ML11213A179

Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate

ML11213A179
Person / Time
Site:	Harris
Issue date:	08/05/2011
From:	Mozafari B Plant Licensing Branch II
To:	Jefferson W Carolina Power & Light Co
Mozafari B
References
TAC ME6169
Download: ML11213A179 (6)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 5, 2011 Mr. William Jefferson, Jr.

Vice President Carolina Power & Light Company Shearon Harris Nuclear Plant P.O. Box 165, Mail Zone 1 New Hill, NC 27562-0165

SUBJECT:

SHEARON HARRIS NUCLEAR PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE (TAC NO. ME6169)

Dear Mr. Jefferson:

By letter dated April 28, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11124A180), as supplemented by letter dated June 23,2011 (ADAMS Accession No. ML11179A052), Carolina Power & Light Company requested approval from the U.S. Nuclear Regulatory Commission (NRC) to increase the core thermal power level of Shearon Harris Nuclear Power Plant, Unit 1 from 2,900 megawatts thermal (MWt) to 2,948 MWt, an increase of approximately 1.66% over the present licensed power level and to change the power plant technical specifications accordingly.

The NRC staff is reviewing your submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). It is requested that your RAI response be provided by August 29, 2011, as discussed with your staff on June 29, 2011. If more time is needed to respond to the RAI, your request for additional time should include a basis for the need for an extension.

w. Jefferson -2 Please feel free to contact me at 301-415-2020 or bye-mail at Brenda.mozafari@nrc.gov if you have any questions on this issue or require additional time to submit your response.

Sincerely, Brenda Mozafari, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-400

Enclosure:

Request for Additional Information cc w/encl: Distribution via Listserv

SHEARON HARRIS NUCLEAR POWER PLANT. UNIT NO.1 REQUEST FOR ADDITIONAL INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE TAC NO. ME6169 By letter dated April 28, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. IVIL11124A180), as supplemented by letter dated June 23, 2011 (ADAMS Accession No. ML11179A052), Carolina Power & Ught Company (the licensee) requested approval from the U.S. Nuclear Regulatory Commission (NRC) to increase the core thermal power level of Shearon Harris Nuclear Power Plant, Unit 1 from 2,900 megawatts thermal (MWt) to 2,948 MWt, an increase of approximately 1.66% over the present licensed power level and to change the power plant technical specifications accordingly. The NRC staff has reviewed the supplemental information, specifically Section V, "Electrical Equipment Design," of Enclosure 2 to the licensee's letter dated June 23, 2011. Based on its review, the NRC staff requests the following additional information:

1. In Enclosure 2,Section V.1.B, "Station Blackout - Class 1 E Battery Capacity," the licensee stated that Shearon Harris Nuclear Power Plant(HNP), Unit 1 has two Class 1 E battery systems with sufficient capacity, including 10% margin. to power station blackout (SBO) loads for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Provide a summary of the Class 1 E battery sizing calculations that demonstrates sufficient capacity exists for the 4-hour SBO coping duration under MUR power uprate conditions. Discuss and provide details of any load-shedding, if considered, in the 4-hour coping duration.

2. In Enclosure 2,Section V.1.C, "Environmental Qualification [EQ] of Electrical Equipment," the licensee stated that they conducted an evaluation and concluded that the power uprate will not impact the equipment qualification.

Provide temperature, pressure, and radiation levels (curves or tables) to demonstrate that the EQ of all equipment remains bounding for both normal operating and under accident conditions for the proposed MUR power uprate.

3. In Enclosure 2,Section V.1.D, "Grid Stability - Power-flow Analysis," the licensee stated that based on summer 2010 study results extrapolated for future years, no thermal or voltage impacts were identified.

Provide a summary of the power flow analysis. Confirm whether the power flow analysis also included winter loading in addition to the summer loading. If not. explain why winter loading was not considered.

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4. In Enclosure 2,Section V.1.D, "Grid Stability - Large Generator Interconnection Power Factor Requirements," the licensee stated that for a 66 Mega Watt electric (MWe) increase on HNP Unit 1, a generator nameplate rating of 1155 Mega Volt Ampere (MVA) at 0.94 Power factor lagging was required.

Provide a summary of the calculation that confirms that the capability of the replacement main generator will bound the MVAs Reactive (MVAR) requirement corresponding to the 66 MWe increase.

5. In Enclosure 2,Section V.1.D, "Grid Stability - Stability Analysis," the licensee stated that Nuclear Plant Interface Requirements (that include a minimum required switchyard voltage and plant post-trip auxiliary loading), remain unchanged as a result of the MWe increase, and that no changes are necessary to existing transmission system operating procedures in order to provide adequate voltage support to HNP.

Provide a summary of the analysis that was performed to validate the above statement.

6. In Enclosure 2,Section V.1.D, "Grid Stability - Short Circuit Analysis," the licensee stated that the evaluation results indicate that the interrupting capability of the transmission equipment in the surrounding area would not be adversely impacted by the proposed generation uprate.

Provide a summary of the analysis that was performed to validate the above statement.

7. In Enclosure 2,Section V.1.E, "Onsite Power Systems - AC [Alternating Current]

Distribution System," the licensee stated that the electrical changes resulting from the power uprate occur in the balance of plant equipment, primarily at the 6.9 kiloVolt (kV) level. The licensee noted that the following loads were affected: main feedwater pumps, condensate pumps, condensate booster pumps, heater drain pumps, and reactor coolant pumps. The licensee stated that the net increase in brake horsepower (bhp) for the motors associated with these pumps is small, in the range of 100-200 horsepower (hp).

Provide the rated hp for the motors associated with the above pumps, and the bhp requirements for pre- and post-MUR power uprate conditions. Also provide a summary of the worst case steady-state voltages at the 6.9 kV buses for pre- and post-MUR power uprate conditions, in a table form, to validate that the voltages remain above the degraded voltage relay settings at the 6.9 kV emergency buses under MUR power uprate conditions.

8. In Enclosure 2,Section V.1.F.i, "Main Generator," the licensee stated that the 29.8 MWe includes approximately 19 MWe associated with the MUR assumed by the uprate and the balance from the other upgrades. Also, the main generator capability curve indicates that at 1021.8 MWe, the main generator is capable of exporting approximately 430 MVAR.

Clarify "other upgrades" in the above statement. Provide a copy of the main generator capability curve to validate that the generator will be operating within the limits of its capability curve.

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9. In Enclosure 2,Section V.1.F.ii, "Isolated Phase Bus," the licensee stated that the normal conditions are defined as full real power (1021.8 MWe) with reactive power at the maximum HNP administrative limit (currently 175 MVAR lagging) and 100% nominal voltage (22 kV).

Explain the basis of the 175 MVAR lagging limit corresponding to 1021.8 MWe. Also, discuss the MVAR lagging requirement corresponding to the 66 MWe increase for which grid stability has been carried out and its impact on the isolated phase bus rating.

10. Provide a discussion on any protective relaying changes due to installation of the replacement main generator and main transformers.

11. Provide a discussion on the auxiliary power requirement for the Cameron Leading Edge Flow Meter CheckPlus System, such as direct current or AC power requirements, and its loading impact on the associated safety-related or nonsafety-related bus.

w. Jefferson - 2 Please feel free to contact me at 301-415-2020 or bye-mail at Brenda.mozafari@nrc.gov if you have any questions on this issue or require additional time to submit your response.

Sincerely, IRA by FSaba fori Brenda Mozafari, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-400

Enclosure:

Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLIC LPL2-2 R/F RidsNrrDorlLpl2-2 RidsNrrDeEeeb RidsNrrLACSola RidsNrrPMShearonHarris RidsOgcRp RidsNrrDorlDpr RidsRgn2MailCenter RidsAcrsAcnwMailCenter ADAMS Accession No. ML11213A179 *BiY memo OFFICE LPL2-21PM LPL2-2/LA EEEB/DE/BC LPL2-2BC LPL2-2/PM NAME BMozafari CSoia DBroaddus BMozafari RMathew DATE 08/02111 (BClayton for) 08/02111 07/27/11

. (SLingam for) 08/05/11 (FSaba for) 08/05/11 OFFICIAL AGENCY RECORD