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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 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 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 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
[Table view] |
Text
l I
i RANCHO SECO ACTION PLAN FOR RESTART REPORT FOR THE MONTHS OF DECEMBER, 1986 AND JANUARY, 1987 l
Prepared By:
J. E. WARD DEPUTY GENERAL MANAGER, NUCLEAR l
FEBRUARY 18, 1987 l
h0 8703180515 870228 PDR ADOCK 05000312 PDR ll-
ACTION PLAN MONTHLY 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 Management, 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
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I. HIGHLIGHlS The months of December 1986 and January 1987 were significant in the course of implementing the Rancho Seco Action Plan. During this time, the majority of the programs detailed in the Action Plan were active and several major milestones were reached:
- On December 15, 1986, the Action Plan was updated with the issue of Amendment 2. This amendment specifically described :
the work which is to be accomplished prior to Restart. Each '
Manager listed his " Priority One" work. Each System Engineer enumerated the modifications, testing, training, and new procedures which were necessary to prepare his system for restart. It is regretted that the rush to complete and issue Amendment 2 resulted in poor quality control of the product.
This will be corrected.
- The new TOI diesels were installed and passed their 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> run tests. This project is ahead of schedule, thus removing this project from the " critical path".
- The pumps which add to and maintain Reactor Coolant System inventory for core cooling were restored to service and tested. These repairs were completed ahead of schedule.
- NRC "Open Items" (specific action items identified during NRC inspections) were attacked by an aggressive closure team. Over half of the 375 open items were closed by January 30.
- Modification and maintenance projects are well defined and active. Many tasks have been completed, although they still require NRC closeout action.
- Meetings were successfully held with the NRC regarding specific program details and process.
- On January 28, 1987, SMUD Senior Management and a Board member presented a report on Restart Progress to the Nuclear Regulatory Commissioners in Washington, D.C. The Commissioners complimented SMUD on the thoroughness of our issue identification process (PP&MIP).
- In January, a 14-man team from Nuclear Reactor Regulation (NdR) and NRC Region V began a 4-week on-site inspection of 7 key systems.
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 continue to grow as restart tasks are initiated. Staffing and expense trends are consistent with budget estimates.
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HIGHLIGHTS (Continued)
I.
- Schedule Restart of the reactor is planned in May with power operation beginning in June. Physics testing will precede power operation. Some tests at power will be conducted in June and July.
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 they are effectively interfaced with the Action Plan and that it, and our commitments, meet their needs and will support a safe and timely restart.
II. INTR 00VCIION 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 this report covers the period of December 1986 and January 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. The SRIP consolidates the input from the Plant Performance and Management Improvement Program (PP&MIP) with the system reviews performed by the Systems Engineer and develops a systems testing program to demonstrate plant material readiness.
- 2. New Issues Affecting Restart Weekly program reports are prepared by the DGM Nuc' lear 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.
- Duke Power Company's Oconee Nuclear Station has had two reactor coolant pump failures. Rancho Seco has the reactor coolant pumps made by the same manufacturer. We are participating in the problem analysis being performed by Duke Power to see if Rancho Seco's pumps could experience the same kind of failure. Preliminarily, we believe that we do not have the same " root cause" problem, but we will continue to analyze this problem area.
III. ACTION PLAN PROGRESS (Continued)
- Although diminishing in potential, the issue of the reliability of electrical power and control cables to be actually installed according to the separation criteria continues to require investment of resources. lhe discovered problems have been mininal, feeding optimism that this issue will not delay restart. A statistical sampling program is being conducted to resolve this issue.
- The reliability of over 160 critically important valves has become an increasingly important issue. These valves, all operated by an attached motor, actuated either automatically or by an operator from a remote control station, must operate as designed in order to allow Rancho Seco to generate power. Testing and evaluations continue. All motor operated valves will be functional prior to restart.
- 3. Closure of Issues The QCI-12 Tracking System (QTS), a computer based tracking system, will document the successful development of closure packages.
- 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.
- a. December 26. 1985 Event Analysis A total of 150 analyses, studies, repairs, and modifications were initiated to investigate and recover from the overcooling event. These resulted in approximately 400 recommendaticns, which have been identified in Amendment 2 of the Action Plan by the respective managers and system engineers for closure.
- b. Precursor Review Approximately 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 Amendment 2 of the Action Plan.
- c. Deterministic Failure Consequence Analysis This portion of the program generated Action Plan items
~
which will be closed before Restart. These analyses documented the effect of component failure on system operation, as well as synergistic effects upon other systems. 1232 recommendations resulted.
III. ACTION PLAN PROGRESS (Continued)
- d. Personnel Interviews i
Interviews with plant personnel resulted in 1631 l
recommendations and generated actions to be completed prior to restart.
- e. BWOG The program inputs are 76 recommendations of an expected !
107. The remaining 31 inputs will be evaluated according to our QCI-12 process in the near future.
- 5. Management. Doerations and Administration
- a. Changes in Supervisory and Management Staff:
Efforts are continuing to identify permanent SMUD Managers 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 contractor-filled positions will be conducted in February and March 1987.
- b. Changes in Organizational Structure:
Efforts are in full stride to define the " Ultimate" or target nuclear organization which will result in the staffing of all nuclear management positions by SMUD people. This is a comprehensive program which will be described in a future Amendment to the Action Plan.
- c. The Systems Review and Test Program (STRP):
Total staffing for this organization is 110 people. All are presently assigned and all key positions have been filled.
Details of the SRTP were presented to the NRC in Washington, D.C. on January 28, 1987.
In December and January an NRC team reviewed the Systems Review and Test Program at Rancho Seco and had no major concerns. They were pleased with the progress made to I date.
- 6. Plant Modifications and Maintenance Improvements l
Section 4C of the Action Plan details the modifications and maintenance required for restart. Actual work is underway on each of the identified projects. Completion of each task is occurring, although item closeout is pending full operation of the QTS and closecut documentation process.
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, . . a III. ACTION PLAN PROGRESS (Continued)
The forthcoming amendment 3 to the Action Plan will describe the SMUD program and plan for scheduling near term and long
. term recommendations.
' 7. Systems Review and Test Program This program is described in Section 4D 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. These will define the scope and depth of the individual system tests. Detailed test procedures are being developed. Approximately 30% are complete.
- 8. Non-Action Plan Related Activities 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.
- 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 management information and control of
- activities and resources. These ef forts allow for the
- budgeting and allocation of resources where necessary to i accomplish the commitments of the Action Plan. The major elements are:
- a. Budget
- b. Personnel and Staffing During the months of December, 1986 and January, 1987, the total staff assigned to the Nuclear Organization increased by approximately 200 people as efforts to staff up to accomplish action plan commitments continued. As of the end of January, there were 879 SMUD employees, 617 craft labor, and 1751 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 staf f during the months of December and January as a percentage of straight time hours worked is as follows:
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. . ., s III. AClION PLAN PROGRESS (Continued)
SMUD 22%
Creft Labor 15%
Consultants /Other Contractors 18%
(located at Rancho Seco and submitting site timesheets)
As of January 31, 1987, a total of 2,630 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 50 temporary trailers.
- 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. Cable routing problems
- b. Reactor coolant pump problems
- c. Failures during system tests
- d. Delays in the regulatory process i
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