ML20128G143

Cycle 3 Startup Test Rept for Seabrook Station Unit 1

ML20128G143
Person / Time
Site:	Seabrook
Issue date:	02/05/1993
From:	NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:
Shared Package
ML20128G127	List: ML20128G124 ML20128G143
References
NUDOCS 9302120165
Download: ML20128G143 (11)

Text

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r?ocket No. 50-443

. s SEABROOK STATION UNIT NO. 1 STARTUP TEST REPORT CYCLE 3 9302120165 930205 PDR ADOCK 05000443 p PDR

. s.

INDEX 1.0 CHRONOLOGICAL

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 1 LPPT RESULTS TABLE 2 PAT FLUX MAP RESULTS TABLE 3 FULL POWER THERMAL / HYDRAULIC DATA 4

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1.0 , CHRONOLOGICAL

SUMMARY

Cycle 3 Fuel Load was completed October 13, 1992. Subsequent operation / testing milestones were completed as follows:

INITIAL CRITICALITY 11/11/92 LPPT COMPLETED 11/13/92 ON LINE 11/13/92 30% PAT COMPLETED 11/16/92 50% PAT COMPLETED 11/19/92 75% PAT COMPLETED 11/20/92 90% PAT COMPLETED 11/21/92 FULL POWER 11/21/92 100% PAT COMPLETED 12/01/92 l,

?2j0 i CORE DESIGN SUMM1JE

-CycleL3 will be Seabrook-Station"a first-18-month fuel cycle.'

The Cycle;3 core ~is designedLto operate 1for 16950 MWD /MTU (444-Effective Full Power Days). LThe: principal change.necessaryLto:

achieve the 18-month: fuel cycle was aniincrease irr both the.

number:and enrichment-of the reloadLfuel1 assemblies. 76-freshi fuel assemblies werel loaded into the Cycle 3 core with'36' having an-enrichment of 4.0 w/o and 40 having an'enrichmanteef 4.4 w/o.- By comparison,' Cycle 2 utilized:60 fresh fuel-assemblies with an enrichment of 3.4 w/o.

The-reload fuel mechanical design is-identical to that used in Cycle 2. The operating featu: es of these fuel' assemblies c aro a removable top nozzle;. debris _ filter bottom nozzle, integral fuel burnable-absorber, extended burnup capability _and anti-snag grids. Two new secondary sources were added-to the core bringing the-totalEin.the core to four. These new sourcesJare located 90* from the existing sources and are intended to' provide an increase in source counts to the Gammametrics1 Shutdown Monitors.

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- 3.0 .. ( LOW' POWER PHYSICS TESTING SUMNARY Tosting was performed in accordance with-the following general' sequences  :

1. Initial-Criticality: Criticality was-achieved _using-a controlled dilution once shutdown and control banks had ,;

been withdrawn.

2. Zero Power Test Range Determinations- This was determined =

• after the point of adding heat had been demonstrated.

Additional emphasis was placed on this measurement to 7; prevent testing too low-in the test range,.thus minimizing _-

gamma contribution to the excore signal, ,

3. On-line verification of the_ Reactivity Computer: This.was.

determined-using-stable startup rates during' flux doubling .

measurements. .

4. Doron endpoint' measurements: Data was obtained witti all .

rods out and control banks inserted.

5. Isothermal Temperature. Coefficient Measurement.(.ITC): ITC was based on the reactivity change resulting from an RCS' temperature change. The Moderator Temperature Coefficient (MTC) was calculated from the ITC Data.

6. Rod Worth Measurements: Individual-Control tank worths .

were measured during rod insertion.- -Total Control Bank worth was measured during_ withdrawal-in overlap. l 1.

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4.0 .

. POWER ASCENSTON TESTING

SUMMARY

Testing wac performed at specified power plateaus of 30%,_50%,

75%, 90%'and 100% Rated Thermal Power (RTP). Power changes were governed by operating procedures and Fuel Preconditioning Guidelines specified by the fuel vendor, Westinghouse.

In order to detereine steady state core power distribution,

' flux mapping was performed at 30%, 50% and 100% using the Movable Incore Detector System. The resultant peaking factors were compared to Techaical Specification limits, to verify that the core was operating within its design limits.

Shermal-hydraulic parameters, nuclear parameters and related instrumentation were monitored throughout the Power Ascension.

Data was compared to previous cycles' power ascensien data to identify any calibration or system problems. The major areas analyzed were:

1. Nuclear Instrumentation Indication: Overlap data was a

obtained between Intermediate Range and Power Range channels. Secondary plant heat balance calculations were performed to verify the Nuclear Instrumentation indications.

2. RCS Delta-T Indication: During the second refueling, the Resistance Temperature Detector (RTD) bypass piping was removed. RCS temperature indication is now being accomplished by means of RTD's directly inserted in the RCS hot and cold leg piping. The initial scaling of RCS ST was set conservatively with respect to power indication. A value of 53 F was chosen. At the 75% power plateau, actual full power AT was extrapolated out using data from 30%, 50% and 75% power and AT rescaled accordingly. Final adjustments were performed at 100%

power and the values provided in Table 3. &

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 aperiodic step changes of 1 F to 2 F in hot leg temperature. A Design Document was written to implement a number of operating contingencies should the UPA be present in Cycle 3. An additional plateau at 75% power was added to the power ascension test program to determine the UPA presence in Cycle 3 and, if so, implement the necessary contingency actions. No Upper Pl9num Anomaly was identified.

4. RCS Temperatures: Data was obtained for all Narrow Range Loop temperatures. Evaluations of Delta-T ( F) a:J Tavg/ Tref Indication were performed.

4j0 , POWER ASCENSION TESTING

SUMMARY

(Continued)

5. Steam and Feedwater Flows: Data was obtained to evaluate flows for individual loop agreement between transmitters and-loop steam flow / feed flow deviations.

6. Steam Pressures Data was btained to evaluate steam generator pressures for inoxvidual loop agreement between transmitters as well as individual turbine impulse pressures.

7. Incore/Excore Calibration: The core was operated at a variety of axial power shapes during flux mapping at 50%

and 100% RTP. This was accomplished through rod motion and subsequent xenon oscillations. Scaling factors were calculated and then used to recalibrate the Nuclear Instrumentation System.

8. RCS Flow: A primary heat balance was performed at.90% RTP to determine total RCS flow.

Other than the considerations of RCS AT and the UPA mentioned above, the power ascension test program roquired no changes from Cycle 2.

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, RESULTSI

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1. ' Low-Power Physics Testing:

All acceptance criteria-were-met. - All review criteria were met.-' See Table.1 for-results.

2. Flux Mapping:- No problems were' identified during the-l flux maps at 30%, 50% and 100% RTP. ~See Table 2 for results.

3. Full Power Thermal / Hydraulic Evaluation:--No problems-were-encountered-with any instrumentation. No Upper Plenum-Anomaly was identified. Total RCS flow was determined to be 102.6% of the allowable Technical Specification limit.

See Table 3-for results.

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TABLE 1 LOW POWER PHYSICS RESULTS: CYCLE 3 ITEM MEASURED PREDICTED ERROR CRITERIA RCS BORON AT CRITICALITY (ppm) 1522 1566 44 i 66 CBD @ 15' 3TEPS)

BORON END POINTS: (ppm)

ALL RODS OUT 1551 1590 39 i 50 CONTROL BANKS INSERTED 1117 1136 19 i 50 ARO ITC (pcm/ F) -3.26 -3.20 0.06 3*

ARO MTC (pcm/ F) -1.55 N/A N/A < 0 l CONTROL BANK ROD WORTHS: (pcm)

D Si 530 1 1 100*

C 882 970 88 1 146*

B 871 906 35 i 136*

A 960 1017 57 1 153*

OVERLAP 3219 3423 206 i 342 W

NOTE:

• Review criteria, all others are acceptance criteria.

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jf TABLE 2 POWER ASCENSION FLUX MAP RESULTS: CYCLE 3 ITEM MAP 1 MAP 2 MAP 3 DATE OF MAP 11/16/92 11/19/92 11/25/92 POWER LEVEL (t) 30.2 48.1 100

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CBD POSITION (STEPS) 175 207 214 RCS BORON (ppm) 1307 1197 1020 Fxy (UNRODDED/ RODDED) 1.7537/1.6945 1,6201 1.5588 Fa 1.5205 1.4678 1.4141 INCORE TILT 1.0156 1.0114 1.0071 L_

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g TABLE'3-FULL POWER THERMAL-HYDRAULIC DATA: CYCLE 3 ITEM -VALUE RCS TvcA 586.0 RCS DELTA-T Loop 1 56.91*F 2 57.12 F 3 55.08'F' 4 56.13*F.

RCS-FLOWS LOOP 1 99794 GPM 2 .99893-GPM. ~

3 104198 GPM-4 100222 GPM TOTAL 404107:GPM AUCTIONEERED HIGH Tvc A 586.75*F- j Tm. 586.95*F IMPULSE PRESSURE 665.9'PSIG SG PRESSURES l . .. .

A- 973.0'Pb1G B '973.3'PSIG-C .974.3 PSIG-D- 971.3-PSIG p:

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