ML18151A718

Rev 0 to Technical Rept NE-978, Surry Unit 1 Cycle 12 Core Performance Rept.

ML18151A718
Person / Time
Site:	Surry
Issue date:	04/15/1994
From:	Brookmire J, Chapman D, Laroe C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18151A719	List: ML18151A718 ML18153A941
References
NE-978, NE-978-R, NE-978-R00, NUDOCS 9405190110
Download: ML18151A718 (58)

Text

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I Surry

. Unit 1 Cycle 12 I

Core I Peiformance 19 Report I Nuclear Analysis and Fuel I Nuclear Engineering Services I April 1994 I

I 9405190110 940509

• VIRGINIA POWER PDR ADOCK 05000280 p PDR

I I TECHNICAL REPORT NE-978 - Rev. 0 f

I SURRY UNIT 1, CYCLE 12 I CORE PERFORMANCE REPORT I

I \UCLEAR ANALYSIS AND FUEL I NUCLEAR ENGINEERING SERVICES VIRGINIA POWER April, 1994 I

le .~ I" PREPARED BY ,f:l,,,, ;j}j ,. ,.,./JAPR 1'/

D. M. Chapman Date I

REVIEWED B Y : ~ ~ ~

I ~- LaRoe Date

__-,1 tl ,*

q.,s-11 I REVIEWED BY: / . ~

T. A. Brookmire Date I 'j:M\

Date I APPROVED I

QA Category: Nuclear Safety Related I

.. Keywords: S1Cl2. CPR, Core I

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,. TABLE OF CONTENTS PAGE I Table or Contents 1 I List of Tables . 2 List of Figures. . . 3 I Section 1 Introduction and Summary. 5 I Section 2 Section 3 Burnup. . . . . . . . . . . . . . . . 13 Reactivity Depletion . . . . . . . . . . . . . . . 23 I Section 4 Power Distribution . . . . . . . . . . . . . . 25 Section 5 Primary Coolant Activity . . . . . . . . . . . . . 47 I Section 6 Conclusions . . . . . . . . . . . . . . . . . . . 55 Section 7 References.

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1* ~E-978 S1Cl2 Core Performance Report Page 1 of 58

I LIST OF TABLES

ABLE TITLE PAGE 4.1 Summary of Flux Maps for Routine Operation . . . . . . . . . 30 I

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SE-978 S1Cl2 Core Performance Report Page 2 of 58 i

I I LIST OF FIGURES

{' PAGE

?IGURE TITLE I

1. 1 Core Loading Map . . . . . .......... 8 I 1. 2 Burnable Poison and Source Assembly Locations. 9

1. 3 ~ovable Detector Locations 10

1. 4 Control Rod Locations. 11

2. 1 Cycle Burnup History 15

') ')

jonthly Average Load Factors 16 I 2.3 Assemblywise Accumulated Burnup: jeasured and Predicted 17 I 2.4 Assemblywise Accumulated Burnup: Comparison of

,. ~easured and Predicted . 18 2.SA Sub-Batch Burnup Sharing 19 2.5B Sub-Batch Burnup Sharing 20 I 2.SC Sub-Batch Burnup Sharing 3.1 Critical Boron Concentration versus Burnup (HFP,ARO) 21 24 I 4.1 Assemblywise Power Distribution - Sl-12-05 31 4.2 Assemblywise Power Distribution - Sl-12-14 32 1* 4.3 Assemblywise Power Distribution - Sl-12-23 33 I 4.4A Hot Channel Factor Normalized Operating Envelope (Applicable Through May 1992) . . . . . . . . . . . . . . . . 34 4.4B Hot Channel Factor Normalized Operating Envelope I (Applicable After May 1992) 35 4.5 Heat Flux Hot Channel Factor, Fq(Z) - Sl-12-05 36

,I 4.6 Heat Flux Hot Channel Factor, Fq(Z) - Sl-12-14 37 I 4. 7 Heat Flux Hot Channel Factor, Fq(Z) - Sl-12-23 38

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LIST OF FIGURES (CONT'D)

FIGURE TITLE PAGE 4.8 Maximum Heat Flux Hot Channel Factor, Fq(Z)*P, vs.

Axial Position . . . . . . . . . . . . . . . . 39 4.9 Maximum Heat Flux Hot Channel Factor, Fq(Z), vs. Burnup 40 4 .10 Maximum Enthalpy Rise Hot Channel Factor, F-delta-H vs.

Burnup 41 I

4.11 Target Delta Flux versus Burnup 42 I 4 .12 Core Average Axial Power Distribution 4.13 Core Average Axial Power Distribution 4.14 Core Average Axial Power Distribution

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Sl-12-05 Sl-12-14 Sl-12-23 43 44 45

.s 4.15 Core Average Axial Peaking Factor vs. Burnup 46 5.1 Dose Equivalent I-131 vs. Time 51 5.2 I-131/I-133 Activity Ratio vs. Time 52 5.3 Measured RCS Xenon-133 vs. Time 53 I 5.4 Measured RCS Iodine-131 vs. Time 54 I

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, Sect:ion 1 I I~TRODUCTIO~ A~D

SUMMARY

I I On i:1nuary --, :?  ::.994, Surry Unit 1 completed Cycle 12. Since the i~it:ial criticality of Cycle 12 on May 1, 1992, the reactor core produced I Jpproximat:ely 1.1623 x 10 3 MBTU (19,587 Megawat:t: days per met:ric t:on of I ~ont:ained uranium). The purpose of this report is to present an analysis of t:he core performance for rout:ine operation during Cycle 12. The

• t* physics tests t:hat :.:ere performed during the st:artup of this cycle were

• ~overed in t:he Surry Unit 1 Cycle 12 Startup Physics Test Report: 1 and, Jl9herefore, will not be included here.

I Surry Unit 1 began a power only coastdown on November 4, 1993, at which I ~ime the burnup was approximat:ely 17,601 MWD/MTU. The coastdown accounted for an additional core burnup of 1,986 MWD/MTU from the end of full power I react:ivity.

i The Cycle 12 core consisted of eight sub-batches of fuel: two fresh I batches (batches 14A and l4B); four once-burned batches, two from Cycle 11 (bat:ches 13A and l3B), one from Cycle 8 (batch 10) and one from Cycle I 10 (part: of batch Sl/12B); and three twice-burned batches, all from Cycle I 11 (bat:ches l'.:'.A, part of l2B, and S2/12A). The Surry 1 Cycle 12 core

~oading map specifying the fuel batch identification and fuel assembly 1*~ocat:1.ons is shown in Figure 1.1. The burnable poison locations and I ~E-978 S1Cl2 Core Performance Report: Page 5 of 58

I source assemoly locations are shown in Figure 1. 2. ~ovable detector locations that were available during Cycle 12 are shown in Figure 1.3.

Controi rod locations are shown in Figure 1.4.

I Routine performance core follow indicators.

involves These are the analysis burnup of four distribution, principal reactivity

,,

depletion, power distribution, and primary coolant activity. The core I

burnup distribution is followed to verify both burnup symmetry and proper batch burnup sharing, ::hereby ensuring that the fuel held over for the I next cycle .;ill be compatible with the new fuel that is Reactivity depletion is monitored to detect the existence of any abnormal inserted.

I reactivity behavior, to determine if the core is depleting as designed, and to indicate the cycle burnup where coastdown operation will begin.

Core power distribution follow includes the monitoring of nuclear hot el channel factors to verify that they are within the Technical I

Specification 2 limits, thereby ensuring that adequate margins for linear power density and critical heat flux thermal limits are maintained. t Lastly, as part of normal core follow, the primary coolant activity is monitored to assess the status of the fuel cladding integrity and to I

compare the concentration of dose equivalent iodine-131 in the reactor i coolant with Specifications 2.

the limits specified by the Surry Technical I

I Each of the four performance indicators is discussed in detail for the I

Surry Cnit 1 Cycle 12 core in the body of this report. The results are summarized below: ..

~E-978 S1C12 Core Performance Report Page 6 of 58 I

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1. Burnup - The burnup tilt (deviation from quadrant symmetry) on the core was no greater than +/-0.41% with the burnup accumulation in each batch deviating from design prediction by no more than +/-2.11%.

I 2. Reactivity Depletion - The critical boron concentration, I used to monitor reactivity depletion, was consistently within +/-0.48% tK/K of the design prediction which is within the +/-1% tK/K margin allowed by I

I Section 4.10 of the Technical Specifications.

3. Power Distribution - Incore flux maps taken each month I indicated that the assemblywise radial power distributions deviated from the design predictions by a maximum average difference of 2.6%. All hot channel factors met their respective Technical Specification limits.

I 4. Primary Coolant Activity The average dose equivalent iodine-131 activity level in the primary coolant during Cycle 12 was le approximately 0.00628 µCi/gm.

operating limit for This corresponds to less than 1% of the the concentration of radioiodine in the primary I coolant. Radioiodine analysis indicated that there were fuel rod defects I in Cycle 12.

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I NE-978 S1Cl2 Core Performance Report Page 7 of 58

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R H Figure 1.1 SURRY UNIT 1 - CYCLE 12 CORE LOADING MAP J

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128 I F E D C B A

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4H9 I 2G3 I 1, 15 I

I FUEL ASSEHBLY DESIGN PARAHETERS I

INITIAL ENRICHHENT (W/0 U-235) l52/12A 3.79 I 10 3.60 12A 3.80 l2B 3.99 SUB-BATCH 13A 3.80 138 4.01 14A 3.81 148 4.02 I

BURHUP AT BOC 12

( HWD/HTUJ ASSEHBLY TYPE 211435 15xl5 17757 15Xl5 35617 15Xl5 32362 l5Xl5 17977 15Xl5 16922 15Xl5 lSXlS 0

lSXlS 0

I HUHBER OF ASSEHBLIES FUEL RODS PER ASSEHBL' 1

za4 I l

204 16 204 24 Z'.04*

24 204 28 204 35 204 28 204 I  !

• ONE ASSEHBLY (4G7J HAD ONE FUEL ROD REPLACED WITH A SOLID STAINLESS STEEL ROD DUl!IHG A RECONSTITUTION PROGRAH.

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\E-978 S1Cl2 Core Performance Report Page 8 of 58 I

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Section 2 BURNUP I

I The Surry Unit 1 Cycle 12 burnup history is graphically depicted in Figure 2.1. Surry 1 Cycle 12 achieved a cycle burnup of 19,587 MWD/MTU.

I As shown in Figure 2.2, the average load factor for Cycle 12 was 92.3%

~hen referenced to rated thermal power (2441 MW(t)). Unit 1 performed a I ?OWer coastdown starting on November 4, 1993 until shutdown for refueling 0n January 22, 1994.

I Radial (X-Y) burnup distribution maps show how the core burnup is II..... shared among the various fuel assemblies, and thereby allow a detailed

~ burnup distribution analysis. The TOTE 3 computer code is used to I calculate these assemblywise burnups. Figure 2.3 is a radial burnup distribution map in which the assemblywise burnup accumulation of the core I ~t the end of Cycle 12 operation is given. For comparison purposes, the design values are also given. Figure 2.4 is a radial burnup distribution I map in which the percentage difference comparison of measured and I predicted assemblywise operation is given.

burnup accumulation at the end of Cycle As can be seen from this figure, the accumulated 12

'*1 assembly burnups were within +/-4.14% of the predicted values. In addition, deviation from quadrant symmetry in the core throughout the cycle was no greater than +/-0.41%.

I The burnup sharing on a batch basis is monitored to verify that the

.. . core is operating as designed and to enable accurate end-of-cycle batch I NE-978 S1Cl2 Core Performance Report Page 13 of 58

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.:urnuo predictions to be made for use in reload fuel design studies.

~ate~ definitions are given in Figure 1.1. As seen in Figures 2.SA, 2.SB,

~~d 2.5C, the batch burnup sharing for Surry 1 Cycle 12 followed design

?redictions closely with no batch deviating from prediction by more than

_,., , .. o,,

_..;. * .I,. ... 0. The batch burnup sharing deviations in conjunction with reasonable agreement between actual and predicted assemblywise burnups, anci symmetric core burnups indicate that the Cycle 12 core did deplete G.S designed.

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I 1* Figure 1.2 l' SURRY UNIT 1 - CYCLE 12 BURNABLE POISON AND SOURCE ASSEMBLY LOCATIONS p H H J H G F E D C A I

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- - - , - - - I SP I I SP 1 - - - - - , - - - -

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3 BURNABLE POISON ROD CLUSTER 5 EURHABLE POISON 12 BURNABLE POISON 16 BURNABLE POISON ROD ROD ROD CLUSTER CLUSTER CLUSTER I

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- HUHBER OF BP RODS or SECONDARY SOURCE

- BP ASS£1tBLY ID IO I

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Figure 1.3 SURRY UNIT 1 - CYCLE 12 MOVABLE DETECTOR LOCATIONS ,.,

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t Figure 1.4 SURRY UNIT 1 - CYCLE 12 CONTROL ROD LOCATIONS I R p N H L K J H 180° I

G F E D C B A I Loop C Outlet I I A I

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.I ~E-978 S1Cl2 Core Performance Report Page 11 of 58

I Figure 2.1 SURRY UNIT 1 - CYCLE 12 CYCLE BURNUP HISTORY I I C-J _r1_ I -- - _lJ _ _Ll_

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t Figure 2.3 SURRY UNIT 1 - CYCLE 12 ASSEMBLYWISE ACCUMULATED BURNUP MEASURED AND PREDICTED (GWD/MTU)

I R p H 11 J H G F E D C B A I 40.57/ 44.98/ 41.471 I HEASURED I I I 40.69/ 44.93/ 40.691 I 41.971 32.09/ 21.04/ 35.461 21.011 32.061 41.801 I 41.781 31.981 20.731 35.051 20.731 31.981 41.781 I PREDICTED I 2

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] I 45.lll 21.131 24.281 40.031 24.041 39.171 24.491 21.741 45.171 3 I 45.741 21.061 24.241 39.751 24.181 39.751 24.241 21.061 45.741 I 45.831 34.181 24.341 41.93/ 24.59/ 54.13/ 23.821 41.651 24.951 34.251 45.251 4 I 45.731 34.071 24.821 42.001 24.23/ 54.261 24.23/ 42.001 24.821 34.071 45.731 I  ;

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I \E-978 S1Cl2 Core Performance Report Page 17 of 58

I I

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Figure 2.4 SURRY UNIT 1 - CYCLE 12 ASSEMBLYWISE ACCUMULATED BURNUP COMPARISON OF MEASURED AND PREDICTED (GWD/MTU)

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10 I 40.431 20.741 39.641 24.221 51.501 24.931 40.941 38.571 40.681 24.201 48.861 23.931 39.451 20.731 40.731 I -0.111 0.051 -0.331 -o.061 -o.251 -0.391 -1.421 -0.821 -2.041 -3.321 -1.201 -1.281 -o.821 0.001 0.031 I 31.751 23.831 41.511 26.121 42.311 24.311 41.411 24.631 41.791 25.601 41.321 24.221 32.671 9

11

• 1 I -o.811 -1.671 -1.111 o.901 -0.041 -2.911 -2.211 -1.611 -1.271 -1.091 -1.561 -0.091 2.071 11 12 I 41.711 21.121 24.941 41.521 25.481 50.401 24.241 51.311 25.721 40.901 24.981 21.301 41.451 I -0.121 0.291 o.461 o.621 -1.541 -2.391 -1.331 -0.641 -o.591 -0.861 o.631 1.141 -o.761 I 45.021 34.361 24.901 41.441 23.541 53.271 23.811 41.581 24.601 34.701 45.731 I -1.551 o.871 o.321 -1.331 -2.861 -1.821 -1.741 -0.991 -o.871 1.841 -0.011 11 lZ el 13 14 I 45.131 21.101 24.271 38.791 23.401 39.331 23.261 22.921 45.451 I -1.321 3.021 0.131 -2.411 -3.221 -1.051 -4.041 -1.211 -0.641 I 41.521 32.651 20.741 34.451 19.881 31.101 41.021 I ARITHl1ETIC AVG I IPCT DIFF = -0.651 13 14 I

I -0.611 2.101 0.031 -1.691 -4.141 -2.741 -1.811 15 I STANDARD DEV I I = o.87 I 40.261 44.301 40.041 I -1.011 -1.391 -1.611 I AVG ABS PCT I I D !FF = l. 13 I 15 I

R p 11 SUB-BATCH SHARING K J H G F E D C A I

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.1

~E-978 S1Cl2 Core Performance Report Page 18 of 58

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I ~E-978 S1Cl2 Core Performance Report Page 21 of 57

• '-

?

I I Section 3

{'

I REACTIVITY DEPLETION I

I The primary coolant critical boron concentration is monitored for the purposes of following core reactivity and to identify any anomalous I reactivity behavior. The FOLOW" computer code was used to normalize "actual" critical boron concentration measurements to design conditions I taking i:ito consideration control rod position, xenon concentration, I moderator temperature, and power level. The normalized critical boron concentration versus burnup curve for the Surry 1 Cycle 12 core is shown

,le in Figure 3. 1. The maximum difference between measured and predicted critical boron concentrations was 55. 3 ppm. The largest reactivity I anomaly was +/-0 .478% !:,.K/K which is within the +/-1% !:,.K/K criterion for

~ reactivity anomalies set forth in Section 4.10 of the Technical Specifications. In conclusion, the trend indicated by the critical boron I concentration verifies that the Cycle 12 core depleted as expected without any reactivity abnormalities.

I I

I I

..

I NE-978 SlC12 Core Performance Report Page 23 of 58

I

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Figure 3.1 SURRY UNIT 1 - CYCLE 12 CRITICAL BORON CONCENTRATION vs. BURNUP (HFP,ARO)

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..

\E-978 S1C12 Core Performance Report Page 24 of 58 I

I I Section 4

{' POWER DISTRIBUTION I

Analysis of core power distribution data on a routine basis is I necessary to verify that the hot channel factors are within the Technical I Specification limits and to ensure that the reactor is operating without any c1bnormal conditions which could cause an " uneven 11 burnup I distribution. Three-dimensional core power distributions are determined from movable detector flux map measurements using the INCORE 5 computer I program. A summary of all full core flux maps taken for Surry l Cycle I 12 is provided in Table 4.1, excluding the initial power ascension flux maps. Power distribution maps were generally taken at monthly intervals le with additional maps taken as needed.

I Radial (X-Y) core power distributions for a representative series of

~, incore flux maps are given in Figures 4.1, 4.2, and 4.3. Figure 4.1 shows a power distribution map that was taken early in cycle life. Figure 4.2 I shows a power distribution map that was taken near the mid-cycle burnup.

Figure 4.3 shows a map that was taken near the end of Cycle 12. The I maximum relative assembly power difference between measured and predicted I for these maps was 7.7% and the cycle maximum average percent difference was 2.6%. In addition, as indicated by the INCORE tilt factors, the power I distributions were essentially symmetric for each case.

I

.. ::if An important aspect of core power distribution follow is the monitoring nuclear hot channel factors. Verification that these factors are I ~E-978 SlC12 Core Performance Report Page 25 of 58

I

,I

..

within Technical Specification limits ensures that linear power density and critical heat flux limits will not be violated, thereby providing adequate thermal margin and maintaining fuel cladding integrity. Surry Technical Specification 3.12 limited the axially dependent heat flux hot I

channel factor, Fq(Z), to 2.32 x K(Z), where K(Z) is the hot channel factor normalized operating envelope. During Cycle 12, there was a I revision to Surry Technical Specification 3.12 which modified the K(Z) envelope 5

• Figure 4.4A shows a plot of the K(Z) curve applicable for the I

maps up to Map 05. Figure 4.4B shows a plot of the K(Z) curve applicable I for Maps 06 through the end of Cycle 12.

I The axially dependent heat flux hot channel factors, Fq(Z),

representative set of flux maps are given in Figures 4.5, 4.6, and 4.7.

for a I

Throughout Cycle 12, the measured values of Fq(Z) were within the el Technical Specification limit. A summary of the maximum values axially-dependent heat flux hot channel factors measured during Cycle 12 of I

is given in Figure 4.8. The minimum margin to the Fq(Z) limit was 18.55%.

It should be noted that the graphical representation of Figure 4.8 does not demonstrate the Fq(Z) limit change. The Fq(Z) limit applicable over I the majority of the cycle is shown. Figure 4.9 shows the maximum values for the heat flux hot channel factor measured during Cycle 12.

I I

The value of the enthalpy rise hot channel factor, F-delta-H, which is the ratio of the integral of the power along the rod with the highest I

integrated power to that of the average rod, is routinely followed. The I

Technical Specification limit for this parameter is set such that the departure from nucleate boiling ratio (DNBR) limit will not be violated. ..

~E-978 S1Cl2 Core Performance Report Page 26 of 58 I

I

~: Additionally, the F-delta-H limit ensures that the value of this parameter

~ used in the LOCA-ECCS analysis is not exceeded during normal operation.

Surry Technical Specification 3.12 was revised in June, 1992 to increase I the F-delta-H limit to 1.56(1+0.3(1-P)), where 1.56 is the F-delta-H at rated thermal power 5

• The measured F-delta-H without any uncertainty I applied is compared directly to this limit.

I In Table 4.1, flux maps through Map 05 have 4% uncertainty included

~ to the listed F-delta-H values and were compared to the 1.55 limit. The flux maps after Map 05 have no uncertainty applied and were compared to I the 1.56 limit. A summary of the maximum values for the enthalpy rise hot channel factor measured during Cycle 12 is given in Figure 4.10. This I figure reflects the 100% power Technical Specification limit, the change

~ i n the 100% power Technical Specification limit and measured F-delta-H values that have the appropriate uncertainty applied. (The limit curve I does not reflect the higher limit for maps taken at power levels less than 100%.) The change in the application of measurement uncertainty I associated with the Technical Specification change explains the sudden I drop in the measured F-delta-H values at beginning of cycle in Figure 4.10. As can be seen from this figure, the minimum margin to the limit I was 4.84% for Cycle 12.

I The target delta flux* is the delta flux which would occur at

~ conditions of full power, all rods out, and equilibrium xenon. The delta flux is measured with the core at or near these conditions and the target I Pt-Pb

~* Oelta Flux= X 100 where Pt= power in top of core (MW(t))

2441 Pb= power in bottom of core (MW(t))

I NE-978 S1Cl2 Core Performance Report Page 27 of 58

I I

..

delta flux is established at this measured point. Since the target delta flux varies as a function of burnup, the target value is updated monthly.

By maintaining the value of delta flux relatively constant, adverse axial power shapes due to xenon redistribution are avoided. This target I delta-flux was also used to establish the operational axial flux difference bands while under CAOC.

I I

The plot of the target delta flux versus burnup, given in Figure 4.11, shows the value of this parameter to have been approximately 2.5% at the I beginning of Cycle 12, decreasing to -2.8% near the middle of Cycle 12, and leveling off at -3.5% at the end of Cycle 12 before increasing during I

the power coastdown. This axial power shift can also be observed in the I corresponding core average axial power distribution for a representative series of maps given in Figures 4.12 through 4.14. In Map Sl-12-05 el (Figure 4.12), taken at 178 MWD/MTU, the axial power distribution had a I shape peaked toward the middle of the core with an axial peaking factor (F-Z) of 1.209. In Map Sl-12-14 (Figure 4.13), taken at approximately I

9,266 MWD/MTU, the axial power distribution peaked slightly toward the I

bottom of the core with an axial peaking factor of 1.148. Finally, in Map Sl-12-23 (Figure 4.14), taken at 16,789 MWD/MTU, the axial peaking I factor Sl-12-14.

was 1. 151, with an axial power distribution similar to The history of F-Z during the cycle can be seen more clearly Map I

in a plot of F-Z versus burnup given in Figure 4.15. I I

In conclusion, the Surry 1 Cycle 12 core performed satisfactorily with power distribution analyses verifying that design predictions were ..

~E-978 SlC12 Core Performance Report Page 28 of 58 I

I I accurate and that: the values of the Fq(Z) and F-delta-H hot channel

{' factors were within the limits of the Technical Specifications.

I I

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!1

'

le I

I I

I

,,

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• • I NE-978 S1Cl2 Core Performance Report Page 29 of 58

I Table 4.1 SURRY UNIT 1 - CYCLE 12

SUMMARY

OF FLUX MAPS FDR ROUTINE OPERATION I I l F-DHCNJ HOT 2 I 3 I I I I

I I BURN I BANK F-QCZJ HOT ICORE FCZJ CORE I AXIAL I NO.I IHAPI IHO. I I

I I_I I

I DATE I

UP lt\lD/

HTU I

I_ _ I I

I D

PIIR I STEPS CZJ I I

CHANNEL FACTOR I ASSYIPINIAXIAL I I IPOINTIF-QCZJ CHNL. FACTOR IASSYIPIN IHAX I

IF-DHCNJIPOINT I 1_ _ 1_1 _ _ 1_ _ 1 _ 1 _ 1 _ _ 1_ _ 1_ _ 1_ _ 1_1 _ _ 1_1 I

I TUT I

I OFF I IF I I SET ITHINI I.AXIAL I FCZJI HAX ILOCI CZ> IILESI I I I I

I 5 105-11-921 178 100.01 220 L05 OKI 30 I 1.866 L051 DK I 1.475 I 30 ll.20911.0161 NWI 2.6921 46 I 6 I 06-10-921 I 7 107-10-921 I 8 108-10-921 I 9 109-14-921 110 110-14-921 1151 2141 3193 4242 5280 99.931 224 100.01 221 100.01 225 99.1181 225 99.9111 224 E03 E03 E03 FU LlD ICI 25 I 1.863 ICI 26 I 1.840 ICI 25 I 1.801 Hll 32 I 1.767 IHI 41 I 1.759 E031 IC I 1.413 I 30 11.20011.0121 NWI 2.Z411 4&

E031 IC I 1.404 I 30 ll.19011.0lGI NWI 1.7981 4&

LlOI GH I 1.408 I 30 ll.17411.0071 Nlfl 1.3261 411 LlOI GH I 1.410 I 30 I Ll60ll.0061 NEI 0.65el ft7 LlOI IH I 1.411 I 37 IL14111l.0061 NEI -0.2831 4&

I LIOI IH I 1.415 I 41 ll.14111.0051 NEI -0.76111 4&

I Ill 111-12-921 6244 99.941 224 LlO IHl42&43 1.763 I 12 I 12-07-921 7105 100 .11 224 LIO IHI 43 1.771 LlOI IH I 1.418 I 42 ll.l4Dll.0041 NWI -1.4461 47 113 IOl-13-931 8260 99.921 224 LlO IHI 45 l.765 LIOI IH I 1.417 I 45 ll.13511.0041 NWI -1.6191 47 114 102-15-931 9266 99.901 224 LlO IHI 4& 1.784 LlOI IH I 1.418 47 ll.14811.0021 NIii -2.7771 47 115 103-15-931 10112 99.921 224 LlO LGI 46 1.784 LlOI LG I 1.421 411 ll.14611.0031 NWI -2.6941 47 116 104-19-931 112110 100.01 224 LlD LGI 47 1.795 LlOI LG I 1.423 48 ll.15311.0021 NWI -3.ZZZI 411 117 105-19-931 118 I0&-18-931 119 107-16-931 120 108-11-931 I 21 I 011-31-931 12277 13209 14214 15060 15417 100.11 224 100.01 223 99.921 222 99.941 222 72.601 172 LlO LID F05 F05 LlO LGI 47 LGI 47 IDI 52 IDI 52 LGI 411 1.799 1.795 1.794 1.7112 1.7112 LIDI LG I 1.422 llOI LG-I 1.423 LIOI LG I 1.419 LlOI LG I 1.410 LIOI DF I 1.416 48 ll.15&11.0021 NWI -3.5741 46 52 ll.15411.0031 NWI -3.5441 47 52 ll.l&Oll.0021 NWI -2.7681 47 52 ll.16311.0041 NIii -3.4911 47 52 ll.16011.0071 NIii -5.6761 OWi I

122 109-15-931 15907 99.981 223 F05 JDI 52 1.763 LIOI LG I 1.401 52 ll.16111.0091 NIii -3.4551 42 I 23 110-11-931 I 24 111-10-931 I 25 111-22-93 I I 26 112-16-931 16789 177811 111126 18809 99.971 223&2241 Kll 95.341 223 87.321 225 73.871 223 I F05 I LIO I LIO FLI 52 JDI 52 LFI 10 LFI 09 1.756 1.631 1.762 1.867 LIOI LF I 1.397 LlOI LF I 1.396 LIOI LF I 1.399 LlOI LF I 1.402 52 11.15111.0041 Nwl -2.a1z1 :sa 52 ll.10911.0061 NIii -0.11661 43 10 ll.16411.0l-OI NWI 3.59111 44 09 ll.22211.0111 NWI 6.MZI 46 I

127 IOl-05-941 19263 62.671 218 I K09 JDI 09 1.991 LIO I LF I 1.407 09 ll.28711.0121 NMI 10.4151 4Z I_I _ _ _ I __I I_ _ _ I_ _ _ _ _ _ _ I __ I_ _ _ _ I _ _ I_ _ I_I _ _I _

NOTES: HOT SPOT LOCATIONS ARE SPECIFIED BY GIVING ASSEKBLY LOCATIONS CE.G. HOB IS TIE CENTER-OF-CORE ASSEIBLY),

FOLLOWED IY THE PIN LOCATION (DENOTED BY THE "T" COORDINATE WITH THE FIFTEEN ROWS OF FUEL RODS LETTERED A THROUGH RAND THE *x* COORDINATE DESIGNATED IN A SIMILAR KANNER).

IN TIE *z- DIRECTION THE CORE IS DIVIDED INTO 61 AXIAL POINTS STARTING FROII THE TOP OF THE CORE.

1. F-QCZJ INCLUDES A TOTAL UNCERTAINTY OF 1.08.

I

2. F-DHCNJ INCLUDES AH UNCERTAINTY OF 1.04 FOR KAPS 06 THROUGH 27.

NAP 05. THERE IS NO UNCERTAINTY APPLIED TD F-DH(NJ FDR

3. CORE TILT - QUADRANT POWER TILT AS DEFINED BY THE INCDRE CODE.

I I

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..

~E-978 SlC12 Core Performance Report Page 30 of 58 I

I Figure 4.1 SURRY UNIT 1 - CYCLE 12 ASSEMBLYWISE POWER DISTRIBUTION Sl-12-05 R p H K J H G F E D C B A I PREDICTED tlEASIJRED

• PCT DIFFERENCE.

0.33 0.37

. 0.35. 0.39. 0.35.

5.1. 5.0. 3.3

• 0.34 PREDICTED 11EASURED

. PCT DIFFERENCE.

1 0.37 0.76 l.14 l.04 1.15 0.76 0.37 I 0.41

. o.:sa . o.79 . 1.18

• 1.01

• 1.11

• a.n . o.3a

• 4.6. 3.9. 3.2. 2.9. l.7. 0.6. 2.1.

l.13 1.23 1.20 l.17 l.20 1.24 l.13 0.40 2

. 0.42. 1.15. 1.26. 1.24. l.18. l.21. 1.24. 1.16. 0.42. 3 I . 0.48 4.1.

0.93 2.1.

1.20 2.2.

1.25 3.3.

l.ll 0.7.

0.94 0.3.

1.11 0.6.

l.25 3.0.

1.20

. 0.41 . 0.95

• 1.21

• 1.28 . 1.14 . 0.% . 1.11 . 1.26

• 1.22

• 0.95

• 0.41

• 2.4. 2.1

• 0.6. 2.1. 2.7. 2.0. 0.1. l . l . l.3. 1.4. 1.6.

4.5

• 0.93 0.48 I 0.37 1.13 1.20 1.33 1.22 1.03 1.13 1.03 l.O. l.O. 1.7. 2.8. 2.4. 3.0. 2.9. 2.0. 1.2. 0.7. *l.2. 0.2. 1.9.

0.76 1.23 1.25 1.22 1.23 1.16 1.25 1.16 1.22

. 0.37. 1.14. 1.22. 1.37. 1.25. 1.06. 1.16. l.05. 1.24. 1.34. 1.19. 1.13. 0.37.

1.23 1.33 1.22 1.20 1.25 1.13 1.24 0.37 0.76 5

. 0.77. 1.24. 1.27. 1.26. 1.26. I.la. 1.28. 1.17. 1.25. 1.22. 1.23. 1.21. 0.75.

I 6

0.6. 0.6. 1.9. 2.7. 2.4. 2.1. 2.4. l.4. 1.0. -0.1. *1.4. *2.0. *l.8.

0.33 1.14 1.20 l.11 l.03 1.16 1.26 1.20 1.26 1.16 l.03 1.11 l.20 1.15 0.34

. 0.34. 1.16. 1.20. l.12. l.04. 1.17. l.26. l.21. 1.27. 1.16. l.OZ. 1.08. 1.16. 1.09. 0.32. 7 2.5. 1.3. o.4. 1.0. 1.2. o.9. 0.1. 1.1. o.4. o.3. -0.9. -2.a. -3.a. -s.o. -4.7.

I 0.37. 1.04 1.17 0.9't 1.13 1.25 l.20 1.19 1.20 1.25 l.13 0.95 l.17

. 0.38

• 1.06 . 1.19 . 0.95

• 1.13

• 1.25 . 1.20

• 1.19 . 1.19

• 1.24

• 1.11

• 0.9Z

• 1.13 . 1.00

• 0.36

• 2.4. 1.6. l.6. 0.7. -0.l. 0.1. 0.5. o.o. -0.7. -0.6. *l.7. -3.l. -3.5. -3.6. -3.2.

1.04 0.37 a

0.33 1.15 1.20 1.11 1.03 l.16 l.26 1.20 1.26 1.16 1.03 l.11 1.20 1.15 0.33

. o.34 . 1.16. 1.21

• 1.11. 1.02. 1.16. 1.26. 1.19. 1.25. 1.14. 1.00. 1.oa. 1.16. 1.12. o.33. 9 2.5. 1.5. l.O. 0.6. *O.l. -o.z. 0.4. -0.5. *0.8. *2.l. *2.2. -3.3. *3.3. *2.8. -1.8.

0.76 1.24 l.25 1.22 1.23 1.16. l.25 l.16 1.24 1.23 1.26 1.24 0.77

. 0.76

• l.24

• 1.26

• 1.25

• 1.26

• 1.15

• 1.24 * *l.15

• 1.22

• 1.20

• 1.22

• 1.20

• 0.74 . u 0.1. 0.1. o.9. 2.0. 1.9. -o.6. -o.6. -o.a. -1.1. -1.a. -3.o. -3.Z. -3.o *

. 0.37 1.13 1.21. 1.33 1.22 1.03 1.13 1.03 1.22 1.33 1.20 1.13 0.37

. 0.38

• 1.16

• 1.23

• 1.36

• 1.23

• 1.01

• 1.12

• 1.03

• 1.22

• 1.32

• 1.19

• 1.12

• 0.36

• 11 2.4. 2.4. 2.2. 2.0. o.6. -1.1. -0.1. -0.1. 0.1. -1.z. -1.1. -1.0. -1.4.

I 0.40 0.93 1.21 1.25 1.11 0.95 1.11 1.25

. 0.42. 0.97. 1.23. 1.25. 1.09. 0.93. 1.09. l.23. l.18. 0.93. 0.40.

1.20 4.7. 3.6. 2.0. -0.2. -1.7. -1.9. -1.8. *1.5.

• l . l . -0.Z. 1.0.

0.41 1.13 1.24 1.21 1.17 1.20 1.23 1.12 0.93 0.40 0.40 12

. 0.42. 1.16. 1.25. 1.18. 1.13. 1.16. 1.18. 1.09. 8.40. 13 I 3.8. 2.9. 0.7. *2.5. -3.3. -3.8. -3.6. *2.3. 0.3.

o.37 0.11 1.15 1.04 1.14

. 0.3a. 0.77. 1.12. 1.01

• 1.10. 0.73. 0.35.

2.9.

o.76 l . l . *2.3. -3.3. -4.2. -3.9. *3.5.

o.36 14 I STAHIWID DEVIATION

=l.274 0.34 0.37

. 0.33. 0.36. 0.32.

. *1.6. -2.7. -4.4.

0.33 AVERAGE

.PCT DIFFERENCE.

= 1.9 15 I SUKttARY t1AP NO: Sl-12-05 DATE: 5/11/92 POWER: 100.oz I CONTROL ROD POSITION: F-Q(Z) = 1.866 QPTR:

D BANK AT 220 STEPS F-DH(N) = 1.475 NW l. 0164 INE 0.9998 I F(Zl = 1.209 SW 1.0053 I

ISE 0.9786

• • I = 178 HWD/HTU =

BURNUP A.O. 2.6927.

NE-978 S1C12 Core Performance Report Page 31 of 58

I

~

Figure 4.2 SURRY UNIT 1 - CYCLE 12 ASSEMBLYWISE POWER DISTRIBUTION Sl-12-14 R 11 K H G F E D C A

?PEDICTED

~EASURED

.PCT DIFFERENCE.

0.31 0.35 0.31

. 0.33 . 0.37

• 0.32 .

,.2. 4.2. 2.9.

PREDICTED MEASURED

. PCT DIFFERENCE.

l I 0.36 0.70 1.03 0.93 l.03 0.71 0.36 0.40

. 0.37. 0.72 . l.04 . 0.94

• l.04 . 0.71 . 0.37.

3.7. 2.5. 1.4. 1.1

• o.3. 1.0 . 2.8.

l.06 1.23 l . l l . 1.24 1.12 1.23 l.06

. 0.42. 1.07. 1.24. 1.13. l.Zl . 1.10. 1.24 . 1.10. 0.43.

0.40 z

3 I

3.1 . 0.5. 0.5. 1.7. -Z.l. -1.4. l.O . 3.8. 5.7.

0.40 0.91 1.28 1.20 1.25 0.99 1.25 1.20 1.28 0.91

. 0.41

• 0.91 . 1.26. 1.20. 1.26. 0.99. 1.22. 1.21 . 1.30. 0.92. 0.41 .

0.3. 0.5. -1.S. 0.4. 0.8. -0.l . -Z.9 . 0.9. l.Z. 1.4 . 2.6.

0.40 4

I o.36 1.06 1.23 1.21 1.33 1.06 1.21 1.06 1.33 1.21

. -1.0. -1.0 . -0.3 . l.O . O.S. l.b. 1.7, 1.0 . 0.6. 0.3. -2.2. l.O. 4.7.

0.70 1.23 1.20 1.34 1.22 1.30 1.21 1.30 1.22 1.33 1.28

. 0.36. 1.05. 1.28. 1.28. 1.34 . 1.08. 1.29. 1.07. 1.34 . 1.:8. 1.25. 1.07. 0.33.

1.20 1.06 1.23 o.36 0.70 5

I

. 0.70. 1.23. 1.20 . 1.34 . 1.23. 1.31 . 1.23. 1.30 . 1.22. 1.33. 1.13. 1.23. 0.71 . 6 0.31

. -0.4. -0.4 . 0.2. 0.2. 0.7. 1.0 . 1.4. 0.6. 0.3. -0.4. -1.3, -0.5, 1.0 .

1.03 1.11 1.25 1.06 1.30 1.17 1.15 1.13 1.30 1.06 1.25 1.11

. 0.33. 1.04. 1.12 . 1.25. 1.05. 1.29. 1.17. 1.15. 1.18. 1.30. 1.06. 1.23. 1.10. 1.01

• 0.31.

4.0 . 1.2. 0.2 . -0.4 . -1.l . -0.8. -0.l . 0.4 . 0.0 . 0.4. -0.l . -1.4 , -1.S, -Z.2. -1.3.

1.03 0.31

• 7 I

o.35 o.93 1.24 o.99 1.21 1.21 1.14 1.03 1.14 1.21 1.21 o.99 1.24 o.93 o.35

. 0.37 . 0.94 . l.24 . 0.99 . 1.25 , 1.20 . l.14

• l.07

• l.14 . l.21 . 1.26 . 0.97 . l.22 . 0.93 . 0.36

• 4.0. 1.5. -0.0 . -O.l . -1.S. -0.2. -0.3. -0.2. -0.2. 0.5. -0.6. -1.7. -1.6. 0.4 . l . l .

a I 0.31 1.03 1.12 1.25 1.06 1.30 1.18 1.14 1.17 1.30 1.06 1.25 1.12 1.03. 0.31.

el

. 0.33. 1.04. 1.11 . 1.25 . 1.09 . 1.31 . 1.17. 1.14

• 1.17. 1.27. 1.05. 1.24. 1.12. 1.04 . 0.32. 9 4.o . 1.0. -o.5 . o.3 . 2.1 . o.9. -o.3. o.o. -o.3. -2.0 * -o.9. -o.3. o.o. 1.5 . 3.3.

0.70 1.23 1.20 1.33 1.22 1.30 1.21 1.30 1.22 1.34 1.20 1.23 0.71

. 0.70. 1.22. 1.20

• 1.36. 1.24. 1.29. 1.20. 1.29. 1.22. 1.33. 1.20 . 1.25. 0.72. lD

. -0.9. -0.9. 0.6. 1.8. 1.8. -0.6. -0.3. -0.4. -0.3. -0.2. -0.l. 1.1. 2.4 .

0.36 1.06 1.28 1.27 1.33 1.06 1.27 1.06 1.33 1.27 1.28

. 0.37. 1.03. 1.30 , 1.23. 1.32. 1.05. 1.26. 1.07. 1.35. 1.28. 1.31 . 1.10. 0.37.

1.5. 1.5. 1.1

• o.6. -o.s. -1.1. -0.3. o.5. 1.3. o.7. 2.1 . 3.3. 3.3.

1.06 0.36 11 I I

0.40 0.91 1.28 1.20 1.25 0.99 1.25 1.19 1.28 0.91 0.40

. 0.42 . 0.93 . 1.29. 1.18. 1.22. 0.97. 1.24. 1.19. 1.29. 0.94. 0.43. 12 3.9 . 2.6. 0.6. -1.S. -Z.7. -Z.2. -1.1 . -0.3. 1.0. 3.7. 5.7.

0.40 l.06 1.23 1.12 1.24 1.11 1.23 1.06 0.40

. 0.42. 1.10 . 1.24. 1.03. 1.20

• 1.03. 1.20

• 1.06. 0.42. 13 3.9. 3.9. 0.5. -2.9. -3.0. -3.0. -2.6. -0.l. 4.6.

0.36 0.71 1.03 0.93 1.03 0.70 0.36

. 0.38. 0.73. 1.03. 0.91

• 0.99. 0.63. 0.35.

3.9. 3.3. o.3. -1.9. -3.5. -3.l . -2.5.

lit I

STANDARD DEVIATION

=1.304 0.31 0.35 0.31

. 0.32. 0.35. 0.30.

2.5. 0.1 * -3.6.

AVERAGE

.PCT DIFFERENCE.

= l.5 15 I

HAP NO: Sl-12-14 DATE:

SUHHARY 2/15/93 POWER: 99.9%

I CONTROL ROD POSITION:

D BANK AT 224 STEPS F-QCZl F-DHCNI

= 1.784

= 1.418 QPTR:

NW 1. a019 NE 0.9999 I

F(Zl = 1.148 SW 1.0015 SE 0.9967 I

= 9266 HWD/HTU = -2. 777%

..

BURNUP A.O.

~E-978 S1Cl2 Core Performance Report Page 32 of 58 I

I Figure 4.3 SURRY UNIT 1 - CYCLE 12 ASSE~BLYWISE POWER DISTRIBUTION Sl-12-23 p H K J H G F E D C A I PREDICTED MEASURED

. PCT DIFFERENCE.

0.34 0.39 0.34

. 0.37 . 0.42

• 0.36

• 7.7 . 7.7 . 5.7

• PREDICTED HEASURED

.PCT DIFFERENCE.

• 0.38 0.71 1.02 0.93 1.02 0.71 0.38 I , 0.42

. 0.41

• 0.73. 1.07. 0.98. 1.07. 0.73. 0.40, 6.0

• 2.9 . 4.8 . 5.8 , 4.7 . 2.6

• 4.1 ,

1.03 1.21 1.09 1.26 l.09 1.21

, 0.44. 1.04. 1.22. 1.13. 1.30, 1.12, 1.25. 1.08. D.45.

1.03 D.42 z

3 5.D

• 1.2. 0.3. 2.9. 2.9. 2.6. 2.6. 4.9, 6.4 *

. D.42, 0.90 1.26 1.16 1.30 1.02 1.30 1.16 1.26 0.90 D.42

. 0.45, 0.91 . 1.23. 1.15. 1.32. 1.03. 1.28, 1.14 . 1.28. 0.93, 0.45.

6.D . l.l * *2.2. -0.3. l.8. l.8. *l.3. *l.5. 1.6. 3.3, 6.5.

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14 I STANDARD DEVIATION

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I

~.I Section 5 PRIMARY COOLANT ACTIVITY I

I The specific activity levels of radioiodines and radioactive noble I gases in the primary coolant are important to core and fuel performance as indicators of failed fuel and are important with respect to offsite I dose calculations associated with accident analyses. Two mechanisms are primarily responsible for the presence of radioiodines and radioactive.

noble gases in the primary coolant. These fission products are always I present due to direct fission product recoil from trace fissile materials plated onto core components and fuel structured surfaces or trace fissile materials existing as impurities in core structural materials. This fissile material is generally referred to as "tramp" material, and the I resulting iodines are referred to as tramp iodine. Fission products will I also diffuse into the primary coolant if a breach in the cladding (fuel defects) exists. Fuel defects are generally the predominant source of I radioiodines and radioactive noble gases in the primary coolant.

I Surry Technical Specification 3.1.D conditionally limits the primary I coolant radioiodine dose equivalent I-131 to a value of 1.0 µCi/gram with provisions that ultimately limit the dose equivalent I-131 activity to a I maximum of 10.0 µCi/gm. 2 Figure 5.1 shows the dose-equivalent I-131 I activity history for Cycle 12. These data show that the dose equivalent

.. I-131 activity remained substantially below 1.0 µCi/gm throughout Cycle 12 operation. The cycle average steady state power dose equivalent I-131 I NE-978 S1C12 Core Performance Report Page 47 of 58

I concentration was 6.28 X 10- 3 µCi/gm which is less than 1% of the full power Technical Specification limit.

JI Correcting the I-131 concentration for tramp iodine involves I

calculating the I-131 activity from tramp fissile sources and subtracting I

this value from the measured I-131. The resultant tramp-corrected I-131 activity is theoretically the I-131 activity from defective fuel. The I magnitude of the tramp-corrected I-131 can then be used as an indication of fuel reliability (the average tramp-correct~d I-131 activity for a I

month is generally referred to as the fuel reliability indicator) as well I

as assisting in quantifying the extent of fuel cladding defects. The monthly fuel reliability indicator through September 1993 generally I remained below 5 X 10- 4 µCi/gm. For PWRs, this is considered to be a typical fuel reliability indicator level for a reactor core with no fuel defects. The fuel reliability indicator increased above 5 X 10- 4 µCi/gm for the remainder of 1993 having a final fuel reliability indicator of I

8.33 X 10- 3 µCi/gm when the cycle ended in January 1994. An increase in I the fuel reliability indicator of this nature indicates the presence of a cladding defect or defects.

I I

The fuel cladding defect(s) became more readily apparent during Cycle 12 late in September 1993. The noble gas activity in the RCS increased I sharply indicating a cladding defect event (see Figure 5.3). The measured (not tramp-corrected) I-131 RCS activity (Figure 5.4) began to noticably I

increase in November 1993. The manner in which the RCS coolant activity I

~

increased, (i.e., a noble gas activity increase followed much later in time by increasing iodine activity) indicates the defect(s) were either NE-978 SlC12 Core Performance Report Page 48 of 58 I

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• • I small or slowly forming. Large defects typically manifest themselves by nearly simultaneous increases in noble gas and iodine RCS activity.

A failed fuel action plan was issued in November 1993. The principle

~ element of the plan was to perform fuel inspections during the subsequent refueling outage to ensure no fuel assemblies with cladding defects were I reinserted for use in Cycle 13. The fuel UT exams resulted in widely varying indications of suspect cladding failures, primarily in fuel I assemblies scheduled to be discharged. Upon reviewing the UT data, there I was not sufficient evidence suggesting the presence of cladding defects in any fuel assemblies other than those being discharged. Given the I uncertainty in the fuel UT data for these assemblies, Westinghouse (Westinghouse was not the fuel UT vendor) agreed to perform additional fuel exams on the suspect discharged fuel assemblies to help determine I their status and potential failure mechanism.

to begin in the 2nd quarter of 1994.

The exams are scheduled I

The ratio of the specific activities of I-131 to I-133 is used to I characterize the type (size) of fuel failure which may have occurred in I the reactor core. Use of the ratio for this determination is feasible because I-133 has a short half-life (approximately 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br />) compared to I that of I-131 (approximately eight days). For pinhole defects, where the diffusion time through the defect is on the order of days, the I-133 I decays leaving the I-131 dominant in activity, thereby causing the ratio I to be roughly 0.5 or more. In the case of large leaks and tramp material,

.. where the diffusion mechanism is negligible, the I-131/I-133 ratio will generally be less than 0.1. The use of these ratios with regard to defect I ~E-978 S1C12 Core Performance Report Page 49 of 58

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• • I size is empirically determined and generally used throughout the commercial nuclear power industry. Figure 5.2 shows the I-131/I-133 ratio data for the Surry 1 Cycle 12. As seen on Figure 5. 2, the ratio began increasing when the fuel defect occurred, but never really attained equilibrium. Therefore, the use of the iodine ratio as a defect size indicator is perhaps not applicable. However, the characteristic nature I

of the increase in noble gas and radioiodine RCS activity suggests the I

defect(s) to be small.

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I el I

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NE-978 S1C12 Core Performance Report Page 50 of 58 I

I

• • I Figure 5.1 SURRY UNIT 1 - CYCLE 12 DOSE EQUIVALENT I-131 vs. TIME I 1.00E+ol+;------------------------------+

)

I I i.om:+oo+------------------------------i l

I j I 1.om:-011------------------------------+

I le .*

• I:* *

• 1!' \ fi a_"

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,. 41d I ft ** *

,, .* .*

I ** *

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• I 'I

• *

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I I 1.00!:-M-t-------,------------------------+ , .

• 'IS I *=*!

0 I 1.00E-05...------------------------....... -----------+

.-a

IC I ' I I I I' .. I " I 31.nJLIIZ Ol!NUYIIZ llSrzan 27JIA.Yn 0"8ZPl3 I

..

DATE I* NE-978 S1C12 Core Performance Report Page 51 of 58

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I I

Figure 5.2 SURRY UNIT 1 - CYCLE 12 I-131 / I-133 ACTIVITY RATIO vs. TIME

• • I 1.D-t-----------------------------------+

j

• I 0.11-t--------------------------------......

I 0.8,t-----------------------------------+

I

• 0.7-t--------------------------------...... I 0

0.8-t--------------------------------...... I

~

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n n

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'-

n

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• I o.,t-----------------------------------+

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• 1

. I 0.3+-----------------------------C------'

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,..., I 0.1 =-.__...._,.....__ -l *=* I O.D

.-

• !

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,M I

31rot82 08HOV92 1811Bn 27DTll3 04SEPl3 1:mzcn 23¥1814

• I

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DA.TB NE-978 SlC12 Core Performance Report Page 52 of 58 I

I

'I

• • I Figure 5.3 SURRY UNIT 1 - CYCLE 12 MEASURED RCS XENON-133 VS. TIME 1.DOZ+ol I

I 1.DOE+oO

• Ja.*

~--.

-

I I

1.00B-01 -~*

--*.

4..,..

le .... .,. ... **-~

• *........

.

..

.....

• **

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. **

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- *

• I 1.00B-03

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I 1.00J!:-05 I I I , I I I I 0

31J1JL82 161'D113 04SBPll3 13DZC8S 23MIRM I

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DATE I NE-978 S1C12 Core Performance Report Page 53 of 58

I Figure 5.4 SURRY UNIT 1 - CYCLE 12 MEkSURED RCS IODINE-131 VS. TIME 1.

1.00J:+ol+---------------------------------+

I I

l.OOE+oo+---------------------------------+

I

• I 1.0QE-01

~

• • I a:

t.:I

a:

~

a.

Cl.I

~ 1.DIJB-02 I

• el

~

• t.J 0

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i 1.DDE-03 I

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,I

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• l.OOE-04+-----------------------------------+

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• =..... I

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1.00E-05..,...___ _ _ _ _ _ _ _ _ _ ___.__ _ _ _ _ _ _ _......._ _ _ _ _ _....__ _

0 I 31Jllt82 OBNDYV2 16PDn 04SBP93 I

DATE

..

NE-978 S1C12 Core Performance Report Page 54 of 58 I

I

..I Section 6 I CONCLUSIONS I

I The Surry 1, Cycle 12 core has completed operation. Throughout this cycle, all core performance indicators compared favorably with the design I predictions and the core related Technical Specification limits were met with significant margin. No significant abnormalities in reactivity or I burnup accumulation were detected. Evaluation of the radioiodines and I radioactive noble gases in the RCS indicate that a fuel cladding defect or defects occurred in late September 1993. Fuel inspections were conducted during the subsequent refueling outage to preclude inserting defective fuel assembies into Cycle 13. The fuel exams indicated that I the defective fuel rod(s) existed in the discharged batches of fuel.

I Additional fuel assembly examinations are scheduled to begin in the second quarter of 1994.

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I NE-978 S1Cl2 Core Performance Report Page 55 of 58

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I THIS PAGE I~TENTIONALLY BLANK el I

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~E-978 SlC12 Core Performance Report Page 56 of 58 I

I Section 7 I REFERENCES I 1) E. A. Hoffman, "Surry Unit 1, Cycle 12 Startup Physics Test Report," Technical Report NE-898, Rev. 0, Virginia Power, July, 1992.

I

2) Surry Power Station Technical Specifications, I Sections 3.1.D, 3.12.B and 4.10.

I 3) T. W. Schleicher, "Virginia Power Fuel Assembly Burnup and Isotopics Calculation Code Manual," Technical Report NE-726, I Rev. O, Virginia Power, February, 1990.

le 4) D. L. Gilliatt, "The Virginia Power FOLLOW Code Manual,"

Technical Report NE-679, Rev. 1, Virginia Power, April, 1991.

I 5) W. D. Leggett, III and L. D. Eisenhart, "INCORE Code,"

WCAP-7149, Westinghouse, December, 1967.

I I 6) Letter from B. C. Buckley (NRC) to W.L. Stewart, "Surry Units 1 and 2 - Issuance of Amendments Re: F-Delta-H Limit and Statistical DNBR Methodology (TAC Nos. M81271 and M82168)",

I Serial No.92-405, dated June 1, 1992.

I 7) W. M. Oppenheimer, "Reload Safety Evaluation Surry 1 Cycle 12 (Pattern CP)", Technical Report NE-874, Rev. O, Virginia Power, February, 1992.

I I

• • I NE-978 SlC12 Core Performance Report Page 57 of 58

REFERENCES (cont.)

3) \;. 11. Oµpenheimer, "Reload Safety Evaluation Surry 1 Cycle 12 (Pattern CP)", Technical Report NE-874, Rev. 1, Virginia Power, April, 1992.

I

9) G. R. Pristas, "Reload Safety Ev.aluation Surry 1 Cycle 12 (Pattern CP) 11 , Technical Report NE-874, Rev. 2, Virginia Power, I September, 1992.

I

10) P. D. Banning, "Surry Unit 1 Cycle 12 Design Report",

Technicai Report NE-881, Rev. 0, Virginia Power, March, 1992. I

• 11) "Surry 1 Cycle 12 TOTE Calculations", Calculational Note PM-425, Rev. 0 and associated addenda, Virginia Power.

I I

12) "Surry 1 Cycle 12 Flux Map Analysis",

Calculational Note PM-437, Rev. 0 and associated addenda, Virginia Power.

13) D. M. Chapman, "Surry 1, Cycle 12 FOLOW Input and Calculations",

I Calculational Note PM-440, Rev. 0, Addendum C, Virginia Power, February, 1994. I I

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~E-978 S1Cl2 Core Performance Report Page 58 of 58 I