ML20217M549
| ML20217M549 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 04/02/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20217M506 | List: |
| References | |
| 50-482-98-11, NUDOCS 9804080129 | |
| Download: ML20217M549 (18) | |
See also: IR 05000482/1998011
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ENCLOSURE 2
U.S NUCLEAR REGULATORY COMMISSION
REGION IV
Docket No.: 50-482
License No.: NPF-42
Report No.: 50-482/98-11
Licensee: Wolf Creek Nuclear Operating Corporation
Facility:. Wolf Creek Generating Station
. Location: 1550 Oxen Lane, NE
Burlington, Kansas
Dates: March 16-20,1998
Inspector: J. Blair Nicholas, Ph.D., Senior Radiation Specialist
Plant Support Branch
Approved By: Blaine Murray, Chief, Plant Support Branch
Division of Reactor Safety
Attachment: Supplementalinformation
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9804000129 980402
PDR ADOCK 05000482
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EXECUTIVE SUMMARY
Wolf Creek Generating Station
NRC Inspection Report 50-482/98-11
This announced, routine inspection reviewed the implementation of the solid radioactive waste
management and the radioactive waste / materials transportation programs. Training and
qualifications, quality assurance oversight, facilities and equipment, procedural guidance, and
annual reports were also reviewed. Overall, good solid radioactive waste management and the
radioactive waste / materials transportation programs were implemented properly.
Plant Suocort
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A good solid radioactive waste management program was implemented. Waste stream
sampling and analyses met regulatory requirements. Solid radioactive waste was
properly classified and characterized for shipment and disposal. The amount of solid
radioactive waste generated showed a significant reduction from 1993 to 1995. From
1995 through 1997, the amount of solid radioactive waste generated remained fairly
steady at approximately 24 cubic meters. The licensee's 3-year average amount of solid
radioactive waste generated showed that the licensee generated less solid radioactive
waste than the industry's median and near the industry's best quartile for radioactive
waste generated. (Section R1.1)
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A goort transportation program for radioactive materials and radioactive waste was
maintained. Documentation and packages were properly prepared for shipment.
(Section R1.2)
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A violation was identified involving the failure to properly label seven radioactive material
containers. (Section .R1.2)
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Good facilities were maintained for the processing, storage, and management of solid
radioactive wastes and transportation activities. An effective radioactive waste
inventory / accountability system was maintained. Housekeeping in the radioactive waste
storage areas was good. (Section R2)
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Procedures and checklists established to implement the solid radioactive waste
management and transportation programs provided proper guidance for the handling,
processing, and shipping of radioactive waste / materials. (Section R3)
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Personnelinvolved in the transfer, packaging, and transport of radioactive materials and
wastes were properly trained and qualified. (Section R5)
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A proper organization and staff were maintained which effectively implemented the solid
radioactive waste management and transportation programs. (Section R6)
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An effective self assessment program of the solid radioactive waste management and
transportation programs was maintained. Timely and effective corrective actions were
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completed on identified problems. There was appropriate evaluation of the contractors'
performance. (Section R7)
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A noncited violation was identified involving an unqualified chemistry technician -
performing the chemistry shift manning responsibilities alone while the station was in
Mode 4 in January 1992. (Sectior. 8.2)
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A noncited violation was identified involving instrumentation used to analyze particulate
air samples which were not calibrated for the type of radiation measured and resulted in
potentially not posting airborne radioactivity areas. (Section 8.3)
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Report Details
.' Summary of Plant Status .
The plant operated at full power during this inspection.
IV. Plant Support
R1 Radiological Protection and Chemistry (RP&C) Controls
R1.1 - Solid Radioactive Waste Manmaament
a. Insoection Scoon (86750)
The inspector interviewed the radwaste health physics supervisor and radiation
. protection technicians assigned to implement the radwaste program. The following solid
radioactive waste management program activities were reviewed:
L - Waste stream sampling results and waste characterization documentation
l .. _ Scaling factors
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. Solid radioactive waste classification
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Quantities of radioactive waste shipped for disposal
. . Waste minimization program
~. Annual radioactive waste effluent release reports
b. Observations and Findinos
l The inspector verified that waste stream samples were taken annually and analyzed to
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meet 10 CFR Part 61 requirements for waste classification and characterization. Eight -
waste streams were identified that consisted of dry active waste, resins, and filters. The
waste stream samples were analyzed by a contractor laboratory.
The inspector verified that a proper radwaste computer code was used to classify the
radioactive waste. Scaling factors determined from waste stream sample analyses were
updated at lea; a'nually in the radwaste computer code data base. The inspector
verified that the iedwaste computer code was updated with the most current revisions of
- the vendor software following verification and quality control of the revisions.
The inspector attended the prejob briefing for the transfer of spent secondary blowdown
resin to a metal liner for shipment to an off-site processor and also observed the resin
transfer operations. The prejob briefing was conducted to coordinate activities. All
p personnel involved with the resin transfer were given clear direction and appropriate ;
radiologicalinformation. Task assignments cf personnel performing the resin transfer !
were clear. All aspects of the resin transfer were performed in accordance with )
procedure. !
The inspector noted that the licensee had reduced the amount of solid radioactive waste
, generated during the past 5 years. Radworker awareness to minimize radioactive waste j
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when performing their assigned tasks was enhanced through general employee training.
Licensee data trends showed these radwaste minimization efforts were effective.
The volume of solid radioactive waste generated prior to segregation, processing, or i
volume reduction was tracked by the licensee. The summary of the volume of solid I
radioactive waste generated for 1993 through 1997 is presented in the table below. For
1993 through 1997, the licensee's data showed a decline in solid radioactive waste I
generated. The licensee met their waste generation goals established for 1993 through
1997. A comparison of the licensee's 3-year average amount of 34 cubic meters of solid
radioactive waste generated from 1994 through 1996 to the industry's 3-year median
value of 42 cubic meters showed that the licensee generated less solid radioactive waste )
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than the industry's median and near the industry's best quartile of 31 cubic meters. The j
licensee's 3-year rolling average of solid radioactive waste generated for 1995 l
through1997 was 24 cubic meters.
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Solid Waste Reduction Results (Cubic Meters of Waste Generated)
1993 71
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1994 54
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1995 20
1996 27 !
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1997 25
The annual radioactive effluent release reports contained the required solid radioactive
waste data. Dry active waste and secondary blowdown resin were shipped to an off-site
vendor for volume reduction and subsequent burial. A summary of the volume and )
activity of solid radioactive waste including resins, irradiated components, and dry active
waste shipped for disposal during the last 5 years is tabulated below. The increases in
volume and activity for 1996 and 1997 were the result of outage activities and the
shipment of accumulated and stored secondary blowdown resin.
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Of Volume Activity l
Year Shipments (m') (Ci)
1993 6 68.78 761.61
1994 10 41.00 605.14
1995 5 89.60 394.08
1996 11 329.40 1660.47
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19U
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10 215.64 669.41
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c. Conclusions -
A good solid radioactive waste management program was implemented. Waste stream
sampling and analyses met regulatory requirements. Solid radioactive waste was
properly classified and characterized for shipment and disposal. The amount of solid
radioactive waste generated showed a significant reduction from 1993 through 1995.
From 1995 through 1997, the amount of solid radioactive waste generated remained
fairly steady at approximately 24 cubic meters. The licensee's 3-year average amount of
solid radioactive waste generated from 1994 through1996 showed that the licensee
generated less solid radioactive waste than the industry's median and near the industry's
best quartile for radioactive waste generated.
R1.2 Transoortation of Radioactive Waste and Radioactive Materials
a. Insoection Scooe (86750)
The inspector interviewed the health physics department's radwaste supervisor and
reviewed the following items:
- . Shipping documentation from selected shipments
. Certificates of compliance for NRC-certified shipping casks
. Copies of current licenses for recipients of radioactive wastes / materials
. Use of a vendor supplied computer program to generate shipping papers
. Packaging and shipping papers
. Marking and labeling of packages for shipment
. Vehicle placarding and driver instructions
. Emergency response information l
- Radiation surveys of packages and vehicles
. Use of system international (SI) units q
b. Observations and Findings
Selected shipping records for shipments performed between January 1997 and February
1998 showed that the licensee had made shipments of both radioactive waste and
radioactive materials. Shipments requiring Type B packaging were made by the
licensee. The inspector verified that the licensee was a registered user for the
NRC-certified shipping casks used. The inspector observed the preparation of a laundry
shipment made during the inspection. The shipment was properly prepared. ,
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Certificates of Compliance for routinely used shipping casks were verified. State l
shipping permits were reviewed. The inspector reviewed selected shipment consignees j
and verified that the licensee maintained on file current copies of the consignees' i
radioactive materiallicenses.
A radwaste computer code was used to determine proper radioactive material ,
transportation categories, shipping packages, labeling, and shipment documentation. ;
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Shipping papers for radioactive material shipments contained the information required by
49 CFR Part 172, Subpart C. In addition to this information, radioactive waste shipment .
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documentation included manifests that' conformed to the requirements of 10 CFR
Part 20, Appendix F and 49 CFR 173.433. Shipping documents included radioactive
activity measurements recorded in system intemational units as well as customary units.
The inspector verified that proper emergency telephone numbers were included with the
shipping papers.
. The licensee maintained photographs of radioactive waste shipments to confirm that
shipments were labeled, marked, and placarded properly. Radiation survey records
indicated that radiation and contamination levels of shipments were within regulatory
limits.-
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In general, the inspector noted that radioactive containers stored in the radioactive waste -
storage building were properly labeled. However, on March 19,1998, the inspector I
observed the activities associated with the receipt and unloading of a radioactive material
shipment of laundry from the off-site laundry contractor. During the emptying of one of
the shipping containers marked radioactive materials, six yellow plastic bags marked
" Wolf Creek trash" were surveyed and placed in a pile on the floor of the radwaste ._
storage building next to other properly labeled yellow bags of radioactive material. The
six yellow bags were not labeled as containing radioactive material. In addition, a purple
cloth bag was also unloaded from the shipping container, surveyed, and placed in a
separate area away from the other bags of radioactive material. The purple cloth bag ;
had a piece of red tape stuck to one side of the bag on which was written a date, PCs, l
and a dose rate of 80 millirem per hour (mrem /hr). Later the same day, the inspector
noted that the above observed yellow bags and purple bag of radioactive material had
not been moved and were still not properly labeled as containing radioactive material.
The inspector mentioned this observation to radiation protection management, and the '
licensee surveyed the bags. The survey results indicated that the six yellow bags had a
. contact dose rate of <2 mrem /hr, but the purple bag had a contact dose rate of
30 mrem /hr and a dose rate of 8 mrem /hr at 1 foot. The licensee wrote Performance j
Improvement Request 980791 and properly labeled the bags.
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10 CFR 20.1904(a) requires that the licensee ensure that each container of licensed
material bears a durable, clearly visible label bearing the radiation symbol and the words .j
" CAUTION RADIOACTIVE MATERIAL," or " DANGER, RADIOACTIVE MATERIAL." The I
label must also provide sufficient information (such as the radionuclides present, an j
l estimate of the quantity of radioactivity, the date for which the activity is estimated,
radiation levels, kinds of materials, and mass enrichment) to permit individuals handling
or using the containers, or working in the vicinity of the containers, to take precautions to
avoid or minimize exposures.
Radiation Protection Procedure RPP 02 215. " Posting of Radiological Controlled Areas,"
paragraph 9.5 states, in part, that containers shall be labeled with information sufficient to
convey the radiological hazards and the controls to prevent or reduce personnel
exposure,
The failure to properly label radioactive material containers is a violation of
10 CFR 20.1904(a) (50-482/9811-01).
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- - c. Conclusions
A good transportation program for radioactive materials and radiMive waste was
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maintained. Documentation and packages were properly prepareu for shipment. In
general, containers were properly labeled. However, a violation was identified involving
the failure to properly label seven radioactive material containers.
R2' Status of Facilities and Equipment
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- a. lnsoection Scone (86750)'
The inspector toured the radwaste processing ' facilities and the low-level radioactive
waste / material storage building and observed radwaste container storage and '
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acccuntability.
b. Findinos and Observations
inspection of'the radioactive waste processing and' storage facilities revealed that good
radwaste facilities were maintained. The radwaste storage areas were properly posted
and controlled. Generally, radwaste containers were properly labeled and marked.
Housekeeping in the radioactive waste storage areas was good. However, some areas
in the radwaste storage building needed aoditional attention.'
Shipments of radioactive wastes were made in a timely. manner to maintain the - ..
radioactive waste inventory at a minimum. The licensee kept good records of radwaste
container accountability.' The inspector verified that selected radwaste containers were :
stored as documented. The inspector concluded that the licensee could account for all
of the radioactive waste inventory,
c; Conclusions
Good facilities were maintained for the processing, storage, and management of solid
radioactive wastes and tratisportation activities. An effective radioactive waste:
~ inventory / accountability system was maintained. Housekeeping in the radioactive waste
storage areas was good.
R3 Radiological Protection and Chemistry Procedures and Documentation
a. Insoection Scooe (86750) .
The inspector reviewed the procedures used to implement the solid radioactive waste
management and transportation programs.
- b; Observations and Findinos
The inspector determined that appropriate guidance was provided in the radwaste
procedures for radioactive waste stream sampling, ver.Jor laboratory analysis, and
. updating the computer code data with new waste stream sample analysis results and
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scaling factors. Effective checklists were utilized to provide guidance for the preparation
of radioactive waste and radioactive materials shipments.
c. - Conclusions
Procedures and checklists established to implement the solid radioactive waste
management and transportation programs provided good guidance for the handling,.
processing, and shipping of radioactive waste / materials.
'R4 Staff Knowledge and Performance
~ The inspector interviewed the radwaste supervisor (qualified shipper) and the two
radiation protection technicians, who were responsible for the implementation of the solid -
radioactive waste management program and all radioactive waste / materials
transportation activities. The radwaste supervisor and one of the radiation protection
technicians were very experienced, and they had an excellent understanding of the
transportation regulations.
R5- Staff Training and Qualification in Radiological Protection and Chemistry :
a. Insoection Scope (86750)
The inspector reviewed the training of personnel who were responsible for the
preparation and packaging of radioactive waste and radioactive materials for shipment.
- The inspector reviewed the following items:
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Training materials related to 49 CFR Parts 171-179 and 10 CFR Part 71 -
- Training and qualification records
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b. Observations and Findinas
The inspector verified that training records documented that the radwaste supervisor
(qualified shipper) and the two radiation protection technicians assigned to perform the
radwaste processing and transportation activities were properly trained and qualified.
The new recently assigned radiation protection technician was in the process of --
completing his training and qualifications to become a qualified shipper and backup to
the radwaste supervisor.
An effective biennial retraining program was conducted in accordance with commitments
made in the response to NRC Bulletin 79-19, " Packaging of Low-Level Radioactive
Waste for Transport and Burial." Training records indicated that radiation protection
technicians, radiation protection decon personnel, two quality evaluation department l
auditors, and the health physics training instructors had received the required training in
radwaste processing and transportation regulatory requirements on a biennial frequency.
The training department's lesson plans and vendor supplied course materials provided a
comprehensive training program,
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c. Conclusions
Personnel involved in the transfer, packaging, and transport of radioactive materials and
radioactive wastes were properly trained and qualifed.
R6- Radiological Protection and Chemistry Organization and Administration
? The organization and staffing for the implementation of the solid radioactive waste
management and transportation programs were reviewed. The radwaste supervisor and
two radiation protection technicians assisted by nine radiation protection department
- decon technicians effectively implemented the radioactive waste management and
transportation programs. One of the two radiation protection technicians had been
recently assigned to the radwaste staff. .There had been no reduction in radweste staff
since the previous inspection of this area conducted in January 1997.
R7 - Quality Assurance in Radiological Protection and Chemistry Activities
R7.1 Solid Radioactive Waste and Transoortation Proaram Aa****ments
a. Insoection Scone (86750)
A biennial audit, two self assessments, a surveillance, and five plant evaluations were
reviewed to evaluate the licensee's effectiveness at identifying and correcting problems.
The review also included the following items: ]
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.. - Training, qualifications, and resumes of auditors
Performance improvement requests of radioactive waste and transportation
activities .
b. Observations and Findinas.
An audit o' f the solid radioactive waste management and transportation programs was
conducted every 24 months during the odd numbered years in accordance with
Technical Specification requirements. Audit K-473, " Process Control Program," was
conducted January 9 through March 31,1997. The inspector determined that the audit
was comprehensive in its review of solid radioactive waste management and
transportation activities. The audit team included two' experienced auditors, who were
trained and knowledgeable of the current transportation regulatory requirements. The
training, qualifications, and experience of the auditors were appropriate.
' Self assessments of the radwaste management and radioactive waste / materials
transportation programs were conducted in November 1995 and September 1996. The
self assessments evaluated dry active waste composition and observations of radwaste
management and transportation activities in progress. The results of the two self
assessments provided to radwaste management an assessment of the major
. contributors to the dry active waste stream and ways to minimize dry active waste
generation and an evaluation of radwaste management program performance and j
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A quality evaluation surveillance was performed of the licensee's implementation of the
Department of Transportation regulations. Plant evaluations of the radwaste processing
areas and the radwaste storage building provided suggestions to improve housekeeping
in the radwaste storage building and surrounding areas.
Audit and self assessment issues were tracked by the performance improvement request
system. The inspector noted that the licensee responded promptly and provided timely
and effective corrective actions to the audit and self assessment issues. Based on the
review of the performance improvement requests involving radioactive waste activities
written during 1997 and 1998, no adverse programmatic trends were noted.
c. Conclusions
An excellent self assessment program was maintained. Through the use of
comprehensive audits, self assessments, surveillances, and plant evaluations, an
excellent management oversight program for the solid radioactive waste management
and transportation programs was maintained. The auditors were trained and
knowledgeable in radioactive waste management and transportation regulatory
requirements. Timely and effective corrective actions were completed on identified
problems.
R7.2 Quality Evaluation Proaram for Contractors
a. Inscection Scooe (86750)
The quality evaluation vendor audit program of contractors performing surveillance i
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activities involving the solid radioactive waste management program was reviewed.
b. Observations and Findinas
Contractors were used to perform the processing of solid radioactive waste and volume
reduction, radwaste transportation and cask rental, radwaste disposal services, and
radiochemistry analyses of radwaste samples for 10 CFR Part 61 waste classification
and characterization requirements.
Nuclear procurement issues committee audits of the contractors were used to evaluate
the performance of their respective radwaste activities. The audits were comprehensive
and satisfactory to evaluate each of the contractor's abilities to perform their respective
radwaste program activities.
c. Conclusion
There was appropriate evaluation of the contractors' performance.
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R8 Miscellaneous Radiological Protection and Chemistry issues
R8.1 (Closed) Insoection Followuo item 9617-01: Evaluation and Validation of Meteorofoaical
Monitorina Data
This item was discussed in NRC Inspection Report 50-482/96-17 and involved the lack of
proper evaluation and validation of meteorological data. No instructions or validation
criteria had been developed to provide the frequency and methods to accurately validate
the meteorological data. The licensee had previously relied on the plant computer's
radiological release information system tc monitor and validate the meteorological data.
However, in 1990, the radiological release information system was replaced with the
nuclear plant information system. The computr. program used for meteorological data
verification and validation that was formerly in the radiological release information system
was not subsequently included in the nuclear plant information system.
The inspector verified that the licensee had written a procedure for the validation of the
meteorological data, had developed and tested a computer program to validate the
meteorological tower instrumentation data, and had completed the validation of the
meteorological data for the years 1990 through 1997. The results of the meteorological
data validation will be reported in the 1997 Annual Effluent Release Report.
R8.2 (Closed) Licensee Event Reoort 92-017: Inadeauate Chemistrv Shift Mannino Due to
Personnel not Meetina Qualification Reauirements
On September 2,1997, the licensee determined that certain chemistry personnel,
historically, may not have met the shift manning requirements of ANSI /ANS 3.1-1978 at
the time the individuals were fulfiiling the shift manning requirements of Technical
Specification 6.2.2. The licensee determined that one of these individuals stood watch
alone and fulfilled the chemistry shift manning requirements for approximately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> on
January 3-4,1992, while the station was in Mode 4. This was identified by the licensee
as a violation of Technical Specification 6.2.2(a), which states, "Each on duty shift shall
be composed of at least the minimum shift crew composition shown in Tabla 6.2-1 "
Table 6.2-1 requires in Modes 1,2, 3, and 4, one chemistry individual to fill the chemistry
shift manning requirements. Also, Technical Specification 6.3 requires unit staff to meet
or exceed the qualifications of ANSI /ANS 3.1-1978. ANSI /ANS 3.1-1978, Section 4.4.3,
Chemistry and Radioachemistry, requires that the responsible person have 5 years
experience in chemistry of which 1 year shall be in radiochemistry at an operating
nuclear power plant.
All chemistry personnel became qualified to perform their duties in accordance with
Administrative Procedure AP 30D-006, " Chemistry Technician Training Program."
However, this procedure did not address the Technical Specification requirements of
' ANSl/ANS 3.1-1978 at the time this issue was identified. The licensee took immediate
corrective action and determined that all current chemistry personnel fulfilling the shift
manning requirements for Technical Specification 6.2.2 met the qualification
requirements of ANS!/ANS 3.1-1978. Chemistry, health physics, and operations
qualification programs were reviewed to ensure appropriate controls were in place such
that individuals filling the required positions met the applicable ANSI /ANS requirements.
The chemistry technician training program procedure, AP 30D-006, was revised to
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' include the qualification requirements of ANSI /ANS 3.1-1978. The inspector verified that
the licensee's corrective. actions were completed.
This nonrepetitive, licensee-identified and corrected violation is being treated as a 'I
noncited violation, consistent with Section Vll.B.1 of the NRC Enforcement Policy.
(50-482/9811-02)
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R8.3 (Closed) Unresolved item 50-482/9809-04: MS-3 Mini Sca!er with HP-210 detector
countino efficiency
The inspector followed up on Unresolved item 50-482/9809-04 discussed in NRC
Inspection Report 50-482/98-09, Section R1.4, issued on March 13,1998. - This issue
pertained to the licensee using a cesium-137 source for determining the efficiency of the
radiation detector (HP-210 detector coupled to an MS-3 scaler) used to ana!yze
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particulate air samples, it was noted that the licensee was using the cobalt-60 derived
air concentration (DAC) value from 10 CFR Part 20, Appendix B, for determining airbome
radionuclide concentrations following the counting of the particulate air samples. The
inspector questioned that since the licensee was basing the airbome radioactivity
concentration using the cobalt-60 DAC value then why were they not using cobalt-60 for
' determining the calibration efficiency of the detector. The licensee stated.that there was
' no cobalt-60 source on site with the same geometry as the cesium-137 source.
Therefore, no comparison could be made.
On March 19,1998, the inspector was informed that a technetium-99 source was used in
lieu of a cobalt-60 source for determining that particular detector calibration efficiency.
The licensee decided to use this source since it was already on site, and the average
beta energy is close to that of cobalt-60. The licensee also stated that they plan on using
the technetium-99 source in the future for this particular detector calibration. The results
indicated that the detector was approximately 40 percent less efficient for detecting beta
particles with an average energy as those emitted from cobalt-60 as compared to the
' cesium-137 source. )
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After it was determined that the calibration efficiency was in error for that particular
detector, the licensee reviewed previous air sample data from the last outage to
determine if any areas should have been posted as an airborne radioactivir/ area in
accordance with their posting requirements. The licensee identified two caset. where an
inaccurate detector efficiency calibration potentially inappropriately resulted in not
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posting an~airbome radioactivity area as required by station procedures.
Procedure RPP-215, " Posting of Radiological Controlled Areas," Revision 12, requires -
that posting of an airborne radiation area will be performed at a level of greater than or
equal to 0.3 DAC. The inspector noted that the licensee's administrative requirement of
, posting an airborne radiation area at a level of 0.3 DAC was below the posting limit of 1.0
DAC required in 10 CFR Part 20. l
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10 CFR 20.1501 states, in part, that each licensee shall make or cause to be made,
surveys that may be necessary for the licensee to comply with the regulations in this ,
part; and are reasonable under the circumstances to evaluate concentrations or
quantities of radioactive material; and the potential radiological hazards that could be
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- present. The licensee .shall ensure that instruments and equipment used for quantitative
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.' radiation measurements are calibrated periodically for the radiation measured.
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Technical Specification 6.8.1 requires, in part, that written procedures be established, -
. implemented, and maintained covering the activities recommended in Appendix A of
Regulatory Guide 1.33, Revision 2 February 1978. Regulatory Guide 1.33, Appendix A,
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Section 7.e.2, includes procedures for radiation surveys.
Procedure RPP 02-210, " Radiation Survey Methods," Revision 13, Section 9.4.7 states,
in part, "If the particulate activity is equal to or greater than 30 percent DAC, then submit
the particulate filter for isotopic analysis and post the area as per RPP 02-215."
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Procedure RPP 02-215, " Posting of Radiological Controlled Areas," Revision 12, requires
that posting of an airborne radiation area will be performed at a level of greater than or
- equal to 0.3 DAC.
The inspector determined that instruments and equipment used for quantitative radiation
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measurements were not calibrated for the radiation measured. Specifically, cesium-137 ,
- was used for the efficiency calibration of the particular detector used to analyze '
. particulate air samples for the presence of cobalt-60, which resulted in potentially not I
posting airborne radioactivity areas in accordance with Station Procedure RPP 02-215.
~ This failure constitutes a violation of minor significance and is being treated as a noncited
violation consistent with Section IV of the NRC Enforcement Policy (50-482/9811-03).
V. Management Meetings
X1' Exit Meeting. Summary
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The inspector presented the inspection results to members of licensee management at
an exit meeting on March 20,1998. The licensee acknowledged the findings presented.
- No proprietary information was identified. J
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ATTACHMENT
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SUPPLEMENTAL INFORMATION
PARTIAL LIST OF PERSONS CONTACTED ,
- Licensee
M. Blow, Superintendent, Chemistry / Radiation Protection
G. Boyer, Chief Administrative Officer
S. Burkdoll, Supervising instructor, Health Physics / Chemistry Training
R Butz, System Engineer, Radiation Monitors
- V. Canales, Supervisor, Suppliers / Materials Quality / Purchasing and Material Services
C. Clark, Health Physics Technician, Radiation Protection
- K. Davison, Acting Plant Manager
T. Harris, Supervisor, Licensing
S. Koenig, Supervisor, Quality Evaluations
G. Lawsen, Superintendent, Maintenance Planning
M. McMullen, Senior Engineer, Design Engineering
- C. Medenciy, Radwaste Supervisor, Radiation Protection
L. Nilges, Health Physics Technician, Radiation Protection
E. Peterson, Supervisor, Quality Control
J. Pippin. Manager, Training
C. Reekie, Engineering Specialist, Regulatory Compliance
C. Rich, Superintendent, instruments & Electrical
R. Skiles, Health Physics Instructor, Training
C. Stone, Quality Specialist, Quality Evaluations
C. Younie, Manager, Operations
NRG
F. Ringwald, Senior Resident inspector
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LIST OF INSPECTION PROCEDURES USED
IP 86750 Solid Waste Management and Transportation of Radioactive Waste
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LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Open 1
50-482/9811-01 VIO Failure to label containers of radioactive material 1
50-482/9811-02 NCV Failure to meet chemistry shift manning requirements
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50-482/9811-03 NCV MS-3 Mini Scaler with HP-210 detector counting efficiency
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Closed
50-482/9617-01 IFl Evaluation and validation of meteorological monitoring data
50-482/92-017 LER Inadequate chemistry shift manning due to personnel not meeting
qualification requirements
50-482/9809-04 URI - MS-3 Mini Scaler with HP-210 detector counting efficiency
50-482/9811-02- NCV Failure to meet chemistry shift manning requirements
50-482/9811-03- NCV MS-3 Mini Scaler with HP-210 detector counting efficiency
LIST OF DOCUMENTS REVIEWED
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ORGANIZATION CHARTS
Chemistry / Health Physics Department - January 1998
TRAINING DOCUMENTATION
Vendor Training Course RC-101, introduction to RADMAN (Windows Version) and Regulatory
Compliance, presented February 24-26,1998
Lesson Plan for Health Physics Technician Training, HW 12-158-01, Revision 5, " DOT and NRC
Regulations and Requirements"
' Lesson Plan for Health Physics Decon Personnel Training, DN 12-158-01, Revision 3, " DOT and
NRC Regulations and Requirements"
Radiation protection department training records
Licensee's response to NRC Inspection and Enforcement Bulletin 79-19
QUALITY ASSURANCE DOCUMENTS l
- Quality Evaluations Biennial Audit Schedule, Revision 13, dated January 29,1997
- Quality Evaluations Audit Plan K-490, Plant Support SALP Area
' Quality Assurance Program Approval for Radioactive Material Packages, expiration date
September 30,2001
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Quality Assurance Audit
' Quality Evaluations Audit Report K-473, " Process' Control Program," conducted January 9 -
through March 31,1997-
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Quality Assurance Surveillance-
LQuality Evaluations Surveillance Report S-3158, " DOT Shipping Regulation Compliance,"
' conducted July 22-30,1996
Vendor Audits
NUPlc Joint Quality Assurance Audit of Scientific Ecology Group, conducted April 15-17,1996 -
NUPIC Joint Quality Assurance Audit of Chem-Nuclear Systems, Inc., conducted May 24-26,-
- 1996
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NUPIC Joint Quality' Assurance Audit of Thermo NUtech, conducted December 9-11,1996
Self Assessments
Self Assessment Report SEL 95-050, " Waste Composition Analysis," conducted November 27-
28,1995
Self Assessment Report SEL 96-036, " Radioactive Material Management Practice Assessment,"
l- conducted September 23-27,1996
Plant Evaluations
" Safety Walkdown of the Radwaste Building," dated December 6,1996
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, " Housekeeping of the Radwaste Building," dated January 21,1997
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! ' " Safety Tour of the Radwaste Building and Surrounding Grounds," dated March 12,1997
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"Radwaste Building Housekeeping Surveillance," dated September 15,1997
j; "Radwaste Material Shipment 97R65," dated November 21,1997
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PROCEDURES
Administrative Procedures
' AP 3_1-001 - " Packaging for Transporting Type B and Fissile Quantities of Radioactive
Materials Quality Program Requirements," Revision 1
' AP 31A-001 " Low Level Radioactive Waste Quality Program Requirements," Revision 0
AP 31 A-100 " Solid Radwaste Process Control Program," Revision 1
AP 31 A-200 ' " Radioactive Waste Program," Revision 0
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Radiation Protection Procedures "
RPP 07-101 " Control of Radioactive Material Management Software and Data Bases,"
Revision 4
RPP 07-110 " Solid Radwaste Packaging," Revision 4
RPP 07-111 " Handling Cartridge Filters," Revision 5
RPP 07-120 ' " Preparation and Shipment of Radioactive Waste," Revision 10
"
RPP 07-121 Preparation and Shipment of Radioactive Material," Revision 8
RPP 07-130 " Verification of Free Standing Water in High Integrity Containers," Revision 2
RPP 07-131 " Bead Resin / Activated Carbon Dewatering Procedure for CNSI 14-215 or
Smaller Liners," Revision 3 '
RPP 07-140 '" Mixed Waste Handling, inspection, and Storage," Revision 4
' MISCELLANEOUS DOCUMENTS
Annual Operating Radioactive Effluent Reports - 1993 through 1996
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