ML062510371

Technical Specifications Changes TS-431 & TS-418 Extended Power Uprate - Replacement Documentation

ML062510371
Person / Time
Site:	Browns Ferry
Issue date:	08/31/2006
From:	O'Grady B Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MC3743, TAC MC3744, TAC MC3812, TVA-BFN-TS-418, TVA-BFN-TS-431
Download: ML062510371 (4)

Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 Brian O'Grady Vice President, Browns Ferry Nuclear Plant August 31, 2006 TVA-BFN-TS-431 TVA-BFN-TS-418 10 CFR 50.90 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 -

TECHNICAL SPECIFICATIONS (TS) CHANGES TS-431 AND TS-418 -

EXTENDED POWER UPRATE (EPU) - REPLACEMENT DOCUMENTATION (TAC NOS. MC3812, MC3743, AND MC3744)

By letters dated June 28, 2004 (ADAMS Accession No. ML041840109) and June 25, 2004 (ML041840301), TVA submitted applications to the NRC for EPU of BFN Unit 1 and BFN Units 2 and 3, respectively. In support of these license amendment requests, TVA has provided a number of engineering calculations and reports which demonstrate the adequacy of BFN operations at EPU conditions. This submittal provides replacements to certain engineering documentation that was previously provided to the NRC staff.

By letter dated August 4, 2006 (ML062220647), TVA provided calculations MDQ0999970046, Rev. 9, "NPSH Evaluation of Browns Ferry RHR and CS Pumps," and MDQ099920060011, Rev. 0, "Transient NPSH/Containment Pressure Evaluation of RHR and Core Spray Pumps." These calculations were referenced in the P"ffed an rIed paW ThDo

U.S. Nuclear Regulatory Commission Page 2 August 31, 2006 response to RAI question ACVB.56/54. Enclosures 1 and 2 are revised calculations MDQ0999970046, Rev. 10 and MDQ099920060011, Rev. 1, respectively. The revised calculations provide corrected information as described in the applicable enclosure coversheets. The enclosed calculations entirely supersede those previously provided.

Additionally, Figure ACVB.56/54-3, "NPSH Requirements for Appendix R," of the August 4, 2006, submittal is superseded by Figure 7.14 of Enclosure 2.

By letter dated May 5, 2006 (ML061300436), TVA submitted Continuum Dynamics, Incorporated (CDI) Report No.05-28P, Rev. 1, "Bounding Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements," and requested that it be withheld from public disclosure pursuant to the provisions of 10 CFR 2.390. At that time, the entire contents of the report were identified as proprietary, and no redacted version of the report was provided. The NRC staff subsequently found, as documented in letter to CDI dated August 8, 2006, that portions of the report did not appear to contain commercial information that would meet the criteria specified in 10 CFR 2.390 for public withholding.

Consequently, CDI has prepared a non-proprietary version (Enclosure 3) of the subject report with the proprietary information redacted. Enclosure 3 is suitable for public disclosure.

TVA has determined that the additional information provided by this letter does not affect the no significant hazards considerations associated with the proposed TS changes. The proposed TS changes still qualify for a categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51.22(c) (9).

No new regulatory commitments are made in this submittal.

If you have any questions regarding this letter, please contact William D. Crouch at (256)729-2636.

U.S. Nuclear Regulatory Commission Page 3 August 31, 2006 I declare under penalty of perjury that the foregoing is true and correct. Executed on this 3 1 st day of August, 2006.

Sincerely, Brian O'Grady

Enclosures:

1. Calculation MDQ0999970046, Rev. 10, "NPSH Evaluation of Browns Ferry RHR and CS Pumps"

2. Calculation MDQ099920060011, Rev. 1, "Transient NPSH/Containment Pressure Evaluation of RHR and Core Spray Pumps"

3. CDI Report No.05-28P, Rev. 1, "Bounding Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements" (redacted version)

U.S. Nuclear Regulatory Commission Page 4 August 31, 2006 cc (w. Enclosures):

State Health Officer Alabama Dept. of Public Health RSA Tower - Administration Suite 1552 P.O. Box 303017 Montgomery, AL 36130-3017 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-3415 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 Margaret Chernoff, 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