IR 05000298/1998014
| ML20217A553 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 04/17/1998 |
| From: | Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20217A523 | List: |
| References | |
| 50-298-98-14, NUDOCS 9804220280 | |
| Download: ML20217A553 (17) | |
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ENCLOSURE U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Docket No.:
50-298 License No.:
DPR 46 Report No.:
50-298/98-14 Licensee:
Nebraska Public Power District l
Facility:
Cooper Nuclear Station Location:
P.O. Box 98 l
Brownville, Nebraska l
Dates:
April 6-9,1998 Inspector (s):
Gilbert L. Guerra, Jr.
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Radiation Specialist
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Approved By:
Blaine Murray, Chief, Plant Support Branch Division of Reactor Safety
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ATTACHMENTS:
Attachment 1:
Supplemental Information Attachment 2:
Effluent Release Data l
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9804220280 980417 PDR ADOCK 05000298 O
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-2-EXECUTIVE SUMMARY Cooper Nuclear Station NRC Inspection Report 50-298/98-14 A routine, announced inspection of the liquid and gaseous radioactive effluent waste management program including organization and management controls, radioactive effluent monitoring, and safety-related air cleaning systems was conducted.
Plant Sucoort Overall, a good liquid and gaseous radioactive effluent waste management program was
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implemented which included proper implementing procedures, a qualified staff, and appropriate quality assurance oversight.
Challenging performance goals were initiated in 1997 for the reduction of radioactive
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effluent waste releases; and improvement in liquid waste activity and volume released was noted in the fourth quarter of 1997 and the first quarter of 1998. Noted improvements were due to the formation of a task force in 1997 which had effectively reduced in-leakage into the radwaste systems (Section R1.1).
A good surveillance program was implemented for the safety-related air cleaning
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ventilation systems (Section R1.2).
The radiochemistry counting room was equipped with properly maintained and calibrated
analyticalinstrumentation (Section R2.1).
The post-accident sampling system was maintained in a proper state of operational
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readiness (Section R2.2).
The liquid and gaseous effluent radiation monitoring instrumentation was properly
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maintained, tested, and calibrated (Section R2.3).
Proper procedures were maintained which contained appropriate detail. Good Annual
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Operating Report Radioactive Effluents for 1995 and 1996 were submitted in a timely manner and contained the required information. Revisions to the Offsite Dose Assessment Manual were appropriately implemented and documented (Section R3.1).
Chemistry personnel had a very good understanding of the liquid and gaseous
radioactive effluent waste management procedures and Offsite Dose Assessment Manual (Section R4.1).
Training and qualification programs for the chemistry technicians were properly
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implemented. The chemistry department had a well trained and qualified staff for conducting radioactive waste effluent processing and release operations (Section R5.1).
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-3-An appropriate chemistry technical staff was maintained which had experienced little
et ange s'nce the last NRC inspection in September 1996 (Section R6.1).
Oversight of the radioactive effluent waste management program was adequate.
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l Contractors used to perform radioactive effluent waste management program Technical Specification required surveillance analyses were properly evaluated (Section R7.1).
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Report Delalla IV. Plant Sunoort R1 Radiological Protection and Chemistry Controls R1,1 Radiological Waste Effluent Management Proorams
a.
Insoection Scoce (84750)
l The implementation of the radioactive effluent waste management program was l
reviewed. This review included: radioactive effluent waste processing, radioactive
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effluent waste sampling and analyses, analyses sensitivities and results, offsite dose results, and performance of required surveillarice tests. The following activities were observed:
The collection of effluent samples from the reactor building and drywell air l
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monitors for analyses of particulates and iodine.
The collection of a liquid waste sample from the floor drain sample tank and
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performance of radiochemistry analyses on the sample and preparation of the
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release permit and valve lineup for discharge.
b.
Observations and Findings The floor drain tank sample taken on April 7,1998, was analyzed in the chemistry laboratory for pH, conductivity, and turbidity; and for principal gamma emitters in the radiochemistry counting facility. The inspector noted that the chemistry technician used L
proper sample handling techniques when collecting and analyzing the floor drain tank sample. The inspector observed the preparation of the radioactive liquid waste effluent i
batch release permit and verified that the correct discharge valve lineup was performed by a station operator and that the alarm setpoints were property set for the liquid radwaste effluent radiation monitor as required by the release permit. Also, air particulate filter and iodine charcoal cartridge samples from the reactor building vent l
sampler and the drywell air vent sampler were collected on April 7,1998, for analyses of i
airborne effluents.
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Quantities of radionuclides released in the liquid and gaseous radioactive effluent wastes l
were within the limits specified in the Technical Specifications. Offsite doses were calculated according to Offsite Dose Assessment Manual methodologies and were within
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regulatory limits. Technical Specification required analyses on composite samples of batch radioactive liquid and particulate effluent waste releases for gross alpha, tritium, strontium-89, strontium-90, and iron-55 were properly performed. The inspector noted that licensee personnel followed the appropriate sampling and analyses, waste release permit preparation, discharge valve lineup, and radiation monitor set point calculation procedures during the observed tasks.
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Effluent release data contained in the annual effluent release reports for 1995,1996, and 1997, (draft) show that effluent releases have been increasing. Quantities of radionuclides released and offsite doses for 1996 were above the national average placing the licensee in worst quartile performance for boiling water reactors. Releases
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for 1997 were generally higher than 1996 releases. This increase is due primarily to fuel pin leaks in early 1996. Also, the station was not able to utilize the augmented off-gas system for a considerable time in 1997. The effects of the leaking fuelis still a factor in offsite releases. A corresponding increase in offsite doses was observed in 1996 and 1997.
The inspector noted that the licensee had begun efforts to reduce effluent release volumes and activity. Improvement in the reduction of liquid radioactive waste had been initiated; however, these efforts were not apparent in the 1997 annual data due to higher releases early in 1997 and averaging these for the year. By trending quarterly data, it is appacent that a reduction in liquid volume and activity content of releases had been initiated. Data provided by the licensee to the inspector showed an average of 2.5 days between releases early in 1997; this had been improved to 6.5 days between releases in late 1997 and early 1998. Performance goals had been set for radioactive waste effluent releases and were tracked on the monthly radiological department self assessment reports. Noted improvements were due to the formation of a task force in 1997 which had effectively reduced in-leakage into the radwaste systems. Other projects were also being pursued by the task force.
i The licensee reported no unplanned releases of radioactive liquid or gaseous waste during 1995,1996, and 1997.
c.
Conclusions The liquid and gaseous radioactive effluent waste management program was effectively implemented. Challenging performance goals were initiated in 1997 for the reduction of
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radioactive effluent waste releases; and improvement in liquid waste activity and volume released was noted in the fourth quarter of 1997 and the first quarter of 1998. Noted improvements were due to the formation of a task force in 1997 which had effectively reduced in-leakage into the radwaste systems; other projects were also being pursued.
R1.2 Enaineered Safetv Feature Filtration and Control Room Habitability Systems i
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Insoection Scoce (84750)
Surveillance and test results for the safety-related air cleaning ventilation systems testing
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program were reviewed to determine compliance with the requirements in the Technical Specifications.
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Observations and Findinas The inspector and a system engineer performed a visualinspection of all the Technical t
l Specification required safety-related ventilation filtration systems. These systems
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contained high efficiency particulate air filters and activated charcoal adsorbers. No problems were identified during the visual inspection of the ventilation filtration systems.
No external damage to the filtration units was identified. All filter housings and ducts l
were well maintained. The areas surrounding the filtration units were clean, free of l
debris, and adequate lighting was provided for visualinspection of housings and
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components.
The inspector verified that the surveillance tests provided for the required periodic functional checking of the safety-related ventilation filtration systems' components,
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evaluation of the high efficiency particulate air filters and activated chr.rcoal adsorbers, and the in-place filter testing of the standby gas treatment system and the control room emergency filter system. Since some of the surveillance tests were only required to be
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performed at 18-month frequencies, the inspector reviewed the last surveillance test results for each of the safety-related air cleaning ventilation systems named above and ensured that the previous two surveillances had been performed as required. The in-place filter testing and activated charcoallaboratory surveillance tests were performed in accordance with approved procedures by a contract laboratory. The inspector noted l
that the Technical Specification requirement for testing the various air cleaning l
ventilation systems' activated charcoal adsorber material after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of operation was being tracked by the control room.
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Conclusions l
A good surveillance program was implemented for the safety-related air cleaning
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ventilation systems which properly provided for the maintenance and testing of the air cleaning systems
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R2 Status of Radiological Protection and Chemistry Facilities and Equipment
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l R2.1 Radiochemistry Countina Room a.
Insoection Scoce (84750)
The radiochemistry counting facility and associated analytical instrumentation were inspected to verify if adequate calibration and quality control programs were in place.
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Observations and Findinas i
l The radiochemistry counting room maintained the appropriate analytical instrumentation to perform the required radiochemistry analytical measurements of the radioactive j
effluent waste samples. Quality control indicators were tracked and trended for the
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-7-gamma spectroscopy counting systems. Data showed that the instruments were operable, well maintained, and calibrated. Chemistry technicians assigned to the radiochemistry counting room were knowledgeable on the use of the instrumentation.
c.
Conclusion The radiochemistry counting room was equipped with properly maintained and calibrated analytical instrumentation to perform the required analyses.
R2.2 Post-Accident Samolina System a.
Insoection Scoce (84750)
Surveillance programs for the post-accident sampling system instrumentation were revievyed.
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Observations and Findinas The inspector visually inspected the post-accident sampling system equipment and reviewed records of functional tests. The post-accident sampling system equipment appeared operational. The inspector noted that surveillance tests to ensure function and calibration of the post accident sampling system were performed semi annually. Five chemistry technicians were qualified and trained on the use of the post accident sampling system. Qualified technicians were required to operate the post-accident sampling system twice per year. Licensee staff indicated that the post-accident sampling system was operable.
c.
Conclusion The post-accident sampling system was maintained in a proper state of operational readiness by the performance of function and calibration checks by qualified chemistry technicians.
R2.3 Liauid and Gaseous Effluent Radiation Monitors a.
Insoection Scoce (84750)
The liquid and gaseous effluent radiation monitors were inspected for operation,
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calibration, and reliability.
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Observations and Findinas
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Source checks, channel checks, and calibrations were performed on the effluent
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radiation monitors. Surveillance records indicated that the liquid and gaseous radioactive waste effluent monitoring instrumentation was properly maintained, tested, I
and calibrated in compliance with the surveillance requirements specified in the l
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-8-Technical Specifications. Conditions noted on performance improvement requests for effluent radiation monitors were properly handled by the licensee.
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Conclusion The liquid and gaseous effluent radiation monitoring instrumentation was poperly maintained, tested, and calibrated.
l R3 Radiological Protection and Chemistry Procedures and Documentation l
R3.1 Badioactive Waste Effluent Procedures. Offsite Dose Assessment Manual. and Annual Ooeratino Reoort Radioactive Effluents i
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Insoection Scoce (84750)
Procedures for the sampling, analysis, and release of radioactive liquid and gaseous waste effluents were reviewed. Revisions to the Offsite Dose Assessment Manualwere
reviewed for any changes to the radioactive effluent waste programs and the radwaste system design and operation. The annual reports concerning radioactive waste effluent releases were reviewed for omissions, obvious mistakes, anomalous measuremerits,
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observed biases, and trends in the data.
b.
Observations and Findinas The chemistry procedures described the responsibilities for collection and analyses of liquid and gaseous radioactive effluent waste samples. Procedures governing radioactive effluent waste sampling contained appropriate detail for chemistry technicians. These procedures provided for the following: sampling of the radioactive liquid and gaseous wastes, radionuclide analyses prior to release, calculation of effluent radiation monitor set points, projected offsite radionuclide concentrations, and offsite doses. No concerns were identified with the licensee's procedures implementing the radiological effluent waste management program.
Good annual radioactive effluent release reports were issued which contained the required information concerning liquid and gaseous effluent releases and annual dose calculation results.
The Annual Operating Report Radioactive Effluents for 1995 and 1996 included changes to the Offsite Dose Assessment Manual, as required. The reports were written in the format described in NRC Regulatory Guide 1.21, Revision 1, June 1974, and contained the information required by the Technical Specifications. Sumrnaries of the quantities of radioactive liquid and gaseous effluents released to the environment, and their
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associated doses to members of the public for 1995 and 1996, were properly documented in the annual reports. The draft data for the 1997 annual report was also reviewed. A summary of the radioactive liquid and gaseous effluent releases and I
associated doses is presented in Attachment 2 to this repor.
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The revision of May 20,1997, to the Offsite Dose Assessment Manual was issued since the last NRC inspection in September 1996. The changes were documented in the appropriate annual radioactive effluent release report. The inspector determined that the changes did not reduce the effectiveness of the radioactive effluent waste management program.
c.
Conclusions Proper procedures were maintained which contained appropriate detail for implementing j
the liquid and gaseous radioactive effluent waste management program. Good Annual Operating Report Radioactive Effluents for 1995 and 1996 were submitted in a timely manner and contained the required information. Revisions to the Offsite Dose Assessment Manual were appropriately implemented and documented.
R4 Staff Knowledge and Performance R4.1 Chemistry Staff a.
Insoection Scoce (84750)
Discussions were held with chemistry personnel to evaluate their knowledge and
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performance of radioactive effluent waste activities.
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Observations and Findings The inspector observed chemistry technicians perform radioactive effluent waste activities and determined that they were familiar with the requirements of the radioactive effluent waste management program.. Chemistry personnelincluding supervisors and technicians maintained a high level of performance and were knowledgeable of the liquid and gaseous radioactive effluent waste management procedures and Offsite Dose Assessment Manual requirements.
c.
Conclusions Chemistry personnel had a very good understanding of the liquid and gaseous radioactive effluent waste management procedures and Offsite Dose Assessment Manual.
R5 Staff Training and Qualification R5.1 Training and Qualification of Che,mistry Personnel a.
InSDAClign_Scoce (84750)
j Training and qualification programs for chemistry technicians involved with conducting the radioactive waste effluent management programs were reviewed and verified.
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Observations and Findings Using computerized training records of qualification tasks completed, the inspector verified that a high percentage of the personnelin the chemistry department were qualified to perform routine radioactive effluent waste management program activities.
Training records showed 7 technicians fully qualified to implement the radioactive effluent sampling and analysis programs. Five of these technicians were also qualified to perform sampling of the post-accident sampling system. One new chemistry technician was working toward completing the appropriate task qualifications. The inspector determined that proper training and qualification programs were being implemented for chemistry technicians, c.
Conclusions Training and qualification programs for the chemistry technicians were properly implemented. The chemistry department had a well trained and qualified staff for conducting radioactive waste effluent processing and release operations.
R6 Radiologica! Protection and Chemistry Organization and Administration R6.1 Chemistry Oroanization and Staffino a.
Insoection Scooe (84750)
The organization, staffing, and assignment of the radioactive waste effluent management program responsibilities were reviewed.
b.
Observations and Findings The radiological department had the responsibility for implementing the radioactive waste effluent management program with assistance from the operations department for performing waste release discharges. Valve lineups and release activities were performed by the operations department. The chemistry group within the radiological department was responsible for sampling and analysis, preparing liquid and gaseous release permits, performing dose calculations, and tracking release data and doses.
The staffing level of the chemistry group was sufficient to perform the duties required by the radioactive effluent waste management program. The staff implementing the i
program has remained essentially the same since the last NRC inspection in September 1996. There was only one new chemistry technician and a new chemistry supervisor.
The inspector noted that the qualifications of the chemistry supervisor were appropriate and met station requirements. The organization was appropriate for implementing the liquid and gaseous effluent management program. The inspector determined that the duties and responsibilities of the radiological department's chemistry group were being effectively implemente.
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Conclusions An appropriate chemistry technical staff was maintained which had experienced little change since the last NRC inspection in September 1996.
R7 Quality Assurance in Radiological Protection and Chemistry Activities R7.1 Radioactive Waste Effluent Manaaement Quality Assurance Proaram a.
Insoection Scoce (84750)
The quality assurance audit program regarding radioactive effluent waste management program activities were reviewed. The review included the audits and self-assessments performed between September 1996 and March 1998.
The quality assurance audit and evaluation program regarding contractors performing surveillance activities involving the radioactive effluent waste management programs and safety-related air cleaning ventilation systems were reviewed.
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_QhSHIYations and Findinas A good quality assurance audit of chemistry activities was performed. The audit of chemistry activities was performed on a 24-month frequency which covered activities of the radioactive effluent waste management program. Specialists were used on the audit tearns from other utilities. Audit team members had previous experience in the areas reviewed and were qualified auditors. Also, a self assessment was performed of chemistry activities during 1997, which provided an evaluation of some radioactive effluent release activities. Previous findings were reviewed and identified items were
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tracked.
Audits of contractors used to perform radiochemistry analyses on radioactive effluent
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waste composite samples and in-place filter testing and laboratory charcoal adsorber analyses on the station's safety related air cleaning ventilation systems were evaluated i
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for inclusion on the qualified suppliers list. These audits were performed by Nuclear Procurement issues Committee (NUPIC) audit teams led by various utilities with interest in the services provided by the vendor. The inspector reviewed the audits performed on j
the contractors and determined that the audits were satisfactory to evaluate the
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contractors' abilities to perform their respective Technical Specification required analyses i
and surveillance activities.
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Conclusions Oversight of the radioactive effluent waste management program was adequate.
l Contractors used to perform radioactive effluent waste management program Technical Specification required surveillance analyses were properly evaluated.
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-12-V. Management Meetings X1 Exit Meeting Summary The inspector presented the results of the inspection to members of licensee management at the conclusion of the inspection on April 9,1998. The licensee acknowledged the findings presented. No proprietary information was identined.
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ATTACHMENT
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l SUPPLEMENTAL INFORMATION l
l PARTIAL LIST OF PERSONS CONTACTED I
Licensee S. Blitchington, ALARA Supervisor G. Bray, Operations Auxiliary Equipment Supervisor L. Bray, Nuclear Licensing and Safety Specialist l
T. Chard, Assistant Manager, Radiation Protection K. Fike, Chemist
l M. Hale, Manager, Radiation Protection B. Houston, Manager, Licensing D. Jones, Radiological /Decon Crewleader l
J. Kuttler, Radwaste Specialist, Radiation Protection l
L. Lockard, Chemistry Supervisor l
l L. Newman, Operations Manager l
M. Peckham, Plant Manager l
R. Sessoms, Senior Manager, Quality Assurance l
J. Teten, Crew Leader, Chemistry l
N. Thoms, Environmental / industrial Safety Specialist l
B. Toline, Audit Supervisor, Quality Assurance l
C. Weers, Radiological Support Supervisor l
B. Williams, Radiation Protection Technician NRG l
l M. Miller, Senior Resident inspector
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l LIST OF INSPECTION PROCEDURES USED IP 84750 Radioactive Waste Treatment and Effluent and Environmental Monitoring LIST OF DOCUMENTS REVIEWED I
Procedures l
l 2.0 Internal Audit Program, Revision 4.5 l
2.5.2.3 Radwaste High Conductivity Liquid Waste Floor Drain Sample Tank Fluid Transfer, Revision 41
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4.15 Elevated Release Point and Building Radiation Monitoring Systems, Revision 19 l
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8.2.1 Chemistry Analysis and Instrument Calibration Schedule, Revision 21 i
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2-8.8.4 Off-Gas Grab Samples Isotopic Analysis, Revision 11.1 8.8.8 Particulate, lodine, and Noble Gas Sample Collection for Effluent Monitors, Control Building Intake, and Drywell Air Monitor, Revision 18 8.8.11 Liquid Radioactive Waste Discharge Authorization, Revision 17 8.11.1 Effects Program, Revision 6 8.4.1.1 Post-Accident Sampling System, Revision 12 i
Surveillance Tests
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6.HV.101 Control Room Ventilation, Revision 2 6.HV.103
, Control Room Emergency Fan Filter Train Differential Pressure Test, Revision 1 6.HV.104 Control Room Emergency Fan Charcoal and HEPA Filter Leak Test, Fan Capacity Test, and Charcoal Sampling, Revision 0
6.HV.105 Control Room Envelope Pressurization Test, Revision 4 6 HV.301 Turbine Building Ventilation Flow Monitors Calibration and Functional Test, Revision 1 C1 6.HV.302 Reactor Building Ventilation Flow Monitor Channel Calibration and Functional Test, Revision 1 C1 6.HV.304 Radwaste Buildings Ventilation Flow Monitor Channel Calibration and Functional Test, Revision 1 i
6.OG.301 Off Gas System Auto Isolation Functional Test, Revision 1 6.OG.303 Off-Gas Flow Monitor Calibration, Revision 0 6.PRM.301 Off-Gas Radiation Monitor Source Check Test, Revision 1 6.PRM.302 Off-Gas Radiation Monitor Linearity Test and Efficiency Determination, Revision 1 6.PRM.303 SW Radiation Monitor Source Check, Revision 1 6.PRM.304 SW Radiation Monitor Source Check and Functional Test, Revision 1.12C 6.PRM.305 SW Radiation Monitor Calibration Check and instrument Channel Test, Revision 1 6.PRM.306 Liquid Radwaste Effluent Flow Monitor Channel Calibration, Revision 0 6.PRM.307 Liquid Radwaste Effluent System Channel Calibration and Channel Functional Test, Revision 1 6.PRM.308 Liquid Radwaste Effluent System Channel Calibration, Revision 1 6.PRM.309 ERP Kaman Monitor Functional Test, Revision 1 C1 l
6.PRM.310 ERP Kaman Monitor Channel Calibration, Revision 4 i
6.PRM.312 Reactor Building Kaman Monitor Functional Test, Revision 1 6.PRM.313 Reactor Building Kaman Monitor Channel Calibration, Revision 2 6.PRM.314 Turbine Building Kaman Monitor Functional Test, Revision 1
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6.PRM.315 Turbine Building Kaman Monitor Channel Calibration, Revision 2 6.PRM.318 Control Room Air Sampling System Functional and Logic Test, Revision 2 6.PRM.319 RW/ARW Kaman Monitor Functional Test, Revision 1 6.PRM.320 Radwaste Buildings Kaman Monitor Channel Calibration, Revision 2 l
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6.10G.301 Augmented Off-Gas Hydrogen Monitor Channel Calibration and Functional, Revision 2 C1 6.1 PRM.304 Reactor Building Ventilation Radiation Monitor Calibration and Functional Test / Source Check, Revision 1 6.1PRM.305 Off-Gas Radiation Monitor Channel Calibration and Functional Test, Revision 1C1 i
6.1 PRM.306 Off-Gas Radiation Monitor Channel Functional Test, Revision 3 6.1 PRM.311 Reactor Building Ventilation Radiation Monitor Source Check, Revision 1 6.1SGT.101 A SGT Filter Differential Pressure, Heater Output, and Fan Motor Running l
Current Test, Revision 0 6.1 SGT.301 SGT Operability Test /Off-Gas Flow Monitor Functional Test, Revision 2 C4
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6.1SGT.401 SGT A Charcoal Filter Leak Test SGT A, Fan Capacity Test, Cooling Flow Test and Check Valve IST, Revision 2 6.1SGT.501 SGT A HEPA Filter and Component Leak Test, Revision 2 l
6.1SGT.601. SGT A Charcoal Filter Carbon Analysis - Methyl lodide, Revision 1 6.1SJAE.301 Steam Jet Air Ejector Flow Monitor Channel Calibration and Channel Functional Test, Revision 1 6.2OG.301 Augmented Off-Gas Hydrogen Monitor Channel Calibration and Functional, i
Revision 2 C1 6.2PRM.304 Reactor Building Ventilation Radiation Monitor Calibration and Functional Test / Source Check, Revision 1 6.2PRM.305 Off-Gas Radiation Monitor Channel Calibration and Functional Test, Revision 11C 6.2PRM.306 Off-Gas Radiation Monitor Channel Functional Test, Revision 4 6.2PRM.311 Reactor Building Ventilation Radiation Monitor Source Check, Revision 1 6.2SGT.101 B SGT Filter Differential Pressure, Heater Output, and Fan Motor Running Current Test, Revision 0 6.2SGT.301 SGT Operability Test!Off-Gas Flow Monitor Functional Test, Revision 2 C3 6.2SGT. '.31 SGT B Charcoal Filter Leak Test SGT B, Fan Ca.oacity Test, Cooling Flow Test and Check Valve IST, Revision 1 6.2SGT.501 SGT B HEPA Filter and Component Leak Test, Revision 1 6.2SGT.601 SGT B Charcoal Filter Carbon Analysis - Methyl lodine, Revision 1 6.2SJAE.301 Steam Jet Air Ejector Flow Monitor Channel Calibration and Channel Functional Test, Revision 1 Quality Assurance Documents Chemistry Self-Assessment 1997 (12/17/97)
1997 2000 Internal Audit Schedule Quality Assurance Audit 97-11. ASP-406," Chemistry," July 31 through August 14,1997 Vendor Audits performed by NUPIC l
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-4-Miscellaneous Documents Organization Chart - Radiological Department - February 1998 Offsite Dose Assessment Manual-5/20/97 Chemistry Training Records i
Annual Operating Report Radioactive Effluents - 1995,1996,1997 (draft)
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