HNP-11-079, Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate License Amendment
| ML11255A132 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/31/2011 |
| From: | Holbrook K Progress Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| HNP-11-079 | |
| Download: ML11255A132 (24) | |
Text
SERIAL: HNP-1 1-079 Progress Energy 10 CFR 50.90 AUG 3 1 2011 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 Jr.,
"Shearon Harris Nuclear Power Plant, Unit 1 - Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate (TAC No. ME6169)," dated August 5, 2011. (ADAMS Accession ML11213A179)
- 2. Email from B. Mozafari, Nuclear Regulatory Commission, to J. Caves, "MUR RAI (EEB) (ME6169)", dated August 4, 2011
- 3. Letter from W. Jefferson to the Nuclear Regulatory Commission (Serial:
HNP-1 1-065), "Shearon Harris Nuclear Power Plant, Unit 1, Docket No.
50-400/Renewed License No. NPF-63, Supplement to Measurement Uncertainty Recapture Power Uprate License Amendment Request," dated June 23, 2011. (ADAMS Accession ML11179A052)
- 4. 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 August 4, 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 percent. 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 4).
Progress Energy Carolinas, Inc.
Harris Nuclear Plant P. 0. Box 165 New Hill, NC 27562
Serial: HNP-1 1-079 Page 2 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.
Please refer any questions regarding this submittal to Mr. David 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
[ 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-1 1-079 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I 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. (PEC),
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 percent. 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. The proposed change will revise Renewed Operating License 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.
By letter dated June 23, 2011, (ADAMS Access No. ML11179A052), CP&L submitted a supplement to the proposed amendment for HNP. The information in the supplement provided updates to Enclosure 2,Section V, "Electrical Equipment Design," of the proposed license 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:
In Enclosure 2,Section V. 1.B, "Station Blackout - Class 1E Battery Capacity," the licensee stated that Shearon Harris Nuclear Power Plant, Unit 1 (HNP) has two Class 1E 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 1E 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.
Page 1 of 22
Enclosure to SERIAL: HNP-1 1-079 SHEARON HARRIS NUCLEAR. POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/R NEWE-D LICENSE NO. NPF-63 RESPONSE. TO REQUEST FOR,ADDITIONAL INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST
Response
HNP calculation E4-0008, 125 VDC E Ba`ttery Sizing and Battery/Panel Voltagesfor Station Blackout, is the basis for verification of the 10 percent margin for SBO. It is based on the equipment loading during a SBO:. The only*possible impact of the MUR power uprate on this calculation would be due to increased decay heat removal. Decay Heat Removal is performed via the Turbine Driven Auxiliar)yFeedwater (AFW) Pump, and by Steam Generator (SG) Power Operated Relief Valves (PORVs). Calculation E4-0008' established the design loading for the equipment used during SBO and then used a computer program to vary the voltage and loads connected for the four hours. As the equipment being used is un-changed, and the calculation uses design electrical load numbers, there is no impact on this calculation by the MUR power uprate, and the calculation remains bounding.
The load shedding used in the SBO coping analysis is unchanged from the analysis prior to the MUR power uprate. As stated in HNP calculation 8S44-P-101, Station Blackout Coping Analysis Report, "Load shed assumptions and requirements in calculations E4-0009 and E4-0010 have been incorporated into EOP-EPP-001 ." E4-0009 is the HNP calculation for 125VDC Non-lE Battery Load Data and Duty Cycle, E4-0010 is the HNP calculation for 125 VDC Non-JE Battery Sizing & Battery/Panel Voltages, and EOP-EPP-001 is the HNP Emergency Operating Procedure for Loss ofAC Power to 1A-SA and 1B-SB Buses.
From HNP calculation E4-0006, Safety Batteries 1A-SA & 1B-SB Load Profile Determination (LOCA/SBO), "During an SBO event, Reference 2.13 directs that both ESS panels' feeder breakers (circuit no. 8 on 125V DC panels DP- 1A-SA and DP- 1B-SB) be manually opened.
This analysis conservatively assumes that they are opened at 60 minutes after the initiation of the SBO event." Reference 2.13 in the above statement refers to EOP-EPP-001.
Step 11 .b in EOP-EPP-0001 states, "Locally de-energize control power to the emergency safeguards sequencers:
" DP-1A-SA CKT #8
" DP-1B-SB CKT #8 The remaining load shedding requirements are listed in Attachment 3 of EOP-EPP-00 1, DC Load Shed List, as follows:
- 1. 125 VDC Non-Safety Loads, RAB 286 South Switchgear Room
- 125 VDC Panel IA (DP-1A)
Page 2 of 22
Enclosure to SERIAL: HNP-l 1-079 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO., 1 DOCKET NO. 50-400/RENETWM LEICENSE No. NPF-63 RESPONSE TO REQUEST FOR ADDITIONALi NFORMATION REGARDTNG MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST
- 125 VDC Panel 1A-I (DP-1A-1)
- 2. 125 VDC Safety Loads, RAB 286 South Switchgear.Room
- 125 VDC Panel lB-SB (DP-1B-SB).,.
- UPP-1A
" UPP-1B VITAL
- UPP-1:BAY7
" UPP-1: BAY 8
- 6. 125 VDC Non-safety Power, TB 286
- DP-1A1ll Page-3of 22
Enclosure to SERIAL: HNP-l 1-079 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 Request 2:
In Enclosure. 2,Section V.1 .C, ."EQ (environmental qualification) 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, pres sure,, 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.
Response
The EQ evaluations performed for the HNP MUR power uprate have demonstrated that the current analyses of record (AORs) remain bounding for EQ, and as a result the EQ Program is not affected by the HNP MUR power uprate. The EPITOME software's mass and energy (M&E) release errors result in new temperature/pressure profiles that have been shown to remain within the existing margins of EQ equipment tests.
The purpose of the EQ evaluation is to determine if the electrical equipment identified in the EQ Program for environmental qualification will continue to operate satisfactorily and continue to perform the intended functions at the uprated conditions to satisfy the requirements outlined in 10 CFR.50.49 "Environmental Qualification of Electric Equipment Important to;Safety for Nuclear Power Plants." . .
The following conditions were evaluated:
- Loss of coolant accident (LOCA) and main steam line break (MSLB) pressure/temperature inside containment
- MSLB/main feedwater line break (MFWLB) pressure/temperature outside
.containment
- ,Other high energy line breaks (HELBs) pressure/temperature outside containment
- Radiation - accident and normal The effect of the MUR power uprate on each of the bulleted topics is discussed below, and for each topic it was concluded that the current AORs remain bounding.
Page 4 of 22
Enclosure to SERIAL: HNP-1 1-079 SHEARON HARRIS NUCLEARPOWER PLANT, UNIT NO. '
DOCKET NO. 50-400/RENEWtEDLICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INTFORMATION-;REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST LOCA and MSLB Pressure/Temperature Inside Containment A review of the HNP Final Safety Analysis Report (FSAR)'Sectio6n 3.6A.2, High Energy Pipe Break Outside Containment,indicates that the pressure/temperature profile calculations' for-both
a LOCA and a MSLB in containment were performed using a power level,: of 1-02 percent of:
rated power. HNP FSAR Section 3.1 IC, Supplemental Environmental Qualificationof Inside ContainmentSafety Related ElectricalEquipment, also indicates that the M&E'release '-.
calculations were performed assuming a 102 percent power level.,- ' .
Calculation HNP-M/MECH-1008, Revised ContainmentAnalysis for an Increase in the Initial Temperaturefrom 120 'F to 135 'F, indicates that the MSLB calculation uses 102 percent of rated power. For LOCA, the double-ended pump suction (DEPS) and double-ended hot'leg (DEHL) analyses within HNP-M/MECH- 1008 use M&E release output from Westinghouse.
Westinghouse indicates that their methodology for M&E release is to use 102 percent of rated-power.
MSLB/MFWLB Pressure/Temperature Outside Containment The MSLB and MFWLB analyses were performed using a power level of 102 percent."of the --
rated power level. HNP FSAR Section 3.11 E, Supplemental Environmental Qualificationof Safety Related ElectricalEquipment Inside the Main Steam Tunnel, indicates that the M&E.
release calculations were performed assuming a 102 percent power level.
The HNP AOR for*the, inside and outside containment long-term steam line breaks assumes a,2 percent calorimetric uncertainty added to the reactor power of 2,900 MWt, with an addition of 12.4 MWt reactor coolant pump heat. Therefore, as long as the sum of the power increase and power calorimetric uncertainty does not exceed 2 percent, there i's no effect on either the'current:
licensing basis long-term steam line break M&E release analysis or the'FSAR conclusions.
Other HELBs Pressure/Temperature Outside Containment The HNP FSAR, Section 3.6A.2.3, EnvironmentalEffect of High Energy Line Breaks..Outside Containment,identifies that the following, high energy pipe systems were considered for pipe rupture analysis outside of containment:
" Chemical and volume control system
- Steam generator blowdown system
" Main steam and feedwater .
" Auxiliary feedwater Page 5 of 22
'.I I% ..1 Enclosure to SERIAL: HNP-11-079 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/R;NEWED LICENSE NO. NPF-63 RESPONSE TO REQUESTFOR ADDITIONAL INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST
- Extraction steam and auxiliary steam lines
. Safety injection systemv. :
All FSAR conclusions related to the long-term and short-term M&E releases remain valid for the HNP MUR power uprate.
Radiation Environments ,to Support Equipment Qualification, Accident and Normal Conditions NUREG-0800, Standard Review Plan (SRP), Section 3.11, Environmental Qualificationof Mechanical and ElectricalEquipment, states that the radiation environment for component qualification shall be based on the integrated effects of the normally-expected radiation environment over the equipment's installed life, plus that associated with the most severe design basis event during or following which the equipment is required to be functional. Thus, for the HNP MUR power uprate, the normal operation and accident environments for safety-related components. are required tobe estimated based on a core power level of approximately 2,948 MWt and 2,958 MWt, respectively...
Because the current licensed core power level of 2,900 MWt adjusted for calorimetric error of +2 percent of power (that is, 2,958 MWt) was assumed in the AORs supporting the above assessments, and the sum of the HNP MUR power uprate power increase (1.66 percent) and the power calorimetric uncertainty (0.34 percent) does not exceed 2 percent, it is concluded that the HNP MUR power uprate operation will have no effect on the accident dose estimates inside and outside containment and will continue to be conservative for the normal operation dose estimates in the Reactor Auxiliary Building.
The normal operation dose inside containment is primarily dependent on the N-16 concentration in the Reactor Coolant System. The normal operation doses inside containment developed in support of the HNP Steam Generator Replacement power uprate reflect the increase in specific activity of N-16 and are based on a core power level of 2,900 MWt. Subsequent to the HNP MUR power uprate, the normal operation dose rate inside containment areas influenced by N-16 will increase by 1.66 percent.
A review of the source documents supporting the current normal operation doses inside containment indicates that the values reported in HNP EQ design basis document represent 60 years of operation at 2,900 MWt (that is, no credit is given to the fact that HNP operated for 14 years at a core power level of 2,775 MWt).
Page.6 of 22
Enclosure to SERIAL: HNP- 11-079 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO.' ]
DOCKET NO. 50-400/RENEWED:LICENSE NO. NPF*63 RESPONSE TO REQUESTFOR ADDITIONAL INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST' Subsequent to the HNP MUR power uprate, the actual power history of FINP-would be: 14 years at a core power level of 2,775 MWt; 10 years at a core power-level of 2,900 MWt; and 36 years at a core power level of 2,948 MWt. For the above operation history, the effective power level averaged over the 60 year period is approximately 2,900. MWt..
Therefore, it is concluded that due to available margin resulting from current methodology, the current normal operation dose estimates for inside-containment locations -remainapplicable&for the HNP MUR power uprate. I' EPITOME Errors - HNP EQ Program Impact Westinghouse found that the M&E release software code EPITOME contains an error which.
could result in an increase in the containment pressure and; temperature for the' DEPS LOCA.
This deficiency has been. identified in the HNP Corrective Action Program. EQ evaluations have been performed to show that the EQ Program's existing test limits provide sufficient margin to address the increases that result from correcting M&E releases for the DEPS LOCA. These .
evaluations concluded that the HNP EQ Program equipment located within containment can be shown to remain fully qualified for a corrected temperature/pressure profile that incorporates corrections to M&E errors in the EPITOME software.
Page 7 of 22
Enclosure to SERIAL: 14NP-1 1-079 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 Request 3:
In Enclosure 2,;:Section V..I .D, "Grid Stability - Power Flow Analysis," the licensee stated that based on summer 20.10 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 c.onsidered:
Response
The power flow analysis examined the impact on the transmission grid of operating the HNP generating unit at the increased power level under both normal and contingency operating conditions. Contingencies included the loss of various transmission lines, as well as the loss of the:HNP unit itself' This. analysis is performed by PEC Transmission Planning using Siemens Power:System Simulator for Engineering (PSSE) software. PSSE is used by the majority of the utilities in the Eastern Interconnection for these types of studies. Since the power increases were to be implemented in several steps beginning in 2010, Transmission Planning examined the impact from that point forward., "Summer 2010" means that a power flow case was used which reflected transmission system loading conditions during the summer peak period. "Extrapolated for future years" means that the .same 'summer peak conditions for future years were examined, based Ion load forecast projections for those years. Since HNP is, within a summer peaking utility, forecasted transmissionsystem loads for a given year are higher in the-stummer than during the winter. Therefore, analysis results using summer loading conditions Would bound results for expected ,winter.loading conditions. The study results indicated that no transmission line overloads (thermal issues) or unacceptable voltages would be expected as a result of the proposed power: increase.
Page 8- of 22
Enclosure to SERIAL: HNP-1 1-079 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 Request 4:
In Enclosure 2,Section V. 1.D, "Grid Stability - Large 'Generator Interconnect Power Factor Requirement," the licensee stated that for a 66 Mega Watt electric (MWe) increase, on'HNPP Unit 1, a generator nameplate rating of 1155 Mega Volt Ampere 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 requirement corresponding to the 66 MWe6 increase. -
Response
PEC Transmission Planning determines the MVAR requirement for generation additions, including MW increases of existing generators. The requirement is that the generation must be capable of delivering theý additional MW output to the point of interconnection (POI) at a 0.95 lagging power factor. For an existing generating unit which is being uprated, this requirement:.
applies only to the MW increase. The existing MW output of the unit is grandfathered at the .
unit's present MVAR capability or a MVAR capability equivalent to 0.95 lagging power, factor..
at the POI, whichever is less. This information is used to determine what the required generator.
MVA/Power Factor nameplate must be to meet the MVAR capability requirement. Figure- 1 . ;
below illustrates how this was done for the, HNP MUR power uprate 66 MW increase.' The- ' -
GrandfatheredCapabilityis shown as a power triangle ,for the original generator, rated at, 1045, MVA. Using the 1045 MVA'and the maximum gross MW output prior to uprate (1005 MW) yields a grandfathered MVAR .capability of 286.4 MVAR. 'By agreement between HNP and Transmission Planning, an IncrementalIncrease of 80 MW was assumed to' allow some margin over the proposed 66 MW increase.. This! 80 MW was used only for purposes of calculating the MVAR requirement and generator nameplate requirement. Using the .80 MW increase, an .
additional 51.9 MVAR would be required at the generator terminals. This value takesinto..
account the additional losses in the main (step up) transformer, referred to as GSU in Figure 1, due to the increase. The Resultant Capabilitytriangle is the geometric sum of the Grandfathered Capability and IncrementalIncrease triangles. From the Resultant Capabilitytriangle, a generator nameplate of 1136.5 MVA at 0.9547 power factor is required. Based on this, the actual installed generator nameplate was chosen to be 1155 MVA at 0.94 power factor. As can be seen in the figure, this does not mean that the entire MW output of the unit conforms to the 0.95 lagging power factor at the POI requirement.
Page 9 of 22
Enclosure to SERIAL: HNP-11-079 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO- 50-400/il'RNEWED LICENSE NO. NPF-63 RESPONSE. TO REQUEST FOR ADDITIONAL INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE
. LICENSE AMENDMENT REQUEST
- UPRA TE ANALYSIS FOR: HarrisUnit #1 ID: 06-02-11.1 MW Flow Post-Uprate Conditionsand Capabilities
" ! MVMAR Flow UAT 80.D Prate 51.9 x=:> 138.8 Losses G
EXiSting Pot
~3U
.1 1005.0 1025.0 =
288.4 E 308.2 1Z:= =>189.8 =
0,9888 PF REQUIRED NAMEPLATE: 1130.5 MVA@ 0.9547 PF For Proposed Uprate of: 80.0 MW GrandfatheredCapability at GeneratorTerminals Incremental Increase at Generator Terminals 95.3
' MVA 288.4 51.9 MVAR MVAR 1005.0 MW 80.0 MW Resultant Capability Requiredat GeneratorTerminaf5 GSU Loading as % of GSU Rating Cont-ngeny Loadino 400.2c 1138.5 (At 0.95 PF Requirement)
M VA 338.2 WVAR Nomal Loading .7 29,1.
(FuUTLoad assuming 0.98 PF) 1085.0 0.9547 PF MW Figure 1. MVAR Capability and Generator Nameplate Requirement Example Page 10 of 22
Enclosure to SERIAL: HNP-1 1-079 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO.1 DOCKET NO. 50-400/RENEWE]D LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST Request 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.
Response
"Minimum required switchyard voltage" is the voltage necessary in the HNP 230 kV switchyard to ensure proper operation of emergency loads following a trip of the HNP generator (for either LOCA or non-LOCA caused trips). Both the minimum required switchyard voltage and the plant post-trip auxiliary loading are provided by HNP Engineering to PEC Transmission Planning as required by NERC Reliability Standard NUC-001-2. Transmission Planning uses this as input in determining how the transmission grid must be operated to ensure adequate switchyard voltage is available from offsite power. Since neither of these values were changed, no transmission system operating procedure changes were necessary to accommodate the proposed power increases.
Page 11 of 22
Enclosure to SERIAL: HNP-1 1-079 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 Request 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 areawould not be adversely impacted by the proposed generation uprate.
Provide a s minmary of the analysis thaf W~as performed to validate the above statement.
Response
The~short circuit:analysis was performed by PEC Transmission Protection and Control Engineering using Aspen OneLiner:software. The analysis considered the change in short circuit current contribution due to the new 1i 55 MVA HNP generator, as well as-the future impact of a new transmission line to be terminated in the HNP 230 kV switchyard (currently scheduled for June 2014). The analysis showed that the maximum available switchyard fault current would be less than 45,000 amps. The short circuit interrupting capability of the existing HNP switchyard breakers are 63,000 amps, except for one 50,000 amp breaker. The 50,000 amp breaker is also acceptable, but is currently scheduled to be replaced for other reasons with a 63,000 amp breaker in the fall of 2011.
Page 12 of 22
Enclosure to SERIAL: HNP-1 1-079 SHEARON HARRIS NUCLEAR POWER PLANT, UNITYNO.'
DOCKET NO. 50-400/RENEWEIO LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION:REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST Request 7:
In Enclosure 2,Section V. LE, "Onsite-Power System's - Aitetnating Current (AC) 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 break horse power (hp) for the motors associated with these pumps is small, in the range of 100-200 hp.
Provide the rated horsepower (hp) for the motors associated with the above pumps, and the'break hp 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.'.
Response
See the table below.
Page 13 of 22
Enclosure to SERIAL: HNP- 11-079 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 Description Rated I BHP 6.9kV Bus 6.9kV Bus Steady State HP Voltages (Note 1)
Pre MUR Post MUR Pre MUR Post MUR Main Feed Water Pump-lA 9000 8582 8736 A .i: 6393 6391 Main Feed Water Pump-lB 9000 -8582 8736 1B " 6316 .63:14 Condensate Pump-lA 2000 -1830 1841 1A .. .6393 6391 Condensate Pump-lB 2000 1830 1841 B 6316 .6314 Condensate Booster Pump-lA 3000 2905 2886 JA 6393 6391 Condensate Booster Pump-lB 3000 2905 2886 B .-6316 6314 Heater Drain Pump-ID 1500 1260 1280 ID 6664 6663---.
Heater Drain Pump-lE 1500 *1260 1280 lE
- 6672 -667*1::.
Reactor Coolant Pump-lA 7000 7000 7000 1A- 6393 - 6391 Reactor Coolant Pump-lB 7000 7000 7000 lB 6316 6314 Reactor Coolant Pump-1C (Bus IC - 7000 7000 7000 1C. -6392 / 6316 63.90 /6313 normally fed from bus 1A. Alternatively fed (Fed from Bus 1A/IB) from bus lB.
Emergency 6.9kV Bus lA-SA N/A N/A N/A 1A-SA 6663 6662 Emergency 6.9kV Bus lB-SB N/A N/A N/A lB-SB 6671 6670 Notes:
- 1. Special Case:
- Minimum switchyard voltage Limit - 222 kV. Scheduled switchyard voltage is 232.5 kV.
- Minimum generator voltage 20.9 kV(95% of 22 kV). Scheduled generator voltage is 21.78 kV.
- Normal loading on 6.9kV buses and Plant Operating Load Factor for 6.9kV buses 1D and 1E.
Degraded Voltage Relay nominal setpoint @6.9kV emergency buses 1A-SA & 1B-1SB is 6420 kV.
Page 14 of 22
Enclosure to SERIAL: HNP-1 1-079 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 Request 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 indicates that at 1021.8 MWe, the main generator is capable of exporting approximately 43,0 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 cur"ve.
Response
The basis for predicting gross generation at uprated conditions was a heat balance calculation that included contributions from the MUR power uprate (the subject of this license amendment request), cooling tower fill replacement, and high pressure turbine modifications. "Other upgrades" in the above statement refer to the cooling tower fill replacement..and high ptessure turbine modifications.
The Generator Capability Curve is a proprietary document that demonstrates the main generator is capable of exporting approximately 430 MVAR at 1021.8 MWe. The generator capability curve is available for audit at HNP. "
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Enclosure to SERIAL: HNP-1 1-079 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO: 50-400/RENEiWED LICENSE NO. NPF-63 RESPONSE TO REQUESTFOR ADDITIONAL INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST Request, 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 17"5 MVAR lagging) and 100% nominal voltage (22 kV).
Explain thebasisof 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.
Response
The 175 MVAR gross output is an administrative limit established by PEC Transmission Planning for operation of HNP under normal conditions. By limiting the HNP generator MVAR output during normal operation, the amount of local area voltage support the unit itself provides is also limited, which limits the grid impact of a trip of the HNP generator. The 175 MVAR value was chosen such that the HNP generator essentially supplies the MVARs for main (step up) transformers and unit auxiliary transformer (UAT) losses. This makes the HNP generator essentially "voltage support neutral" in that, upon a unit trip, the MVAR output and the MVAR losses will both go away. The proposed uprate of 66 MW is small enough that it is not necessary to revise the 175 MVAR limit. It should be noted that, on rare occasions, the Transmission System Operator could request HNP to exceed the 175 MVAR, if deemed appropriate for system conditions. Therefore, the 175 MVAR limit should not be used as a "hard limit" for determining potential equipment loading.
The basis of the "MVAR lagging requirement" is to ensure that the generator has sufficient capability to respond to transient conditions (e.g. faults on the transmission system) or more extreme contingencies (e.g. the loss of multiple transmission lines or localized voltage problems). Under these conditions an increased MVAR output for transient periods of several seconds to possibly several hours may be necessary. This level of support is never used as a part of routine operations and would be extremely rare. The MVAR lagging requirement (which is established as described in the response to Question #4) is somewhat independent of the 175 MVAR administrative limit.
The existing isophase bus will require increased cooling to accommodate the increase in MWe.
The plant will implement a modification to the isophase bus duct cooling during the planned spring 2012 refueling. The modification will result in sufficient cooling margin to increase the Page 16, of 22
Enclosure to SERIAL: HNP-1 1-079 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFOR.MATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST' bus rating to accommodate the increased MWe production. As part of this modificatiofrpackag6 an engineering study to determine whether or not modifications to the bus insulators will be necessary to address the increase fault current will be'perforihned. In the evenit a modification to the insulators is necessary, this will also be accomplished during the spring 2012 refueling. The*
modification design has not yet been completed; however the resultant modificatidn will be such that the isophase bus rating will be increased to make the isophase bus capability consistent with the generator output rating at the new uprate condition.,
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Enclosure to SERIAL: HNP-1 1-079 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RT.E.EWED LICENSE NO. NPF-63 RESPONSE.TO REQUEST FOR ADDITIONAL INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE- AMENDMENT REQUEST Request 10:
Provide a-discussion on any protectiverelaying changes due to installation of the replacement main generator and main transformers..,
Response
The Main Generator replacement project, completed in November 2010, included replacement of the generator protective relaying,. The discrete electromechanical relays were replaced by multifunction digital relays. for. generator protection. These multifunction relays provide the following generatorprotective functions: Phase Distance (21), Overexcitation (Volts/Hz) (24),
Reverse Power (32), Loss of Field (40), Negative Sequence (46), Inadvertent Energization (50/27), Neutral Overvoltage (59N), Loss of Potential (60), Ground (64/37G), Underfrequency (81) and Differential (87G). In addition, a new Generator and Main Transformer Differential digital relay was installed.
It isanticipated that the Main Transformer protective relay functions, which"are currently proviIded by discrete eleciromechanical relays, will be provided by one multifunctional digital relay as part of the transformer 'replacement project.
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11 Enclosure to SERIAL: HNP- 11-079 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEW-ED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONALriNFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPPATE LICENSE AMENDMENT REQUEST Request 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 non-safety-related bus.
Response
The LEFM CheckPlus System consists of an electronic cabinet installed in thýe8 Secoridary Sampling Equipment Enclosure located in the Turbine Building, and measuremient spool pieces installed in each of the three main feedwater lines. Two t120 VAC, siigle phase, 60 Hz power' sources are supplied to the LEFM CheckPlus system.
LEFM Electrical Load Description The LEFM Check Plus system is not required to function during a postulated: accident or event'.
Therefore, the system, uses non-safety power sources, and emergency diesel generator loading"is unaffected. There are two independent measurement systems (A and B) in one cabinet. Each measurement system has its own independent power supply. Each power supply is fed by a separate circuit from a separate power source to maintain independence.
LEFM Electronic Cabinet Power Power Panel PP-1D341 and Power Panel PP-1E341 provide the LEFM Check Plus system electronic cabinet's two power sources. Both are existing panels with excess capacity and spare breakers and are supplied from different plant electrical busses. These power sources are not safety-related. Therefore, the LEFM Check Plus system does not impact any safety-related power supplies or emergency diesel generator loading.
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Enclosure to SERIAL: HNP-1 1-079 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 504-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO .REQUEST FOR ADDITIONAL INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENTREQUEST Load Changes to PP-1D341 Panel PP-1D341 had a spare three pole 20 A breaker that was originally designed for a 3200 VA load. This breaker was removed and replaced with three 'single pole 20 A breakers. One is used for the 600 VA LEFM load and the other two are spares. The overall impact to the panel load calculation is a decrease in total load by 2600 VA (+600 - 3200).
Load Changes to PP-1E341 Panel PP-1E34 1 had a spare single pole 40 A breaker. This breaker was removed and replaced with a single pole 20QA breaker for the 600 VA LEFM load. The panel is rated for 30 kVA and currently. carries a normal load of 11.3 kVA. The overall impact to the panel load calculation is an increase in total load by 0.6 kVA to 11.9 kVA.
Pressure Transmitter Cabinet and Secondary Sampling Equipment Enclosure Air Handler Power Power Panel PP-1E343 supplies power to the new pressure transmitter cabinet (1CAB-T1-C3 1) loads. Cabinet 1CAB-Ti-C31 contains a space heater for freeze protection, and a light with a Page 20 of 22
Enclosure to SERIAL: HNP-1 1-079 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEW*ED LICENSENO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL- INFORMATION REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER,0PRATE LICENSE AMENDMENT REQUEST 120 VAC receptacle. Power PanelPP-1E343 also powers the Secondary Sampling Equipment Enclosure air handlers. Panel PP-1E343 is fed from MCCGIE34-via a 45 kVA 480 - 120/208 volt transformer. MCC 1E34 is fed from 480 V Bus 1E3 via 6.9-kV/480 V Auxiliary Transformer. This power source is not safety-related. Therefore, safety-related power supplies and emergency diesel generator 1oading is unaffected.
MCC 1E34 CKT 16 11875AG 1-2/C #10 L o ad Ch ang es to P P -1E 34 3 . . . .... :-..
Two new single pole 15 A breakers were added to panel PP- 1E343. The space heater is an 848 VA load, and the cabinet light is a 41 VA load. The new air handlers each add' 0.5A (5.5 A old unit compared to 6.0 A new unit) to their respective circuits. "The total indrease load to Th.e shpply PP-1E343 for the two new air handlers is 2 x 0.5A x 208 VAC*=208 VA.
transformer is rated for 45 kVA and currently carries a normal load of 2737 kVA. .The overallt' impact to the panel load calculation is an increase in total load of 1.1 kVA to 28.8 kVA, which is well within the supply transformer's 45 kVA rating.
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Enclosure to SERIAL: HNP- 11-079 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 Conclusion The LEFM CheckPlus system is powered from non-safety related busses and does not impact safety-related power supplies or the emergency diesel generator's loading. The additional LEFM CheckPlus system loading is within the capacity of the existing electrical supply busses.
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