HNP-12-044, Response to Request for Additional Information on License Amendment Request - Measurement Uncertainty Recapture Power Uprate

Response to Request for Additional Information on License Amendment Request - Measurement Uncertainty Recapture Power Uprate

ML12100A160
Person / Time
Site:	Harris
Issue date:	03/26/2012
From:	Burton C Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
HNP-12-044
Download: ML12100A160 (5)

Text

Christopher L. Burton Progress Energy Vice President Harris Nuclear Plant

$,,*AR 2 6 z Progress Energy Carolinas, Inc.

Serial: HNP-12-044 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400 / RENEWED LICENSE NO. NPF-63

Subject:

REQUEST FOR LICENSE AMENDMENT MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE REQUEST FOR ADDITIONAL INFORMATION RESPONSE RELATED TO REACTOR CORE SAFETY LIMITS

Reference:

Letter from C. L. Burton to the U.S. NRC, "REQUEST FOR LICENSE AMENDMENT, MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE," Serial HNP-I 1-001 dated April 28, 2011, ADAMS Accession No. ML11124A180 Ladies and Gentlemen:

By letter dated April 28, 2011, Carolina Power & Light Company (CP&L), doing business as Progress Energy Carolinas, Inc., submitted a Request for License Amendment to the U.S.

Nuclear Regulatory Commission (NRC). The proposed amendment would increase the rated thermal power of Shearon Harris Nuclear Power Plant, Unit No. 1 (HNP) from 2,900 megawatts thermal (MWt) to 2,948 MWt, an increase of approximately 1.66 percent, and change the Technical Specifications (TS) accordingly. The proposed uprate is characterized as a measurement uncertainty recapture (MUR) using the Cameron Leading Edge Flow Meter (LEFM) CheckPlus System to improve plant calorimetric heat balance measurement accuracy.

In a telephone discussion with the NRC staff, the staff provided a request for additional information (RAI) related to proposed changes to the TS Reactor Core Safety Limits shown in Figure 2.1-1. The response to the request for additional information is provided in the enclosure to this letter.

This RAI response provides additional information to clarify the application, does not expand the scope of the application, and does not impact either the significant hazards consideration or the environmental consideration in the Request for License Amendment.

In accordance with 10 CFR 50.91(b), CP&L is providing the state of North Carolina with a copy of this response.

PO. Box 165 New Hill, NC 27562 T> 919.362.2502 F> 919.362.2095

U.S. Nuclear Regulatory Commission Page 2 HNP-12-044 This document contains no new regulatory commitments.

Please refer any questions regarding this submittal to Mr. David Corlett, Supervisor - HNP Li-cbnsing/Regulatory Programs, at (919) 362-3137.

I declare under penalty of perjury that the foregoing is true and correct. Executed on I[

2 U 2017 1.

Sincerely,

Enclosure:

REQUEST FOR ADDITIONAL INFORMATION RESPONSE RELATED TO REACTOR CORE SAFETY LIMITS cc:

Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mr. W. L. Cox, III, Section Chief N.C. DENR Ms. A. T. Billoch Col6n, NRC Project Manager, HNP Mr. V. M. McCree, NRC Regional Administrator, Region II

HNP-12-044 Enclosure SHEARON HARRIS NUCLEAR POWER PLANT / UNIT NO. 1 DOCKET NO. 50-400 / RENEWED LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE REQUEST FOR ADDITIONAL INFORMATION RESPONSE RELATED TO REACTOR CORE SAFETY LIMITS

U.S. Nuclear Regulatory Commission HNP-12-044 Enclosure Page 1 of 2 By letter dated April 28, 2011, Carolina Power & Light Company (CP&L), doing business as Progress Energy Carolinas, Inc., submitted a Request for License Amendment to the U.S.

Nuclear Regulatory Commission (NRC). The proposed amendment would increase the rated thermal power of Shearon Harris Nuclear Power Plant, Unit No. 1 (HNP) from 2,900 megawatts thermal (MWt) to 2,948 MWt, an increase of approximately 1.66 percent, and change the Technical Specifications (TS) accordingly. The proposed uprate is characterized as a measurement uncertainty recapture (MUR) using the Cameron Leading Edge Flow Meter (LEFM) CheckPlus System to improve plant calorimetric heat balance measurement accuracy.

In a telephone discussion with the NRC staff, the staff provided a request for additional information related to proposed changes to the TS Reactor Core Safety Limits shown in Figure 2.1-1. The response to the request for additional information is provided below.

Question No. 1: What are the current and proposed (post-uprate) breakpoints for the three Reactor Core Safety Limit curves?

Response No. 1:

Technical Specification Figure 2.1-1 RCS Tave ('F)

Pressure Fraction of (psig)

Rated Power Proposed Current (Post-Uprate) 0 654.75 654.75 2375 0.96 626.91 625 1.2 604.59 599 0

645.25 645.25 2235 0.96 617.41 613 1.2 595.09 589 0

627 627 1960 0.96 599.16 598 1.2 576.84 575

U.S. Nuclear Regulatory Commission Page 2 of 2 HNP-12-044 Enclosure Question No.2: Describe the methodology for developing the new values.

Response No. 2:

The Reactor Core Safety Limit (RCSL) curves are a series of isobars in power and core average temperature (Tave) that establish the operating regions for these parameters, such that both Departure from Nucleate Boiling (DNB) in the core and hot leg saturation are avoided. The lower power or flatter region of the RCSL is established by the requirement that hot leg saturation must be prevented. The steeply-sloped, higher-power region is established by the requirement that the DNB limit must not be exceeded.

The lines are confirmed by a process that tests a sample of cases that vary pressure, power and Tave. A limiting axial power shape is used for the DNB calculation. The lines are drawn so that positive margin exists for the cases analyzed. Statistical combination of uncertainties for reactor coolant system temperature, power and pressure are in accordance with AREVA NP methodology EMF-92-08 1 (P)(A), "Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors."

To create the proposed measurement uncertainty recapture (MUR) RCSLs, the process extrapolated the flatter line segment to the MUR 0.96 fractional power. Some cases failed due to DNB and the 0.96 fraction of rated power points were adjusted until a successful, positive margin was achieved.