HNP-11-076, Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate License Amendment Request: Difference between revisions
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Ladies and Gentlemen: | Ladies and Gentlemen: | ||
On July 29, 2011, the Harris Nuclear Plant (HNP) received a request from the NRC (Reference | On July 29, 2011, the Harris Nuclear Plant (HNP) received a request from the NRC (Reference | ||
: 2) for additional information needed to facilitate the review of the License Amendment Request to increase the rated thermal power (RTP) level from 2900 megawatts thermal (MWt) to 2948 MWt, and make Technical Specification changes as necessary to support operation at the uprated power level. The proposed change is an increase in RTP of approximately 1.66%. The proposed uprate is characterized as a measurement uncertainty recapture using the Cameron Leading Edge Flow Meter CheckPlus System to improve plant calorimetric heat balance measurement accuracy. This original request was submitted as Serial: HNP- 11-001 (Reference 3). | : 2) for additional information needed to facilitate the review of the License Amendment Request to increase the rated thermal power (RTP) level from 2900 megawatts thermal (MWt) to 2948 MWt, and make Technical Specification changes as necessary to support operation at the uprated power level. The proposed change is an increase in RTP of approximately 1.66%. The proposed uprate is characterized as a measurement uncertainty recapture using the Cameron Leading Edge Flow Meter CheckPlus System to improve plant calorimetric heat balance measurement accuracy. This original request was submitted as Serial: HNP-11-001 (Reference 3). | ||
The Enclosure to this submittal contains HNP's response to the NRC's request for additional information. | The Enclosure to this submittal contains HNP's response to the NRC's request for additional information. | ||
This document contains no new Regulatory Commitment. | This document contains no new Regulatory Commitment. | ||
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Harris Nuclear Plant P. 0. Box 165 New Hill, NC 27562 | Harris Nuclear Plant P. 0. Box 165 New Hill, NC 27562 | ||
Serial: HNP- 11-076 Page 2 Please refer any questions regarding this submittal to Mr. Dave Corlett, Supervisor - HNP Licensing/Regulatory Programs, at (919) 362-3137. | Serial: HNP-11-076 Page 2 Please refer any questions regarding this submittal to Mr. Dave Corlett, Supervisor - HNP Licensing/Regulatory Programs, at (919) 362-3137. | ||
I declare under penalty of perjury that the foregoing is true and correct. Executed on | I declare under penalty of perjury that the foregoing is true and correct. Executed on | ||
[ | [ | ||
Keith Holbrook Manager - Support Services Harris Nuclear Plant RKH/kab | AUG 1 52011 1 | ||
Sincerely, Keith Holbrook Manager - Support Services Harris Nuclear Plant RKH/kab | |||
==Enclosure:== | ==Enclosure:== | ||
Response to Request for Additional Information cc: | Response to Request for Additional Information cc: | ||
Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mr. W. L. Cox, III, Section Chief, N.C. DENR Mr. V. M. McCree, NRC Regional Administrator, Region II Mrs. B. L. Mozafari, NRC Project Manager, HNP | |||
Enclosure to SERIAL: HNP- 11-076 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST Summary By letter dated April 28, 2011, (ADAMS Accession No. ML11124A180), Carolina Power & | Enclosure to SERIAL: HNP-11-076 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST Summary By {{letter dated|date=April 28, 2011|text=letter dated April 28, 2011}}, (ADAMS Accession No. ML11124A180), Carolina Power & | ||
Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., submitted a proposed amendment for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP). The proposed amendment will increase the rated thermal power (RTP) level from 2900 megawatts thermal (MWt) to 2948 MWt, and make Technical Specification (TS) changes as necessary to support operation at the uprated power level. The proposed change is an increase in RTP of approximately 1.66%. The proposed uprate is characterized as a measurement uncertainty recapture (MUR) using the Cameron Leading Edge Flow Meter CheckPlus System to improve plant calorimetric heat balance measurement accuracy. The proposed change will revise Renewed OL NPF-63 Maximum Power Level; Appendix A, TS definition of RTP; Reactor Core Safety Limits; Reactor Trip System Instrumentation; Minimum Allowable Power Range Neutron Flux high setpoint with Inoperable Steam Line Safety Valves; and TS Bases Section 3/4.7.1 to reflect the uprated reactor core power level. | Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., submitted a proposed amendment for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP). The proposed amendment will increase the rated thermal power (RTP) level from 2900 megawatts thermal (MWt) to 2948 MWt, and make Technical Specification (TS) changes as necessary to support operation at the uprated power level. The proposed change is an increase in RTP of approximately 1.66%. The proposed uprate is characterized as a measurement uncertainty recapture (MUR) using the Cameron Leading Edge Flow Meter CheckPlus System to improve plant calorimetric heat balance measurement accuracy. The proposed change will revise Renewed OL NPF-63 Maximum Power Level; Appendix A, TS definition of RTP; Reactor Core Safety Limits; Reactor Trip System Instrumentation; Minimum Allowable Power Range Neutron Flux high setpoint with Inoperable Steam Line Safety Valves; and TS Bases Section 3/4.7.1 to reflect the uprated reactor core power level. | ||
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information submitted by the licensee, and based on this review determined the following information is required to complete the evaluation of the subject amendment request: | The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information submitted by the licensee, and based on this review determined the following information is required to complete the evaluation of the subject amendment request: | ||
Request 1: | Request 1: | ||
Containment and Ventilation request for additional information (RAI): | Containment and Ventilation request for additional information (RAI): | ||
Section 11.2.40, "Mass and Energy Releases - FSAR [Final Safety Analysis Report] 6.2.1," of | Section 11.2.40, "Mass and Energy Releases - FSAR [Final Safety Analysis Report] 6.2.1," of to your supplemented {{letter dated|date=June 23, 2011|text=letter dated June 23, 2011}}, that discussed EPITOME Code error. EPITOME is a code used by Westinghouse in the loss-of-coolant accident (LOCA) long-term mass and energy (M&E) calculation, which supplies input to the containment response. Westinghouse discovered that the computer code (EPITOME) used to generate the M&E inputs for the containment peak pressure analysis contains an error which could result in an increase in the containment pressure and temperature for the double ended pump suction LOCA, including a maximum increase in the peak containment pressure of up to 5 psi and temperature of up to 5.5 deg F. The licensee states: | ||
The Harris Nuclear Power Plant (HNP) power uprate LOCA long-term mass and energy evaluation was predicated on no Page 1 of 2 | The Harris Nuclear Power Plant (HNP) power uprate LOCA long-term mass and energy evaluation was predicated on no Page 1 of 2 | ||
Latest revision as of 04:27, 13 January 2025
| ML11235A516 | |
| Person / Time | |
|---|---|
| Site: | Harris |
| Issue date: | 08/15/2011 |
| From: | Holbrook K Progress Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| HNP-11-076, TAC ME6169 | |
| Download: ML11235A516 (4) | |
Text
SERIAL: HNP-11-076 SProgress Energy AUG 1 5 011 U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST
References:
- 1. Letter from B. Mozafari, Nuclear Regulatory Commission, to W. Jefferson, "Shearon Harris Nuclear Power Plant, Unit 1 - Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate (TAC No. ME6169)," dated August 5, 2011
- 2. Email from B. Mozafari, Nuclear Regulatory Commission, to J. Caves, "MUR RAI (Cont/Vent ME6169).docx," dated July 29, 2011.
- 3. Letter from C. L. Burton to the Nuclear Regulatory Commission (Serial:
HNP-1 1-001), "Shearon Harris Nuclear Power Plant, Unit 1, Docket No.
50-400/Renewed License No. NPF-63, Request for License Amendment, Measurement Uncertainty Recapture Power Uprate," dated April 28, 2011.
(ADAMS Accession ML11124A180)
Ladies and Gentlemen:
On July 29, 2011, the Harris Nuclear Plant (HNP) received a request from the NRC (Reference
- 2) for additional information needed to facilitate the review of the License Amendment Request to increase the rated thermal power (RTP) level from 2900 megawatts thermal (MWt) to 2948 MWt, and make Technical Specification changes as necessary to support operation at the uprated power level. The proposed change is an increase in RTP of approximately 1.66%. The proposed uprate is characterized as a measurement uncertainty recapture using the Cameron Leading Edge Flow Meter CheckPlus System to improve plant calorimetric heat balance measurement accuracy. This original request was submitted as Serial: HNP-11-001 (Reference 3).
The Enclosure to this submittal contains HNP's response to the NRC's request for additional information.
This document contains no new Regulatory Commitment.
In accordance with 10 CFR 50.91 (b), HNP is providing the state of North Carolina with a copy of this response.
Progress Energy Carolinas, Inc.
Harris Nuclear Plant P. 0. Box 165 New Hill, NC 27562
Serial: HNP-11-076 Page 2 Please refer any questions regarding this submittal to Mr. Dave Corlett, Supervisor - HNP Licensing/Regulatory Programs, at (919) 362-3137.
I declare under penalty of perjury that the foregoing is true and correct. Executed on
[
AUG 1 52011 1
Sincerely, Keith Holbrook Manager - Support Services Harris Nuclear Plant RKH/kab
Enclosure:
Response to Request for Additional Information cc:
Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mr. W. L. Cox, III, Section Chief, N.C. DENR Mr. V. M. McCree, NRC Regional Administrator, Region II Mrs. B. L. Mozafari, NRC Project Manager, HNP
Enclosure to SERIAL: HNP-11-076 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST Summary By letter dated April 28, 2011, (ADAMS Accession No. ML11124A180), Carolina Power &
Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., submitted a proposed amendment for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP). The proposed amendment will increase the rated thermal power (RTP) level from 2900 megawatts thermal (MWt) to 2948 MWt, and make Technical Specification (TS) changes as necessary to support operation at the uprated power level. The proposed change is an increase in RTP of approximately 1.66%. The proposed uprate is characterized as a measurement uncertainty recapture (MUR) using the Cameron Leading Edge Flow Meter CheckPlus System to improve plant calorimetric heat balance measurement accuracy. The proposed change will revise Renewed OL NPF-63 Maximum Power Level; Appendix A, TS definition of RTP; Reactor Core Safety Limits; Reactor Trip System Instrumentation; Minimum Allowable Power Range Neutron Flux high setpoint with Inoperable Steam Line Safety Valves; and TS Bases Section 3/4.7.1 to reflect the uprated reactor core power level.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information submitted by the licensee, and based on this review determined the following information is required to complete the evaluation of the subject amendment request:
Request 1:
Containment and Ventilation request for additional information (RAI):
Section 11.2.40, "Mass and Energy Releases - FSAR [Final Safety Analysis Report] 6.2.1," of to your supplemented letter dated June 23, 2011, that discussed EPITOME Code error. EPITOME is a code used by Westinghouse in the loss-of-coolant accident (LOCA) long-term mass and energy (M&E) calculation, which supplies input to the containment response. Westinghouse discovered that the computer code (EPITOME) used to generate the M&E inputs for the containment peak pressure analysis contains an error which could result in an increase in the containment pressure and temperature for the double ended pump suction LOCA, including a maximum increase in the peak containment pressure of up to 5 psi and temperature of up to 5.5 deg F. The licensee states:
The Harris Nuclear Power Plant (HNP) power uprate LOCA long-term mass and energy evaluation was predicated on no Page 1 of 2
Enclosure to SERIAL: HNP-1 1-076 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST changes to the existing mass and energy release analysis of record due to the power uprate.
Since the licensee used the EPITOME code in its existing M&E release analysis for HNP, provide information on how this code error affects HNP's containment response analysis for a LOCA, specifically regarding the calculated peak pressure and peak temperature.
Response
LOCA M&E Releases were recalculated to resolve the EPITOME code error and additional previously-identified discrepancies. The reanalysis was based upon the Harris analysis of record that considers inputs that bound both uprate and current operating conditions. After resolving the errors in the LOCA M&E calculation and incorporating the results into the containment response analysis, the Harris plant remains double ended hot leg (DEHL) break limited with no change in the peak DEHL break pressure at 56.50 psia and peak containment atmosphere temperature at 270.2'F. The double ended pump suction (DEPS) break blowdown peak pressure remains the same at 54.80 psia, but the post-blowdown peak pressure increases by 2.74 psia to a new value of 55.74 psia. As a result, the DEPS break case is now limited by the post blowdown pressure. Although the DEPS analysis changed, the DEHL analysis remains bounding and unchanged. Therefore, there is no impact on the subject LAR due to the referenced error in the EPITOME code.
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