IR 05000312/2005001

IR 05000312-05-001, on 01/31-02/03/05; Sacramento Municipal Utility District; Rancho Seco Nuclear Generating Station. Decommissioning Report; No Violations

ML050620520
Person / Time
Site:	Rancho Seco
Issue date:	03/03/2005
From:	Spitzberg D NRC/RGN-IV/DNMS/FCDB
To:	Shetler J Sacramento Municipal Utility District (SMUD)
References
IR-05-001
Download: ML050620520 (19)

Text

March 3, 2005

SUBJECT:

NRC INSPECTION REPORT 050-00312/05-001

Dear Mr. Shetler:

An NRC inspection was conducted on January 31 through February 3, 2005, at your Rancho Seco Nuclear Generating Station. On February 3, 2005, at the conclusion of the inspection, an exit briefing was conducted with Mr. Steve Redeker, Plant Manager, and other members of your staff. The enclosed report presents the scope and results of that inspection.

The inspection was an examination of activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license. Within these areas, the inspection included reviews of your organization and staffing, employee safety concerns program, decommissioning funding, safety reviews, surveillances and testing activities, and the status of decommissioning activities. No violations of NRC regulations were identified during the inspection.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be made available electronically for public inspection in the NRC Public Document Room or from the NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/Adams.html. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the public without redaction.

Should you have any questions concerning this inspection, please contact Mr. Emilio Garcia, Health Physicist, at (530) 756-3910 or the undersigned at (817) 860-8191.

Sincerely,

/RA JVEverett for/

D. Blair Spitzberg, Ph.D., Chief Fuel Cycle and Decommissioning Branch Docket No.: 50-312 License No.: DPR-54

Sacramento Municipal Utility District

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Enclosure:

NRC Inspection Report 050-00312/05-001

REGION IV==

Docket Nos.:

050-00312 License Nos.:

DPR-54 Report Nos.:

050-00312/05-001

Licensee:

Sacramento Municipal Utility District Facility:

Rancho Seco Nuclear Generating Station Location:

14440 Twin Cities Road Herald, California Dates:

January 31 through February 3, 2005 Inspector:

Emilio M. Garcia, Health Physicist Approved By:

D. Blair Spitzberg, Ph.D., Chief Fuel Cycle and Decommissioning Branch Attachments:

Supplemental Information Partial List of Documents Reviewed ADAMS Entry :

IR 05000312-05-001 on 01/31-02/03/05; Sacramento Municipal Utility District; Rancho Seco Nuclear Generating Station.

Decommissioning Report; No Violations.

-2-EXECUTIVE SUMMARY Rancho Seco Nuclear Generating Station NRC Inspection Reports 050-00312/05-001 The licensee was actively conducting dismantling activities in the reactor building, auxiliary building, spent fuel building and other exterior areas. All spent fuel had been removed from the spent fuel pool and placed in the Independent Spent Fuel Storage Installation (ISFSI). The reactor vessel head, pressurizer, pressurizer drain tank and the two steam generators had been removed from the reactor building and shipped to an off-site disposal facility.

Organization, Management and Cost Controls

All managerial positions were staffed with experienced individuals familiar with their job responsibilities. The organization and staffing were as required by the Rancho Seco Quality Manual (Section 1.1).

• The licensee had implemented a program for plant personnel to identify safety concerns. Licensee personnel interviewed during this inspection were aware of the licensees safety concerns program and felt comfortable identifying safety issues to plant management (Section 1.2).

• The licensees decommissioning funding status was reviewed and found to meet the requirements of 10 CFR 50.75. Based on licensee projections of decommissioning costs and the amount of work completed at the end of 2004, adequate funding would be available to complete site decommissioning (Section 1.3).

Safety Reviews, Design Changes, Modifications

Safety screenings were conducted in accordance with the licensees procedures and applicable regulations. Qualified reviewers and Commitment Management Review Group members and alternates were appropriately trained (Section 2).

Maintenance and Surveillance

Limited surveillance and testing activities were required of plant equipment since the relocation of the spent fuel to the ISFSI and the disposal of the spent fuel pool water.

One of the systems requiring surveillance and testing was the liquid effluent radiation monitor, which had been inoperable since August 16, 2004. Compensatory measures for collecting and analyzing samples was implemented during this period in accordance with the licensees Offsite Dose Calculation Manual (Section 3).

Decommissioning Performance and Status Review

Dismantlement activities continued in the reactor building, auxiliary building, spent fuel building and other exterior areas. The reactor vessel head, pressurizer, pressurizer relief tank and steam generators had been removed from the reactor building and

-3-shipped for disposal. Additionally, all major components in the auxiliary building had been removed and shipped for disposal. Characterization radiation surveys had been initiated in the auxiliary building. Most liner plates had been removed from the walls of the spent fuel pool (Section 4).

Solid Radioactive Waste Management And Transportation of Radioactive Materials

Audit and surveillance activities related to solid radwaste management and to transportation of radioactive materials were being effectively implemented by the licensee (Section 5.1).

• The licensee had implemented a transportation program for radioactive materials and radioactive waste in accordance with NRC and U.S. Department of Transportation regulations (Section 5.2).

-4-Report Details Summary of Facility Status The Rancho Seco Nuclear Generating Station was permanently shut down in June 1989. All spent reactor fuel has been moved to an onsite Independent Spent Fuel Storage Installation (ISFSI). At the time of this inspection, the licensee was conducting decommissioning activities at the site. Decommissioning was being performed under the provisions of the incremental decommissioning option of Rancho Secos Post Shutdown Decommissioning Activities Report, dated March 20, 1997.

Decommissioning work activities included the auxiliary building, reactor building, spent fuel building and exterior areas. All major components in the auxiliary building had been removed, packaged and shipped for disposal. In the reactor building, the major piping, the four reactor coolant pumps, the core flood tanks, reactor vessel head, pressurizer, pressurizer drain tank, and one steam generator had been removed, packaged and shipped offsite for disposal. The second steam generator had been removed from the reactor building and was shipped to a disposal site during this inspection. In the fuel handling building, the spent fuel pool water had been processed and released offsite. Most of the pool liner plates had been cut, removed and shipped for disposal.

Organization, Management and Cost Controls (IP 36801)

1.1 Organization a.

Inspection Scope The inspector reviewed the licensees organizational structure against the requirements of the Rancho Seco Quality Manual (RSQM),Section I, Organization.

b.

Observations and Findings The licensees organization was consistent with the Rancho Seco Quality Manual,Section I, Organization. There had been no changes to procedure RSAP 0101, Nuclear Organization Responsibilities and Authorities, or to procedure RSAP-0260, Commitment Management Review Group and Commitment Tracking System. The licensee had issued an updated Rancho Seco Management Organization Chart to reflect the individuals assigned to each position. This organization chart was dated January 2005. At the time of this inspection, all the managerial positions were staffed with experienced individuals with many years of service with the licensee. All the managers were familiar with their responsibilities.

c.

Conclusion All managerial positions were staffed with experienced individuals familiar with their job responsibilities. The organization and staffing were as required by the Rancho Seco Quality Manual.

-5-1.2 Employee Safety Concern Program a.

Inspection Scope The inspector reviewed the licensees employee safety concerns program.

b.

Observations and Findings The licensees employee safety concern program was described in procedure RSAP-1308, Potential Deviation from Quality, also known as the PDQ process. The inspector selected four site personnel to interview regarding their knowledge of the Potential Deviation from Quality (PDQ) process. These individuals indicated that they felt comfortable bringing concerns to their supervisors. All of the employees were aware that they could initiate a PDQ or alternatively bring concerns to the NRCs attention.

These individuals also indicated that they had received training on the safety concerns program while working for the licensee.

A total of 36 PDQs were opened in 2004. One PDQ had been initiated as of February 1, 2005. None of these issues had been submitted anonymously. Furthermore, all of the PDQs had been reviewed by the Commitment Management Review Group and were either closed or were being resolved.

c.

Conclusion The licensee had implemented a program for plant personnel to identify safety concerns. Licensee personnel interviewed during this inspection were aware of the licensees safety concerns program and felt comfortable identifying safety issues to plant management.

1.3 Cost Controls a.

Inspection Scope The inspector reviewed the licensees program for implementing the requirements of 10 CFR 50.75(f)(1), and reviewed the licensees decommissioning fund status through the end of 2004. The inspector also discussed cost controls with the licensees decommissioning/nuclear project control coordinator.

b.

Observations and Findings 10 CFR 50.75(f)(1) requires each power reactor licensee to submit a report on a 2-year basis of (1) the amount of decommissioning funds estimated to be required for decommissioning; (2) the amount accumulated to the end of the preceding calendar year; (3) a schedule of annual amounts remaining to be collected; (4) the assumptions used regarding the rates of escalation in decommissioning cost; (5) the rates of earnings on decommissioning funds; (6) rates of other factors used in funding projections; (7) any contracts upon which the licensee is relying pursuant to

-6-10 CFR 50.75(e)(1)(v); (8) any modifications occurring to a licensees current method of providing financial assurance; and (9) any material changes to trust agreements. This regulation requires the biennial report to be submitted by March 31 of the reporting year.

The report covering the decommissioning fund status through calendar year 2003 was submitted to the NRC on March 18, 2004. This timely report included information on the nine items required in 10 CFR 50.75(f)(1).

Records maintained by the licensee indicated that on December 31, 2003, the book value of the decommissioning trust fund was $91,175,051.02 with a par value of

$91,707,208.58. The book value used by the licensee is the value at which an asset is carried on a balance sheet. The par value is the value of the bond, note or other investment at the time of maturity. The asset summary provided by the bank managing the account listed the market value of the total investments at $91,413,093.58 as of December 31, 2003. The value reported in the 2003 annual Decommissioning Fund Status report of $91.7 million was consistent with the par value calculated by the licensee.

The licensees records for the 2004 decommissioning funding were also reviewed. The licensees decommissioning/nuclear project control coordinator stated that the licensee internally updated their cost estimates twice per year and had estimated their costs through 2028. The licensees total decommissioning cost estimate as of the end of 2004 was $529.7 million, with an estimated 62.3 percent of the decommissioning cost completed. The decommissioning trust fund had a book value of $88.6 million as of December 31, 2004. The Sacramento Municipal Utility District was committed to adding

$27 million per year to the fund through 2008. Based on the current value of the fund and the projected additions, sufficient funding to complete the decommissioning of the site would be available.

c.

Conclusion The licensees decommissioning funding status was reviewed and found to meet the requirements of 10 CFR 50.75. Based on licensee projections of decommissioning costs and the amount of work completed at the end of 2004, adequate funding would be available to complete site decommissioning.

Safety Reviews, Design Changes, and Modifications (IP 37801)

2.1 Inspection Scope The inspector reviewed selected 10 CFR 50.59 safety screenings conducted since the previous inspection.

2.2 Observations and Findings The Commitment Management Review Group minutes for the period of April 2004 through January 26, 2005, were reviewed. During this time, six safety screenings

-7-associated with the Part 50 license had been approved by the Commitment Management Review Group. No full safety evaluations had been performed or were required. Table 1 provides a list of the safety screenings performed. The inspector reviewed the screening packages. The packages were complete and had been reviewed in accordance with 10 CFR 50.59 requirements. The packages were signed by both a qualified reviewer and the plant manager. All reviewers were on the list of qualified reviewers. Training records indicated that they had successfully completed training as a 10 CFR 50.59 and 10 CFR 72.48 reviewer and had received refresher training within the last 12 months. The minutes of the Commitment Management Review Group indicated that the screenings had been reviewed, discussed and unanimously approved by the Commitment Management Review Group. Records maintained by the licensee indicated that Commitment Management Review Group members and alternates had been trained. Commitment Management Review Group training included being a qualified reviewer.

Table 1 Safety Screenings

Topic Reviewer CMRG Approval CMRG Signature

RSQM Section XVIII, Audits, Rev 10 Mannheimer 4/6/04 4/7/04 Redeker

Reclassification of Auxiliary Building ventilation fans Mannheimer 4/27/04 4/27/04 Redeker

Cosumnes Power Plant (CPP) Construction and Operation Mannheimer 8/24/04 8/24/04 Redeker

10 CFR 50 License Amendment 198, Administrative Clean-up of license requirements Jones 12/21/04 12/22/04 Redeker

RSQM Section XVIII, Audits, Rev. 11 Mannheimer 1/10/05 1/12/05 Redeker

CAP-002, Offsite Dose Calculation Manual, Rev 17 Nicolls 12/21/04 01/26/05 Redeker 2.3 Conclusion Safety screenings were conducted in accordance with the licensees procedures and applicable regulations. Qualified reviewers and Commitment Management Review Group members and alternates were appropriately trained.

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Maintenance and Surveillance (IP 62801)

3.1 Inspection Scope The inspector reviewed the status of required surveillances and testing of the liquid effluent radiation monitor.

3.2 Observations and Findings The current listing of the status of surveillances and routine tests was reviewed. As of February 3, 2005, there was one overdue surveillance/routine test. The overdue surveillance related to the calibration of the liquid effluent radiation monitor. With the relocation of the spent fuel to the ISFSI and the treatment and release of the spent fuel pool water, there were very few maintenance and surveillance requirements for equipment onsite. The only remaining system of importance was the liquid effluent radiation monitor (R-15017A). The two required surveillances associated with this system were the quarterly test and the refueling interval calibration. For these surveillances the licensee used a dedicated radioactive check source. However, sometime prior to August 16, 2004, this radioactive check source was inadvertently disposed of as radioactive waste. As a result of not having a check source available to verify proper operation of the liquid effluent radiation monitor, the licensee returned the radiation monitor to the manufacturer for calibration along with a new check source for determination of the radiation monitors response to the check source. The check source used with the liquid effluent radiation monitor was not an off the shelf item but was special ordered from Europe. The new check source and the liquid effluent radiation monitor were expected back to the site on May 15, 2005. The liquid effluent radiation monitor had been inoperable since August 16, 2004. The licensee had collected and analyzed grab samples during this time period as allowed by their Offsite Dose Calculation Manual as a compensatory measure.

3.3 Conclusion Limited surveillance and testing activities were required of plant equipment since the relocation of the spent fuel to the ISFSI and the disposal of the spent fuel pool water.

One of the systems requiring surveillance and testing was the liquid effluent radiation monitor, which had been inoperable since August 16, 2004. Compensatory measures for collecting and analyzing samples was implemented during this period in accordance with the licensees Offsite Dose Calculation Manual.

Decommissioning Performance and Status Review (IP 71801)

4.1 Inspection Scope The licensees dismantlement activities were reviewed. Tours of the site were conducted to observe work activities underway, including observation of housekeeping, safety practices, fire loading and radiological controls.

-9-4.2 Observations and Findings Tours of the reactor building, auxiliary building, spent fuel building and other areas of the plant were conducted to observe dismantling and decommissioning activities in progress. The work observed was being conducted in a safe and orderly manner.

Radiological controls, including postings and barriers, were in place. The inspector also noted good housekeeping and fire protection practices in all areas.

The reactor vessel head, pressurizer, pressurizer relief tank and steam generators had been removed from the reactor building and shipped for disposal. This left only the reactor vessel and reactor internals as the last major components. The missile shields were being relocated to the bottom of the D ring to permit better access to the reactor vessel. Fire extinguishers were located at each elevation in the reactor building. The fire extinguishers had been serviced within the last year. Emergency kits were also located at each elevation and included eye wash, emergency horns and a flash light. All of these kits were complete and operable with the exception of the emergency horn at the plus 60' elevation which needed replacement of the can of pressurized air. This was brought to the attention of the appropriate licensee representative.

All major components had been removed from the auxiliary building. The licensee was now removing the electrical equipment, cabling, and the heating, ventilation and air conditioning ducts from various elevations in the building. The licensee was also conducting characterization radiation surveys at the minus 20-foot elevation.

Most liner plates had been removed from the walls of the spent fuel pool. All the milling work for removing the spent fuel pool liner plates had been completed. Remaining liner plates were to be removed with a cutting torch.

4.3 Conclusion Dismantlement activities continued in the reactor building, auxiliary building, spent fuel building and other exterior areas. The reactor vessel head, pressurizer, pressurizer relief tank and steam generators had been removed from the reactor building and shipped for disposal. Additionally, all major components in the auxiliary building had been removed and shipped for disposal. Characterization radiation surveys had been initiated in the auxiliary building. Most liner plates had been removed from the walls of the spent fuel pool.

Solid Radioactive Waste Management And Transportation of Radioactive Materials (IP 86750)

5.1 Audits and Surveillances a.

Inspection Scope The inspector reviewed the licensees audit and surveillance program and selected several audits and surveillances for detail review.

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Observations and Findings The inspector reviewed Audit Report 04-A-006, Process Control Program (PCP) and Packaging & Transportation of Radioactive Waste, dated August 4, 2004. In addition, the inspector reviewed the licensees surveillance log and noted that in calender year 2004, of the 49 surveillances that had been conducted, 22 related to radioactive waste shipments and an additional three addressed waste stream evaluation or material disposal. In calender year 2005, of the four surveillances that had been conducted, as of the time of this inspection, one related to radioactive waste shipments and two addressed waste stream evaluation or material disposal. The inspector selected three surveillances for review, Surveillance Reports 04-S-018, approved on May 6, 2004, 04-S-020, approved on June 3, 2004, and 05-S-004, approved on February 7, 2005.

The individuals assigned to perform the audit were trained and qualified and were independent of the areas being audited. The audit and surveillances included performance based elements. The audit identified that three of the four procedures reviewed that had PCP in their title were signed by the area superintendent instead of the plant manager. Procedure RSAP-0500 Review, Approval and Changes of Procedures, in effect at the time required the plant managers signature for these procedures, but if an area superintendent was acting for the plant manager, that individual could approve the procedure. The auditor concluded that it was not possible to determine if, at the time the procedures were signed, if the area superintendent was acting for the plant manager. The auditor initiated a PDQ recommending that RSAP-0500 be revised to require area superintendents to clarify when they were signing a procedure on behalf of the plant manager. RSAP-0500 was revised effective October 6, 2004, to incorporate this recommendation. No quality related problems were identified during the audit and surveillances related to solid radwaste management and transportation of radioactive materials. Recommendations identified in the surveillances were addressed by the audited department.

c.

Conclusion Audit and surveillance activities related to solid radwaste management and to transportation of radioactive materials were being effectively implemented by the licensee.

5.2 Shipping of Low-Level Radioactive Waste for Disposal, and Transportation of other Radioactive Material a.

Inspection Scope The inspectors reviewed shipping records to determine if radioactive waste shipments were in compliance with applicable NRC and U.S. Department of Transportation (DOT)

regulations.

-11-b.

Observations and Findings As of February 3, 2005, 69 shipments of radioactive material had been completed in 2004 and 2005. Four records were selected for reviewed. These were for Shipments04-056, 04-060,05-003 and 05-004 related to the shipments for the steam generators. The records documented compliance with the requirements of 49 CFR 173.427 for surface contaminated object (SCO). The emergency response telephone number listed on the waste manifests was confirmed as the telephone number for the Rancho Seco secondary alarm station. The shipping records included copies of the radiological surveys conducted, Form 540 Uniform Low-Level Radioactive Waste Manifest, emergency response information, instructions to the carrier for maintenance of exclusive use shipment controls and the vehicle inspection report.

Documents requiring shipper certification were signed by a licensee representative.

Records of the training of individuals who signed or otherwise performed functions related to the transport of hazardous material were reviewed. The individuals involved with these shipments had received appropriate training as required by 49 CFR 172, Subpart H.

Subsequent to the site visit, the licensee telephonically informed the inspector on February 8, 2005, that damage to the steam generator had occurred while in transit to the low-level burial site. The steam generator was being shipped by train. Studs used to secure a flange on the penetrations on the steam generator had rubbed against the side of a bridge or tunnel. The minor damage was detected by railroad personnel during a scheduled crew change. The new crew, while completing their turnover inspection, found concrete debris on the car carrying the steam generator and noticed that the polymer coating had been scraped from four of the threaded studs on the steam generators flange. Other railroad representatives examined and measured the package and concluded that the package still met the specified dimensions and was properly secured to the rail car. The railroad representatives recommended that the package continue on its way to the consignee. The licensee was contacted and concurred. Later examinations by the licensees radioactive waste superintendent and a senior radiation protection technician confirmed that the damage was minor and that no detectable radioactive contamination was released to the environment.

c.

Conclusion The licensee had implemented a transportation program for radioactive materials and radioactive waste in accordance with NRC and U.S. Department of Transportation regulations.

Exit Meeting Summary The inspector presented the inspection results to the plant manager and other members of licensee staff at the exit meeting on February 3, 2005. The licensee did not identify as proprietary any information provided to, or reviewed by, the inspector.

ATTACHMENT 1 PARTIAL LIST OF PERSONS CONTACTED Sacramento Municipal Utility District M. Bua, Radiation Protection/Chemistry Superintendent M. Braun, Sr. Nuclear Engineer J. Delezenski, Quality Assurance/Licensing/Administration/Training Superintendent L. England, Coordinator, Project Controls Decommissioning D. Gardner, Decommissioning Project Manager R. Jones, Sr. Nuclear Engineer S. Nicolls, Radiological Health Supervisor S. Redeker, Manager, Plant Closure and Decommissioning G. Roberts, Maintenance Superintendent M. Snyder, Radioactive Waste Superintendent INSPECTION PROCEDURES USED IP 36801 Organization, Management, and Cost Controls IP 37801 Safety Reviews, Design Changes, and Modifications IP 62801 Maintenance and Surveillances IP 71801 Decommissioning Performance and Status Review IP 86750 Solid Radioactive Waste Management and Transportation of Radioactive Materials ITEMS OPENED, CLOSED, AND DISCUSSED Opened None Closed None Discussed None LIST OF ACRONYMS CMRG Commitment Management Review Group DOT Department of Transportation IP Inspection Procedure ISFSI Independent Spent Fuel Storage Installation PCP Process Control Program PDQ Potential Deviation from Quality RSAP Rancho Seco Administrative Procedure RSQM Rancho Seco Quality Manual SCO surface contaminated object

ATTACHMENT 2 PARTIAL LIST OF DOCUMENTS REVIEWED Audits and Surveillances

Rancho Seco Audit Report No. 04-A-006, Process Control Program (PCP) + Packaging

& Transportation of Radioactive Waste, dated August 4, 2004.

• Surveillance Report 04-S-018, Objectives: Verify that the radioactive waste shipment meets DOT and SMUD requirements prior to departure from Rancho Seco, surveillance period April 20-29, 2004.

• Surveillance Report 04-S-020, Objectives: Verify that the radioactive waste shipment meets DOT and SMUD requirements prior to departure from Rancho Seco, surveillance period June 3, 2004.

• Surveillance Report 05-S-004, Objectives: Verify that the radioactive waste shipment meets DOT and SMUD requirements prior to departure from Rancho Seco, surveillance period Jan. 6, & Feb. 1-2, 2005.

Data Sheets

2004 Rancho Seco Audit Log, as of February 1, 2005.

• 2004 Surveillance (QC) Log, as of February 1, 2005.

• 2004 SWLLRW Tracking Spreadsheet, as of February 3, 2005.

• 2005 SWLLRW Tracking Spreadsheet, as of February 3, 2005.

• Computerized Record Class Attendance Sheet, course DE03B1400, DOT/NRC Refresher Training - Spring 2003, print out dated February 3, 2005.

• Computerized Record Class Attendance Sheet, course DE04B2200, Radioactive Waste Packaging, Transportation & Disposal, print out date February 3, 2005.

• Computerized Record Class Attendance Sheet, course DE04B2300, Update to DOT Regulations: HM230, print out dated February 3, 2005.

• Computerized Record Class Attendance Sheet, course ST01N0100, 50.59 Training, print out dated February 1, 2005.

• MPC&D 04-031, CMRG Membership, dated March 24, 2004.

• MPC&D 04-041, CMRG Membership, dated April 20, 2004.

• MPC&D 05-014, Qualified Reviewer List, dated February 1, 2005.

• PDQ Log, as of February 1, 2005.

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Qualified Reviewer Annual Refresher Training, reading assignment August 10, 2004.

• Rancho Seco Computerized Surveillance Schedule, Surveillances by SP#, status as of February 3, 2005.

• Rancho Seco Computerized Surveillance Schedule, Routine Tests by RT#, status as of February 3, 2005.

• Spreadsheet Titled Decommissioning Portfolio 12/31/2003.

• Spreadsheet Titled Decommissioning Portfolio 12/31/2004.

• Training Attendance Roster, Rancho Seco Radioactive Waste Transportation Security Plan, dated December 8, 2003.

• Uniform Low-Level Radioactive Waste Manifest, Form-540, Shipment Number 04-056, shipment dated December 1, 2004.

• Uniform Low-Level Radioactive Waste Manifest, Form-540, Shipment Number 04-060, shipment date December 1, 2004.

• Uniform Low-Level Radioactive Waste Manifest, Form-540, Shipment Number 05-003, shipment date February 2, 2005.

• Uniform Low-Level Radioactive Waste Manifest, Form-540, Shipment Number 05-004, shipment date February 2, 2005.

Meeting Minutes

CMRG Meeting Held on April 7, 2004, at 8:00 a.m.

• Special CMRG Meeting held on April 19, 2004, at 10:00 a.m. and continued on April 20, 2004 at 11:00 a.m.

• Special CMRG Meeting held on April 22, 2004, at 3:00 p.m.

• CMRG Meeting held on July 14, 2004, at 8:00 a.m.

• Special CMRG Meeting held on July 19, 2004, at 8:30 a.m.

• CMRG Meeting held on August 25, 2004, at 8:00 a.m.

• CMRG Meeting held on December 22, 2004, at 8:00 a.m.

• CMRG Meeting held on January 12, 2005, at 8:30 a.m.

• CMRG Meeting held on January 26, 2005, at 8:30 a.m.

-3-Procedures

Rancho Seco Quality Manual,Section I, Organization, Revision 11, effective August 26, 2002.

• Rancho Seco Administrative Procedure RSAP 0101, Nuclear Organization Responsibilities and Authorities, Revision 29, effective September 4, 2003.

• Rancho Seco Administrative Procedure RSAP-0260, Commitment Management Review Group and Commitment Tracking System, Revision 12, effective September 4, 2003.

• Rancho Seco Administrative Procedure RSAP-0500, Review, Approval and Changes of Procedures, Revision 20, effective October 6, 2004.

• Rancho Seco Administrative Procedure RSAP 1308, Potential Deviation from Quality, Revision 17, effective February 13, 2003.

Reports

DPT 04-115, Decommissioning Project Status, October 2004.

• DPT 04-122, Decommissioning Project Status, November 2004.

• DPT 05-006, Decommissioning Project Status, December 2004.

• DPT 05-Draft, Decommissioning Project Status, January 2005.

• MPC&D 04-024, dated March 18, 2004, from Manager, Plant Closure and Decommissioning to U. S. Nuclear Regulatory Commission, Subject: Rancho Seco Report on Decommissioning Funding Status.

• MPC&D 04-030, dated April 7, 2004, from Manager, Plant Closure and Decommissioning to U. S. Nuclear Regulatory Commission, Subject: Changes to Rancho Seco Quality Assurance Program.

• MPC&D 05-012, dated January 27, 2005, Rancho Seco Weekly Update for January 21-27, 2005.

• PDQ 04-0012, Fractured Support Steel Discovered Inside the Pressurizer Relief Tank, complete package, finished April 21, 2004.

• PDQ 04-0025, Loss of Site Power Caused Several Failures Resulting in an Unplanned Liquid Release and Compensatory Security Measures at the ISFSI

Radiological Characterization of the Steam Generator Shipping Packages, Revision 1, February 23, 2004.

• Rancho Seco Commitment Tracking System Reports for PDQ or DQ number 04-001 through 05-001.

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U. S. Department of Transportation Regulatory Exemption DOT-E-13338, effective October 5, 2004.

• Watts Happening Newsletter January 24, 2005 issue.

• Well Fargo, Asset Summary as December 31, 2003, SMUD Decom Trust Fund Escrow Account.

• Well Fargo, Asset Summary as December 31, 2004, SMUD Decom Trust Fund Escrow Account.