BSEP 17-0006, Information Transmittal for NRC Model Development

Information Transmittal for NRC Model Development

ML17040A406
Person / Time
Site:	Brunswick
Issue date:	01/19/2017
From:	Pope A Duke Energy Progress
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 17-0006
Download: ML17040A406 (5)

Text

Brunswick Nuclear Plant

(-,DUKE P.O. Box 10429

<{; ENERGY Southport, NC 28461 January 19, 2017 Serial: BSEP 17-0006 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Information Transmittal for NRC Model Development

References:

1. Letter from William R. Gideon (Duke Energy) to the U.S. Nuclear Regulatory Commission Document Control Desk, Request for License Amendment Regarding Core Flow Operating Range Expansion, dated September 6, 2016, ADAMS Accession Number ML16257A418.

2. Letter from William R. Gideon (Duke Energy) to the U.S. Nuclear Regulatory Commission Document Control Desk, Response to Request for Supplemental Information for License Amendment Regarding Core Flow Operating Range Expansion, dated November 9, 2016, ADAMS Accession Number ML16330A504.

3. NRC E-mail Capture, Regulatory Audit Plan for Brunswick Steam Electric Plant Unit Nos. 1 and 2 to Support Review of the License Amendment Request Regarding Core Flow Operating Range Expansion Maximum Extended Load Line Limit Analysis Plus, Docket Nos. 50-325 and 50-324, dated October 19, 2016, ADAMS Accession Number ML16294A273.

4. Letter from Annette H. Pope (Duke Energy) to the U.S. Nuclear Regulatory Commission Document Control Desk, Information Transmittal for NRG Model Development, dated October 27, 2016, ADAMS Accession Number ML16320A177.

5. Letter from Annette H. Pope (Duke Energy) to the U.S. Nuclear Regulatory Commission Document Control Desk, Information Transmittal for NRG Model Development, dated November 17, 2016, ADAMS Accession Number ML16330A012.

Ladies and Gentlemen:

By letter dated September 6, 2016 (i.e., Reference 1), as supplemented by letter dated November 9, 2016 (i.e., Reference 2), Duke Energy Progress, LLC (Duke Energy), submitted a license amendment request (LAR) for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2, to support an expansion of the core power-flow operating range (i.e., Maximum Extended Av o' N~~

U.S. Nuclear Regulatory Commission Page 2 of 3 Load Line Limit Analysis Plus (MELLLA+ )). By Reference 3, the NRC initiated an audit to support their review of the LAR by conducting confirmatory calculations using the TRACE computer code.

Prior to issuance of the NRC audit plan, a telephone call was held on September 20, 2016, to discuss the feasibility of Duke Energy providing certain BSEP core-modelling information to support NRC development of a TRACE computer model. During the call, Duke Energy identified two items that may be used to support the NRC's model development efforts. The first item was AREVA Document Number 51-9173927-000, ATRIUM' 10XM Data for Brunswick MELLLA+

LAR Support. Duke Energy provided this information by letter dated October 27, 2016 (i.e.,

Reference 4). The second item was the General Electric Hitachi (GEH) TRACG computer code base deck that supports the BSEP MELLLA+ license amendment request, and the associated TRACG User's Manual. Duke Energy provided th.is information by letter dated November 17; 2016 (i.e., Reference 5).

On December 8, 2016, via a telephone conference call, the NRC identified the need for certain control blade information to support the NRC modelling effort. The information enclosed was provided to the NRC via electronic mail on December 13, 2016, in response to the request. The information is identical to that submitted via email.

No regulatory commitments are contained in this letter.

Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager - Regulatory Affairs, at (91 O) .457-2487.

Sincerely, Anne e H. Pope Director - Organizational Effectiveness Brunswick Steam Electric Plant J

WRM/wrm

Enclosure:

Control Blade Information

U.S. Nuclear Regulatory Commission Page 3 of 3 cc:

U.S. Nuclear Regulatory Commission (Electronic Copy Only)

ATTN: Mr. Andrew Hon (Mail Stop OWFN 8G9A) 11555 Rockville Pike Rockville, MD 20852-2738 Andrew.Hon@nrc.gov U.S. Nuclear Regulatory Commission, Region II ATTN: Ms. Catherine Haney, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 U.S. Nuclear Regulatory Commission ATTN: Ms. Michelle P. Catts, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 Chair - North Carolina Utilities Commission (Electronic Copy Only) 4325 Mail Service Center Raleigh, NC 27699-4300 swatson@ncuc.net

BSEP 17-0006 Enclosure Page 1 of 2 Control Blade Information Information on Control Blade Notch Size:

Control blade insertion is calibrated in notches, where one notch equals 3 inches. Position of the control blade is described by the number of notches withdrawn. Thus, 00 notch is full insertion and 48 notches is full withdrawal. Total travel of the control blade is 144 inches while the active fuel length is 150 inches. At full blade insertion (i.e., 00 notch}, the top of the control material is 7 inches below top of the active fuel. Since the physical notches in the control rod drive are 6 inches apart, the control blade notch position is always even.

Control Blade Material:

Type-304 stainless steel tubes for both the B4C tubes and sheath.

Schematic:

The following table contains associated parameters of interest. A schematic is provided below.

BWR4 D-Lattice Original Equipment Blade Data Schematic Parameter inches cm Dimension Central Support Span 1.58 4.0132 J Blade Span (Maximum) 9.88 25.0952 2*K Blade Thickness (Nominal) 0.312 0.7925 L Blade Sheath Thickness 0.056 0.1422 Poison Tube Wall Thickness 0.025 0.0635 Poison Tube OD 0.188 0.4775 Control Blade Tip Radius 0.156 0.3962 Absorber Zone Axial Length 143 363.22 Roller Diameter (Nominal) 0.520 1.32 Velocity Limiter Diameter (Maximum) 9.265 23.533 Number of B4C Tubes (Per Wing) 21 21 B4C Density (g/cm 3 ) 1.76.

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