ML050310428

License Renewal Application - Annual Update

ML050310428
Person / Time
Site:	Browns Ferry
Issue date:	01/31/2005
From:	Abney T Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MC1704, TAC MC1705, TAC MC1706
Download: ML050310428 (10)

Text

January 31, 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 - ANNUAL UPDATE (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 (BFN),

Units 1, 2, and 3.

TVA is required by 10 CFR 54.21(b) to report changes annually to the BFN current licensing basis that materially affect the contents of the LRA, including the Updated Final Safety Analysis Report supplement.

TVA has completed a review of the pertinent documentation and identified changes which materially affect the contents of the BFN LRA. The enclosure to this letter contains the changes to the BFN LRA.

U.S. Nuclear Regulatory Commission Page 2 January 31, 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 31st day of January, 2005.

Sincerely, Original signed by:

T. E. Abney Manager of Licensing and Industry Affairs

Enclosure:

cc: See page 3

U.S. Nuclear Regulatory Commission Page 3 January 31, 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 January 31, 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 January 31, 2005 GLS:BAB Enclosure cc (Enclosure):

A. S. Bhatnagar, LP 6-C K. A. Brune, LP 4F-C J. C. Fornicola, LP 6A-C R. G. Jones, NAB 1A-BFN K. L. Krueger, POB 2C-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://BFN License Renewal Annual Update Letter TVA Response

ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

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

ANNUAL UPDATE (SEE ATTACHED)

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

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

ANNUAL UPDATE 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 (BFN),

Units 1, 2, and 3.

TVA is required by 10 CFR 54.21(b) to report changes annually to the BFN current licensing basis that materially affect the contents of the LRA, including the Updated Final Safety Analysis Report supplement.

Listed below are the changes which materially affect content of the BFN License Renewal Application.

RAW COOLING WATER SYSTEM (024)

Plant modification deleted carbon steel strainers. This deletes the following line items from Table 3.3.2.4 on page 3.3-90:

Table 3.3.2.4: Raw Cooling Water System (024) - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG -

1801 Vol.

2 Item Table 1 Item Notes Strainers PB Carbon and Low Alloy Steel Inside Air (external)

Loss of material due to general corrosion.

Systems Monitoring Program (B.2.1.39)

VII.I.1-b 3.3.1.5 A

Strainers PB Carbon and Low Alloy Steel Raw Water (internal)

Loss of material due to galvanic corrosion.

Open-Cycle Cooling Water System Program (B.2.1.17)

VII.C1.6-a None H, 3 Strainers PB Carbon and Low Alloy Steel Raw Water (internal)

Loss of material due to MIC, biofouling,

general, crevice, and pitting corrosion.

Open-Cycle Cooling Water System Program (B.2.1.17)

VII.C1.6-a 3.3.1.17 A

E-2 HIGH PRESSURE FIRE PROTECTION SYSTEM (026)

Plant modification deleted components shown on drawing 3-47E850-8. Therefore, drawing 3-47E850-8-LR is no longer required as a license renewal boundary drawing. In the list of License Renewal Drawings in Section 2.3.3.6 on page 2.3-47, delete drawing 3-47E850-8-LR. There are no changes to the component types, materials, or environments for this system as a result of this change.

EMERGENCY EQUIPMENT COOLING WATER SYSTEM (EECW) (067)

The following component type/material/environment combinations were inadvertently omitted. The alternate fuel pool cooling lines had always been in scope for EECW, but it was overlooked that this alternate fuel pool cooling path is in a standby mode and so not filled with water until manually placed into service.

This results in additional line items to Table 3.3.2.20 as shown below:

Table 3.3.2.20: Emergency Equipment Cooling Water System (067) -

Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG -

1801 Vol.

2 Item Table 1

Item Notes Fittings PB Cast Iron and Cast Iron Alloy Air/gas (internal)

Loss of material due to general corrosion One-Time Inspection Program (B.2.1.29)

VII.C1.1-a None F, 1 Valves PB Copper Alloy Air/gas (internal)

None None VII.C1.1-a None F, 3 REACTOR RECIRCULATION SYSTEM (068)

Plant modification deleted or abandoned components on drawing 3-47E817-2, and added components to drawing 3-47E844-2.

Therefore, drawing 3-47E844-2-LR is a new Reactor Recirculation System boundary drawing and drawing 3-47E817-2-LR is no longer required. This affects the list of License Renewal Drawings in Section 2.3.1.4 on page 2.3-12. There are no changes to the component types, materials, or environments for this system as a result of these changes.

E-3 HIGH PRESSURE COOLANT INJECTION SYSTEM (073)

Plant walkdowns created new drawing 1-47E812-2. This drawing should be included in the list of License Renewal Drawings in Section 2.3.2.3 on page 2.3-23. Component types, materials, and environments for the in-scope components shown on drawing 1-47E812-2 are already included in Section 2.3.2.3, Section 3.2.2.1.3, and Table 3.2.2.3. Therefore, no changes to the component types, materials, or environments for the High Pressure Coolant Injection System are required.

LICENSE RENEWAL BOUNDARY DRAWINGS License renewal boundary drawings have been maintained to reflect the current license renewal boundaries such that they are consistent with the LRA, RAI responses, change documentation, etc. Examples of some of the administrative changes made to the boundary drawings include:

• The reference drawing interface arrows for piping runs corrected as interfaces between drawings change

• Other valves and fittings added on drawings but to portion of the drawings that are not in license renewal boundary scope

• Specific BFN Unit IDs (i.e. valve numbers updated for a commodity that is already in scope)

• Leak off / drain valves removed from license renewal boundary drawings when found removed from system These drawing changes do not materially affect the contents of the LRA.

B.2.1.32 ASME Section XI Subsection IWE Program By letter dated March 1, 2004 (Accession No. ML0406200480), NRC authorized relief requests 1-CISI-1, 1-CISI-2, and 1-CISI-3 related to Containment Inservice Inspection Program for Unit 1.

Therefore, Exceptions 1, 2, and 3 to the ASME Section XI Subsection IWE Program are applicable to Units 1, 2, and 3.

LRA Update The following two items are not material changes to the CLB.

Both items are administrative errors made at the time of the

E-4 issuance of the application. In both cases, the license renewal boundary diagrams were appropriately marked and the aging management reviews were appropriately performed, but the table line item was marked incorrectly:

REACTOR VESSEL VENTS AND DRAIN SYSTEM (010)

The (a)(2) block in Section 2.3.1.3 on page 2.3-9 was inadvertently marked No. The corrected table is shown below:

(a)(1)

(a)(2)

(a)(3)

FP (a)(3)

EQ (a)(3)

ATWS (a)(3)

SBO Yes Yes No No No No The associated boundary drawings appropriately identified the components as being in-scope for 10 CFR 54.4(a)(2). There are no new component types, materials, or environments introduced into the system as a result of this change.

REACTOR CORE ISOLATION COOLING SYSTEM (071)

The (a)(2) block in Section 2.3.3.23 on page 2.3-84 was inadvertently marked No. The corrected table is shown below:

(a)(1)

(a)(2)

(a)(3) FP (a)(3) EQ (a)(3)

ATWS (a)(3)

SBO Yes Yes Yes (F.3)

Yes (F.4)

Yes (F.7)

Yes The associated boundary drawings appropriately identified the components as being in-scope for 10 CFR 54.4(a)(2). There are no new component types, materials, or environments introduced into the system as a result of this change.