ML073400098
| ML073400098 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 12/03/2007 |
| From: | Brian Bonser NRC/RGN-II/DRS/PSB2 |
| To: | Campbell W Tennessee Valley Authority |
| References | |
| IR-08-002 | |
| Download: ML073400098 (11) | |
See also: IR 05000390/2008002
Text
December 3, 2007
Tennessee Valley Authority
ATTN: Mr. William R. Campbell
Chief Nuclear Officer and
Executive Vice President
6A Lookout Place
1101 Market Street
Chattanooga, TN 37402-2801
SUBJECT:
NRC INSPECTION REPORT NO. 50-390/2008002 AND 50-391/2008002
Dear Mr. Campbell:
On February 11-15 and February 25-29, 2008, the NRC will perform the baseline Occupational
Radiation Safety Inspection at the Watts Bar Nuclear Plant (NRC Inspection Procedures
71121.01, 71121.02, and 71122.02 and the radiation safety section 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 pre-inspection visit with your staff
for January 14-16, 2008. The material requested will be reviewed and collected at that time.
We have discussed the schedule for these inspection activities with your staff and understand
that 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, Heather Gepford, at (404) 562-4659, or the Plant Support Branch 1 Chief, Brian
Bonser, at (404) 562-4653.
In accordance with 10 CFR 2.390 of the NRCs Rules 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).
2
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/ reading-rm/adams.html
(the Public Electronic Reading Room).
Should you have any questions concerning this letter, please contact us.
Sincerely,
/RA/
Brian R. Bonser, Chief
Plant Support Branch 2
Division of Reactor Safety
Docket Nos. 50-390, 50-391
License No. NPF-90 and Construction
Permit No. CPPR-92
Enclosure: Pre-Inspection Document Request
cc: See Page 3
3
cc w/encl:
Gordon P. Arent
New Generation Licensing Manager
Tennessee Valley Authority
5A Lookout Place
1101 Market Street
Chattanooga, TN 37402-2801
Ashok S. Bhatnagar
Senior Vice President
Nuclear Generation Development
and Construction
Tennessee Valley Authority
Electronic Mail Distribution
James R. Douet
Vice President, Nuclear Support
Tennessee Valley Authority
Electronic Mail Distribution
H. Rick Rogers, Vice President
Nuclear Engineering & Technical Services
Tennessee Valley Authority
3R Lookout Place
1101 Market Street
Chattanooga, TN 37402-2801
Michael D. Skaggs
Site Vice President
Watts Bar Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
General Counsel
Tennessee Valley Authority
Electronic Mail Distribution
John C. Fornicola, General Manager
Nuclear Assurance
Tennessee Valley Authority
Electronic Mail Distribution
Larry E. Nicholson, General Manager
Performance Improvement
Tennessee Valley Authority
4X Blue Ridge
1101 Market Street
Chattanooga, TN 37402-2801
Beth A. Wetzel, Manager
Corporate Nuclear Licensing and
Industry Affairs
Tennessee Valley Authority
Electronic Mail Distribution
Michael K. Brandon, Manager
Licensing and Industry Affairs
Watts Bar Nuclear Plant
Tennessee Valley Authority
P. O. Box 2000
Spring City, TN 37381
Michael J. Lorek, Plant Manager
Watts Bar Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
County Executive
Rhea County Courthouse
375 Church Street, Suite 215
Dayton, TN 37321
County Mayor
P.O. Box 156
Decatur, TN 37322
Lawrence E. Nanney, Director
TN Dept. of Environment & Conservation
Division of Radiological Health
Electronic Mail Distribution
4
Masoud Bajestani
Vice President
Watts Bar Unit 2
Watts Bar Nuclear Plant
Tennessee Valley Authority
P.O. Box 2000
Spring City, TN 37381
Ann Harris
341 Swing Loop
Rockwood, TN 37854
James H. Bassham, Director
Tennessee Emergency Management Agency
Electronic Mail Distribution
_________________________
OFFICE
RII:DRS
RII:DRS
RII:DRS
RII:DRS
SIGNATURE
/RA/
/RA/
NAME
B. Bonser
H. Gepford
DATE
12/3/2007
11/30/2007
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO
Enclosure
Pre-Inspection Document Request
Occupational Radiation Safety Cornerstone
L i c e n s e e:
Watts Bar Nuclear Plant
Docket Numbers:
50-390, 391
Inspection Dates:
February 11-15 and February 25-29, 2008
Inspection Procedures to be performed:
Access Controls to Radiologically Significant Areas
ALARA Planning and Controls
Radioactive Gases and Liquid Effluent Treatment & Monitoring Systems [limited
scope, Sections 02.01(e), 2.02 (d & e)]
Radioactive Material Processing and Transportation
71151
Performance Indicator Verification
The most recent inspection completed for the listed inspection procedures was performed on June
21-25, 2007. Unless otherwise specified, 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 CD
contents 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 Heather Gepford at 404-562-4659. Thank you in advance
for all your effort in putting together this material.
Assistance Requested During Bagman Trip
G
Introductions to, and discussions with, licensee personnel who will be assisting with the
inspection
G
Plant familiarization tour
Assistance Requested During On-Site Inspection
G
Identification of work activities during the inspection for inspector observations, including
notification of pre-job briefings, notification of diving activities, audio/visual surveillance for
remote job coverage.
G
Health physics assistance in plant walk-downs assessing access controls, e.g. verifying the
posting and locking of entrances to HDR-HRA and VHRA, and spent fuel pool controls.
G
Health physics assistance in plant walk-downs/job coverage of ongoing outage activities to
assess access controls and ALARA practices.
2
Enclosure
G
Discussions with appropriate individuals regarding access controls and ALARA planning.
G
Schedule of transportation shipments during the inspection and notification of opportunities
for observations of shipment preparation/receipt; discussions with appropriate individuals
regarding the transportation program.
General Information Request
G
Telephone numbers of contacts
G
Plant and Radiation Protection organizational charts, including personnel involved in solid
radwaste processing and transportation of radwaste/radioactive materials.
G
Electronic copy of applicable chapters of UFSAR (e.g. radiation protection program, liquid
and solid radioactive waste program, etc.)
G
Outage schedule, including work activities to be conducted during the week(s) of the
inspection
G
List of active radiation work permits, including those specific to outage activities, with their
administrative limits, electronic dosimeter dose rate limit, and dose limit.
G
List of radiation protection procedures
G
Corrective Action Program procedures
G
Procedure(s) for identifying, notification, tracking, and correcting PI occurrences.
G
List of all Performance Indicators (PIs) and copies of associated corrective action reports
for Occupational Exposure Control Effectiveness and RETS/ODCM Radiological Effluent
Occurrences
G
Audits and self-assessments performed since the last inspection that encompass the areas
of (1) access controls, (2) the ALARA program and implementation, (3) liquid and solid
radwaste processing, and (4) transportation of radioactive material/radwaste.
71122.01 Radioactive Gases and Liquid Effluent Treatment & Monitoring Systems
G
Procedures for onsite/offsite surface/groundwater monitoring activities and leak detection
G
Summary of spill, leak, or unexpected liquid discharge data documented in the sites
10 CFR 50.75(g) files. Note: Only provide summary, 50.75(g) file details may be reviewed
during onsite inspection
G
List of PERs issued since June 2006 for tritium or other radioisotopes in ground water
wells, or identification of spills or leaks from contaminated systems, structures, and
components.
G
Audits and self assessments conducted since June 2006 for groundwater monitoring.
3
Enclosure
G
Annual Effluent/REMP Reports for CY 2006: focus on surface and groundwater
monitoring.
71121.01 Access Controls to Radiologically Significant Areas
G
Site and corporate procedures associated with the access control program. Procedures
should include:
<
Radiological surveys, postings, and radiation control barricades
<
Security and control of high radiation sources/objects stored in pools
<
Radiation Work Permits
<
Radiological Job-Coverage
<
Controlling access to High Radiation Areas (HRAs), High Dose Rate High Radiation
Areas (HDR-HRAs), and Very High Radiation Areas (VHRAs)
<
Key controls for all high radiation areas
<
Radioactive material control, including contamination and hot particles
<
Dosimetry monitoring (electronic dosimeters, multi-badging, etc.)
<
Calculations of internal exposures
G
List of the 10 most exposure significant work areas within radiation areas, high radiation
areas (<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
RWPs for the top five dose rate areas or tasks.
G
Plant/elevation maps of all HRAs, LHRAs, HDR-HRAs (>25 rem in one hour @ 30 cm), and
VHRAs. Include areas with the potential to become a HRA during routine operations or
outages.
G
Internal dose assessments, including calculations, for any internal exposures greater that
50 mrem CEDE since the last inspection.
G
List of PERs generated since the last inspection related to access controls, including the
following:
<
Access controls, including high radiation area radiological incidents
<
Radiological events caused by radiation worker errors
<
Radiological events caused by radiation protection technician errors
71121.02: ALARA Planning and Controls
G
Site and corporate procedures associated with maintaining site dose ALARA, including
those involving ALARA work activities. These procedures should include:
<
ALARA program implementation, including ALARA committee activities and ALARA
planning, briefing, and reviews
<
Radiation work permit preparation and worker compliance
4
Enclosure
<
Processes used to estimate and track work activity specific exposures
<
Making changes to dose estimates during task performance
<
Work controls
<
Engineering controls
<
Exposure mitigation requirements
G
ALARA documents related to current outage:
<
List approximately 10-15 work activities planned during the inspection likely to result
in the 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.
<
ALARA planning packages for the five highest dose jobs being performed during
the outage
<
Temporary shielding requests generated for the outage.
G
ALARA documents related to previous outage:
<
Completed ALARA packages (including post-job reviews) for the five work activities
that were completed during the last outage which had the greatest collective dose
and/or presented significant radiological risk.
<
List of five activities (including ALARA package number) from the previous outage
in which the work scope changed or was extended and alternative ALARA
measures were taken to respond to the emergent conditions.
<
List of five activities from the previous outage in which the estimated work hours
were significantly different than the actual hours expended.
<
List of five activities in which the estimated and actual hours expended were
accurate.
G
Documents related to the ALARA planning process:
<
Annual ALARA goals for 2006-2008, previous/current outage ALARA goals, and the
methodology utilized to make the projections.
<
Most recent annual ALARA report and most recent refueling outage report.
<
ALARA Committee activity summaries (e.g. meeting minutes) for three months or 3
meetings after the last refueling outage and the three months or 3 meetings prior to
the upcoming refueling outage.
G
Outline of the source term reduction strategy. Information should include:
<
Historic trends and current status of plant source term
<
Factors that affect the source term
<
Activities employed to reduce the source term
<
Specific sources identified for reduction actions
<
Source term reduction evaluation
<
Results achieved since last inspection
G
Records for declared pregnant workers since the last inspection, listing their monthly
radiation exposure during the term or year-to-date.
5
Enclosure
G
List of PERs generated since the last inspection related to the ALARA program, including
the following:
<
ALARA planning
<
Post-job review identified problems
<
Radiation worker practices
<
Occurrences where the collective exposure was greater than intended dose
determined to be ALARA for the individual work activities
71122.02 Radioactive Material Processing and Transportation
G
Site and corporate procedures/manuals describing licensee compliance with 10 CFR Parts 20, 61, and 71 and 49 CFR Parts 170-189. Procedures/manuals should include:
<
Solid and liquid radwaste processing procedures
<
Procedure(s) for transferring radioactive waste resin and sludge discharges into
shipping/disposal containers.
<
Waste stream mixing and/or sampling procedures, including (1) waste
concentration 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 parameters
<
Shipping/transportation procedures
<
Cask loading and closure procedures (licensee and vendor) applicable to last three
cask transports
G
Process Control Program (PCP).
G
Most recent Annual Radioactive Effluents Release Report.
G
Most recent radio-chemical sample analysis results (i.e., 10 CFR Part 61" analysis) for
each of the radioactive waste streams (e.g., dry active waste (DAW), ion exchange resins,
mechanical filters, and sludges and activated materials, etc.).
G
List and documentation of any changes made to the radioactive waste processing systems
(liquid and solid) and/or the PCP since the last inspection and associated 10 CFR 50.59
documentation, as appropriate.
G
Copies of applicable transport cask Certificate of Compliance for the last three transport
cask shipments.
G
Training and qualification records for personnel responsible for radioactive waste
processing and radioactive material shipment preparation activities.
G
Copy of the Radioactive Shipping Log for the last 12 months. (The inspector will select
transportation shipping packages for review during the inspection.)
G
List of PERs generated since the last inspection involving radioactive waste and radioactive
material/waste transportation.
6
Enclosure
G
Available for onsite review during the inspection:
<
Site drawing(s) showing the location of all stored radioactive materials and all
stored radioactive waste.
<
Plant drawings sufficient to permit the inspector to walk-down the liquid and solid
radioactive 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 process
equipment that is not operational and/or is abandoned in place.
<
Information concerning the sites waste disposal volume and waste reduction
program.
<
Training curriculum and primary lesson plans for qualifying persons, including
vendors, for radwaste processing, packaging, and making shipments of
radioactive materials and radioactive waste as specified by 49 CFR 172.
71151 Performance Indicator Verification
G
List of all PERs since January 2007 using keywords: HRA, LHRA, VHRA, unintended dose,
unlocked door, offsite dose, ODCM, etc.
G
Monthly PI reports since January 2007.
G
List of all dose rate alarms > 1 R/hr and all dose alarms since January 2007.
G
All final release point effluent monitor out-of-service dates since January 2007.
G
Most recent gaseous and liquid effluent release permits.
Lead Inspector Contact Information:
Heather Gepford, Ph.D., CHP
(404) 562-4659
hjg1@nrc.gov
Mailing Address
US NRC Region II
ATTN: Adam Nielsen
61 Forsyth Street, SW
Suite 23T85
Atlanta, GA 30303-3415