ML12340A111
| ML12340A111 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 12/20/2012 |
| From: | Andrew Hon Plant Licensing Branch II |
| To: | James Shea Tennessee Valley Authority |
| Hon, Andy | |
| References | |
| TAC ME8877 | |
| Download: ML12340A111 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555"()001 December 20,2012 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SUB..IECT:
WATTS BAR NUCLEAR STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO ALLOW SELECTIVE IMPLEMENTATION OF ALTERNATE SOURCE TERM TO ANALYZE THE DOSE CONSEQUENCES ASSOCIATED WITH FUEL-HANDLING ACCIDENTS (TAC NO. ME8877)
Dear Mr. Shea:
By letter dated June 13,2012, as supplemented by letter dated August 2,2012, Tennessee Valley Authority submitted a license amendment request for Watts Bar Nuclear Plant, Unit 1.
The proposed amendment request would allow selective implementation of alternate source term to analyze the dose consequences associated with fuel-handling accidents.
The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that additional information is required to complete our review. The specific information requested is addressed in the enclosure to this letter. The proposed questions were discussed by telephone with your staff on November 28, 2012. Your staff confirmed that these questions did not include proprietary or security-related information and agreed to provide a response within 45 days from the date of this request for additional information (RAI).
J. Shea
- 2 The NRC staff considers that timely responses to RAls help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-8480 or via e-mail Andrew.Hon@nrc.gov.
Sincerely,
~d--
Andrew Hon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390
Enclosure:
Request for Additional Information cc w/encl: Distribution via ListServ
REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO SELECTED IMPLEMENTATION OF THE ALTERNATIVE SOURCE TERM TO ANALYZE THE DOSE CONSEQUENCES ASSOCIATED WITH FUEL HANDLING ACCIDENTS FUEL HANDLING ACCIDENT TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-390 By application dated June 13, 2012, to the U.S. Nuclear Regulatory Commission (NRC),
Tennessee Valley Authority (TVA) submitted a license amendment request (LAR) for Watts Bar Nuclear Plant (WBN), Unit 1 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12171A317). The proposed change will selectively implement an Alternate Source Term (AST) methodology in accordance with Regulatory Position C. 1.2.2 of Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors," by modifying the WBN, Unit 1 licensing basis for determining offsite and Control Room doses due to a Fuel-Handling Accident. A license amendment is required for AST implementation in accordance with Title 10 of the Code of Federal Regulations, Part 50, Section 50.67(b)(1).
The NRC staff is reviewing your submittal and has determined that additional information is required to complete its review.
- 1.
Page E1-6 of Enclosure 1 to the June 13, 2012, submittal discusses a fuel-handling accident scenario that assumes that the containment is open.
Please 1) confirm that, in this case when the containment is classified as "open,"
the only effluent release location to the environment is through the Shield Building vent or Auxiliary Building vent, or 2) if this is not the case, describe the other pathways and justify that the limiting case has been identified.
- 2.
Table 5, page E1-20, provides some of the inputs for calculation of one of the control room atmospheric dispersion factors (X/Q values) using the ARCON96 computer code, but does not include all of the inputs for the unspecified release location. Table 5 lists two control room X/Q values, one for the Auxiliary Building vent and one for the Shield Building vent. Enclosure 3 of the June 13, 2012, letter is a compact disk that provides a file entitled ARCON96 Output File. This file includes computer input and output information for approximately 16 different cases.
Enclosure
- 2
- a.
Please identify and discuss the computer runs in the ARCON96 Output File that are pertinent to the June 13, 2012, LAR and pinpoint the cases used to identify the bounding doses to the control room operators.
- b.
Do the generated X/a values model the bounding doses considering those due to loss of offsite power or other single failures?
- c.
Which X/a values were used to model unfiltered inleakage into the control room and why is the use of these X/a values appropriate?
- 3.
Watts Bar Final Safety Analysis Report Figure 1.2-1 was annotated and previously docketed as Attachment 12 to a TVA letter dated July, 31,2010 (ADAMS Accession No. ML102290258), in support of a licensing action related to Watts Bar, Unit 2. Please confirm that information on this figure is consistent with the current WBN, Unit 1 LAR, or provide a similar annotated figure for the current LAR that highlights the release and receptor locations on a facility layout diagram drawn to scale.
J. Shea
- 2 The NRC staff considers that timely responses to RAls help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-8480 or via e-mail Andrew.Hon@nrc.gov.
Sincerely, IRA!
Andrew Hon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390
Enclosure:
Request for Additional Information cc w/encl: Distribution via ListServ DISTRIBUTION:
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