IR 05000312/2006004
| ML063400133 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/06/2006 |
| From: | Spitzberg D NRC/RGN-IV/DNMS/FCDB |
| To: | Shetler J Sacramento Municipal Utility District (SMUD) |
| References | |
| IR-06-004 | |
| Download: ML063400133 (34) | |
Text
UNITED STATES NUCLEAR REGULATORY C O M M I S S I O N ber 6, 2006
SUBJECT:
NRC INSPECTION REPORT 050-00312/06-004
Dear Mr. Shetler:
An NRC inspection was conducted on November 13 through 16, 2006, at your Rancho Seco Nuclear Generating Station. At the conclusion of the site visit, an exit briefing was conducted with the acting Plant Manager and other members of your staff. 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 to safety 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 maintenance and surveillance program; decommissioning performance, and solid radioactive waste management and transportation of radioactive materials.
Also enclosed is a copy of the Oak Ridge Institute for Science and Education (ORISE) report on the confirmatory survey results for the Reactor Building Dome upper structural surfaces.
ORISE is the NRC contractor laboratory for radiological measurements. This confirmatory survey was conducted on June 7 and 8, 2006. The ORISE independent measurements confirmed that the radiological conditions of the upper structural surfaces of the Reactor Building Dome meet the site-specific release criteria as presented in your license termination plan.
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:llwww.nrc.aov/readina-rm/Adams.html. To the extent possible, your response, if any, 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 concernin'g this inspection, please contact Mr. Emilio Garcia, Health Physicist, at (530) 756-391 0 or the undersigned at (817) 860-81 91.
Sincerely, D. Blair Spitzberg, Ph.D., Chief Fuel Cycle and Decommissioning Branch Docket No.: 050-00312 License No.: DPR-54
Enclosures:
1. NRC Inspection Report 050-00312/06-004 2. ORISE Report RFTA NO.06-003
REGION IV==
Docket No.: 050-00312 License No.: DPR-54 Report No.: 050-00312/06-004 Licensee: Sacramento Municipal Utility District Facility: Rancho Seco Nuclear Generating Station Location: 14440 Twin Cities Road Herald, California Dates: November 13-16, 2006 Inspector: Emilio M. Garcia, Health Physicist Accompanied D. Blair Spitzberg, Ph.D., Chief and Approved By: Fuel Cycle and Decommissioning Branch Attachments: Supplemental Information Partial List of Documents Reviewed
-2-EXECUTIVE SUMMARY Rancho Seco Nuclear Generating Station NRC Inspection Reports 050-00312/06-004 This inspection was a routine, announced inspection of decommissioning activities being conducted at the Rancho Seco Nuclear Generating Station. Areas inspected included the maintenance and surveillance program; decommissioning performance and solid radioactive waste management and transportation of radioactive materials.
Maintenance and Surveillance
. The licensee no longer had any safety-related structures, systems or components. The licensee continued to maintain their liquid effluent monitor. Checks and calibrations of the liquid effluent monitor had been conducted at the required intervals (Section I).
Decommissioning Performance and Status Review The licensee continued the dismantlement and removal of contaminated components in a safe manner (Section 2).
Solid Radioactive Waste Management and Transportation of Radioactive Materials Audits and Surveillances of the solid radioactive waste management and transportation of radioactive materials program were performance-based, and their overall quality was good. The licensee had an effective program for identifying and correcting deficiencies or weaknesses related to the solid radioactive waste management and transportation of radioactive materials program (Section 3).
. Changes to the licensees organization, personnel, equipment, and procedures had not negatively affected the solid radwaste management and transportation of radioactive materials program (Section 3).
Individuals responsible for processing, testing, storage, and shipping (including certification) of low level radioactive waste and other radioactive materials had received the initial required training (Section 3).
The licensee maintained copies of the applicable regulations and the licenses of recipients of radioactive materials, and had identified those individuals authorized to certify low level radioactive waste shipments (Section 3).
. 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 3).
-3-Inspection of Final Survevs
. The NRC contractors independent measurements of the upper structural surfaces of the Reactor Building Dome confirmed that the radiological conditions meet the site-specific release criteria as presented in the license termination plan submitted by the licensee and currently under NRC review. The results of radiological measurements of soil samples made by the NRC contractor laboratory were in agreement with results obtained by the licensee laboratory on the same samples (Section 4).
-4-Reoort 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/or 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 the two steam generators had been removed, packaged and shipped offsite for disposal.
In the fuel handling building, the spent fuel pool (SFP) water had been processed and released.
The pool liner plates had been cut, removed and shipped for disposal. Contaminated portions of concrete in the SFP were being removed. The reactor vessel internals had been segmented, packaged and either shipped for disposal or stored onsite. During this inspection the reactor vessel was undergoing segmentation.
1 Maintenance and Surveillance (IP 62801)
a. Inspection Scope The inspector reviewed the status of required Surveillance and testing. The inspector discussed this area with the Maintenance Superintendent and reviewed selected records.
b. 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)(I), nor any 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 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, the licensee would still need to process water generated from the reactor vessel internals segmentation and the reactor vessel segmentation. The licensee had opted to maintain their liquid effluent radiation monitor.
The inspector reviewed the maintenance of a liquid effluent radiation monitor, R-15017A. The licensee performed quarterly tests and annual calibrations of this monitor. Records maintained indicated that the licensee had performed these Surveillances at the required intervals.
-5-The inspector interviewed the Maintenance Superintendent and reviewed a printout of the Rancho Seco Computerized Surveillance Schedule dated November 13, 2006.
This document listed the status of Surveillances and routine tests. Seven routine tests or Surveillances were beyond their due dates, but none exceeded their 25% extended schedule period permitted by the surveillance and routine test programs. None of these tests were related to safety-related structures, systems or components.
c. Conclusion The licensee no longer had any safety-related structures, systems or components. The licensee continued to maintain their liquid effluent monitor. Checks and calibrations of the liquid effluent monitor had been conducted at the required intervals.
2 Decommissioning Performance and Status Review (IP 71801)
a. Inspection Scope The inspector toured portions of the site to observe work activities including housekeeping, safety practices, fire loading and radiological controls.
b. Observations and Findings The licensee had completed the segmentation of the reactor vessel internals and had separated and packaged the irradiated components into the various waste categories.
These wastes included a canister containing the greater than Class C (GTCC) waste.
The lid on this canister had been welded and the canister vacuum dried. The canister had been stored in the ISFSI. Class B and C containers had been stored on site.
During this inspection the two canisters with Class A waste were shipped to a waste disposal site.
The reactor vessel segmentation was ongoing during this inspection. This process continued without any personnel or equipment contaminations.
Tours of the reactor, auxiliary, fuel handling, and turbine buildings 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. Good housekeeping and fire protection practices were noted in areas observed.
c. Conclusion The licensee continued the dismantlement and removal of contaminated components in a safe manner.
3 Solid Radioactive Waste Management and Transportation of Radioactive Materials (IP86750)
-6-3. I Audits and Surveillances a. Inspection Scope The inspector reviewed reports of recently conducted Audits and Surveillances to determine implementation of the commitments made in the Section XVIII, Audits, of the Rancho Seco Quality Manual (RSQM), as it relates to the solid radioactive waste management and transportation of radioactive materials program. The inspector also reviewed the qualification records for the individual involved in the audit and surveillance.
b. Observations and Findings The inspector reviewed audit report 06-AOO7, dated July 11, 2006. This audit focused on wet and dry waste processing and the packaging and transportation of radioactive waste. This audit had been conducted from May 24 through June 21 , 2006. The inspector confirmed that the audit was conducted according to the commitments in the RSQM. The individual that conducted the audit was independent of the function being audited. The audit included the use of an approved checklist. The auditor was qualified and authorized to perform the audit in the area audited. The audit did not identify any findings, but it included a recommendation for which the licensee had initiated actions to address. The audit was conducted in a timely manner and was overall of good quality.
No other audit of this area had been performed since the last inspection.
The inspector reviewed the licensees surveillance log and noted that in calender year 2005 of the 28 Surveillances that had been conducted, 15 related to radioactive waste and/or shipments. In calender year 2006, as of November 13, of the 25 Surveillances that had been conducted, 18 related to radioactive waste and/or shipments. The inspector selected three Surveillances for review: Surveillance Reports 05-S-028, approved on March 23, 2006; 06-S-017, approved on August 3, 2006; and 06-S-018, approved on August 3, 2006. The individual assigned to perform the Surveillances was trained and qualified and was independent of the areas being audited. The Surveillances included performance-based elements. No quality related problems were identified during the Surveillance related to solid radwaste management and transportation of radioactive materials.
c. Conclusion Audits and Surveillances of the solid radioactive waste management and transportation of radioactive materials program were performance-based, and their overall quality was good. The licensee had an effective program for identifying and correcting deficiencies or weaknesses related to the solid radioactive waste management and transportation of radioactive materials program.
-7-3.2 Changes a. Inspection Scope The inspector interviewed cognizant personnel and reviewed selected documents to determine if any major changes had taken place since the last inspection in the organization, personnel, facilities, equipment, programs or procedures that may have effected the solid radwaste management and transportation of radioactive materials program.
b. Observations and Findings The Principal Decommissioning Radiological Engineer was focusing most of his time on the solid radwaste management and transportation of radioactive materials program.
The position of Radwaste Supervisor was currently being held by a contractor. The Interim Onsite Storage Building (10s) had under gone some upgrades including refurbishing of some doors, painting of walls and the addition of air conditioning. Four procedures related to the solid radwaste management and transportation of radioactive materials program had been revised and are listed in Attachment 2.
c. Conclusions Changes to the licensees organization, personnel, equipment, and procedures had not negatively effected the solid radwaste management and transportation of radioactive materials program.
3.3 Training and Qualifications of Personnel a. Inspection Scope The inspector interviewed cognizant personnel and reviewed selected documents to determine if individuals that were responsible for processing, testing, storage, and shipping (including certification) of low level radioactive waste and other radioactive materials had received training and periodic retraining in the Department of Transportation (DOT) and NRC regulatory requirements, the waste burial license requirements, and in the instructions and operating procedures.
b. Observations and Findings Procedure RP0.309, Radioactive Waste Control Program, last revised in March 2006, included a description of the training required for each type of worker involved in the processing, testing, storage, and shipping of radioactive materials. This description was consistent with requirements of DOT regulations. The description specified general awareness, safety, security, and function specific training. The procedure designated a training module RWO for general awareness, safety and security and function specific into three training modules RWI, RW2, and RW3 for the different worker classifications.
-8-The inspector noted that these module codes were not reflected on the course descriptions that were used in the licensees training information management system (TIME). The inspector also noted that although all workers involved in the processing, testing, storage, and shipping of radioactive materials had received the initial training required by this procedure and DOT regulations, two were overdue for refresher security training. Although the recurrent training had not occurred, the individuals were familiar with their security responsibilities.
The licensee opened problem report P.Q. 06-0030 to address these matters of minor significance.
c. Conclusions Individuals responsible for processing, testing, storage, and shipping (including certification) of low level radioactive waste and other radioactive materials had received the initial required training.
3.4 Implementation of the Solid Radioactive Waste Program a. Inspection Scope The inspector interviewed cognizant personnel and reviewed selected documents to determine if the licensee maintained copies of the applicable regulations and licenses of recipients of radioactive materials shipped from the site, and had identified those individuals authorized to certify low level radioactive waste shipments in accordance with Section II of Appendix F to 10 CAR 20.1001-20.2402.
b. Observations and Findings The licensee maintained paper copies and had access to electronic copies of the NRC, DOT and States of Utah and Tennessee regulations, and had copies of the licenses for the low level radioactive waste disposal site and the materials recovery site to which licensed material were shipped. The licensee issued an annual memorandum to file that identified the individuals, their signatures and their initials that were authorized to certify radioactive shipments. This memorandum also included the names, signature and initials of the individuals authorized to perform quality assurance functions associated with radioactive shipments generated at the site. The inspector reviewed this memorandum dated November 8, 2006.
c. Conclusions The licensee maintained copies of the applicable regulations and the licenses of recipients of radioactive materials, and had identified those individuals authorized to certify low level radioactive waste shipments.
-9-3.5 Shipping of low level radioactive waste for Disposal, and Transportation of other Radioactive Material a. Inspection Scope The inspector observed the loading of a Class A waste container into a transportation cask for shipment to a waste disposal site. The inspector reviewed records of radioactive materials shipments.
b. Observations and Findinns On November 15, 2006, the licensee loaded waste liner MU-806-0149 into a transport cask for shipment to a waste disposal site. This cask contained shipping package RS-RVI-036 which was classified as Class A waste. The inspector noted that the licensees personnel had followed a written check list while conducting the receipt inspection, loading, blocking and bracing, marking and labeling the package and placarding the transport trailer. Direct radiation and contamination surveys were petformed by the licensee personnel through this evolution. The licensee took appropriate precautions to maintain radiological exposure ALARUMS.
As of November 15, 2006, 54 shipments of radioactive material had been made in 2006.
The inspector reviewed three records of these shipments. These were for Shipments06-027, 06-051, and 06-053. The emergency response telephone number listed on the waste manifests was confirmed as the telephone number for the Rancho SCO secondary alarm station. The shipping records included copies of the radiological surveys conducted, Form 540 Uniform Low-Level Radioactive Waste Manifest as applicable, 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 CAR 172, Subpart H.
The Dismantlement Superintendent - Radiological stated that the licensee had not received any notices of noncompliance from DOT or other competent state authorities.
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.
4 Inspection of Final Surveys (IP 83801)
On June 7 and 8, 2006, representatives from the Oak Ridge Institute for Science Education (ORISE) working for 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 seven soil samples previously collected and
-10-analyzed by the licensee were sent to ORISE for independent evaluation. The results of these surveys were reported to the NRC on October 25, 2006.
The ORISE report notes that their survey for the upper structural surfaces of the Reactor Building Dome confirmed that the radiological conditions meet the site-specific release criteria as presented in the license termination plan submitted by the licensee and currently under NRC review. The report also notes that the results of the licensees laboratory analysis on seven soil samples were consistent and in agreement with ORISE analytical results.
A copy of the ORISE report is included as an enclosure.
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 November 16, 2006. 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. But, Radiation Protection/Chemistry Superintendent R. Decker, Final Status Survey Lead Engineer D. Gonzales, Acting Radwaste Supervisor J. Field, Engineering Superintendent W. Hawley, Dismantlement Superintendent - Operations, Acting Plant Manager K. Johnson, Rad Waste Technical Analyst R. Jones, Supervising Quality Engineer D. Koontz, ISFSI Supervisor L. Langley, Asset Protection Specialist S. Redeker, Plant Manager G. Roberts, Maintenance Superintendent E. Ronningen, Dismantlement Superintendent - Radiological M. Steinbacher, Radiation Protection Supervisor INSPECTION PROCEDURES USED IP 62801 Maintenance and Surveillance IP 71801 Decommissioning Performance and Status Review IP 83801 Inspection 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
-2-LIST OF ACRONYMS CAR Code of Federal Regulations DOT Department of Transportation GTCC Greater than Class C IP Inspection Procedure 10s Interim Onsite Storage Building ISFSI Independent Spent Fuel Storage Installation RISE Oak Ridge Institute for Science Education RPO Radiation Protection RSQM Rancho SCO Quality Manual ssc Structures, Systems or Components SFP Spent Fuel Pool TIME Training Information Management System
ATTACHMENT 2 PARTIAL LIST OF DOCUMENTS REVIEWED Audits and Surveillances
. Rancho SCO Audit Report No. 06-A-007, Process Control Program (PCP) + Packaging
& Transportation of Radioactive Waste, Report date July 11, 2006, Audit dates May 24 -
June 21, 2006.
Data Sheets
. Printout of the Rancho SCO Computerized Surveillance Schedule dated November 13, 2006.
. Memorandum to File DPT 06-040, dated November 8, 2006, subject: Signature Authority for Radioactive Shipments.
. Printouts for selected individuals training records maintained in TIME, the training information management system.
. Records file for shipments06-027, 06-051, and 06-053.
Procedures
. Rancho SCO Administrative Procedure RSAP-I 601, Rancho SCO Surveillance Program, Revision 10, effective July 22, 2004.
. Rancho SCO Administrative Procedure RSAP-1605, Routine Test Program, Revision 5, effective August 26, 2002.
. Radiation Control Manual RP0.305.16, Radioactive Material Receipts, Revision 5, effective October 17, 2006.
. Radwaste Control Manual RP0.309, Radioactive Waste Control Program, Revision 2, ary 8, 2006
SUBJECT:
CONFIRMATORY SURVEY RESULTS FOR THE REACTOR BUILDING DOME UPPER S T R U C T U W SURFACES, RANCHO SECO NUCLEAR GENERATING STATION, HERALD, CALIFORNIA (DOCIWT NO. 50-312, RFTA N O .06-003)
Dear A h . I-Iiclaiian:
The Oak lhdge Instihite for Science and Education (ORISE) performed conhinatoiy suivey activities on die Reactor Buildmg Doine Upper Struchiral Surfaces at die Ralicho Seco Nuclear Generating Station in Herald, California on June 7 and S, 2006. Tliese suivey activities were requested and approved by die U.S. Nuclear Regulatoiy Coiniiissioii (NRC). Enclosed are die c o i i f ~ i n a t o isuivey
-~~
results documentbig these suivey activities. The survey activities included beta surface scans, &ect measurements for total net beta activity, and liiiited gross alpha and gtoss beta removable activity measurements.
If you have any questions or comments, please direct diem to me at 565.576.0065 or J. Scott 1G-kat S65.574.0685.
Sincerely, Wade C. Adams I-Iealtli Pliysicist/Project Leader Survey Projects WCA:ar Eiiclosure C: B. Watson, NRC/NI\/ISS/TWFN T-7ElS E. Abelquist, ORISE E. IGiox-Daviii, NRC/NMSS/TVDN SA23 S.I k k , ORISE E. Garcia/NRC/Region IV File/1695 Voice: S65.576.0065 Fax: 565241.3497 E-inad: AdarnsW@orau.gov
CONFIRMATORY SURVEY RESULTS FOR THE REACTOR BUILDING DOME UPPER STRUCTURAL SURFACES RANCHO SECO NUCLEAR GENERATING STATION HERALD, CALIFORNIA INTRODUCTION The Sacramento Muiicipal Utdty District (SMUD) operated tlie Rancho Seco Nuclear Generating Station (RSNGS) froin 1976 to 1989 under Atoiiic Energy Coimiission Docket Number 50-312 aiid License Number DPR-54. In August 1989, SMUD notified the U.S. Nuclear Regulatoiy Coimnission (NRC) tliat tliey sliut down RSNGS permanently. In May 1991, SMUD submitted tlie Rancho Seco Decoimiissioiling Plan wlzicli was approved by tlie NRC in March 1995. SMUD began decoimnissioihg activities in Febivaiy 1997 and completed transfer of all the spent nuclear fuel in August 2002.
RSNGS was a 913-niIWe pressurized water reactor (PUR) designed by Beclitel Power Coiporation.
The plant incoiForated a pressurized mater type nuclear steam supply system (NSSS) supplied by Babcock and Wilcox Company; a turbine generator and electrical systems; engineered safety features; radioactive waste systems; fuel handhig systems; histrunentation and control systems; tlie necessay audalries; and stmctues to house plant systems and otlier onsite facilities.
Due to a public vote die previous day, on June 7, 1989, RSNGS permanently shut down after approximately 14 years of operation. On August 29, 1989, SMUD forlnally notified die NRC of die permanent cessation of operations at tlie RSNGS. SMUD subinitted the Post Shutdown Decoimiissioiing Activities Report (PSDAR), in accordance witli 10 CFR 50.82 (a) (4), 111 AiIarcli 1997. In A p d 2006, SMUD subinitted a license terinkiation plan (LTP) tliat has yet to be approved by tlie NRC (SMUD 2006a). SMUD currently is conducting decoiitainination efforts and performing final status smveys (FSS) in tlie remaining structural surfaces and open land areas.
The NRC requested tliat tlie Oak Ridge Institute for Science and Education (ORISE) perform a confu-matoiy survey of die upper sttuctwal surfaces of die Reactor Budding Dome at tlie RSNGS (Figures 1 aiid 2). Wde on site, tlie NRC site representative also requested tliat ORISE perform interlaboratoiy coinpallison analyses on several arclived soil samples tliat would be provided by RSNGS personnel. The conhnatoiy smveys were performed on June 7 and 8,2006.
PROCEDURES Confirinatoiy surveys were performed in accordance witli a site-specific surTey plan tliat was submitted to and approved by tlie NRC (ORISE 2006a). The site-specific survey plan follows tlie guidance provided in the ORISE Survey Procedures and Quality Assurance Manuals (ORISE 2004 and 2005).
Reactor Dome U m e r Structural Surfaces Due to die dfficulty and hazards associated witli performing hand-held detector surveys of tlie Reactor Bdding Dome, SMUD opted to use tlie Contahinetit Bwldtng Surface Single Nuclide Renovation/Deinolition Scenario derived concentration guideline levels (DCGLs) for surfaces above tlie polar crane rail as described in Table 6-12 of die LTP (SMUD 2006a). In lieu of d m c t Rancho Seco Nuclear Generating Station 1695\Reports\2006-10-25 Confxmatory Survey Results
surface activity ineasureiiient with hand-held ra&ological instrumentation, SMUD chose to perforin in.sits/gaimiia spectcoscopy ineasurements of the doine surfaces (SMUD 2006b). The detector geoinetry for the dome survey was defined as a 28 square meters (in)circular plane wid1 a source to detector distance of 3 ineters (in).Each individual circular plane, also designated as die field-of-view (FOV), was designated at a p d or ineasmeinent location.
SMUD used site-specific suppleinental DCGLs for CO-60and Cs-137 for deterinking surface release c ~ t e r i a(SMUD 2006a and b). ORISE judgmentally selected five grid blocks for conhinatoiy surveys based upon final status survey (FSS) results which approached unity.
Beta surface scans were performed using hand-held gas proportional detectors coupled to rateineter-scalers with audlble indicators. Surface scans were performed on up to 80% of die judgmentally selected grid block surfaces. Particular attention was gveii to cracks, joints, aiid horizontal swfaces in die evaluated structural surfaces wliere material inay have accumulated.
Direct ineasureinents for beta activity were performed at 31 (a ininhim of five locations witlGii each grid) locations on tlie evaluated structural surfaces w l d i were avdable for conhiiiatory survey activities. Smear sainples were collected at tluee du-ect ineasureiiient locations of elevated suxface activity witlin Grid CRC052 to deterinine removable activity levels at these locations. Direct measurements locations are indicated on Figuxes 3 tluougli 7.
Interlaboratoiv ComDarisoii Soil Samples At tlie request of tlie NRC site representative, ORISE was tasked with conducting an interlaboratoiy coinparison to evaluate die quality of tlie licensees radioanalpcal procedures. Therefore, ORISE reviewed RSNGS characterization soil sainple data and selected seven soil samples, collected aiid analyzed by SMUD, for interlaboratoiy coinparison analyses. These samples were slGpped by SMUD personnel and received by ORISE laboratoiy personnel on July 10, 2006.
!?YAMPLEh A L V S I S AND DATA INTERPRETATION Radlological data and sample iiiedia were returned to tlie ORISE laboratoiy in Oak Ridge, T N for analysis and inteiyretation. Raloassays were performed in accordance witli tlie ORISE Laboratoiy Procedures Manual (ORISE 2006b). Soil samples were analyzed by gaimna spectroscopy for tlie pximaiy radionuclides-of-coiicerii [POC @e.,CO-60and Cs-137)]. However, spectra were also reviewed for additional gaimna-emitting fission and activation products associated with tlie RSNGS and otlier identifiable total absorption peaks. Soil sainple results were reported in units of picoculries per grain (pCi/g). Diy smear samples were analyzed for gross alpha and gross beta activity using a low-baclrgound gas proportional counter. Smear results and direct measureinents for total surface activity were converted to uiits of lsintegratioiis per ininute per 100 square centimeters (dpin/ 100 cin) .
FINDINGS AND RESULTS Reactor Dome Surface Activitv Measurements Beta surface scans identified several areas of elevated beta activity on tlie horizontally positioned inetal bracket. The brackets previously connected air conditioning ductworlr to die iiiside surface of tlie reactor buildlng walls. Beta surface scans dld not identify elevated beta activity on tlie vertical Rancho Scco Nuclear Generating Station 2 1695\Rcports\2006-10-25 Confirmatory Survey Results
concrete surfaces of tlie Reactor Building Dome walls. Total net beta activity measurements ranged fkom -13,000 to 410,000 dpiii/lOO cin'. Removable activity nieasureiiieiits ranged fkoin 9 to 26 dpm/lOO ciii' for alpha and 230 to 890 dpin/lOO an' for beta. Surface activity level results are presented in Table 1.
Iiiterlaboratorv Sample kialvses Prior to shipping, SMUD re-analyzed die seven soil sainples selected by ORTSE. The analytical results for die coiiiparative evaluation of die RSNGS characterization samples are provided in Table 2. The results indicate tliat tlie quality of tlie SMUD laboratoiy data, w i t h die parameters of sample preparation and analytical procedures, were comparable witli ORISE's analytical results.
COMPARISON OF CONFIRMATORY SURVEY RESULTS AGAINST THE RELEASE CRITERIA The major contaiihmts identified by SMUD at RSNGS are beta-gaiima emitters-fission and activation products-resulting froin reactor operation. Cesimn-137 and CO-60have been identified during characterization as die predoininant radionuclides present on structural surfaces. SMUD developed site-specific DCGLs (wluch have yet to be approved by tlie NRC) based on dose i n o d e h g not to exceed 25 mem/year total effective dose equivalent (TEDE) as presented in Section 6 of tlie LTP (SMUD 2006a). The DCGLs for swfaces were modified by SMUD to reflect tlie ratio of radionuclide concentrations in tlie specific suivey units (Su> diat were being evaluated.
The applicable surface activity guidehies froin the LTP and decomSssioiing teclmical basis document (DTBD)-05-015 for die stmctwal surfaces above die polar crane in tlie Reactor Budding
-
Dome are as follows (SMUD 2006a and c):
I Derived Concentration Guideline Levels (dpm/100 cm')
Radionuclides Co-60" Cs-137" Gross Betab EMC" DCGL 40,200 182,000 43,000 593,400 All of tlie duect beta activity measurement results on die concrete structural surface walls (vertical surfaces) were well witlin tlie DCGLs for CO-60and Cs-137 as provided in tlie LTP (SMUD 2006a). The 25 duect measurement results (on tlie vertical concrete walls) were also witli.11 die gross beta activity DCGL as determined by SMUD personnel using die LTP and teclmical basis documents (SMUD 2006a,b and c). However, die six direct beta activity measurement locations on the metal brackets tliat exceeded die gross beta activity DCGL were typically less tlian 500 cin'.
SMUD determined two area factors tliat were not independently verified by ORISE, one for Cs-137 wlich was 14.9 and one for CO-60which was 13.8; ORISE used tlie lowest area factor in deterinining tlie elevated measurement comparison (EMC) criteria for a 1 m2 area to be conseivative. Tlis corresponds to a DCGL,, of 593,400 dpm/lOO an2. All of die direct beta Rancho Seco Nuclear Generating Station 3 1695\Reports\2006-10-25 Confirmatory Suiwy Results
surface activity ineasureinents on tlie metal brackets were less tliaii tlie SMUD derived DCGL,,,
for CO-60.
SUMMARY Beta surface scans identified several areas of elevated beta activity on the hollizontal surfaces of die reinair-Litlg metal brackets &tl&i tlie Reactor Budding Dome. Direct ineasureiiients were performed at 31 locations of wlich six locations were on tlie metal brackets; tlie rein&ting locations were on die vertical concrete walls. The 25 du-ect ineasureiiient results on tlie concrete walls (vertical surfaces) were well &tl&i die individual DCGLs for CO-60 and Cs-137 and tlie gross beta activity DCGL for st.mct7Lu.al surfaces. As tlie survey results indicated, hollizontal surfaces, such as on die iiietal brackets, exhibited elevated beta activity levels tliat exceeded die gross beta activity DCGL; however, tliese measurement locations were typically less than 500 ciii2 and were witllii die DCGL,,,, release criteria. Therefore, die results of tlie survey activities for tlie upper stmctural surfaces of the Reactor Btulduig Dome confirmed tliat die radiologcal coiiditioiis meet tlie site-specific release criteria as presented in the licensees LTI.
ORISE performed interlaboratoiy comparison analyses on seven RSNGS cliaractellzation soil samples; tlie results inlcated tliat die quality of tlie SMUD laboratoiy data were coiisisteiit and in agreement witli ORISEs analytical results.
Rancho Seco Nuclear Generatins Station 4 lG95\Reports\2006-10-25 Confumatorp Survey Results
1695-001 (1)
>
N NOT TO SCALE FIGURE 1: Location of Rancho Seco Nuclear Generating Station, Herald, California Rancho Seco Nuciezu G c n e i a h g Stahon 5 1695\Repoits\2006-10-~5 Coiiiumatoiy Suvey Results
16Y.5-902 (I)
I
/ SPRAY PONDS TURBINE BUILDING ISFSI I SWITCHYARD
/
AUXILIARY ADMINISTRATION BUILDING BUILDING NOT TO SCALE FIGURE 2: Plot Plan of the Industrial Area at Rancho Seco Nuclear Generating Station Rancho Seco Nuclear Generating Station 6 1695\Reports\2006-10-25 Confiinatoiy Survey Results
1695-003 (3)
-.,----
/// 5
7 3
Ledge WlEASUREMENT LO CATIONS NOT TO SCALE
- SINGLE-POINT FIGURE 3: Reactor Dome CRCO52 - Measurement Locations Raiicho Seco Nuclear Generating Station 7 1695\Reports\200G-l0-25 Confxrnatoiy Sun-ey Kesdts
1G95-004 (2)
14
MEASUREMENT LOCATIONS N O T TO SCALE if SINGLE-POINT FIGURE 4: Reactor Dome CRCO76 - Measurement Locations Rancho Seco Nuclear Generating Station S 1695\Reports\2006-10-25 Coi&matory Survey ltesults
1695-005 (2)
MEASURE&.NTLOCATIONS NOT TO SCALE iY SINGLE-POINT FIGURE 5: Reactor Dome CRC089- Measurement Locations Rancho Scco Nuclear Generating Station 9 1695\Reports\200G-10-25 ConfumatoT Survey Results
1695006 (2)
/------
\
2s
\\\__ --.----
MEASUREMENT LOCATIONS N O T T O SCALE
$# SINGLE-POINT FIGURE 6 : Reactor Dome CRCll4 - Measurement Locations Rancho Seco Nuclear Generating Station 10 1695\Rcports\2006-10-25 Confimatoiy Survey Results
1695-007 (3)
11 I
Metal Bracket 21,000 cpm Ventilation Bracket 9 Ledge 30,000 cpm Metal Box 52,000 cpm E
c 12 13
\
MEASUREMENT LOCATIONS N O T TO SCALE
- SINGLE-POINT FIGURE 7: Reactor Dome CRC168 - Measurement Locations liancho Seco Nuclear Generating Station 11 161)5\Reports\2006-10-~5Confirmatory S u w y Results
TABLE 1 SURFACE ACTIVITY LEVELS REACTOR D O M E UPPER STRUCTURAL SURFACES RANCHO SECO NUCLEAR GENERATING STATION HERALD, CALIFORNIA Locatioii/Grid Total Beta Activityb Removable Activity (dpm/100 an')
Block" (dpin/IOO cm2)
Alpha Beta 1 79,000 9 230 2 150,000 16 330 3 410,000 26 590 4 -6,800 __ __
5 -5,900 _- __
6 -13,000 __ __
7 -2,soo __ __
S -370 __ __
9 7,500 __ __
10 360 __ __
11 S90 __ __
12 2,700 __ __
~
13 27,000 __ _-
(1 Grid CRC076 14 _- __
13,000 15 12,000 __ __
ir ~~ 16 12.000 17 -590 __ _-
1s 12,000 _- __
19 4.500 __ __
20 2,700 __ _-
21 12,000 __ __
22 -1,800 __ __
23 -520 __ __
~~ ~
Rancho Seco Nucleac Gctieiatuig Station 12 1695\Repoits\200G-10-25Confiiinatoiy Survey Results
TABLE 1 (continued)
SURFACE ACTIVITY LEVELS REACTOR D O M E UPPER STRUCTURAL SURFACES RANCHO SEGO NUCLEAR GENERATING STATION HERALD, CALIFORNIA.
Locatioii/Grid Total Beta Activityb Removable Activity (dpin/100 cm')
B lo cl" (dpm/100 ciii')
Alpha Beta 24 4,000 __ _-
25 9,900 __ __
26 6,400 __ __
27 2,500 __ __
25 2,500 __ __
29 75,000 __ __
30 210,000 __ __
31 280,000 __ __
Rancho Seco Nuclear Generating Station 13 1695\Reports\2006-10-25 Confirmatory Survey Results
TABLE 2 RADIONUCLIDE CONCENTRATIONS INTERLABORATORY COMPARISON SOIL SAMPLES RANCHO SECO NUCLEAR GENERATING STATION HERALD, CALIFORNIA I
Radiomiclide Concentratioii (pCi/g)
Identification i Radioiiuclide SMUD" ONSE i SMUD Previous Current Mil- 54 -0.15 t- 0.15b __ C
__
CO-60 I 1.45 k 0.14 I 1.69 I 2.52 XBS100030DSOlA Cs-134 0.05 k 0.07 __ __
Cs-137 46.6 I 1.6 61.2 86.4 ELI-152 0.03 k 0.20 __ __
Eu-154 0.06 i: 0.16 _- __
Mil-54 1.2 k 2.5 __ __
CO-60 2.86 I 0.16 2.9 3.19 Cs-134 0.13 I 0.08 -_ _-
SA81OOOOODSOlA Cs-137 113.1 k 3.7 115 122 Eu-152 0.15 k 0.24 __ -_
ELI-154 0.08 k 0.16 _- _-
Mil-54 -0.02 I 0.05 __ __
CO-60 2.75 I 0.12 5.63 2.83 SA83700 1D S01 Cs-134 0.01 k 0.02 __ __
Cs-137 24.30 k 0.76 20.2 20.4 ELI-152 0.04 i: 0.09 __ __
Eu-154 0.04 IfI 0.08 __ __
Mn-54 0.13 k 0.16 _- __
CO-60 0.06 k 0.07 0.05 0.06 Cs-134 0.12 I 0.09 __ __
SB837001DS 12 Cs-137 48.1 I 1.6 31.1 33.5 Eu-152 -0.15 I 0.18 __ __
Eu-154 -0.03 I 0.12 __ __
Mn-54 0.00 k 0.01 __ __
CO-60 0.37 k 0.05 0.34 0.34 Cs-134 0.01 I 0.02 __ __
cc8430020s001ss Cs-137 4.46 I 0.18 4.25 4.11 Eu-152 0.02 I 0.06 __ __
Eu-154 -0.03 k 0.09 _- __
Rancho Seco Nuclear Generating Station 14 1695\Reports\7006- 10-25 Confirmatoiy Sunrey Results
TABLE 2 (contiuued)
RADIONUCLIDE CONCENTRATIONS INTERLABORATORY COMPARISON SOIL SAMPLES
]RANCHO SECO NUCLEAR GENERATING STATION HERALD, CALIFORNIA Radionuclide Concentration hCi/p.)
Sample Identification Radioiiuclide ORISE ORISE §MUD I Mil-54 -0.11 k 0.19 __ _-
CO-60 0.04 k 0.03 0.09 0.06 1695S0006 ccs430020s005ss 0.04 t 0.03 I -- I --
Cs-137 1.95 rt 0.10 2.01 2.03 I Eu-152 0.00 k 0.06 _- __
Eu-154 0.02 k 0.09 __ __
Mn-54 0.05 k 0.07 _- _-
I Co-60 0.12 Cs-134 1695S0007 SlOOOlOSFPCP Cs-137 2.09 0.09 1.42 0.01 k 0.03 __ __
-0.03 rt 0.05 I I
_-
I
__
ace-60 and Cs-137 concentrations provided by SMUD personnel. Previous concentrations were performed during characterization surveys. Current concentration are when the site re-analyzes the samples prior to submitting them to ORISE.
LLJncertaintiesrepresent the 95% confidence level based on total propagated uncertainties.
CRadionuclide concentrations were not provided.
Rancho Seco Nuclear Generating Station 1695\Rcports\2006-10-25 Confirmatory Survey Results
REFERENCES Oak l d g e Institute for Science and Education (ORISE). Survey Procedures Manual for the Eiivii-omnental Sumey and Site Assessment Program. Oak l d g e , Tennessee; September 2, 2004.
Oak l d g e Institute for Science aiid Education. Quality Assurance Manual for tlie Eiiviroimiental Sumey and Site Assessment Program. Oak Ridge, Tennessee; July 28,2005.
Oak Ridge Institute for Science and Education. Proposed Conhrinatoly Sumey Plan for die Reinainiiig Structural Surfaces, Embedded Piping, Standing Water aiid Open Lalid Area Survey Units, Raiicho Seco Nuclear Generating Station, Herald Cahforiia pocliet No. 50-312; W T A No.
06-0031. Oak Ridge, Tennessee; Juiie 2,2006a.
Oak l d g e Iiistitute for Science and Education. Laboratoiy Procedures Manual for Independent Eiivii-oiunental Assessment and Veltlficatioii Prograin. Oak Ridge, Tennessee; A p d 18, 2006b.
Sacrainento Municipal Utility District (SMUD). License Teunkation Plan, Raiicho Seco Nuclear Generating Station, Herald, California; April 2006a.
Sacranento Municipal Utility District. Decoilllnissioiling Tecluical Basis Document: Use of In Situ Gaimiia Spectroscopy for Final Site Survey. DTBD-06-003, Revision 0.Raiicho Seco Nuclear Geiierating Station, Herald, California; May 24,2006b.
Sacramento Municipal Utdity District. Decoimiissionhig Technical Basis Document: Sttucture Nuclide Fraction aiid DCGLs. DTBD-05-015, Revision 0. Raiicho Seco Nuclear Generating Station, Herald, Califoriia; June 2,2006~.
Rancho Seco Nuclear Generating Station 16 1695\Reports\2006-10-25 Confirmatory Survey Results
Sacramento Municipal Utility District -4-bcc w/enclosure (via ADAMS distribution):
LDWert CLCain J BHickmnan, NRR/DLPM/PDIV-2 ACMcMurray, NRR/DSSA/SPLB DBSpitzberg EMGarcia SPAtwater KEGardin FCDB File SUNS1 Review Complete: EMG ADAMS: UNO Initials: EMG Publicly Available UNon-Publicly Available Elsensitive Non-Sensitive DOCUMENT NAME: s:\dnrns\!fcdb\!ema\rsO604.wod final r.\ R9,\7M16\
12/ /06 1 2 6 /06