ML16049A463

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Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate
ML16049A463
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 02/29/2016
From: Farideh Saba
Plant Licensing Branch II
To: James Shea
Tennessee Valley Authority
Saba F, NRR/DORL/LPL2-2
References
CAC MF6741, CAC MF6742, CAC MF6743
Download: ML16049A463 (5)


Text

UNITED STATES

  • NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FEbrun:y 29 t 2016 Mr. Joseph W. Shea Vice President, Nuclear Licensing
  • Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT

. REQUEST REGARDING EXTENDED POWER UPRATE (CAC NOS. MF6741, MF67 42, AND MF67 43)

Dear Mr. Shea:

By letter dated September 21, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15282A152), as supplemented by letters dated November 13, December 15, and December 18, 2015 (ADAMS Accession Nos. ML15317A361, ML15351A113, and ML15355A413, respectively), Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request (LAR) for the Browns Ferry Nuclear Plant, Units 1, 2, and 3. The proposed amendment would increase the authorized maximum steady-state reactor core power level for each unit from 3,458 megawatt thermal (MWt) to 3,952 MWt. This LAR represents an increase of approximately 20 percent above the original licensed thermal power level of 3,293 MWt, and an increase of approximately 14.3 percent above the current licensed thermal power level of 3,458 MWt.

The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittals and determined that additional information is needed. On February 9, 2016, the NRC staff forwarded, by electronic mail, a draft of the staff's request for additional information (RAI) to TVA. On February 16, 2016, TVA informed the NRC staff that no clarification call is needed.

The official questions are found in the enclosed RAI. This request was discussed with Mr. Daniel Green of your staff, and it was agreed that TVA would respond by April 1, 2016. In addition, Mr. Green confirmed that the enclosed RAI does not contain any sensitive information.

J. Shea If you have any questions, please contact me at 301-415-1447 or Farideh:Saba@nrc.gov.

Sincerely, Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296

Enclosure:

Request for Additional Information .

cc w/enclosure: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST REGARDING EXTENDED POWER UPRATE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 DOCKET NOS. 50-259, 50-260, AND 50-296 By letter dated September 21, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15282A152), as supplemented by letters dated November 13, December 15, and December 18, 2015 (ADAMS Accession Nos. ML15317A361, ML15351A113, and ML15355A413, respectively), Tennessee Valley Authority (TVA) submitted a license amendment request (LAR) for the Browns Ferry Nuclear Plant, Units 1, 2, and 3. The proposed amendment would increase the authorized maximum steady-state reactor core power level for each unit from 3,458 megawatt thermal (MWt) to 3,952 MWt. This LAR represents an increase of approximately 20 percent above the original licensed thermal power level of 3,293 MWt, and an increase of approximately 14.3 percent above the current licensed thermal power level of 3,458 MWt.

/

The U.S. Nuclear Regulatory Commission staff from the Radiation Protection and Consequence Branch (ARCS): Division of Risk Assessment, Office of Nuclear Reactor Regulation, reviewed the submitted LAR and its supplements, and determined that the following information is needed to complete the review of health physics (HP) portions of TVA submittals.

ARCB-HP-RAI 01 NEDC-33860 (LAR Attachment 6 (proprietary) and Attachment 8 (non-proprietary), "Safety Analysis Report for Browns Ferry Nuclear Plant Units 1, 2, and 3 Extended Power Uprate"),

Section 2.10.1.1, page 2-487, states that the installation of the new steam dryers will ensure that the moisture carryover will remain very low. What is the expected value of the moisture carryover with the new steam dryers, and how does it compare with the current design basis value?

ARCB-HP-RAI 02 NEDC-33860, Section 2.10.1.1, page 2-487, states that an increase by a factor of 1.32 in the radiation levels under extended power uprate (EPU) conditions may exceed the original design crheria of 1 millirem (mrem)/hour in the turbine building general area. Provide an estimate of the maximum dose rate above the design criteria expected in the turbine building general area under EPU conditions. Verify that the radiation zoning design basis for the facility will be updated.

Enclosure

ARCB-HP-RAIO 3 NEDC-33860, Table 2.9-12, "Post-LOCA Mission Doses," states the mission doses for the Control Roomrrsc to Post-Accident Sampling Station to be 6.59 roentgen equivalent man (rem), 13. 7 rem, and 14 rem for Units 1, 2 and 3, respectively. A footnote at the bottom of the table indicates that these doses, which are greater than the regulatory limit of 5 rem for a single individual, can be distributed over a number of individuals. Provide a description of the tasks involved in each of these missions and how they will be distributed such that no single individual

  • perfor"ming these missions will exceed 5 rem.

ARCB-HP-RAI 04

'- NEDC-33860, page 2-494, second paragraph, and Table 2.10-2, state that the post-EPU N-16 skyshine contribution to offsite normal radiation dose is expected to be negligible. Provide justification for this conclusion.

J.Shea If you have any questions, please contact me at 301-415-1447 or Farideh.Saba@nrc.gov.

Sincerely,

/RA/

Farideh E. Saba, Seni.or Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296

Enclosure:

Request for Additional Information cc w/enclosure: Distribution via Listserv DISTRIBUTION:

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OFFICIAL RECORD COPY