ML051660547

License Renewal Application - Response to NRC Request for Additional Information for the Time-Limited Aging Analysis (Tlaas) Identified in 4.7.2 and 4.7.5 of LRA

ML051660547
Person / Time
Site:	Browns Ferry
Issue date:	06/15/2005
From:	Crouch W Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MC1704, TAC MC1705, TAC MC1706
Download: ML051660547 (8)

Text

June 15, 2005 10 CFR 54 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 Gentlemen:

In the Matter of

)

Docket Nos. 50-259 Tennessee Valley Authority

)

50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS 1, 2, AND 3 -

LICENSE RENEWAL APPLICATION (LRA) - RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION FOR THE TIME-LIMITED AGING ANALYSIS (TLAAs) IDENTIFIED IN 4.7.2 AND 4.7.5 OF LRA (TAC NOS. MC1704, MC1705, AND MC1706)

By letter dated December 31, 2003, TVA submitted, for NRC review, an application pursuant to 10 CFR 54, to renew the operating licenses for the Browns Ferry Nuclear Plant, Units 1, 2, and 3. As part of its review of TVAs LRA, the NRC staff, through an informal request on June 9, 2005, requested that TVA provide additional information for the TLAAs identified in Sections 4.7.2 and 4.7.5 of the LRA.

The enclosure to this letter contains the specific NRC request for additional information and the corresponding TVA response.

U.S. Nuclear Regulatory Commission Page 2 June 15, 2005 If you have any questions regarding this information, please contact Ken Brune, Browns Ferry License Renewal Project Manager, at (423) 751-8421.

I declare under penalty of perjury that the foregoing is true and correct. Executed on this 15th day of June, 2005.

Sincerely, Original signed by:

William D. Crouch Acting Manager of Licensing and Industry Affairs

Enclosure:

cc: See page 3

U.S. Nuclear Regulatory Commission Page 3 June 15, 2005 Enclosure cc (Enclosure):

State Health Officer Alabama Department of Public Health RSA Tower - Administration Suite 1552 P.O. Box 303017 Montgomery, Alabama 36130-3017 Chairman Limestone County Commission 310 West Washington Street Athens, Alabama 35611 (Via NRC Electronic Distribution)

Enclosure cc (Enclosure):

U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 Mr. Stephen J. Cahill, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Senior Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970 NRC Unit 1 Restart Senior Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970 cc: continued page 4

U.S. Nuclear Regulatory Commission Page 4 June 15, 2005 cc: (Enclosure)

Margaret Chernoff, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)

One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)

One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Yoira K. Diaz-Sanabria, Project Manager U.S. Nuclear Regulatory Commission (MS 011F1)

One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Ramachandran Subbaratnam, Project Manager U.S. Nuclear Regulatory Commission (MS 011F1)

One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739

U.S. Nuclear Regulatory Commission Page 5 June 15, 2005 JEM:TLE:BAB Enclosure cc (Enclosure):

B. M. Aukland, POB 2C-BFN A. S. Bhatnagar, LP 6-C K. A. Brune, LP 4F-C J. C. Fornicola, LP 6A-C R. G. Jones, NAB 1A-BFN R. F. Marks, Jr., PAB 1A-BFN F. C. Mashburn, BR 4X-C N. M. Moon, LP 6A-C J. R. Rupert, NAB 1F-BFN K. W. Singer, LP 6A-C M. D. Skaggs, PAB 1E-BFN E. J. Vigluicci, ET 11A-K NSRB Support, LP 5M-C EDMS, WT CA-K s://Licensing/Lic/BFN LR Clarification of TLAAs in 4.7.2 and 4.7.5 of LRA.doc

ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION (LRA)

RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION FOR THE TLAAs IDENTIFIED IN 4.7.2 AND 4.7.5 OF LRA (SEE ATTACHED)

E-1 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION (LRA)

RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION FOR THE TLAAs IDENTIFIED IN 4.7.2 AND 4.7.5 OF LRA By letter dated December 31, 2003, TVA submitted, for NRC review, an application pursuant to 10 CFR 54, to renew the operating licenses for the Browns Ferry Nuclear Plant, Units 1, 2, and 3. As part of its review of TVAs LRA, the NRC staff, through an informal request on June 9, 2005, requested that TVA provide additional information for the TLAAs identified in Sections 4.7.2 and 4.7.5 of the LRA.

This enclosure contains the specific NRC request for additional information and the corresponding TVA response.

NRC REQUEST Describe the details of the 10 CFR 54.3 evaluation for the TLAAs identified in Sections 4.7.2 (Corrosion - Flow Reduction) and 4.7.5 (Corrosion - Minimum Wall Thickness) of the LRA.

TVA RESPONSE TO NRC REQUEST

a. Section 4.7.2 The last sentence of the Summary Description of Section 4.7.2 of the LRA states Thus, calculations using the design document's time dependent decreasing effective pipe diameter to verify 40-year flow requirements are TLAAs.

This calculation evaluates the flow reduction due to corrosion in carbon steel piping used in raw water systems.

The functional basis for determining the acceptability of the piping in different systems at BFN is based on periodic flow testing as described in the following BFN site procedures:

Technical Instruction 0-TI-171, RHRSW Sump Pump Flow Rate Test, Surveillance Instruction 0-SI-4.5.C.1(4), EECW System Annual Flow Rate Test, Surveillance Instructions 1/2/3-SI-4.5.C.1(3), RHRSW Pump and Header Operability and Flow Test, and

E-2 Surveillance Instruction 0-SI-4.11.B.1.g, High Pressure Fire Protection System Flow Test.

Based on this further review, TVA has determined that the calculations should not be considered to be a TLAA, and all of Section 4.7.2 is deleted from the LRA.

b. Section 4.7.5 The Summary Description for Section 4.7.5 of the LRA states:

Corrosion/erosion results in decreasing pipe wall thickness. This wall thickness reduction can result in the loss of the system pressure boundary. Corrosion allowance values specified in design documents were used to determine the minimum wall thickness values. These design documents specified corrosion allowance values for a 40-year service life. These calculations which used the corrosion allowance values specified in the design documents are considered a TLAA.

These calculations evaluate corrosion/erosion that result in decreasing pipe wall thickness.

The functional basis for ensuring the wall thickness acceptability is accomplished by inspection, testing, and monitoring activities performed by BFN site procedures that implement SPP-9.7, Corrosion Control Program.

Based on this further review, TVA has determined that the calculations should not be considered to be a TLAA, and all of Section 4.7.5 is deleted from the LRA.