IR 05000528/1994032
| ML17311A408 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/09/1994 |
| From: | Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML17311A407 | List: |
| References | |
| 50-528-94-32, 50-529-94-32, 50-530-94-32, NUDOCS 9411220107 | |
| Download: ML17311A408 (28) | |
Text
APPENDIX U.S.
NUCLEAR REGULATORY CONMISS ION
REGION IV
Inspection Report:
50-528/94-32 50-529/94-32 50-530/94-32 Licenses:
NPF-41 NPF-51 NPF-74 Licensee:
Arizona Public Service Company P.O.
Box 53999 Phoenix, Arizona Facility Name:
Palo Verde Nuclear Generating Station, Units 1, 2, and
Inspection At:
Wintersburg, Arizona Inspection Conducted:
October 17-21, 1994 Inspectors:
J.
B. Nicholas, Ph.D., Senior Radiation Specialist Facilities Inspection Programs Branch G. L. Guerra, Radiation Specialist Facilities Inspection Programs Branch Approved:
B aine Nurray, C ief, Fa ities Inspection Programs Branch D te Ins ection Summar Areas Ins ected Units
2 and
Routine, announced inspection of the solid radioactive waste management and transportation of radioactive materials programs including:
organization and management controls; training and qualifications; quality assur ance program; changes to the solid radioactive waste management program; radioactive waste classification, waste characterization, and shipping requirements; interim storage of solid radioactive waste; procurement and selection of packages; preparation of packages for shipment; delivery of completed packages to carriers; records, reports, and notifications; and reports of radioactive effluents and radioactive waste shipments.
Results Units
2 and
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The radiation protection support services section had experienced no turnover of personnel during the past 2 years (Section l. 1).
94ii220i07 94iiiB PDR
- DOCK 05000528 G,PDR
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Good radiation protection department management controls were being implemented to support the solid radioactive waste program (Section 1.1).
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The radiation protection support services section was fully st'affed with qualified and experienced personnel (Section 1. 1).
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An excellent training program for the radiation protection support services section personnel was being implemented (Section 2. 1).
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An excellent nuclear assurance audit and excellent nuclear assurance evaluations of the solid radioactive waste management and transportation programs were performed by qualified auditors and provided excellent program evaluation and management oversight.
Timely, technically appropriate corrective actions were implemented to address audit findings (Section 3.1).
Good procedures were implemented that addressed the processing, packaging, handling, classification and characterization, and transporting of radioactive waste and materials (Section 4. 1).
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Good ALARA practices were implemented by radiation protection support services section personnel involved with handling solid radioactive waste (Section 4.1).
A good radioactive waste minimization program was being implemented (Section 4.1).
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A good solid radioactive waste management program was being implemented (Section 4.2).
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Proper interim storage for radioactive waste was provided in the Dry Active Waste Processing and Storage Facility and inside the radiological controlled area at each reactor unit (Section 4.4).
Good implementing procedures were in place that addressed selection of packages, preparation of packages for shipment, and delivery of the completed packages to the carrier (Section 5. 1).
A licensee-identified non-cited violation involving the incorrect manifesting of two radioactive waste shipments was reviewed (Section 5.'1).
Personnel responsible for the shipment and transportation of radioactive waste and/or materials were knowledgeable of the regulatory requirements and the burial site license conditions (Section 5. 1).
Summar of Ins ection Findin s:
A non-cited violation was identified (Section 5. 1.4).
-3-Attachment:
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Attachment Persons Contacted and Exit Neeting
DETAILS
ORGANIZATION AND MANAGEMENT CONTROLS (86750)
The inspectors reviewed the organization and staffing of the radiation protection department to determine agreement with commitments in the Updated Safety Analysis Report and compliance with the requirements in Technical Specification 6.2.
1. 1 Discussion The inspectors reviewed the organizational structure of the radiation protection department and, specifically, the radiation protection support services section which was,responsible for the management and implementation of the solid radioactive waste management and transportation programs.
The inspectors reviewed the organizational structure and staffing for changes in the radiation protection support services section since the previous NRC inspection of this area.
The inspectors noted that there had been no personnel changes in the radiation protection support services section during the past 2 years.
The organizational structure and staffing of the radiation protection department was as defined in the Updated Safety Analysis Report and Technical Specifications.
Radiation protection departmental administrative procedures were reviewed for the assignment of responsibilities for the management and implementation of the solid radioactive waste management and transportation programs.
The inspectors determined that the duties and responsibilities specified in the station procedures were being implemented and that the solid radioactive waste management activities were well managed.
Radiation protection support services personnel were trained and qualified in their responsibilities to perform the required solid radioactive waste management and transportation of radioactive materials activities in accordance with the Offsite Dose Calculation manual, Process Control Program, and NRC and Department of Transportation requirements.
The inspectors interviewed several radiation protection support services personnel and determined that they were familiar with the requirements of the solid radioactive waste management and transportation programs and maintained a high level of performance.
The radiation protection support services section was fully staffed with qualified and experienced personnel to perform solid radioactive waste processing and transportation of radioactive materials activities.
1.2 Conclusions The organizational structure and staffing of the radiation protection department and radiation protection support services section met the commitments in the Updated Safety Analysis Report and the requirements in the Technical Specifications.
During the past 2 years, the radiation protection support services section had not experienced any turnover of personnel.
Radiation protection department and radiation protection support services section management controls were being implemented in accordance with station procedures, The radiation protection support services section was fully staffed with qualified and experienced personne TRAINING AND QUALIFICATIONS (86750)
The inspectors reviewed the training and qualification programs for the radiation protection support services section personnel responsible for implementing the solid radioactive waste management and transportation programs to determine agreement with commitments in the Updated Safety Analysis Report and compliance with the requirements in Technical Specifications 6.3 and 6.4.
2. 1 Discussion The inspectors discussed the radiation protection support services personnel training and qualification program with the radiation protection/chemistry training supervisor, the radiation protection training coordinator, and the senior radiation protection instructor who conducted the radioactive waste training program for the radiation protection support services personnel.
The inspectors reviewed the radiation protection personnel qualification requirements and training program description procedure, job qualification standard procedure, job qualification cards and job performance measures, and lesson plans and course materials for the training course on radioactive waste packaging/shipping and receiving of radioactive materials which was presented annually to train and requalify the radiation protection support services section personnel.
The inspectors also reviewed selected training records for selected radiation protection support services section personnel.
Based on the review, it was determined that the training and training materials were of excellent quality and that the radwaste supervisor and the radiation protection technicians currently responsible for the processing and transportation of solid radioactive materials had completed the required training to perform their assigned duties.
Radioactive waste packaging and transportation regulatory requirement training was provided on an annual frequency.
The inspectors determined that all of the radiation protection support services section personnel had completed the regulatory requirement training and were knowledgeable of the applicable NRC, Department of Transportation, and burial site license requirements.
2.2 Conclusions An excellent training program for the radiation protection support services section personnel was being implemented.
EQUALITY ASSURANCE PROGRAM (86750)
The inspectors reviewed the quality assurance audit and monitoring programs regarding the solid radioactive waste management and transportation programs to determine agreement with the commitments in the Updated Safety Analysis Report and compliance with the requirements in Technical Specifications 6.5.3.5.d and 6.5.3.5.j.
3. 1 Discussion The inspectors reviewed the nuclear assur ance audit schedule for 1989 through 1994.
The schedule reflected a biennial audit schedule for the process
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control/radwaste shipping progra'm.
The audit schedule indicated that the process control/radwaste shipping audit was performed during the odd numbered years.
The audit schedule was in compliance with the Technical Specification audit frequency requirement.
The inspectors reviewed the nuclear assurance scoping matrix and audit plan for the process control/radwaste shipping audit and the qualifications of the nuclear assurance auditors who performed the process control/radwaste shipping audit (Audit 93-008) since the previous NRC inspection of the solid radioactive waste management and transportation programs.
The inspectors reviewed the 1993 report of the nuclear assurance audit of the
"Process Control/Radwaste Shipping" (93-008),
which was conducted during the time period July 19 to August 20, 1993, for scope, thoroughness of program evaluation, and timely followup of identified deficiencies.
The audit was performed by a team of qualified personnel, who were knowledgeable in solid radioactive waste management and transportation programs at nuclear power generation facilities.
The audit was conducted in accordance with nuclear assurance procedures and schedules.
The audit team evaluated the implementation of the solid radioactive waste management (Process Control Program)
and radwaste shipping and transportation programs.
As a result of the 1993 audit, one guality Deficiency Report, eight Corrected-on-the-Spot, and one guality Audit Recommendation were issued.
The guality Deficiency Report identified a deficiency in the manner in which radwaste was stored in the Dry Active Waste Processing and Storage Facility.
Radwaste containers in the storage area of the building were not arranged in a manner to provide self-shielding as prescribed in the Updated Safety Analysis Report description of storage techniques, as well as the station's
CFR 50.59 evaluation of the Dry Active Waste Processing and Storage Facility.
In addition, the Updated Safety Analysis Report and
CFR 50.59 evaluation requirements had not been incorporated into station radwaste procedures for the storing of radioactive material in the Dry Active Waste Processing and Storage Facility.
The inspectors reviewed the corrective actions taken to resolve the audit guality Deficiency Report and verified that the guality Deficiency Report was closed promptly.
The 1993 audit concluded that the programs to minimize, store, process, and ship radioactive waste and materials were being implemented effectively.
Audit 93-008,
"Process Control Program/Radwaste Shipping,"
was comprehensive and of excellent quality to evaluate the licensee's performance in implementing the solid radioactive waste management and transportation programs.
The audit was conducted in agreement with Updated Safety Analysis Report commitments and met Technical Specification requirements.
The inspectors reviewed 10 selected nuclear assurance evaluation reports of the solid radioactive waste management and transportation programs activities conducted during the time period January 1,
1993, through September 30, 1994.'he inspectors determined that the nuclear assurance evaluation reports of the solid radioactive waste management and transportation programs were comprehensive and conducted at a sufficient frequency to evaluate the licensee's compliance with Technical Specification and Process Control Program requirements.
Of the nuclear assurance evaluation reports reviewed, no deficiencies were identified.
The nuclear assurance evaluation reports were of excellent quality and satisfactory to evaluate the licensee's performance and provide periodic management oversigh The licensee used three contractors to provide various radwaste services such as incineration, compaction, wet waste processing, solidification, and shipment of solid radioactive waste for burial after processing and volume reduction.
The licensee also used a contractor laboratory to perform radiochemical analyses of the station's various liquid and solid radioactive waste as required in 10 CFR Part 61 to classify and characterize the solid radioactive waste prior to disposal, The licensee had performed audits of the solid radioactive waste processors and the contractor's laboratory.
3.2 Conclusions An excellent nuclear assurance audit and excellent nuclear assurance evaluations of the solid radioactive waste management and transportation programs were performed by, qualified auditors.
The audit and evaluations were comprehensive and provided excellent program evaluation and management oversight.
Audits of the contractors used to perform solid radioactive waste processing and volume reduction and laboratory analyses were performed.
SOLID RADIOACTIVE HASTE NANAGENENT (86750)
The inspectors reviewed the solid radioactive waste management program to determine whether it met applicable regulatory requirements.
4. 1 Chan es to the Pro ram The inspectors reviewed changes that had been made in the facilities, equipment, and procedures that affected the performance of the solid radioactive waste management program.
The licensee had revised radiation protection department and radiation protection support services section procedures used by the radiation protection technicians in processing, packaging, handling, and transporting radioactive waste and materials and the Process Control Program since the previous NRC inspection of this area.
The inspectors reviewed selected revised procedures and noted that they provided detailed specific instructions for performing individual job task requirements.
The procedures were easy to follow and were specifically directed toward compliance of regulatory requirements.
The licensee had established and implemented a radioactive waste minimization'rogram.
The licensee was using a new device for handling and transferring highly radioactive spent filter cartridges to high integrity containers.
This equipment significantly reduced the radiation exposure to personnel processing the spent filter cartridges.
The licensee was also using remote video equipment to monitor high radiation exposure jobs and a robot to perform high radiation exposure tasks when possible.
These program innovations were considered to be strengths and excellent ALARA practices.
Another example of good ALARA practices being implemented was that the station had reduced the radiation dose of the radiation protection support services section personnel over the past 4 years by the establishment of an effective radioactive waste minimization program as well as the use of remote handling and monitoring equipment while performing high radiation exposure jobs.
This was demonstrated by the following data:
in 1991 the radiation protection support
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services section personnel total dose was 12,259 millirem, 12,890 millirem in 1992, 5,937 millirem in 1993, and 7,257 millirem through September 30, 1994.
4.2 Solid Radioactive Waste Mana ement The inspectors reviewed the solid radioactive waste management program to determine agreement with commitments in the Updated Safety Analysis Report and compliance with the requirements of the Process Control Program.
The licensee disposed of radioactive spent resin, filter cartridges, and waste evaporator sludge by transferring and dewatering the spent resin and evaporator sludge in high integrity containers and shipping the high integrity containers off site to a licensed radioactive waste burial site.
Extensive use of procedure checklists was noted.
The inspectors noted that the shipments were prepared, inspected, and documented by radiation protection support services section personnel in accordance with regulatory requirements.
The licensee disposed of dry active waste by placing it in strong-tight containers or sealand containers and shipping it off site to a contractor who segregated and processed it for volume reduction prior to shipment for burial.
The inspectors observed the licensee prepare a 20 liter sample of contaminated liquid for shipment (94-SH-141) to a contractor for analysis.
The liquid sample was prepared, blocked and braced with wood, and packed with sufficient absorbent material in a 55-gallon Type A drum for shipment.
The drum was inspected, surveyed, marked, labeled, and documented by radiation protection support services personnel in accordance with NRC and Department of Transportation regulatory requirements.
The inspectors reviewed selected radioactive waste shipping manifest forms and shipping papers that accompanied each shipment of radioactive waste.
The completed shipping manifests and documentation reviewed complied with the requirements of 10 CFR 20.2006.
4.3 Radioactive Waste Classification Waste Characterization and Shi in Re uirements The inspectors reviewed the licensee's program for the control, classification, characterization, and shipment of solid low-level radioactive waste and disposal site license.conditions to determine compliance with the requirements of 10 CFR 20.2006, 61.55, and 61.56, and the recommendations of NRC Branch Technical Position, Revision 1,
"Papers on Low-Level Radioactive Waste Classification and Waste Form."
The inspectors determined that the licensee had sent annual samples of dry active waste, evaporator sludge, high activity spent resin, low activity spent resin, and spent filter cartridges from each of the three reactor units to a
contract laboratory during 1992, 1993, and 1994 to determine radionuclide concentrations and scaling factors for those radionuclides which the licensee was not capable of directly measuring.
The inspectors reviewed the licensee's analytical records for selected waste samples of solid radioactive waste and scaling factor information generated for characterizing the solid radioactive waste prior to shipment to meet
CFR Part 61 requirement.4 Interim Stora e of Solid Radioactive Waste As part of the licensee's long-range radioactive waste management plan, the licensee was keeping abreast of the radioactive waste burial site development in the Southwest Compact and was providing for interim storage of th'eir radioactive waste on site for a minimum of 5 years or until the Southwest Compact burial site in California was ready to receive radioactive waste.
The inspectors inspected the licensee's radioactive waste interim storage areas inside the Dry Active Waste Processing and Storage Facility and in the fenced radiological controlled yard area at each of the three reactor units and noted that these areas were secured, posted properly, and provided ample interim storage space for the amount of radioactive waste that would be generated by the station in 5 years.
The inspectors also reviewed the plans and drawings for the construction of a new radioactive waste storage facility to be constructed within the site's owner controlled area starting in November 1994.
4.5 Conclusions Good procedures that addressed processing, packaging, handling, classification and characterization, and transporting of radioactive waste and materials were maintained.
Good ALARA procedures were implemented by radiation protection support services section personnel.
The licensee was implementing a good radioactive waste minimization program.
A good solid radioactive waste management program was being implemented.
The licensee had analyzed solid radioactive waste streams from each of the three reactor units for the determination of radionuclide concentrations and scaling factors.
The licensee had provided for interim storage of their radioactive waste inside the Dry Active Waste Processing and Storage Facility and inside the radiological controlled area at each reactor unit.
TRANSPORTATION OF RADIOACTIVE NATERIALS (86750)
The inspectors reviewed the transportation program for shipment of radioactive materials and solid radioactive waste to determine compliance with the requirements in 10 CFR Parts 20, 61, and 71; and
CFR Parts 172-189.
5. 1 Discussion 5. 1. 1 guality Assurance Program The inspectors verified that the licensee had received NRC Form 311, "guality Assurance Program Approval," which documented NRC approval that the licensee's submitted quality assurance program complied with 10 CFR Part 71, Subpart H,
for the transportation of radioactive materials.
The approval expires Narch 31, 1996.
5. 1.2 Procurement and Selection of Packages The inspectors reviewed the licensee's procurement of Department of Transportation and NRC-certified containers.
The licensee used strong-tight containers for the shipment of low specific activity dry radioactive waste and laundry.
Of the 494 shipments made in 1992, 1993, and 1994, 113 shipments
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The remaining radioactive materials shipments were of laundry, radioactive sources, samples for radiochemical analyses, empty containers, and dry active waste or radioactive materials that were being shipped to a contractor for processing and volume reduction.
The licensee maintained current documentation on the manufacturer's design testing, maintenance, and NRC Certificates of Compliance for all radioactive waste certified containers and casks used by the licensee.
5. 1.3 Preparation of Packages for Shipment The inspectors verified that the licensee had procedures and checklists for the preparation of radioactive waste and materials shipments.
A review of the licensee's procedures and shipping records and discussions with the radiation protection support services section personnel indicated that the certified cask's manufacturers handling, loading, and inspecting procedures were used in preparing shipping casks for shipment.
The procedures provided for visual inspection of the package prior to filling the container, instructions for closing and sealing the container, marking and labeling requirements, and determining compliance with radiation and contamination limits.
The licensee routinely used a checklist to assure that procedures were followed, and that packages were prepared properly for shipment in accordance with NRC, Department of Transportation, state, and burial site requirements.
Discussions with radiation protection support services section personnel involved in the preparation of packages of radioactive waste and materials for shipment indicated that they possessed an excellent knowledge of the licensee's procedures and NRC and Department of Transportation regulations pertaining to the preparation of packages for shipment.
The licensee maintained current transport permits for transportation of radioactive materials to or through the states of Tennessee and South Carolina.
The licensee also maintained current copies of radioactive material licenses for recipients of shipped radioactive waste and materials.
5. 1.4 Delivery of Completed Packages to Carriers The inspectors verified that the licensee's procedures included the required NRC and Department of Transportation regulations.
A review of selected records and shipping papers for radioactive waste shipments indicated that the licensee had prepared appropriate manifests and shipping papers in accordance with approved procedures ("Radman" computer software)
and that the shipping papers included the necessary information to comply with regulatory requirements.
The licensee used exclusive use carriers for all radioactive waste shipments and assured that the following items were in accordance with NRC and Department of Transportation regulations and station procedures:
radiation levels were within required limits, transport vehicles were placarded properly, surface contamination on packages did not exceed requirement levels, and blocks and/or braces were in place to prevent damage or shifting of the load during transi On October 19, 1994, the licensee completed its investigation of the discovery of two spent filters which were documented as shipped for burial, but were found to be still in their possession.
On June 17, 1994, spent filter No. 2-93-$ -022 was found in Unit 2 when it was thought to have been shipped to Barnwell, South Carolina, for burial on Nay 7, 1994.
Similarly, on August 4, 1994, spent filter No. 3-94-S-025 was found in Unit 3 when it was also thought to have been shipped to Bar nwe11, South Carolina, for burial on June 12, 1994.
A Condition Report/Disposition Request (CRDR),
No. 2-4-0252, was initiated with the discovery of the first spent filter for investigation and corrective action.
Later, a
Human Performance Enhancement System investigation based on CRDR No. 2-4-0252 was initiated.
The discovery of the second spent filter on August 4, 1994, pr'ompted the generation of CRDR No. 9-4-0574 which was subsequently added to the Human Performance Enhancement System investigation because of its similarity to the first spent filter discovery.
The Human Performance Enhancement System investigation concluded that the actual cause of these two spent filter incidents could not be positively identified.
However, evidence strongly supported two inappropriate behavioral factors.
One, radiation protection support services section technicians used handwritten lists of spent filters to be loaded into a high integrity container for shipment rather than using the actual spent filter data sheets, identified as Appendix B's by the licensee, which indicated where the spent filters were to be found.
Second, the radiation protection support services section technicians assumed that the handwritten lists included all spent filters that were to be loaded into the high integrity container.
Corrective actions which were taken included taking a spent filter inventory in each of the three reactor units to ensure no other deficiencies existed; reanalyzing the waste shipments to ensure spent filter deletion errors did not change waste classification;= correcting shipping manifests and notifying the disposal facility of the discrepancies; revising Procedure 76DP-9RFOl,
"Transfer and Storage of Radioactive Filters," to incorporate proper documentation of the location and disposition of a spent filter on the "Filter Data Sheet";
and discontinue the use of "handwritten lists" to load selected spent filters into high integrity containers for burial.
These events were determined to be a violation of 10 CFR 20.2006 and Appendix F to
CFR Part 20, which require that the shipping manifest indicate as completely as practicable the physical description of the waste, the volume, radionuclide identity and quantity, the total radioactivity, and the principal chemical form.
However, this violation will not be subject to enforcement action because the licensee's efforts in identifying and correcting the violation met the criteria specified in Section VII.B.2 of Appendix C to
CFR Part 2.
5. 1.5 Records, Reports, and Notifications The inspectors reviewed selected records of several different types of waste shipments made by the licensee during 1992, 1993, and 1994.
The shipments were adequately documented to meet NRC and Department of Transportation regulations.
The licensee maintained records of all radioactive waste and/or
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'shipments as required.
The records included all shipping documentation, radiation surveys, and required notification information.
5.2 Conclusions The quality assurance program for radioactive material packages was NRC approved.
Good implementing procedures that addressed selection of packages, preparation of packages for shipment, and delivery of the completed packages to the carrier were maintained.
A violation regarding the incorrect manifesting of two radioactive waste shipments was self-identified by the licensee.
In general, the solid radioactive waste transportation program was being implemented 'in accordance with regulatory requirements.
Personnel responsible for the shipment and transportation of radioactive waste and/or materials were knowledgeable of the regulatory requirements and the burial site license conditions.
REPORTS OF RADIOACTIVE EFFLUENTS AND RADIOACTIVE WASTE SHIPMENTS (86750)
The inspectors reviewed reports concerning the solid radioactive waste shipments and transportati on acti vities to determine compliance with the requirements of 10 CFR 50.36(a)(2)
and Technical Specification 6.9. 1.8 and the Offsite Dose Calculation manual.
6. 1 Discussion The inspectors reviewed the Radioactive Effluent Release Reports, for the time period January 1,
1992, through June 30, 1994.
These reports were written in the format described in NRC Regulatory Guide 1.21, Revision 1, June 1974, included the information required by the Technical Specifications and the Offsite Dose Calculation manual and provided a summary of the radioactive solid waste shipped from the station for processing and/or burial.
The inspectors reviewed the latest revision to the Process Control Program, Revision 3, January 1994.
During the time period January 1,
1992, through June 30, 1994, the inspectors reviewed the licensee's records for shipment of solid low-level radioactive waste and noted that the licensee had completed 486 radioactive waste shipments by exclusive use vehicle to burial sites in Washington, South Carolina, and Nevada prior to the closing of the waste burial sites on July 1, 1994.
The licensee had not made any shipments of spent fuel.
The inspectors reviewed the licensee's records of radioactive waste shipments for burial since 1989.
The following table summarizes the total volume and
t
-13-curie content of the solid low-level radioactive waste shipped for the period 1989 through June 1994.
'::..CUr."i'e':.:.::,Co'n'tent'.:.";::,
1989 1990 1991 1992 1993 June 1994
78
154
.145 144 874.00 765.85 483.00 424.70 228.72 217.97 674.19 240.32 890.78 1172.80 643.49 416.25 6.2 Conclusion Radioactive Effluent Release Reports were submitted in a timely manner, and the reports contained all the required information presented in the recommended forma ~
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ATTACHMENT
PERSONS CONTACTED l. 1 Licensee Personnel S. Bell, Radiation Protection Senior Training Instructor
- K. Brewer, Health Physicist, Radiation Protection Technical Services J. Carroll, Radwaste Technician P. Donnelly, Radwaste Technician
- N. Fladager, Supervisor, Radiation Protection Support Services
- J. Gaffney, Hanager, Radiation Protection Outage and Naintenance
- F. Gowers, Site Representative, El Paso Electric
- A. Haugen, Evaluator, Nuclear Assurance Plant Support
- R. Hazelwood, Engineer, Nuclear Regulatory Affairs
- R. Henry, Site Representative, Salt River Project
- V. Huntsman, Nanager, Radiation Protection Support Services E. Keller, Radwaste Technician
- D. Leith, Technical Advisor, Radiation Protection Technical Services E. Nedlin, Radwaste Senior Technician G. Nelson, Radiation Protection Training Coordinator
- B. Picchiottino, Supervisor, Radiation Protection/Chemistry Training
- H. Shea, Director, Site Radiation Protection
- J. Steward, Nanager, Radiation Protection Technical Services 1.2 NRC Personnel
- K. Johnston, Senior Resident Inspector A. NacDougall, Resident Inspector H. Freeman, Resident Inspector
- B. Nurray, Chief, Facilities Inspection Programs Branch In addition to the personnel listed above, the inspectors contacted other personnel during the inspection.
- Indicates those present at the exit meeting on October 21, 1994.
EXIT NEETING An exit meeting was conducted on October 21, 1994.
During this meeting, the inspectors reviewed the scope and findings of the inspection.
The licensee did not express a position on the inspection findings documented in this report.
The licensee did not identify as proprietary any information provided to, or reviewed by, the inspector \\
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