ML20091P579

Cycle 2 Startup Test Rept for Seabrook Station,Unit 1. W/

ML20091P579
Person / Time
Site:	Seabrook
Issue date:	01/29/1992
From:	Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-92009, NUDOCS 9202030179
Download: ML20091P579 (11)

Text

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. Ne'w Hampshire Y h Ted C. Feigenbovm President and Chief becutive Othcer NYN 92009 January 29, 1992 Ur.,cd States Nue:a.ar Regulatory Commission Washington, D.C. 40355 A;tention: Document Control Desk

References:

Fa.ility Operating License No. NPF 86, Docket No. 50 443

Subject:

Cycle 2 Startup Report Gentlemen:

In accordance with the requircments of Technical Specificcion 6.8.1.1, enclosed is the Cycle 2 Startup Report for Seabrook Station.

Should you have any questions, please contact Mr. Terry L. !!arpster, Director of Licensing Serviews, at (603) 474-9521, extension 2765.

Very truly yours, Qc,7 'p dw' Ted C, Feigenbaum TCF:JMP/ tad ec: Mr. Thomas T. Martit.

Regional Administrator U. S. Nuclear Regulatory Co w i' Region i 475 Allendale Road King of Prussia, PA 19406 Mr. Gordon E. Edison, Sr. Project Manager Project Directorate I-3

- Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Noel Dudicy NRC Senior Resides.t inspector P.O. Box 1149 P202030179 920129 FDR ADOCK 05000443 -

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• Avvvv PDR new nampume on nee Division of Public Service Company of New Hampshire P.O Box 300. Scobrook, NH 03874

• Telephone (603) 474 9521 0 j/ \

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4 SEABROOK STATION UNIT NO. 1. ,

FACILITY OPERATING LICENSE NPP-86

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Docket No. 50-443

-STARTUP TEST REPORT ,

CYCLE 2 ,

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INDEX l'.0-. CHRONOLOGICAL

SUMMARY

2.0 ' CORE: DESIGN-

SUMMARY

3.0 -LOW. POWER Pl!YSICS TESTING

SUMMARY

-(LPPT) i 4 '. 0 POWER ASCENSION TESTING

SUMMARY

(PAT) 5.0 TEST RESULTS TABLE 3 LPPT RESULTS TABLE 2 PAT: FLUX MAP RESULTS ,

TABLE 3 FULL POWER THERKJJ / HYDRAULIC DATA f

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'fl . 0 - CH110NOLOGICAL

SUMMARY

Cycle 2 Fuel Load was completed-September 9, 1991.  ;

Subsequent-operation / testing milestones-were completed as i follows: .!

INITIAL CRITICALITY 10/09/91

• 10/12/91

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LPPT COMPLETED s ON LINE 10/16/91  ;

30% PAT COMPLETED 10/19/91 50% PAT COMPLETED 10/23/91 '

90% PAT COMPLETED 10/25/91 FULL POWER 10/29/91 100% PAT. COMPLETED 11/14/91 f

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4 4 2.0 CORE DESIGN

SUMMARY

- The Cycle 2 Core is designed-to operate for 11550 MWD /MTU (302.7 EFPD), This cycle utilized 60 reload fuel assemblies with an enrichment of 3.4 w/o U-235 arranged in a low leakage loading pattern. The reload fuel assemblies for cycle 2 incorporated a number of mechanical design changes to improve the overall operation of the fuel. Those changes are:

1. Reconstitutable Top Nozzle: This change allows for easier removal and replacement of fuel rods.

2. Debris Filter Bottom Nozzle: This change minimizes the possibility of fuel damage due to debris in the Reactor Coola:.t System by preventing any foreign material f rom entering the active fuel regicn of the core.

3. Integral' Fuel Burnable Absorber (IFBA): Burnable poisons for Cycle 2 utilize the IFBA design in place of the burnable poison rod assemblies used in Cycle 1.

There are a total of 3712 IFBA rods in Cycle 2.

4. Extended Burnup Capability: The fuel rod plenum was '

enlarged slightly to accommodate more' fission gas buildup from longer operating cycles.

5. Anti-Snag Grids - Anti-Snag grids are used to minimize the potential for grid strap damage during fuel handling operations, u

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- 3.0 LOW POWER PHYSICS TESTING

SUMMARY

Testing was performed in accordance with the following-general sequence:

1. = Initial Criticality: Criticality was achieved using a controlled dilution once shutdown and control banks had been withdrawn (CBD 9 140 steps). -

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 flux doubling measurements.

4. Boron endpoint measurements: Data was obtained with all rods out and control bank: inserted.

5. Isothermal' Temperature Coefficient Measuremont-(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 measurement: Individual Control-Bank worths were meacured during rod insertion. Total Control Bank worth was measured during withdrawal in overlap.

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4.0 EpWER ASCENSION TESTING

SUMMARY

Testing was performed at specified powcr plateaus of 30%,

50%, 90% and 100% RTP. Power changes were governed by operating procedures and Fuel Proconditioning Guidelines specified by the fuel vendor, Westinghouse.

In order to determine steady state core power distribution, flux mapping was done at 30%, 50% and 100% using the Movable Incore Detector System. The resultant peaking factors were compared to Technical Specification limits, to determine any e limitations on further power ascension.

Thermal --hydraulic parameters, nuclear parameters and related instrumentation were monitored throughout the Power Ascension. The major areas of concern were:

1. Nuclear Instrumentation Indication: Overlap data was '

obtained between Intermediate Range and Power Range ct;annels. Secondary plant heat balance calculations were performed to verify the Nuclear Instrumentation indications at 30% and 90% RTP. Precision Heat Balance Calculations were performed at 50% and 100% RTP.

2. RCS Temperatures: Data was obtained for all Narrow Range Loop temperatures. Evaluation of Delta T and Tavg Indication were performed.

3. RCS Flow: A precision heat balance was performed at 50% RTP using primary and secondary data to determine total RCS flow.

4. Steam and Feedwater Flows: Data was obtained to determine the full power values for individual loop agreement between transmitters, loop steam flow,..ed flow deviations and steam flow normalization factors.

5.. Tref Program Parameters: Data was obtained to determine the full power values for steam generator pressures, turbine impulse pressures and Tref indication.

( 6. Incore/Excore Calibration: The core was operated at a i variety of axial power shapes during flux mapping at l

50% (48%) 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..

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i 5.0 RESUL1S 1 Low Power Physics testing: All acceptance criteria were met.- All review criteria were met'with the er.ception of the individual worth of Control Bank B.

_ The fuel vendor, Westinghouse, evaluated the data and attributed it to testing too low in the Zero Power Test Range (Gramma santribution to excore signal). Control rod worth measurements (overlap) were done at a higher power level with acceptable results. See Table 1 for results.

2. Flux Mapping: No problems were id.entified during the 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. Only loop-Delta T indication required minor rescaling. Total RCS flow was-determined to be 103% of the allowable Technical Specification limit. See Table 3 for results.

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LOW POWER PHYSICS RESULTS: CYCLE 2 l

l ITEM MEASURED PREDICTED -ERROR -CRITERIA RCS BORON AT 1297 1304 7~ i 5.

CRITICALITY (ppm)

CBD @ 140' steps) i

--- d BORON END' POINTS:(ppm) .

ARO -1341 1335 -6 1.50 CONTROL-BANKS-INSERTED 911 905 6- 1 50 ARO ITC (ppm /*F) -2.73 -3.69 .96 13*

ARO MTC (ppm /*F) .94 N/A N/A- <0 CONTROL BANK ROD WORTHS :(pcm)

D 373 418 45 t :100 *:

C 984- 1118 134 1 168*

B. 756 907 151- i 136*

A 1365 1438 73 .i 216*

, OVERLAP 3752 3881 129 i 388 NOTE:

• Review criteria, all others are acceptance criteria.

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TABLE 1 LOW POWER PHYSICS RESULTS: CYCLE 2 ITEM MEASURED PREDICTED ERROR CRITERIA I

RCS BORON AT 1297 1304 7 1 So CRITICALITY (ppm)

CBD @ 140 steps)

BORON END POINTS:(ppm)

ARO 1341 1335 6 1 50 CONTROL BANKS INSERTED 911 905 6 1 50 ARO ITC (ppm / F) -2.73 -3.69 .96 1 13*

ARO MTC (ppm / F) .94 N/A N/A I <0 CONTROL BANK ROD WORTHS :(pcm)

D 373 418 45 1 100*

C 984 1118 134 1 168*

B 756 907 151 1 136*

A 1365 1438 73 216*

OVERLAP 3752 3881 J29 1 388 NOTE:

• Review criteria, all others are acceptance criteria.

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W TABLE 2 POWER ASCM4SION PLUX MAP JESULTS: CYCLE 2 ITEM. MAP 1 MAP 2' MAP 3 Date of Map- 10/19/91 10/21/91 11/01/91 3

Power-level (%) 29.7 48.3 100 CBD Position (Steps) 148 164 192 RCS Doron-(ppm) 1055 993 838 Fn(unrodded/ rodded) 1.5424/1.6762 1.5215/1.6536 1.5859 Fg 1.4262 1.4042 1.4059 Incore Tilt 1.0094 1.0088 1.0049 I

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TABLE 3 i

FULL POWER THERMAL-HYDRAULIC DATA: CYCLE 2

- ITEM VALUE RCS Average 587.2'F ,

Temperature ,

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- RCSLDelta-T Loop 1 55,64 'F 2 55.46 'F

-3 55.23 'F 4 55.80 'F RCS Flows Loop _.1 100748 gpm 2 99995 gpm 3 104392 gpm 4- 98725 gpm T

'otal 403860_gpm Tref- 587.25 F Impulse Pressure 672.6 psig i

SG Pressures A- - 984.2 psig B- _ 980.4-paig C 982.2.psig D - 979.9-psig 4

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