ML050980086

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Request for Additional Information for the Review of the Browns Ferry Nuclear Plant, Units 1, 2, and 3, License Renewal Application
ML050980086
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 04/08/2005
From: Subbaratnam R
NRC/NRR/DRIP/RLEP
To: Singer K
Tennessee Valley Authority
Subbaratnam R NRR/DRIP/RLEP, 415-1478
References
TAC MC1704, TAC MC1705, TAC MC1706
Download: ML050980086 (7)


Text

April 8, 2005 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 or the applicant) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54), to renew the operating licenses for Browns Ferry Nuclear (BFN), 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, in the enclosure, areas where additional information is needed to complete the review.

These RAIs were discussed with Mr. Ken Brune of your staff and a mutually agreeable date for this response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1478 or e-mail rxs2@nrc.gov.

Sincerely,

/RA/

Ram Subbaratnam, 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/encls: See next page

April 8, 2005 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 or the applicant) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54), to renew the operating licenses for Browns Ferry Nuclear (BFN), 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, in the enclosure, areas where additional information is needed to complete the review.

These RAIs were discussed with Mr. Ken Brune of your staff and a mutually agreeable date for this response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1478 or e-mail rxs2@nrc.gov.

Sincerely,

/RA/

Ram Subbaratnam, 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/encls: See next page DISTRIBUTION: See next page Adams Accession No.: ML050980086 Document Name: E:\\Filenet\\ML050980086.wpd OFFICE PM:RLEP PM: RLEP LA:RLEP SC:RLEP NAME YDiaz-Sanabria RSubbaratnam YEdmonds SLee DATE 04/ 07 /05 04/ 07 05 04/ 07 /05 04/ 08 05 OFFICIAL RECORD COPY

BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc:

Mr. Ashok S. Bhatnagar, Senior Vice President Nuclear Operations Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Michael J. Lorek, General Manager Nuclear Engineering 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. Fredrick C. Mashburn, Senior Program 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

BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc:

BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc:

Ken Brune, Manager Browns Ferry License Renewal Project Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801

DISTRIBUTION: Letter to: K. Singer, Re: RAI for review of Browns Ferry Nuclear Plant, Units 1 and 2, Dated: April 8, 2005 Adams Accession No.: ML050980086 HARD COPY RLEP RF E-MAIL:

RidsNrrDrip RidsNrrDe G. Bagchi K. Manoly W. Bateman J. Calvo R. Jenkins P. Shemanski J. Fair RidsNrrDssa RidsNrrDipm D. Thatcher R. Pettis G. Galletti C. Li K. Winsberg (RidsOgcMailCenter)

R. Weisman M. Mayfield A. Murphy S. Smith (srs3)

S. Duraiswamy Y. L. (Renee) Li RLEP Staff M. Chernoff C. Julian (RII)

S. Cahill (RII)

A. Hodgdon C. Carpenter D. Coe E. Kleeh M. Marshall

Enclosure BROWNS FERRY NUCLEAR, UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION (LRA)

REQUEST FOR ADDITIONAL INFORMATION (RAI)

RAI 2.3.3.21-1 License renewal drawings 2-47E810-1-LR and 3-47E810-1-LR show thermal tees (location F6) to be within the scope of license renewal and subject to an AMR. Thermal tees are the passive and long-lived components, however thermal tee component type is not listed in LRA Table 2.3.3.21-1 as a component type subject to an AMR, nor is it included in a component type in Section 2.3.5, "Notes Associated with Section 2.3 Tables." Please justify the exclusion of these components from being subject to an AMR in accordance with the requirements of 10 CFR 54.21(a)(1).

RAI 2.3.3.21-2 License renewal drawings 2-47E810-1-LR and 3-47E810-1-LR show fusible plugs (location D2) to be within the scope of license renewal (in blue color for 54.4(a)(2) component in scope) and subject to an AMR. The "NOTE" of the drawing associated with fusible plugs states that fusible plug (FUPG) is a threaded pipe plug with a low temperature eutectic alloy which is attached to the RWCU pipe upstream of FCV-69-94. Eutectic material will melt on high temperature, venting the control air line, which closes isolation valve FCV-69-94. Also, another drawing note states that the system shall be qualified for an elevated temperature excursion up to 562E F during an Appendix R event from the non-generative heat exchanger outlet to FCV-69-94.

a.

The fusible plugs are neither listed in LRA Table 2.3.3.21 as a component type subject to an AMR, nor as a subcomponent of the component types listed in Section 2.3.5.

Please justify the exclusion of these components from being subject to an AMR in accordance with the requirements of 10 CFR 54.21(a)(1).

b.

Based on the drawing notes mentioned above, it appears that FCV-69-94 satisfy the criterion in 10 CFR 54.4(a)(3) for an environmental qualification and/or fire protection regulated event. However, the piping and components associated with this valve, including the above mentioned fusible plugs, are shown as being in scope in accordance with the criterion in 10 CFR 54.4(a)(2). Explain why valve FCV-69-94 functions differently from its associated pipeline.

RAI 2.3.3.21-3 Browns Ferry Nuclear Plant FSAR, Revision 20, Section 4.9 (page 4.9-2) states that:

Reactor coolant is continuously removed from the reactor coolant recirculation system, cooled in the regenerative and non-regenerative heat exchangers, filtered and demineralized, and returned to the feedwater system through the shell side of the regenerative heat exchanger. The Unit 3 RWCU system has the capability to return the processed fluid to the feedwater system through both reactor feedwater lines A and B.

However, Unit 2 RWCU system has only one return line through reactor feedwater line B.

License renewal drawing 3-47E810-1-LR shows (location E7) the reactor water cleanup system return line to the reactor feedwater line B only. Indicate whether feedwater line A is within the scope of license renewal and subject to an AMR, or provide an explanation for its exclusion. (Alternatively, provide a drawing that shows the reactor water cleanup system return to feedwater line A for Unit 3.)

RAI 2.3.3.21-4 License renewal drawing 1-47E810-1-LR shows flow indicators, FI 85-75 (location G3) and FI-85-77 (location G1), and flow element, FE-69-13 (location C5), as excluded from the scope of license renewal. These flow indicators and flow element serve a pressure boundary function and are passive and long-lived components. It is noted that similar flow indicators and flow elements on drawings 2-47E810-1-LR and 3-47E810-1-LR are shown as within the scope of license renewal and subject to an AMR. However, flow indicators are neither listed in LRA Table 2.3.3.21 as a component type subject to an AMR, nor as a subcomponent of the component types listed in Section 2.3.5.

a.

Justify the exclusion of the aforementioned flow indicators and flow element in Unit 1 from the scope of license renewal and being subject to an AMR in accordance with the requirements of 10 CFR 54.4(a) and 10 CFR 54.21(a)(1), respectively.

b.

Clarify whether flow indicators are included in other component types listed in LRA Table 2.3.3.21, or justify the exclusion of them from being subject to an AMR in accordance with the requirements of 10 CFR 54.21(a)(1).

RAI 2.3.3.21-5 License renewal drawing 3-47E810-1-LR shows a 4-inch pipeline to waste collector and surge tank inside the pipe tunnel to radwaste (location B4) as excluded from the scope of license renewal. However, the same pipeline on the license renewal drawing 1-47E810-1-LR (location B6) is shown as being in scope of license renewal in accordance with the requirements of 10 CFR 54.4(a)(2). Clarify this apparent discrepancy.