ML20148R447
| ML20148R447 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 07/02/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20148R435 | List: |
| References | |
| 50-416-97-10, NUDOCS 9707070392 | |
| Download: ML20148R447 (24) | |
See also: IR 05000416/1997010
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ENCLOSURE
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U.S. NUCLEAR REGULATORY COMMISSION
l REGION IV
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l Docket No.: 50-416
License No.: NPF-29 -
Repod No.: 50-416/97-10
Licensee: Entergy Operations, Inc.
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Facility: Grand Gulf Nuclear Station
Location: Waterloo Road i
Port Gibson, Mississippi
Dates: June 2-5,1997
Inspectors: J. Blair Nicholas, Ph.D.
Senior Radiation Specialist
Gilbert L. Guerra
Radiation Specialist
Headquarters Stephen P. Klementowicz
Support: Health Physicist, Office of Nuclear Reactor Regulation
Approved By: Blaine Murray, Chief
Plant Support Branch
ATTACHMENTS:
Attachment 1: Supplemental Information
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Attachment 2: Summary of Annual Radioactive Effluent Release Report Data
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9707070392 970702
PDR ADOCK 05000416
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EXECUTIVE SUMMARY
Grand Gulf Nuclear Station
NRC Inspection Report 50-416/97-10 .
Plant Sunoort
- The liquid and gaseous radioactive waste effluent management programs were
effectively implemented. Offsite doses to the environment from the liquid and
gaseous radioactive waste effluents were within regulatory limits (Section R1.1).
- Although reductions have occurred during the past 2 years, with significant
reductions for the first 6 months of 1997, the licensee has historically released
higher than the boiling water reactor industry's average volumes of liquid
radioactive waste. The tritium activity released annually was the highest in the
industry for boiling water reactors (Section R1.1).
- The engineered-safety feature air cleaning ventilation systems were properly
maintained and tested (Section R1.2).
- The radiological environmental monitoring program was effectively implemented
(Section R1.3).
- A commitment was made to re-instate the sampling of fish media at a reduced
frequency of annually (Section R1.3).
- An effective meteorological monitoring program was implemented (Section R1.4).
- The radiochemistry counting room analytical instrumentation was properly
maintained, tested, and calibrated (Section R2.1).
- Liquid and gaseous radioactive waste management systems were installed and
operated properly (Section R2.1).
- Liquid and gaseous effluent radiation monitoring instrumentatien was operable and
properly maintained, tested, and calibrated (Section R2.2).
- Environmental sampling stations were properly n.aintained with operable and
calibrated equipment (Section R2.3).
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- The meteorological towers were properly maintained with calibrated
instrumentation. Meteorological data recovery was greater than 90 percent
(Section R2.4).
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- Revisions to the offsite dose calculation manual were properly documented.
- Program implementing procedures were maintained and contained sufficient detail
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Annual radioactive effluent release reports and annual radiological environmental
j operating reports for 1995 and 1996 were submitted in a timely manner and
contained the required information (Section R3.2).
- Chemistry personnel had an excellent understanding of the radioactive liquid and
gaseous waste effluent management program, radiological environmental monitoring
program, offsite dose caiculation manual, and regulatory requirements (Ssction R4).
Training and qualification programs for senior radiochemists, chemistry specialists,
and radwaste operators were properly implemented. A trained and qualified staff
for conducting radioactive waste effluent processing, effluent release operations,
radiological environmental monitoring program activities was maintained
(Section RS).
- In the past 1 % years, the chemistry department experienced approximately a
20 percent staff reduction including the two current vacancies. The radwaste
operations staff changed very little (Section R6).
- Oversight of the radioactive waste effluent management program and the
radiological environmental monitoring program was good. The quality assurance
audit and surveillance reports of the radiological waste effluent management
program and radiological environmental monitoring program activities were
technically comprehensive and provided good program evaluation (Section R7.1).
- There was appropriate evaluation of the contractors' performance (Section R7.2).
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Report Details
Summarv of Plant Status
The unit was at power operations during the inspection. There were no operational l
occurrences that impacted the results of the inspection.
IV. Plant Support
R1 Radiological Protection and Chemistry Controls
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R1.1 Radioloaical Waste Effluent Manaaement Proarams I
a. Insoection Scope (84750) I
implementation of the radioactive waste effluent management program, as
described in the offsite dose calculation manual and the technical requirements
manual, o as reviewed. This review included: Radioactive effluent waste
processin > radioactive effluent waste sampling and analyses, analytical sensitivities
and resul ,, offsite dose results, and performance of required surveillance tests.
The follow r.g activities were observed:
Collection of the weekly air particulate filters and charcoal cartridges from
the offgas/radwaste building vent, turbine building vent, containment building
vent, and fuel handling building vent on June 3,1997, and performance of
radiochemistry analyses (principal gamma emitters) of the samples.
Collection of the monthly tritium and noble gas samples from the radwaste
building vent on June 4,1997, and the performance of the required
surveillance testing analyses to monitor the continuous effluent release point.
Updating of the chemistry department's computer data base with the current
monthly and quarterly composite sample analytical data for liquid and
gaseous effluents.
b. Observations and Findinas
The inspectors noted that during the performance of the observed activities the
responsible chemistry personnel referred to and followed the appropriate sampling
and analytical procedures while performing the sample collections and analyses.
The required sampling, testing, approvals, and release controls for the liquid and
gaseous effluent sample collections and analyses were performed in accordance
with technical requirements manual and offsite dose calculation manual
requirements.
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Based on the review of six batch liquid radioactive waste effluent release permits
and selected gaseous radioactive waste effluent sample analyses for samples from,
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the four continuous ventilation release points for the period January 1996 through
May 1997, the inspectors verified that the processing, sampling, analyses, and ,
monitoring of the batch liquid radioactive waste effluents and the continuous
i discharges of the radioactive gaseous waste effluents were conducted properly.
] Quantities of radionuclides released were within the limits specified in the offsite
dose calculation manual. Offsite doses were calculated according to offsite dose
- calculation manual methodologies and were within regulatory limits. Required
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analyses of monthly and quarterly composite samples of liquid and gaseous
radioactive waste effluents were performed in accordance with offsite dose
. calculation manual requirements. ,
in recent years, the licensee released higher than the boiling water reactor
industry's average volumes of liquid radioactive waste, and during 1993 through
1996, the licensee's release volume of liquid radioactive waste was the highest for
boiling water reactors nationally. However, the inspectors noted that during the
past 2 years the licensee had reduced the number of liquid batch releases and the
liquid effluent volume released from the plant. The liquid effluent data for the first
6 months of 1997 showed a significant decrease in the volume of liquid radioactive -
waste released.
During 1993 through 1996, the tritium activity levels increased due to increased
boron concentration in the reactor water as a result of stress corrosion cracking of
the control blade absorber tubes. Tritium activity increases based on control blade
depletion reached a maximum in 1996. Control blade replacement is scheduled for
future refueling outages with the expectation that the tritium activity released will
decrease in the liquid and gaseous radioactive waste releases. The licensco's
tritium activity released annually has been the worst in the industry for boiling water
reactors. The control blade degradation had also affected, to a minor extent, an
increase in fission and activation products in both the liouid and gaseous radioactive
waste effluents as shown in Attachment 2. However, the summary of dose data in ;
Attachment 2 shows that the annual do ;es from liquid and gaseous radioactive (
effluents was not significantly affecter by the increased tritium, fission, and
activation product activity.
c. Conclusions
The liquid and gaseous radioactive waste effluent management programs were
effectively implemented. Proper sample handling techniques were used by the
licensee while collecting and handling samples. Quantities of radionuclides released
in the liquid and gaseous radioactive waste effluents were within the offsite dose
calculation manual limits. Offsite doses to the environment from the liquid and
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gaseous radioactive waste effluents were calculated using offsite dose calculation
manual methodologies. Although reductions have occurred during the past 2 years,
with significant reductions for the first 6 months of 1997, the licensee has
historically released higher than the boiling water reactor industry's average .
volumes of liquid radioactive waste.- The tritium activity released annually was the
highest in the industry for boiling water reactors.
R1.2 Enaineered-Safety Feature Air Cleanina and Control Room Habitability Systems
a. Inspection Scope (84750)
Selected surveillance tests and test results for the engineered-safety feature air
cleaning ventilation systems' testing program were reviewed to determine
compliance with the requirements in Technical Specifications 3.6.4.3 and 3.7.3 and
the station's ventilation filter testing program in Technical Specification 5.5.7.
b. Observations and Findinas
The engineered-safety feature air cleaning ventilation systems contained high
efficiency particulate air filters and activated charcoal adsorbers.
The inspectors performed a visual inspection with the system engineer of the
standby gas treatment system and the control room fresh air system. The visual
inspection of the filtration systems did not identify any problems. No external
damage to the filtration units was identified. All filter housings and ducts were well ;
maintained. The areas surrounding the filtration units were clean, free of debris, '
and the filtration units were adequately lighted inside and outside to provide for
visual inspection of housings and components.
The surveillance testing program included the required periodic functional checking l
of the ventilation systems' components, evaluation of the high efficiency particulate l
air filters and activated charcoal adsorbers, and in-place filter testing of the high i
efficiency particulate air filters and charcoal systems. Since some of the j
surveillance tests were only required to be performed every 18-months, the l
inspectors reviewed the last completed surveillance test and verified that the
previous two surveillance tests were performed as required at the 18-month !
frequency. Selected records and results of surveillance tests for the period January 1
1996 through May 1997 for the standby gas treatment system (Trains A and B) and
the control room fresh air system (Trains A and B) verified that the required
surveillance tests were performed. The activated charcoal efficiency tests were
properly performed by an offsite contract laboratory. All surveillance test results
were verified to be within Technical Specification limits. ;
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The Technical Specification requirement for testing the air cleaning 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
following the previous laboratory testing was tracked by the control room and the
system engineer. .
c. , Conclusions
The engineered-safety feature air cleaning ventilation systems' surveillance program
was properly implemented. All surveillance test results met Technical Specification
requirements.
R1.3 Radioloaical Environmental Monitorina Proaram
a. Insoection Scone (84750)
The inspectors reviewed the radiological environmental monitoring program to
determine compliance with the requirements in the offsite dose calculation manual.
The inspectors reviewed in detail the reductions to the radiological environmental
monitoring program implemented in July 1996,
b. Observations and Findinos
The inspectors visited selected environmental media sampling locations associated
with the radiological environmental monitoring program. The following types of
sampling locations were inspected: airborne, surface water, and vegetation. The
inspectors verified that the environmental sampling stations were located as
required in the offsite dose calculation manual. Also, the inspectors accompanied
and observed an environmental specialist collect air particulate and charcoal
cartridge samples for shipment and analysis. All sample analyses for the
radiological environmental monitoring program were performed by the offsite
Entergy System's environmental laboratory. The collection, processing, and
analytical requirements for radiological environmental media samples were
conducted in accordance with the offsite dose calculation manual.
Changes to the radiological environmental monitoring program were made and the
offsite dose calculation manual was revised accordingly. Several of the
environmental media sample types were reduced both in number of samples and in
the frequency of sampling. The inspectors found that the licensee reduced the
radiological environmental monitoring program in general agreement with regulatory
guidance. Regulatory Guide 4.1, " Programs for Monitoring Radioactivity in the
Environs of Nuclear Power Plants," Revision 1, April 1975, provides guidance
acceptable to the NRC staff. This regulatory guide states, ". . . if the licensee is
able to demonstrate from levels in environmental media or calculations that the
doses and concentrations associated with a particular pathway are sufficiently
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small, the number of media sampled in the pathway and the frequency of sampling
may be reduced. An adequate program with emphasis on indicator organisms and
selected media should still be continued in order to confirm that the levels of
radioactivity in environmental media remain small." .
The inspectors reviewed all changes to the radiological environmental monitoring
program. The inspectors noted that the requirement for sampling fish media was
removed from the radiological environmental monitoring program. Specifically, the
requirement for sampling fish media was removed based on historical analytical data
and the rationale that fish are not confined to and do not congregate in the
discharge area as stated in the licensee's evaluation.
The inspectors noted that the bases documented in the licensee's Technical
Requirements Manual, Section 7.6.3.2, for the radiological environmental monitoring
program states that a program shall be provided to monitor the radiation and
radionuclides in the environs of the plant. The program shall provide (1)
representative measurements of radioactivity in the highest potential exposure
pathways, and (2) verification of the accuracy of the effluent monitoring program
and modeling of environmental exposure pathways. Also, the licensee stated in
their annual radioactive effluent release reports that the maximum dose contribution
from liquid effluents was considered to occur in the adult age group via
consumption of fish. Based on the above information, the inspectors determined l
that the reasons for the elimination of the environmental fish sample media was
inappropriate in that an evaluation was not performed to establish a technical basis ;
for eliminating the fish sample. )
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The inspectors noted that fish samples were collected in June 1996, and June I
1997. Therefore, the intervals between samples did not exceed one year. j
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During the inspection, the inspectors received a commitment from the chemistry
superintendent that the licensee would re-instate sampling of the fish media at the
reduced frequency of annually. This commitment was confirmed during the exit i
meeting on June 5,1997.
c. Conclusions
The radiological environmental rnonitoring program was effectively implemented.
Reductions to the environmental monitoring program were made in accordance with
NRC guidance. A commitment was made to re-instate the sampling of fish media at
a reduced frequency of annually.
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R 1,4 Meteoroloaical Monitorina Proaram
a. Insoection Scoce (84750) ,
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The inspectors reviewed the meteorological monitoring program to determine I
agreement with the recommendations of NRC Regulatory Guides 1.23 and 1.97, l
and compliance with Technical Requirements Manual, Section 6.3.3. {
Meteorological data collection and data review procedures were reviewed, and the !
data were discussed with licensee personnel.
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b. Observations and Findinas
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The licensee utilized two meteorological towers equipped with the required
instrumentation. The instrumentation was in agreement with the guidance in
Regulatory Guide 1.23. Data from the meteorological instrumentation were
collected by the plant computer and displays of the meteorological data were
available to operations personnel and at the emergency facilities. Licensee
procedures for the review and verification of meteorological data were maintained. l
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c. Conclusions
An effective meteorological monitoring program was implemented. A proper
meteorological data collection and review program was established. The
performance of the meteorological monitoring program agreed with regulatory
guidance.
R2 Status of Radiological Protection and Chemistry Facilities and Equipment
R2.1 Radiochemistry Countina Room and Radioactive Waste Effluent Processina System
a. Inspection Scope (84750)
The inspectors observed analytical measurements of radiological effluent samples
performed in the radiochemistry counting room. The radioactive liquid and gaseous
waste processing equipment were inspected. Equipment inspected in the radwaste
building included the equipment drain waste collection tank, floor drain waste
collection tank, the liquid radioactive waste processing equipment, and the gaseous
radioactive wa: te processing equipment.
b. Observations and Findinas
The radiochemistry counting room maintained sufficient state-of-the-art analytical
instrumentation to perform the required sample analyses of the liquid and gaseous
radioactive waste effluents. The instrumentation was properly calibrated and well
maintained. Records of calibrations and daily operational quality contr'al checks
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, were maintained. Senior radiochemists assigned to the radiochemistry counting
- . room were knowledgeable on the use of the instrumentation.
The liquid radioactive waste processing and storage systems were installed as ,
j described in the Updated Final Safety Analysis Report and were operated in
accordance with station procedures.
, The gaseous radioactive waste processing system was installed as described in the 4
l_ Updated Final Safety Analysis Report and was operated in accordance with station
. procedures.
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j- No major equipment or design modifications were made to the liquid or gaseous
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radioactive waste effluent management systems.
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c. Conclusions ;
j' The radiochemistry counting room analytical instrumentation was properly
j maintained, tested, and calibrated. Liquid and gaseous radioactive waste
! management systems were installed and operated properly.
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l R2.2 Liauid and Gaseous Effluent Radiation Monitors
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a. Inspection Scoce184750)
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j- The liquid and gaseous effluent radiation monitors were inspected for operation,
- calibration, and reliability. ' The liquid and gaseous radioactive waste effluent
radiation monitor source check, channel check, channel functional test, and channel
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- calibration records were reviewed to determine compliance with Technical
j Requirements Manual, Sections 6.3.9 and 6.3.10, and the Offsite Dose Calculation
j- Manual, Tables 6.3.91 and 6.3.10-1.
b. Observations and Findinas l
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- All surveillance test records reviewed for the period January 1996 through May i
- 1997 indicated that the liquid and gaseous radioactive waste effluent monitoring l
l instrumentation were properly maintained, tested, and calibrated in compliance with !
the surveillance requirements specified in the technical requirements manual and
offsite dose calculation manual.
c. Conclusion
Liquid and gaseous effluent radiation monitoring instrumentation was operable and
properly maintained, tested, and calibrated.
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R2.3 Environmental Monitorina Eauipment and Facilities
a. Inspection Scope (84750)
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The inspectors visited selected environmental sampling stations to verify that
stations were properly maintained and equipment was operable and properly
calibrated. Sample preparation and storage facilities were inspected to verify that l
sufficient supplies and spare equipment were available.
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b. Observations and Findinas l
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Air sampling equipment in use was operational and properly calibrated. The l
environmental specialists were responsible for the calibration of the air samplers.
The environmental sample storage and shipment preparation facility was stocked
with the necessary equipment and supplies to perform the required radiological
environmental monitoring program sampling activities and the preparation of the
environmental samples for shipment to the offsite environmental laboratory. The
inspector determined that environmental samples were properly prepared for
shipment to the offsite environmental laboratory for analyses.
c. Conclusions
Sufficient supplies and spare environmental sampling equipment to perform the
environmental sampling activities required in the offsite dose calculation manual
were maintained. Environmental sampling stations were properly maintained with
operable and calibrated equipment.
R2.4 Meteorotoaical Monitorina Eauioment (84750)
a. Inspection Scope
The inspectors inspected the meteorological instrumentation at the meteorological
towers and reviewed the associated calibration records to ensure that the
meteorological instrumentation on the towers was operable, calibrated, and
maintained in accordance with written procedures and the guidance in Regulatory
Guide 1.23. Selected meteorological monitoring instrumentation calibration
procedures and associated records were reviewed.
b. Observations and Findinas
The instrumentation at the two meteorological towers was operational and properly
calibrated. The meteorological sensing and recording equipment was calibrated
semiannually by the licensee's instrument and controls technicians. The calibrations
were conducted in accordance with approved procedures for wind speed, wind
direction, and air temperature difference. The primary meteorological tower was
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equipped with dual instrumentat!on (Channels A and B) for wind speed, wind ,
direction, and temperature sensing instrumentation at the 10 and 50 meter l
elevations. Also, the licensee maintained a secondary meteorological tower with
i wind speed, wind direction, and temperature sensing instrumentation at a 10 meter
elevation. Backup power to the towers was provided by batteries and an electrical
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generator. Meteorological data was available in the control room and emergency
response facilities via the plant computer. All records reviewed indicated that the
meteorological monitoring instruments were properly maintained, tested, and
calibrated at required frequencies.
The licensee had obtained greater than 90 percent meteorological data recovery !
during the period January 1996 through May 1997.
c. Conclusions ,
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The meteorological towers were properly maintained with allinstrumentation
calibrated at the required frequency. Meteorological data recovery was greater than
90 percent.
R3 Radiological Protection and Chemistry Procedures and Documentation
R3.1 Chanaes to the Offsite Dose Cdculation Manual and Procedures
a. Insoection Scoce (84750).
Revisions to the offsite dose calculation manual were reviewed for any changes to
the radioactive waste affluent management program, radiological environmental
monitoring program, and the radwaste system design and operation, including the
performance of proper 10 CFR 50.59 reviews, and changes to the implementing
procedures regarding the radioactive waste effluent management program and the
radiological environmental monitoring program.
Procedures for the sampling, analysis, and release of radioactive liquid and gaseous
waste effluents and procedures for the collection and processing of environmental
media samples were reviewed.
b. Observations and Findinas
Revisions 17,18,19, and 20 to the offsite dose calculation manual were issued
since the last NRC inspection conducted in January 1996. The revisions
implemented changes resulting from the Improved Technical Specifications which
incorporated updated meteorological parameters used in calculation of gaseous
effluent doses and noble gas setpoints, added the reverse osmosis system
, equipment to the liquid radwaste treatment system diagram, added a table showing
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deposition constants at the nearest residence in each meteorological sector,
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modified the sampling requirements for an inoperable offgas pretreatment radiation
monitor, sampling and analyses reductions affecting the radiological environmental )
monitoring program. The results of the changes to the radiological environmental . ,
monitoring program are discussed in Section R1.3. '
' The radioactive waste effluent management program's implementing procedures
described the responsibilities for collection and analyses of liquid and gaseous
radioactive waste effluent samples. Procedures for batch release of liquid
radioactive waste effluents provided proper guidance regarding sampling, tank
recirculation, analyses, release limits, monitoring, and approvals. The procedures
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were written with sufficient detail to effectively conduct the required radioactive
waste management program activities. The inspectors reviewed the sample .
collection procedures and identified no concerns. l
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c. Conclusions l
Revisions to the offsite dose calculation manual were properly documented. ,
Program implementing procedures were maintained and contained sufficient detail. !
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R3.2 Annual Reports
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a. Insoection Scope (84750)
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The inspectors reviewed the annual reports for 1995 and 1996 concerning the j
radiological effluent management program and the radiological environmental '
monitoring program activities to determine compliance with the requirements of
Technical Specifications 5.6.2 and 5.6.3 and the offsite dose calculation manual.
These documents were reviewed for omissions, obvious mistakes, anomalous
measurements, observed biases, trends in the data, and laboratory inter-
comparisons.
b. Observations and Findinas
The annual radioactive effluent release reports for 1995 and 1996 were written in j
the format described in NRC Regulatory Guide 1.21, Revision 1, June 1974, and '
contained the required information. Summaries of the quantities of radioactive
liquid and gase effluents released to the environment, and their associated doses
to members of .ie public were properly documented in the reports. A summary of
the radioactive liquid and gaseous effluent releases and associated doses is
presented in Attac' nent 2 to this report.
The annual reports documented changes to the offsite dose calculation manual as
required.
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Effluent monitoring instrumentation was not out of service in excess of Technical
Specification requirements during the time period reviewed.
During 1995 and 1996 seven unplanned gaseous releases occurred via the turbine
building smoke exhaust hatches and were properly documented in the annual
radioactive effluent release reports. Each of the unplanned releases was evaluated
as a ground level release and included in the gaseous effluent release data from the
plant. The inspectors noted that the unplanned gaseous releases had no significant
effect on the total gaseous effluents released from the plant.
Sample results, included in the 1995 and 1996 annual radiological environmental
operating reports, indicated that environmental media sampling and analyses were
performed as required. Discrepancies or missed samples were reported as required.
The inspectors noted that sampling, analyses, and reporting requirements were met.
The annual land use censuses were conducted as required, and the results were
included in the annual reports.
c. Conclusions
Annual radioactive effluent release reports and annual radiological environmental
operating reports for 1995 and 1996 were submitted in a timely manner and
contained the required information.
R4 Staff Knowledge and Performance
a. inspection Scope (84750)
Personnel in the chemistry department were observed and interviewed to determine
their knowledge of regulatory and offsite dose calculation manual requirements
regarding the implementation of the liquid and gaseous radioactive waste
management program and the radiological environmental monitoring program,
b. Observations and Findinas
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The inspectors observed senior radiochemists perform some of their duties and
responsibilities in the implementation of the radioactive waste effluents program and
determined that they were familiar with the requirements of the radioactive waste
management program. Chemistry personnel including supervisors and technical
staff were knowledgeable of the programmatic procedures, offsite dose calculation
manual requirements, and regulatory requirements and maintained a high level of
performance. Batch radioactive liquid waste effluent releases and continuous
radioactive gaseous waste effluent releases were properly performed during the
period January 1996 through May 1997.
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The inspectors noted that good practices were used by the environmental
specialists in maintaining sample integrity. All activities observed were conducted
in an orderly fashion. The inspectors noted that the licensee's staff knowledge of
sampling procedures, offsite dose calculation manual, and NRC requirements was .
excellent.
c. Conclusions
Chemistry personnel had an excellent understanding of the radioactive liquid and
gaseous waste effluent management program, radiological environmental monitoring l
program, offsite dose calculation manual, and regulatory requirements.
R5 Staff Training and Qualification
a. Inspection Scooe (84750)
Training and qualification programs for senior radiochemists and radwaste operators
responsible for implementing the radioactive waste effluents management program
were reviewed.
Training and qualifications of senior radiochemists and radwaste operators were
verified.
The training and qualification program for the chemistry specialists responsible for
implementing the radiological environmental monitoring program were reviewed.
b. Observations and Findinas
The training and qualification programs for radwaste operators and chemistry
technical staff included required formal classroom training and on-the-job training.
The inspectors determined that proper training and qualification programs were
implemented for the radwaste operators and the chemistry technical staff.
Nine senior radiochemists had completed the required training to be qualified to
perform all radioactive waste effluent management program activities, and three
chemistry specialists were trained and qualified to perform all radiological
environmental monitoring program activities.
Completed qualification cards documented that nine radwaste operators were
trained and qualified.
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c. Conclusions
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Training and qualification programs for senior radiochemists, chemistry specialists,
and radwaste operators were properly implemented. The experience, training, and
working knowledge of the chemistry department and the operations department
personnel met the training and qualification requirements for conducting radioactive
waste liquid and gaseous effluent processing and release operations and
environmental monitoring activities.
R6 Radiological Protection and Chemistry Organization and Administration
a. Inspection Scope (84750)
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Organization, staffing, and lines of authority of the chemistry and radwaste
operations departments, which were responsible for implementing the radioactive
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waste effluent management program and the radiological environmental monitoring
program responsibilities, were reviewed.
Administrative and chemistry departmental procedures were reviewed for the
assignment of responsibilities for the management and implementation of the l
radioactive waste effluent management program and the radiological environmental
monitoring program,
b. Observations and Findinas
Chemistry and radwaste operations personnel were responsible for the
implementation of the radioactive waste effluent management program and the
radiological environmental monitoring program. Management controls were
effective in implementing the required programs. Since the previous NRC
inspection, the personnel responsible for the radiological environmental monitoring
program were incorporated into the chemistry department.
The chemistry department was adequately staffed. However, there had been
changes in the chemistry technician staff during the past 1 % years. The chemistry
department had reduced the number of chemistry positions from 32 to 28. The !
chemistry department currently has two positions vacant. The chemistry i
superintendent assumed the position in September 1996, and one new chemistry i
radiochemist was hired in February 1997. The licensee's reduction in chemistry
staff did not appear to have adversely affected implementation of the radioactive !
waste effluent management program and the radiological environmental monitoring j
program.
The radwaste operations department was adequately staffed, and personnel had not
changed significantly during the past 1 % years.
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Staffing of the chemistry and radwaste operations departments met Technical ;
j Specification requirements, in the past 1 % years, the chemistry department .
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experienced approximately a 20 percent staff reduction including the two current
- vacancies. The radwaste operations staff changed very little. )
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R7 Quality Assurance in Radiological Protection and Chemistry Activities
F R7.1 Radioactive Waste Effluent Quality Assurance Proaram
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- a. Insoection Scope (84750)
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j Quality assurance audit and surveillance reports concerning the radioactive waste
l effluent management program and radiological environmental monitoring program
activities were reviewed for scope, thoroughness of program evaluation, and timely
followup of identified deficiencies and to determine compliance with Technical
Requirements Manual, Section 7.4.2.8. The review included the one annual audit of
- the combined programs and the one surveillance of the radiological environmental
monitoring program performed since January 1996.
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The licensee's standard audit plan for developing audits of Regulatory Guide 4.15
and the offsite dose calculation manual and implementing procedures was reviewed.
l The qualifications of the quality assurance auditors were reviewed.
b. Observations and Findinas
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The Master Audit Plan, Revision 23, issued February 13,1997, and the'1997 Audit
{ Program Plan, issued December 17,1996, showed scheduled and completed audits
i for the period 1995 through 1997. The master audit plan indicated that the audits
of the radioactive waste effluent management program, radiological environmental
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monitoring program, the offsite dose calculation manual, and Regulatory Guide 4.15
i were being performed concurrently on an annual frequency. The audit schedule
l was in compliance with the technical requirements manual and quality assurance
audit procedures.
! Annual audits encompassing the radioactive waste effluent management program,
- radiological environmental monitoring program, offsite dose calculation manual, and
implementing procedures were performed in accordance with the technical
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requirements manual requirements.
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The quality assurance radioactive waste effluent management program and
e radiological environmental monitoring program audit and surveillance report of the
- radiological environmental program performed since January 1996 were conducted
! in accordance with quality assurance procedures by qualified auditors, who were
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knowledgeable in radiological waste effluent programs, radiological environmental
j monitoring programs, and offsite dose calculation manual requirements at nuclear
power facilities. The audit report of the radioactive waste effluent management and
radiological environmental monitoring programs was of high quality, technically .
comprehensive, and provided good oversight and evaluation of the licensee's
performance in implementing the radioactive waste effluent management program
and the radiological environmental monitoring program,
c. Conclusions
Oversight of the radioactive waste effluent management program and the
radiological environmental monitoring program was good. The quality assurance
audit and surveillance reports of the radiological waste effluent management
program and radiological environmental monitoring program activities were I
technically comprehensive and provided good program evaluation. I
R7.2 Rurfity
u Assurance Proaram for Contractors
a. Inspection Scope (84750)
The quality assurance vendor audit program regarding contractors and the offsite
environmental laboratory performing surveillance activities involving the radioactive
waste effluent program, radiological environmental monitoring program, and
engineered-safety feature air cleaning ventilation systems was reviewed.
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b. Observations and Findinas
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A contractor laboratory was used to perform required radiochemistry analyses of
liquid and airborne particulate radioactive waste effluent composite samples. A
second contractor was used to perform in-place filter testing of the station's
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engineered-safety feature ventilation systems and perform laboratory analyses of
the charcoal adsorber material. River Bend Station's environmental laboratory was ;
used to perform analyses of the radiological environmental samples.
The licensee used nuclear procurement issues committee audits of the two
contractors and an audit of the River Bend Station's environmental laboratory
performed by River Bend Station's quality assurance department to evaluate the
performance of the contractors and enviror. mental laboratory in performing their
respective surveillance testing requirements. The audits were comprehensive and
satisfactory to evaluate each of the contractor's abilities to perform their respective
Technical Specification required analyses and surveillance testing activities,
f c. Conclusion
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There was appropriate evaluation of the contractors' performance.
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V. Manaaement Meetinas
X1 Exit Meeting Summary
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The inspectors presented the results of the inspection to members of licensee
management at the conclusion of the inspection on June 5,1997. The licensee
acknowledged the findings presented. Mr. G. Coker, Chemistry Superintendent,
- committed to reinstate the fish media sampling at an annual frequency. No
proprietary information was identified.
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ATTACHMEMT 1
SUPPLEMENTAL INFORMATION
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PARTIAL LIST OF PERSONS CONTACTED
Licensee -
J. Hagan, Vice President, Operations
C. Abbott, Reviews Supervisor, Quality Programs
R. Benson, Radwaste Supervisor, Radiation Control
R. Buckley, Corporate Environmentalist
W. Cade, Operations Assistant, Operations
G. Coker, Superintendent, Chemistry
D. Cooper, Lead Non-licensed Operator Requalification Training instructor
D. Crawley, Environmental Specialist, Chemistry
J. Czaika, Nuclear Specialist
K. Daniels, Senior Radiochemist, Chemistry
L. Daughtery, Technical Coordinator, Nuclear Safety and Regulatory Affairs
C. Ellis, Training Coordinator, Chemistry
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W. Garner, Audit Supervisor, Quality Programs
M. Guynn, Supervisor, Radiation Control
C. Holifield, Licensing Engineer, Nuclear Safety and Regulatory Affairs
W. Hughey, Director, Nuclear Safety and Regulatory Affairs
R. Ingram, Supervisor, Nuclear Safety and Regulatory Affairs
R. Jackson, Senior Licensing Specialist, Nuclear Safety and Regulatory Affairs
M. Jones, Technical Specialist, Nuclear Safety and Regulatory Affairs
J. Lassetter, Technical Specialist, Chemistry
R. McCann, Senior Radiochemist, Chemistry
M. Michalski, Radwaste Coordinator, Operations
R. Moonaw, Manager, Maintenance
B. Philpott, Senior Radiochemist, Chemistry
J. Purvis, Senior Radiochemist, Chemistry
R. Ruffin, Licensing Specialist, Nuclear Safety and Regulatory Affairs
J. Venable, Manager, Operations
NRC
K. Weaver, Resident inspector
in addition to the personnel listed above, the inspectors contacted other personnel during
this inspection.
LIST OF INSPECTION PROCEDURES USED
IP 84750 Radioactive Waste Treatment, and Effluent and Environmental
Monitoring
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LIST OF DOCUMENTS REVIEWED
Oraanization Charts .
Chemistry Department
Quality Assurance Documents
Master Audit Plan, Revision 23, February 13,1997
1997 Audit Program Plan, December 17,1S96
Standard Audit Plan for Regulatory Guide 4.15 and Offsite Dose Calculation Manual,
Revision O
AUDITS AND SURVEILLANCES
Quality Program Audit Report QPA 12.01-96, " Regulatory Guide 4.15 and Offsite Dose
Calculation Manual," August 5-15,1996
Quality Surveillance Report, " Environmental Sampling," September 10,1996
Vendor Audits
" Yankee Atomic Environmental Laboratory (Y 123)," June 19-20,1995
" Commonwealth Edison NUPIC Audit of NCS Corporation Audit Number G96-10,"
November 18-21,1996
" River Bend Station Quality Assurance Audit of Effluent and Environmental Monitoring
Programs, Audit 96-06-1-ENVL/REMP," June 10 21,1996
PROCEDURES
06-CH-SG17-M-0042, "Radwaste Release Dissolved Gases," Revision 100,
March 20,1995
06-CH-SG17-M-0043, "Radwaste Monthly Composite," Revision 102, August 1,1996
06-CH-SG17-M-0046, " Liquid Effluent Dose Calculations," Revision 101,
, December 9,1996
06-CH-SG17-O-0045, "Radwaste Release Post Release Calculations," Revision 101,
September 26,1996
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06-CH-SG17-P-0041, "Radwaste Release Pre-release Analysis," Revision 102, . l
September 11,1996 I
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06-CH-SG17-O-0044, "Radwaste Release Quarterly Composite," Revision 100, .
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March 20,1995 1
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06-CH-1D17-M-0003, " Building Ventilation Gaseous Tritium," Revision 100,
! January 20,1997 i
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06-CH-1D17-M-0005, " Building Ventilation Exhaust Gaseous Isotopic," Revision 101, ;
February 21,1997 )
- 06-CH-1D17-M-0018, " Gaseous Release Points Particulate Alpha Activity," Revision 101,
!' March 20,1995
06-CH-1D17-Q-0019, " Gaseous Release Points Particulate Sr 89,90," Revision 100,
h March 20,1995
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- 06-CH-1D17-W-0017, " Gaseous Release Points lodine, Tritium, and Particulates," '
Revision 102, November 25,1996
l 06-CH-1N64-M-0033, "Offgas Post Treatment Exhaust Gaseous Isotopic," Revision 102,
October 30,1996
06-CH 1T48-M-0037, " Standby Gas Treatment Exhaust Gaseous isotopic," Revision 101,
February 4,1997
06-CH 1000-M-0049, " Gaseous Effluent Dose Calculations," Revision 100,
March 31,1995
06-CH-1000-M-0050, " Tritium, lodine and Particulates Gaseous Effluent Dose ;
Calculations," Revision 100, March 31,1995 l
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06-CH-1000-M-0059, "31-Day Dose Projectisn," Revision 100, March 20,1995
06-ME-1T48-R-0005, "In-Place Testing of Standby Gas Treatment Filtration System," ,
Revision 101, September 23,1996 I
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! 06-ME-1Z51-R-0006, "in-Place Testing of Control Room Emergency Filtration System,"
Revision 101, September 23,1996 '
l 06-ME-1000-R-0007, " Charcoal Adsorber Chemical Analysis," Revision 100,
i . March 20,1995
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l 08-S-03-1, " Qualification of Chemistry Program," Revision 14, February 17,1997
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08-S 03-9, " Qualification of Chemistry Personnel," Revision 13, February 17,1997
06-EN-S000-V-0001, " Radiological Environmental Sampling," Revision 102,
- September 16,1996 ,
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08-S-09-9, " Review of Radiological Environmental Analytical Results," Revision 3,
May 14,1997
REPORTS
Annual Radioactive Effluent Release Reports - 1995 and 1996
Annual Radiological Environmental Monitoring Reports - 1995 and 1996
Miscellaneous Documents
Offsite Dose Calculation Manual, Revision 20, July 1996
Selected Liquid Radioactive Waste Batch Release Permits
Chemistry department training records l
Radwaste operations department training records
Air cleaning systems surveillance test records
Evaluation 96-0036-R00 for the Radiological Environmental Monitoring Program
Radiological Environmental Program Results 1978-1996
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Attachment 2
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Summary of All Uquid Effluent Releases . l
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1 1993 1994 1995 1996 l
Number of Batch Releases 263 273 225 197
Fission & Activation Products 1.656E-01 2.395E-01 3.525E-01 3.825E-01 -
(Curies)
Tritium (Curies) 62.87 161.70 131.10 216.40
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Dissolved & Entrianed Noble Gases 5.765 E-04 2.444E-04 2.202E-04 1.185E 03 )
(Curies) l
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Waste Volume Released (Uters) 2.681 E + 07 2.780E + 07 2.272E + 07 1,945E + 07 l
Summary of All Airborne Effluent Releases
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Continuous Releases 1993 1994 1995 1996
Fission & Activation Products 94.46 33.54 58.46 93.20
(Curies)
Total lodine-131 (Curies) 4.716E-04 4.901 E-05 1.152 E-04 6.565E-04
Particulates w/Ti a > 8 Days (Curies) 8.877E-05 4.234E-05 7.922 E-05 2.973E-05
Gross Alpha (Curies) 2.681 E-08 1.723E-07 7.590E-08 5.610E-08
Tritium (Curies) 22.92 53.12 45.32 87.90
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Maximum Annual Doses From Gaseous & Uquid Effluent Reieases
1993 1994 1995 1996
Uquid Effluents
Organ (Liver) (mrem) 0.226 0.086 0.094 0.181
Whole Body (mrem) 0.156 0.070 0.049 0.071
Gaseous Effluents
Gamma Air Dose (mrad) 0.021 0.014 0.027 0.041
Beta Air Dose (mrad) 0.023 0.010 0.028 0.045
lodine-131,133, Tritium, and 0.240 0.071 0.061 0.135
Particulates w/T n > 8 Days (mrem)
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