ML043440045

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RAI, Extended Power Uprate
ML043440045
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 12/30/2004
From: Chernoff M
NRC/NRR/DLPM/LPD2
To: Singer K
Tennessee Valley Authority
Chernoff, M H, NRR/DLPM, 301-415-4041
References
TAC MC3812
Download: ML043440045 (5)


Text

December 30, 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:

BROWNS FERRY NUCLEAR PLANT, UNIT 1 REQUEST FOR ADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE (TAC NO. MC3812)

(TS-431)

Dear Mr. Singer:

By letter dated 28, 2004, the Tennessee Valley Authority (TVA or the licensee), submitted to the U.S. Nuclear Regulatory Commission (NRC) an amendment request for Browns Ferry Nuclear Plant (BFN), Unit 1. The proposed amendment would change the BFN, Unit 1 operating license to increase the maximum authorized power level from 3293 to 3952 megawatt thermal (MWt). These changes represent an increase of approximately 20 percent above the current maximum authorized power level for Unit 1. The proposed amendment would also change the BFN licensing bases and associated Technical Specifications to credit 3 pounds per square inch gage (psig) for containment overpressure following a loss-of-coolant accident, and increase the reactor steam dome pressure by 30 psig.

The NRC staff has reviewed your submittal and finds that a response to the enclosed request for additional information is needed before we can complete the review. If you have any questions, please contact me at (301) 415-4041.

Sincerely,

/RA/

Margaret H. Chernoff, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-259

Enclosure:

Request for Additional Information cc w/encl: See next page

Enclosure REQUEST FOR ADDITIONAL INFORMATION EXTENDED POWER UPRATE (EPU)

TENNESSEE VALLEY AUTHORITY BROWNS FERRY PLANT, UNIT 1 DOCKET NO. 50-259 1.

Explain why the reactor coolant pressure boundary (RCPB) piping materials are not affected by the power uprate.

2.

Identify the materials of construction for the Reactor Recirculation System piping and discuss the effect of the requested extended power uprate (EPU) on the material. If other than type "A" (per NUREG 0313) materials exist, discuss any augmented inspection programs and discuss the adequacy of augmented inspection programs in light of the EPU.

3.

Section XI of the American Society of Mechanical Engineers (ASME) Code allows flaws to be left in service after a proper evaluation of the flaws is performed in accordance with the ASME,Section XI rules. Indicate whether such flaws exist in the Reactor Recirculation System piping and evaluate the effect of the EPU on the flaws.

4.

Discuss flaw mitigation steps that have been taken for the RCPB piping and discuss changes, if any, that will be made to the mitigation process as a result of the EPU.

5.

The U.S. Nuclear Regulatory Commission (NRC) staff has determined that setpoint Allowable Values (AV) established by means of Instrumentation, Systems, and Automation Society document ISA 67.04 Part 2, Method 3 (Method 3) do not provide adequate assurance that a plant will operate in accordance with the assumptions upon which the plant safety analyses have been based. These concerns are summarized in the June 17, 2004, letter from Mr. Ledyard B. Marsh to Mr. Alex Marion, Nuclear Energy Institute, available on the public website under ADAMS Accession Number ML041690604. In this submittal, several setpoint AVs have been established using Method 3. Tennessee Valley Authority should describe the approach intended to ensure that at least 95 percent probability with at least 95 percent confidence that the associated action will be initiated with the process variable no less conservative than the initiation value assumed in the plant safety analyses. The approach presented should be detailed and should explicitly address how the approach provides adequate assurance that the safety analysis assumptions will not be violated.

6.

Provide a detailed discussion on the impact of the EPU on the fire protection program and post-fire safe-shutdown analysis evaluation. General Electric report ?GE ELTR NEDC-33047P, Rev. 2 in Enclosure 4 appears to be the only discussion of the fire protection program, fire suppression and detection systems in the submittal.

7.

Discuss how the change in the fluence by EPU will affect the surveillance capsule withdrawal schedule (i.e., discuss whether there are any effect on the Boiling Water Reactor Vessel Internals Project, Integrated Surveillance Program, as applicable to Unit 1, because of this power uprate).

8.

Discuss the effects of the EPU on the Upper Shelf Energy of the beltline components and the welds of the Unit 1 reactor pressure vessel.

9.

Provide a discussion on any potential emergency action level changes that have been identified as a result of the proposed power uprate.

10.

Provide a list specifically identifying all design bases changes, excluding Technical Specification changes, in the submittal requiring prior NRC approval.

11.

In Enclosure 4, Section 7.4, a flow margin of 5 percent is established for the feedwater/condensate system. Dicsuss the basis for this criterion and how it compares with the pre-EPU margin. Discuss whether this is a change to the licensing basis, and how the flow margin and feedwater pump runout assumptions will be confirmed during startup testing.

12.

Provide a description of the major differences in the Unit 1 operation; procedures; system configuration; and flow, pressure, and level setpoints as compared to those of Units 2 and 3.

13.

In Enclosure 4, Section 4.2.5 addresses protective coatings. Discuss the effect of extended shutdown on qualified coatings, the measures taken, and the inspection results.

ML043440045 NRR-088 OFFICE PDII-2/PM PDII-2/PM PDII-2/LA PDII-2/SC NAME EBrown MChernoff CHawes for BClayton MMarshall DATE 12/29/04 12/24/04 12/16/04 12/30/04

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UNIT 1 REQUEST FOR ADDITIONAL INFORMATION REGARDING EXTENDED POWER UPRATE (TAC NO.

MC3812)

Distribution PUBLIC PDII-2 R/F OGC ACRS EBrown KJabbour BClayton (hard copy)

MMarshall EHackett JLyons LMarsh TChan DTrimble RDennig DRoberts LLund MYoder GGeorgiev JBongarra EThrom JTappert FAkstulewicz MMasnik GThomas KManoly JDixon-Herrity CWu JTatum EMarinos DThatcher SWeerakkody LMarsh HLi RPettis NIqbal BSheron RJenkins SKlementowiz MRubin JStang NTrehan AHayes RPederson MStutzke SLaur RMatthew SCoffin MKhanna EImbro JUhle AAttard EWeis, NSIR KWilliams, NSIR SCahill, RII LRaghavan

Mr. Karl W. Singer 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. Larry S. Bryant, 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 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