ML063530037

Core Operating Limits Report for Cycle 7 Operation

ML063530037
Person / Time
Site:	Browns Ferry
Issue date:	12/14/2006
From:	Crouch W Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TVA-COLR-BF1C7
Download: ML063530037 (9)

Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 December 14, 2006 U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Mail Stop:

OWFN, Pl-35 Washington, D.C. 20555-0001 Gentlemen:

In the Matter of

)

Docket No.

50-259 Tennessee Valley Authority BROWNS FERRY NUCLEAR PLANT (BFN)

UNIT 1 -

CORE OPERATING LIMITS REPORT (COLR)

FOR CYCLE 7 OPERATION In accordance with the requirements of Technical Specification 5.6.5.d, enclosed is the initial issue of the Unit 1 Cycle 7 COLR.

The Unit 1 Cycle 7 COLR was issued, to include Shutdown Margin criteria, in support of fuel loading as the unit proceeds toward restart.

There are no new commitments contained in this letter.

If you have any questions, please contact me at (256) 729-2636.

Sincerely, William D. Crouch Manager of Licensing and Industry Affairs Enclosure cc:

See page 2 DQ3O

U.S. Nuclear Regulatory Commission Page 2 December 14, 2006 Enclosure cc (Enclosure):

Mr.

Malcolm T.

Widmann, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, S.W.,

Suite 23T85 Atlanta, Georgia 30303-8931 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970 Ms.

Eva A.

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

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

U.S. Nuclear Regulatory Commission Page 3 December 14, 2006 DTL:JWD:BAB Enclosure cc (w/o Enclosure):

B.

M. Aukland, POB 2C-BFN M. Bajestani,

NAB, 1A-BFN A.

S.

Bhatnagar, LP 6A-C R.

H. Bryan, BR 4X-C R.

G. Jones, NAB lA-BFN G.

V.

Little, NAB ID-BFN R.

A.

DeLong, SAB-lA-BFN B.

J.

O'Grady, PAB IE-BFN K. W. Singer, LP 6A-C P.

D. Swafford, LP 6A-C E.

J.

Vigluicci, ET IIA-K NSRB Support, LP 5M-C EDMS WT CA-K (with Enclosure)

S:licensing\\lic\\submit\\subs\\COLR U1C7RO.doc

ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNIT 1 CORE OPERATING LIMITS REPORT (COLR),

REVISION 0, FOR CYCLE 7 OPERATION (SEE ATTACHED)

TVA Nuclear Fuel Core Operating Limits Report QA Document TVA-COLR-BF P

C7 Revision 0, Paee I Browns Ferry Nuclear Plant Unit 1 Cycle 7 CORE OPERATING LIMITS REPORT (COLR)

TENNESSEE VALLEY AUTHORITY Nuclear Fuel Design BWR Fuel Engineering Department Prepared By:

Verified By:

Approved By:

Reviewed By:

Approved By:

Earl E. Riley, Sr. Engineering Specialist BWR Fuel Engineering

'Brye C. Mitchell, Nuclear Engineer BWR Fuel Engineering Grgr trk Manager BWR Fuel Efigineering J.M-Keck, Supervisor Browns Ferry Reactor Engineering PGCChairman Date:

f/- /9 -O(.

Date:

____/7___

Date:

1-17-D6, Date: // z /4(-

Date:

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Revision 0 (11/20/2006)

Pages Affected: All Revision 0 (11/20/2006)

Pages Affected: All

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF 1 C7 Revision 0, Page 2 Revision Log Revision Date Description Affected Pages 0

11/20/2006 Initial Release of Interim COLR (to support Fuel Loading Only)

All Browns Ferry Nuclear Plant Unit I Cycle 7

TVA Nuclear Fuel TVA-COLR-BF 1 C7 Core Operating Limits Report Revision 0, Page 3

1. INTRODUCTION This Core Operating Limits Report (COLR) for Browns Ferry Nuclear Plant Unit 1 Cycle 7 is prepared in accordance with the requirements of Browns Ferry Technical Specification 5.6.5. This is an interim COLR issued to support fuel loading for the upcoming cycle. This COLR revision addresses only the following Technical Specification limit:

Shutdown Margin (SDM) Limit (Technical Specification 3.1.1)

The following core operating and Technical Specification limits are only required for operation and are not included in this interim COLR:

a. Average Planar Linear Heat Generation Rate (APLHGR) Limit (Technical Specifications 3.2.1 and 3.7.5)

b. Linear Heat Generation Rate (LHGR) Limit (Technical Specification 3.2.3)

c. Minimum Critical Power Ratio Operating Limit (OLMCPR)

(Technical Specifications 3.2.2, 3.3.4.1, and 3.7.5)

d. Average Power Range Monitor (APRM) Flow Biased Rod Block Trip Setting (Technical Requirements Manual Section 5.3.1 and Table 3.3.4-1)

e. Rod Block Monitor (RBM) Trip Setpoints and Operability (Technical Specification Table 3.3.2.1-1)

Browns Ferry Nuclear Plant Unit ] Cycle 7

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF I C7 Revision 0, Page 4

2. APLHGR LIMIT (TECHNICAL SPECIFICATIONS 3.2.1 AND 3.7.5)

The APLHGR limit will be supplied in a later COLR revision prior to Unit 1 Cycle 7 operation.

3. LHGR LIMIT (TECHNICAL SPECIFICATION 3.2.3)

The LHGR limit will be supplied in a later COLR revision prior to Unit I Cycle 7 operation.

4. OLMCPR (TECHNICAL SPECIFICATIONS 3.2.2, 3.3.4.1, AND 3.7.5)

The MCPR Operating Limit (OLMCPR) will be supplied in a later COLR revision prior to Unit 1 Cycle 7 operation.

5. APRM FLOW BIASED ROD BLOCK TRIP SETTING (TECHNICAL REQUIREMENTS MANUAL SECTION 5.3.1 AND TABLE 3.3.4-1)

The APRM Rod Block trip setting will be supplied in a later COLR revision prior to Unit I Cycle 7 operation.

6. ROD BLOCK MONITOR (RBM) TRIP SETPOINTS AND OPERABILITY (TECHNICAL SPECIFICATION TABLE 3.3.2.1-1)

The RBM trip setpoints and applicable power ranges will be supplied in a later COLR revision prior to Unit 1 Cycle 7 operation.

7. SHUTDOWN MARGIN (SDM) LIMIT (TECHNICAL SPECIFICATION 3.1.1)

The core shall be subcritical with the following margin with the strongest OPERABLE control rod fully withdrawn and all other OPERABLE control rods fully inserted (Ref. 2).

SDM > 0.38% dk/k Browns Ferry Nuclear Plant Unit I Cycle 7

TVA Nuclear Fuel TVA-COLR-BF I C7 Core Operating Limits Report Revision 0, Page 5 (Final)

8. REFERENCES

1. Global Nuclear Fuel Analytical Methodology

References:

a) NEDE-24011-P-A-15, "General Electric Standard Application for Reactor Fuel",

. September 2005.

b) NEDE-24011-P-A-15-US, "General Electric Standard Application for Reactor Fuel (Supplement for United States)", September 2005.

2. Browns Ferry Unit 1 Custom (pre-ITS) Technical Specification Section 4.3.A.1, "Reactivity margin core loading".

Browns Ferry Nuclear Plant Unit 1 Cycle 7