IR 05000312/2006002

IR 05000312-06-002, on 06/05-08/2006, Rancho Seco

ML061860673
Person / Time
Site:	Rancho Seco
Issue date:	07/05/2006
From:	Spitzberg D B NRC/RGN-IV/DNMS/FCDB
To:	Shetler J Sacramento Municipal Utility District (SMUD)
References
IR-06-002
Download: ML061860673 (18)

Text

July 5, 2006

Mr. James Shetler, Assistant General ManagerEnergy Supply Sacramento Municipal Utility District 6201 'S' Street P.O. Box 15830 Sacramento, California 95852

SUBJECT: NRC INSPECTION REPORT 050-00312/06-002

Dear Mr. Shetler:

An NRC inspection was conducted on June 5 through 8, 2006, at your Rancho Seco NuclearGenerating Station. At the conclusion of the site visit, an exit briefing was conducted with theacting Plant Manager and other members of your staff. Subsequent to the site visit, on June 22, 2006, the inspector telephonically contacted the Plant Manager to provide additionalinformation regarding the inspection findings. The enclosed report presents the scope and results of the inspection. The inspection was an examination of activities conducted under your license as they relate tosafety and compliance with the Commission's rules and regulations and with the conditions of your license. Within these areas, the inspection included reviews of your auditing and corrective action program; maintenance and surveillance; decommissioning performance andstatus review; occupational radiation exposure; and final surveys. In addition, the staff from the Oak Ridge Institute for Science and Education (ORISE) conducted confirmatory radiation measurements. During this inspection, a violation of 10 CFR 20.2001 related to the improper disposal of a small amount of licensed material was reviewed. This non-repetitive and licensee corrected violation is being treated as a Non-Cited Violation, consistent with Section VI.A.8 ofthe NRC Enforcement Policy.In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, itsenclosure, and your response (if any) will be made available electronically for public inspectionin 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) 860-8191.

Sincerely,/RA/D. Blair Spitzberg, Ph.D., ChiefFuel Cycle and Decommissioning BranchDocket No.: 050-00312License No.: DPR-54

Enclosure:

NRC Inspection Report 050-00312/06-002cc w/enclosure:Thomas A. Baxter, Esq.

Shaw, Pittman, Potts & Trowbridge 2300 N. Street, N.W.

Washington, DC 20037QA/Licensing SuperintendentRancho Seco Nuclear Generating Station 14440 Twin Cities Road Herald, CA 95638-9799Sacramento County Board of Supervisors 700 H. Street, Suite 2450 Sacramento, CA 95814Assistant General CounselSacramento Municipal Utility District 6201 S Street P.O. Box 15830 Sacramento, CA 95852-1830Radiation Program DirectorCalifornia Radiologic Health Branch State Department of Health Services P.O. Box 997414 (MS 7610)

Sacramento, CA 95899-7414 Sacramento Municipal Utility District- 3 -Site Document Control SupervisorSacramento Municipal Utility District Rancho Seco Nuclear Generating Station 14440 Twin Cities Road Herald, CA 95638-9799Commissioner's OfficeCalifornia Energy Commission 1516 Ninth Street (MS 34)

Sacramento, CA 95814-5512 Sacramento Municipal Utility District- 4 -bcc w/enclosure (via ADAMS distribution):LDWert CLCain JBHickmnan, NRR/DLPM/PDIV-2ACMcMurray, NRR/D SSA/SPLBDBSpitzberg EMGarcia SPAtwater KEGardin FCDB FileSUNSI Review Complete: EMGADAMS: OYes GNo Initials: EMG OPublicly Available GNon-Publicly Available GSensitive ONon-SensitiveDOCUMENT NAME: s:\dnms\!fcdb\!emg\rs0602.wpdfinal r:\_RS\2006\ RIV:DNMS:FCDBC:FCDBEMGarcia (via e-mail)DBSpitzberg/RA DBSpitzberg for//RA/07/05/0607/05/06OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax ENCLOSUREU.S. NUCLEAR REGULATORY COMMISSION REGION IV Docket No.:050-00312 License No.:DPR-54 Report No.:050-00312/06-002 Licensee:Sacramento Municipal Utility DistrictFacility:Rancho Seco Nuclear Generating StationLocation:14440 Twin Cities Road Herald, California Dates:June 5 through 8, 2006 Inspector:Emilio M. Garcia, Health Physicist Approved By:D. Blair Spitzberg, Ph.D., ChiefFuel Cycle and Decommissioning Branch

Attachments:

Supplemental InformationPartial List of Documents Reviewed

-2-EXECUTIVE SUMMARYRancho Seco Nuclear Generating StationNRC Inspection Reports 050-00312/06-002This inspection was a routine, announced inspection of decommissioning activities beingconducted at the Rancho Seco Nuclear Generating Station. Areas inspected included self-assessment, auditing and corrective action; maintenance and surveillance; decommissioningperformance and status review; occupational radiation exposure; and final surveys. Self-assessment, Auditing and Corrective Action *The licensee was effectively maintaining their Corrective Action Program to control theidentification, evaluation, and resolution of problems. Audits conducted in calendar year 2005 and scheduled for calendar year 2006 addressed all facility activities required to beaudited. All lead auditors for calendar years 2005 and 2006 audits met qualification requirements (Section 1). Maintenance and Surveillances*The licensee no longer had any safety-related structures, systems or components. Thelicensee continued to maintain their liquid effluent monitor. Checks and calibrations ofthe liquid effluent monitor had been conducted at the required intervals (Section 2).Decommissioning Performance and Status Review*The licensee continued the dismantlement and removal of contaminated components ina safe manner (Section 3).Occupational Radiation Exposure*A violation of 10 CFR 20.2001 was identified related to the unauthorized disposal of asmall amount of contamination on an article of personal clothing which was later detected by another licensee. In accordance with NRC guidance, this non-repetitive,licensee corrected violation is documented as a non-cited violation (Section 4).Inspections of Final Surveys*Confirmatory measurements of the dome of the containment building and previouslycollected soil samples were conducted by the staff of the Oak Ridge Institute for Science Education, contractors to the NRC. The results of these surveys will be reported in a later separate addendum to this report (Section 5)

-3-Report DetailsSummary of Facility StatusThe Rancho Seco Nuclear Generating Station was permanently shut down in June 1989. Allspent 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 Seco's Post Shutdown Decommissioning Activities Report dated March 20, 1997. Decommissioning work activities included the auxiliary building, reactor building, spent fuelbuilding 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 drain tank, and the two steam generators had been removed, packaged and shipped offsite for disposal. In the fuel handling building, the spent fuel pool water had been processed and released. The pool liner plates had been cut, removed and shipped for disposal. During this inspection, the reactor vessel internals segmentation project was being completed. All cuts had been made and segments packaged. Segmentation pool water cleanup was in progress.1Self-assessment, Auditing, and Corrective Action (IP 40801)

1.1Inspection ScopeThe inspector reviewed the licensee's administrative procedures that control theidentification, evaluation, and resolution of problems; the Quality Assurance (QA) Plan;and other controlled documents for the conduct of QA audits and surveillances. Theinspector also reviewed the licensee's QA audit organization, staffing, and qualifications. 1.2Observations and Findings a.Identification, Evaluation, and Resolution of ProblemsThe licensee's program for the resolution of non-conformances, material orprogrammatic deficiencies, or conditions adverse to quality or safety remained as described in Section 1.2a of Inspection Report 50-312/2002-004, Section 2.2a of Inspection Report 50-312/2003-004 and Section 1.2 of Inspection Report 50-312/2005-002. This program was called the Rancho Seco Corrective Action Program. Table 1 lists the applicable procedures of the Corrective Action Program.

Two of these procedures had been revised since this area was last inspected in May 2005: Rancho Seco Administrative Procedure (RSAP)-0206, Commitment Management Review Group & Compliance Management Tracking System and RSAP-1301, Corrective Action Program.

-4-RSAP-0260 was revised to incorporate the District-wide compliance managementtracking system, and to revise definitions, responsibilities, and forms to be used with thenew system. RSAP-1301 was revised for minor editorial changes to improve clarity and to removeand update out-of-date reverences. These changes did not diminish the licensee's program for the identification, evaluation, and resolution of safety related problems.Table 1Rancho Seco Corrective Action Program ProceduresNumberTitleRev.EffectiveRSAP-0102Stop Work Order6Mar 03, 1994 RASP-0260Commitment Management Review Group and CommitmentTracking Systems13Jan 09, 2006RSAP-1301Corrective Action Program6Sep 14, 2005RSAP-1305Corrective Action Request3Dec 09, 1993RSAP 1308Potential Deviation from Quality17Feb 13, 2003RSAP-1310Deviation from Quality8Sep 24, 2002In calendar year 2005, 27 Potential Deviation from Quality (PDQ) reports were initiatedand 2 out of these 27 were determined to be a Deviation from Quality (DQ). No Corrective Action Requests or Stop Work Orders were initiated in calendar year 2005.

As of June 8, 2006, 14 PDQs had been initiated during the calendar year with 3 of the 14 determined to be Deviation from Quality. One was pending review. No Corrective Action Request or Stop Work Orders had been initiated in 2006. The inspector reviewed the list of PDQs and DQs that remained open. There were 11 open items, including 3 opened in 2006. The oldest item was from calendar year 2004. The inspector concluded that the licensee was appropriately addressing the timely resolutions of these open items. The inspector reviewed selected records of recent Commitment Management ReviewGroup (CMRG) meetings and noted that the meeting frequency and group membershipwas as described in procedure RSAP-0260, Commitment Management Review Group and Commitment Tracking Systems. These records indicated that the CMRG was conducting initial reviews and characterizations of new PDQs. The CMRG was also assigning tasks, establishing priorities and reviewing proposed resolutions for PDQs andother identified problems. The inspector concluded that the licensee was effectively maintaining their Rancho Seco Corrective Action Program to control the identification, evaluation, and resolution of problems. b.QA Audit Organization, Staffing, and QualificationsThe licensee's Quality Assurance Audit Organization and Staffing had changed sincethis area was last inspected in April 2005. The position of Superintendent, Quality Assurance/Licensing/Administration/Training was eliminated as of the end of May 2005,

-5-when the incumbent retired. Responsibilities for leading the QA audit group wasassigned to the Supervising Quality Engineer. Besides the Supervising Quality Engineer there were two other full time auditors and, on occasion, specialists were tasked with leading or participating in audits. Records reviewed indicated that all audits conducted in 2005 and as of June 8, 2006, were led by auditors with current certifications. The inspector reviewed records of audits conducted since this area was last inspected inApril 2005. The licensee had conducted 15 audits in calendar year 2005 and had completed 1 audit in calendar year 2006, with 1 more underway. A total of 10 audits were scheduled to be performed in CY 2006. One of the reports in calendar year 2006 audits had been issued as of the time of the inspection. Audits conducted in calendar year 2005, and to be conducted in calendar year 2006, addressed all 34 facilityactivities listed in Rancho Seco Quality Manual Section XVIII at the required frequency. In calendar year 2005, the licensee had conducted 28 surveillances and as ofJune 8, 2006, the licensee had conducted 15 surveillances in calendar year 2006. Theinspector selected audit reports 05-A-007, 05-A-013 and 06-A-004 and surveillancereports 05-S-017, 06-S-006 and 06-S-012 for review. The inspector confirmed that the audit and surveillances were conducted per the commitments in the Rancho SecoQuality Manual. The individuals that conducted the audit and surveillances wereindependent of the areas being audited. The audits used approved checklists. The audit team personnel were qualified and were authorized to perform the audits or surveillances in the areas audited. The audits and assessments were conducted in a timely manner.1.3ConclusionThe licensee was effectively maintaining their Corrective Action Program to control theidentification, evaluation, and resolution of problems. Audits conducted in calendar year 2005 and scheduled for calendar year 2006 addressed all facility activities required to beaudited. All lead auditors for calendar years 2005 and 2006 audits met qualification requirements.2Maintenance and Surveillance (IP 62801) a.Inspection ScopeThe inspector reviewed the status of required surveillances and testing. The inspectordiscussed this area with the Maintenance Superintendent and reviewed selected records. b.Observations and FindingsWith 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), norany non-safety-related SSC as defined in 10 CFR 50.65(b)(2). The licensee had reviewed their Maintenance Rule procedure and concluded that it was no longer

-6-required with fuel in the ISFSI. With the processing of the water in the spent fuel pool,the potential for significant liquid effluent releases was greatly diminished; however, thelicensee would still need to process water generated from the reactor vessel internalssegmentation and the reactor vessel segmentation. The licensee had opted to maintaintheir liquid effluent radiation monitor. The inspector reviewed the maintenance of liquid effluent radiation monitor, R-15017A. The licensee performed quarterly tests and annual calibrations of this monitor. Records maintained by the licensee indicated that the licensee had performed thesesurveillances at the required intervals. The inspector interviewed the Maintenance Superintendent and reviewed a printout ofthe Rancho Seco Computerized Surveillance Schedule dated June 5, 2006. This document listed the status of surveillances and routine tests. Three routine tests or surveillances were beyond their due dates, but the licensee was pursuing resolution of the problems that caused the delays. None of these tests were related to safety-related structures, systems or components.Major maintenance activities ongoing during the inspection were the repair of themotherboard for the controller of the Y-112 Interim Onsite Storage Building crane and the repair of the A-536 Reactor Building Purge Air Exhaust system. c.ConclusionThe licensee no longer had any safety-related structures, systems or components. Thelicensee continued to maintain their liquid effluent monitor. Checks and calibrations ofthe liquid effluent monitor had been conducted at the required intervals.3Decommissioning Performance and Status Review (IP 71801)

a.Inspection ScopeThe inspector interviewed cognizant personnel, reviewed selected documents andtoured portions of the site to observe work activities including housekeeping, safety practices, fire loading and radiological controls. b.Observations and FindingsThe ISFSI Supervisor briefed the inspector on the status of the canister containing thegreater than Class C (GTCC) waste. The GTCC waste was generated from the segmentation of the reactor vessel internals project. The licensee had loaded the canister with the GTCC basket. The canister contained in the transfer cask had been removed from the segmentation pool, the canister lid had been welded and the canister was under going vacuum drying. Since there was no source of heat in the contents of the canister vacuum drying was progressing slowly. The canister with the GTCC waste would eventually be stored in the ISFSI.

-7-The licensee had completed the segmentation of the reactor vessel internals and hadseparated and packaged the irradiated components into the various waste categories. The Dismantlement Superintendent - Operations briefed the inspector on schedules forreactor vessel segmentation, packaging, disposal, and on concrete removal in the fuel handling and reactor buildings.Tours of the reactor, auxiliary, fuel handling, and turbine buildings were conducted toobserve 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. Good housekeeping and fire protection practices were noted in areas observed. c.ConclusionThe licensee continued the dismantlement and removal of contaminated components ina safe manner.4Occupational Radiation Exposure (IP 83750)

a.Inspection ScopeThe inspector reviewed the circumstances related to a report received by the NRC fromanother licensee involving contamination identified on the clothing of a contractoremployee who last worked at Rancho Seco. b.Observations and FindingsOn March 9, 2006, while performing an entrance whole body count on a contractoremployee, V.C. Summer Nuclear Station staff identified cobalt-60 (Co-60) contaminationon a pair of pants worn by the contractor employee. The contractor employee was last employed by Rancho Seco. When notified by V.C. Summer Nuclear Station of their findings, Rancho Seco staff opened problem report PDQ 06-0007 and conducted an evaluation. This PDQ was elevated to a DQ when reviewed by the Commitment Management Review Group. V. C. Summer staff reported to Rancho Seco that their survey using a small articlemonitor determined that the activity was 19,755 disintegrations per minute (dpm) overthe entire pair of pants. On February 23, 2006, the contractor had completed his workat Rancho Seco. When he last exited the radiologically controlled area the contractor was surveyed by personnel contamination monitor and no detectable contamination wasidentified. The contractor then received an exit whole body count. This whole body count detected Co-60 contamination. The whole body count identified 24.9 nano-curiesof Co-60 or 921.3 dpm. A subsequent whole body count of the individual with his outside clothing removed determined that the contamination was not on the individualbut only on his clothing, most likely his pants. The Rancho Seco staff reviewed the results of the whole body counts and decided that since the individual's clothing hadsuccessfully "passed" the personnel contamination monitor which constitutes the

-8-instrument designed to prevent inappropriate release of licensed material on personalitems, that no further action was required other than to advise the individual to wash his pants. Rancho Seco procedure RP.305.09A exempt from additional monitoring personal items successfully monitored by personnel contamination monitors. Thus, the monitoring of the pants by the whole body counter was not required. Rancho Seco staff did not at the time decontaminate the individual's pants nor confiscate them. At the time of the inspection, the problem report was not closed but the evaluationperformed had concluded that no licensee procedures had been violated. However, the licensee had identified the need to change its established practices to prevent the release of licensed material under these, or similar circumstances. The licensee modified their practice to require that all individuals who had visited their radiological controlled area receive their exit WB count in disposable paper suits and without wearing their personal items of clothing other than their underwear. Also if contamination was identified in any personal item, that item would confiscated and notreleased to the individual until decontaminated. Subsequent to the inspection, onJune 22, 2006, the Radiation Protection Superintendent informed the inspector thatthese practices had now been incorporated into the licensee's procedures.Although the licensee's procedure RP.305.09A exempts from additional monitoringpersonal items successfully monitored by personnel contamination monitors, Rancho Seco, nonetheless, monitored the individual while he was wearing his pants and identified the contamination. Further, Rancho Seco permitted the individual to exit theirrestricted area with detectable licensed material on his pants. This is a violation of 10 CFR 20.2001, disposal of licensed material by an unapproved method. This non-

repetitive, licensee corrected failure satisfies the criteria as a non-cited violation (NCV 050-00312/0601-01).Records maintained by Rancho Seco indicated that their personnel contaminationmonitors had been calibrated using the vendor's procedure at the required frequencies and the instruments were checked weekly with an appropriate radiation source.

Instruments failing the source check were declared inoperable until repairs were completed and they pass the source check. The inspector observed a source check of one of the personnel contamination monitors. c.ConclusionsA violation of 10 CFR 20.2001 was identified related to the unauthorized disposal of asmall amount of contamination on an article of personal clothing which was later detected by another licensee. In accordance with NRC guidance, this non-repetitive,licensee corrected violation is documented as a non-cited violation.

-9-5Inspection of Final Surveys (IP 83801) a.Inspection ScopeIndependent confirmatory radiological measurements were performed on the dome ofcontainment and on historical soil samples previously collected and analyzed by the licensee. The status of onsite disposal was discussed. b.Observations and FindingsOn April 12, 2006, the licensee submitted their License Termination Plan (LTP) to NRC. This LTP included proposed derived concentration guide lines (DCGLs) for meeting the public dose limits after license termination. This LTP was under review by the NRC atthe time of the inspection and the proposed DCGLs had not been accepted by NRC. The licensee recognized that the DCGLs had not yet been approved but had started conducting final status surveys expecting that the DCGLs would be approved.Representatives from the Oak Ridge Institute for Science Education (ORISE) workingfor the NRC reviewed records of final status surveys of the dome of the containment building and conducted independent confirmatory radiological measurements of the dome. In addition six soil samples previously collected and analyzed by the licensee were sent to ORISE for independent evaluation. The results of these surveys will bereported in a separate addendum to this report.The inspector inquired from the Dismantlement Superintendent - Radiological, ifradioactive material had been disposed of by burial onsite. The Dismantlement Superintendent - Radiological stated that based on review of historical documents anddiscussion with personnel, the licensee had determined that no radioactive material had been disposed of by burial onsite. The Dismantlement Superintendent - Radiological stated that although this conclusion was not currently noted on either their Historical SiteAssessment nor their License Termination Plan, he intended to revise at least one of these documents to record this conclusion. c.ConclusionConfirmatory measurements of the dome of the containment building and previouslycollected soils samples were conducted by the staff of the Oak Ridge Institute for Science Education, contractors to the NRC. The results of these surveys will be reported in a later separate addendum to this report.7 Exit Meeting SummaryThe inspector presented the inspection results to the acting plant manager and othermembers of licensee staff at the exit meeting on June 8, 2006. Subsequent to the sitevisit, the inspector contacted the licensee on June 22, 2006, to provide additional information regarding the inspection findings. The licensee did not identify as proprietary any information provided to, or reviewed by, the inspector.

ATTACHMENT 1PARTIAL LIST OF PERSONS CONTACTEDSacramento Municipal Utility DistrictM. Bua, Radiation Protection/Chemistry SuperintendentR. Decker, Final Status Survey Lead Engineer J. Field, Engineering Superintendent W. Hawley, Dismantlement Superintendent - Operations, Acting Plant ManagerR. Jones, Supervising Quality Engineer D. Koontz, ISFSI Supervisor L. Langley, Asset Protection Specialist G. Pillsbury, Final Status Survey Lead EngineerG. Roberts, Maintenance Superintendent E. Ronningen, Dismantlement Superintendent - Radiological P. Terry, EngineringINSPECTION PROCEDURES USEDIP 40801Self-assessment, Auditing and Corrective ActionIP 62801Maintenance and SurveillancesIP 71801Decommissioning Performance and Status Review IP 83801 Inspections of Final SurveysITEMS OPENED, CLOSED, AND DISCUSSED Opened050-00312/0601-01NCVDisposal of a small amount of licensed material by anunauthorized means. Closed050-00312/0601-01NCVDisposal of a small amount of licensed material by anunauthorized means. DiscussedNone

-2-LIST OF ACRONYMSCFRCode of Federal RegulationsCMRG Commitment Management Review Group Co-60Cobalt-60 CTSCommitment Tracking System DCGLsDerived Concentration Guide Lines dpmDisintegrations per Minute DQDeviation from Quality GTCC Greater than Class C IPInspection Procedure ISFSI Independent Spent Fuel Storage Installation LTP License Termination Plan ORISEOak Ridge Institute for Science Education PDQ Potential Deviation from Quality QAQuality Assurance RSAPRancho Seco Administrative Procedure RSQMRancho Seco Quality Manual SSC Structures, Systems or Components ATTACHMENT 2PARTIAL LIST OF DOCUMENTS REVIEWEDAudits and Surveillances*2005 Surveillance Log*2006 Surveillance Log as of June 8, 2006.*2006 Quality Audit Schedule, dated December 20, 2005.

• 2005 Quality Audit Log

• 2006 Quality Audit Log as of June 8, 2006.

• Rancho Seco Audit Report No. 05-A-007, Rancho Seco Quality Assurance and AuditProgram, Audit dates June 21 through July 27, 2005. Report dated August 4, 2005.*Rancho Seco Audit Report No. 05-A-013, Fire Protection, Audit dates October 30through December 28, 2005. Report dated January 25, 2006.*Rancho Seco Audit Report No. 06-A-004, Control of purchased Material, Equipment,and Services Handling, Shipping, and Storag, Audit dates February 23 through March 28, 2006. Report dated March 30, 2006.*Surveillance Report 05-S-017, Objective: Witness calibration of SMUD CTE-27705Theodolite at California Surveying & Drafting Supply, Inc. Surveillance periodSeptember 30, 2005.*Surveillance Report 06-S-006, Objective: Verify lack of foreign debris inside the GTCCbasket and verify that the GTCC basket lid is installed properly. Surveillance periodFebruary 7, 2006.*Surveillance Report 06-S-012, Objective: Verify that surveys in the upper parking lot arewere performed in accordance with the referenced instructions and procedures.

Surveillance period May 17, 2006.*Lead Auditor Certification records for Robert E. Jones, Michael L. Braum, Glenn RlHoward, Richard Mannheimer and Wayne Thomas.Data Sheets*Potential Deviation from Quality Log, 2005 and 2006 through June 8, 2006.*Rancho Seco Work Order 18013180, A-536 Reactor Building Purge Air Exhaust. As ofJune 6, 2006.*Rancho Seco Work Order 18013300, A-536 Reactor Building Purge Air Exhaust. As ofJune 6, 2006.

-2-*Rancho Seco Computerized Surveillance Schedule printout as of June 6, 2006.*SP.418A, Quarterly Test of Liquid Effluent Radiation Monitor (R-15017A), performedDecember 5, 2005.*SP.418A, Quarterly Test of Liquid Effluent Radiation Monitor (R-15017A), performedDecember 8, 2005.*SP.418A, Quarterly Test of Liquid Effluent Radiation Monitor (R-15017A), performedMarch 14, 2006.*SP.418A, Quarterly Test of Liquid Effluent Radiation Monitor (R-15017A), performedJune 1, 2006.*Deviation from Quality 06-0007, Release of worker's clothing after identifying Co-60contamination during exit whole body count, and associated records as of June 14, 2006.Meeting Minutes*CMRG Meeting Held on February 9, 2005.

• CMRG Meeting Held on April 27, 2005.

• CMRG Meeting Held on June 30, 2005.

• CMRG Meeting Held on July 27, 2005.

• CMRG Meeting Held on August 3, 2005.

• CMRG Meeting Held on September 14, 2005.

• CMRG Meeting Held on October 12, 2005.

• CMRG Meeting Held on February 14, 2006.

• CMRG Meeting Held on February 23, 2006.

• CMRG Meeting Held on April 12, 2006.

Procedures*Rancho Seco Administrative Procedure RSAP-0260, Commitment Management ReviewGroup & Compliance Management Tracking System, Revision 13, effective January 9, 2006.

-3-*Rancho Seco Administrative Procedure RSAP-1301, Corrective Action Program,Revision 6, effective September 14, 2005.