ML070990480
| ML070990480 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 04/04/2007 |
| From: | Brian Bonser NRC/RGN-II/DRS/PSB1 |
| To: | Swafford P Tennessee Valley Authority |
| References | |
| Download: ML070990480 (10) | |
Text
April 4, 2007Tennessee Valley Authority ATTN:Mr. Preston D. SwaffordActing Chief Nuclear Officer and Executive Vice President6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR POWER PLANT, NOTIFICATION OF INSPECTIONAND REQUEST FOR INFORMATION
Dear Mr. Singer:
On May 21-25, 2007, the NRC will perform the baseline Occupational Radiation SafetyInspection at Watts Bar, (NRC Inspection Procedures 71121.01, 71121.02, 71122.02, and Radiation Safety Sections of 71151). Experience has shown that this inspection is resource intensive both for the NRC inspectors and your staff. In order to minimize the impact to your on-site resources and to ensure a productive inspection, we have enclosed a request for documents needed for this inspection. It is important that all of these documents are up-to-date and complete, in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection. The lead inspector has scheduled a two-day preinspection visit with your staff for April 24-26, 2007. The material requested will be reviewed and collected at that time.We have discussed the schedule for these inspection activities with your staff and understandthat our regulatory contact for this inspection will be Jerry Bushnell of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector, Ruben Hamilton at (404) 562-4672. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter andits enclosure will be available electronically for public inspection in the NRC Public DocumentRoom or from the Publicly Available Records (PARS) component of NRC's document system TVA2(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).Sincerely,
/RA/
Brian R. Bonser, ChiefPlant Support Branch 1 Division of Reactor SafetyDocket Nos.: 50-390License Nos.: NPF-90
Enclosure:
Pre-Inspection Document Request cc w/encl:Ashok S. Bhatnagar Senior Vice President Nuclear Operations Tennessee Valley Authority Electronic Mail DistributionLarry S. Bryant, Vice PresidentNuclear Engineering & Technical Services Tennessee Valley Authority Electronic Mail DistributionMichael D. SkaggsSite Vice President Watts Bar Nuclear Plant Tennessee Valley Authority Electronic Mail DistributionPreston D. SwaffordSenior Vice President Nuclear Support Tennessee Valley Authority Electronic Mail DistributionGeneral CounselTennessee Valley Authority Electronic Mail Distribution(cc w/encl cont'd - See page 3)
TVA3(cc w/encl cont'd)John C. Fornicola, General Manager Nuclear Assurance Tennessee Valley Authority Electronic Mail DistributionBeth A. Wetzel, ManagerCorporate Nuclear Licensing and Industry Affairs Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801Robert H. Bryan, Jr., General ManagerLicensing & Industry Affairs Tennessee Valley Authority Electronic Mail DistributionJames D. Smith, Acting ManagerLicensing and Industry Affairs Watts Bar Nuclear Plant Tennessee Valley Authority Electronic Mail DistributionMichael J. Lorek, Plant ManagerWatts Bar Nuclear Plant Tennessee Valley Authority Electronic Mail DistributionCounty ExecutiveRhea County Courthouse 375 Church Street, Suite 215 Dayton, TN 37321-1300County MayorP. O. Box 156 Decatur, TN 37322Lawrence E. Nanney, DirectorTN Dept. of Environment & Conservation Division of Radiological Health Electronic Mail DistributionAnn Harris341 Swing Loop Rockwood, TN 37854(cc w/encl cont'd - See page 4)
TVA4(cc w/encl cont'd)
James H. Bassham, Director Tennessee Emergency Management Agency Electronic Mail DistributionDistribution w/encl
- B. Moroney, NRR RIDSNRRDIRS PUBLIC
_________________________OFFICERII:DRSRII:DRPRII:DRSSIGNATURERARARANAMEHAMILTONWIDMANNBONSERDATE4/4/20074/4/20074/4/20074/ /20074/ /20074/ /20074/ /2007 E-MAIL COPY? YESNO YESNO YESNO YESNO YESNO YESNO YESNO Enclosure Pre-Inspection Document RequestOccupational Radiation Safety CornerstoneLicensee:Watts Bar Nuclear PlantDocket Number(s):50-390 Inspection Dates:May 21-25, 2007Inspection Procedures to be performed:
71121.01 Access Controls to Radiologically Significant Areas (March 2006)71121.02 ALARA Planning and Controls (March 2005) 71122.02 Radioactive Material Processing and Transportation (March 2005) 71151 Performance Indicator Verification (March 2006)The most recent inspection completed for the listed inspection procedures was performed islisted in parenthesis. Documentation is requested from the date of the previous inspection to the present. We would prefer as much of the information as possible in electronic form. An index to the CDcontents is also helpful. For those items requesting a list of documents/areas, the inspectors will select documents/areas from the list for on-site review. If any of the requested information is too burdensome to provide electronically or as hard copies during the bagman trip, simply indicate that the requested material is available for onsite review by the inspectors.If you have any questions, please call Ruben Hamilton at 404-562-4672. Thank you in advancefor all your effort in putting together this material.Assistance Requested During Bagman Trip GIntroductions to, and discussions with, licensee personnel who will be assisting with theinspection GPlant familiarization "tour"Assistance Requested During On-Site Inspection GIdentification of work activities during the inspection for inspector observations, includingnotification of pre-job briefings, notification of diving activities, audio/visual surveillance for remote job coverage.
GHealth physics assistance in plant walk-downs assessing access controls, e.g. verifyingthe posting and locking of entrances to HDR-HRA and VHRA, and spent fuel pool controls.GHealth physics assistance in plant walk-downs/job coverage of ongoing outage activitiesto assess access controls and ALARA practices.
2Enclosure GAssistance in plant walk-downs of the solid and liquid radwaste processing systems.
GDiscussions with appropriate individuals regarding access controls and ALARA planning.
GSchedule of transportation shipments during the inspection and notification ofopportunities for observations of shipment preparation/receipt; discussions with appropriate individuals regarding the transportation program.General Information Request GTelephone numbers of contacts GPlant and Radiation Protection organizational charts, including personnel involved insolid radwaste processing and transportation of radwaste/radioactive materials.
GElectronic copy of applicable chapters of UFSAR (e.g. radiation protection program,liquid and solid radioactive waste program, etc.)
GOutage schedule, including work activities to be conducted during the week(s) of theinspection G List of active radiation work permits, including those specific to outage activities, withtheir administrative limits, electronic dosimeter dose rate limit, and dose limit.
G List of radiation protection procedures GCorrective Action Program procedures GProcedure(s) for identifying, notification, tracking, and correcting PI occurrences.
GList of all Performance Indicators (PIs) and copies of associated corrective actionreports for Occupational Exposure Control Effectiveness and RETS/ODCM Radiological Effluent Occurrences GAudits and self-assessments performed since the last inspection that encompass theareas of (1) access controls, (2) the ALARA program and implementation, (3) liquid and solid radwaste processing, and (4) transportation of radioactive material/radwaste.71121.01 Access Controls to Radiologically Significant Areas GSite and corporate procedures associated with the access control program. Procedures should include:
Radiological surveys, postings, and radiation control barricadesSecurity and control of high radiation sources/objects stored in poolsRadiation Work PermitsRadiological Job-CoverageControlling access to High Radiation Areas (HRAs), High Dose Rate HighRadiation Areas (HDR-HRAs), and Very High Radiation Areas (VHRAs) Key controls for all high radiation areas Radioactive material control, including contamination and hot particlesDosimetry monitoring (electronic dosimeters, multi-badging, etc.)Calculations of internal exposures 3Enclosure GList of the 10 most exposure significant work areas within radiation areas, high radiationareas (<1R/hr), or airborne radioactivity areas in the plant. This may include areas with low dose rates but high collective dose. Identify any high radiation areas with significant dose gradients (factor of five or more), including underwater diving activities.
G List of HRAs, LHRAs, HDR-HRAs (>25 rem in one hour @ 30 cm), and VHRAs. Includeareas with the potential to become a HRA during routine operations or outages.
GInternal dose assessments, including calculations, for any internal exposures greaterthat 50 mrem CEDE since the last inspection.
G List of corrective action reports generated since the last inspection related to accesscontrols, including the following:
Access controls, including high radiation area radiological incidents Radiological events caused by radiation worker errorsRadiological events caused by radiation protection technician errors GAvailable for onsite review during inspection:Elevation maps with most recent operating and outage radiation survey levels.RWPs for the top five dose rate areas or tasks.71121.02: ALARA Planning and Controls GSite and corporate procedures associated with maintaining site dose ALARA, includingthose involving ALARA work activities. These procedures should include:
ALARA program implementation, including ALARA committee activities andALARA planning, briefing, and reviewsRadiation work permit preparation and worker complianceProcesses used to estimate and track work activity specific exposuresMaking changes to dose estimates during task performanceWork controlsEngineering controlsExposure mitigation requirements GMost recent annual ALARA report and most recent refueling outage report.
GAnnual ALARA goals for 2004, 2005, and 2006 and the methodology utilized to makethe projections.
GHistoric trends and current status of plant source term.
G List approximately 10-15 work activities planned during the inspection likely to result inthe highest personnel collective exposures and those which present the greatest radiological risk to workers (e.g. work in HRAs, diving, potentially changing radiological conditions). Include the dose projections and ALARA package numbers.
GALARA Committee activity summaries (e.g. meeting minutes) for three months or 3meetings after the last refueling outage and the three months or 3 meetings prior to the upcoming refueling outage.
GCompleted ALARA packages (including post-job reviews) for the five work activities thatwere completed during the last outage which had the greatest collective dose and/or presented significant radiological risk.
G List of five activities (including ALARA package number) from the previous outage inwhich the work scope changed or was extended and alternative ALARA measures were taken to respond to the emergent conditions.
4Enclosure G List of five activities from the previous outage in which the estimated work hours weresignificantly different than the actual hours expended. List five activities in which theestimated and actual hours expended were accurate.
GOutline of the source term reduction strategy. Information should include:Historic trends and current status of plant source termFactors that affect the source termActivities employed to reduce the source termSpecific sources identified for reduction actionsSource term reduction evaluationResults achieved since last inspection G List of activities since that last inspection that were reviewed for ALARA problems andactions taken to prevent recurrence.Include corrective action report number(s) if
applicable.
GList of corrective action reports generated since the last inspection related to the ALARAprogram, including the following:
ALARA planningPost-job review identified problemsRadiation worker practicesOccurrences where the collective exposure was greater than intended dosedetermined to be ALARA for the individual work activities GAvailable for onsite review during the inspection:ALARA planning packages for jobs being performed during the outageTemporary shielding requests generated for the outage.Records of personnel monitored for radiation exposure that show the total TEDEto date for each person. If possible, sort individuals by work group.Records for declared pregnant workers since the last inspection, listing theirmonthly radiation exposure during the term or year-to-date.71122.02 Radioactive Material Processing and Transportation GSite and corporate procedures/manuals describing licensee compliance with 10 CFRParts 20, 61, and 71 and 49 CFR Parts 170-189. Procedures/manuals should include:
Solid and liquid radwaste processing proceduresProcedure(s) for transferring radioactive waste resin and sludge discharges intoshipping/disposal containers.Waste stream mixing and/or sampling procedures, including (1) wasteconcentration averaging, (2) use of scaling factors and calculations used to account for difficult-to-measure radionuclides, and (3) ensuring waste stream composition data accounts for changing operational parametersShipping/transportation proceduresCask loading and closure procedures (licensee and vendor) applicable to lastthree cask transports GProcess Control Program (PCP).
GMost recent Annual Radioactive Effluents Release Report.
GMost recent radio-chemical sample analysis results (i.e., "10 CFR Part 61" analysis) foreach of the radioactive waste streams (e.g., dry active waste (DAW), ion exchange resins, mechanical filters, and sludges and activated materials, etc.).
5Enclosure GList and documentation of any changes made to the radioactive waste processingsystems (liquid and solid) and/or the PCP since the last inspection and associated 10 CFR 50.59 documentation, as appropriate.
GCopies of applicable transport cask Certificate of Compliance for the last three transportcask shipments.
GTraining and qualification records for personnel responsible for radioactive wasteprocessing and radioactive material shipment preparation activities.
GCopy of the Radioactive Shipping Log for the last 12 months. (The inspector will selecttransportation shipping packages for review during the inspection.)
GList of corrective action reports generated since the last inspection involving radioactivewaste and radioactive material/waste transportation.
GAvailable for onsite review during the inspection:Site drawing(s) showing the location of all stored radioactive materials and allstored radioactive waste.Plant drawings sufficient to permit the inspector to walk-down the liquid and solidradioactive waste processing systems to verify current system configuration/operation agree with the descriptions contained in the UFSAR and in the PCP. Documentation describing the status of any radioactive waste processequipment that is not operational and/or is abandoned in place. Information concerning the site's waste disposal volume and waste reductionprogram.Training curriculum and primary lesson plans for qualifying persons, includingvendors, for radwaste processing, packaging, and making shipments of radioactive materials and radioactive waste as specified by 49 CFR 172.