ML17310B077

PVNGS Unit 1 Cycle 5 Startup Rept.

ML17310B077
Person / Time
Site:	Palo Verde
Issue date:	02/24/1994
From:	ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17310B078	List: ML17310B077 ML17310B082
References
NUDOCS 9403080057
Download: ML17310B077 (15)

Text

ENCLOSURE PALO VERDE NUCLEAR GENERATING STATION UNIT 1 CYCLE 6 STARTUP REPORT 9403080057 940224 PDR ADOCK 05000528 P PDR

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.':-.;II:;!':,'Starhip':Repo'it'< .",'q TABLE OF CONTENTS Introduction Low Power Physics Testing Power Ascension Testing.

Cycle 5 Core Load Map.

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'ntroduction The Palo Verde Unit 1 Cycle 5 Core is designed for a burnup of 437 Effective Full Power Days (EFPD). The core loading is detailed in the following table (Core Map on page 8).

Bate Assembly Number of Fuel Rods per Nominal Shims per Average Designation Assemblies Assembly Enrichment Assembly Exposure Gwd/T 168 3.76 G3 48 16 0 52 3.30 168 4.03 G2 24 16 0 62 3.30 180 4.03 Gl 12 52 3.76 0

184 4.03 0 0 52 3.76 172 4.03 F5 32 12 21.786 52 S.60 168 4.03 F4 16 16 21.332 62 3.60 176 8.80 F3 20.907 62 S.60 172 3.80 F2 12 22.172 62 3.60 180 8.80 F1 24 18.647 52 8.60 4.03 FO 0 12,997 3.80 168 4.03 E6 16 32.639 62 3.70 168 3.90 E4 16 16 37.105 62 3.60 168 3.90 E2 16 30.606 62 3.60 168 4.03 El 62 8.90 16 35.106 184 4.03 EO 0 27.667 52 3.90 208 2.78 B1 16 18.462 12 1.92

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"- " '":Unit 1 -.Cycle 5'."',","

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The Cycle 5 core makes use of a low-leakage fuel management scheme, in which previously burned assemblies are placed on the core periphery. The majority of the fresh Batch 6 fuel is located throughout the interior of the core where they are mixed with previously burned fuel to minimize power peaking.

Initial criticality for Cycle 5 was declared at 04:04 on November 24, 1993.

Low Power Physics Testing began at 05:00 on November 24, 1998 and ended at 00:57 on November 25,1993. Power Ascension Testing began at 28:85 on November 27, 1993 and concluded at 12:00 on December 5, 1993.

The testing evolution is controlled by two procedures 72PY-9RX01 "Low Power Physics Testing" and 72PA-9ZZ07 "Reload Power Ascension Test."

The tests performed under the control of 72PY-9RX01 are:

AllRods Out (ARO), Hot Zero Power (HZP), Critical Boron Concentration Isothermal Temperature Coefficient Measurement Rod Swap Testing Inverse Boron Worth Measurement.

The tests performed under the control of 72PA-9ZZ07 are:

Radial Power Distribution - 20% Rated Thermal Power (RTP)

Radial Power Distribution - 70% RTP Axial Power Distribution - 70% RTP Radial Power Distribution - 100% RTP Axial Power Distribution - 100% RTP Hot Full Power, ARO, Critical Boron Concentration.

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Test Criteria The following acceptance criteria apply to each of the tests performed during Low Power Physics Testing and Power Ascension:

Critical Boron Concentration (HZP) g 100 ppm of predicted Isothermal Temperature Coefficient Measurement g 3 pcm/ F of predicted CEA 1bsting Reference Group g 10% of predicted

'II.st Group(s) g 15% or g 100 pcm of predicted

'Ibtal Worth g 10% of predicted Inverse Boron Worth g 15%

Radial Power Distribution - 20% ~ 10% of predicted Radial Power Distribution - 70% g 0.1 RPD units

< 0.05 RMS Peaking Factors - 70% g 10% of predicted Radial Power Distribution - 100% g 0.1 RPD units

< 0.05 RMS Peaking Factors - 100% g 10% of predicted Critical Boron Concentration (HFP) g60 ppm Low Power Physics Vesting AllRods Out (ARO) Critical Boron Concentration (CBC)

This test is performed by obtaining an RCS Boron Sample at equilibrium conditions near ARO (CEA Group 5 -130" W/D) and adjusting this concentration for the reactivity worth of withdrawing Group 6 to ARO.

The measured RCS concentration was 1557ppm which was adjusted to 1558 ppm. The Design HZP ARO CBC is 1656 ppm. This value was within the acceptance criteria.

Isothermal Temperature Coefficient (ITC)

This test is performed by raising and lowering the RCS Temperature and measuring the associated changes with Core Reactivity. The measured ITC with Group 5 at approximately 139" W/D was -1.28 pcm/'F. The prediction forDesign ITC was -1.32 pcm/ F and was corrected to test

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conditions. The corrected Design ITC was -1.37 pcm/ F. The measured ITC met the acceptance criteria and satisfied the surveillance requirement of Technical Specification 4.1.1.8 Rod Worth Measurements The Rod Swap Measurement method was utilized to test the worth of ALL Shutdown and Regulating CEA Groups. The basic technique associated with Rod Swap is measuring one Group through the Boration/

Dilution method (Reference Group) and then swapping it with each of the remaining Groups ('II.'st Groups). The results are summarized in the following table:

Measured Adjusted Measured Design Percent Test Group(s)

Position Position Worth Worth Difference Grp 5, SD 94.00 99.56 -610.8 -578.2 -5.33 A(20)

Grp 2,4 109.50 109.87 -667.7 -647.6 -3.01 D B(9) 109.50 110.24 -670.4 -645.0 -3. 9 SD A(16), SD 114.75 114.60 -692.6 -657.4 -5.09 B(19)

Grp 1 116.25 116.33 -700.8 -666.7 -4.88 SD B(10) 108.25 108.22 -659.1 -647.5 -1.76 D (8) 95.50 95.36 -584.7 -575.5 -1.58 SD B(6) 126,77 126,52 -744.1 -720.2 -8.20 SD A(21) 96.47 95.81 -587.5 -576.0 -1.96 D B(7) 126,02 125.88 -741,6 -720.8 -2.82 eference

-782.5 -778.0 -0,58 Group (Grp 3)

'Ibtal Worth -7441.8 -7212,9 -8.08 Alltest results met the acceptance criteria.

Inverse Boron Worth The Inverse Boron Worth (IBW) is determined by obtaining the measured worth of the CEA Reference Group (Group 3) from Rod Swap Testing and the change in Boron Concentration to get the Reference Group Diluted to the Lower Electrical Limit. The measured IBW was 125.28 ppm/%EX/K The design IBW was 123.8 ppm/%6K/K The acceptance criteria was met.

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Power Ascension Testing Flux Symmetry Verification - 20% RTP This test is performed by obtaining a flux map from the Fixed Incore Detector System and processing this information with CECOR. The output from CECOR yields a full core map of Relative Power Density.

The maximum deviation obtained was 8.626% and the minimum deviation was'-5.455%. The acceptance criteria for this test was met.

Core Power Distribution Verification - 70% RTP This test is performed by obtaining a flux map from the Fixed Incore Detector System and processing this information with CECOR. The output from CECOR yields a full core map of Relative Power Density.

The maximum deviation obtained was 0.0587. The Root Mean Square (RMS) deviation was -0.0159, Allacceptance criteria for the Radial Power Distribution were met.

The second portion of testing at 70% includes the verification of the Axial Power Distribution. This involves a comparison of the Axial Shape through 51 nodes with predicted, and a RMS evaluation. Both of these measurements were found to exceed the acceptance criteria. The Axial Deviation was -0.1055 (g 0.1) and the RMS was 0.0628 (~0.05). ARer discussions with ABB/CE it was determined that the Predictions provided did not model the End of Cycle (EOC) 4 adequately. At EOC-4 there was an extensive coastdown performed involving both power reductions and temperature reductions. The model used to predict Cycle 5 values did not include this coastdown.

ABB/CE delivered new predictions for 70% RTP and 98% RTP which properly modelled EOC-4. The data collected at 70% RTP was re-evaluated. The maximum deviation on the Axial Power Distribution was

-0.0769 and the RMS was 0.0233. All acceptance criteria for this measurement were met.

Peaking factor comparisons (percent difference from predictions) were as follows: Fzy Oe359%> Fr Oo'208%< Fz Ool10%> and Fq 1o596%o AO parameters met the acceptance criteria.

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.'age Core Power Distribution Verification - 100% RTP 7

This test is performed by obtaining a flux map from the Fixed Incore of 8 Detector System and processing this information with CECOR. The output from CECOR yields a full core map of Relative Power Density.

The maximum deviation obtained was 0.0697 and the minimum deviation was 0.0149. All acceptance criteria for this measurement were met.

The second portion of testing at 98% RTP includes the verification of the Axial Power Distribution. This involves a comparison of the Axial Shape through 51 nodes with predicted, and a Root Mean Square evaluation.

The Axial Deviation was -0.0901 Q 0.1) and the RMS was 0.0315 (g0.05).

All acceptance criteria for this measurement were met.

Peaking factor comparisons (percent difference from predictions) were as follows: F~ -1.147%, Fr -0.072%, F~ 1.746%, and F< -1.231%. All parameters met the acceptance criteria.

Critical Boron Concentration - 100% RTP This test is performed at ARO HFP equilibrium conditions. A RCS Sample is taken and corrected to the nominal conditions which the prediction was calculated. The measured RCS concentration was 1019 ppm which was adjusted to 1013 ppm. The Design HZP ARO CBC was 1052 ppm. The measured value was within the acceptance criteria.

-PVNGS Unit 1 "Cycle 5

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'"'"'age Cycle 5 Core Load Map 8 of 8 T S R P N M L K I H G F E D C B A 241 240 17 PIE420 PIE429 PIE012 PIE003 PIE009 PIE412 PIE427 P2E110 PIE114 PIE018 PIG001 PIF521 PIC111 PIG004 PIE021 PIE107 P2E105 221 220 219 218 217 216 215 214 2D 211 15 PIE209 PI Fill PIG215 PIF119 PIE019 PIC219 PIF122 PIG208 PIF112 PIE210 210 206 208 201 197 196 P2E114 PIG103 PIF401 PIG346 PIF512 PIC327 PIF501 PIC317 PIF416 PIGI06 P2E109 195 194 191 189 188 187 186 183 184 183 182 181 PIEIO9 PIF114 PIC302 PIG340 PIF307 PIG326 PIF517 PIG341 PIF403 PIG214 PIF109 PIE110

~ 180 179 178 PIFA23 PIE001 PIG218 176 174 PIC333 PI F201 PIC322 171 170 169 PIC323 PIF531 PIC330 PIF203 167 166 165 PIC217 PIE022 PIFA15 11 ~ 163 162 161 PIE419 PIC008 PIFI23 PIC321 159 158 PIC311 156 PIC305 154 PIC304 152 151 150 149 147 PIC343 PIF530 PIG314 PI F120 PIC003 PIFA28

~ 146 145 144 143 142 141 140 139 138 137 136 135 D4 133 132 131 PIE024 PIF518 PIC209 PIFSIS PIC328 PIFS32 PIC303 PIF121 PIF124 PIF103 PIC307 PIF520 PIC33S PIF511 PIC211 PIF522

~ 129 128 127 126 PIE014 PIC107 PIE011 PIG331 124 123 PIG318 PIF409 121 120 119 118 117 116 115 PIB122 PIFIOI PIF412 PIG332 PIF308 PIG329 PIEOIS II4 ID

~ 112 111 110 PIEOIO PIF503 PIC221 108 107 106 106 104 103 102 101 100 99 PIG345 PIFS02 PIC316 PIFI06 PIF116 PIF102 PIC301 PIF519 PIG347 PIF514

~ 94 93 91 PIE417 PIC007 PIF118 PIC319 PIFSI3 PIC339 PIF301 PIC310 PIF413 PIC312 PIF302 PIC334 81 PI F105 PIE430

~ 78 77 76 PIE422 PIE017 PIC216

'74 69 PIF202 PIG336 PIF523 PIG324 PIFSIO PIG325 PIF204 PIC337 PIF411 62 PIFA02 61 60 82 51 50 49 48 47 PIE112 PIF113 PIC212 PIC342 PIF516 PIF305 PIC338 PIF504 PIC315 PIF406 PIG206 PIFI07 PIE106 42 41 39 38 37 36 P2E107 PIG108 PIF41S PIC320 PIG344 PIF527 PIC313 PIF410 PIC201 PIRM1 PIC102 P2E112 31 28 27 25 24 21 20 19 PIE211 PIFIIS PIG222 PIF104 PIG213 PIE005 PIG220 PIF117 PIG210 PIF110 PIGIIO PIE208 18 17 16 15 14 13 12 10 9 P2EIII PIE116 PIE020 PIC005 PIF528 PIG112 PIF524 PIG002 PIE016 PIE118 P2E115

'7 6 5 3 2 I PIE421 PIE432 PIE006 PIE013 PIE007 PIE431 PIE418

~ - Neutron Source

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