IR 05000312/2007004

IR 05000312-07-004, on 10/15-18/2007, Rancho Seco, Decommissioning Activities

ML073200888
Person / Time
Site:	Rancho Seco
Issue date:	11/16/2007
From:	Whitten J Division of Nuclear Materials Safety IV
To:	Shetler J Sacramento Municipal Utility District (SMUD)
References
IR-07-004
Download: ML073200888 (19)

Text

UNITED STATES NU CLE AR RE GU LATOR Y C O M M I S S I O N ber 16, 2007

SUBJECT:

NRC INSPECTION REPORT 050-00312/07-004

Dear Mr. Shetler:

A Nuclear Regulatory Commission (NRC) inspection was conducted on October 15-18, 2007, at your Rancho Seco Nuclear Generating Station. At the conclusion of the inspection an exit briefing was conducted with the acting plant manager and other members of your staff. The enclosed inspection report presents the scope and results of the 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 maintenance and surveillance activities, decommissioning performance, final status surveys, solid radioactive waste management, and transportation of radioactive materials. The inspection determined that you were conducting decommissioning activities in compliance with license and regulatory requirements. No violations were identified, and no response to this letter is required.

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.

Sacramento Municipal Utility District -2-Should you have any questions concerning this inspection, please contact Mr. Emilio Garcia, Health Physicist, at (530) 756-3910 or the undersigned at (817) 860-8197.

Sincerely,

/RA/

Jack E. Whitten, Chief Nuclear Materials Safety Branch B Docket No.: 050-00312 License No.: DPR-54

Enclosure:

NRC Inspection Report 050-00312/07-004 (w/Attachment)

Sacramento Municipal Utility District -3-

REGION IV==

Docket No.: 050-00312 License No.: DPR-54 Report No.: 050-00312/07-004 Licensee: Sacramento Municipal Utility District Facility: Rancho Seco Nuclear Generating Station Location: 14440 Twin Cities Road Herald, California Dates: October 15 through 18, 2007 Inspector: Emilio M. Garcia, Health Physicist Approved By: Jack E. Whitten, Chief Nuclear Materials Safety Branch B Attachments: Supplemental Information Partial List of Documents Reviewed Enclosure

EXECUTIVE SUMMARY Rancho Seco Nuclear Generating Station NRC Inspection Report 050-00312/07-004 This inspection was a routine, announced inspection of decommissioning activities being conducted at the Rancho Seco Nuclear Generating Station. Areas inspected included maintenance and surveillance, decommissioning performance and status review, inspection of final status surveys, and solid radwaste management and transportation of radioactive materials.

Maintenance and Surveillance

• The licensee no longer had any safety-related structures, systems or components, and the requirements of the Maintenance Rule were no longer required to be implemented at this site. The licensee had continued to maintain their schedule on other surveillances and routine tests (Section 1).

Decommissioning Performance and Status Review

• The licensee continued to dismantle and remove contaminated components and to remediate contaminated surfaces in a safe manner. Final status surveys had been completed on 159 of 284 survey units (Section 2).

Inspection of Final Status Surveys

• Confirmatory measurements on imbedded piping in the turbine building and on selected surfaces of the auxiliary building were conducted by the staff of NRCs contractor, Oak Ridge Institute for Science Education (ORISE). One soil sample was collected by the contractor from the retention basin area and sent for analysis. The results of these confirmatory surveys when received from NRCs contractor will be reported at a later date in a separate addendum to this report (Section 3).

Solid Radwaste Management and Transportation of Radioactive Materials

• Audit surveillances conducted by the licensee of the transportation of radioactive materials were performance-based and their overall quality met NRCs expectations (Section 4.1).

• Changes to the licensees organization, personnel, facilities, equipment, programs, and procedures had not negatively effected the solid waste management and the transportation of radioactive materials program (Section 4.2).

• Personnel involved in the transfer, packaging and transport of radioactive waste and transportation of other radioactive materials had received initial training and periodic retraining (Section 4.3).

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• The licensee maintained copies of the applicable regulations and the radioactive materials license for each recipient of radioactive materials made from the site (Section 4.4).

• The licensee had implemented a transportation program for radioactive materials in accordance with NRC and the U.S. Department of Transportation (DOT) regulations (Section 4.5).

-3- Enclosure

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 under the provisions of the incremental decommissioning option of Rancho Secos Post Shutdown Decommissioning Activities Report dated March 20, 1997.

Decommissioning work activities conducted by the licensee included the auxiliary building, reactor building, spent fuel building, and exterior areas. All major components had been removed, packaged, and shipped offsite for disposal. In the auxiliary building, remediation and final status survey activities continued below the grade level. In the reactor building, the concrete and steel removal project conducted by a contractor of the licensee was under way with approximately 6.2 million pounds of the concrete and steel removed and shipped offsite. In the fuel handling building, the vertical walls were being remediated with 1/4 to 4 inches of the surfaces being removed as needed. At the time of the inspection, approximately 56 percent of survey units had been completed by the licensee.

1 Maintenance and Surveillance (IP 62801)

1.1 Inspection Scope The inspector reviewed the status of required maintenance, surveillance, and testing. The inspector interviewed the Maintenance Superintendent and reviewed selected records.

1.2 Observations and Findings With the relocation of the spent fuel to the ISFSI, the licensee no longer had any safety-related structures, systems or components (SSC) as defined in 10 CFR 50.65(b)(1), nor any non-safety-related SSC as defined in 10 CFR 50.65(b)(2).

The licensee had previously reviewed its Maintenance Rule procedure and concluded that it no longer was required to implement these activities at the site.

The inspector reviewed a printout of the Rancho Seco Computerized Surveillance Schedule dated October 17, 2007, that listed the status of surveillances and routine tests. Six routine tests or surveillances were beyond their due dates, but none were beyond their established grace period. The licensee indicated that it did not expect that any of these surveillances or tests would exceed their grace period.

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1.3 Conclusion The licensee no longer had any safety-related structures, systems or components, and the requirements of the Maintenance Rule were no longer required to be implemented at this site. The licensee was maintaining their schedule on other surveillance and routine testing activities as required.

2 Decommissioning Performance and Status Review (IP 71801)

2.1 Inspection Scope The inspector interviewed cognizant personnel, reviewed selected documents, and toured portions of the site to observe work activities including housekeeping, safety practices, fire protection practices, and radiological controls.

2.2 Observations and Findings The inspector conducted tours of the auxiliary, fuel handling, and turbine buildings and observed dismantlement and decommissioning activities in progress. Decommissioning work observed by the inspector during the tour was conducted in a safe and orderly manner. The inspector conducted independent radiological surveys using a Ludlum Model 2401-EC survey meter (NRC No.

21175G, calibration due date July 10, 2008). Radiological controls, including postings and barriers, were observed by the inspector to be in place. Good housekeeping and fire protection practices were implemented by the licensee in the areas toured by the inspector.

The reactor building concrete and steel removal project was in progress. As of October 9, 2007, approximately 11.4 million pounds of concrete and steel had been removed by the contractor and approximately 6.2 million pounds had been packaged for shipment to a low level radioactive waste disposal site. The licensee estimated that an additional 24.5 million pounds remained at the site to be demolished. This decommissioning project continues with the licensee and contractors staff working two ten hour shifts Monday through Friday. The inspector noted that 7 of the 30 rail shipments of concrete and steel planned by the licensee had occurred at the time of this inspection. When question by the inspector about the status of the reactor building concrete and steel removal project, the licensee indicated the project was expected to be completed by April 30, 2008.

In the fuel handling building, remediation continued with the licensee removing from 1/4 to 4 inches of contaminated concrete from the wall surfaces. The licensee projected that it would complete remediation of the fuel handling building by December 1, 2007.

The licensee continued to make final status surveys in the lower levels of the auxiliary building and in outside areas of the site. As of October 19, 2007, final status surveys in 159 of the 284 designated survey units had been completed.

The final status survey data was collected by the licensee, required-5- Enclosure

investigations of survey units were conducted, and the data was evaluated. At the time of this inspection, the database validation effort was ongoing. The Dismantlement Superintendent - Radiological when interviewed by the inspector stated that the Ranch Seco staff would be prepared to submit the first set of final status surveys to the NRC shortly after the NRC approves the License Termination Plan (LTP).

At the time of this inspection, concrete removal from the South and North waste water basins had been completed and the packaging and disposal of the concrete was scheduled to be completed by November 15, 2007.

The licensee plans to complete dismantlement and remediation of the reactor building by April 30, 2008. The licensee anticipates that the last of the final status surveys will be completed by the end of September 2008, and the last final status survey report will be submitted to the NRC by the end of October 2008.

2.3 Conclusion The licensee continued to dismantle and remove contaminated components and to remediate contaminated surfaces in a safe manner. Final status surveys had been completed on 159 of 284 survey units.

3 Inspection of Final Surveys (IP 83801)

3.1 Inspection Scope Independent confirmatory radiological measurements were performed on imbedded piping in the turbine building and on surfaces of the auxiliary building.

One soil sample was collected from the retention basin area.

3.2 Observations and Findings On April 12, 2006, the licensee submitted their LTP to NRC. This LTP included proposed Derived Concentration Guide Lines (DCGLs) for meeting the public dose limits after license termination. At the time of this inspection, the LTP was under review by the NRC and the DCGLs proposed by the licensee had not been accepted by NRC. The licensee recognized that the DCGLs had not yet been approved by the NRC, but had started conducting final status surveys with the expectations that the DCGLs would be approved.

Representatives from the ORISE working as a contractor for the NRC reviewed records of final status surveys on imbedded piping in the turbine building and on surfaces of the auxiliary building. The ORISE personnel conducted independent confirmatory radiological measurements of selected locations and compared their survey results with the licensee. In addition, a soil sample was collected from the retention basin area and sent to ORISE for independent evaluation. The results of these surveys will be reported at a later date in a separate addendum to this report.

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3.3 Conclusion Confirmatory measurements on imbedded piping the turbine building and on selected surfaces of the auxiliary building were conducted by the ORISE staff.

One soil sample was collected from the retention basin area and sent for analysis. The results of these surveys will be reported at a later date in a separate addendum to this report.

4. Solid Radwaste Management and Transportation of Radioactive Materials (IP 86750)

4.1 Audits and Surveillances a. Inspection Scope The inspector reviewed the audits and surveillances made by the licensee of the solid radwaste management and transportation of radioactive materials programs.

b. Observations and Findings No licensee audits had been performed related to the solid radwaste management and transportation of radioactive materials programs since the licensee was last inspected in November 2006. The last audit was conducted in the May -June 2006 time frame with the next schedule audit of this subject area scheduled by the licensee in calendar year (CY) 2008.

In CY 2006, 26 audit surveillances had been conducted by the licensee with 18 being related to radioactive waste, shipments of radioactive waste material, and disposal or processing site visits. As of October 15, 2007, 22 audit surveillances had been conducted with 14 related to these areas. The inspector selected five audit surveillance reports for review: 06-S-25, 06-S-26, 07-S-012, 07-S014, and 07-S-01. None of the surveillance reports reviewed by the inspector identified any problems or made any recommendations.

c. Conclusions Audits and surveillances of the transportation of radioactive materials were performance-based and was determined by the inspector to be complete. The overall quality of the audits and surveillances met the NRCs expectations.

4.2 Changes in the programs a. Inspection Scope The inspector interviewed cognizant personnel and reviewed selected documents to determine if any major changes had occurred since the last inspection in organization, personnel, facilities, equipment, programs, and procedures that may have affected the solid waste management and transportation of radioactive materials program.

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b. Observations and Findings The Principal Decommissioning Radiological Engineer stated that the majority of his time was focused on the solid waste management and transportation of radioactive materials program. The inspector noted that the program had one less radioactive waste handling technician than was assigned during the previous inspection. Three procedures related to the solid waste management and transportation of radioactive materials program had been revised and are listed in the Attachment to this report. No other changes since the last inspection had occurred on the solid waste management and transportation of radioactive materials program.

c. Conclusions Changes to the licensees organization, personnel, facilities, equipment, programs, and procedures had not negatively effected the solid waste management and transportation of radioactive materials program.

4.3 Training a. Inspection Scope The inspector interviewed cognizant personnel and reviewed selected documents to determine if all personnel involved in the transfer, packaging and transport of radioactive waste and transportation of other radioactive materials had received initial training and periodic retraining in the DOT and NRC regulatory requirements, the waste burial license requirements, and in the instructions and operating procedures.

b. Observations and Findings Procedure RP.309, Radioactive Waste Control Program, last revised on May 10, 2007, included descriptions of the training required for each type of worker involved in the transfer, packaging, and transport of radioactive materials. These descriptions of the required training were reviewed by the inspector and were determined to be consistent with the requirements of DOT regulations. The training required by the revised procedure included general awareness, safety, security, and function specific training. The revised procedure designated three function specific training modules RW1, RW2, and RW3 for the different worker classifications. The procedure also specified that function specific training be completed within 90 days of employment or if a change in job function had occurred. With the exception of an RP Technician that was recently assigned to the group, all workers involved in the transfer, packaging and transport had received the required initial training and retraining. The new RP Technician was expected to complete the job specific training within 90 days of his assignment.

c. Conclusions Personnel involved in the transfer, packaging and transport of radioactive waste and transportation of other radioactive materials had received initial training and periodic retraining.

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4.4 Implementation of the Solid Radioactive Waste Program a. Inspection Scope The inspector interviewed cognizant personnel and review selected documents to determine if the licensee had maintained copies of the applicable regulations and licenses of recipients of radioactive materials shipped from the site.

b. Observations and Findings The licensee maintained paper copies of the applicable regulation and also had access to electronic copies of the NRC, DOT and States of South Carolina, Tennessee, and Utah regulations. The inspector confirmed that the licensee had copies of the licenses for all recipients of radioactive materials shipped from the site since this area was last inspected in CY 2006.

c. Conclusions The licensee maintained copies of the applicable regulations and the licenses of the recipients of radioactive materials that were shipped from the site.

4.5 Shipping of Low Level Radioactive Waste for Disposal, and Transportation of Other Radioactive Materials a. Inspection Scope The inspector observed portions of rail road and tractor trailer shipments of radioactive waste being shipped from the site to a waste disposal site. The inspector reviewed the shipping records of radioactive materials shipments made from the site.

b. Observations and Findings On October 17, 2007, the inspector observed the departure of a rail shipment containing debris from the demolition of the concrete and steel structures inside the reactor building. These shipments were made by the contractor conducting the dismantlement of the reactor building. No discrepancies of NRC and DOT regulations were observed by the inspector for this rail shipment. On October 18, 2007, four tractor trailers shipments (shipments numbers07-160, 07-161,07-162, and 07-163). were observed by the inspector departing from the site. The inspector noted that the licensees personnel had followed a written check list which included confirming the proper loading, blocking and bracing, marking, and labeling of the packages and the use of placarding, as appropriate. Direct radiation surveys were made by the licensees personnel. No discrepancies of NRC or DOT regulations were observed by the inspector on these four tractor trailer shipments.

As of October 18, 2007, 163 shipments of radioactive materials had been made in CY 2007. In CY 2006, 62 shipments of radioactive materials were made by-9- Enclosure

the licensee. The inspector selected the records of five shipments to review,07-011, 07-055,07-117, 07-161, and 07-163. Each shipping record reviewed by the inspector included a copy, as applicable, of the radiological surveys conducted by the licensees staff, NRC Form 540, Uniform Low-Level Radioactive Waste Manifest for each shipment, emergency response information as required, instructions provided to the carrier for maintenance and control of a exclusive use shipment, and a special nuclear material exemption certificate. The emergency response number listed on the waste manifest was confirmed by the inspector as the telephone number used by the Rancho Seco secondary alarm station.

Documents requiring shipper certification were signed by an authorized licensee representative. The inspector confirmed that the individuals involved with these shipments had received the appropriate training required by 49 CFR 172, Subpart H.

The Principal Decommissioning Radiological Engineer stated that during the time frame covered by the inspection the licensee had not received any notices of noncompliance from DOT or other competent State authorities.

c. Conclusions The licensee had implemented a transportation program for radioactive materials in accordance with NRC and the DOT regulations.

5 Exit Meeting Summary The inspector presented the inspection results to the acting plant manager and other members of licensee staff at the exit meeting on October 18, 2007. The licensee did not identify any information provided to, or reviewed by, the inspector as proprietary.

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PARTIAL LIST OF PERSONS CONTACTED Sacramento Municipal Utility District M. Bua, Radiation Protection/Chemistry Superintendent L. England, Coordinator, Project Controls Decommissioning J. Field, Engineering Superintendent W. Hawley, Dismantlement Superintendent - Operations L. Hoist, Nuclear Document Control Supervisor R. Jones, Supervising Quality Engineer, Acting Plant Manager D. Koontz, ISFSI Supervisor L. Langley, Security Specialist G. Pillsbury, Lead Radiological Engineer S. Redeker, Manager, Nuclear Plant Closure and Decommissioning (Plant Manager)

J. Roberts, Maintenance Superintendent E. Ronningen, Dismantlement Superintendent - Radiological M. Snyder, Principal Decommissioning Radiological Engineer INSPECTION PROCEDURES USED IP 62801 Maintenance and Surveillance IP 71801 Decommissioning Performance and Status Review IP 83801 Inspections of Final Surveys 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 CY Calendar Year DCGLs Derived Concentration Guide Lines DOT US Department of Transportation ISFSI Independent Spent Fuel Storage Installation LTP License Termination Plan ORISE Oak Ridge Institute for Science Education SSC Structures, Systems or Components Attachment

PARTIAL LIST OF DOCUMENTS REVIEWED Audits and Surveillances

• Audit Log, 2006.

• Audit Log, 2007 as of October 15, 2007.

• Surveillance Log, 2006.

• Surveillance Log, 2007 through October 15, 2007.

• Surveillance report 06-S-025, approved September 28, 2006.

• Surveillance report 06-S-025, approved September 28, 2006.

• Surveillance report 06-S-026, approved November 16, 2006.

• Surveillance report 07-S-012, approved April 19, 2007.

• Surveillance report 07-S-014, approved May 3, 2007.

• Surveillance report 07-S-019, approved July 12, 2007.

Correspondences and Memorandums

• Watts Happening, October 8, 2007 issue.

• Correspondence dated October 10, 2007, from James Allen, Project Manager, Duratek to Wayne Hawley, SMUD, subject Monthly Progress Report.

Data Sheets

• 2006 Radioactive Material Shipment Index.

• 2007 Radioactive Material Shipment Index, as of October 18, 2007.

• Radioactive Shipment 07-011 file.

• Radioactive Shipment 07-055 file.

• Radioactive Shipment 07-117 file.

• Radioactive Shipment 07-161 file.

• Radioactive Shipment 07-163 file.

• Training Information Management System Employee Report Card for Michael Snyder as of October 18, 2007.

-2- Attachment

• Training Information Management System Employee Report Card for Paul Melendy as of October 18, 2007.

• Training Information Management System Employee Report Card for Tom Imura as of October 18, 2007.

• Training Information Management System Employee Report Card for Donald Russell as of October 18, 2007.

• Training Information Management System Employee Report Card for David G Gonzales as of October 18, 2007.

• Training Information Management System Employee Report Card for Ramon Gonzales as of October 18, 2007.

• Training Information Management System Employee Report Card for Mark J Star as of October 18, 2007.

• Training Information Management System Employee Report Card for Karl C Johnson as of October 18, 2007.

Procedures

• Decommissioning Survey Implementing Procedure DSIP-0310, Surface Soil, Subsurface Soil, and other Bulk Media Sampling and Preparation, Revision 1, effective April 19, 2007.

• Radwaste Control Manual RP.309, Radioactive Waste Control Program, Revision 3, effective May 10, 2007.

• Radwaste Control Manual RP.309.I.03, Radioactive Waste Classification and Waste Form, Revision 11, effective April 16, 2007.

• Radwaste Control Manual RP.309.I.06, Curie Calculation, Revision 3, effective January 8, 2007.

• Radwaste Control Manual RP.309.II.02, Container Inspection, Selection and Radioactive Material Packaging, Revision 11, effective September 25, 2007.

Reports

• Master Surveillance Schedule by Due Date, dated October 17, 2007.

• Master Routine Tests Schedule by Department, date October 15, 2007.

-3- Attachment