SBK-L-10033, Cycle 14 Startup Report
| ML100570174 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 02/22/2010 |
| From: | Freeman P NextEra Energy Seabrook |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| SBK-L-10033 | |
| Download: ML100570174 (11) | |
Text
--. 5 NEXTeraM ENERGY f d February 22, 2010 Docket No. 50-443 SBK-L-10033 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Seabrook Station Cycle 14 Startup Report In accordance with the requirements of Technical Specification 6.8.1.1, enclosed is the Cycle 14 Startup Report for Seabrook Station.
Should you require further information regarding this matter, please contact Mr. Paul V. Gurney, Reactor Engineering Supervisor, at (603) 773-7776.
Very truly yours, FPL Energy Seabrook, LLC Paul 0. Freeman Site Vice President cc:
S. J. Collins, NRC Region I Administrator D. Egan, NRC Project Manager, Project Directorate 1-2 W. Raymond, NRC Senior Resident Inspector AcLX' NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874
ENCLOSURE TO SBK-L-10033
SEABROOK STATION UNIT NO. 1 STARTUP TEST REPORT CYCLE 14
INDEX 1.0 CHRONOLOGICAL
SUMMARY
2.0 CORE DESIGN
SUMMARY
3.0 SUBCRITICAL PHYSICS TESTING
SUMMARY
(SPT) 4.0 POWER ASCENSION TESTING
SUMMARY
(PAT) i
1.0 CHRONOLOGICAL
SUMMARY
Operation/testing milestones were completed as follows:
CYCLE 14 FUEL LOAD COMPLETED 10/27/09 SPT COMPLETED 11/07/09 INITIAL CRITICALITY 11/09/09 ON LINE 11/12/09 30% PAT COMPLETED 11/12/09 50% PAT COMPLETED 11/13/09 80% PAT COMPLETED 11/14/09 94% PAT COMPLETED 12/26/09 FULL POWER 12/26/09 Note: After completion of PAT testing at 80% power on 11/14/09, power was reduced to 65% due to turbine torsional vibration. The unit was maintained 65% power until 12/06/09 when the unit was shut down for turbine repairs. The unit was returned to service on 12/24/09 and PAT resumed at 94% power on 12/25/09.
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2.0 CORE DESIGN
SUMMARY
The Cycle 14 core is designed to operate for 21,000 MWD/MTU. 84 fresh fuel assemblies were loaded into the Cycle 14 core. 24 have an enrichment of 4.40 w/o and 60 have an enrichment of 4.80 w/o. In addition, the top and bottom 6 inches have an enrichment of 2.6 w/o creating an axial annular blanket. By comparison, Cycle 13 utilized 84 fresh fuel assemblies, 52 with an enrichment of 4.20 w/o and the remaining 32 at 4.60 w/o, both with a similar 2.6 w/o axial annular blanket configuration.
The fuel mechanical design used in the Cycle 14 core is the Westinghouse Robust Fuel Assembly (RFA) design. All fuel utilizes ZIRLO for fuel clad, control rod guide tubes and instrument thimbles. The top and bottom grids are Inconel-718. The six low-pressure drop mid-zone and three intermediate flow mixer grids are ZIRLO with ZIRLO sleeves.
In addition, all fuel contains a Performance+ debris mitigation grid located at the bottom end plug of the fuel rod.
The Cycle 14 core was designed for a rated thermal power (RTP) condition of 3648 MWt.
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3.0 SUBCRITICAL PHYSICS TESTING
SUMMARY
This was the second application of Subcritical Physics Testing (SPT) at Seabrook. The following testing sequence was performed with the reactor in MODE 3 using a laptop computer based Data Analysis System (DAS).
- 1. Rod Worth Measurement: Total control bank and shutdown bank worth was measured using the Subcritical Rod Worth Measurement (SRWM) technique with the DAS.
- 2. Boron Endpoint Measurement: The boron endpoint was analytically determined by the DAS using the SRWM data.
- 3.
Isothermal Temperature Coefficient Measurement (ITC): This was determined using the DAS in conjunction with a Reactor Coolant temperature change. The Moderator Temperature Coefficient (MTC) was calculated from the ITC Data.
All acceptance criteria were met and the results are presented in Table 1.
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4.0 POWER ASCENSION TESTING
SUMMARY
Testing was performed at specified power plateaus of 30%, 50%, 80%, 94%, and 100%
Rated Thermal Power (RTP). Power changes were governed by operating procedures and fuel preconditioning guidelines.
Thermal-hydraulic parameters, nuclear parameters and related instrumentation were monitored throughout the Power Ascension. Data was compared to previous cycle power ascension data at each test plateau to identify calibration or system problems.
The major areas analyzed were:
- 1. Core Performance Evaluation: Flux mapping was performed at 30%, 50%, and 100% RTP using the Fixed Incore Detector System. The resultant peaking factors and power distribution were compared to Technical Specification limits to verify that the core was operating within its design limits. All analysis limits were met and the results are summarized in Table 2.
- 2. Nuclear Instrumentation Indication: Overlap data was obtained between the Intermediate Range and Power Range channels. Secondary plant heat balance calculations were performed to verify the Nuclear Instrumentation indications.
- 3. RCS Delta-T Indication: All RCS AT loops were initially scaled using cycle 13 values. Data from 30%, 50%, 80% and 94% RTP met prescribed acceptance criteria. Data was evaluated at 100% RTP and the AT loops were re-scaled.
- 4. Upper Plenum Anomaly Evaluation: In early 1992, Westinghouse notified Seabrook Station that it might be susceptible to a phenomenon known as the Upper Plenum Anomaly (UPA). The UPA is primarily characterized by a periodic step change of I°F to 2°F in hot leg temperature and a corresponding change in steam flow. Cycle 14 data collected at 100% RTP identified the presence of UPA. The 100% RTP data confirmed that instrumentation changes to the delta-T loops implemented in early 2005 successfully mitigated the impact of UPA events on the delta-T instrumentation.
- 5. RCS Temperatures: Data was obtained for the Narrow Range Loop temperatures.
Evaluations for Delta-T (°F) and TAVG /TREF Indication were performed. The data was as expected.
- 6. Steam, feedwater venturi, and feedwater ultrasonic flows: Data was obtained for the steam, feedwater venturi, and feedwater ultrasonic flows. Evaluations for deviations were performed. The data was as expected.
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4.0 POWER ASCENSION TESTING
SUMMARY
(Continued)
- 7. Steam Generator Pressures: Data was obtained for the steam generator pressures.
Evaluations for deviations between redundant channels on individual steam generators were performed. The data was as expected.
- 8. Turbine Impulse Pressure (TRF): The scaling of TUF was evaluated during the power ascension and found acceptable for continued power increase to 100%. Once steady state 100% RTP conditions were reached, the turbine impulse pressure was evaluated and determined to be acceptable.
- 9. "Incore/Excore Calibration: Scaling factors were calculated from flux map data using the single point calibration methodology. The nuclear instrumentation power range channels were re-scaled at 50% and 100% RTP.
- 10. RCS Flow: The RCS flow was measured at the 94% RTP plateau using elbow tap measurements to minimize the effects of observed hot leg streaming. The calculated RCS flow value met the Technical Specification requirements.
- 11. Digital Electro Hydraulic Control (DEHC) System: During Refueling Outage 13, the Station upgraded the turbine control system to a digital system. Testing of the DEHC system was conducted as part of the power ascension test program.
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TABLE 1 SUBCRITICAL PHYSICS TEST RESULTS: CYCLE 14 MEASURED PREDICTED ACCEPTANCE ITEM (M)
(P)
RESULT CRITERIA CONTROL AND SHUTDOWN (M/P)x100 BANK TOTAL ROD WORTH:
(pcm) 6296 6387 98.6%
>90%
BORON END POINT:
HZP ALL RODS OUT 2067 ppm 2067 ppm 0 pcm
+/- 1000 pcm ALL RODS OUT MTC (pcm/!F)
-1.45 N/A N/A
<+ 4.083
- NOTE:
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TABLE 2 POWER ASCENSION FLI JX MAP RFST JITS: CYCLE 14 CYCLE 14 ITEM MAP I MAP 2 MAP 3 DATE OF MAP 11/12/09 11/13/09 12/26/09 POWER LEVEL (%)
28.9 49.2 100.0 CONTROL BANK D POSITION (steps)
FQ 2.2366 2.1912 1.8672 FAH 1.5966 1.5388 1.4481 MAXIMUM NCRILT 1.0181 1.0117 1.0131 INCORE TILT MAXIMUM MEASURED TO PREDICTED POWER 10.588 8.215 6.517 DISTRIBUTION ERROR
(%)
ABSOLUTE AVERAGE MEASURED TO PREDICTED POWER 2.706 2.392 1.962 DISTRIBUTION ERROR
(%)
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