operation. Resolution of discrepancies of unknown extent place these vital systems in the most likely position of delaying restart or being on the " Critical Path".
Although diminishing in potential, the issue of the.
reliability of electrical power and control cables to be actually installed according to the Appendix "R" separation criteria of the Code of Federal Regulations, continues to require investment of resources. The discovered problems have been minimal, feeding optimism that this issue will not delay' restart. A total of 243 cables are being " walked down" to resolve this issue. To date, only 11 minor problems have surfaced out of 234 completed inspections.
The reliability of 173 critically important motor operated (MOVs) valves continues to be an important issue. These valves are all operated at an attached motor which is actuated either automatically or by an operator from a remote control station. To comply with Technical Specifications, all MOVs must be functional prior to Restart; thus far 66 valves have successfully passed overthrust testing.
- 3. Closure of Issues The QCI-12 process will eventually document the successful development of closure packages. Amendment 4 to the Action Plan will indicate the completed actions which have been submitted by the representative manager or system engineer to Quality.
- 4. Systematic Assessment Program This program provides the input to the QCI-12 " Plant Performance and Management Improvement Program" (PP&MIP). The program is essentially complete, as shown in the following discussion of each input area.
III. ACTION PLAN PROGRESS (Continued)
- a. December 26. 1985 Event Analysis 1 A total of 150 analyses, studies, repairs, and modifications were initiated to investigate and recover from the overcooling event. These resulted in approximately 400 recommendations, which have been identified in the Action Plan by the respective managers and system engineers for closure.
- b. Precursor Review A total of 1396 documents, applicable to Rancho Seco, have been reviewed to determine the appropriateness of previous reviews and implementing actions. These also are reflected in management and system-related work lists enumerated in of the Action Plan.
- c. Deterministic Failure Consecuence Analysis This portion of the program generated a series of Action Plan items which will be closed before Restart. These analyses documented the effect of component failure on system operation, as well as the synergistic effects upon other systems. A total of 1232 recommendations resulted from this analysis program.
- d. Personnel Interviews Interviews with plant personnel resulted in 1631 recommendations and generated actions to be completed prior to restart.
- e. BWOG The program inputs thus far total 76 recommendations of an expected 150 to 200. The remaining inputs will be evaluated according to our QCI-12 process in the near future when officially received.
- 5. Management. ODerations and Administration
- a. Changes in Supervisory and Management Staff:
Efforts are continuing to identify permanent SMUD management individuals for every key position. Both NRC and SMUD realize the importance of employing these managers prior to Restart so that they may function as a cohesive team before the contractor managers depart. Interviews for all the remaining contractor-filled positions will be conducted in April and May, 1987. At this time George Coward and Joe Ferlit have been named permanent SMUD
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III. ACTION PLAN PROGRESS (Continued)
Assistant General Managers. Ray Ashley has been replaced by John Vinquist as Manager of Nuclear Licensing. Mr.
Vinquist will act as Licensing Manager until the perm.1nent SMUD manager is named, which is expected to occur in April.
- b. Changes in Organizational Structure:
Efforts are in full stride to implement the " Ultimate" or target nuclear organization by staffing of all nuclear management positions with SMUD people.
- c. The Systems Review and Test Program (STRP):
Total staffing for this organization is 110 people. All positions, including all key positions have been filled.
Recent indications are that the NRC is increasingly concerned with the slow progress of the test program.
Strong corrective action is being initiated to expedite this vital task.
- 6. Plant Modifications and Maintenance Improvements Section 4C of the Action Plan details the modifications and maintenance required for restart. Actual work is underway on most of the identified projects.
- 7. Systems Review and Test Program This program is described in Section 40 of the Action Plan and is rapidly becoming the comprehensive effort envisioned in the Plan. As noted above, the program is now 100% staffed.
Implementation of the programmatic structure.has been initiated.
In addition, the detailed system review documents are completed.
Detailed test procedures are being developed; approximately 41%
are complete.
- 8. Non-Action Plan Related Activities l
l The Foothills Fault is being investigated for its possible influence on Rancho Seco seismic design criteria. We do not expect that this study will result in any impact upon the plant design bases. The second phase contract has been let to Bechtel Corporation to perform additional trenching.
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III. ACTION PLAN PROGRESS (Continued)
- 9. Resource Commitments and Utilization As.a part of the expansion necessary to support the Action Plan,. implementation programs have'been strengthened or put in place to provide improved management information and. control of.
activities and resources. These efforts allow for the budgeting and allocation of resources, where necessary, to accomplish the commitments of the Action Plan. The major elements are:
- a. Personnel and Staffing During the month of March, 1987, the total staff assigned to the Nuclear Organization decreased by about 10%. On April 1, 1987, there were 896 SMUD employees and 1578 consultant /other contractors assigned to the nuclear organization with a small number of SMUD and consultant personnel assigned to various locations other than Rancho Seco.
Approximate overtime utilization of the staff during the month of March as a percentage of straight time hours worked is as follows:
SMUD 18%
Craft Labor 15%
Consultants /0ther Contractors 18%
(located at Rancho Seco and submitting site timesheets)
As of April 1, 1987, a total of 2,474 people were directly supporting Rancho Seco and the restart effort. _On a typical day-shift, approximately 2,000 people are physically present within the security fence. This has required staggering of working schedules and has created an office space shortage requiring utilization of over SC temporary trailers.
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.10. Schedule At present we expect the. plant to be producing power in'the third quarter 1987. There exists potential for delay due to:
-a. Decay Heat System repairs
- b. Cable. routing problems
- c. Failures during system tests
- d. Delays in the regulatory process
- e. MOV problems l
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