ML101410535

Notification of Inspection and Request for Information

ML101410535
Person / Time
Site:	Watts Bar
Issue date:	05/21/2010
From:	Brian Bonser NRC/RGN-II/DRS/PSB1
To:	Krich R Tennessee Valley Authority
References
Download: ML101410535 (11)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II SAM NUNN ATLANTA FEDERAL CENTER 61 FORSYTH STREET, SW, SUITE 23T85 ATLANTA, GEORGIA 30303-8931 May 21, 2010 Mr. R. M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801

SUBJECT:

WATTS BAR NUCLEAR PLANT NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION

Dear Mr. Krich:

During the period of July 12-16, 2010, the NRC will conduct baseline radiation safety inspection activities at the Watts Bar Nuclear Plant. The inspection will evaluate activities in the Public and Occupational Radiation Safety cornerstones using NRC Inspection Procedures (IP) 71124.01, 71124.04, 71124.05, 71124.06, and 71124.07, focusing on radiation protection activities associated with radiological hazard assessment, occupational dose assessment, radiation detection instrumentation, radioactive liquid and gaseous effluent treatment, and the radiological environmental monitoring program. The inspection will also review the public and occupational radiation safety performance indicators using IP 71151.

This will be the first time that IPs 71124.01, 71124.04, 71124.05, 71124.06, and 71124.07, implemented January 1, 2010, are performed at Watts Bar. 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, thereby minimizing the number of additional documents requested during the preparation and/or the onsite portions of the inspection. The inspector has requested that the subject informational material be made available to the NRC staff by June 18, 2010, to allow preparation for the inspection.

We have discussed the schedule for these inspection activities with your staff and understand that our regulatory contact for this inspection will be Mike Brandon of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector, Heather Gepford at (404) 997-4659.

TVA 2

In accordance with 10 CFR 2.390 of the NRC=s ARules of Practice,@ a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm.html (the Public Electronic Reading Room).

Sincerely,

/Ruben Hamilton RA for/

Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Docket No.: 50-390 License No.: NPF-90

Enclosure:

Watts Bar Nuclear Plant, Notification of Inspection and Request for Information cc w/encl.: (See page 3)

G SUNSI REVIEW COMPLETE OFFICE RII:DRS RII:DRS SIGNATURE RKH /RA for/

RKH /RA for/

NAME HJGepford BRBonser DATE 05/21/2010 05/21/2010 E-MAIL COPY?

YES NO YES NO YES NO YES NO YES NO YES NO YES NO

TVA 3

cc w/encl:

D. E. Grissette Vice President Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381 G. A. Boerschig Plant Manager Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381 M. K. Brandon Manager Licensing and Industry Affairs Watts Bar Nuclear Plant Electronic Mail Distribution E. J. Vigluicci Assistant General Counsel Tennessee Valley Authority 6A West Tower 400 West Summit Hill Drive Knoxville, TN 37902 County Mayor P.O. Box 156 Decatur, TN 37322 Division of Radiological Health TN Dept. of Environment & Conservation 401 Church Street Nashville, TN 37243-1532 Ann Harris 341 Swing Loop Rockwood, TN 37854

TVA 4

Letter to R. M. Krich from Brian Bonser dated May 21, 2010

SUBJECT:

WATTS BAR NUCLEAR PLANT NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION Distribution w/encl:

C. Evans, RII L. Slack, RII OE Mail RIDSNRRDIRS PUBLIC RidsNrrPMWattsBar1 Resource RidsNrrPMWattsBar2 Resource

Enclosure Pre-Inspection Document Request Occupational Radiation Safety Cornerstone Licensee:

Watts Bar Nuclear Plant Docket Number(s):

50-390 Inspection Dates:

July 12-16, 2010 Procedure(s): 71124.01 Radiological Hazard Assessment and Exposure Controls 71124.04 Occupational Dose Assessment 71124.05 Radiation Monitoring Instrumentation 71124.06 Radioactive Gaseous and Liquid Effluent Treatment 71124.07 Radiological Environmental Monitoring Program 71151 Performance Indicator Verification (Public & Occupational Radiation Safety cornerstones)

Documentation is requested from September 2009 to the present for each of the inspection procedures. We would prefer as much of the information as possible in electronic form. An index to the CD contents is also helpful. For those items requesting a list of documents/areas, the inspector will select documents/areas from the list for on-site review.

If you have any questions, please call Heather Gepford at 404-997-4659. Thank you in advance for all your effort in putting together this material.

Assistance Requested During On-Site Inspection Accompaniment on the weekly REMP run to observe sample collection Identification of work activities during the inspection for inspector observation, such as liquid or gaseous effluent releases/sampling and radiologically significant jobs.

Assistance with plant walk-downs during the inspection of systems such as liquid and gaseous waste/effluent processing areas and radioactive material storage areas.

General Information Request Telephone numbers of contacts Plant, Radiation Protection, and Chemistry organizational charts List of radiation protection and chemistry (e.g. effluent processing/release) procedures FSAR sections related to (1) radiation protection program and activities, (2) radiation monitoring instrumentation associated with airborne radioactivity, process streams, effluents, area radiation monitoring, materials/articles, post-accident monitoring, etc., (3) radioactive effluent treatment systems and flow paths, and (4) radiological environmental monitoring program, including meteorological monitoring instrumentation Most recent DAW 10 CFR Part 61 analytical results.

2 Enclosure Offsite Dose Calculation Manual and most recent Land Use Census results Corrective Action Program and Performance Indicator collection/reporting procedures Audits and self-assessments performed since January 2009 that address (1) radiation protection, (2) radiation monitoring program, including the onsite calibration facility, (3) radioactive material control, (4) external and internal dosimetry, (5) the radiological environmental monitoring program, (6) the radioactive liquid and gaseous effluent program, and (7) the groundwater monitoring program.

71124.01: Radiological Hazard Assessment and Exposure Controls

1.

Site and corporate procedures associated with assessing and controlling radiological hazards. Procedures should include:

a. Radiological surveys, postings, and radiation control barricades

b. Security and control of high radiation sources/objects, including those stored in pools

c. Radiation Work Permits

d. Radiological Job-Coverage

e. Controlling access to High Radiation Areas (HRAs), High Dose Rate High Radiation Areas (HDR-HRAs), and Very High Radiation Areas (VHRAs), including key controls

f. Radioactive material control, including contamination, hot particles, and survey/release of material for unrestricted use

g. Dosimetry monitoring (electronic dosimeters, multi-badging, whole body counting/internal dose assessment, etc.)

2.

Description of any changes to plant operations that could result in a new radiological hazard for workers or members of the public.

3.

List of the most exposure significant radiologically risk-significant work activities planned for the outage, including at least five activities scheduled during the week of the inspection.

4.

List or map of HRAs, LHRAs, and VHRAs. Include areas with the potential to become a HRA during routine operations and/or outages.

5.

RWPs for the 5 highest dose rate areas or outage tasks and RWPs for airborne areas.

6.

Inventory of nonexempt licensed materials, including storage location.

7.

List of unusual dosimetry occurrences, including electronic dosimeter malfunctions/alarms.

8.

List of corrective action program (CAP) condition reports generated since September 2009 related to radiological hazard assessment and control, including the following:

a. Exposure controls, including high radiation area radiological incidents

b. Radiation monitoring (e.g. surveys, contamination, airborne)

c. Radiological events caused by radiation worker errors

d. Radiological events caused by radiation protection technician errors

3 Enclosure 71124.04: Occupational Dose Assessment

1.

Site and corporate procedures associated with dosimetry operations. Procedures should include:

a. Issuance/use of external dosimetry (routine, multibadging, extremity, neutron, declared pregnant workers, assigning dose of record, etc.)

b. For non-NVLAP accredited passive dosimeters, procedures for calibration, application of calibration factors, zeroing, etc.

c. Calibration and use of electronic dosimeters, including, if applicable, use of a correction factor to address response of ED with respect to TLD

d. Assessment of internal dose (operation of whole body counter, assignment of dose based on DAC-hours, urinalysis, etc.)

e. Evaluation of, and dose assessment for, radiological incidents (e.g. distributed contamination, hot particles, loss of dosimetry, etc.)

2.

Most recent NVLAP accreditation report

3.

List of the types of dosimetry used, e.g. TLD, OSL, bubble dosimeter, electronic dosimeter, by manufacturer and, if applicable, model number

4.

List of any internal dose assessments exceeding 10 mrem CEDE and any skin dose assessments performed since September 2009

5.

List of CAP condition reports generated since September 2009 related to internal and external dosimetry, dose assessment, etc.

71124.05: Radiation Detection Instrumentation

1.

Site and corporate procedures associated with radiation detection and monitoring instrumentation. Procedures should include:

a. Portable radiation survey instrument calibrations and source checks

b. Electronic dosimeter calibration and use

c. Whole body counter, personnel contamination monitor, portal monitor, and small article monitor calibrations and source checks

d. Area radiation monitor alarm setpoint values and setpoint bases, calibration, and source checks

e. Effluent monitor alarm setpoint bases and calculational methods

f. Collecting and analyzing high-range, post-accident iodine effluent samples

g. Maintenance and calibration/certification of calibration sources/ranges

2.

List of in-service survey instrumentation including air samplers, small article monitors, personnel contamination monitors, portal monitors, whole body counters, neutron monitoring instrumentation, etc.

3.

Technical Specifications related to post-accident monitoring instrumentation, effluent monitoring, and emergency assessment

4 Enclosure

4.

Most recent channel calibration and functional test for the following effluent/process monitors, post-accident monitoring instruments, and area radiation monitors:

a. 1-RE-90-120, Steam Generator Blowdown Effluent Monitor

b. 1-RE-90-101, Aux Building Ventilation Effluent Monitor

c. 1-RE-90-131, Containment Purge Air Exhaust Effluent Monitor

d. 1-RE-90-290, RHR Post Accident Monitor

e. 1-RE-90-272, Reactor Building Upper Compartment Post Accident

f. 1-RE-90-274, Reactor Building Lower Compartment Post Accident

g. 1-RE-90-59, Containment Refuel Floor ARM

h. SI Pump Area Airborne Particulate Activity (CAM)

5.

Whole body counter calibration reports since September 2009, calibration/check source information, and WBC analysis library

6.

System health reports for the RMS system for the past year

7.

List of CAP condition reports generated since September 2009 related to radiation monitoring instrumentation, including the following:

a. Radiation survey instruments/calibrations

b. Radiation Monitoring System, including effluent monitors, process monitors, and area radiation monitors

c. Chemistry count lab, including cross-check analysis and QC

d. Whole body counter, PCMs, PMs, and SAMs 71124.06: Radioactive Liquid and Gaseous Effluent Treatment

1.

Site and corporate procedures associated with implementing the effluent program and the groundwater monitoring program. Procedures should include those that address:

a. Effluent sampling

b. Effluent monitor setpoint determinations

c. Dose calculations

d. Groundwater monitoring and reporting of spills/leaks

e. Methodology for determining effluent stack/vent flow rates

2.

Radiological Effluent Release Reports for calendar years 2008 and 2009.

3.

List of all unmonitored spills, leaks, or unexpected liquid/gaseous discharges since the last inspection. Provide the LER, event report, and/or special report if applicable.

4.

List of non-radioactive systems that have become contaminated and any 10 CFR 50.59 evaluations performed.

5.

List of any changes to the effluent release points or effluent treatment systems and associated 50.59 documentation

6.

Material condition surveillance records for effluent system components not readily accessible, including those inaccessible due to radiological conditions

5 Enclosure

7.

Most recent effluent release permits for continuous gaseous, batch gaseous, continuous liquid, and/or batch liquid releases.

8.

Results of inter-laboratory comparison program for count lab

9.

Most recent test results for filtered ventilation systems (e.g. HEPA and charcoal filters),

specifically, the containment and auxiliary building ventilation systems and the main stack.

10. Groundwater monitoring results since January 2009.

11. List of changes to written ground water monitoring program for identifying/controlling contaminated spills/leaks

12. List of onsite surface water bodies (e.g. ponds, retention basins, lakes) that contain or potentially contain radioactivity

13. List of CAP condition reports generated since September 2009 related to liquid and gaseous effluent treatment and monitoring, unmonitored spills, leaks, or effluent discharges, or the groundwater monitoring program.

71124.07: Radiological Environmental Monitoring Program

1.

Site and corporate procedures associated with radiological environmental monitoring, including:

a. Collection, preparation, and analysis of environmental samples including air samples, TLD stations, ground and surface water, sediment, vegetation, milk, fish, etc.

b. Calibration and maintenance of sampling equipment

c. Calibration and QC activities for sample counting instruments

d. Sampling and monitoring program to detect leaks from contaminated or potentially contaminated systems, structures, or components

e. Meteorological instrument calibration, operation, and routine surveillances

2.

Radiological Environmental Operating Reports for the years 2008 and 2009

3.

List of structures, systems, or components that contain or could contain licensed material for which there is a credible mechanism for the radioactive material to reach ground water

4.

Summary of leaks and/or spills since September 2009, i.e. additions to the 50.75(g) file

5.

Calibration and maintenance records for air samplers and composite water samplers since September 2009

6.

Interlaboratory comparison program results for the past two years (in-house laboratory or vendor laboratory).

7.

Calibration/surveillance/maintenance records for the meteorological monitoring instruments since September 2009

6 Enclosure

8.

List of CAP condition reports generated since September 2009 related to the radiological environmental monitoring program, including meteorological monitoring.

71151: Performance Indicator (PI) Verification

1.

Monthly PI reports since October 2009, and copies of associated condition reports for any RETS/ODCM Radiological Effluent occurrences

2.

Liquid and gaseous effluent release permits which specify the monthly (September 2009 -

May 2010), quarterly (3rd quarter 2009 through 2nd quarter 2010), and annual (calendar year 2009) curies released by isotope and associated public dose assessments.

3.

List of all corrective action documents since October 2009 using keywords such as: HRA, LHRA, VHRA, unintended dose, unlocked door, etc.

4.

List of all electronic dosimeter (ED) dose rate alarms > 1 R/hr and all ED dose alarms since October 2009.

Inspector Contact Information:

Heather J. Gepford (404) 997-4659 Heather.Gepford@nrc.gov Mailing Address US Nuclear Regulatory Commission, Region II ATTN: Heather Gepford 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303