ML20077S455

Startup Physics Testing Rept,Cycle 17

ML20077S455
Person / Time
Site:	Monticello
Issue date:	01/09/1995
From:	NORTHERN STATES POWER CO.
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ML20077S435	List: ML20077S432 ML20077S455
References
NUDOCS 9501240100
Download: ML20077S455 (3)

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Attachment A Startuo Physics Testina Report. Cycle 17 I I

Shutdown Marain [?emonstration (Test 0073) 1 Withdrawal of the highest worth control rod as calculated by the NSP Nuclear Analysis

and Design group (NSP-NAD), plus additional reactivity to account for the 0.25%

delta-k Technical Specification margin requirement, the 0.05% allowance for inverted absorber tubes, a 0.21% allowance for temperature defect (140 degrees F), a 0.08%

allowance for calculational uncertainty, and a 0.26% allowance for the Technical Specification "R" value, still showed the reactor to be subcritical, thereby demonstratini shutdown margin compliance. Demonstration of subcriticality after sufficient notch withdrawals to account for the above numerical values is the acceptable and required  ;

result. l Benchmark Critical (Test 8079)

One benchmark critical was performed. In recent past cycles, rod worth calculations had been performed by NSP-NAD, who had performed the licensing analyses and by GE, who had performed confirmatory calculations. For Cycle 17, confirmatory calculations were performed in-house at NSP-NAD, using the CASMO3/ SIMULATE computer code package which is expected to be licensed for use with Cycle 18 licensing analyses. The licensing calculations for Cycle 17 were performed using the CASMO-Ile/NDH code package. These two code packages predicted the same top two high worth control rods, but reversed in order. (i.e. CASMO-lie /NDH predicted Rod A as the high worth rod, and Rod B as the second highest worth rod, while CASMO3/ SIMULATE predicted Rod B as the high worth rod and Rod A as the second highest worth rod.) Rod A and B were diagonally adjacent to each other. As a result, if criticality were to occur beyond the withdrawal of the second control rod in the l benchmark critical, then the two benchmark criticals for the two code packages would I reduce to the same benchmark critical rod configuration (since the benchmark criticals utilize withdrawal of diagonally adjacent control rods). This was indeed found to be true.

The benchmark critical occurred within 0.30% (early) delta-k of the predicted critical position for CASMO-lie /NDH and within 0.03% delta-k of the predicted critical position of CASMO3/ SIMULATE. These results are acceptable because they fall within the +/-

1% delta-k acceptance band for reactor criticals, and are within the 0.70% reliability factor (approximately 2 sigma) calculated by NSP-NAD. Note that the minimum shutdown margin during the cycle calculated usir g CASMO-lie /NDH methods is 1.308% delta-k, so a 0.30% (early) adjustment still leaves abundant shutdown margin H: \ DATA \NhCCORR\C17 SUR PT . DOC 95o1240100 950109 PDR ADOCK 0500o263 p PDR

Attachment A January 9,1995

Page 2 ,

. remaining. Similarly, the minimum shutdown margin during the cycle calculated using the CASMO3/ SIMULATE confirmatory calculations was 1.44%.

in-Seouence Critical i The reactor was started up in the A2R3 sequence for BOC17. Criticality occurred 2

0.29% delta-k early, according to CASMO-lie /NDH, and occurred within 0.01% delta-k l

of the predicted critical position of CASMO3/ SIMULATE. These in-sequence critical results are acceptable, since they fall within the +/- 1% delta-k acceptance band for reactor criticals.

Temperature Coefficient Data The data taken during the Cycle 17 startup was compared to the prediction based on NSP-NAD methods. The maximum difference in the temperature defect between the reactor and the NSP-NAD predictions is approximately 0.06% delta-k. This value is j similar to past cycles and is reasonable. There is no quantitative acceptance band for i this data.

.i Summary

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) All data collected satisfied acceptance criteria. There was no anomalous data.

Physics testing for the new core loading, including the 8 Siemens 9x9-IX (ATRIUM 9B) fuel bundles, was satisfactory.

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, TRANSMITTAL MANIFEST _ {

! - NORTHERN STATES POWER COMPANY J ,

j NUCLEAR LICENSING DEPARTMENT i

MONTICELLO NUCLEAR GENERATING PLANT a

H Startuo Physics Testina Report. Cycle 17 -

Correspondence Date.

j Monticello Intemal Site Distribution Special Instruchons Kaleen Hilsenhoff...... USAR File...... ...........Yes No x 4

Steve Ludders ... ......NRC Commitraent .....Yes No x l Ula Imholt...... .. . . .... Monti OC Sec ...........Yes No x - 10, No dist to OC members below if YES l Mel Opstad.. . . .........Monti SAC Sec..... ....Yes No x -8 i

• Mail Room ... .. ........ Monti Posting. ...........Yes No x -7 l j Monticello Intemal Site Distribution:

) *Monti Document Control File J C Grubb, NGSS, OC W J Hill, Plant MGR, SAC, OC L L Nolan, GSSA, OC ,

C A Schibonski, GSE, OC B D Day, MGR MTC, OC M F Hammer, GSM, OC Operating Exponence Coord  ;

J E Windschill, GSRS, OC W A Shamla, NQD

, I i M W Onnen, GSO, OC Monti Site Lic File Harold Paustian Steve Ray, SR Res insp, NRC ,

Dan Wegener l

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j NSP Intemal Distribution j j E L Watzi R O Anderson, Dir LMI, SAC l 1 L H Waldinger, SAC T E Amundson, Dir NQD, SAC '

Communications Dept Yes No x

Extemal NSP Distribution j

• Doc Control Desk, NRC Kris Sanda, State of Mann  :

Regional Admin-lli,NRC J E Silberg, I Beth Wcuel, NRR-PM, NRC I 1

• Advance Distribution made by Site Licensing Manifest Date: January 9,1995

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