ML042180449
| ML042180449 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/03/2004 |
| From: | Abney T Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TAC MC1768, TAC MC1769, TAC MC1770 | |
| Download: ML042180449 (7) | |
Text
August 3, 2004 10 CFR 54 10 CFR 51 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 (LR) APPLICATION - DETAILED EXPLANATION OF HOW THE LR APPLICATION BOUNDS THE BFN EXTENDED POWER UPRATE (EPU) SUBMITTALS (TAC NOS.
To assist the Nuclear Regulatory Commission (NRC) staff in its review of the Tennessee Valley Authority (TVA) applications for LR and EPU of the BFN units, TVA is submitting the enclosed detailed explanation of how the LR application bounds the BFN EPU submittal. The enclosure is essentially a road map which documents the review of plant systems included in the scope of LR to identify design or operational changes created by EPU.
This letter contains no new regulatory commitments.
If you have any questions about this information, please contact Ken Brune, Manager, BFN License Renewal Project, at (423) 751-8421 or, e-mail address: kabrune@tva.gov.
I declare under penalty of perjury that the foregoing is true and correct. Executed on this third day of August 2004.
Sincerely, Original signed by T. E. Abney Manager of Licensing and Industry Affairs
U.S. Nuclear Regulatory Commission Page 2 August 3, 2004 Enclosure cc: State Health Officer Alabama Department of Public Health RSA Tower - Administration Suite 1552 P.O. Box 303017 Montgomery, Alabama 36130-3017 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 on page 3
U.S. Nuclear Regulatory Commission Page 3 August 3, 2004 cc: Mr. Kahtan N. Jabbour, Senior Project Manager U.S. Nuclear Regulatory Commission MS 08G9 One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Ms. Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission MS 08G9 One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. William F. Burton, Senior Project Manager U.S. Nuclear Regulatory Commission MS 011F1 Two White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Yoira K. Diaz-Sanabria, Project Manager (w/enclosure)
U.S. Nuclear Regulatory Commission MS 011-F1 Two White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739
ENCLOSURE E-1 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2, AND 3 REVIEW OF THE BROWNS FERRY LICENSE RENEWAL APPLICATION (LRA) FOR EXTENDED POWER UPRATE (EPU) CONDITIONS
SUMMARY
The Browns Ferry License Renewal Application was developed in parallel with the EPU submittal. By our February 28, 2004 letter (Reference 1) additional information was provided discussing the effects of EPU on the LRA. This letter concluded that all evaluations in support of the LRA are valid at the uprated power level, except those associated with Section 4.3, Metal Fatigue. License Renewal Application Sections 4.2 and 4.3 were later updated by our letter of May 28, 2004 to reflect extended power uprate conditions (Reference 2).
The changing operational characteristics that potentially affect the identified aging mechanisms following extended power uprate are identified in Attachment 1. These operational characteristics were reviewed for the systems affected, as delineated in, to verify the license renewal application remains valid.
The Browns Ferry License Renewal Application is consistent with the final extended power uprate submittals (References 3 and 4).
REFERENCES
- 1.
Letter from T. E. Abney (TVA) to U.S. Nuclear Regulatory Commission, Browns Ferry Nuclear Plant (BFN) - Units 1, 2 and 3 - January 28, 2004 Meeting Follow-Up - Additional Information, dated February 19, 2004.
- 2.
Letter from T. E. Abney (TVA) to U.S. Nuclear Regulatory Commission, Browns Ferry Nuclear Plant (BFN) - Units 1, 2 and 3 License Renewal Application -
Update of Application Sections 4.2 and 4.3 to Reflect Extended Power Uprate Conditions, dated May 28, 2004
- 3.
Letter from T. E. Abney (TVA) to U.S. Nuclear Regulatory Commission, Browns Ferry Nuclear Plant (BFN) - Unit 1-Proposed Technical Specifications (TS)
Change TS - 431 - Request for License Amendment - Extended Power Uprate (EPU) Operation, dated June 28, 2004.
- 4.
Letter from T. E. Abney (TVA) to U.S. Nuclear Regulatory Commission, Browns Ferry Nuclear Plant (BFN) - Units 2 and 3 - Proposed Technical Specifications (TS) Change TS - 418 - Request for License Amendment Extended Power Uprate (EPU) Operation, dated June 25, 2004.
E-2 ATTACHMENT 1 OPERATIONAL CHARACTERISTICS POTENTIALLY AFFECTED BY EPU CONDITIONS Operating Characteristic Unit 1 Units 2 and 3 Power Level 3952 MWt Same Full Power Core Flow Range 101.5 to 107.6 Mlb/hr 99 to 105 % of rated flow Same Rated Core Flow 102.5 Mlb/hr Same Recirculation Flow Increased < 3%
Same Recirculation Temperature Increased < 2°F Same Full Power Steam Flow 16.44 Mlb/hr Same Maximum Nominal Dome Temperature 551°F Same Maximum Nominal Dome Pressure 1050 psia Same Full Power Feedwater Flow 16.39 Mlb/hr Same Full Power Feedwater Temperature 394.5 °F Same HPCI Turbine/Pump Speed 4100 rpm Same HPCI Pump Discharge Head 2930 feet Same RCIC Turbine/Pump Speed 4600 rpm Same RCIC Pump Discharge Head 2930 feet Same Neutron Fluence The neutron fluence values used for the license renewal evaluations are based on EPU conditions.
Same Cumulative Fatigue Usage Factors The cumulative fatigue usage factors values used for the license renewal evaluations are based on EPU conditions.
Same Plant Area Temperatures The increased heat loads during normal plant operation result in a maximum area temperature increase of < 3ºF Same Plant Area Radiation Levels The increase in radiation levels does not affect radiation zoning or shielding in the various areas because it is offset by conservatism in the original design, source terms used and analytical techniques.
Same
E-3 ATTACHMENT 2 REVIEW FOR POTENTIAL IMPACT DUE TO EPU CONDITIONS LRA Section System/Structure
/Component Reference 3,,
PUSAR Section Changes in Unit 1 System Operating Characteristics Reference 4,,
PUSAR Section Changes in Units 2 and 3 System Operating Characteristics 3.4.2.1.1 Main Steam System (001) 3.5, 3.11, and Table 1-2 Steam flow rate Steam temperature Steam pressure 3.5, 3.11, and Table 1-2 Steam flow rate 3.4.2.1.3 Feedwater System (003) 3.5, 3.11, and Table 1-2 Feedwater flow rate Feedwater temperature Feedwater pressure 3.5, 3.11, and Table 1-2 Feedwater flow rate Feedwater temperature 3.4.2.1.4 Heater Drains &
Vents System (006) 3.11 Steam flow rate Steam temperature Steam pressure 3.11 Steam flow rate 3.4.2.1.5 Turbine Drains and Miscellaneous Piping (008) 3.11 Steam flow rate Steam temperature Steam pressure 3.11 Steam flow rate 3.1.2.1.4 Recirculation (068) 3.4, 3.5 and 10.4 Recirculation flow Recirculation temperature 3.4, 3.5 and 10.4 Recirculation flow Recirculation temperature 3.3.2.1.23 Reactor Core Isolation Cooling (071) 3.5, 3.8, and 3.11 Turbine/Pump Speed Pump Discharge Head 3.5, 3.8, and 3.11 3.2.2.1.3 High Pressure Coolant Injection (073) 3.5, 3.11, and 4.2.1 Turbine/Pump Speed Pump Discharge Head 3.5, 3.11, and 4.2.1 3.1.2.1.1 and 3.1.2.1.2 Reactor Vessel and Internals (RVI) 3.3 Reactor coolant temperature Reactor coolant flow rate 3.3 Reactor coolant temperature Reactor coolant flow rate
E-4 ATTACHMENT 2 REVIEW FOR POTENTIAL IMPACT DUE TO EPU CONDITIONS LRA Section System/Structure
/Component Reference 3,,
PUSAR Section Changes in Unit 1 System Operating Characteristics Reference 4,,
PUSAR Section Changes in Units 2 and 3 System Operating Characteristics 4.2 Reactor Vessel and Internals (RVI) 3.3.1 Neutron fluence 3.3.1 Neutron fluence 4.3.1 and 4.3.2 Reactor Vessel and Internals (RVI) 3.3.2.2 Cumulative fatigue usage factors 3.3.2.2 Cumulative fatigue usage factors 3.6 Various Organic Polymers/
Temperature 6.6 Plant area temperatures 6.6 Plant area temperatures 4.4 Environmental Qualification 10.3.1 Plant area temperatures Plant area radiation levels 10.3.1 Plant area temperatures Plant area radiation levels 3.5.2.1.1 Primary Containment Structures 6.6 Plant area temperatures 6.6 Plant area temperatures 3.5.2.1.2 Reactor Buildings 6.6 Plant area temperatures 6.6 Plant area temperatures 3.5.2.1.20 Turbine Buildings 6.6 Plant area temperatures 6.6 Plant area temperatures 3.5.2.1.26 Structures and Component Supports Commodities 6.6 Plant area temperatures 6.6 Plant area temperatures