ML20210R805
| ML20210R805 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 08/10/1999 |
| From: | NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO) |
| To: | |
| Shared Package | |
| ML20210R795 | List: |
| References | |
| NUDOCS 9908170220 | |
| Download: ML20210R805 (11) | |
Text
1 Docket No. 50-443 SEABROOK STATION UNIT NO.1 STARTUP TEST REPORT CYCLE 7 j
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9908170220 990810 PDR ADOCK 05000443 P.
PDR t.
INDEX 1.0 C11RONOLOGICAL
SUMMARY
2.0 -
CORE DESIGN
SUMMARY
3.0 LOW POWER PHYSICS TESTING
SUMMARY
(LPPT) 4.0 POWER ASCENSION TESTING
SUMMARY
(PAT) 5.0 TEST RESULTS TABLE I LPPT RESULTS TABLE 2 PAT FLUX MAP RESULTS TABLE 3 FULL POWER TIIERMAIAiYDRAULIC DATA i
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r-1.0,
, CllRONOLOGICAL
SUMMARY
l Cycle 7 Fuel Load was completed April 27, 1999. Subsequent operation / testing l
milestones were completed as follows:
INITIAL CRITICALITY 05/11/99 LPPT COMPLETED 05/13/99 ON LINE 05/13/99 30% PAT COMPLETED 05/14/99 50% PAT COMPLETED 05/16/99 75% PAT COMPLETED 05/16/99 90% PAT COMPLETED 05/17/99
- OFF LINE 05/19/99
- ON LINE 05/21/99 FULL POWER 05/22/99
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Problems with Turbine vibration delayed power operation above 90%. The Unit was taken off-line after completion of testing at 90% to correct the source of vibration.
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2.0 CORE DESIGN
SUMMARY
The Cycle 7 core is designed to operate for 19,384 MWD /MTU (500 Effective Full Power Days) with a coastdown to 19,884 MWD /MTU. Eighty (80) fresh fuel assemblies were loaded into the Cycle 7 core. Seventy-six have an enrichment of 4.00 w/o and four have an enrichment of 4.95 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 i
6 utilized 84 fresh fuel assemblies,80 with enrichments of 4.95 w/o with a similar 2.6 w/o axial annular blanket configuration and the remaining 4 at 2.40 w/o without the axial annular blanket configuration.
Fresh assemblies for this cycle are Vantage 5H ZIRLO. This design utilizes ZlRLO for fuel clad, control rod guide tubes and instrument thimbles and Zircaloy-4 for the six low l
pressure drop mid grids. The mechanical design is identical to the Cycle 6 design, which utilized the Inconel protective bottom grid.
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3.0 LOW POWER PilYSICS TESTING
SUMMARY
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Testing was performed in accordance with the following general sequence:
- 1. Initial Criticality: Criticality was achieved using a controlled withdrawal of the Control banks once all the Shutdown banks had been withdrawn.
- 2. Zero Power Test Range Determination: This was determined after the point of adding heat had been demonstrated.
- 3. On-line Verification of the Reactivity Computer: This was determined using stable startup rates during fiux doubling measurements.
- 4. Boron Endpoint Measurement: This was determined with all the Control and Shutdown banks withdrawn and again with only the Control banks inserted.
- 5. Isothermal Temperature Coefficient Measurement (lTC): This was determined from the reactivity change measured during a Reactor Coolant temperature change. The Moderator Temperature Coefficient (MTC) was calculated from the ITC Data.
- 6. Rod Worth Measurement: Individual Control Bank worths were measured during rod insertion.
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4.0,
, POWER ASCENSION TESTING
SUMMARY
l Testing was performed at specified power plateaus of 30%,50%,75%,90% and 100%
i Rated Thermal Power (RTP). Power changes were govemed by operating procedures and fuel preconditioning guidelines.
In order to detennine the core power distribution, flux mapping was performed at 30%,
l 50% and 100% RTP using the Fixed Incore Detector System. The resultant peaking l
factors were compared to Technical Specification limits to verify that the core was operating within its design limits.
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:
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- 1. Nuclear Instrumentation Indication: Overlap data was obtained between the l
Intennediate Range and Power Range channels. Secondary plant heat balance calculations were performed to verify the Nuclear Instrumentation indications.
- 2. RCS Delta-T Indication: The initial scaling of RCS AT was left the same as Cycle 6. At 90% RTP, actual full power AT was extrapolated out using data from 30%,50%,75% and 90% and AT was rescaled accordingly. Final adjustments were performed at 100% RTP.
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- 3. Upper Plenum Anomaly: In early 1992, Westinghouse notified North Atlantic that Seabrook Station may be susceptible to a phenomenon known as the Upper Plenum Anomaly (UPA). The UPA is primarily characterized by a periodic step changes of 1 F to 2 F in hot leg temperature. Cycle 7 data collected at 100% RTP identified the presence of UPA in RCS loops 2 and 3.
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- 4. RCS Temperatures: Data was obtained for the Narrow Range Loop temperatures.
Evaluations for Delta-T ('F), T vo Deviation Alarm Setpoint and T o / Tat, 4
4t Indication were performed.
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4.0, POWER ASCENSION TESTING
SUMMARY
(Continued)
Evaluations for deviations between redundant channels on individual steam generators were performed.
- 6. Steam Generator Pressures: Data was obtained for the steam generator pressures.
Evaluations for deviations between redundant channels on individual steam j
generators were performed.
- 7. Turbine Impulse Pressure (Tarr): The initial scaling ofimpulse pressure was left the same as Cycle 6. Impulse pressure was evaluated at the 75% and 90% RTP plateaus to determine if the existing scaling would support continued power increase. The i
Cycle 7 full power value was within 8.2 PSIG of the initial scaling value. This meets the allowed deviation criteria.
- 8. Incore/Excore Calibration: Scaling factors were calculated from flux map data using the single point calibration methodology. The nuclear instrumentation power range channels were rescaled at 50% and 100% RTP.
- 9. RCS Flow: A primary heat balance was performed at 90% and 100% RTP to determine total RCS flow. The measured flow was corrected for the effects of RCS
" hot leg temperature streaming" using Westinghouse methodology.
The power ascension test program required no major changes from Cycle 6.
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c 5.0 RESULTS
- 1. Low Power Physics Testing: Acceptance criteria and review criteria were met. See Table 1 for results.
- 2. Flux Mapping: No problems were identified during the flux maps at 30%,50%, and 100% RTP. See Table 2 for results.
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- 3. Full Power Thermal /Ilydraulic Evaluation: No problems _were encountered with the instrumentation. An Upper Plenum Anomaly was identified in Loops 2 and 3. See Table 3 for results.
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TABLE 1 LOW POWER PIIYSICS RESULTS: CYCLE 7 ITEM MEASURED PREDICTED ERROR CRITERIA l
CONTROL BANK D POSITION 178 steps 100 steps 227 pcm iS00 pcm AT CRITICALITY BORON END POINTS:
l ALL RODS OUT_
' 2017 ppm 2052 ppm 225 pcm 1000 pcm CONTROL BANKS INSERTED 1508 ppm 1527 ppm 123 pcm 500 pcm
- e ALL RODS OUT ITC (pcmf'F)
-2.13
-1.08 1.05 2*
ALL RODS OUT MTC (pcm/'F)
-0.47 0.62 N/A
+ 1.85**
CONTROL BANK ROD WORTHS:
(pcm)
- D 445 445 0
+100+
e C 928.5 959 30.5 f144+
e B 826 828 2
il24*
A-1218 1217 1
1183*
- TOTAL 3417.5 3449 31.5 23104 1345 NOTE:
- Review criteria, all others are acceptance criteria.
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1 l-TABLE 2
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l POWER ASCENSION FLUX MAP RESULTS: CYCLE 7 l
ITEM MAP 1 MAP 2 MAP 3 DATE OF MAP 05/14/99 05/15/99 05/24/99 l
POWER LEVEL (%)
28.97 47.90 100 l
l CONTROL BANK D
162 191 228 POSITION (steps)
RCS BORON (ppm) 1821 1674 1401 l
l F
2.1028 2.0648 1.81577 o
FA,,
1.5133 1.4802 1.43006 INCORE TILT 1.0179 1.0172 1.0082 1
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TABLE 3 FULL POWER TilERMAL-HYDRAULIC DATA: CYCLE 7 ITEM VALUE REACTOR COOLANT T vo 586.51 *F 4
REACTOR COOLANT DELTA-T:
LOOP 1 58.74 *F e LOOP 2 58.10 F 57.46 "F LOOP 3 e
57.50 F e LOOP 4 REACTOR COOLANT FLOW:
(corrected for hot leg streaming affects) l TOTAL 399618 GPM 1
AUCTIONEERED111G11T vo 587.55 F 4
l Tntr 587.54 "F TURBINE IMPULSE PRESSURE 674.03 PSIG l
STEAM GENERATOR PRESSURES: