Text

Cycle 12 Startup Physics Test Rept. W/920731 Ltr
	ML18152A035
Person / Time
Site:	Surry
Issue date:	07/15/1992
From:	Hoffman E, Laroe C, Stewart W; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	92-491, NUDOCS 9208110252
	Download: ML18152A035 (59)
	v • d • e

~

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 31, 1992 United States Nuclear Regulatory Commission Serial No.92-491 Attention: Document Control Desk NL&P/CGL R1 Washington, D. C. 20555 Docket No. 50-280 License No. DPR-32 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST REPORT As required by Surry Technical Specification 6.6.A.1, enclosed are five (5) copies of the Virginia Electric and Power Company Technical Report NE-898, entitled "Surry Unit 1, Cycle 12 Startup Physics Test Report." This report summarizes the results of the physics testing program performed after initial criticality of Cycle 12 on May 1, 1992. The results of the physics tests were within the applicable Technical Specification limits.

Very truly yours, 1

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W. L. Stewart Senior Vice President - Nuclear Enclosures - Surry Unit 1, Cycle 12 Startup Physics Test Report (5 copies) cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station

e e TECHNICAL REPORT NE-898 - Rev. 0 SURRY UNIT 1, CYCLE 12 STARTUP PHYSICS TEST REPORT NUCLEAR ANALYSIS AND FUEL NUCLEAR ENGINEERING SERVICES VIRGIN IA POWER JULY 1992 PREPARED BY:t.~, 2-(~

E. A. Hof man 7/03/q-z-Date REVIEWED BY: c:-:::~ Afi---

Date J. w.

APPROVED B Y : ~ ~ 7Jsi42 D. Dz~dosz ~

QA Category: Nuclear Safety Related Ke~words: S1C12, Startup

e. e CLASSIFICATION/DISCLAIMER The data, techniques, information, and conclusions in this report have been prepared solely for use by Virginia Electric and Power Company (the Company), and they may not be appropriate for use in situations other than those for which they have been specifically prepared. The Company therefore makes no claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability. In particular, THE COMPANY MAKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING OR USAGE OF TRADE, with respect to this report or any of the data, techniques, information, or ~onclusions in it. By making this report available, the Company does not authorize its use by others, and any such use is expressly forbidden except with the prior written approval of the Company. Any ~uch written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein. In no event shall the Company be liable, under any legal theory whatsoever (whether contract, tort, warranty,. or strict or absolute liability), for any property damage, aental or physical injury or death, loss of use of property, or other daaage resulting from or ari~ing out of the use, authorized or unauthorized, of this report or the data, techniques, information,.or conclusions in it.

"*-RQR ~,r.12 Startup Test Report Page 1 of 57

e* e TABLE OF CONTENTS PAGE Classification/Disclaimer ***.************.***.****** ,... 1 Table of Contents. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 List of Tables. . . . . . * . * . . . * * * * * * * * * * * * * * . * * * . . * . * * * * * . .

3 List of Figures......................................... 4 Preface. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 Section 1 Introduction and Summary................... 7 Section 2 Control Rod Drop Time Measurements......... 16 Section 3 Control Rod Bank Worth Measurements........ 21 Section 4 Boron Endpoint and Worth Measurements...... 26 Section 5 Temperature Coefficient Measurement........ 30 Section 6 Power Distribution Measurements............ 32 Section 7 References................................. 40 APPENDIX Startup Physics Tests Results and Evaluation Sheets........................ 41 r

N~-RQR ~,r.12 Stnrtuo Test Report Page 2 of S7

e LIST OF TABLES TABLE TITLE PAGE 1.1 Chronology of Tests *..***....*.*.**..*****..********** 10 2.1 Hot Rod Drop Time Summary *.*..****.****...***.**.***** 18 3.1 Control Rod Bank Worth Summary........................ 23 4.1 Boron Endp~ints Summary............................... 28 5.1 Isothermal Temperature Coefficient Summary............ 31 6.1 Incore Flux Hap Summary............................... 35 6.2 Comparison of Measured Power Distribution Parameters With Their Technical Specification Limits............. 36

~~-AQA ~1r.12 Startuo Test Report Page 3 of 57

e LIST OF FIGURES PAGE FIGURE TITLE I

Core Loading Map . ......................... * . * . * . * . * * * * * *

11 1.1 Beginning of Cycle Fuel Assembly Burnups ************.**** 12 1.2 Incore Movable Detector Locations **.******************.** 13 1.3 Burnable Poison and Source Assembly Locations ************ 14 1.4 Control Rod Locations *.....**.***.******.********.******* 15 1.5 Typical Rod Drop Trace ........*.*..................*..... 19 2.1 Rod Drop Time - Hot Full Flow C.onditions ***************** 20 2.2 Bank B Integral Rod Worth - HZP ************************** 24 3.1 Bank B Differential Rod Worth - HZP ******* ~ ************** 25 3.2 Boron Worth Coefficient ...*...***...*.....*..**.........* 29 4.1 Assemblywise Power Distribution - 28% Power *.*........... 37 6.1 Assemblywise Power Distribution - 69% Power ..*.........** 38 6.2 Assemblywise Power Distribution - 100% Power ************* 39 6.3

\ft:" - O O II Page 4 of 57

e e PREFACE This report presents the analysis and evaluation of the physics tests which were performed to verify that the Surry 1, Cycle 12 core could be operated safely, and makes an initial evaluation of the performance of the core. It is not the intent of this report to discuss the particular methods of testing or to present the detailed data taken. Standard test techniques and methods of data analysis were used. The test data, results and evaluations, together with the detailed startup procedures, *are on file at the Surry Power Station. Therefore, only' a cursory discussion of these items is included in this report. The analyses presented include a brief summary of each test, a comparison of the test results with design predictions, and an evaluation of the results.

The Surry 1, Cycle 12 Startup Physics Tests Results and Evaluation Sheets are included as an appendix to provide additional information on the startup test results. Each data sheet provides the following information: 1) test identification, 2) test conditions (design), 3) tes~

conditions (actual), 4) test results, 5) acceptance criteria, and 6) comments concerning the test. These sheets provide a compact summary of the startup test results in a consistent format. The design test conditions and design values of the aeasured parameters were completed prior to the startup physics testing. The entries for the design values were based on the calculations performed by Virginia Electric and Power Company's Nuclear Analysis and Fuel Group 1

During the tests, the data sheets were used as guidelines both to verify that the proper test conditions were met and to facilitate the preliainary comparison between NF.-898 S1C12 Startup Test Report Page 5 of 57

e measured *and predicted test results, thus enabling a quick identification of possible problems occuring during the tests.

NF-RgR S1C12 Startup Test Report Page 6 of 57

e. e SECTION 1 INTRODUCTION AND

SUMMARY

On February 29, 1992 Unit No. 1 of the Surry Power Station shutdown for its eleventh refueling. During this shutdown, 65 of the 157 fuel assemblies in the core were replaced with 63 fresh fuel, and 2 once-burned assemblies. The eleventh cycle core consists of 8 sub-batches of fuel:

two fresh batches (batches 14A and 14B); four once burned batches, two from Cycle 11 (batches 13A, and 13B), one from Cycle 8 (batch 10), and one from Cycle 10 (a single batch 12B assembly); three twice-burned batches from Cycles 10 and 11 (batches S2/12A, and 12A, and 23 batch 128 a*ssemblies). Note that batch 12B has both once and twice burned assemblies. The core loading pattern and the design parameters for each batch are shown in Figure 1.1. Fuel assembly burnups are given in Figure 1.2. The incore movable detector locations are ~dentified in Figure 1.3.

Figure 1.4 identifies the location and number of burnable poison rods and source assemblies for Cycle 11, and Figure 1.5 identifies the Jocation and number of control rods in the Cycle 12 core.

On Hay 1, 1992 at 2218, the twelfth cycle core achieved initial criticality. Following criticality, startup physics tests were performed as outlined in Table 1.1. A sumaary of the results of these test follows:

1. The measured drop tiae of each control rod was within the 2. 4 second limit of Technical Specification 3.12.C.1.

~F-RgR ~,r.12 St~rtun Test Report Page 7 of 57

e* e

2. The reference control rod bank was measured with the dilution method, and the results were within 2.9% of the design predictions. Individual control° rod bank worths were *easured using the rod swap technique 2 and the results ~ere within 3.9%

of the design predictions. The sum of the individual measured control rod bank worths was within 0.4% of the design prediction.

These results are within the design tolerance of +/-15% for individual bank worths (+/-10% for the rod swap reference bank worth) and the design tolerance of +/-10% for the sum of the individual control rod bank worths.

3. Measured critical boron concentrations for the two control bank configurations were within 31 ppm *of the design predictions.

These results were within the design tolerances and also met the

Technical Specification 4.10 criterion that the overall core reactivity balance shall be within +/-1% ~k/k of the design prediction.

4. The boron worth coefficient *easurement was within 0.5% of the design prediction, which is within the design tolerance of +/-10%.

5. The *easured isothermal temperature coefficient (ITC) for the all-rods-out configuration was within 0.35 pc*/ 8 F of the design prediction. . This result is within the design tolerance of +/-3 pc*/'F. The *easured ITC was -2.16 pc*/'F. When the Doppler temperature coefficient and a 0.5 pca/'F uncertainty are accounted for in the +l.O pca/ 1 F KTC li*it of Technical w~-ROR ~,r.12 StBrtun Test Report Page 8 of 57

e e Specification 3.1.E.1, the MTG requirement is satisfied as long as the ITC is less than or equal to +0.82 pcm/°F.

6. Measured core power distributions were within established acceptance criteria based on Technical Specification limits.

However j a design tolerance on core tilt was exceeded for the flux map taken at less than 30% *power. The impact of the core tilt on safety analysis physics parameters was evaluated and was found to be bounded by the results of the current analysis. The core tilt is discussed further in Section 6. Generally, the measured core power distribution was within 3. 7% of the design predictions. The heat flux hot channel factors, F-Q(Z), and enthalpy rise hot channel factors, F-DH(N), were within the limits of Technical Specifications Section 3.12.B.1.

In summary, all startup physics test r~sults were acceptable.

Detailed results, specific design tolerances and acceptance criteria for each measurement are presented in the following sections of this report.

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e e.

Table 1.1 SURRY 1 - CYCLE 12 STARTUP PHYSICS TESTS CHRONOLOGY OF TESTS Reference Test Date Time Power Procedure Hot Rod Drop - Hot Full Flow 4/30/92 2248 HSD 1-NPT-RX-007 Zero Power Testing Range 5/02/92 0332 HZP 1-NPT-RX-008 Reactivity Computer Checkout 5/02/92 0455 HZP l-NPT-RX-008 Boron Endpoint - ARO 5/02/92 0940 HZP 1-NPT-RX-008 Temperature Coefficient - ARO 5/02/92 1048 HZP 1-NPT-RX-008 Bank B Worth 5/02/92 1208 HZP 1-NPT-RX-008 Boron Endpoint - Bin 5/02/92 1208 HZP 1-NPT-RX-008 Boron Worth Coefficient 5/02/92 1208 HZP 1-NPT-RX-008 Bank D Worth - Rod Swap 5/02/92 1717 HZP 1-NPT-RX-008 Bank C Worth - Rod Swap 5/02/92 1834 HZP 1-NPT-RX-008 Bank A Worth - Rod Swap 5/02/92 1901 HZP 1-NPT-RX-008 Bank SB Worth - Rod Swap 5/02/92 1919 HZP 1-NPT-RX-008 Bank SA Worth - Rod Swap 5/02/92 1947 HZP 1-NPT-RX-008 Flux Map - P ~ 30% 5/03/92 1134 28% 1-NPT-RX-002 Flux Map - 50% SP S 75% 5/05/92 0735 69% 1-NPT-RX-002 Flux Map - 95% SP S 100% 5/11/92 1251 100% 1-NPT-RX-002 ur._ooo c:'H"1? ~t~-rt11n T~st Renart Page 10 of 57

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- one assallbly is reconstituted with 203 fuul rods and ona solid stainless steal rod NF.-R98 S1Cl2 Startup Test Report Page 11 of 57

e Figure 1.2 SURRY UNIT 1 - CYCLE 12 BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS p N L I .J H 6 F E II A R

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e Figure 1.3 SURRY UNIT 1 - CYCLE 12 INCORE MOVABLE DETECTOR LOCATIONS R p N N L I( .J H G F E D C I ,.

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~~~~~--'~~~--~R._.QR ~,r.12 Startuo Test Report ~~~-

Page 13 of 57

e e Figure 1.4 SURRY UNIT 1 - CYCLE 12 BURNABLE POISON AND SOURCE ASSEMBLY LOCATIONS p L K .J H 6 F E D C B A R N I I I I I I I I 1 I

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12P - 12 BURNABLE POISON ROD CLUSTER I I I I 16P 17P 16 BURNABLE POISON 17 BURNABLE POISON ROD ROD CLUSTER CLUSTER

,I_ _ ,I _ _ II_ _ I, 15 20P - 20 BURNABLE POISON ROD CLUSTER SSx - SECONDARY SOURCE I---- xxP or SSx BPIII NUIHIER OF BP RODS or SECONDARY SOdH:E ID

- BP ASSEIIBLY ID ut:- _ on o ~,r,? ~~~rtttn Test Reoort Page 14 of 57

e e Figure 1.5 SURRY UNIT 1 - CYCLE 12 CONTROL ROD LOCATIONS R p L K J G F E D C. B A N

" H 180° I

Loop C I I I* I Loop B l Outlet I __ I_._I __ I Inlet I I A I I D I I A I I 2

__ 1__ 1_ _ 1__ 1_ _ 1_*_1 __ 1__ 1_ _

N-41 I I I I SA I I SA I I SP I I N-43 3

_ _ 1__ 1__ 1__ 1__ 1__ 1_ _ 1__ 1__ 1_ _ 1_ _

I I c I I B I I I I B I I C I I 4

_ _ 1__ 1_ _ 1__ 1__ 1__ 1__ 1_ *_ 1__ 1__ 1_ _ 1_ _ 1__

1 I SP I I SB I I SP I I I I SB I I I I s 1_ _ 1__ 1_ _ 1__ 1__ 1__ 1__ 1__ 1__ 1__ 1_ _ 1_ _ 1__ 1 (Al IBI IDI ICI IDI IBI IAI 6 Loop C _ _ I __ I __ I __ I __ I __ I __ I __ I __ I __ I __ I __ I __ I __ I __ Loop B Inlet I I I SA I I I I SB I I SB I I SP I I SA I I I Outlet 7 1_ _ 1_ _ 1_ _ 1__ 1__ 1_ _ 1__ 1__ 1_ _ 1_ _ 1__ 1_ _ 1__ 1_ _ 1__ 1 0

9o - I I D I I I I c I I I I C I I I* I D I I - 270° 8 1_ _ 1_ _ 1_ _ 1_ _ 1__ 1_ _ 1__ 1__ 1__ 1__ 1__ 1_ _ 1_ _ 1__ 1_ _ 1 I I ISAI ISPI ISBI ISBI I I ISAI I I 9 1_ _ 1_ _ 1_ _ 1__ 1__ 1__ 1__ 1__ 1_ _ 1_ _ 1__ 1_ _ 1_ _ 1_ _ 1_ _ 1 IAI IBI IDI ICI IDI IBI IAI 10 1_ _ 1_ _ 1__ 1__ 1_ _ 1__ 1__ 1__ 1_ _ 1__ 1_ _ 1_ _ 1_ _ 1 I I. I ISBI I I ISPI ISBI ISPI I 11 1_ _ 1_ _ 1_*_1 __ 1__ 1__ 1__ 1__ 1__ 1__ 1_ _ 1_ _ 1__ 1 I I c I I B I I I .I B I I C I I 12 1_ _ 1_ _ 1__ 1__ 1_ _ 1__ 1__ 1_ _ 1_ _ 1_ _ 1_ _ 1 I ISPI ISAI ISAI I I I 13

.N-44 I __ I _ I __ I _ I _ I _ I __ I __ I __ I N-42 I I A I I D I I A I I 14 1__ 1_ _ 1_ _ 1 _ 1 _ 1 __ 1__ 1 I I I I 1S Loop A I __ I __ I __. I Loop A Absorber Outlet Inlet Haterial I0 Ag-In-Cd o Function NU11ber of Clusters Control Bank D 8 Control Bank C 8 Control Bank B 8 Control Bank A 8 Shutdown Bank SB 8 Shutdown Bank SA 8 SP (Spare Rod Locations) 8 u~-RoR ~,r1? ~t~~tnn Test Report Page 15 of 57

e e SECTION 2 CONTROL ROD DROP TIME MEASUREMENTS The drop time of each control rod was measured at hot full-flow reactor coolant system (RCS) conditions (Tavg above 547+/-5°F) in order to verify that the time from initiation of the rod drop to the entry of the rod into the dashpot was less than or equal to the maximum allowed by Technical Specification 3.12.C.1.

The rod drop times were measured by withdrawing a rod bank to its fully withdrawn position, and removing the movable gripper coil fuse and stationary gripper coil fuse for the particular rod of the bank to be dropped. This allowed the rod to drop into the core as it would during a plant trip. The stationary gripper coil voltage, the Individual Rod Position Indication (!RPI) primary coil voltage signals and 60 Hz trace were recorded to determine the rod drop time. This procedure was repeated for each control rod.

As shown on the sample rod drop trace in Figure 2.1, the initiation of the rod drop is indicated by the decay of the stationary gripper coil voltage when the stationary gripper coil fuse is removed. As -the rod drops, a voltage is induced in the IRPI primary coil. The magnitude of this voltage is a function of control rod velocity. As the rod enters the dashpot region of the guide tube, its velocity slows causing a voltage decrease in the IRPI coil. This voltage reaches a minimum when the rod reaches the bottom of the dashpot. Subsequent variations in the trace are caused by rod bouncing.

w~-RQR ~,r.12 Startup Test Report Page 16 of 57

e The measured drop times for each control rod, for each test, are recorded on Figure 2.2. The slowest, fastest, and average drop times are summarized in Table 2.1. Technical Specification 3.12.C.1 specifies a maximum rod drop time from loss of stationary gripper coil, voltage to dashpot entry of 2.4 seconds with the RCS at hot,. full flow conditions.

These test results satisfied this limit.

~~N_F._.-898 S1C12 Startup Test Report Page 17 of 57

e.

Table 2.1 SURRY UNIT 1 - CYCLE 12 STARTUP PHYSICS TESTS HOT ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME F-14 1.32 sec. E-05 1.22 sec. 1.26 sec.

u~-RaR ~,r,, ~~~rtun Test Renort Page 18 of 57

Figure 2.1 SURRY UNIT 1 - CYCLE 12 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE 8allDln Of Datmt (BegiliillQ a Fftl UpUn en rraca, I.

'--------------.---....-----t Slatlal*Y Gn,plr Col YollOI Tl'ICI i...---RodDmp11ml-----

80HZIAPI r,f~AJ.LAAJ.~~ P111m11,eoa YolaQITrace P11"t111~"1"t1<Wti~~,w.t,1+1-"""'rJ,+1,~""11-..,.._.,..,.""',w,1,1,W,1...,..IWl..&1.11:willlliWW.J,W.W...~ IOHZTl'ICI ROD DROP TIME MEASUREMENT Page 19 of 57

e Figure 2.2 SURRY UNIT 1 - CYCLE 12 STARTUP PHYSICS TESTS ROD DROP TIME - HOT FULL FLOW CONDITIONS R p L K J ti 6 F E D C B ,.

N I I I I I I I 1

~ - - - - 1 _ _ 1_ _ 1_ _ 1 ~ - - - -

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~"~t:'_.._._,,_ooci ~,,.,., ~t-~,-t-,,n TP.!:t RP.oort Page 20 of 57

e SECTION 3 CONTROL ROD BANK WORTH MEASUREMENTS Control rod bank worths were measured for the control and shutdown banks using the rod swap technique 2

The initial step of the rod swap method diluted the predicted most reactive control rod bank (hereafter referred to as the reference bank) into the core and measured its reactivity worth using conventional test techniques. The reactivity changes resulting from the reference bank movements were recorded continuously by the reactivity computer and were used to determine* the differential and *integral worth of the reference bank. For Cycle 12, Control Bank B was used as the reference bank.

After the completion of the reference bank reactivity worth measurement, the reactor coolant system temperature and boron concentration were stabilized with the reactor just critical and the reference bank near full insertion. Initial statepoint data for the rod swap maneuver were obtained by moving the reference bank to its fully inserted position and recording the core reactivity and moderator temperature. From this point, a rod swap maneuver was performed by withdrawing the reference bank several steps and then one of the other control rod banks (i.e., a test bank) was inserted to balance the reactivity of the reference bank withdrawal. This sequence was repeated until the test bank was fully inserted and the reference bank was positioned such that the core was just critical. This measured critical position (HCP) of the reference bank with the test bank fully inserted was used to determine the integral reactivity worth of the test bank.

"~-RQR ~1C12 Startuo*Test Report Page 21 of 57

e The core reactivity, moderator temperature, and the differential worth of the reference bank were recorded with the reference bank at the MCP.

The rod swap maneuver then was repeated in reverse such that the reference bank again was near full insertion with the test bank fully withdrawn from the core. This rod swap process was then repeated for each of the other control and shutdown banks.

A summary of the test results is given in Table 3.1. As shown in this table and the Startup Physics Tests Results and Evaluation Sheets given in the Appendix, the individual measured bank worths for the control*

and shutdown banks were within the design tolerance (+/-10% for the reference bank, +/-15% for test banks of worth greater than 600 pcm, and

+/-100 pcm for test banks of worth less than or equal to 600 pcm). The sum of the individual measured rod bank worths was within 0.4% of the design prediction. This is well.within the design tolerance of +/-10% for the sum of the individual control rod bank worths.

The integral and differential reactivity worths of the reference bank (Control Bank B) are shown in Figures 3.1 and 3.2, respectively.

The design predictions and the measured data are plotted together in order to illustrate their agreement. In summary, the measured rod worth values were satisfactory.

t..Tt"-11011 ~,r.,, ~tArtuo Test Report Page 22 of 57

e e Table 3.1 SURRY UNIT 1 - CYCLE 12 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH

SUMMARY

MEASURED VS. PREDICTED MEASURED PREDICTED PERCENT DIFFERENCE WORTH WORTH (%)

BANK (PCM) (PCM) (M-P)/P X 100 B-Reference Bank 1362.0 1324.0 2.9 D 1097.7 1104.0 -0.6 C 878.5 913.7 -3.9 A 394.8 401.6 -1. 7*

SB 1181.1 1174.0 0.6 SA 938.6 960.6 -2.3 Total Worth 5852.7 5877. 9 -0.4

- The difference is less than 100 pcm.

NE-898 S1C12 Startup Test Report Page 23 of 57

e

/

Figure 3.1 SURRY UNIT 1 - CYCLE 12 STARTUP PHYSics* TESTS BANK B INTEGRAL ROD WORTH - HZP ALL OTHER .RODS WITHDRAWN 1

+ .: *:~:~!'*~,."'

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e.

Figure 3.2 SURRY UNIT 1 - CYCLE 12 STARTUP PHYSICS TESTS BANK B DIFFERENTIAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN uu.......,.~~-~'!""'-~~~-.:-~-=-:~:--~~-:-~-:--:-""":'~-:-,_..***."!"-.:-~~~~~-~"'!"..,...,.-~~~:--'!""'!""~

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~_!'l(:~~=-.;..~.;...;...;...;.'""!~;-;.-~.;.:~+~...;,~~~~~:"":""~':'"'~~-*~-,1-----------1-~~-

. ;~ -* -predicted 0 I IS 25 a 41 II e 71 * * , . 111 121 , . 141 , . , . 1111* , . 2D1 211 m BANK PDSmON (STEPS)

'NE-898 S1C12 Startup Test Report Page 2S of S7

l e* e SECTION 4 BORON ENDPOINT AND WORTH MEASUREMENTS Boron Endpoint With the reactor critical at hot zero power, reactor coolant system (RCS) boron concentrations were measured at selected rod bank configurations to enable a direct comparison of measured boron endpoints with design predictions. For each critical boron concentration measurement, the RCS conditions were stabilized with the control banks at or very near a selected endpoint position. Adjustments to the measured critical boron concentration values were made to account for off-nominal control rod position and moderator temperature, if necessary.

The results of these measurements are given in Table 4.1. As shown in this table and in the Startup Physics Tests Results and Evaluation Sheets given in the Appendix, the measured critical boron endpoint values were within their respective design tolerances and met the requirements of Technical Specification Section 4.10 regarding core reactivity balance. In summary, the boron endpoint results were satisfactory.

Boron Worth Coefficient The measured boron endpoint values provide stable statepoint data from which the boron worth coefficient or differential boron worth (DBW) was determined. By relating each endpoint concentration to the integrated rod worth present in the core at the time of the endpoint measurement, the value of the DBW over the range of boron endpoint concentrations was obtained.

!:t.r::.:i:":....:-:2R~o:!..!11~_:c::'U_I,rr_;_.J_,z? St 1trtun Test_ F ~port Page 26 of 57

e A plot of the boron concentration versus inserted control rod worth is shown in Figure 4.1. As indicated in this figure and in the Appendix, the measured DBW was -7 .44 pcm/ppm. This is within 0.5% of the predicted value of -7.40 pcm/ppm and is well within the design tolerance of +/-10%.

In summary, the measured boron worth coefficient was satisfactory.

>>~-RQR ~,r.,i Sta~tun Test Report Page 27 of 57

e Table 4.1 SURRY UNIT 1 - CYCLE 12 STARTUP PHYSICS TESTS BORON ENDPOINTS

SUMMARY

MEASURED vs. PREDICTED Measured Predicted Difference Control Rod Endpoint Endpoint M-P Configuration (ppm) (ppm) (ppm)

ARO 1842 1811 31 B Bank In 1659 1663* 4

The predicted endpoint for the B Bank In configuration was adjusted for the difference between the measured and predicted values of the endpoint taken at the ARO configuration as shown in the boron endpoint Startup Physics Test Results and Evaluation Sheets in the Appendix.

ur._ono ~,r,? ~t~rtnn Test Reoort Page 28 of 57

e.

Figure 4.1 SURRY UNIT 1 - CYCLE 12 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT 1,~e-r--s-*i Measured DBW = -7.44 pcm/e_p_m_ _ _ _ ___

~-=~--=-------------------------------

i '~

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Page

e e SECTION 5 TEMPERATURE COEFFICIENT MEASUREMENT The isothermal temperature coefficient (ITC) at the all-rods-out condition is measured by controlling the reactor coolant system (RCS) temperature with the steam dump valves to the condenser, establishing a constant heatup or cooldown rate, and monitoring the resulting reactivity changes on the reactivity computer. This test sequence includes a cooldown followed by a heatup.

Reactivity was measured ~uring the RCS cooldown of approximately

3. 0 °F and the RCS heatup of approximately* 5. 7°F. Reactivity and temperature data was taken from the reactivity computer and strip chart recorders. Using the statepoint method, the temperature coefficient was determined by dividing the change in reactivity by the change in RCS temperature. An X-Y plotter, which plotted reactivity versus temperature, confirmed the statepoint method in ~alculating the measured ITC.

The predicted and measured isothermal temperature coefficient values are compared in Table 5.1. As can be seen from this summary and from the Startup Physics Test Results*and Evaluation Sheet given in the Appendix, the measured isothermal temperature coefficient value was within the design tolerance of +/-3 pcm/°F and met the requirements of Technical Specification 3.1.E.1. In summary, the measured result was satisfactory.

Page 30 of 57

e. e Table 5.1 SURRY UNIT 1 - CYCLE 12 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

MEASURED vs. PREDICTED CORE CONDITIONS ISOTHERMAL TEMPERATURE COEFFICIENT (PCM/°F)

BANK TEMPERATURE BORON POSITION RANGE CONCENTRATION C/D H/U AVE. DIFFER.

(OF) (ppm) MEAS. PRED. (M-P) 543.6 D/217 to 1842 -2.39 -1.92 -2.16 -:2 .51 0.35 549.3

~~-RQR s1r.1, StRrtuo Test Report Page 31 of 57

e* e SECTION 6 POWER DISTRIBUTION K~ASUREKENTS The core power distributions were measured using the movable incore detector flux mapping system. This system consists of five fission chamber detectors which traverse fuel assembly instrumentation thimbles in up to 50 core locations (see Figure 1. 3). For each traverse, the detector voltage output is continuously monitored on a strip chart recorder, and scanned for 61 discrete axial points by the PRODAC P-250 process computer. Full core, three-dimensional power distributions are determined from this data using the Westinghouse computer program, INCORE 3

INCORE* couples the measured voltages with predetermined analytic power-to-flux ratios in order

to determine the power distribution for the whole core.

A list of the full-core flux maps taken during the startup test program and the measured values of the important power distribution parameters is given in Table 6.1. A comparison of these measured values with their Technical Specification limits is given in Table 6.2. Flux Map 1 was taken at 28%. power to verify the radial power distribution (RPD) predictions at low power. Figure 6.1 shows the measured RPDs from this flux map. Flux maps 3 and 5 were taken at 691 and 100%. power levels with different control rod configurations. These flux maps were taken to check at-power design predictions and to measure core power distributions at various operating conditions. The radial power distributions for these maps are given in Figures 6.2 and 6.3. These figures show that the measured relative assembly power values were generally within 3.71 of the predicted values. Flux map 2 was taken at-481 power for I/E calibration

.I" Page 32 of 57

e and flux map 4 was taken at 95% to give the operators a new target delta flux. The measured F-Q(Z) and F-DH(N) peaking factor values for the at-power flux maps were within the limits of Technical Specifications 3 .12 .B .1.

The design tolerance on core tilt (average quadrant power tilt from INCORE 3 ) was exceeded for the map taken at less than 30% power. This tolerance is set to ensure that the power distribution assumptions inherent in the safety analysis are met. The INCORE 3 tilt of 3.71%

(compared to a design tolerance of 2.24%) was evaluated as to the impact on safety analysis key physics parameters. The evaluation showed that a low power tilt of this magnitude would not cause any key physics parameters to ex<;:eed the corresponding safety analysis limits'. All Technical Specification in-core power distribution limits were met for flux map 01. The d*esign tolerance on core tilt was subsequently met for the higher power flux maps.

Prior to the first in-core/ex-core power range detector calibration, the cor*e tilt as measured by the ex-core detectors exceeded 2%. This condition existed for a period greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. As stated previously, hot channel factors were measured at 28% power and all limits were met. In accordance with Technical Specification 3.12.B.7, a special report was submitted to the NRC 5

The report included an evaluation of the possible causes of the core tilt. The ex-core quadrant power tilt limits were met following the first in-core/ex-core power range detector calibration.

In conclusion, the power distribution measurement results were considered to be acceptable with respect to the design tolerances (excepted as noted above), the accident analysis acceptance criteria, and NE-898 S1C12 Startup Test Report Page 33 of 57

the Technical Specification limits. It is therefore anticipated that the core will continue to operate safely throughout Cycle 12.

~~-~Q~ ~1C12 Startuo Test Report Page 34 of 57

e TABLE 6.1 SURRY UNIT 1 - CYCLE 12 STARTUP PHYSICS TESTS INCORE FLUX KAP

SUMMARY

l z BURN F-UCZJ HOT F-DHCNJ HOT CORE FCZJ CORE HAP HAP UP BANK CHANNEL FACTOR CHNL.FACTOR HAX TILT AXIAL NO.

DESCRIPTION HO. DATE HWD/ PWR D OFF OF HTU CZl STEPS ASSY PIN AXIAL ASSY PIN F-DHCN) AXIAL FCZ> HAX LDC SET THIH POINT F-QCZ> POINT (7.) BLES P ~ 30Z l 5-03-92 4 28 150 LOS DIC 31 Z.344 LOS DK 1.611 31 1.416 1.037 NW -5.30 48 I/E CALIBRATION 2 5-04-92 12 48 155 LOS DK 30 Z.14Z LOS DK l.SSZ 31 1.340 1.024 NW -4.87 48 50Z ~ P ~ 75,: 3 5-05-92 ZB 69 163 LOS DK 34 Z.0114 LOS DK 1.530 32 1.319 1.021 NW -5.94 48 TARGET DELTA FLUX 4 5-09-92 99 95 185 LOS DK 30 1.943 LOS DK 1.493 30 l.Z54 1.015 NW -0.89 48 95,: 2: P 2: 10oz 5 5-11-92 178 100 Z20 LOS DK 30 1.866 LOS DIC 1.475 30 l.Z09 1.016 NW 2.69 46 NOTES: HOT SPOT LOCATIONS ARE SPECIFIED BY GIVING ASSEHBLY LOCATIONS CE.G. H-8 IS THE CENTER-OF-CORE ASSEHBLY>,

FOLLOWED BY THE PIN LOCATION (DENOTED BY THE "Y"' COORDINATE WITH THE SEVENTEEN ROWS OF FUEL RODS LETTERED A THROUGH RAND THE "X" COORDINATE DESIGNATED IN A SIHILAR HAHNER).

IN THE "Z" DIRECTION THE CORE IS DIVIDED INTO 61 AXIAL POINTS STARTING FRON THE TOP OF THE CORE.

l. F-UCZI INCLUDES A TOTAL UNCERTAINTY OF 1.08 (87.J. '

Z. CORE TILT - DEFINED AS THE AVERAGE QUAIJRAHT POWER TILT FROlt IHCORE.

NF.-898 S1C12 Startup Test Report Page 35 of 57

e , ~

Table 6.2 SURRY UNIT 1 - CYCLE 12 STARTUP PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR TECHNICAL SPECIFICATION LIMITS PEAK F-Q(Z) HOT F-Q(Z) HOT F-DH(N) HOT CHANNEL FACTOR* CHANNEL FACTOR** CHANNEL FACTOR MAP MEAS LIMIT NODE MEAS LIMIT NODE MARGIN MEAS LIMIT MARGIN NO. (%) (%)

1 2.344 4.640 31 2.341 4.630 30 49.4 1.611 1.885 14.5 2 2.142 4.630 30 2.142 4.630 30 53.7 1.552 1. 791 13.3 3 2.084 3.340 34 2.084 3.340 34 37.6 1.530 1.692 9.6 4 1.948 2.445 30 1.946 2.421 26 19.6 1.4'P 1.575 5.2 5 1.866 2.315 30 1.859 2.293 26 18.9 1.475 1.550 4.8

The Technical Specification's limit for the heat flux hot channel factor, F-Q(Z), is a* function of core height. The value for F-Q(Z) listed above is the maximum value of F-Q(Z) in the core.

The Technical Specification's limit listed above is evaluated .at the plane of maximum F-Q(Z).

- The value for F-Q(Z) listed above is the value at the plane of m1n1mum margin. The minimum margin values listed above are the minimum percent difference between t~e measured values of F-Q(Z) and the Technical Specification's limit at that node for each map.

The measured F-Q(Z) hot channel factors include 8% total uncertainty.

I" NF.-~QR S1C12 Startun Test Report Page 36 of 57

e.

Figure 6.1 SURRY UNIT 1 - CYCLE 12 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 28% POWER p J H C F E D C II A R N

" L I(

PREDICTED *

0.29 0.31 0.29 PREDICTED *

"EASURED

0.31. 0.33. 0.31. * -tlEASIJRED

1

PCT DIFFERENCE.

7.1. 6.8. 5.4 * .PCT DIFFERENCE *

o.36

o.-75

1.10

0.90

1.10

o.76

o.36

0.39. 0.80. 1.16. 0.95. 1.15. 0.78. 0.37. z

8.1. 5.9. 5.3. 5.1. 4.0. Z.9. 3.4 *

0.40. 1.18. 1.29. l.Zl. 1.15. l.Zl 1.30 1.19 0.40

0.43. 1.25. 1.35. 1.27. 1.18. 1.24. 1.34. 1.23. 0.4Z

3

7.5

5.4

4.6

5.4

3.0

Z.6

Z.9

3.7

4.3 *

. 0.40. 0.97. 1.28. 1.31. 1.13. 0.93. 1.13 1.31 1.29 0.97 0.40 *

. 0.42. l.OZ. 1.33. 1.37. 1.18. 0.97. 1.16. 1.31. 1.29. 0.98. 0.40. 4

4.6. 5.0. 3.7. 4.5. 4.Z. 3.7. Z.4. 0.3. 0.6. 0.7. 0.9 *

. o.36. 1.18. 1.28. 1.39. 1.24. 1.oz. 1.14. 1.oz. 1.24. 1.40. 1.29. 1.19. o.36 .

. 0.37. l.Zl. 1.34. 1.48. 1.30. 1.05. 1.17. 1.03. l.Z5. 1.40. l.Z6. 1.18. D.36. 5

. Z.5. Z.5. 4.4. 6.1. 4.8. 3.4. Z.6. 1.6 ** 1.0. 0.1. -z.z. -0.7. l.Z *

. 0.75. 1.29. 1.31. 1.24. l.lZ 1.14 l.Z6 1.14 l.lZ l.Z4 1.31 1.29. D.75

. 0.77. 1.33. 1.37. 1.31. 1.16. 1.15. 1.27. 1.14. l.lZ. l.Z3. 1.27. l.ZS. 8.73. 6

. Z.7. Z.7. 4.5. 5.8. 3.9. 1.3. 1.3. o.z. -0.l. -0.9. -Z.9. -3.4. -Z.6.

O.Z9. 1.10. l.ZO. 1.13. l.OZ. 1.14. 1.25. l.Zl. l.Z6. 1.14. 1.oz 1.13 l.Zl 1.10. O.Z9

0.31 . 1.15. 1.24. 1.11. 1.05.1015. 1.z4. 1.zo. l.Z3. 1.12. o.98. 1.01. 1.14. 1.03. o.za. 7

. 8.2. 5.0

3.0. 3.6. 3.3. 1.3. -0.9. -0.S. -1.a. -z.o. -3.Z. -5.3. -5.3. -6.l. -5.6

0.31 0.90 1.14. 0.93. 1.13. 1.26. 1.zo 1.19 1.zo. 1.Z6 1.14 o.93 1.14 o.9o. o.31

. o.34. o.94. 1.zo

o.96. 1.15. 1.21. 1.19. 1.16. 1.15. 1.zo. 1.01. o.a9. 1.09. a.as. ~.3o. a

. 7.7. S.Z. 4.9. 3.3. l.S. 1.3. -1.l. -Z.5. -4.4. -4.8. -5.6. -4.9. -4.8. ~.7. -4.3.

0.29 1.10. l.Zl 1.13. l.OZ 1.14 l.Z6. 1.zo. 1.zs. 1.14. 1.01. 1.13 l.ZO 1.10 D.29 *

. o.3Z. 1.11. 1.26. 1.11. 1.05. 1.15. 1.23. 1.16. 1.19. 1.06. o.95. 1.01. 1.14. 1.05. o.za. 9

. a.z. 5.9. 4.7. 3.7. 3.6. 1.3. -z.z. -3.5. -4.9. -6.6. -6.1. -5.4. -5.o. -4.3. -3.z*.

0.7S. 1.30. 1.31 1.24 1.12 1.14 l.ZS. 1.13. 1.11. 1.23 1.30 1.29 0.75

. 0.78. 1.35. 1.36. 1.29. 1.13. 1.11. l.ZZ. 1.09. 1.07. 1.18. 1.23. l.Zl. 1.71. 10

. 4.0. 4.0. 4.Z. 4.Z. 1.0. -Z.4. -3.l. -4.1. -4.3. -4.6. -S.8. -5.9. -5.4.

o.36 1.19. 1.29. 1.39. 1.24. 1.01. 1.13. 1.01 1.zz 1.~a. 1.za. 1.111. o.36 *

o.38. 1.zs. 1.35. 1.45. 1.24. o.99. 1.10. o.99. 1.21. 1.33 .* 1.z3. 1.13. o.34. 11

5.6

5.6

5.0

4.3

D.6 * -Z.6 * -Z.9 * *-Z.l * -1.5 * -3.6 * -3.9 * -4.0 * -4.4 *

o.4o. o.97. 1.2a. 1.31. 1.13. o.93. 1.12. 1.29. 1.26. o.96. o.4o *

. 0.43. 1.03. 1.34. 1.31. 1.10. 0.90. 1.08. l.ZS. l.ZZ. 0.93. 0.39. lZ

7.Z. 6.0. 4.Z. O.Z. -Z.6. -Z.9. -3.1. -3.3. -3.3. -3.0. -z.z.

0.40 1.19. 1.30 l.Zl. 1.14 1.19 1.27. 1.16. D.39 *

0.42

1.zz

1.30

1.11

1.10

1.14

1.zo

1.11

o.311

13

5.Z

3.Z

0.4 * -z.a * -3.4 * -4.5 * -5.l * -4.3 *. -Z.6 *

0.36 D.75. 1.10. 0.89. 1.09. D.74. 0.35 *

0.37. 0.76. 1.07. D.86. 1.03. 8.70. 0.33. 14

3.Z. 1.3. -Z.4. -3.9. -5.Z. -5.Z. -5.l.

STANDARD 0.29

0.31

0.29 *

AVERAGE

DEVIATION *

0.29. C.30. O.Z7. .PCT DIFFERENCE. 15

l.837 * -1.8. -3.3. -5.5.

3.7 SUNHARY HAP NO: Sl-12-01 DATE: 05/03/92 POWER: 281.

CONTROL ROD POSITIONS: F-QCZJ = 2.344 CORE TILT CINCOREJ:

D BANK AT 150 STEPS F-DH(NJ = 1.611 NW 1.0371 NE 0.9958 F(ZJ = 1.416 SW 1.0171 SE D.9500 BURNUP = 4 fflfD/tfTU A*.C. = -S.3!!1.

NF.-898 S1Cl2 Startup Test Report Page 37 of 57

e* e Figure 6.2 SURRY UNIT 1 - CYCLE 12 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 69% POWER.

R p N L K J H G F E D C I A PREDICTED *

0.32. 0.34. 0.32. PREDICTED *

~ASURED

0.33. 0.36. 0.33.

HEASURED

l

. PCT DIFFERENCE.

5.7. 5.4. 4.0 * .PCT DIFFERENCE *

0.37. 0.77. 1.12. 0.95. 1.13. 0.77. 0.37.

0.38. 0.80. 1.16. 0.98. 1.15. 0.78. 0.38

2

3.6. 3.9. 3.5. 3.2. 2.4. 1.5. 2.5 *

0.41. 1.17. 1.27. 1.21. 1.15. 1.21. 1.27. 1.17. 0.41.

o.42. 1.19. 1.30. 1.25. 1.11. 1.22. 1.29. 1.21. o.43

3

3.1. 1.5. 2.1. 3.4. 1.1. 0.9. 1.5. 3.0. 3.9 *

. o.41. o.96. 1.25. 1.2a. 1.12. o.94. 1.12. 1.28. 1.25. o.96. o.41 *

0.42. 0.98. 1.25. 1.32. 1.16. 0.97. 1.13. 1.30. 1.27. 0.98. 0.41. 4

2.3. 2.1. 0.5. 2.7. 3.3. 2.6. 0.5. 1.6. 1.5. 1.4. 1.0.

o:;;*:*i:i,*:*i:zs*:*i:;;.*:*i:zz*:*i:02*:*i:i;*:*i:02*:*i:zz*:*i:;;.*:*i:zs*:*i:i,*:*o:i,*:

o.38. 1.19. 1.2a. 1.41. 1.26. 1.06. 1.11. 1.04. 1.24. 1.38. 1.24. 1.11. o.37

5

1.6. 1.6. 2.3. 3.B. 3.3. 4.2. 3.2. 1.6. 1.5. 1.3. -0.8. -0.4. 0.5 *

0.11. 1.21. 1.2a. 1.22. 1.14. 1.14. 1.25. 1.14. 1.14. 1.22. 1.2a. 1.21. o.77 *

0.78. l.Z9. 1.31. 1.26. 1.17. 1.16. 1.27. 1.14. 1.14. l.2Z. 1.26. 1.24. 0.75. 6

. 1.1. 1.6. 2.1. 3.1. z.a. z.o. 1.a. o.6. 0.1. -o.o. -1.4. -z.5. -z.6 *

0.32. 1.12. 1.20. 1.12. l.OZ. 1.13. 1-24. 1.zo. 1.25. 1.14. 1.02. 1.12. l.Zl. 1.12. 0.32 *

o.3z. 1.15. 1.23, 1.14. 1.03. 1.14. 1.zs. 1.20. 1.24. 1.13. 1.00. 1.oa. 1.16. 1.01. 0.30. 7

. 2.3. z.4. 1.9. 1.a. 1.z. o.6. 0.2 *. 0.3. -o.a. -o.6. -1.6. -3.6. -3.8. -5.o. -4.2 *

. 0.34. 0.95. 1.15. 0.94. 1.13. 1.25. 1.19. 1.19. 1.19. 1.25. 1.13. 0.94. 1.15. 0.95. 0.34 *

. o.35. o.97. 1.19. o.96. 1.13. 1.26. 1.19. 1.1a. 1.1a. 1.23. 1.11. 0.91. 1.12. o.9Z. o.33. a

. 1.9. z.2. 3.1. z.o. 0.2. o.9. o.o. -0.1. -1.6. -1.6. -Z.5. -3.4. -3.3. -z.a. -z.1 *

0.32. l.lZ. 1.21. 1.12. I.OZ. 1.14. 1.25. 1.19. 1.24. 1.14. l.OZ. 1.12. l.Zl. 1.12. 0.32 *

. o.3Z. 1.15. 1.23. 1.14. 1.05. 1.15. 1.24. 1.1a. 1.23. 1.10. o.99. 1.10. 1.1a. 1.10. o.31. 9

. Z.3. Z.l. 1.9. Z.l. 3.4. 1.3. -1.0. -1.0. -1.5. -Z.9. -z.z. -z.z. -2.6. -Z.3. -1.5 *

0.11. 1.21. 1.2a. 1.22. 1.14. 1.13. 1.zs. 1.~3. 1.14. 1.zz. 1.2a. 1.21. o.77 *

0.11. 1.21. 1.31. 1.26. 1.16. 1.12. 1.24. 1.12. 1.12. 1.zo. 1.26. 1.24. o.74. 10

o.3. o.3. z.o. 3.3. 1.5. -1.0. -a.a. -1.3. -1.9. -1.1. -1.6. -2.5. -3.l *

o.37. 1.11. 1.zs. 1.36. 1.22. 1.02. 1.13. 1.oz. 1.21. 1.35. 1.24. 1.11. o.37.

- 0.38. 1.20. 1.za. 1.39. 1.22. 1.01. 1.12. 1.01. l.Zl. 1.33. 1.23. 1.15. 0.36. 11

Z.3. Z.3. Z.4. Z.6. 0.5. -0.9. -0.6. -o.3. -0.4. -1.a. -1.4. -1.3. -1.a *

0.41. 0.96. 1.25. 1.28. 1.12. 0.94. 1.11. 1.27. 1.23. 0.96. 0.41.

o.43. 1.00. 1.2a. 1.2a. 1.10. o.93. 1.09. 1.24. 1.zo. o.94. o.41

lZ

4.4. 3.7. z.5. 0.2. -1.4. -1.5. -1.9. -2.3. -z.z. -1.6. 0.2 *

o.41. 1.11. 1.21. 1.21. 1.15. 1.zo. 1.zs. 1.15. n.4o *

D.42. 1.17. 1.27. 1.18. 1.12. 1.15. 1.20. 1.11. 0.40. 13

2.4. o.3. -o.5. -2.0. -2.6. -3.7. -4.5. -3.S. -1.0 *

0.37. 0.77. 1.13. 0.95. 1.12. D.76. D.36.

D.37. 0.77. 1.10. 1.92. 1.07. 0.73. 0.35

14

0.3. -0.5. -2.2. -3.1. -4.1. -4.3. -4.6

STANDARD *

1.32. 1.34. 0.31.

AVERAGE

DEVIATION *

0.31 .*C.33. 1.31. .PCT DIFFERENCE. 15

l.ZZ2 * -2.l. -3.1. -4.2.

2.1 SUlfflARY HAP NO: Sl-12-03 DATE: 05/05/92 POWER: 697.

CONTROL ROD POSITIONS: F-Q(Z) = 2.084 CORE TILT (INCORE):

D BANK AT 163 STEPS F-DH(N) = 1.530 NW 1.0207 NE 0.9994 F<Z> = 1.319 SW 1.0068 SE 0.9732 BURNUP = 28.4 tND/tlTU A.O.= -S.9427.

.....;;.~,~~~-~R~o::....::R~~~~1~r-'--'-1' ~t~rtuo Test Report Page 38 of 57

-e e Figure 6.3 SURRY UNIT 1 - CYCLE 12 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 100% POWER p L It J H C F E D II A R N

" C PREDICTED

0.33 0.37 0.34 PREDICTED

NEASURED . 0.35. 0.39. 0.35. NEASURED 1

PCT DIFFERENCE.

5.1. 5.0. 3.3 * .PCT DIFFERENCE *

0.37. 0.76. 1.14. 1.04. 1.15. 0.76. 0.37

0.38. 0.79. 1.18. 1.07. 1.17. 0.77. 0.311. z

4.6

3.9

3.Z - Z.9

1.7

0.6

Z.l *

0.40. 1.13. l.Z3. l.ZO. 1.17. 1.zo. l.Z4. 1.13 0.40 *

0.4Z. 1.15. l.Z6. l.Z4. 1.18. l.Zl. l.Z4. 1.16. 0.4Z. 3

4.1. Z.l. Z.Z. 3.3. 0.7. 0.3. 0.6. 3.0. 4.5 *

0.40. 0.93. 1.zo. l.Z5. 1.11. 0.94 1.11 l.ZS. l.ZO. 0.93. 0.40 *

0.41. 0.95. l.Zl. l.Z8. 1.14. 0.96. 1.11. l.Z6. l.ZZ. 0.95. 0.41. 4

. Z.4. Z.l. 0.6. Z.l. Z.7. z.o. 0.1. 1.1. 1.3. 1.4. 1.6 *

. 0.37. 1.13. l.ZO. 1.33. l.ZZ 1.03_. 1.13. 1.03 l.ZZ. 1.33. 1.zo. 1.13 0.37

0.37. 1.14. l.ZZ. 1.37. l.Z5. 1.06. 1.16. 1.05. l.Z4. 1.34. 1.19. 1.13. 0.37. 5 1.0. 1.0. 1.1. z.8. z.4. 3.o. z.9. z.o. 1.z. 0.1. -1.z. o.z. 1.9.

0.76. l.Z3. 1.25. 1.zz. l.Z3. 1.16 l.Z5. 1.16. l.Z3. l.ZZ. 1.25. l.Z4. 0.76 * --'

. 0.77. l.Z4. l.Z7. 1.26. l.Z6. 1.18. l.Z8. 1.17. l.Z5. l.ZZ. l.Z3. l.Zl. 0.75. 6

0.6. 0.6. 1.9. Z.7. Z.4. Z.l. Z.4. 1.4. 1.0. -o.l. -1.4. -z.o. -1.8.

o.33 1.14. 1.zo. 1.11. 1.03. 1.16. 1.Z6. 1.zo. 1.z6. 1.16. 1.03. 1.11. 1.zo. 1.15. o.34 *

0.34

1.16

l.ZO ** l.lZ

1.04

1.17

l.Z6

l.Zl

l.Z7

1.16

I.DZ

1.08 . 1.16

1.09

0.3Z

7

z.5. 1.3. o.4. 1.0. 1.z. o.9. 0.1. 1.1. o.4. o.3. -o.9. -Z.8. -3.8. -5.o. -4.7

0.37 1.04. 1.17. 0.94. 1.13. 1.25. l.ZO 1.19. l.ZO. l.ZS. 1.13. 0.95. 1.17. 1.04. 0.37 *

. o.38. 1.06. 1.19. o.95. 1.13. 1.z5. 1.zo. 1.19. 1.19. 1.24. 1.11. o.9Z. 1.13. 1.00. o.36. 8 I

Z.4. 1.6. 1.6. 0.7. -0.1. 0.1. 0.5. 0.0. -0.7. -0.6. -1.7. *3.1. -3.5. -3.6. *3.Z. I o.33 1.15 1.zo 1.11 1.03. 1.16. 1.26. 1.zo. 1.26. 1.16. 1.03. 1.11. 1.zo. 1.15. o.33 *

. 0.34. 1.16. l.Zl. 1.11. l.OZ. 1.16. 1.26. 1.19. l.ZS. 1.14. 1.00. 1.08. 1.16. 1.12. 0.33. 9

z.5. 1.5. 1.0. o.6. -0.1. -o.z. o.4. -o.5. -o.8. -z.1. -z.z. -3.3. -3.3. -2.8. -1.8.

o.76 1.z4 1.z5 1.zz. 1.Z3. 1.16. 1.25. 1.16. 1.24. 1.23. 1.Z6. 1.z4. o.77 *

o.76. 1.z4. 1.26. 1.25. 1.26. 1.15. 1.24. 1.15. 1.2z. 1.zo. 1.zz. 1.zo. o.74. 10 0.1. 0.1. 0.9. z.o. 1.9. -o.6. -o.6. -o.8. -1.1. -1.8. -3.o. -3.Z. -3.o.

o.37 1.13. 1.zo. 1.33. 1.zz. 1.03. 1.13. 1.03. 1.zz. 1.33. 1.zo. 1.13. o.37 *

o.38. 1.16. 1.z3. 1.36. 1.Z3. 1.01. 1.1z. 1.03. 1.zz. 1.32. 1.19. 1.12. o.36. 11

. z.4. 2.4. z.z. z.o. a.6. -1.1. -0.1. -0.1. 0.1. -1.z. -1.1. -1.0. -1.4.

0.40 0.93. l.Zl. l.Z5. 1.11 0.95. 1.11. l.ZS. l.ZO. 0.93. D.4D *

0.4Z. D.97. l.Z3. l.ZS. 1.09. D.93. 1.09. l.Z3. 1.18. D.93. 0.40. lZ

4.7. 3.6. z.o. -o.z. -1.1. -1.9. -1.a. -1.5. -1.1. -o.z. 1.0 *

0.40. 1.13. l.Z4. l.Zl. 1.17. l.ZO. 1.23. l.lZ. 0.40 *

0.4Z. 1.16. l.ZS. 1.18. 1.13. 1.16. 1.18. 1.09. 0.4U. 13

3.8. Z.9. 0.7. -Z.5. -3.3. -3.8. -3.6. -Z.3. D.3 *

0.37. 0.77. 1.15. 1.04. 1.14. 0.76. D.36 *

0.311. D.77. l.lZ. 1.01. 1.10. 0.73. 0.35. 14

Z.9. 1.1. -Z.3. -3.3. ~.2. -3.9. -3.5.

STANDARD *

D.34. 0.37. 1.33.

AVERAGE

DEVIATION *

D.33. 0.36. D.3Z. .PCT DIFFERENCE. 15

=l.Z74 * -1.6. -Z.7. -4.4.

1.9 SUHHARY HAP NO: Sl-12-05 DATE: 05/11/92 POWER: 1007.

CONTROL ROD POSITIONS:* F-Q(Z) = 1.866 CORE TILT (INCORE):

D BANK AT 220 STEPS F-DH(N) = 1.475 NW 1.0164 NE 0.9998 FlZJ = 1.209 SW 1.0053 SE 0.9786 BURNUP = 178 HWD/NTU A.O. = 2.692%

Page 39 of 57

e. e SECTION 7 REFERENCES

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

Technical Report NE-881, Revision O, Virginia Power, March, 1992.

2. T. K. Ross, W. C. Beck, "Control Rod Reactivity Worth Determination By The Rod Swap Technique," VEP-FRD-36A, December, 1980.

3. W. Leggett and L. Eisenhart, "The INCORE Code," WCAP-7149, December, 1967.

4. Surry Unit 1 and 2 Technical Specifications, Sections 3.1.E.1, 3.12.B.1, 3.12.B.7, 3.12.C.1, and 4.10.

5. "Virginia Electric and Power Company Surry Power Station Unit 1 Special Report Quadrant to Average Power Tilt Exceeds 2.0% for Greater than 24 Hours", letter from W.L. Stewart (VP) to Document Control Desk (USNRC), Serial No.92-377, dated June 3, 1992.

6. "Surry Power Station Unit 1 M/D Map Sl-12-01 Results", memo from C.B. LaRoe to J.W. Henderson, dated May 4, 1992.

..!'c!.!'":........o~n~o-~<:"_!_1~r1 '>_ S +-" .-f-11n 'T'p !": t Rf'DOTt Page 40 of S7

e APPENDIX STARTUP PHYSICS TESTS RESULTS AND EVALUATION SHEETS NE-898 S1Cl2 Startup Test Report Page 41 of 57

e SURRY POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Zero Power Testing Range Determination Reference Proc No /Section: l-NPT-RX-008 Sequence Step No:

II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): 0 Gonditions SDA: 225 SDB: 225 CA: 225 Other (specify):

(Design) CB: 225 CC: 225 CD:* Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ( °F): 54fo. 3 Test Power Level (X F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify) :

(Actual) CB: 225 cc: -m:l\tl;.Fd q5 Below Nuclear Heating Date/Time Test Performed:

s /'). /q;;. 03:3;;1.

Reactivity Computer IV Initial Flux toi:ls X lO

-~amps Background Reading Flux Reading At Point of Nuclear llN. 1:,.0 -7 Heating sJ~;J. -3;&~ lO amps Test Results

l110Y..IQ-~ to ID,Q )( lO-~amps Zero Power Testing Range Reference Not Applicable V FSAR/Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met** : ?YES _NO VI Acceptance Criteria is met** : _YES _NO Comments

At The Just Critical Position

- Design Tolerance and Acceptance Criteria are met if ZPTR is below Point of Nuclear Heating and above background.

Prepared By: L~<.(_* Reviewed By:

~~-Rg~ s1r.12 St3rtuo Test Report Page 4Z of 51

e. e SURRY POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Reactivity Computer Checkout Reference Proc No /Section: l-NPT-RX-008 Sequence Step No:

II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level (t F. P. )_: 0

.Conditions SDA: 225 SOB: 225 CA: 225 Other (specify):

(Design) CB: 225 CC: 225 CD:

Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (°F) :S41. I Test Power Level (t F.P.): 0 Conditions SDA: 225 SOB: 225 CA: 225 Other (Specify):

(Actual) CB: 225 cc: m ~J,.,.<tS. Below Nuclear Heating Date/Time Test Performed:

5/~r,~ ol..(:SS Measured Parameter Pc = Heas. Reactivity using p-compute r IV (Description) Pt = Predicted Reactivity Pc= + '"'~-s -44 .. 0 Measured Value Pt= ... 'ii .5 - L\'-\.,

Test tD = - d-o \ -1 .. (c Results Design Value %D = {(pc-Pt)/pt} x lOOt S 4.0t Reference WCAP 7905, Rav. 1, Table 3.6 V FSAR/Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met : _LYES ~NO*

VI Acceptance Criteria is 11et : ..L_YES _NO Comments

At The Just Critical Position Allowable Range = :!: + '-I b. S , - ~ l.{ .. 0 Prepared By: '1-:rQ~"C.-

Reviewed By:

Page 43 of 57

e

...... - SURRY POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET

.-. - ~ - - .- ~ - .

r. **.:. --:. *. -

I Test

Description:

Critical Boron Concentration - ARO Reference Proc No /Section: 1-NPT-RX-008 Sequence Step No:

II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: 225 sos*: 225 CA: 225

Other (specify) :

(Design) CB: 225 CC: 225 CD: 225 Below Nuclear Heating Ill Bank Positions (Steps) RCS Temperature (°F): s~,.'I Test Power Level(% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify):

(Actual) CB: 225 CC: 225 CD: 225 ~elow Nuclear Heating, Date/Time Test Performed:

s/1/'11 I O'i'lo Heas Parameter H*

rv (Description) (Ce) ARO; Critical Boron Cone - ARO Measured Value H Test (Design Cond) (Ce) ARO= li'1'2..

Results

- Design Value (Design Cond) CB= 1811 +/- 50 PP*

Reference Technical Report NE-881, Rev. 0

. D V FSAR/Tech Spec aC8 x c8 S 1000 pea Acceptance Criteria Reference Technical Specification 4.10.A Design Tolerance is 11et . LYES _NO Acceptance Criteria is 11et . ,/ YES _NO VI Comments ac8 = -7.36 pcm/pp*

D K CB= l(CB) ARO - -~151; CB is design value~

Prepared By:

u.,. ~---- Reviewed B J ~ ~

=u.:..i;-.::.-.:.Ao:::_R:_____.c::'--','-'-'-r,, StArtno T*est Reoort Page 44 of 57

e e SURRY POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Isothermal Temperature Coefficient - ARO Reference Pree No /Section: 1-NPT-RX-008 Sequence Step No: '

II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):

(Design)

CB: 225 CC: 225 *CD: 225 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (°F): !9+5 Test Power Level(% F.P.): 0 Conditions SDA: 225 SOB: 225 CA: 225 Other (Specify):

(Actual) CB: 225 CC: 225 CD: Below Nuclear Heating Date/Time Test Performed:

s /1-/,1. I I O~f Meas Parameter ISO IV *(Description) (a T )ARO Isothermal Temp Coeff - ARO ISO Test Measured Value (a T )ARO = -Z.I (0 pcJJ./°F (CB = tC'iJl. ppm)

Results Design Value ISO .,. Ii (Actual Cond) (a T )ARO= -2,.c; I pcra/°F (CB = *l. ppm) *r

'*-1 I

ISO Design Value (a T )ARO= -2.81 +/- 3.0 pcm/°F (Design Cond)

(CB = 1811 ppm)

Reference Technical Report NE-881, Rev. 0 V ISO Dop Acceptance FSAR/Tech Spec a T .s o.a2*pcm/°F a T = -1.68 pcm/°F Criteria Reference TS 3.1.E, Technical Report NE-881, Rev. 0 VI Design Tolerance is met Acceptance Criteria is met * - -_NO

./' YES

..lal.,YES NO Comments

Uncertainty on aTHOD = 0.5 pcm/°F (

Reference:

memorandum from C. T. Snow to E. J. Lozito dated June 27, 1980).

Prepared By: * '&, y'/. L Reviewed By: ~ Si).~

~,r.,, ~tartun Test Report Page 45 of 57

e e SURRY POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Cntl Bank B Worth Heas.,Rod Swap Ref. Bank Reference Proc No /Section: l-NPT-RX-008 Sequence Step No:

II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other {specify) :

(Design) CB:Hoving CC: 225 CD: 225 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (°F): S'fG,..3 Test Power Level (t F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify):

(Actual) CB:Hoving CC: 225 CD: 225 Below Nuclear Heating Date/Time Test Performed:

6/z./llf7- 12-ot REF Measured Parameter I B ; Integral Worth of Cntl Bank B, (Description) All Other Rods Out IV REF Test Measured Value I B = J'3e-'Z. 0 Results '

Design Value REF (Design Conditions) I B = 1324 +/- 132 pcm Reference Technical Report NE-881, Rev. 0 If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result V FSAR/Tech Spec on safety analysis. SNSOC may specify Acceptance . that additional testing be performed

Criteria Reference VEP-FRD-36A Design Tolerance is met : _:!__YES _NO VI Acceptance Criteria is 11et : ..i._YES _NO Comments Reviewed By: i,J.i,: t£. W,cou,,

~)J'...'.:i;-....:-~R~a~R-~c::21cr1 ? . ~ t- ~ rt11n Test Reoort 46 of 57

e e SURRY POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Critical Boron Concentration - B Bank In Reference Pree No /Section: l-NPT-RX-008 Sequence Step No:

+------------------------------

II Bank Positions (Steps) RCS Temperature (°F): 547 Test Conditions SilA: 225 SOB: 225 CA: 225.

Power Level(% F.P.): 0 Other (specify):

(Design) CB: 0 CC: 225 CD: 225 Below Nuclear Heating

+------"'---------+--------------

III _____________

.__Bank Positions (Steps) _, RCS Temperature (°F): .s3',,~-

Test Power Level(% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify):

(Actual) CB: 0 CC: 225 CD: 225 Below Nuclear Heating

+-----~--------~

Date/Time Test Performed:

~fi'2- / 2./) I' Meas Parameter H IV (Description)* (CB)B; Critical Boron Cone - B Bank In H

Measured Value (CB)B = /659 i'P"'

Test (Design Cond)

Results Prev Design Value C8 = 1632 + AC 8 +/- (10 + 132.4/laC 8 f)ppm (Design Cond)

CB = /b '-3 ppm : .:2 8' /?I'~

Reference Technical Report NE-881, Rev. 0 V FSAR/Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met : ...t:::)ES _NO Acceptance Criteria is met : .......rfs _NO VI Comments ac 8 = -7.40 pcm/ppm Prev H ACB = (CB)ARO - 1811

/3~ 1.. - / Ill ~ .3 f ff'"'

Prepared Reviewed By: ;;c 8.e..l NE-898 S1C12 Startup Test Report Page 47 of 57

e SURRY POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

HZP Boron Worth Coefficent Measurement Reference Proc No /Section: 1-NPT-RX-008 Sequence Step No:

II Bank Positions (Steps) RCS Tempera~~re (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):

-(Design) CB:Hoving CC: 225 CD: 225 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (°F): s.Y,,

Test Power Level(% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify):

(Actual) CB:Hoving CC: 225 CD: 225 Below Nuclear Heating Date/Time Test Performed:

s;i.A;_

7

/ :z..o; Measured Parameter IV (Descript~on) ac8 , Boron Worth Coefficient Measured Value aCB = - 7, <I~ fu,,.ltl'f(\

Test Results Design Value (Design Conditions) ac 8 = -7.40 +/- 0.74 pcm/ppm Reference Technicai Report NE-881, Rev. 0 FSAR/Tech Spec Not* Applicable V

Acceptance Criteria Reference Not Applicable Design Tolerance is met : /yES _NO VI Acceptance Criteria is 11et : .....-YES _NO Comments Prepared Reviewed By:

ur. - o o o Page

e. e.

SURRY POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Cntl Bank D Worth Measurement-Rod Swap Reference Proc No /Section: 1-NPT-RX-008 Sequence Step No:

II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level (t F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):

(Design) CB:Moving CC: 225 CD:Moving Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (°F): St'!>,?

Test Power Level(% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify):

(Actual) CB:Moving CC: 225 CD:1foving Below Nuclear Heating Date/~e* Test Performed:

S:,

'2../92.-

/

/71/'/

Meas Parameter RS (Description_) In; Int Worth of Cntl Bank D-Rod Swap IV RS (Adj. Keas. Crit. Ref Bank Test Measured Value In* = /097,7 iX"'Position =J,I steps)

Results Design Value RS (Adj. Meas. Crit. Ref Bank (Actual Cond) Io = //OY f J,'- ~1ition = /l,'I steps)

RS Design Value Io= 1104 +/- 166 pcm (Critical Ref Bank (Design Cond) .Position= 184 steps)

Reference Technical RepQrt NE-881, Rev. O, VEP-FRD-36A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed.

Criteria .

Reference VEP-FRD-36A Design Tolerance is met : ~S_NO VI Acceptance Criteria is met : S ~NO Comments Prepared By~c;U Reviewed By:

We-RQR s1r.12 Startup Test Report Page 49 of 57

e*

SURRY POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Cntl Bank C Worth Measurement-Rod Swap Reference Pree No /Section: l-NPT-RX-008 Sequence Step No:

II Bank Positions (Steps) RCS Temperature (°F): *547 Test Power Level(% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):

(Design) CB:Hoving CC:MovingCD: 225 Below Nuclear Heating Ill Bank Positions (Steps) RCS Temperature (°F): sz;,.,

Test Power Level(% F.P.): 0

.Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify):

(Actual) CB: _Hoving CC: Hov ingCD: 225 Below Nuclear Heating Date/Tt-4 Test Performed:

~;. 1-- /~3</

I ,

Meas Parameter RS (Description) Ic ; Int Worth of Cntl Bank C-Rod Swap IV RS . (Adj. Meas. Crit. Ref Bank Test . Measured Value le = g73, S' pe,11 Position = /.3, steps)

Results Design Value RS (Adj. Meas. Crit. Ref Bank (Actual Cond) Ic = 91~,7 Position = /3, steps)

-/37 ~

RS Design Value le= 902 +/- 135 pcm (Critical Ref Bank (Design Cond) Position= 156 steps)

Reference Technical Report NE-881, Rev. o, VEP-FRD-36A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed.

Criteria Reference VEP-FRD-36A Design Tolerance is met : ~S_NO VI Acceptance Criteria is aet : _YES _NO Comments Prepared B y ~ . £ ? X #

Reviewed By:

r

\.TC' - !!O !!

~,ri? ~-t::irt11n 'l'Pst Reuort Page

e SURRY POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Cntl Bank A Worth Measurement-Rod Swap Reference Proc No /Section: 1-NPT-RX-008 Sequence Step No:

II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level (t F.P.): 0 Conditions SDA: 225 SDB: 225 CA:Moving Other (specify):

(Design)* CB :Hoving CC: 225. CD: 225 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (°F): .sY,,

Test Power Level (t F.P.): 0 Conditions SDA: 225 SOB: 225 CA:Hoving Other (Specify):

(Actual) CB:Hoving CC: 225 CD: 225 Below Nuclear Heating Date/Time Te$t Performed:

s/:L/'12-- /9()/

Meas Parameter RS (Pescription) IA ; Int Worth of Cntl Bank A-Rod Swap IV RS . (Adj. Meas. Crit. Ref Bank Test Measured Value IA = 3'ic/. 'I f=P\ Position= t'l--steps)

Results Design Value RS (Adj. Meas. Crit. Ref Bank (Actual Cond) IA = ~61l'1til,e.;,.. Position = /'l-steps)

RS Design Value IA= 419 +/- 100 pcm (Critical Ref Bank (Design Cond) Position= 96 steps)

Reference Technical Report NE-881, Rev. O, VEP-FRD-36A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed.

Criteria Reference VEP-FRD-36A Design Tolerance is met : ~S_NO VI Acceptance Criteria is met : -~-NO Comments Prepared By ~~ , (k;/ ~, -*p .. Reviewed ~y: ~2.Pal.

_W'f:'-RQR ~1Cl2_Startuo*Test Report Page 51 of 57

e. .

SURRY POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Shutdown Bank B Worth Meas. - Rod Swap Reference Proc No /Section: l-NPT-RX-008 Sequence Step No:

II Bank Positions (Steps) R_CS Temperature ( °F) : 547 Test Power Level Ct F.P.): 0 Conditions SDA: 225 SDB:HovingCA: 225 Other (specify):

(Design) CB:Hoving CC: 225 CD: 225 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (°F): s-'1$"; 7 Test Power Level (l F.P.): 0 Conditions SDA: 225 SDB:HovingCA: 225 Other (Specify):

(Actual) CB:Hoving CC: 225 CD: 225 Below Nuclear Heating Date/Ti~Test Performed:

Si'-, 92- /~/9 Meas Parameter RS (Description)" 1SB; Int Worth of Shutdown Bank B-Rod Swap IV RS / / (Adj. Meas. Crit*. ~ef Bank Test Measured Value 1sB = //I , Ftf\ Position =/&l..steps)

Results Design Value RS ~O (Adj. Hess. Crit. Ref Bank (Actual Cond) 1sB =//7 t J'7~ ~osition =/l'~teps)

RS Design Value 1sB = 1174 +/- 176 pcm (Critical Ref Bank (Design Cond) Position = 194 steps )

Reference Technical Report NE-881, Rev. o, VEP-FRD-36A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/Tech Spec. safety analysis. SNSOC may specify that Acceptance additional testing be performed.

Criteria Reference VEP-FRD-36A Design Tolerance is met : VYES _NO VI Acceptance Criteria is met : ~S_NO Comments Prepared Reviewed By:

'-lt:"_ QOR

~,r,? ~t-:i,-t,in Test Reoort Page

e e SURRY POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Shutdown Bank A Worth Meas. - Rod Swap Reference Proc No /Section: 1-NPT-RX-008 Sequence Step No:

II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level (1 F.P.): 0 Conditions SDA:HovingSDB: 225 CA: 225 Other (specify):

(Design) CB:Hoving CC: 225 CD: 225 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (°F): ~-YS:

Test Power Level (1 F.P.): 0 Conditions SDA:HovingSDB: 225 CA: 225 Other (Specify):

(Actual) CB:Hoving CC: 225 CD: 225 Below Nuclear Heating Date/Time Test Performed:

s;;/9J

/ /

/9.Y?

Heas Parameter RS (Description) 1 sA; Int Worth of Shutdown Bank A-Rod Swap IV RS (Adj. Meas. Crit. Ref Bank Test Measured Value 1sA = 938,, p,- Position =/?$'steps)

Results

Design Value RS (Adj. Heas. Crit. Ref Bank (Actual Cond) 1 sA = 9'";~1/Y-,_..,. !osition = /YYsteps)

RS Design Value 1 sA = 960 "+/- 144 pcm (Critical Ref Bank (Design Cond) Position= 164 steps )

Reference Technical Report NE-881, Rev. 0, VEP-FRD-36A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed.

Criteria Reference VEP-FRD-36A J

./

Design Tolerance is met :

VI Acceptance Criteria is aet --:~

_ ES _NO NO Comments Prepared

B y : ~ ~ Reviewed By:

NE-898 S1C12 Startup Test Report r:

Page 53 of 57

e SURRY POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Total Rod Worth - Rod Swap Reference Pro~ No /Section: l-NPT-RX-008 Sequence Step No:

II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level (t F.P.): 0 Conditions SDA:Hoving SDB:Hoving CA:Hoving Other (specify):

(Design) CB:Hoving CC:Hoving CD:Ht>ving Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ( °F): S"'l5'i b Test Power Level(% F.P.): 0 Conditions SDA:Hoving SDB:Hoving CA:Hoving Other (Specify) :

(Actual) CB:Hoving CC:Hoving CD:Hoving Below Nuclear Heating D a ~ ~ . s t Performed:.

2- 2-C:2..1.......

/ /

Meas Parameter (Description) 1Total; Int Worth of All ~anks - Rod Swap IV Test Measured Value 1Total = gs;i.,7 ;:;~

Results Design Value (Actual Cond) 1Total = S?77,9 t ~,e,.,_

Design Value 1Total = 5883 +/- 588 pcm (Design Cond)

Reference Technical Report NE-881, Rev. O, VEP-FRD-36A If Design.Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/Tech Spec safety analysis. Additional t~sting Acceptance must be performed.

Criteria Reference VEP-FRD-36A VI.

Design Tolerance is met Acceptance Criteria is met

9v;s _NONO

_YES Comments I

Prepared B y : ~ ~ Reviewed By:

r NF-RQR ~,r.12 Startun Test Report Page 54 of 57

e. e.

SURRY POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET r Tes: Descripcicn: M/D Flux Map-At Power Reference Pree No/ Section: l*NPT*RX-008,002 Sequence Stap No:

II Bank Positions (Steps) RCS Teaperature (°F):TREF +/-1 Test Pa11er Level (1 F.P.): <JO Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):

(Design) CB : 225 CC:

CD:

Hust have~ 38 tbiablu**

III Bank Posicions (Steps) RCS Teaperature( °F): SSS.7 1*

-.est . Power Level(: F.P.):J_~.04*

Other (Specify):

Conditions' SDA: 225 SDB: 225 CA: 225 (Actual) CB : 225 CC : J.25 CD: i$0 Date/Time Test Perforaad:

5/3/q;;. 11: 3Y !

MAX. REL NUC EHTIIAL TOTAL HEAT KAXDRJII POS IV Meas Para:aeter ASSY PW1 RISE HOT FLUX HOT INCOIE (Description) : DUT CHAN FAf:r CHAN FACT QUADUIIT (H*P)/P F*dff(N) F*Q(T) POWEi TILT

(o.(.?;~t' Measured Value P: eo.q > \oG, 11 . ;i:344., l.0'3il .

Test. t~.,-,_- +or Results P: .c. o.ct '

Design Value*

(Design Ccnds) ....

I Ill la P1 AO.I I ID,- P, c l.t

"*. -,.* NA NA S 1.0224 jwCAP*790S lwCAP-7905 I Referenc* i REV.1 NONE NONE ! REV.l V FSAR/Tech Spec NONE raai.ssu*.xa..,, r~a, I .... a lllJ NONE Acceptance Criteria R=ference NONE TS 3.12.B TS 3.12.B NONE Design Tolerance is mec : ru .i_No VI Accept&Dca Cricaria is **t. : 7_YES -~O Coaaents '* As Req uired

"* ~ust have at lease 16 thiables for quarter care maps for multi-point calibrations.

?repared By: Reviewed

~~-RQR s1r.12 ~tartuo Test Report Page SS of 57

e* e.

SUD! POWEi STATION UMIT 1 CYCLE 12 STAJtTUP PHYSICS TEST RESULTS AHD EVALUATION SHEET I j Tut Duc:ripcicm: tt/D Flmr: ttarAt Power Rafarenca Proc No/ Sec:ciaa: l*HPT*Rl*OOl 002 Saqaaaca Step Ho:

9 II Bok Positiau (Su,a) RCS Tuperamre ( 1 F):Tnr-:tl T*~

Camlictaa i-------------+

I SDA: l2S SDI: 22S CA: 2%5 II PaNr Lnel (% F.P.): SOISP<7S1 j Otber (specify):

(Daip) CB : 2.:5 CC : 22S CD: '* I !mSC hne ~ 31 thiabl_..

III Bok Poai~iaaa (St... ) RCS TenpK11aan(*F): ,SG.&., o Tut Power Laval (% F. P. ) : &'?, y 6 i:

Conciitioaat SDA: 22.5 SDI: 2.2.S CA: 2.2S Otber (Specify):

(Actual) CB : 22.5 CC : 2.2S CD: / lt,,3 Daca/T~T..c Perforr1i*

!Al. IEL WC EHTIAL torAL BEAT ll&llmlP. POS, IV K- Par-car ASS! PVI RISE HOT Ftm HOT nrcmr

(Ducrip~iola) % DDT CUN FM:T CUN FM:f QUam~

(ll*P)/P F-dl(I) F-Q(T) POllll.tTII.T

-SA/. .f,....

~:!' 0.f, I tt-llnll Vala .f.£,,,,. l'w- /.S=>O / :i. ,08'1 j.020?

Tac Rualcs Dutp Value (Duip Conda)

~

p,. (J.9

............... NA NA s 1.ana WCAP-7905 vcu-fN5

Refenaca IEV.1 ~ONE NOii m.1 I

V FSAI/Tacb Spec NONE 1........,,,,,. ~,,,

Ac:c:epuaca Criteria I Rafenac:a NCIIE TS 3.U.I TS 3.1%.1 NUIS Duiga Tolerace is**~ : ~TES _NO AccaptaD~ Criteria is **t : Lm_No VI C ma *

- I fer aulti*pcillc calibrac1cms.

Praparad B y ~ t;~,£/j. Rewiwed By: *£Ht-~-

Page 56 of 57 ri

e SURRY POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

M/D Flux Hap-At Power Reference Proc No/ Section: l-NPT-RX-008,002 Sequence Step No:

II Bank Positions (Steps) RCS Teaperature (°F):TREF +/-1 Test Power L~vel (t F.P.): 95~1001 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify) :

(Design) CB: 225 cc: 225 CD:

Kust have~ 38 thiables**

III Bank Positions (Steps) RCS Teaperature( °F) : S-'-i "I Test Power Level (t F .P.): leO ")0 Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify) :

(Actual) CB: 225 cc: 225 cD: a~o LU, +hiMb\e.~

Date/Time Test Perforaed:

S'\

MAX. REL NUC ENTHAL TOTAL HEAT HAXI!fll!I POS.

IV Heas Parameter ASSY PWR RISE HOT FLUX HOT INCOIE (Description) 1 DIFF CHAN FACT CHAN FACT QUADIANT (K-P)/P F-dH(N) . FeQ(T) POWEJr;TitT Test Results Design Value (Design Conds)

I I 1ft , - ft a I.I

,,,I.ft,- ft CI.I NA NA :S 1.0208 WCAP-790S WCAP-7905 Reference REV.l NONE NONE REV.1 V FSAR/Tech Spec NONE NONE .

Acceptancer--------------------+--------------i--------------+-------------1---------------

Criteria Reference NONE TS 3.12.B TS 3.12.B NONE*

Design Tolerance is aet : ~S_NO Acceptance Criteria is met : _YES _NO VI Coaaents

As Required

- Hust have at least 16 thiables for multi-point calibrations.

S1Cl2 Startup Test Report

Page *57 of 57

ML18152A035

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