ML20100G835

Startup Test Rept,Cycle 5. W/

ML20100G835
Person / Time
Site:	Seabrook
Issue date:	02/16/1996
From:	Dacimo F NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-96008, NUDOCS 9602260264
Download: ML20100G835 (14)

Text

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1 North North Atlantic Energy Service Corporation P.O. Box 300

$ Atlaritic Seah,oet Nn 03874 (603) 474-9521 The Northeast Utilities System NYN-96008 February 16,1996 4

United States Nuclear Regulatory Comnussion Washington,D.C. 20555 Attention:

Document Control Desk

Reference:

Facility Operating License No. NPF-86, Docket No. 50-443

Subject:

Cycle 5 Stanup Repod Gentlemen:

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In accordance with the requirements of Technical S,wihdon 6.8.1.1, enclosed is the Cycle 5 Startup Report for Seabrook Staten Should you have any questions, please contact Mr. Anthany M. Callendrello, Licensing Manager, at (603) 474-9521, extension 2751.

i Fred R. Dacuno Vice President -Nuclear Operations

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FRD:ALLysl Enclosure 9602260264 960216 1

PDR ADOCK 05000443 p

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United States Nuclear Regulatory C i==laa February 16,1996 At*A Document Contml Desk Page Two 1

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Mr. 'Ihomas T. Martin i

Rqponal Administrator U. S. Nuclear Regulatory Comniinaian RegirmI 475 All-imle Road King of Prussia, PA 19406 Mr. Albert W. De Agazio, Sr. Project Manager Project Duectorate I-4 Division of Reactor Projects U.S. Nuclear Regulatory Commianian Washington,DC 20555 Mr. John B. Maalanald l

NRC Senior Remiave laspector P.O. Box 1149 Seabrook,NH 03874 J

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e North Atlantic February 16,1996 ENCLOSURE 1 TO NYNA6005 i

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I Docket No. 50-443 l

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SEABROOK STATION UNIT NO. I h

STARTUP TEST REPORT CYCLE 5 t

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1.0 CHRONOIDGICAL

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 LPFrRESULTS TABLE 2 PAT FLUX MAP RESULTS i

l TABLE 3 FULL POWER THERMAllHYDRAULIC DATA l

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1.0, C$RONOLOGICAL

SUMMARY

Cycle 5 Puel Load was w.pc-:-j November 26, 1995.

Subsequer.t operation / testing milemtanes were wrA as folkms:

INITIAL CRITICAllTY 12/09/95 IEFI'COMPLEIED 12/10/95 ONIJNE 12/11/95 30% PAT COMPIETED 12/12/95 50% PAT COMPIEIED 12/14/95 75% PAT COMPLETED 12/15/95 90% PAT COMPLETED 12/15/95 1

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FULL POWER 12/16/95 100% PAT COMPLETED 01/12/ %

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t CORE DESIGN

SUMMARY

2.0 Cycle 5 is designed to be a transition core to longer 24 rnonth cycle lengths. 'Ihe Cycle 5 core is designed to operate for 20372 MWD /MTU (530 Effective Full Power Days). 80 fresh fuel assembhes were loaded into the Cycle 5 core with 24 having an enrichment of 4.4 w/o and 56 having an enrichment of 4.8 w/o. In addition, the top and bottom 6 inches of the 80 assemblies have an enrichment of 2.6 w/o creating an axial annular blanket. By comparison, Cycle 4 utilized 72 fresh fuel assemblies with enrichments of 3.6 and 4.0 w/o and no axial annular blanket.

Presh assemblies for this cycle are Vantage 5H 'nntn. This design utilim ZIRID for fuel clad, control rod guide tubes and instrument thimbles and Zircaloy-4 for the 6 low pressure drop mid srids. 'Ihe mechanical design is similar to that used in previous cycles with the addition of an inconel psutective bottom grid.

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l 3.0 LdW POWER PHYSICS TESTING

SUMMARY

Testing was performed in accordance with the folkming general sequence:

1. Initini Crih%: Criricality was achieved using a controlled withdrawal of control banks once shutdown banks had been withdrawn.

2. Zero Power Test Range Determination: This was deterrnined aAer the point of addmg heat had been demonstrated. Additional emphasis was placed on this rnessurement to prevent testing too low in the test range, thus minimizing gamma contribution to the excore signal.

3. On-line Verification of the Reactivity Computer: 'Ihis was determined using stable startup rates during flux doubling measurements.

4. Baron endpoint measurements: Data was obtained with 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.

'Ihe Moderator Temperature Coefficient (MIC) was cahilaw from the ITC Data.

6. Rod Worth Measurements: Contml Bank worths were measured during rod insertion and individual as well as total bank worths were cahilaW.

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i 4.0

. POWER ASCENSION TESTING

SUMMARY

Tesdng was performed at specified pomw plateaus of 30%,50%,75%,90% and 100% Rated

'Ihermal Power (RTP). Powe. etanges wese govemed by operating procedures and fuel g+-

• -- - '; guidaliaan specified by the fuel vendor, Westinghouse.

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In order to detenine the core power distribution, flux mapping was performed at 30%, 50%

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and 1005 RTP using the Fixed Incore Twarear System. 'Ihe remdtant peaking factors were j

compared to Technical Specification limits, to verify that the core was operating within its I

design limits.

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'Ibermal hydraulic parameters, nuclear parmnumers and related instrumentation were monitored j

@ the Power Ascension. Data was aunpmed to pnwious cycles' power ascension data

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to identify any cahbration or system problems. W ;aqior areas analysed were:

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1. ?lucientInstrumentationIndication: Overlap data was obtained between Internwliate Range and Power Range channels. Secondary plant heat balance calcidatinris were performed to j

verify the Nuclear Instrumentadon indications.

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2. RCS Delta-T Indication: 'Ihe initial scaling of RCS AT was left the same as Cycle 4. At 75% RTP, actual full power AT was extrapolated out using data from 30%, 50% and 75%

l and AT rescaled wC. gly. At 90% RTP, AT was again evaluated and no rescaling was i

required to support a power ircrease to 100% R'IP. Final adjustments were performed at 1005 RTP.

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3. Upper Plenum Anomaly:

In early 1992, Westinghouse notified North Atlantic that j

Seabrook Station may be==Teilde to a phmomenon 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 &#=e. A Design Document was prepJed at that time to implement a qumber of operating conti.+.. des should the UPA be present. Cycle 5 data collected at

'JO% RTP identified the presence of UPA for RCS loops 2 and 3. As a result, Revised (nor Average Scaling (RTAS) was implemented for loop 2 Tesor signal Witianing circuitry.

4. RCS Temperatures:

Data was obtained for all Narrow Range loop temperatures.

Evaluations of Delta-T (*F) and T o / Tm,Irwiinatiari were pufuis.ed.

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, POWER ASCENSION TESTING

SUMMARY

(Continued)

5. Steam and Feedwater Pkus: Data was obtained to evaluate fkms for individual loop agreement between transmitters and loop steam fkm/ feed fkw deviations.

6. Steam Fressures: Data was obtained to evaluate steam generator pressures for individual loop agreement between trancmilkrs.

The initial scaling of inw=3 pressure was left the same 1

7. 'Ibrbine i==1-Pressure (Tay):

as Cycle 4. i=:=3 pressure was evaluated at each plateau to determine if the existing 1

scaling would support continued power incnnse. Final adjustmena were performed at 1005 RTP.

8. Incase /Excore Onlihration: Scaling factors wuse c=Im1M from flux map data using the single point cahbration methodology. h nuclear instrumentation power range channels were rescaled at 50% and 100% RTP.

9. RCS Pkm: A primary heat balance was y L..d at 90% RTP to determine total RCS fkm. h measured fkw was conected for the effects of RCS " hot leg temperature streatug" using Westinghouse methodology [WCAP-14541].

Other than procedure d rw to accommodate initial criticality using contral banks vice dilution and additional monitoring requirements for " Wkle Band Opention" (Ucense Amendment 33) the power ascension test prograt:1 required no rmpor changes from Cycle 4.

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5.0,

,RESULTS J

1. Iow Power Physics Testing:

Both amT*=re and review criteria were revised per Westinghouse lener 94 NA#-G-0030, recommardled Westinghouse physics test results. All Tm criteria were met. All 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%

i RTP. See Table 2 for results.

3. Full Power 'Ihermal/ Hydraulic Evaluation: No problems were encountered with any instrumentation. An Upper F:enum Anomaly was identified and RTAS was implemented for RCS loops 2 Tu ignals. Total RCS flow was determined to be 100.8% of the s

allowable Technical SpecL%tian limit. See Table 3 for results.

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TABLE 1 LOW POWER PHYSICS RESULTS: CYCLE 5 ITEM MEASURED PREDICTED ERROR CRITERIA CBD POSITION AT CRITICALITY 99 steps 69 steps 87 pcm

• 500 pcm BORON END POINTS:

• ALL RODS OUT 1938 ppm 1959 ppm 139 pcm

• 1000 pcm

. CONTROL BANKS INSERTED 1410 ppm 1424 ppm 98 pcm

• 500 pcm

• ARO ITC (pcm/*F)

-2.09

-1.34 0.75

• 2*

ARO MTC (pcm/*F) 0.43

+ 0.32 N/A

< 1.95**

CONTROL BANK ROD WORTHS: (pcm)

• D 621 586 35

• 100*

• C 953 949 4

• 142*

. B 810 800 10

• 120*

• A 1257 1232 25

• 185*

• TOTAL 3641 3567 74 23210

• 357*

NOTE:

• Review criteria, all others are acceptance criteria.

• • COLR limit is 2.19 (the max over the entire cycle),1.95 is the BOL surveillance limit.

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4 TABLE 2 POWER ASCENSION FLUX MAP RESULTS: CYCLE 5 ITEM MAP 1 MAP 2 MAP 3 l

4 DATE OF MAP 12/12/95 12/13!95 12/16/95 POWER LEVEL (%)

29.4 49.1 100.0 t

i CBD POSITION (steps) 181 191 225 RCS BORON (ppm) 1682 1618 1395 Fq 1.9750 1.8890 1.9182 Pan 1.5463 1.5095 1.4976 INCORE TILT 1.011 1.0106 1.0089 TABLE 3 FULL POWER THERMAL-HYDRAULIC DATA: CYCLE 5 ITEM VALUE RCS T vo 586.4 'F 4

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RCS DELTA-T:

• LOOP 1 59.62 'F

• LOOP 2 58.49 'F e LOOP 3 56.99 'F e LOOP 4 58.64 *F RCS FLOWS:

(corrected for hot leg streaming affects) e LOOP 1 97303 GPM e LOOP 2 99857 GPM e LOOP 3 102823 GPM e LOOP 4 98667 GPM 398650 GPM

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AUCTIONEERED HIGH T vo 587.34 'F 4

Tane 586.79 'F i

IMPULSE PRESSURE 665.8 PSIG SG PRESSURES:

• A 971.6 PSIG e B 971.3 PSIG

• C 970.3 PSIG

• D

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