ML043090573
| ML043090573 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/04/2004 |
| From: | Yoira Diaz-Sanabria NRC/NRR/DRIP/RLEP |
| To: | Singer K Tennessee Valley Authority |
| DIAZ-SANABRIA, Y /NRR/DRIP/RLEP 415-1594 | |
| References | |
| TAC MC1704, TAC MC1705, TAC MC1706 | |
| Download: ML043090573 (7) | |
Text
November 4, 2004 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2 AND 3, LICENSE RENEWAL APPLICATION (TAC NOS. MC1704, MC1705 AND MC1706)
Dear Mr. Singer:
By letter dated December 31, 2003, Tennessee Valley Authority (TVA) submitted an application pursuant to 10 CFR Part 54, to renew the operating licenses for the Browns Ferry Nuclear Plant, Units 1, 2 and 3, for review by the U.S. Nuclear Regulatory Commission (NRC). The NRC staff is reviewing the information contained in the license renewal application (LRA) and has identified areas where additional information is needed to complete the review.
Specifically, the enclosed requests for additional information (RAIs) are related to Sections 3.1.2.4, B.2.1.13, and 4.7.8. Drafted forms of these RAIs were discussed with TVA staff on a telephone conference call on October 6, 2004.
Based on discussions with Ken Brune of your staff, a mutually agreeable date for your response to the RAIs is within 30 days from the date of this letter. If you have any questions regarding this letter or if circumstances result in your need to revise the response date, please contact me at (301) 415-1594 or by e-mail at yks@nrc.gov.
Sincerely,
/RA/
Yoira K. Diaz Sanabria, Project Manager License Renewal Section A License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260 and 50-296
Enclosure:
As stated cc w/encl: See next page
November 4, 2004 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2 AND 3, LICENSE RENEWAL APPLICATION (TAC NOS. MC1704, MC1705 AND MC1706)
Dear Mr. Singer:
By letter dated December 31, 2003, Tennessee Valley Authority (TVA) submitted an application pursuant to 10 CFR Part 54, to renew the operating licenses for the Browns Ferry Nuclear Plant, Units 1, 2 and 3, for review by the U.S. Nuclear Regulatory Commission (NRC). The NRC staff is reviewing the information contained in the license renewal application (LRA) and has identified areas where additional information is needed to complete the review.
Specifically, the enclosed requests for additional information (RAIs) are related to Sections 3.1.2.4, B.2.1.13, and 4.7.8. Drafted forms of these RAIs were discussed with TVA staff on a telephone conference call on October 6, 2004.
Based on discussions with Ken Brune of your staff, a mutually agreeable date for your response to the RAIs is within 30 days from the date of this letter. If you have any questions regarding this letter or if circumstances result in your need to revise the response date, please contact me at (301) 415-1594 or by e-mail at yks@nrc.gov.
Sincerely,
/RA/
Yoira K. Diaz Sanabria, Project Manager License Renewal Section A License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260 and 50-296
Enclosure:
As stated cc w/encl: See next page ADAMS Accession no. ML043090573 DISTRIBUTION: See next page
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SLee DATE 11/3/04 11/4/04 11/3/04 10/25/04 11/4/04 OFFICIAL RECORD COPY
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Enclosure BROWNS FERRY UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION (LRA)
REQUEST FOR ADDITIONAL INFORMATION (RAI)
RELATED TO SECTIONS 3.1.2.4, B.2.1.13, AND 4.7.8 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) Program RAI B.2.1.13-1 The staffs position regarding screening criteria to determine susceptibility of components to thermal aging embrittlement of CASS is detailed in the letter dated May 19, 2000, from Christopher Grimes, Nuclear Regulatory Commission (NRC), to Douglas Walters, Nuclear Energy Institute (NEI). The licensee states that the only in-scope CASS components that were determined to be susceptible to thermal aging embrittlement are the main steam line flow restricting venturis. The following information is requested.
(a)
Please provide the material specification including material grade, chemical content, casting method (i.e. either static or centrifugal), percent ferrite (using Hulls equation factors or a method producing an equivalent level of accuracy) and operating temperature for the flow restricting venturis.
(a)
Have the flow restricting venturis been evaluated in accordance with the guidance detailed in the May 19, 2000, NRC letter?
(b)
Are the components considered potentially susceptible to thermal aging embrittlement when screened using the criteria outlined in the May 19, 2000, NRC letter?
Emergency Equipment Cooling Water (EECW) Weld Flaw Evaluation RAI 4.7.8-1 The applicant states that analysis was performed on 17 EECW system piping welds that have flaws larger than what is normally considered acceptable. Please discuss the circumstances under which these flaws were discovered and provide a list and description of each of the 17 welds in question including the code class, flaw inspection history, flaw sizes and a detailed description of any analysis including the method that was used to determine flaw growth.
Reactor Recirculation System Aging Management Evaluation RAI 3.1.2.4-3 In Table 3.1.2.4 Page 3.1-54 (on CD ROM version of LRA) lists a copper alloy material used in heat exchangers operating in a raw water (internal) environment. The aging effects are listed as loss of material due to biofouling, microbiologically induced corrosion (MIC), crevice and pitting corrosion. The applicant lists the AMP as the One-Time Inspection Program (B.2.1.29).
The table item shows that neither the component or the material and environment combination is evaluated in NUREG-1801. The table notes indicate that the aging effects identified for this material/environment combination are consistent with industry guidance.
(a)
Identify the heat exchangers involved and the type of copper alloy (including material specification). Discuss the age, operating history, and inspection history of the heat exchangers. Discuss the consequence of leakage in the heat exchangers. Based on the operating and inspection history, explain why periodic inspections are not necessary during the extended license period.
(b)
Discuss in detail the extent of the planned One-Time inspection and explain why a One-Time inspection will be adequate to detect early stages of degradation that may effect the reliable operation of the heat exchanger through the extended licensing period.
RAI 3.1.2.4-4 In Table 3.1.2.4 Page 3.1-55 lists copper alloy piping operating in a treated water (internal) environment. NUREG-1801 Vol. 2 Item VII.C2.1-a. The aging effects are listed as loss of material due to crevice and pitting corrosion. The applicant lists the AMP as the One-Time Inspection Program (B.2.1.29). Table 3.1.2.4 notes show that the material is not listed in NUREG-1801 for this component. The table notes indicate that the aging effects identified for this material/environment combination are consistent with industry guidance.
Discuss the age, operating history and inspection history of the aforementioned copper alloy piping. Discuss the consequence of leakage of this piping. Discuss in detail the extent of the planned One-Time inspection and explain why a One-Time inspection will be adequate to detect early stages of degradation that may effect the reliable operation of these components through the extended licensing period. In addition, please provide the material specification of the piping.
RAI 3.1.2.4-5 In Table 3.1.2.4 Page 3.1-62 lists stainless steel valves operating in a treated water (internal) environment. The table notes show that the aging effect in NUREG-1801 (V.C.1-b) for this component, material and environment combination is not applicable. The table notes also indicate that based on the system design and operating history, MIC and biofouling are not applicable to the treated water portions of this system.
Discuss the age, operating history, and inspection history of the valves. Provide a detailed explanation of the attributes of the system design that make degradation due to MIC and biofouling not applicable.
RAI 3.1.2.4-6 In Table 3.1.2.4 identifies a One-Time inspection specified in B.2.1.29 as a part of the Aging Management Program (AMP). According to B.2.1.29 a One-Time inspection is applicable for piping and fittings with diameter less than 4 inch nominal pipe size (NPS). Identify whether the reactor recirculation system has previously experienced cracking due to stress corrosion cracking (SCC), intergranular stress corrosion cracking (IGSCC) or cyclic loading, and the extent of cracking. If cracking has occurred, identify whether the cracking was in piping less than 4 inch NPS and/or over 4 inch NPS. Identify the method of the One-Time inspection. The LRA does not address the type and frequency of the inspection requirements as a part of the AMP, for piping greater than 4 inch NPS. Identify the AMP used for piping greater than 4 inch NPS.
Tennessee Valley Authority BROWNS FERRY NUCLEAR PLANT cc:
Mr. Ashok S. Bhatnagar, Senior Vice President Nuclear Operations Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. James E. Maddox, Vice President Engineering & Technical Services Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Michael D. Skaggs, Site Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 General Counsel Tennessee Valley Authority ET 11A 400 West Summit Hill Drive Knoxville, TN 37902 Mr. John C. Fornicola, Manager Nuclear Assurance and Licensing Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Kurt L. Krueger, Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Mr. Jon R. Rupert, Vice President Browns Ferry Unit 1 Restart Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Mr. Robert G. Jones Browns Ferry Unit 1 Plant Restart Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Mr. Mark J. Burzynski, Manager Nuclear Licensing Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. Timothy E. Abney, Manager Licensing and Industry Affairs Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Mr. Bobby L. Holbrook Senior Resident Inspector U.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611-6970 State Health Officer Alabama Dept. of Public Health RSA Tower - Administration Suite 1552 P.O. Box 303017 Montgomery, AL 36130-3017 Chairman Limestone County Commission 310 West Washington Street Athens, AL 35611 Mr. Fred Emerson Nuclear Energy Institute 1776 I St., NW, Suite 400 Washington, DC 20006-2708
Tennessee Valley Authority BROWNS FERRY NUCLEAR PLANT cc:
Ken Brune, Manager Browns Ferry License Renewal Project Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801