ML103140311
| ML103140311 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 11/08/2010 |
| From: | - No Known Affiliation |
| To: | Division of Operating Reactor Licensing |
| References | |
| Download: ML103140311 (17) | |
Text
1 WBN2Public Resource From:
Boyd, Desiree L [dlboyd@tva.gov]
Sent:
Monday, November 08, 2010 11:54 AM To:
Wiebe, Joel; Poole, Justin; Raghavan, Rags; Milano, Patrick; Campbell, Stephen Cc:
Crouch, William D; Hamill, Carol L; Boyd, Desiree L
Subject:
TVA Letter to NRC_11-5-10_Part 30 and Part 40 License Application Attachments:
11-5-10_Part 30 and Part 40 License Application_Final.pdf Please see attached letter that was sent to the NRC today.
Thank You,
~*~*~*~*~*~*~*~*~*~*~*~*~*~*~
Désireé L. Boyd WBN2LicensingSupport SunTechnicalServices dlboyd@tva.gov 4233658764
~*~*~*~*~*~*~*~*~*~*~*~*~*~*~
Hearing Identifier:
Watts_Bar_2_Operating_LA_Public Email Number:
160 Mail Envelope Properties (7AB41F650F76BD44B5BCAB7C0CCABFAF17D162EB)
Subject:
TVA Letter to NRC_11-5-10_Part 30 and Part 40 License Application Sent Date:
11/8/2010 11:53:56 AM Received Date:
11/8/2010 11:54:09 AM From:
Boyd, Desiree L Created By:
dlboyd@tva.gov Recipients:
"Crouch, William D" <wdcrouch@tva.gov>
Tracking Status: None "Hamill, Carol L" <clhamill@tva.gov>
Tracking Status: None "Boyd, Desiree L" <dlboyd@tva.gov>
Tracking Status: None "Wiebe, Joel" <Joel.Wiebe@nrc.gov>
Tracking Status: None "Poole, Justin" <Justin.Poole@nrc.gov>
Tracking Status: None "Raghavan, Rags" <Rags.Raghavan@nrc.gov>
Tracking Status: None "Milano, Patrick" <Patrick.Milano@nrc.gov>
Tracking Status: None "Campbell, Stephen" <Stephen.Campbell@nrc.gov>
Tracking Status: None Post Office:
TVANUCXVS2.main.tva.gov Files Size Date & Time MESSAGE 322 11/8/2010 11:54:09 AM 11-5-10_Part 30 and Part 40 License Application_Final.pdf 448547 Options Priority:
Standard Return Notification:
No Reply Requested:
No Sensitivity:
Normal Expiration Date:
Recipients Received:
U.S. Nuclear Regulatory Commission Page 2 November 5, 2010 cc (Enclosures):
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Licensing Assistance Team Division of Nuclear Materials Safety U. S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., N.E., Suite 1200 Atlanta, Georgia 30303-1257 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 U. S. Nuclear Regulatory Commission Director, Office of Federal and State Materials and Environmental Management Programs Washington, DC 20555-0001
U.S. Nuclear Regulatory Commission Page 3 November 5, 2010 bcc (Enclosures):
Stephen Campbell U.S. Nuclear Regulatory Commission MS 08H4A One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Loren R. Plisco, Deputy Regional Administrator for Construction U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., N.E., Suite 1200 Atlanta, Georgia 30303-1257 Completed NRC Forms 313 Application for Materials License 10 CFR Part 30 10 CFR Part 40
Information Requested in Items 5 through 11 of NRC Form 313 Application for Materials License Tennessee Valley Authority Watts Bar Nuclear Plant (WBN) - Unit 2, Docket No. 50-391
- 5. RADIOACTIVE MATERIAL Note: The radioactive material identified below represents materials specifically required for WBN Unit 2.
(a) Element and Mass Number (b) Chemical or Physical Form (c) Maximum Amount
- 1. Any byproduct material with Atomic Numbers of 1 through 83 inclusive Any 100 millicuries (mCi) per radionuclide and 1 curie total.
- 2. Barium 133 Sealed Source Up to 9 microcuries (Ci) per source and 17 Ci total.
- 3. Cesium 137 Sealed Source Up to 110 mCi per source and 122 mCi total.
- 4. Uranium 234 Sealed Source 0.011 mg per source and 0.08 mg total
- 5. Uranium 235 (93%)
238 (5.5%)
234 & 236 (1.5%)
Fission Chambers 3.9 grams of Uranium per fission chamber 4 fission chambers total of 15.6 grams
- 6. Californium 252 Startup Sources Up to 286 micro grams per source.
2 sources for a total of up to 572 micro grams. Note*
- 7. Technetium 99 Sealed Source 0.11 Ci per source and 0.11 Ci Total
Surveillance Capsule 20 mg Neptunium and 14 mg Uranium per capsule (maximum of 6 capsules)
Note*: The activity of the sources is specified to be 6.1EE8 neutrons per second at fuel load. The exact amount of Californium needed to provide the specified activity will be determined at fabrication.
E2-1 Information Requested in Items 5 through 11 of NRC Form 313 Application for Materials License
- 6. PURPOSE(S) FOR WHICH LICENSED MATERIAL WILL BE USED x
Lines 1 through 4 and 7: Calibration and standardization of radiochemical laboratory counting room instrumentation and plant radiation monitoring equipment.
x Line 5: Source and intermediate range detectors - fission chambers.
x Line 6: Startup sources for WBN Unit 2.
x Line 8: Reactor vessel surveillance capsules.
- 7. INDIVIDUAL(S) RESPONSIBLE FOR RADIATION SAFETY PROGRAM AND THEIR TRAINING EXPERIENCE The individuals responsible for the radiation safety program at WBN are:
- Anthony Wayne Hooks, WBN Radiation Protection Manager (RPM)
- Steven E. Woods, Health Physicist The RPM/Radiation Safety Officer (RSO) or designee is responsible for implementation, development, and direction of the site/facility Radiation Protection Program in accordance with applicable regulations and Nuclear Power Group (NPG) requirements.
They shall use, to the extent practicable, procedures and engineering controls based upon sound radiation protection principles to achieve occupational doses and doses to members of the public that are as low as is reasonably achievable (ALARA).
The factors listed below were used to determine that Anthony Wayne Hooks has sufficient experience in radiation protection and health physics to satisfy the education requirement for the position of RPM in the absence of a scientific degree in nuclear technology.
Anthony Wayne Hooks On Job Training Formal Course Type of Training Where Trained Training Yes No Yes No Business Administration Athens State College - Athens, Alabama BS Business Administration X
X Health Physics Initial Technician Training Program TVA Browns Ferry Nuclear Plant (BFN) 24 months - 640 Classroom hours X
X Health Physics Initial Technician Training Program BFN 3,200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> of on-the-job training X
X E2-2 Information Requested in Items 5 through 11 of NRC Form 313 Application for Materials License Anthony Wayne Hooks On Job Training Formal Course Type of Training Where Trained Training Yes No Yes No Radiation Protection Technical Training TVA University (TVAU)
Radiological Transportation and Shipping - 8 hrs X
X Radiation Protection Technical Training TVAU Control of Radiological Work - 8 hrs X
X Radiation Protection Technical Training TVAU Radiological Protection Fundamentals - 16 hrs X
X Radiation Protection Technical Training TVAU Radiological Environs Monitoring - 16 hrs X
X Radiation Protection Technical Training TVAU Radiological Bioassay -
16 hrs X
X Radiation Protection Technical Training TVAU HAZWOPER Training -
40 hrs X
X Radiation Protection Technical Training TVAU Health Physics Procedures - 40 hrs X
X Radiation Protection Technical Training TVAU Operational Bioassay -
40 hrs X
X Health Physics Biennial Training TVAU 250 hrs:
Reactor Theory Radiological Counting Statistics Radiological Detection and Measurements Modes of Radiological Decay Interaction of Radiation w/Matter Atomic and Nuclear Structure Internal and External Dosimetry X
X Health Physics Technician BFN 1986 to 1996 at BFN -
Radiological Control X
X Health Physics Technician TVA Watts Bar Nuclear Plant (WBN) 1999 to 2005 at WBN -
Radiation Protection X
X First Line Supervisor WBN 2005 to 2008 at WBN -
Radiological Protection X
X E2-3 Information Requested in Items 5 through 11 of NRC Form 313 Application for Materials License Anthony Wayne Hooks On Job Training Formal Course Type of Training Where Trained Training Yes No Yes No Radiation Protection Superintendent WBN 2008 to 2010 at WBN -
Radiological Protection X
X E2-4 Information Requested in Items 5 through 11 of NRC Form 313 Application for Materials License Experience in the handling and use of radioisotopes for Steven E. Woods is listed below:
Steven E. Woods On Job Training Formal Course Type of Training Where Trained Training Yes No Yes No Masters Health Physics, MBA, BS Chemistry Illinois Institute of Technology (IIT),
Chicago, Illinois Radiation Biophysics X
X Masters Health Physics, MBA, BS Chemistry IIT Case Studies in Health Physics X
X Masters Health Physics, MBA, BS Chemistry IIT Radiation Physics X
X Masters Health Physics, MBA, BS Chemistry IIT Standard, Statutes, and Regulations X
X Masters Health Physics, MBA, BS Chemistry IIT Internal Dosimetry X
X Masters Health Physics, MBA, BS Chemistry IIT Principles of Radiation Measuring Instrumentation X
X Masters Health Physics, MBA, BS Chemistry IIT External Dosimetry X
X Masters Health Physics, MBA, BS Chemistry IIT Statistics, Algebra, Calculus, Differential Equations X
X Radioactivity Measurements and handling of radioactive material WBN 29 years at WBN X
X
- 8. TRAINING FOR INDIVIDUALS WORKING IN OR FREQUENTING RESTRICTED AREAS Nuclear Power Group (NPG) personnel at WBN currently meet the qualification and training recommendations of NRC Regulatory Guide (RG) 1.8, Personnel Selection and Training, Revisions 1 or 2, American National Standards Institute (ANSI) Standard N18.1-1971, and ANSI/American Nuclear Society (ANS) Standard 3.1-1981 with the alternatives as outlined in the NRC approved TVA Nuclear Quality Assurance Plan (QAP), TVA-NQA-PLN89-A.
E2-5 Information Requested in Items 5 through 11 of NRC Form 313 Application for Materials License Accordingly, TVA has committed to the WBN site RPM meeting the education and experience as described in Regulatory Guide (RG) 1.8, Revisions 1 or 2 (as described below), and the endorsed ANSI N18.1-1971 and ANSI/ANS-3.1-1981 standards.
Because of TVAs commitment to both ANSI N18.1-1971 and ANSI/ANS-3.1-1981 standards, the RPM must meet the more restrictive of the composite qualifications and training of both documents.
The applicable TVA personnel meet the recommendations of RG 1.8, Revision 2, for personnel qualifying on positions identified in regulatory position C.1 after January 1, 1990. Personnel qualified on these positions prior to this date still meet the recommendations of RG 1.8, Revision 1-R. As specified in regulatory position C.2, all other positions meet the recommendations of ANSI/ANS N18.1-1971.
- 9. FACILITIES AND EQUIPMENT General WBN is a two-unit, pressurized water reactor power generating facility, located approximately 50 miles northeast of Chattanooga at the Watts Bar site in Rhea County, Tennessee. The facility is owned and operated by the Tennessee Valley Authority.
Unit 1 received its low power operating license (NPF-20) on November 9, 1995, and its full power operating license (NPF-90) on February 7, 1996. TVA declared commercial operation on May 25, 1996.
Unit 2 received a construction permit on January 1, 1973, and was placed in deferred status by letter to the NRC dated July 14, 2000. By letter dated August 3, 2007, TVA notified the NRC of its intention to resume unrestricted construction activities, under the existing construction permit and to obtain an operating license prior to April 1, 2012.
TVA expects to place Unit 2 in commercial operation by October 1, 2012.
All byproduct materials specified in Item 5 will be received and stored in shielded storage cabinets except when in use/installed. Lead storage cabinets and remote handling equipment will be provided as necessary to minimize radiation exposure of personnel.
Containment Radiation Monitor 2-RE-90-112 utilizes 0.05, 0.5, and 5 microcurie (Ci)
Barium-133 (Ba-133) calibration sources and an 8 Ci Ba-133 checksource. The Steam Generator Blowdown Liquid Monitors, 2-RE-90-120 & -121, utilize a 0.1 Ci Ba-133 calibration source. All checksources will be properly shielded and permanently installed in the plant as part of the detector assemblies. Calibration sources are used to calibrate the plant equipment to specified ranges and are stored in approved locations.
The Cesium-137 (Cs-137) sealed sources specified in Item 5.3 consist of 10 mCi and 100 mCi calibration sources. The 10 mCi and 100 mCi sources will be contained in General Atomic Company RT-10 and RT-11 calibrators respectively, and will be used to E2-6 Information Requested in Items 5 through 11 of NRC Form 313 Application for Materials License calibrate the plant area radiation monitors. The calibrators will be placed in their shields and the unit stored in a shielded storage cabinet when not in use. Detectors 2-RE-90-2 and 2-RE-90-256 utilize a 205 Ci checksource; 2-RE-90-421 and -422 utilize a 215 Ci checksource; 2-RE-90-423 utilizes a 204 Ci checksource; and 2-RE-90-424 utilizes a 211 Ci Cs-137 checksource. Detectors 2-RE-90-120 and -121 utilize 8 Ci checksources.
The Technetium-99 (Tc-99) sealed source in Item 5.7 is a 0.1 Ci source used to calibrate the RD-52 detector used in 2-RE-90-119, -130, and -131.
The Reactor Building Upper and Lower Post Accident Monitors, 2-RE-90-271, -272, -
273, & -274, utilize a 0.01 mg Uranium-234 (U-234) checksource (keep-alive) and the 100 mCi Cs-137 calibration source discussed previously. All checksources will be properly shielded and permanently installed in the plant as part of the detector assemblies. Calibration sources are used to calibrate the plant equipment to specified ranges and are stored in approved locations.
The Uranium-235 sealed sources specified in Item 5.5 are fission chambers to be used for source and intermediate range neutron flux monitoring. Prior to installation, the sources will be properly shielded and stored in a controlled area.
The Californium-252 sealed sources specified in Item 5.6 will be properly shielded and stored in a controlled area prior to installation in the reactor vessel.
The reactor vessel surveillance capsules are used to monitor reactor vessel material embrittlement. The internal Neptunium 237 and Uranium 238 sources are used to measure integrated flux at specific neutron energy levels.
Prior to installation, all radiation monitoring systems will be properly shielded and stored in a controlled area. Spare licensed instrument sources will be suitably shielded and stored in the same controlled area or in a shielded storage cabinet when not in use.
TVA provides controls for calibration, testing, maintenance, and repair of radiological/
instrumentation and equipment which meet applicable 10 CFR Part 20 radiological surveillance and monitoring requirements through Procedure RCDP-8, Radiological Instrumentation/ Equipment Controls.
The following list includes the instrumentation available in the radiochemical laboratory and the portable plant monitoring equipment normally available for routine health physics work.
E2-7 Information Requested in Items 5 through 11 of NRC Form 313 Application for Materials License Radiochemical Laboratory Instrumentation (Planned)
Type Instrument Number Available Radiation Detected Sensitivity Range Use 4096-channel High Purity Germanium (HPGe) detectors 5
gamma See Note 1
measuring Liquid scintillation counting system 2
low-energy beta Liquid :
1E-05 uCi/ml Gas:
1E-06 uCi/ml measuring Ion Chamber survey meter 4
beta/gamma 0-10,000 R/hr survey GM survey meter (Frisker) 20 beta/gamma 0-50,000 cpm survey Note 1: HPGe sensitivity for liquid gamma emitters is 5E-07 uCi/ml, 1E-06 uCi/ml for I-131, and 1E-05 uCi/ml for dissolved and entrained gases. HPGe sensitivity for noble gases is 1E-04 uCi/ml, 1E-12 uCi/ml for I-131, and 1E-10 uCi/ml for I-133.
Health Physics Instrumentation Type Instrument Number Available Radiation Detected Sensitivity Range Use Neutron dose rate meter with BF3 tube detector.
Eberline Model PNR-4 or equivalent 4
neutrons (0.025 ev to 10 Mev) 0-5,000 mrem/hr survey Alpha survey meter, Eberline Model PAC-4S with AC-3 alpha probe (window-1.5 mg/cm2) or equivalent 4
alpha 0-2,000,000 cpm survey Beta-gamma dose rate meter with telescoping probe. Model 6112 Teletector (Window-30 mg/cm2) or equivalent 8
beta/gamma 0-1,000 R/hr survey E2-8 Information Requested in Items 5 through 11 of NRC Form 313 Application for Materials License E2-9
- 10. RADIATION SAFETY PROGRAM The requirements of TVA Procedure NPG-SPP-05.1, Radiological Controls, apply to all aspects of radiation protection associated with TVA NPG 10 CFR Part 50 licensed nuclear facilities. This document states the minimum requirements for the Radiation Protection (RP) program at the nuclear sites. The NPG RP Program fulfills the requirements of 10 CFR Parts 19, 20, and 30 through 34, and 40. The RP Program is further established to meet, to the extent practicable, the guidelines contained in INPO 05-008, Guidelines for Radiological Protection at Nuclear Power Stations, and ANSI Inspection Criteria 8.1 through 8.10.
TVA procedure NPG-SPP-05.6, Controlling Byproduct and Source Material, provides the Byproduct and Source Material (BSM) source control process for TVA NPG facilities.
This procedure provides for the receipt of radioactive material and the control and accountability of BSM licensed sources. The program fulfills the NRC requirements in 10 CFR 20, 30 through 34, and 40 for the storage and control of licensed material.
- 11. WASTE MANAGEMENT The Site Chemistry organization has a radioactive effluents monitoring program, as required by the site administrative Technical Specifications (TS), established in the Offsite Dose Calculation Manual (ODCM). The ODCM contains the methodology by which compliance with 10 CFR Part 20 and 10 CFR Part 50 is demonstrated. In addition, the methodology used to comply with the requirements of 40 CFR Part 190 and 40 CFR §141.16 is documented in the ODCM. Radioactive effluent release monitoring meets the applicable requirements of RG 1.21, Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste, RG 4.15, Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination) - Effluent Streams and the Environment, and RG 4.1, Radiological Environmental Monitoring for Nuclear Power Plants, as defined by site-specific procedures.
Disposal of sources is governed by procedures NPG-SPP-05.6, Controlling Byproduct and Source Material, and RCI-127, Byproduct and Source Material Control. Offsite disposal of sources is governed by applicable site procedures governing packaging, labeling, shipping, and/or disposal of radioactive material.