Text

Cycle 5 Startup Physics Test Rept
	ML18139A785
Person / Time
Site:	Surry
Issue date:	10/31/1980
From:	Leberstein J, Ross T; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
ML18139A784	List: ML18139A783; ML18139A785;
References
	VEP-FRD-37, NUDOCS 8011040014
	Download: ML18139A785 (73)
	v • d • e

I I

I I.,

I I

'*1 I

I

1

1 I

I I

.I

1

'1 VEP-FRD-37 Vepco SURRY UNIT 2, CYCLE 5 STARTu*p PHYSICS TEST J.

FUEL

VI R GlNI A 8 0 11 0 4* 0 tJl'f -~*

REPO*R*T

.\\

NOTICE*. -

\\

THE AT. TACHED FILES ARE OFF.ICl~L RECORDS OF THE '

DIVISION.OF DOCUMENT CONTROL. THEY HAVE BEEN

'CHARGED TO YOU FOR A LIIYIITED TIME PERIOD AND

MUST BE RETURNED TO THE RECORDS F.ACILITY.

BRANCH 016.

PLEASE ob NOT SEND

DOCUMENTS CHARGED OUT THROUGH THE MAIL. REMOVAL OF ANY :

PAGE(S). FROM DOCUMENT FOR REPRODUCTION MUST '.

BE REFERRED TO FILE PERSONNEL.

Docket# ~o- ~s,

C,o,ri,trnl # 0<>11ocJt>o1z..

I J

DEADLINE RETURN DATE Date 1012.91g~f Dssumeirt:i

'B~~U~TQRJ D9.;C§ f~

REG.UI.ATORY.DOCKET.Flt[ COPY RECORDS FACILITY BRANCH*

RESOURCES DEPARTMENT ELECTRIC POWER COMPANY

I I

I

I I

Approved:

VEP-FRD-37 SURRY UNIT 2, CYCLE 5 STARTUP PHYSICS TEST REPORT Group BY J. H. LEBERSTIEN T. K. ROSS Nuclear Fuel Operation Group Fuel Resources Department Virginia Electric and Power Company Richmond, Virginia October, 1980 REGULATORY.DOCKET fill COP1.

I I

I CLASSIFICATION/DISCLAIMER The data,.techniques, information, and conclusions in this report have been prepared solely for use by the Virginia Electric and Power Company (the Company),

and they may not be appropriate for use in situations other than those for which they were 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 conclusions 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 such 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 liabiiity), for any property damage, mental or physical injury or death, loss of use of property, or other damage resulting from or arising out of the use, authorized or unauthorized, of thi~ report or

~

the data, techniques, information, or conclusions in it.

I I

I i

I

,I I

I I'

I I

I I*

I I

. ACKNOWLEDGEMENTS The authors would like to acknowledge the cooperation of the Surry Power Station personnel in performing the tests documented in this report.

Special thanks are due Messrs. L. J, Curfman, J. I. Kelly, D. Padula, and R. H. Blount, Also,. the authors would like to express their gratitude to Dr. E. J. Lozito for his aid and guidance in preparing this report, We would like to thank Ms. C. E. Bullock for her patience and accurate typing of the text.

ii

I

.I I

I I

SECTION 1

2 3

4 5

6 7

8 APPENDIX TABLE OF CONTENTS TITLE Classification/Disclaimer Acknowledgements List of Tables List of Figures

Preface Introduction and Summary Control Rod Drop Time Measurements Reactor Coolant System Flow Measurement Control Rod Bank Worth Measurements.

Boron Endpoint and Worth Measurements Temperature Coefficient Measurements Power Distribution Measurements References Startup Physics Test Results and Evaluation Sheets iii PAGE NO.

i ii iv V

vi 1

8 13 15 20 24 28 42 A.l

I I

1*

I I

TABLE 1.1 2.1 3.1 4.1 5.1 6.1 7.1 7.2 LIST OF TABLES TITLE Chronology of Tests **

Hot Rod Drop Time Summary.

Reactor Coolant System Flow Measurement Summary.

Control Rod Bank Worth Summary Boron Endpoints Summary *****

Isothermal Temperature Coefficient Summary Incore Flux Map Summary.**.**..**,

Comparison of Measured Power Distribution Parameters PAGE NO.

3 10 14 17 22 25 30 With Their Technical Specifications Limit..*,.,

31 iv

I I

I' I

I I

I FIGURE 1.1 1.2 1.3 1.4 2.1 2.2 4.1 4.2 5.1 6.1 6.2 7.1 7.2 7.3 7.4 7.5 7.6 7.7 7.8 7.9 7.10 LIST OF FIGURES TITLE Core Loading Map *.**

Assembly ID's and Incore Instrumentation Locations Burnable Poison and Source Assembly Locations Control Rod Locations Typical Rod Drop Trace Rod Drop Time - Hot*Full Flow Conditions.

Bank B Integral Rod Worth - HZP Bank B Differential Rod Worth - HZP Boron Worth Coefficient Isothermal Temperature Coefficient - HZP, ARO Isothermal Temperature Coefficient - HZP, B-Bank In Assemblywise Power Distribution - HZP, ARO **.

Assemblywise Power Distribution - HZP, B-Bank In Assemblywise Power Distribution - D-Bank At 1'06 Steps Assemblywise Power _Distribution.,... I/E Cal. - Flux ijap Assemblywise Power Distribution - I/E Cal, - Flux Map Assemblywise Power Distribution - I/E Cal. - Flux }!ap Assemblywise Power Distribution.,... I/E Cal~ - Flux ijap Assemblywise Power Distribution.,... I/E Cal, ~ Flux Map Assemblywise Power Distribution - I/E Cal~ - Flu~ Map Assemblywise Power Distribution.,... HFP, Eq, Xenon.,,

V PAGE NO.

4 5

6 7

11 12 18 19 23 26 27 32 33 34 35

36.

37 38

39.

40 41

I I

PREFACE The.purpose of this report is to present the analysis and evaluation of the physics tests which were performed to verify that the Surry 2, Cycle 5 core could be operated safely, and to make an initial evaluation of the expected 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 includes a brief summary of each test, a comparison of the test results with design predictions, and an evaluation of the results.

The Surry 2, Cycle 5 Startup Physics Tests Results and Evaluation Sheets have been 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) test 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 measured parameters were completed prior to startup physics testing.

The entries for the design values were based oµ calculations performed by Vepco's Nuclear Fuel Engineering 1

Group.

During the tests, the data sheets were used as guidelines both to verify that the proper test conditions were met and to facilitate the preliminary compari-son between measured and predicted test results, thus enabling a quick identi-fication of possible problems occurring during the tests.

The appendix to this report contains the final completed and approved version of the Startup Physics Tests Results and Evaluation Sheets.

vi

I I

I Section 1 INTRODUCTION AND

SUMMARY

On February 4, 1979, Unit No. 2 of the Surry Power Station was shut-down for its fourth refueling and a steam generator replacement outage.

During this shutdown, 64 of the 157 fuel assemblies in the core were replaced with fresh fuel assemblies.

The second cycle core consists of six batches of fuel:

two once-burned batches from Cycle 4 (Batches 6Al and 6B), one tw:,ice-buined batch that is carried over from Cycles 3 and 4 (Batch 5A), one~thrice-burned batch that is carried over from Cycles 2, 3 and 4 (Batch 4B2), and two fresh batches (Batches 7A and 7B).

The core loading pattern and the design parameters for each batch are shown in Figure 1.1.

The core location of each fuel assembly is identified in Figure 1.2 together with the incore instrumentation locations.

Figure 1.3 identifies the location and number of burnable poison rods in the Cycle 5 core.

Figure 1.4 identifies the location and number of control rods in the Cycle 5 core.

On August 14, 1980, at 1208, the fifth cycle core achieved initial criticality.

Following criticality, startup physics tests were performed as outlined in Table 1.1.

A summary of the results of these tests follows:

1. ~e drop time of each control rod was confirmed to be within the 1.8 second limit of the Technical Specifications. 2

2.

The reactor coolant system flow rate was confirmed to be greater than the minimum limit specified in the Final Safety Analysis Report. 3

3.

Individual control rod bank worths for all control rod banks were measured using the rod swap technique4 and were.. *found *to be. within

13. 2% of thia design predictions.

The sum of. the individual c0ntrol.rod

bank worths was measured to be.within 3.8% of the design prediction.

1

I I

I These results are within the design tolerance of +15% for indi-vidual 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.

4.

Critical boron concentrations for two control bank configurations were measured to be within 43 ppm of the design predictions.

These results are within the design tolerances and also met the accident analysis acceptance criterion.

5.

The boron worth coefficient was measured to be within 5.9% of the design prediction, which is within the design tolerance of

+10% and met the accident analysis acceptance criterion.

6.

Isothermal temperature coefficients for two control bank config-urations were measured to be within 0.6 pcm/°F of the design predictions.

These results are within the design tolerance of

+3 pcm/

8 F and also met the accident analysis acceptance criterion.

7.

Core power distributions for various HZP and at-power conditions were generally within 6% of the predicted power distributions.

For all maps, the hot channel factors were measured to be within the limits of the Technical Specifications.

Generally, all measurement parameters met their respective design value tolerances.

All measurement parameters met their respective accident analysis acceptance criteria.

In summ~ry, all startup physics test results were acceptable.

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

2

I I

I

-1 I

I I

Table 1.1 SURRY UNIT 2 -

BOL CYCLE 5 PHYSICS TESTS CHRONOLOGY OF TESTS Test Date Time Power Hot Rod Drops-Hot Full Flow 8-8-80 1748 HSD Reactivity Computer Checkout 8-15-80 0040 HZP Boron Endpoint -

ARO 8-15-80 0358 HZP Temperature Coefficient -

ARO 8-15-80 0825 HZP Flux Map -

ARO 8-15-80 1154 HZP Bank :B Worth 8-15-'80 1820 HZP Boron Endpoint - B Iri 8-16-80 0428 HZP Temperature Coefficient - B Ir. 8-16-80 0601 HZP Flux Map-B In 8-16-80 0842 HZP Bank D Worth - Rod Swap 8-16-80 1616 HZP Bank C Worth -

Rod Swap 8-16-80 1744 HZP Bank A Worth -

Rod Swap 8-16-80 1759 HZP Bank SB Worth - Rod Swap 8-16-80 1941 HZP Bank SA Worth -

Rod Swap 8-16-80 2206_

HZP Flux Map*,,,_. *D at 106 Steps 8-18-80 1108

."'5%

Flux Map - I/E Calibration 8-20-80 1221

"-'42%

Flux Map - I/E Calibration 8-21-80 0233

'v5 0%

Flux Map - I/E Calibration 8-21-80 2307

'v61%

Flux Map - I/E Calibration 8-26-80 1538

"'71%

Flux Map - I/E Calibration 9-1-80 1054

'v89%

RCS Flow Measurement 9-12-80 1040 rvl00%

Flux Map - HFP, Eq. Xenon 9-12/80 1422

",100%

3 Reference Procedure PT-7.0 PT28.ll(B)

PT28.ll(C)

PT28.ll(D)

OP-57/PT28.2 PT28. ll (E)

PT28.ll(C)

PT28.ll(D)

OP-57/PT28.2 PT28. ll (F)

PT28. ll (F)

PT28.ll(F)

OP-57/PT28.2 OP-57/PT28.2 OP-57/PT28.2 OP-57/PT28.2 OP-57/PT28.2 OP-57/PT28.2 ST-52 OP-57/PT28.2

I I

, I I

I I

I p

N M

L Figure 1.1 SURRY UNIT 2 -

CYCLE 5 CORE LOADING HAP K

J l:i G

F E

D C

B A

I I ~i 7B 16Al j I I

I I

'1*

I

( l~ri~Sj O O 16.18 i--' _,____--+---+----;.---'----,--- l 2~:~,1 1~, I,fi' *:i: I,fi' 0~~ h' 7:T I !

I 1

2 J

.. 6B I 7B 7B 6B I 6B If 6B I 7B

., I 6B 9.27 o.o o.o 14.04 15.33 4.13 o.o o_.o 9.45 I ~

1"14 vn 1rn1

?n, T,,

~,

~~~s I /~ j1/~2 /~

1!~1 /

1

/~

j1}~81. /~

~\\8j ~\\6

1 4

I ~i1 2

c10 P07 H07 B07 Kl3 Pll.

I I

5 D09 Cl2

.,ni; T11 r, 'i r., 1 T.()I; Ml 1 Mno 22\\2 j /~ I o~~ 19-~~ 23\\812/ 7419~~2 1

121\\9 22~91 j 1o~~s 1 ~\\

~\\ I 2/091

i.

II j

7B I 7B 6B I 5 j 6B I 7B I 6Al I 7B I 6B I 5 I 6B I 7B

\\ 7B l i,*

o.o I o.o 14.13 23.09 1 9.95 o.o 15.64 o.o 9.99 22.98 14.34 1 o.o I o_.o 1--

1 1

6 j

J02 Kll f 1'!03 112 C04 Fll.

G02 I -

6Al I 7B I 6BI.

7B i 5 I 7B I 6Al I 7 A / 6Al I 7B j

- I 7B I 6B I 7B I 6Al I 16.391 o.o 14.12 0.0 121.80 o.o 15.821 o.o 115. 71 0.0 121'.46 o.o '114.10 o.o 16.44[,

JQ6 Nll

, E09 ! -

DOS 104 109 Cll

G06, I

0~~ I ~\\ I 5 I 7B 22.08 o.o

D07

'---* 6E 9.44 BOS 6B I 5 I 6B I 7B I 6Al I 7B I 6BI I

5 I 6B I 7B I 7B l-10 1ii~9. 2~0;s 1~i~4 o:o 1~0~6 o:o

.1~i~o 2:0~1 1~i~o! o:o I o.o l 7A.

I 6B

~ 5

~

5 I 6B 1*

5 I 5. I 6B !. ]_j,.

f 7B I 5 j

_ 1 a: o 10.0 23.1* 21.84 9.oo 21.82 23.12 9.89 I o.o o.o 121.91 -i --

. D03 ElO JOS GOl I GOS 110 Gl4 MQ7 l

6B I 7 A I 6B 7B I 6Al I 7B

1 6B I

7 A 1*

6B 16B 12 1;0~s a. o 1~0~0. o. o 1~0!0_;:_o_:_o_.;.-..;~69~* 3-8..,../ _o_._o_,._1-~*-0-~3-*9...

i>.Q""'2~---!

6B I 7B 7B I 6B 1*

6B I 6B I 7B 7B I 6B 9.46 o.o o.o j 14.24 15.43 114.06,

1 o_.o o.o 9.37? ~

E02 113, Fl3 I El3 I

____ 13 5 I 7B 7B 6B 7B 7B I S l

22.09 o.o o.o s.86 j o~o o.o 22.23 ;...

1 ---------- 14 I,..;:G~0..:..4 __;_. ----i'--=-:--:--+--=G==l~S -.-:--:--.---*-!ll...

1' 1i1:"11J O:~

1 1

1t*:.io i-------

F09

K09

~Batch 3

/ 4"- Burnup (10 HWD/HTU)

~

Previous Location (Cycles 2,3 or 4)

FUEL ASSB-IBLY DESIGN PARAMETERS oaLcn 4B2 5

6Al 6B 7A 7B Initial Enrichment (w/o U235) 3.10 3.11 2.91 3.20 3.13 3.41 Burnup At BOC-5 (HWD/MTU) 28,803 22,296 16,033 12,008 0

j 0

Assembly Type 17Xl7 15Xl5 15Xl5 lSXlS 15Xl5 15Xl5 Number Of Assemblies 1

24 20 48 12 52 Fuel Rods per Assembly I

264 204 204 204 204 I

204 I

I Figure 1.2 SURRY UNIT 2 -

CYCLES I

~

ASSEMBLY ID's AJ.'o!D INCOF.E INSTRUMENTATION LOCATIONS

-~oo I,

p

~

AA T

T rt p

~

I.

K J

G F

N M

I I

j I

J J,_I

f.

v19 I rnz I voz l

I I

J.

I I

1 Looo c e

O I

I

, Loop B I

I Outiet Inlet I

I V""°'\\ I ""I T24 I SNl I 1N3 I W40 1N9 13: I Tl7 l ~/. I.

I 2

E D

C B

tN-41)

I"'-

0 0

181 I

lw32 I 4Nl 2N3 I W4S I W34 I Wl9 I ON4 lNS I W04 J

J 1 f @

0 fl 0

@ I I j

I I

I I I O I W37 I 0~2 I W46 V2; 2N4 I ":: 0 I W25 I W41 ~ I I

I I TlS I 4N9 I 017 I W21 II T04

1 Tl6 I W22 I Tl3 I T23 W39 I lLl I 2N7 I TOl H-5 I

0 o

O Q,@@

1 ti 2N2 I 1N7 W2S j. T22 I W35 I ON2

1 Vl2 I lNO j W33 T21 I WOl ONl SN2 i

~

6 Loop B I

. I 1

0 I @ (

0

! Ell

! I Outlet.

~~~~t c * ~v'a?'I 3N4

1 woz I 4N4 Tl2 I 3Nl

'J v22 I OL9 I vos I 4N7 I Tll 12N1 I w10 I 4N2 I vzo ! 7

. /

\\~ 0. 0 1

I I

fl I fD

. 0

@ J--l /

I

'900 _

4NO I wso I W06 I V03 I W42 I VOS I OLJ I RD2 I 011 I V24 I W24 I VlO I W27 I W07

, W8 l 8 _ 2700 elo!@I 1 !o:

.o,o.~.o:

.@.ao, I

L" I ON9 I"" I '; i '!' I "" j vis I 0

~ Iv,! I o; I 707 I

'NS I "" I mi I v~~J,

' 2Ns J ON61' w11 I Tzo J wo3 1* 3N7 I vo4 I 1N4

) ws1 j Toz J w44 I 3N2 j rn6 j--io I

I 10

~

I I

TlS

,,., I '; I ":' I 'O I 703 I "@ I 708 I'; I W~3 I OLS I '"' I 714 ~--

,__] W481' wo9 I OL6 I ws21

ON3 I '716 I ON71' was j u21' w30 I was. i I

I I

0 01 001@

EJ I W29 I 2NO I ON8

, W4 7 I Wl3 ~

3!0 I 4NS I W20 ! -

lJ L_

. @ I,,__

I @

1

. O J 14N' I lN'

"' I '~ 14N' I 'O I O

~

I v~ I s~ I v~ !

\\\\

~

5 Loop A I

Loop A Outlet i 0 Inlet 0

~

Fuel Assembly I.D. Number l____::f-Indicates Location and Type of Incore Instrumentation 8 - M/D Q-T/C

@) - Buth M/D and T/C 5

I :

I I

I I-I I

I 1*

I I

I I "

I I

I Figure 1.3 SURRY UNIT 2 -

CYCLE 5 BURNABLE POISON AND SOURCE ASSEMBLY LOCATIONS R

P N

M L

K J

H.

G F

E

o C

B A

I 11 I I I

I I

I I

I.T

)

PS 12 12 I

I I I

I J

I 8 16 l ss I 16 8

I I

I I 112 I 116 I I

l I 16 12 I l l 8

12 I

PS - Primary Source SS -

Secondary Source

- Depleted Burnable Poison 6

48 Depleted Burnable Poison Rods 688 Fresh Burnable Poison Rods 1

2 3

I I

I.*.

I.

I I.

1*

ii I I I

I I

Figure 1.4 SURRY ~IT 2 -

CYCLE 5 CONTROL ROD LOCATIONS RP N

1 L

K..J HG Ft DCB A

I I I I I. I I

I I

I. I 101 0

101 I

fT I I I &

I I

1 I I

l 1.01 0 I

181 101 I I

_, I l

. I I l I

l~I I

I I

I *191 I

I H-I I

I 10H-10! 101 lGI 101 101 8

l I&!

I I lwl I l I Mi I l

!91 I

I I

181 I. I !81 I

I !81 I

I 18/

I I I

I I

I I l&I I

I I

l&I i

I iyl l~i I

I I

I SA I 1

I I.

i 2

6 7

3

')

I 101 181 101 181 !GI 181 101j-]:J I I I 191 I I I I l"o/1 I I 1--ll L_I 181 181 I I 181 181 J I

I I I l&I 101 Function Control Bank D Control Bank C Control Bank B Control Bank A Shutdown Bank SB Shutdown Bank SA I I

/&I i

I GI 101 7

I I

I Number of Clusters 8

8 8

8 15

I I

Section 2 CONTROL ROD DROP TIME MEASUREMENTS The drop time of each control rod was measured at cold and at hot RCS' conditions in order to confirm satisfactory operation and to verify that the rod drop times were less than the maximum allowed by the Technical Specifica-tions.

The hot control rod drop time measurements were run with the RCS at hot, full flow conditions (~547°F, ~2235 psig) and are described below.

The rod drop time measurements were performed by first withdrawing a rod bank to its fully withdrawn position, and then removing the movable gripper coil fuse and stationary gripper coil fuse for the test rod.

This allows the rod to drop into the core as it would in a normal plant trip.

The data recorded during this test are, the stationary gripper coil voltage, the LVDT (Linear Variable Differential Transformer) primary coil voltage and a 60Hz timing trace which are recorded via a visicorder.

The rod drop time to the dashpot entry and to the bottom of the dashpot are determined from this data.

Figure 2.1 provides an example of the data that is recorded during a rod drop time measurement.

As shown 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.

A voltage is then induced in the LVDT primary coil as the I

I rod drops.

The magnitude of this voltage is a function of the rod velocity.

When the rod enters the dashpot section of its guide tube, the velocity slows causing a*voltage decrease in the LVDT coil.

The LVDT voltage then reaches a minimum as the rod reaches the bottom of the dashpot.

Subsequent variations in

~

the trace are caused by the rod bouncing.

This procedure was repeated for each I

I I

control rod.

8

I I

I The measured drop times for each control ro*d: 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 1.8 seconds with the RCS at hot, full flow conditions.

All test results met this limit.

9

I I

I Table 2.1 SURRY UNIT 2 - CYCLE 5 BOL PHYSICS TEST HOT ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASHPOT ENTRY Slowest Rod Fastest Rod Average Time E-11, 1.29 sec.

J-9, 1.14 sec.

1.22 sec.

ROD DROP TIME TO BOTTOM OF DASHPOT Slowest Rod Fastest Rod Average Time E-11, 1.83 sec.

G-9, 1.68 sec.

1.76 sec.

10

Figure 2.1 SURRY UNIT 2 -

CYCLE 5 DOL PHYSICS 'l'ES'l' TYPIC/\\L ROD DROP 'fHJ\\CE

~---,~ =t=,~=~~;c~C:::~:.:l:~~t:~1;:r* I I ! : ; i ; J I 1** ! r*-,~-L

--*-* -- ---- -- *---- *----- -- *--*. ---- **--*- --.- _.___... :_ *: *-*I I

I.

I

! I 7"*- __ ~-

_I. -ttJ.0J 01--.. o:*.=r. ot.Dr-;..or ~

I i

1*

-~---

.,,..-- *--~;,-

.. LNJD.T.. r :<-T \\)f'R cp.1.L... :..

~ JPE ?*I; ::a~;; :

~ D ~r,u ~. ~b.L~,1 I'\\;' *1w, !,/~/ W11', NW~ V

-I- - --.*

A~~--\\ ~iOi X *. ~~~fl\\~\\-! Ii(\\ W(\\ \\\\\\\\H_I!'

11

~~l ~~ :11 :>or,

\\I ! *,

i 1*

i ! i -I-1\\Jl\\ \\\\/1:\\::i\\'\\~ \\\\ 1-1

- - - - -* *.-**.. :.. ------*---*=-;_I_ U~~,t\\l/1t\\r\\ll\\1lu11 ~'\\j*'1qq 1u,u11111!,* *j

.. L.. _ - **.J. -l l

l!ll(l}II /H JJJ1111,

11 l1 i

. _i\\ __ 1.v __,_1 ____ *1_,111~_,,:1_11, _1_1::_':1u:_*_*'i*_'-,*:,r,,,_:,,,~_*_*;_**,1_:1i **.:/.it\\H,J.1,,.u11.,.. 1_.,!.. _,.*_' *._,,,_i.,1,_J.-' __ :._,.. _i:11!,J __ 1;.1_ji-_: __ i fi'ti r1(i dfii'iD'\\'1\\f nn < -~--- -~---.-;~ ---~--.~~ :~--~ :~*-* -~---_ ;*'~:: *:*- --**! *. - l

)II I -I.

1

- - tll*

111 ' htli1111 iilt,i1 *, U1Ll 1l!1,;11111*;*,:/111'ii'/['*

1 1/i-:

1

...... _________. ___. ______ )ROPJLl'\\r. _Jc.D1.::.n FL; ________..:--- ___ DN:-iU. -.oJ_ Jq TZ 11D 1 *.o 1. ro 1.J~v\\a

1--r,-l-, ___,.__ ___ J-__,,---***--1-**-;*--1-::-:--*,---,

i

,-.~

J.:::~:)TlO:r\\ (;:-

-- --*- --.* --*-** **-. -- ____.;_t,-.:,;

_. I.

l_*'--.-1--,----~- **- ----.-* *-, I*

i.

. I I. I..... **-*1*-*-... *-. **-l')*.-,I\\ r-1..-y,*I 1

i.

I

'1

~-~>.::*:.:... _ :1'--* 11

A~Wi,~\\\\W,\\\\\\/hlr1 W, ~'.l~W)~Allli~A~V,~/NN0~~~~1N,~~w'{~JN~.1 "i~Nll'.;VI/,~ }N~~ IHI$ I*/~'.'/// !(!Nlf.~'h1i!!!Jr!f }W 11, NII Ii/!;\\ \\','t,\\ Yi:,.,~',',',\\~~

. 1}11N<:; TRP-.CE~_:S~t\\~\\Ol'-l: 13us fREQUE~--lC'(

I I

I

-1 I

I I

R Figure 2.2 SURRY UNIT 2 -

CYCLE 5 BOL PHYSICS TEST ROD DROP TIME -

ROT FULL FLOW CONDITIONS P

N M

L K.

J H

G F

E D

C B

A 1.16 1.75 1.19

1. 70 I - I I

I I

I t----t--1~, --+--l _

___, _ _,_____ 1

l. 20 I

I _ I

l. 77

-,---1 ------+-,-

2 I

i:;~ I i:~~

I 1

1 3

I i:;~ I i:;~ I I

i:;~ I I i:;i I I I 4

I I ::;:

I I

I I :: ~~ I I

I. I 1

1 5

1.16 I l 19 I l 21 I 11 18 I 1

1.16 11.20 k 6

l. 70 1: 70 1: 72 I 1: 69

l. 70 11, 80 I I

1 1.181

1. 72 I Ii:~~

Ii:;~ I I I I i:;~ I I 1 7

1 1.191 I

1.69 I

I I

i i:;~ I I

I Ii:~; I l s I i:;~ I I I

I 1.20 I

1. 72 I ~:~: I I l I ~:;~ I I I s I~:;~ l 11.16 1.19 1.26 1.14 1.18 1.17

11. 20 i 1.74

1. 69

1. 78

l. 71 I 1. 7o

1. 70 1.80 i-I l

1.181 I

I I

I 11.29 i I

I

1. 76 1.83 I

E I 1.19 1.141 11.181 11.18 I I

1. 71 1.69

1. 70 1.69 l

I I I 11.181 11.21 I I

I

1. 70

1. 75 12 l3 11.20 I 1.22 11.20 I 1.82

1. 74

1. 78 15 D

Rod Drop Time to Dashpot Entry (sec.)

Rod Drop Time to Bottom of Dashpot (sec.)

12

I I

I Section 3 REACTOR COOL.ANT SYSTEM FLOW MEASUREMENT The reactor coolant flow rate is measured in order to verify that the minimum flow rate requirement is satisfied.

The RCS flow rate is determined using the calorimetric measurement technique.

Precision calorimetric data I

(i.e., feedwater temperature, feedwater flow, and steam pressure) are obtained in order to accurately determine the secondary-side heat rate.

The primary-side I

I I

enthalpy rise is determined from the RCS pressure and the temperature increase associated with each RCS loop.

The flow for each RCS loop is determined by establishing a primary-side to secondary-side heat balance.

Steam generator blowdown heat loss, system heat losses, and the power produced by the reactor coolant pumps are taken into account in the heat balance.

A reactor coolant flow measurement was performed at 100% power.

This data was analyzed using 5

the RXFLOW computer code.

A sunnnary of the results for this test is given in Table 3.1.

As shown by this table, the test results demonstrated that the RCS flow limit was met.

13

k Table 3.1 SURRY UNIT 2 -

CYCLE 5 BOL PHYSICS TEST REACTOR COOLANT SYSTEM FLOW MEASUREMENT

SUMMARY

. Percent Loop A Loop B Loop C Total Flow Minimum Flow Power Flow ( gpm)

Flow (gpm)

Flow ( gpm)

(gpm)

Limit* (gpm) 100%

100,665 97,854 100,030 298,549 265,500 FSAR Section 4.1.3; Letter from C. M. Stallings (Vepco) to H. R. Denton (NRC) dated May 31, 1979 (Serial No. 388); Letter from C. M. Stallings (Vepco) to E. G. Case (NRC) dated November 16, 1977 (Serial No. 516).

I I

I Section 4 CONTROL ROD BANK WORTH MEASUREMENTS Control rod bank worth measurements were obtained for all control and shutdown banks using the rod swap technique.

The first step in the rod swap procedure was to dilute the most reactive control rod bank (hereafter referred to as the reference bank) into the core and measure its reactivity worth using conventional test techniques.

The reactivity changes resulting from the 6

reference bank movements were recorded continuously by the reactivity computer and were used to determine the differential and integral worth of the reference bank (Control Bank B).

At the completion of the reference bank reactivity worth measurement, the reactor coolant system temperature and boron concentration were stabilized such that the reactor was critical with 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.

At this point, a rod swap maneuver was performed by withdrawing the reference bank while one of the other control rod banks (i.e., a test bank) was inserted.

The core was kept nominally critical throughout this rod swap and the maneuver was continued until the test bank was fully inserted and the reference bank was at the position at which the core was just critical.

This measured critical position (MCP) of the reference bank with the test bank fully inserted is the major parameter of interest and was used to determine the integral reactivity worth of the test bank.

Statepoint data (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 was then performed in reverse order such that the reference bank once again was near full insertion and the test bank was once again fully withdrawn from the core.

The rod swap process was then repeated for all of the other control rod banks (control and shutdown).

15

I I

A summary of the results for these tests is given in Table 4.1.

As shown by this table and the Startup Physics Test Results and Evaluation Sheets given in the Appendix, the individual measured bank worths for all of the control and shutdown banks were within the design tolerance (+10% for the I

reference bank and +15%. for the test banks).

The sum of the individual control I

I rod bank worths was measured to be within 3.8% 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 worth of the reference bank

~

(Control Bank B) are shown in Figures 4.1 and 4.2, respectively.

The design I

I I

I*

I I

I*

I I

predictions and the measured data are plotted together in order to illustrate their agreement.

In sunnnary, all measured rod worth values were satisfactory.

16

I I

I 1*

I I

Table 4.1 SURRY UNIT 2 -

CYCLE 5 BOL PHYSICS TEST CONTROL ROD BANK WORTH

SUMMARY

MEASURED PREDICTED PERCENT DIFFERENCE BANK WORTH WORTH (M"""~) x 100 (PCM)

(PCM) p B-Reference Bank 1284 1225

+4.8 D

1218 1214

+o.3 C

849 850

+0.1 A

. 6-50 574

+13.2 SB 952 969

-1.8 SA 1159 1059

+9.4 Total Worth 6112 5891

+3.8 17

I I

I*

I I

I*

I I

I*

I,,

I I

I

1

c u

0.....

I I-a:::

0 3:

_J a:

a::::

C) w I-z 1--1 0

0 N

0 0

N D

0

(.O' D

D 0

a::)

0 I..J I

I I

I r

I i

I I

I -

I I

I 0

FJGURE 4.1 2

CYCLE 5 BOL PHYSICS TEST SURRY UNIT BANK B INTEGRAL ROD NORTH HZP i

i I

r I

r I I I

I I

I i I

/

I I

I I I I i I r

r I

i I I I I I

I I I I

I I I

I I

I I : I

' I I I I

I I

I I I I I

I i

i I i I

I I I I i

I I I

I I

I

! I I

I I

I I I I I

I I

I I I I I I I i I '

i I I I

I I I I :

i I I

I I I I I I

I I

I I I

I I

I I !

I

! I I

r I i

! I I !

I I

I !

r I I I I I :

I I

I. i I I r

I I I I I

I I !

i

! I I '

r I '

I I

I I I

' I I I I

I r I I !

I I I I I

I I

I I I

! I I i

i : I 1--..:... :.

i i

! I :,.

I B BANK*HJTH ALL OTHER BANKS OUT PREOJCTEO

?IE 11Ef!SUREO I i I I

I I

I i

r r

I i I I

I I

I i I I I !

I I

I i

i I r I I r

I I

i I I I

I i

I I !

I I

I '

I I

I !

I I

I i I I

I I

i I

I I

I r

I I

r i I I

I I

i I i I i I I

I I

I I i I

I I I ! I I

I I

I i I !

I r

I I I

I ! i I I I ! i i I I I

I I

i ' I I

I

' I I I

I I

r I

I I I.

I I

! I '

I !

I I

I I I I '

I I I I I I I I i r

I '

I I

I I I

i I I I ! ! I I

I I :

I

I I I : i ! I !

I I I I I I

i I i i I i ' ! i I

r I

I I I

i I

I I i ! :

I 1 I I I i I I I

! I i

i i I !

i

! i I

I I r

r i I I i ! I I

I I i I i

I I

., i !

I I I i I I

! I

' ' I I I I I i i

I i I I I i I

I I i i I I I

I I I I I ! i I

I ' I I I i

I I I

' I I I I I

I !

I I I I

I I

i ' !

I

' I I I i I

I ! I i ! I I I

I i

r '

I I

I '

I I

I

' I I :

I I ' i i I ' I r I I I I I i I I I I

I i

I I I i

I I

I I I I I

i I

i ! I I

' I I !

I I I I I : I I I I I I i

' I I

I I ' I i

I I

i I !

I I

I I I

! I I

I I I I

I I i

-,.........., i i

I I

I i i i i I I

I i I I I i I

I ' i I I

I I

I I I I

I I I

I I

I I I

I I i

I I

I i

i 40 I

I I I i I I I I I

I I i I I

I I

I I i 'l'-"

! i I i

I I

I I I I I I I

I I I

I ~' r i

! I I I I I

I

! I ' I I I i I

I

,.N I

I I I i

I I I I

I I

i I

I I i

I I I I

I i

I I

'II' 'I I

I I

I I '\\.l.'

I I

I I I

I I 1,1 I

I I

I I I i

I I I

I I

I l",1! I' I I I I

I I I I !

I I

I I I I I I

I I

i I I I I I I

I iR..

1'.

i I

I I I

~ i i

I I

I I,..._

I'-

I I

I

i, ~,!

I I

Ii.. I"-

I I I

I i

IN "

I I

I I I......,

i I I I

80 BANK 8 I

I I

i I

I I

I i I I I

I i I I

I I

I 120 POSITION 18 I

I

"'"""-t" I I

I i

I l~~l I

1";

I i

-~ I I I

I........

I I

160 (STEPS) i I

I I

i I

I

! I i

I I

i I I I

I I I I I I I !

I I

I I i I I i

I I

! I I

I I I I I I I

I I i I I !

I I I I I I

I I I I

i :

I I :

! I I

I I

I ' I I I I I

I I I I I I I

i I ! I I

i i

I I I I I I !

I

! I i i i

I I I ;

r ' I I

! I I

I

! i I ! '

I ! I

! I

i '

I i

I

' i :

! : : i I

. I I I i i

! I I

I I I ! ! :

i I

I I I I i I !

' ! i : !

I I !

r I ! I i I i I I r

i i

I I I I I I I

! I ! i I I

I' I I

I l I I I I '

I i I '

I

! I :

i I

I i I

I i i '

I i ' I i I

! I I i I I I i I i !

I I I I I

I i i ! I '

I I I I I

i j

I I I

I I I I I I I I I

! I I i !

I

! I I

I i I I l I I i I i I I I I i I I

I I I I ! !

I I I !

! ' I I I I I ;

I I I

I I i I I I I I I I I I I i I I

I I I I

! I I

I I I I '

I I I I I i

I ! I I I ! I I I I I I i I

I I I I I I I

I i=

I I ! '>I I

I I I

I I I""'

I I

~

I 200 I

I I

I

' I I

I i

I I

i i

I i

i I :

I I

I i

I I

I 228

I I

I C) a N -

a C) a

_J a:

-a r-0 z*

w"<1' cc w

LL LL a

>--iC)

0.

N C)

C) i I

I I

I FIGURE 4.2 SURRY BANK UNIT 2 CYCLE 5 BOL PHYSICS ROD WORTH TEST HZP i

I i

I I

I I I i I I

I I

I I i I

I '

I I

I ' I I I ! I !

I I

i i

I I I I I I i I

I I :

I i i I I I

I I I I !

I I

I

~-

y I

I I

i I

I I

I i

I I

I i

! I I \\

I I ! *1 I

I I !

I I i i

I I !

I I i I

I I

I I I i I

I I I !

i I

I I

I i

I I i I

I I I I

B I

I i

I I

I I I I I I i

i I i I !

I '

I I DIFFERENTIAL S SANK WJTH ALL OTHER BANK5 CUT PREOJCTEO ME/15UREO i

I I

I i I i :

I I I

I i I i i I

I i

I I !

I I

I I I I

I I

I I I I

I I I

i I

I I

i I

I I i I I

I I

I i

I I

I i

I I

I I !

i I

I I

I I I

I I

I I :

i I I I I

I I i I

I ' I I

I I I I ! I I : I i I I I i I ! I i

I i I

I i I i

I '

I I

I j 'k"V,;;10; I

! I i i I

I I

I I I I

I i I

I *;~ : I I I I I I i I I

I I

;C i I I i

I I I I

I I

' I I I :

I I

I I I I I i I i I i I

I I i I

I I': I i I

,<(>JI:

' : ! I I

I I ;

I I

I I I

"'-,,,i I

I i

I I i I

\\.., : i I i~ ' '

ni i ' i '

I I ' I I I I I I

r I

I I -

I

~V' '

I

' I I :,

I i I I I

! I i ' ~I I

I '

I I i i

I I

I

I ! I/'

I i

I '

I I

I I I I i !

I ' ! i I

11: ,vi.[

! I i I I I I I I

"'I I I 1/i I I :

I I

I

! I I I I i

I I i I

I '

r"I I,-.....,

I ! I i i I i /I I I i I i I I ;

~ ; I i I....._ I i : '

i I I I !

I : I '

I ' i i

I ! I I I

_, I i I I i I ! !. !

i I

'<llitl I ! ! ! I I

" I I I I I I

I I I I I

i I

l!'\\t<J!f?ffi ';t!

I i

'II I i I

I I

I

' ~I :

I

! 'l/;*

'I(:

I I

I '

I i

I

! I ! I I I

! I i

I I I I I :

i I

I I I

I I

I I I I I I I

i I

I I I

' I I I

I i i i I

I !

I I

I I '

I i !

I I I I I i I

I

' I '

I I

I I I i I I I ' I I

I i I

I I I i I i i

I i I

i I ' I I

i I I I

I I

i I

I I

I i '

I I i I !

I I I :

I :

i I

I : I I

I i

I I,.

I : '

I I

I I :

i I : I :

I I I i

' ; I I

i I

i i

-~

i '1 '

! I :

I I

I : :

i ',~;"'~,'

I

~,...,, ' i '

\\ld ! :

' i "

I

'i

' I I i I I '

I I

I I I I i I I i '

i I

' ;11:i I

i I '

I i I

I I

I I I

I I

I l':I I

I i

I I

I I.,.,

I I

I

l'(i I

I 311 I

I I

I i

!<I

~I I

I/

I I

I 40 I

,I I

I I II i I

r I I I I /I I i I I

/ I I

I I I

I I

I I I I I

i I

I I

I I I

I I

I I I

I I ~*-

I I

I 80 BANK 8 I ' I I I I I I I I i I I

I I

I I I I i I i

I i !

I I

I I i I

I i

I I

I I I I I I I

I I I I

I I

I I I

I I

I i

I I I

I I

I i I

I I

I I I I

I I I I I I I

I l I

11'-" n I Air n'N.~

I

.;;.:-_i I

.....,.-; I.....

,-.i.

,_. I

\\

I I

120 POSITION 19 I

I I

I I ! I ' ~.f::I I

I i I I I

I I i i I I

I I I

! I I I I

I I

' I ' I I

I I

i I

I I

i I

I I

I I I I I I

I I

' +-

I

~c....

160 (STEP) i I

I I

I i

I I ! I I

!I;

,1 i

I I I i 'I I

I ! I

I !

! I I

I i

I I

I ! i I

! ;I'\\

I i I I i I \\I I

I I i I I I I

I

' I \\

I I ' I I

' I I

I i I I

i I

I I I I

i\\

I I I I I

I I

I I i

I I

i I I I I

I I i I I I

I I

I i

I I

I I I

I I,...._

i I

I I I I I I I

J I

200 I

I I ! !

I I I I : I I ! !

I I I I I I I : I I ' I I

I I

! i I I : '

I ! I I

I I

I i

I I

i I :

I i

I I

I : ' :

i i

I I I

i I

I I i I i

I I i I i I

I i I I i

I I

I i I

I I I I I

I i I I i I

I II I I

! 1,,t I I

I I

I I,,

I I

11 I

I

(

228

I I

I 1, I

I I

Section 5 BORON ENDPOINT AND WORTH MEASUREMENTS Boron Endpoint With the reactor critical at hot zero power, reactor coolant system boron concentrations were measured at selected rod bank configurations to enable a direct comparison of measured boron endpoints with design predictions.

For each measurement, the RCS conditions were stabilized with the control bank at or very near a selected endpoint position.

The critical boron concentra-tion was then measured.

If necessary, an adjustment to the measured critical boron concentration value was made to account for off-nominal core conditions, i.e., for rod position and moderator temperature.

The results of these measurements are given in Table 5.1.

As shown in this table and in the Startup Physics Test Results and Evaluation Sheets given in the Appendix, all measured critical boron endpoint values were within their respective design tolerances.

All measured values met the accident analysis acceptance criterion.

In summary, all results were satisfactory.

Boron Worth Coefficient The measured boron endpoint values provide stable statepoint data from which the boron worth coefficient was determined.

A plot of the boron concentration as a function of integrated reactivity can be constructed by relating each boron endpoint concentration to the integrated rod worth present in the core at the time of the endpoint measurement.

The value of the boron worth coefficient, over the range of boron endpoint concentrations, is obtained directly from this plot.

The boron worth plot is shown in Figure 5.1.

As indicated in this figure and in the Appendix, the boron worth coefficient of reactivity was measured to be -9.11 pcm/ppm.

The measured boron worth coefficient is within 5.9% of the predicted value of -8.60 pcm/ppm and is well within the 20

I

~

design tolerance of +10%.

The measurement result also met the accident analysis acceptance criterion.

In summary, this result was satisfactory.

I I

I 21

I I I

I I-I I

I I

I Table 5.1 SURRY UNIT 2 - CYCLE 5 BOL PHYSICS TEST BORON ENDPOINTS

SUMMARY

Control Rod Measured Predicted Difference Configuration Endpoint Endpoint M-P (ppm)

(ppm)

ARO 1437 1394*

+43 B Bank In 1296 1301*

-5 The predicted endpoint for the B Bank in configuration has been 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.

22

- **-... -.... -j -* - -**.. -.... ).. -.. - -

w 2400 2000 FIGURE 5. 1 SURRY UNIT 2 -

CYCLE 5 BOL PHYSICS TEST BORON WORTH COEFFICIENT l!J ENDrOJNl NEASURENENTS

---+----l-----1---l--l---l----l-- --- -

--* *--1-----1---+--- --.,--l-,l-l-1---1---1--1---l-1--+--t-+--t--t--t l--l-+---+---1---l---+--+--l---,--J--t---t-- - -- -- -+-t--1--1---1--+--+--l----1---+--+-t------t-t-i-1 l-~-l-----l---+---+--1--1--*- --1-t-- *- --- - -

_ __,___,_____, __ --1--1--+---!----~ --

~-+----l----+--l---+--+--l--l--+--1---r---1-----1--,--1--1--+---l-l---J-11-1-1-+--t-+ 1-+--+---+---1--l---+--+---f---J--t---t-*- -- -- -

--- ---l---l--1-1-1--.J___L__j___L__L_---1.-_f--l--t--+--

-l--l--f-11-----rf-f--+- ---~ -- -- -

-- ~ "'-9.11 pcm/ppm ---1--1----1--

ac B

L 1 6 0 0 -l--l--l--1---1---l--+--1--l-il--l-+--t---t-+--t---t--t--t--t ----

- ---- -~~~~.,.-+---+--1---;---1 u

(L

~-~-l-----1--1---l--+---l-- ---+---I-- --- **---*- *-*--* **-- --- -- 1--- _,_____ -

- - --* --- -'--*-~-- -

,r-.....-=--...+--t---J--l--l--l--1---- -

l'---._ir-........~l,.,.-1--1--+---I- --*- --------- *---- ------- ---* _____., --*----- --- *-*-t,--- -l----l-1---1-*- -l-li--1 p....__ I°"-..

=: 1 2 o o -l--+--+--+--l-~c--+-J.-l---1-l-+-+-+--+-+--l--t--t--t--t--t---i----i---t~~-i-,-r-,11

~,

1-u a:

w er 800 400 0

._..__ _____ *--~i----*----------------

1-1--1--+.-1--l--i--+--t~

.. --~i"'---- --- -

--- -i--

1----*-J-f-f--1-- __ ------~ ___., ---*-- ****-*-* *-*-* **---- -

1--- ---- -- -

--1-li- -* --l- ---

~t'-.

r-----..

,_ _ _, _ _,__ ____ ---'--- __ --- ----- --. --*- --- _____ t::--,, K - ---- --f---+--1-- 1--1--1---+--I

--~-.... -.c-r--

~--1---

1-~~l---*1**--~- -

-~

----- --* -- *-- -- **-- ----- --- -- ~

'-----1-.....

~~

,~ --L--+ --- -

L-L--1--- -

-lr-,..,.__!--"'"1..-~--1---1-1-*

,_,_.,___,---~--------------- --*-----------*--*-*----

--+-l-----1-- ----- -- ---- ----------

------- -- ---- *---*------- ---*-- _..__ __ r--......_r"- -

I'-- **-

1280 1300 1320 1340 1360 1380 1400 1420 1440 BORON CONCENTRATION lPPMl

I I

I

.I I

'i

1.

I I

,I I

Section 6 TEMPERATURE COEFFICIENT MEASUREMENTS The isothermal temperature coefficient measurements were accomplished by controlling the RCS heat gains/losses with the steam dump valves to the condenser, establishing a constant and uniform heatup/cooldown rate, and then monitoring the resulting reactivity changes on the reactivity computer.

These measurements were performed at very low power levels in order to minimize the effects of non-uniform nuclear heating, thus, the moderator and fuel were approximately at the same temperature (between 543-549 °F) during these measure-ments.

To eliminate the boron reactivity effect of outflow from the pressurizer, the pressurizer level was maintained constant or slightly increasing during these measurements.

Isothermal temperature coefficient measurements were performed at various control rod configurations.

For each rod configuration, reactivity measurem.ents were taken during both RCS heatup and cooldown ramps during which the RCS temperature varied approximately 6°F.

Reactivity was determined using the reactivity computer and was plotted against the RCS temperature on an x-y recorder.

The temperature coefficient was then determined from the slope qf the plotted lines.

The x-y recorder plots of reactivity change vs. RCS temperature for each measurement are shown in Figures 6.1 and 6.2.

The predicted and measured isothermal temperature coefficient values are compared in Table 6.1.

As can be seen from this summary and from the Startup Physics Test Results and Evaluation Sheets given in the Appendix, all measured isothermal temperature coefficient values were within the design tolerance of +3 pcm/°F and met the accident analysis acceptance criterion.

In summary, all measured results were satisfactory.

24

N U1 BANK POSITION (STEPS)

. B.

D 228 209 21 228 Table 6.1 SURRY UNIT 2 - *cYCLE 5 BOL PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

TEMPERATURE BORON ISOTHERMAL TEMPERATURE COEFFICIENT RANGE CONCENTRATION (PCM/°F)

(OF)

(PPM)

HEATUP COOLDOWN AVERAGE PREDICTED DIFFERENCE (M-P) 543-549 14'*4

-2.24

-2.76

-2.50

-3.05

+0.55 543-549 1303

-5.61

-5.17

-5.39

-5.61

+0.22

I I

I

'I I

I I

'I I

I I

-a

~ -

~

E-l H

H E-l c.., <

~

Figure 6.1 SURRY UNIT 2 -

CYCLE 5 BOL PHYSICS TEST ISOTHERMAL TEMPERATURE COEFFICIENT HZP, ARO TEMPERATURE (°F) 26

I I

.I I

I

~

C,.)

P-t -

>4 E,-,1 H

~

E,-,1 C,.) <

~

Figure 6.2 SURRY UNIT 2 - CYCLES BOL PHYSICS TEST ISOTHERMAL TEMPERATURE COEFFICIENT HZP 1 B-BANK IN HORTZONTAL SCALE 1°F/inch TEMPERATURE (°F) 27

I I

I Section 7 POWER DISTRIBUTION MEASUREMENTS The core power distributions were measured using the incore movable detector flux mapping system.

This system consists of five fission detectors which traverse fuel assembly instrumentation thimbles in 50 core locations (see Figure 1.2).

For each traverse, the detector output is continuously monitored on a strip chart recorder.

The output is also scanned for 61 discrete axial points by the PRODAC P-250 process computer.

Full core, three-dimensional power distributions are then determined by analyzing this data using the Westing-7 house computer program, INCORE.

INCORE couples the measured flux map data with predetermined analytic power-to-flux ratios in order to determine the power distribution for the whole core.

A list of all the flux maps taken during the test program together with a list of the measured values of the important power distribution parame-ters is given in Table 7.1.

The measured power distribution parameter values are compared with their Technical Specifications limits in Table 7.2.

Flux Maps 1 and 2 were taken at zero power.

These flux maps serve as base case design checks.

Figures 7.1 and 7.2 show the resulting radial power distributions associated with these flux maps.

The results of Flux Map 1 indicated a quadrant power tilt ratio of slightly greater than 2%.

However, during this map, the flux level was low and there was a significant amount of flux drift. It is believed that this contributed to the high tilt indication.

Subsequent flux map results confirmed that the quadrant power tilt ratio was less than 2%.

Flux Maps 4 through 13 were taken over a wide range of power levels and control rod configurations.

These flux maps were taken to check the at-power design predictions and to measure core power distributions at various operating conditions.

These maps also provide incore/excore calibration data for the 28

I I

I nuclear instrumentation system.

The radial power distributions for these maps are given in Figures 7.3 through 7.10.

These figures show that the measured relative assembly power values are generally within 6% of the predicted values.

In conclusion, all power distribution measurement results were considered to be acceptalbe with respect to the design tolerances, the accident analysis acceptance criteria and the Technical Specification limits. It is therefore anticipated that the core will continue to operate safely throughout Cycle 5.

29

w 0

MAP BANK POSI'flON DESCRIPTION MAP PWR (S'l'EPS)

NO.

(%)

n D

ASSY.

Flux Map -

ARO l

0 228 216 F06 Flux Map - n In 2

0 33/34 228 1109 Flux Map 4XlC

..,5 228 106/107 Kl4 Flux Map -

5 43 228 170 B06 I/E Calibration Flux Map -

6 50 228 183/184 B06 I/E Calibration Flux Map -

7 61 228 190 B06

'I/E Calibration Flux Map -

9++

58 228 171 B06 1/E Calibration Flux Map -

11+1+

71 228 185 B06 1/E Calibration Hux Map -

12 88 228 190 Kl4 1/E Calibration Flux Map -

HFP, 13 100 228 215 ll06 Eq. Xenon

'l'al>le 7.1 SURRY UNI'l' 2 -

CYCLE 5 IIOL PHYSICS TES'J'S INCOllE FLUX MAP SUMMAIIY FT 110'1' Q

F~II HOT CHANNEL FACTOR*

CHANNEL FAC'fOJlH AXIAL FT N

PIN POIN'1' Q

ASSY.

PIN FAIi LK 13 2.48 1106 DE 1.46 HG 13 2.lll GOS Ill 1.81 LM 44 2.42 DOS HG 1.55 DE 33 1.99 B06 DE 1.45 DE 23 1.91 B06 DE 1.43 DE 24 1.85 D07 Ill 1.42 DE 32 1.93 D07 Ill 1.43 DE 33 1.84 B06 DE 1.41 KL 23

1. 79 D07 111 1.40 DE 3/i 1.72 D07 Ill 1.39 CORE Fz MAX F +

QPTRx AXIAL xy OFFSET AXIAL

(%)

POINT Fz 14 1.64 1.44 1.023

+35. r2 13 1.44

1. 76 1.006

+21.60 43 1.51 1.53 1,019

-23.87 32 1.30 1.41 1.011

-.-2.49 23 1.28 1.39 1.009

+3.87 23 1.25 1.38 1.008

+2.49 32 1.29 1.39 1.011

-1.97 33 1.24 1.37 1.005

-1.20 23 1.23 1.34 1.008

+1.26 23 1.17 1.35 1.005

+1.13 Notes:

Hot spot locations are specified by giving assembly locations {e.g. 11-8 is the center-of-core assel)lbly location), followed by the pin location (aenoted by the "Y" coordinate with the fifteen rows of *fuel rods lettered A through k nnd the "x"* coordinate designated in a similar manner). In the "Z" direction the core is divided into 61 axial points starting from the top of the core.

T

-FQ includes a total uncertainty of 1.08.

- N FAil includes_ a measurement uncertainty of 1.04

+F is evaluated at the midplane of the core.

xy xQPTR - Quadrant Power Tilt Ratio. This value is the maximum QlfR of the upper and lower halves of the core.

xxMap 3 was aborted,

++Map 8 was a quarter core M/D flux map.

+++Map 10 was a quarter core M/D flux map.

NO.

OF tl!Il!BLES 42 50 47 50 47 49 48 46 48 49

Table 7.2 SURRY UNIT 2 '- CYCLE 5 BOL PHYSICS TESTS COMPARISON OF MEASURED POWER DISTRIBU'J:ION l'AllAMETERS WI'l'll 'l'l!ElR TECHNICAL SPECIFICATIONS LIMIT T

FQ Hot Channel Factor a N

Fllll Hot Channel Factorb N ILOCA Fl\\11 ASSY

!lot Channel Factorb

,N ILOCA F Ml ROD Hot Channel Factorb Minimum Margin Mar~in Margin Margin Map Measured Limit

(%)

Measured Limit

(%)

Measured Limit

(%)

Measured Limit

(%)

5

1. 99 4.36 54.5 l.45

1. 73 16.2 1.29 3.43 62.4

1. 46 3.61 59.6 6

1. 91

_ 4.27 55.3 1.43

1. 71 16.4 1.28 2.95 56.6 1.43 3.10 53.9 7

1. 85 3.51 47.2 1.42

1. 67 15.0 1.27

2.,,2 47.5 1.42 2.54 44.1 9c

1. 93 3.76 47.9 1.43 1.68 14.9 1.28 2.53 1,9. 4 1.43 2.65 46.0 lld

1. 84 3.07 39.4 1.41

1.64 l/i.O 1.27 2.08 38.9 1.42 2.18 34.9 12

1. 79 2.43 26.3 1.l,O 1.59 ll.9 1.27 1.68 24.4 1.39

1. 76 21.0 13

1. 72 2.18 20.4 1.39 1.55 10.3 1.28 l.l,8 13.5 1.39 1.55 10.3 a The Technical Specifications limit for the heat flux hot channel factor, Factor, FT, is a function of core height, The value for FT listed above is the maximum value of FT in the core.

The Technical Specifigations limit listed above is evaluated at the r2ane of maximum FT.

The minimum margin Salues listed above are the minimum percent difference between the measured values of Fq(Z) and th~ Technical Specifications limit for each map.

All measured F6 hot channel factors include 8% total uncertainty.

b

,,N 1,N l I.OCA N j LOCA The measured values for the enthalpy rise hot channel factors, ~Lill'

Lill ASS). and F LIU ROD, include 4% measurement uncertainty.

cMap 8 was a quarter core M/D flux map.

d Hap 10 was a quarter core M/D flux map.

I I

I R

Figure 7.1 SURRY UNIT 2 CYCLE 5 BOL PHYSICS TEST ASSEMBLYWISE POWER DISTRIBUTION HZP, ARO F'

H M

L K

J H

G E

D C

B PREDICTED 0.40 0.73 0.40 MEASURED

F'CT DIFFEREIICE.

0.41

0.7S

0.40

2.~. 2.3. 0.7.

PP.ED!CTED 11EASL1REO

.PCT DlFFf~EHCE.

0.39 0.?4 l.06 l.13 1.06 0.94 0.39

0.40

0.95. 1.07, l,14

l.07. 0.93. 0.19.

2.5. 0.3. 1.1

l.2

0.2 * -1.q.

0.1.

o.52 1.01 1.11 1.22 1.~o 1.22 1.11 1.01 o.s2

0.54. 1.03. 1.18. 1.22

1.21

1.22. 1.1q, l.03. 0.54,

2.4

2.5

1.2.

0.2.

0.5

o.3

o.~.

1.1.

3.2.

o.52 a.es 1.14 1.18 1.21 1.10 1.21 1.1~

1.14 a.ea. o.s2

o.5o

o.aa. 1.11. 1.11. 1.19. 1.oa. 1.22. 1.21. 1.11. o.?o. o.55.

. -5.l, -0.1,

2.2. -0.l * -l.7. -1.4; 0.6. 2.9, 2.6.

2.7.* 5.5,

0.39 1.01 l,14 1.23 1.01 1.02 1.20 l.02 1.01 1.23 1.14 1.01 0.3?

0.37

0.96

l.13. 1.24. l.00. 0.97. 1.16

1.02, 1.03. l.iS

1.16

1.06. 0.43.

. -5.l. -5.l. -1.1

0.7, -1.3. -5.0. -3.3. -0.4.

2.3. 1.8.

2,7,

6.6. 10.3.

0.94

1.17. 1.18. 1.01

1.23. l.El. 1.11, l,Zl

1.23, 1.01. 1.18, 1.17. 0.9,.

0.94. 1.17, 1.17. 0.99. l.~O, 1.16. 1.07, 1.17, 1.21. 1.03. l.CO. 1.24. 1.02.

. -0.2. -0.3. -0.5. -1.5. -2.4. -3.5. -2.9. -3.l * -1.2.

E.l.

2.4.

6.3.

6.0.

A 0.40 1.06 1.22 1.21 1.02 1.21 1.09 1.15 1.09 1.21 1.02 1.21 1.22 1.06 0.40

0.41. 1.10, 1.27, 1.21. 0.99. 1.17. 1.06

l,li. 1.06, 1.21. 1.08

1.24. 1.27. 1.12, 0.42,

2.a. 3.3.

4.l.

o.3. -3.s. -3.o. -2.3 * -2.s. -2.a

o.,

5.o.

2.a.

4.4. 5.3. 5.3.

.

0,73. 1.13. 1.20. 1.10. 1.20. 1.11. 1.15. 0,87. 1.15. l.ll. l.ZO. 1.10

1.20, 1.13, 0.73.

, 0.75. 1.16. 1.23, 1.09. 1.15. 1.07, 1.13. 0.86

1.15. 1.14. 1.22. 1.13. 1.24

1.18. 0.77.

2.7.

2.6

2.0. -0.3. -4.6 * -3.1 * -2.3. -1.4. -o.o.

2.8

l.l.

2.8,

3.3. 4.4

5.0

0.40 1.06 1.22 1.21 1.02 1.21 1.0?

1.15 1.09 1.21. 1.02 1.21 1.22 1.06 0.40

, 0.41

1.09. 1.24. 1.19. 1.01. 1.11. 1.02

1.14. 1.10. 1.11. 1.01. 1.22

1.24. 1.10. o.~2

2.8.

2.2

1.6. -1.3. -1.3. -3.4, -5.7. -l,3. 1.0 * ~2-7 J -1.0.

0.5.

2.2

3.2

3.3 *

. 0.94. 1.17. 1.18. 1.01. 1.23. 1.21. 1.11. 1.21. 1.23. 1.01. 1.18. 1,17. 0.94.

. 0.97. 1.19, 1.14. 0.98. 1.18, 1.14. 1.06. 1.18. 1.21. 0.99. 1.16

1.17. 0,96

3.2. 1.6. -3.o. -3.o. -4.2. -5.8. -4.l * -2.0. -1.7. -1.a. -1.1

o.4.

1.8.

0.39 1.01 1.14 1.23 1.01 1.02 1.20 1.02 1.01 1.23 1.14 1.01 0.39

. 0.41, l.06

1.13. 1.17. 0,97. 0.99, 1.14. 0.99. 1.00. 1.22

1.16. 1.05. 0,41.

5.5. 5.5. -1.0 * -5.3. -3.7. -3.7. -5.5. -3.3. -0.5. -1.3

1.3. 4.2. 4,7.

o.52 a.as 1.14 1.18 1.21 1.10 1.21 1.1a 1.14 o.a8 o.sz

o.55. o.89. 1.oa. 1.16

1.21. 1.01. 1.1a. 1.11. 1.13. o.92

0.57.

5.5. 1.J. -5.3. -1.1. -0.1. -2.1. -2.s. -o.8. -1.0

5.o. 9,1 *

0.52. 1.01, 1.17. 1.22, 1.20

1.22 - 1.17. 1.01

0.52 *

0.55

0.96

1.18. 1.22*. 1.20, l,25. 1.24. 0.99. 0.57.

....,-:-~.~::.:. :~:\\:.. \\~;:. :~ ::. ;. :-~:~; ;:/:~. :-.-}: r.-~:;~:~.:.. !:~.:

STAUOARO DEVIATION

=2.036

0;39. 0.94. 1.06

1.13. 1.06

o. 14. 0.39.

0.41

0.99. 1.09. 1.16

1.12. 1.00. 0.41 *

5.5, 5,4. 2.8. 3.1. 5.l. 5,7. 5,7.

0.40 0.73. 0.40

0.42

0.77. 0.42.

s.J. s.4. s.a.

AVERAGE

.PCT DIFFERENCE.

2,8 MAP NO: S2-5-l DATE: 8/15/80 FT= 2.476 POWER== 0%

CONTROL ROD POSITIONS:

D BANK AT 216 STEPS Q

N FAH = 1. 462 F

= 1. 644 z

A. 0, = +35.921 BURNUP

== 0 MWD/MTU 32 QPTR:

NW 0.982 NE*

1.023 SW 0.984 SE - 1.011 3

5 6

7 8

9 10 11 12 13 14 15

I I

I R

p H

Figure 7.2 SURRY UNIT 2 -

CYCLE 5 BOL PHYSICS TEST ASSEMBLYWISE POWER DISTRIBUTION HZP, B-BAi.'lK IN M

K J

H G

E D

C B

PREDICTED MEASURED

,PCT DIFFEREtlCE,

0. 46 0. 86

0. 46

, 0.46

0.86, 0.46,

o.s, o.s

0.2

PREDICTED 11EASUPED

.PCT DIFFERENCE *

.................................................. ~

0.37 0.95 l.16 1.2?

1.16 0.95 0.37

, 0.37, o.,s

l.16, 1.29. 1.16, 0.94. 0.37,

0.2,

0.3. -o.o. -0.2. :0,3 * -0.4.

0.7.

0.46 0.86 l,Ol l.22 l,30 1,22 l.Ot 0.86 0.46

, 0,46

0.86

1.01, l.22

1,28. 1,21, l.Ol

0.87. 0.47.

0.2,

0.3.

0.3 * -0,0, -1,0. -0,7. -0.l.

l.O.

2,3.

0.46 0.74 0.90 0.63 1.14 l.16 1.14 0.63 0.10 0,74 0.46

, 0.47, 0.75, 0.89, 0.62. 1.12. 1.15. 1.13

0.63. 0.90. 0.76

0.48, 2.1.

0.2 * -0.2 * -1.6, -1.4, -1.4, -0.6, -0.l,

0.6.

1.5,

4.9,

0.37 0.86 0.90 l,04 0.92 l.ll 1.39 l.11 0.92 1.04 0.90 0.86 0.37

o.Ja

o.a,. o.o,

1.01

o.9o

1.01. 1.35. 1.oa. o.91. 1.oJ

o.91. 0.,1

o.fto.

3.5

3.3. -o.5. -2.6 * -~.4 * -3.4 * -2.9 * -2.2 * -1.6. -o.a. 1.7. 6.2

10.1 *

, 0.95, 1.01. 0.63, 0.92. 1,39, l.49. 1.41, l.49, l.39. 0.92. 0.63, l.01. 0.95 *

0.98, 1.05. 0.63, 0.90, 1.35. 1.44, 1.36, l.ft4. 1.33, 0.92. 0.64, 1.06. 1.02

3.5. 3.4. -0.7. -3.0, -3.0, -3.4. -3.6, -3.6, -4,0. -0.8

1.0

S,l

8.2.

0.46 1.16 1.22 1.14 1.11 1.49 1.45 1.57 1.45 1.49 1.11 1.14 1.22 1.16 0.46,

0.49, l,21

1.27, 1.15. 1.07, 1.45, 1.40, l.SJ. 1.40, 1.44, l.O?

1.16, 1.28. 1.23. 0.49

6,9,

4.6,

3.5.

0.7, -3.2, -3.0, -2.9. -3.1, -3.0, -3.4. -1.3

2.2.

4.8.

6.2,

6.6,

0.86

1.29, 1.30. 1.16, 1.39, 1,41, 1.57, 1.21

1.57, 1.41, 1,39. 1.16. 1.30

1.29 '. 0.86,

0.91, 1.35. 1.35, 1,17, 1.34, 1.37, 1.53, 1.18. 1.53. 1.37. l.36. 1.2~, 1.36, l.38, 0.?4.

6.9

s.o :

4.o

o.6. -3.3. -2.a. -2.a. -Z.4. -2.a. -3.l. -1.0.

1.3.

4.8.

9.4

0.46 1,16 l,22 1.14 1.11 1.49 1.45 1.57 1.45 1.49 1.11 1.14 l.22 l.16 0.46

, 0.49, l,22, 1.27. 1.15. 1.09. 1.45. 1.38. 1.53, 1.41. 1.44, 1.09. 1,17. 1,£8. 1.25, o.sz,

6.9. 5.o.

4.o

o.5. -1.a. -z.9. -4.3. -z.a. -z.1 * -3.3. -1.a.

3.1.

4.8

a.o. 12.s

0.95 1.01 0.63 0.92 l,39 1.49 1.41 1.49 1.39 0,92 0.63 1.01 0.95

. o.9a

1.05

o.64. o.9o

1.35

1.,.2. 1.34. 1.43. 1.36. o.92

o.64. 1.os

1.00

3.9, 3.7, 0.3. -Z.2. -3.l. -4.7. -5.3, -4.0, -z.z. -0.4.

1.6,

3.7,

6.2

0.37 0.86 0.90 1.04 0.92 1.11 1.39 1.11 0.92 1.04 0.90 0.86 0;37

o.38. o.89. 0,90

1.01

0.90

1.05

1.2a. 1.0,

o.90. 1.os. Q,92

o.9o

o.39.

3.9, 3.8. 0.8. -3.0, -3.2 * -5.l, -7.6 * -5.9 * -Z.7.

0,6,

Z.8.

4.7, 6,l

0.46 0.74 0.90 0.63 l,14 l.16 1.14 0.63 0.90 0.74 0.46

0.47. 0.75, 0,87, 0.62, l.10

1.11, 1.10

0.63. ~.90

0.77, 0.49,

3.8,

l,l, *-3.0, -Z.9, -3,2, -4.9, -3.6, -1.3, 0.6,

3.4, 6.5,

, 0.46, 0.86, 1.01, 1.22. l.30, 1.22, l,01

0.86

0.46,

, 0.48. 0.93, 1.04, 1.16. 1.26

1.22, l.02, 0.87, 0.48, 6.o.

a.1

2.8 * -3.1 * -l.l * -0.2

0;9

l.6

4.6

0.37 0.95 1.16 1.29 1.16 0.95 0.37

, 0.40, l.01, 1,10, 1.30, 1.18, 0.96, 0.37, 8.2,

6.9,

1.5

0.6

1.6,

1,6,

0.9,

STANDARO DEVIATION

=2.311 0.46 0.66 0.46

, 0.48, 0.69, 0.47, 4.8, 3.S, 2.2,

AVERAGE

,PCT DIFFEREIICE, 3,0 MAP NO: S2-5-2 CONTROL ROD POSITIONS:

D BANK AT 228 STEPS B BANK AT 34/33 STEPS DATE: 8/16/80 FT= 2.809 Q

N F t.H = 1. 806 F = 1. 440 z

A. 0. = +21. 595 BURNUP

e O MWD/MTU 33 POWER :e 0%

QPTR:

NW 0.991 NE

1. 006 SW 0.997 SE - 1.006 4

5 10 11 13 14 15

I 11 I

I I

I R

p H

Figure 7.3 SURRY UNIT 2 -

CYCLE 5 BOL PHYSICS TEST ASSEMBLYWISE POWER DISTRIBUTION D-BANK AT 106 STEPS H

L K

J II s

0 C

9 P~EOICTEO HEASUREO

.PCT DIFFEREtlCE, 0,37 0.63 0.37

0.37, O.o3. 0.37.

0.5. -o.o,

1.5,

PREDICTED t1E.4SU1lEO

,PCT DIFFEREIICE.

o.42 o.97 1.00 o.~o 1.00 o.97 o.42

0.43. 0.?6, l.00

0.87, 1.02. 1.00

0.44.

1.4, *l,2, -C,6 * -1,l,

1.3,

3,1

3.7.

0.58 1.09 1.23 1.22 1.16 1.22 1.23 1.09 0.58

o.se

1.10. 1.22

1.21

1.15. 1.22

1.25

1.12

o.,o.

l.Z

1.2 * -0.3. -1.2. -1.l

0.3. 1.9

J.l

4.5.

o.se o.96 1.23 1.23 1.24 1.11

1.24 1.23 1.23 o.9&

o.sa

0.59, 0.97. 1.24, 1.* 2

1.22, 1.10

1.24. 1.24, 1.,6, 1.01. 0.61

1.1. 1.J

1.0 * -o.6. -1.4. -1.0 * -o.J

0.1.

2.e.

4.9.

6.3.

0.42 l.09 1.23 1.27 0.99 I.02 I.21 1.02 0.99 1.27 1.23 l,09 0.42

0.43

1.11, 1.24, 1.27. 0,98, 0.99, 1.18, l.00, 0.99, 1.29. I.Jl, 1.10, 0.43.

2.1

2,0

0,7, -0,4. -1,3 * -2.8 * -3.l. -1.9 * -0,2,

1.2,

7.0

8,1,

3.I,

0.97 l,23 1.* 3 0.99, 1.01 1.15, 1.10, 1.15, 1.01. 0.99 1.23, 1.23 0.97.

, 0.99, 1.25

1.23. 0.97, 0.98. 1.10, 1.04

1.12, 0.98, 1.01. 1.28, 1.28, 1.00.

2.1

2.l

0.4. -1.9. -2.8. -4.0 * -s.o * -2.7 * -2.8

1.6,

3.9

4.4.

3.2,

A 0,37 1.00 1,22 1.2~

1.02 1.15 1.06 1.15 1.06 1.15 1.02 1.24 1.22, 1.00 0.37.

o.3?. 1.04. 1.24. 1.,3. o.oa

1.11

1.,2, 1.11. l.D4

1.12. 1.01. 1.26. 1.2s. 1.04. o.Js.

6.8.

3.5.

2.0 * -0.7. -4.1. *3.8. -3.6 * -3.3. -1.6. -2.5. -I.O,

1.7.

2.6.

3.4.

3.9.

i

o: 6; * * *;: ;o * *

i: i6 * *

i: ii* *

i: ii..

i: ia * *

i: is** *;: ~; * *

i: is* *

i: ia * *

i:; i..

i: ii* *

i: i6 * * *a: 90 * * *.;: 6; *

o.67. o.94. 1.1,. 1.09. 1.1q. 1.a4. 1.11. o.e5. 1.11. 1.os, 1.1a. 1.1J. 1.1s

o.94. c.68

6.6

4.0.

2.1 * -i.1. -~.J * -5.4. -3.3, -2.7. -J.6 * -4.6. -3.2.

1.3.

1.1.

4.1.

a.o

0.)7 1.00 1.22 1.24 1.02 1.15 l.06 1.15 l.06 1.15 l.U2 I.24 l.~2, 1.00. 0.37,

0.19. 1.04

1,25. l.Zl

0.96. 1.~9. 1,02, 1.10. 1.02, l.O~

0,98. l.Z4. I.ZS, 1.00. 0,41.

6.8.

J.9.

2.4. -2.s. -,.z. -5.5 * -4.o * -4.0 * -'+.4. -s.:; * -3.9.

o.. z.

2.1.

7,3. lJ.J

0.97 1.23 l.ZJ 0.?9 1.01 1,15 l.IO 1,15 1.01 0.?9 l.ZJ, l.23 0.97.

, 1.00. l,Z6

l,ZO, 0.13, 0.1~

1.10, I.04. J,09, 0.?7. 0.97. I.Z3. 1.:6, I.04,

2.6.

2.5, -2.l. -5.6, -5.I, -4.3. -5.0, -5.l * -4.0 * *l,S, -0.l

Z.6

6.6,

0.42 1.09 l.Z3 1.27 0.99 1,02 1.21

1,02, 0.99 1.27. 1,23. l,09

0.42.

0,43

1.12. 1.:0. l.21, o. 0 S

o.~a, 1.14, O.?i, 0.96. l.Z3

l.Z6. 1.14

0.45,

2.s

2.s. -2.1. -s.1. -J.7. -3.9. -,.o * -s.2. -3.l.

o.a.

z.4

4.s.,.1.

o.sa o.96 1.23 1.23 1.z1 1.11 1.24 1.23 1.23 o.?6 o.58.

. 0.59. 0,91. I.16, l.?O

1.21

1.07. I.ZO

1.22. l.c3

0.99. 0,62

2.5. -5.l, -5.1. -2.7. -2.0 * -4.), -3.5. -0.5,

0.6,

2.7.

7,5 *

. o.5a. 1.09. 1.2J

1.22

1.16

1.22. 1.23. 1.0,

o.s8.

0.62

1.1a

1.21

1.1a

1.12

1.:2. 1.24

1.11. 0.60.

1.a

1.a

J.4 * -3,l * -4.o * -o.o

1.5.

1.4

4.4 *

-** -~- -

0.42 0.97 1.00 0.90 1.00 0.97 0.42

0.45

1-04

1.03, 0.91, 1.03, 1.00, 0.43

1.1. 7.6

2.4. 1.1

2.6

2.s

1.2

STAHOARO OEYIATIOH

=2.195 0.37 0.63 0.37 0.39, 0.67 0.!8 7.3 S.8,

3,5

AVERAGE

.PCT DIHEREHCE.

3.2 MAP NO: S2-5-4 CONTROL ROD POSITIONS:

DATE: 8/18/80 FT= 2.415 Q

POWER QPTR:

== 5%

D BANK AT 107/106 STEPS N

F t:.H = 1.545 NW 0.986 F = 1.512 z

A. 0. = -23.873 BURNUP

== 0 MWD/HTU 34 NE 1.019 SW 0.992 SE - 1.003 4

s 6

ai 11 12 13 14 15

I I

I R

p N

Figure 7.4 SURRY UNIT 2 -

CYCLE 5 BOL PHYSICS TEST ASSEMBLYWISE POWER DISTRIBUTION I/E CALIBRATION -

FLUX MAP M

L K

H G

E D

C B

PREDICTED MEASURED

,PCT DIFFERENCE.

*0.41 0.72 0.41

0.40. 0.71, 0.41 *

-1.l, -1.4. O.l.

P~EDICTED MEASURED

PCT DIFFEREllCE.

0.42 0.95 1.03 1.04 l.03 0.95 0.42

0.41

0.94. 1.02. 1.02. 1.03. 0.97. 0.42.

-2.4. -1.7. -1.5. -1.9.

0.1,

l.8.

1.0.

, 0.56. 1.04. 1.17. 1.20. 1.18. 1.20. 1.17. 1.04. 0.56 *

0.55. l.03. 1.16, 1.17. 1.15, 1.18

1.17. 1.04. 0.56.

-2.2 * -0.8. -0.7. -2.0. -2.1. -1.2

0.7. 0.3. -0.1 *

0.56 0.93. 1.17 1.18 1.20. 1.10 1.20. 1.18 1.17 0.93 0.56

. 0.56

0.92. 1.17. 1.17. 1.17. l.06. 1.18. 1.18. 1.17. 0.?4, 0.59.

. -0.5, -0.9. 0.1 * -1.5 * -3.l. -4.0. -2.2. -0.6,

0.1.

1.5.

3.9.

0.42 1.04 1.17 1.24 1.01 l.03 1.20 1.03 1.01 1.24 1.17 1.04 0.42

0.42

1.05. 1.16. 1.22. 0.99. 0.99. 1,15. 1.00. 0.99. 1,22. l,22. l.lD. 0.44.

0.9.

0.9. -0.7. -2.l. -2.l. -3.9. -4.0. -2.9. -2.3. -1.8.

4.8.

6.0.

5.9.

. 0.95. 1.17. 1.18. 1.01. 1.14, 1.18. 1.11, 1.18. 1.14. 1.01. 1,18. 1.17, 0.95.

0.96. 1.18. l,18. 1.00

1.11, 1.14. 1.00. 1.15. 1.10. 1.01. 1.21. 1.23. 1.02.

1.1

1.1. -o.6. -1.s. -2.5. -2.9. -3.o. -2.4. -3.7. -o.3.

2.4. 5.6.

6.9.

A 0.41 1.03 1.20 1.20 1.03 1.18 1.09 1.16 1.09 1,18 1,03 1.20 1.20 1.03 0.41 0.42. 1.04. 1.21

1.19. 1.00

1.15. l.07, 1.14. l.08. 1.15

1.03. 1.23. 1.24. 1.10. 0.43.

3.1.

1.0,

0.8. -1.2. -3.l, -2.3. -1.4, -1.6, -1.0. -2.3. -0.7.

2.2,

3.5.

6.6,

5.~,

0.72. 1.04, 1.18. 1.10. 1.20. 1.11. 1.16, 0.89, 1.16, 1.11. 1.20, 1.10. 1.18. 1.04, 0.72,

0.74. 1.05. 1.17

1.08. 1.15, 1.08. 1.15

0.89. 1.14. 1.08. 1.19. 1.12. 1.20

1.06. 0.75.

3.1. o.8. -a.a. -2.1. -4.4. -3.2. -1.1 * -0.1. -1.5 * -2.5. -1.2.

1.8.

1.9.

2.4.

s.o *

0.41, 1.03. 1.20. 1.20. 1.03. 1.18. 1.09. 1.16

1.09. 1.18. 1.03. 1.20. 1.20. 1.03, 0,41.

0.42, 1.06

1.22, l,19. 1.00

1.13. 1.04. 1.13. 1.07, l.J5. 1.01. 1.20. 1.22. 1.07. 0.43.

3.1.

2.3. 1.8. -1.3. -3.4. -4.0. -4.5, -2.3. -1.3. -2.4. -2.0

0.1.

1.6.

3.7. 5,9.

0.95 1.17 l,18 1.01 1.14 1.18 1.11 1.18 1.14 1.01 1.18 1.17 Q.95

, 1.00

1.22. 1.19. 0.98. 1.10, 1.12. 1.07, 1.15. 1.12, 1.00, 1,18. 1.18, 0.99,

4.7. 4.6,

0.2. -3.2, -4.0, -4.5. -3.4. -2.5. -2.2, -1.2. -0.5, 1.6,

4.1.

, 0.42, 1.04. 1.17, 1.24. 1.01

1.03, 1.20, 1.03, 1.01. 1.24. 1.17, 1.04. 0.42.

0.43. 1.07. 1.17. 1.20, 0.99. 1.00, 1.16. 1.00

0.99. 1.24. 1.18. 1.06

0.43.

J,Q

2.?.

0.3. -3.2, -2.6, -2,7, -3.5. -3.6 * -2.8. -o.o,

1.0

2.1,

3.4,

0.56 0.93 l,17 l,18 1.20, 1.10 1.20 1,16. 1.17 0.93 0.56

, 0.57. 0.92, 1.13, l.17, 1.20

l.08. 1.16. l,l?. 1.18, 0.95, 0.58,

1.3. -o.5. -3.2 * -1.1. -o.5. -2.5. -1.9. 0.2,

o.8.

2.0

2.a *

, 0.56, 1.04. 1.17, 1.20. 1,18, 1.20. 1.17, l.04, 0.56.

, 0.58, l,06

1.18. 1.18, 1.14. 1.21, 1.21, 1.07, 0.58,

1.?. 2.1. 1.s. -1.9. -3.o

o.6

3.4. 2.9. 2.4

STAHDARO DEVIATION

=l.462

o.42. o.95. 1.03. 1.04. 1.03. o.?s. o.42 *

, 0.43. 0,99, 1.05, 1.04. 1.06

0,98, 0,43 *

2.7, 3.5, 1.1.

0.6

2.0, 2.9, 3.5.

0.41 0.72 0.41

, 0.43. 0.74. 0.42, 4.4,

3.7

2,6,

AVERAGE

.PCT DIFFERENCE.

2.3 MAP NO: S2-5-5 DATE: 8/20/80 FT=l.985 POWER"' 43%

CONTROL ROD POSITIONS:

D BANK AT 170 STEPS Q

N F tiH - 1.-446 F = 1.299 z

A. 0. = -2.494 BURNUP"' 10 MWD/MTU 35 QPTR:

NW 0.989 NE 1.011 SW 0.997 SE - 1. 003 l *.

3

4.

5 6

1.

a*

10' ll 12 13 14 15

I I

I R

p H

Figure 7.5 SURRY UNIT 2 -

CYCLE 5 BOL PHYSICS TEST ASSEMBLYWISE POWER DISTRIBUTION I/E CALIBRATION -

FLUX MAP M

K J

H G

D C

8 PREDICTED MUSUPEO

.PCT DIFFERENCE, 0.41 0.72 0.41

0.42

0.73

0.42

1.6.

1.3.

1.s

PREDICTED MEASURED

,PCT DIFFEP.EHCE, 0,42 0.95. 1.04 1.06 1.04 0.95 0.42

0.41. 0.95

l.04, l.05, l.04, 0.96

0.42 *

. -1.1.

0.4 ** -0.l * -0.7, 0.3.

l.l.

1.2.

0.56 1.03 1,16 1.20 l.18 l,ZO 1.11 1.03 O.S6

, O.S6. l.03. 1.17, 1.20. 1.15. 1.18. l.lb, l.C4. 0,57 *

, *l.O,

O.l

0.7, -0.l, -2.3, *l.3 * -0.2,

0.5,

1.4,

0.56 0.92 l.16 1.18 1.20 l.10 l,20, l.18 l.16 0.92 O.S6

o.57. o.92. 1.11. 1.11. 1.19. 1.oa. 1.1a

1.16. 1.16

o.93. o.ss.

l.O, -0.2. 0.4, *0.6 * -1.~. -1.6 * -2.0. -1.6. -0.3.

l.l.

3.2.

0.42 1.03 1.16 1.24 1.02 l.03 1.20 1.03 1.0[

1.24 1.16 1.03 0.42

0.43, 1.06, 1.16, 1.21

1,00, 1.01, 1.18, 1.01, 0.99, 1.22, l.JQ

1.07. 0.44.

2.6,

2.6, -o.s. -2,7, -l.8, -2.0 * -2.0, -2.5, -2.6, -1.7.

2,2,

4.l,

5.3,

0.95 1.16 1.18 1.02 1.16 1.18 1.11 1.18 1.16 1.02 l,18 1.16 0.95

0.98. l.~9. 1.18. 0.99. 1.13. 1.16

l.09, l.15. l.ll, 1.01. 1.20, 1.21. 1.00.

2.7.

2,6, -0.4, -z.s, -2.7, -2.2, -2.l, -2,Q, -4.6, -0.8.

1.4,

4.1,

5.7, A

0.41 1.04 1.20 1.20 l.03 1.18 1.09 1.16 1.0?

1.18 1.03 1.20 1.20 1.04 0.41 0.42, l.06, 1.22

1.20

1.00. l.15. 1.07. 1.13. 1.06, l,14. l.03. l.[3. l.24, l.10. 0.44,

2.9. 1.9. 2.2. -0.4. -2.9. -2.b, -2,l, -2.2. -2,5, -3.3. -0.2

2.2,

3.3.

5.7.

6.2

0.72 1.06 1.18 1.10 l.20 1.11 1.16 0.89 1.16 l.ll 1.20 l.10 1.18 1.06 0.72 o.74. 1.01. 1.19. 1.09. 1.16, 1.os. 1.14. a.ea. 1.15. 1.10

1.21

1.12

1.*o. 1.11. o.78

2.7, 1.4,

0.4, -0.7. -,.2 * -2.4 * -2.l, -1.5. -1,2 * -1.1.

0.7, 1.9, 1.9.

4.7, 7.2

0.41 1.04 1.20 1.20 1.03 1.18 1.09 1.16 1.09 l.18 1.03 1.20 1.20 l.04 0,41 0,42, l.O~

1.21, l.l?, l,02, 1.16, 1.07, l,15, l.09. l.17. 1.03, 1.21, 1,22

1.08. 0.44,

2.9,

l.9, !*3, -0.5. -1.4, -2.1, -2.l, -0.8, -0.3, -0.9, -0.4,

0.8, l.4.

4.4,

7,5, 0.95 1.16 1.18 1.02 1.16 1.18 l.ll 1.18, l,16 1.02 1.18 1.16 0,95

. 0.97, 1.19. 1.18. 0.99

1.13, l,15. 1.08. l.16, 1.14, 1.01

I.la. 1.18. 0,98.

2.5,

Z.5. -0.4. -2,7. *2.7, -2.4 * -2.5. -1,7 ~-l.b. -0.?.

0.1

1.3. 3.0.

0.42 1.03 1,16 1.24 1.02 l.03 1.20 I.OJ 1.02 1.24 1.16 1.03 0,42

, 0.42

1.05. 1.15. 1.19. 0,99. 1.01, 1.15, 1.00, l.CO, 1.22, l,17

l.06, 0.43,

1.7.

1.7. -0.9. -4.4. *2,4, -2.l, -3,8, -3.0, -1.i * -1.3

1.0

2,6

3,1

0.56 0.92 1.16 1.18 1.20 1.10 1.20 1.18 1.16 0.92 0.56

0.57. 0.91. 1.11, I.lb

1.20. l.07. 1.13, l.18

1.17. 0.94. 0.58.

l.O * *l,l, -4.4, *l,5, *0,4 * -2,4 * *l.4,

0,3,

0.5

2.3

4.0

STA!lO~RO DEVIATIO!l

=l. 427 0.56 1.03 1.16 1.20 1.18 1.20 1.16 1.03 0.56

, 0.57. 1.04

1.17. l,18, 1.15. 1.21

l.20, L.06

0.58,

l.l,

1.2

0.8, -1.4. -2.2. l.l

3.3,

2.9. 3.l *

, 0,42, 0,95 l,04, 1.06 1,04 0.95 0.42

, 0.42

0.98. 1.06

1.07. l,06, 0.98, 0.43.

1,2

3.3. 2.5. l.3. 2.5,

3,1

3.3.

0.41 0.72 0.41

, 0.44, 0.76

0.42,

6.0,

4,7.

3.0

AVERAGE

.PCT DIFFEREHCE.

= 2.0 4

5 7

8 9

10

ll

).2 13

14.

15 MAP NO: S2-5-6 DATE: 8/21/80 FT = 1. 909 POWER= 50%

CONTROL ROD POSITIONS:

D BANK AT 184/183 STEPS Q

N F ~H = 1. 426 F =

z 1.281 A. 0. = +3.873 BURNUP = 25 MWD/MTU 36 QPTR:

NW 0.994 NE 1.000 SW 0.997 SE - 1.009

I I

I p

H Figure 7.6 SURRY UNIT 2 -

CYCLE 5 BOL PHYSICS TEST ASSEMBLYWISE POWER DISTRIBUTION I/E CALIBRATION - FLUX MAP H

L K

H G

u PREDICTED H.EASUREO

,FCT DIFFERENCE.

0.41 0.73 0.41

, 0.41, 0,73. 0.41 *

-o.a. -o.a. -0.2

PllECICTED t1EASUREO

,PCT DIFFEREHCE

o.41 o.95 1.04 1.os 1.u.. *** o.95 o.41

o.41. o.9,,. 1.0::s

1.00

1.04

o.. 95. 0.42.

-0.2 * -1.0. -1.5 * -1.1. -o.a. o.4. o.7.

0.56 l.OZ l,16 l.20 1.18 1.20 l,16 l.02 0.56

, 0.56

l.03. 1.15, 1.18, 1.15, 1.18, 1.15

1.03, 0.56,

, -0.l,

0.4, -0.2. -1.3, -2.7, -1.6. -0.3,

0.4.

l.3.

0.56, 0,91, l.lS, l.la, 1.20, 1,10

1.20

1.18. l.15

0.9l. 0.56,

, 0.56. 0.91, 1.16, l,17. 1.18, 1.08. 1.18, 1.16, 1.15, 0,92, 0.57,

0,6, -0.2,

0.2. -0,9. -1.7, -2,l * -1.9, -1,2, -0.2,

0.3,

3.0,

0.41 1.02 1.15 1.24 1.02 1.03 1.20 1.03 1.02 1.24, 1.15 1.02, 0.41

, 0.42, 1.04, 1.15, 1.21, l.00, 1.02, 1.18. 1.01, l.00, 1.22, 1.17, 1.06. 0.44.

1.2.

1.2 * -a.a. -2.5 * -1.s. -1.4. -i.7. -1.a. -l.9. -L.4 ~.

l.6

3.9.

s.7.

o.95 1.16 1.1a 1.02 1.1a 1.19 1.11 1.19 1.1a 1.02 1.1a. 1.16. o.95

. 0.96, 1.17, 1.17, l,00, 1.16, 1.17, 1.10, 1.17 ~ 1,15, l.Ol, l,19,-1,20, 1.00,

1.2.

1.1. -o.a. -1.9. -1.9. -1.2 * -1.4. -1.1. -3.o. -o.4.

1.~.

J.6

s.o.

0.41 1.04 1.20 1.20 1.03 l,19 1.09 1.16 1.09 1.19 1.03 1.20 1.20 1.04 0.41

, 0.43, 1.06, 1.21. 1.19. 1.01, l,17. 1.08, 1.15, 1.08, 1.17, 1.04. 1.22, 1.23. 1.08. 0.43.

2.a

1.0.

0.1. -a.a. -2.::s * -1.6 * -o.6. -o.9. -o.9. -1.1.

o.5. z.z.

2.6

J.o.

J.5

0.73 1.08 1.18 1.10 1.20 1.11 1.16 0.89 1.16 1.11 1.20 1.10 1.18 1.08, 0.73

. 0.75, l,09. 1.18, l.09, 1.17, l,09, 1.15, 0.89, 1.16, l.ll, l.~l, 1.12. 1.:0, 1.10. 0.77,

2,7.

0.9. -0.2, -1.0 * -2.7. -1.7. -0.5, -0.2, -0.l, -0.2

1.0.

l.7,

1.6,

2.0.

4.3,

0,41 1.04 1.20 l.ZO 1,03 1.19 l.O?

1,16 l.09 1.19 l,C3 l.ZO l.ZO l.04 0.41

0,43, 1.C6, 1.21, l.19. 1.02, 1.17, 1.07, l,16, l.09, 1.18. l.03. l.ZO. 1.21, 1.08. 0.44.,

z.a.

1.a

1.2. -o.4. -1.1 * -1.1. -1.1 * -o.3

o.4 * -o.3 * -o.3. o.3. t.4. 3,4

6.1*.

, 0.95 1.16 1.18 1.02 l.18 1.19, l.ll 1.19, 1.18 1.02 1.18 1,1?, 0.95,

. 0.97, 1,19, 1.18, l.00, 1.15. l,16, 1.09, 1.17, 1.17, 1.01. 1.17. 1.17, 0.98.

2.a.

~.1. -0.1. -2.2 * -2.2. -z.o. -2.1. -1.1 * -1.0 * -o.a. -o.4

1.~

z.9.

0,41 1.02 l.15, l.24 l.02 l.03 l.20 l.03 l.O:?, l.24 l.15 l.OZ ** 0.41

o.~2

1.04. 1.1s,. 1.19

0,99

1.01

1.1s. 1.01

1.01. 1.22

1.16. 1.04

o.42

2.0,

2.0. -0.5, -3.7, -2.3 * -2.2, -3.7. -2.6 * -1.l * **l.l,

0.6.

l.9,

2,5,

MAP NO:

0.56 0,91 1.15 l,18 1.20 1.10 1.20 1.18 l.15 0.91 0.56

, 0.56

0,91

1.11, 1.16, l,18, 1.07, 1.16, 1.18, l,16, 0.93, 0,57,

l,3 * -o.7 * -,.7. -1.e * -1.2 * -2.a. -1.5

0.4

o.6.

2.1

2.e.

0.56 1.02 1.16 1.20 1.1e 1.20. 1.16 1.02 o.5~

, 0,57, l,05, 1.17, l,17. l.15

1.20, 1.19, l.05, 0.57, 2,0,

2,6,

l,l, -2,2, -3.0,

O.l.. 2,7.

2.7

2.5

0.41 0.95 l.04 1.08 1.04 0.9~

0.41

, 0,43, 0.99, l,06, 1.08, 1.05, 0.97, 0.43,

2.a. 4.o

1.a

0.2

o.a

2.0.

2.9

STMIOARO DEVIATION

=l,191 0.41 0.73

, 0,44, 0.76 5.4.

3.6 0,41*,.

0.42

l. l AVERAGE

,PCT DIFFERENCE,

= l, 7 S2-5-7 DATE: 8/21/80 POWER "'

CONTROL ROD POSITIONS:

FT = 1.854 QPTR:

Q 61%

D BANK AT 190 STEPS N

F.tiH = 1.416 NW 0.993 F = 1. 252 NE 1.000 z

A. 0. = +2.493 SW 0.999 BURNUP "' 30 MWD /MTU SE - 1.008 37 3

4 5

7

10 ll 13

, 14 15

I I

I R

p Figure 7.7 SURRY UNIT 2 -

CYCLE 5 BOL PHYSICS TEST ASSEMBLYWISE POWER DISTRIBUTION I/E CALIBRATION -

FLUX MAP H

L K

H G

0 C

B PREDICTED MEASURED

,!'CT DIFFERENCE.

0.41 0.72 0.41

, 0.40, 0.7l, 0.41,

, -1.4. -l.4. -0.4,

PP.EOICTEO tlEASUREO

.PCT OIFFEREHCE, 0.42 0.95 l.04 l.05 1.04 0.95 0.42

0.4Z. 0.94. 1.02

l.03, l.03. 0.96

0.42 *

-0.4 * -1.5, -1.8, -2.0, -0.7,

l,O,

l.O,

0.56 1.03 l.16 1.20 l.18 1.20 1.16 1.03 0,56

, 0.56, 1.04

1.16. 1.18. l.15. l.18. 1.17. 1.04, 0.57,

-o.3

0.2 * -o.5. -1.a. -2.7. -1.b

o.J.

o.6.

1.1

0.56 0.92 1.16 l,18 l.20 l.10 1.20 1.18 1.16 0.92 0.56

. o.s1. o.92

1.11. 1.11

1.11. 1.01. 1.18

1.18. 1.11. o.94

o.sa

0.1. -o.J

o.z. -1.z * -2.5 * -3.3.--z.2 * -o.s.

o.6.

1.6

3.6.

0,42 1.03 l.16 l.Z~

1.01 1.03 1,20 1.03 1.01 1.24 1.16 l.OJ 0.42

, 0.42. 1.05, 1.15, 1.21, 0,99, 1.01, 1.17, 1.01. l,00, 1.24, 1.20, 1.08, 0.44.

1.6,

l,6. -0.9 * -2.7. -2.l. -2.4. -2.9. -2.6 * -1.6 * -0.4,

3.0.

4.,.

6.2.

0.95 1.16 1.18 l.Ol l.lS 1.18 l.ll l.18 l.15 l.Ol 1.18 l.16 0.95

, 0.97, l.18. 1.17, 0,98, l.12

1.15, 1.08

1.15

1.11. 1.01, l.Zl, l.:c. 1.00,

l.4

1.4. -1.l. -3.0. -2.7. -2.Z, -2.5. -2.5. -3.9, -0.0.

2.3,

4.4.

5.6,

0,41 l.04 l.20 l.ZO 1.03 1.18 1.09 1,16 1,09 1.18 l.03 1.20 1.20 1.04 O.~l

0.42

1.05. 1.21, 1.19

1.00

1.15

1.07. 1.14, 1.07. l.l5. 1.04. 1,24, 1.23. 1.08, 0.4Z.

2.6,

1,6,

1.2. -0.9, -3.5 * -z.6, -1.5 * -1.6 * -1.3. -2,l.

0.4.

2.7,

2,9.

4,3.

J.7,

0.72 1.05 1.18 1.10 1.20 1.11 1.16 0.89 1.16 l.ll 1.20 1.10 1.18 1.05 0.72

0.1~. 1.06. 1.11. 1.09

1.16. 1.08.,.14

o.a9

1.15. 1.10

1.21. 1.1J. 1.to. 1.01. o.,s.

Z.5,

1.7.

1.1. -0.9, -3.7. -Z.6, -1.3. -0.7, -0.S * -0.7.

0.9.

Z.2.

1.9.

1.9. 4.5

0.41 l.04 1.2~

1.20 l.03 1.18 1.09 l,l6 l.09 l.18 1.03 1.20 1.20 l.04 0.41

. o.*z, 1.06. l.Z3. 1.20, 1.01, 1,15, 1.07. 1.16. 1.09. 1.17, 1.03, 1.21, l.ZZ. l,07. 0.44.

2.6,

Z.5.

Z.3. -o.4 * -1.9. -2.6 * *1,4

0.0 * -o.z * -1.l, -0.6

0.8.

1.7.

J.6,

6.4,

MAP NO:

o.os l,16 1.18 1.01 l.15 1.18 1.11 1.18 l.15 1.01 1.18 1.16 0.?5

o.98

1.20. 1.1a

o.9?. t.12

1.1J. 1.oa. 1.11

1.13

1.01. 1.1a. 1.18. o.98

3.5,

J.4.

O.l. -Z.6. -Z.7. -4.3 * -Z.6, -l.6, -l.5. -1.B.

0.1,

1.6,

3.4

0.4Z 1.03 1.16 l.Z4 l.Ol 1.03 l,ZO l.03 l,01 1.24 1.16 l,03 0.42

, 0.43. l.06, l.16, 1.20. 0,99. 1.01. 1.15. 1.00, l.00, 1.23. 1.18, l.06

0.43,

2.4,

2.4. -0.3, -J.7, -2.3. -2.3. -3.9. -Z.9. -1,6, -0.8.

l.Z.

2.7, 3.3,

0.56 0.92 1.16 1.18 1.20 1.10 1.ZO 1.18 1.16 0.92 0.56

o.57. o.92

1.12

1.16. 1.11

1.01

1.19. 1.19, 1.1a. o.95

o.sa.

l.3, -0.6, -3.7. -1.6, -0.?, -2,7, -l.3,

0.6,

l,0,

2,7. 3.8.

STAHOAP.O

, 0.56, 1.03. l.16, 1.20, l,18, l,20. l.16, l.03, 0.56,

, 0.58. l.07, l.18, :.17. l.15, 1.20

1.21

1.07. 0.58,

2.5

3.6

l.7 * -1.9, -2.9,

0.4. 3.6,

3.5

3.3.

o.~2

o.95 1.04 1.05 1.04 o.95 o.42

, 0.43, 0,99, 1.05, 1.05, 1.04

0.97, 0.43,

3.6

4.2,

1.5,

o.o,

0.7.

2.3

3.8,

0,41 0.72 0,41 OEVIATIOH

0.43, 0.74, 0.41

4,8. 3,2

0.8,

.I.VERAGE

,PCT OIFFEREHCE,

= 2.0

1.319 S2-5-9 DATE: 8/24/80 POWER CONTROL ROD POSITIONS:

FT = 1.933 QPTR:

Q D BANK AT 171 STEPS N

Ft,H = 1.429 NW F = 1. 291 NE z

A. o. = -1. 970 SW

= 58%

0.985 1.004 1.000 BURl.UP = 65 MWD/MTU SE - 1.0ll 38 3

4" 5_

6 8

10 ~

11.

lZ 15

I I

I

! I H

Figure 7.8 SURRY UNIT 2 -

CYCLE 5 BOL PHYSICS TEST ASSEMBLYWISE POWER DISTRIBUTION I/E CALIBRATION - FLUX MAP n

L J

11 r

P'REDICTEO MEASURED

PCT DIFFERENCE.

0.41 0.73 0.41

0.41

0.73. 0.41 *

0.4. 0.3.

0.4

PREDICTED MEASURED

.PCT DIFFEREUCE

0.41 0.95 1.04 1.07 1.04 0.95 0.41

. 0.41

0.95

1.03. 1.0*

1.04. 0.95. 0.42.

-0.1. -o.z * -0.9. -1.3. -0.6

0.3.

0.9.

0.56 1.02 l.16 l.ZO 1.18 1.20 1.16 1.02 0.56

. 0.56

1.02

1.16

1.19. 1.15. 1.18. 1.16, 1.04. 0.57.

-0.2. -0.2 * -o.z * -0.7. -2.7. -1.2.

0.5.

l.l.

l.9

0.56 0.92 1.16 1.18 1.20 1.10 1.20 1.18 1.16 0.92 0.56

0.56. 0.91. 1.13

1.16

1.18. 1.08

1.19. 1.18. 1.16. 0.93. 0.58

1.0 * -0.6. -2.l * -l.5. -l.3. -1.6 * -1.l

0.6.

0.7. 1.2.

3.3

0.41 1.02 1.16 1.24 1.02 1.03 1.20 1.03 1.02 1.24 1.16 1.02 0.41

. 0.42

1.04

1.15

l.ZO

l.00

1.02

1.18. 1.02. 1.01

1.23

1.18. 1.07. o.,4

1.a. 1.0 * -o.9. -3.l * -1.9. -1.0. -1.2 * -1.2. -1.1 * -o.7

1.7.

4.1

6.1

0.95 1.16 1.18 l.02 1.18 1.19 1.11 1.19

1.18 1.02 1.18 1.16 0.?5

0.96. 1.17

l.17. 1.00. l.16

1.18. l.10. l.16. l.14. l.Ol. 1.19. l.21

l.00

l.5.

1.5 * -o.5. -1.1 * -1.6 * -o.a. -1.1 * -1.a. -3.3 * -1.0

o.9.

4.1.

s.1

A o.41 1.04 1.zo 1.20 1.03 1.19 1.09 1.16 1.0, 1.19 1.03 1.20 1.20 1.04 o.41

0.42

1.05

1.21. 1.19. 1.01

1.17. 1.09. 1.15

1.08. 1.16

1.00

1.21. 1.23. 1.08. 0.43.

2.1

1.1

o.9. -o.6. -2.2 * -1.3. -o.z. -o.a * -1.2. -2.0. -2.1.

0.1.

z.3.

3.5.

3.2.

O.i3 1.07 1.18 1.10 1.20 l.ll 1.16 0,89 1.16 1.11 l."O 1.10 1.13 1.07 0,73

o.;s. 1.oa. 1.1?. 1.09

1.11. 1.10. 1.16. o.a9

1.16. 1.11. 1.1,. 1.11. 1.20. 1.01. o.76.

l.?

0.1

0.2 * -0.1 * -z.5. -1.l. -0.1. Q.l. -o.o. -o.z. -o.5.

o.7.

1.1.

1.a.

4.o.

0,41 1.04 l.ZO l.ZO 1.03 1.19 1.09 1.16 1.09 1.19 l.~3 1.20 l.:o 1.04 O.~l.

0.42. l.C6 * !.21

1.20. 1.03. 1.17

1.08. 1.16. 1.10, 1.19. 1.03. l.ZO. l.Zl

1.07. 0.44.

2.1.

1.4.

1.0 * -0.2 * -o.4. -1.3. -1.3

o.z.

o.9. -o.~. -o.z.

o.4

1.2

3.o

s.7.

0.95 1.16 1.18 1.02 1.18 1.19 l.ll 1.19 1.18 l.C2 l.18 l.16 0.95

0.97. 1.18. 1.17. 1.00. 1.15. 1.17. 1.09. 1.18. 1.17. l.01

1.18. 1.17

0.97.

l.9

l.9. -o.3. -2.1 * -z.o. -l.6. -l.6. -~.s. -o.a. -o.a. -0.1

1.0

2.4.

0.41 1.02 1.16 l.Z4 l.02 1.03 1.:0 1.03 1.02 1.24 l.16 1.02 0.41

0.42

1.04

1.15

l.19

0.99

1.01

1.16

0.99. 1.00. 1.22

l.17. l.05

0.43.

1.a. 1.e * -a.a. -4.l. -2.4 * -l.9. -3.3. -3.a * -2.0. -l.4.

o.9. 2.l

z.7.

0.56 0.92 1.16 1.18 1.20 1.10 1.20 1.18 1.16 0.9Z 0.56

O.S7. 0.91, 1.11, 1.15

l.18

1.07. 1.18

1.18. 1.17

0.94

0.58

1.e * -o.s. -4.l. -z.o * -1.z * -2.1. -1.1.

o.6. *a.a. 2.4.

l.6

ST At/DARO

0.56

l.02. 1.16

l.ZO

1.18. 1.20, 1.16

1.02. 0.56 *

0.57

1.06

1.17. 1.17. 1.15

1.20. 1.18

1.05

0.57.

2.S

3.3. l.4. -2.2. -3.0.

0.1

2.3

2,4

3.1

0.41 0.95 1.04 1.07 1.04 0.95 0.41

, 0.43. 0.99

1.06

1.06

1.06

0.97. 0.42

3.3

4.4

1.9. 0.4. 1.3. 2.1,

2.3 *

- - - - o:;.i***o:1;***0:;.i****************

OEVIATIOH

0.44. 0.76. 0.42,

S.6.

4.0. 1.7.

AVERAGE

.PCT DIFFEREflCE

l.6

1.z34 MAP NO: S2-5-ll DATE: 8/26/80 POWER ::: 71%

CONTROL ROD POSITIONS:

FT = 1.842 QPTR:

Q D BANK AT 185 STEPS N

FtH = 1. 410 NW 0.996 F = 1.239 z

NE 1.004 A. o. = -1.195 SW 0.995 BURNUP ::: 9 0 MWD /MTU SE - 1. 005 39 l

2 7

10 ll

12.

14 15

I I

I R

Figure 7.9 SURRY UNIT 2 -

CYCLE 5 BOL PHYSICS TEST ASSEMBLYWISE POWER DISTRIBUTION I/E CALIBRATION - FLUX MAP p

tl H

L K

J H

u PREDICTED NEAS!.mED

,PCT DIFFEREtlCE, 0.42 0.74 0.42

, 0.42, 0.74, 0,42,

. -0.1. -0.2, -0.1,

PREDICTED NEASURED

.PCT OIFFEF.EIICE.

0.42 0.94 l.04 l.07 1.04 0.?4 0.4Z

, 0.42, 0.?4. 1.03. 1.07, 1.04, 0.94. 0.42,

, -0,8. -0,3, -0.2. -0.4. -0.l, -0.3, -0.3.

0.56 l,OZ 1.14 1.19 1.18 1.19 1.14 l.OZ 0.56

O.S6. 1.01, 1.14. 1.18. 1.17. 1.18, l,14, l,01. 0.56,

, -0.8, -0.5, -0.2, -0.4, -0.7. -0.8, -0.7. -0.5, -0.3,

0.56 0.9Z 1,15 1.17 l.19. 1.10 1.19 l.17 1,15 0.92 0,56

, 0.56, 0.91, l.14, 1.16, l,18, l.09, 1.18, 1.16, 1.14. 0.92, 0.58,

O.l * -0.9, -0.7. -l.2, -o.~. -l.l, -1.l * -1.l, -0.6.

O,l.

Z.l,

, 0.42, l,02, 1.15 l.24 l.OZ, 1.04, 1.20 1.04 1.02 1.24 1.15 1.02 0.42

, 0,42, 1.03. l,14

1,20, 1.01, 1.03

1.19. l,02. l.Ol. l.22

l.l~. 1.05, 0.44,

0,9.

0,8, -1.0, -Z.8. -1,7, -1.2, -1.J. -1.4, -1.6. -1.3,

l.Z,

3.4.

5.1.

, 0.94. l.14, 1.17. 1.02. 1.18. 1,19. l,12. 1.19

1.18. 1.02. 1.17, 1.14. 0.94,

, 0.95, 1.15. 1.16, l.Ol

1.17. 1.18. l.ll

l.18

1.16

1.02, 1.18. I.la. 0.95,

o.6

o.6. -o.8 * -1.4. -1.6 * -1.0. -1.z * -o.9. -Z.3. -o.4

o.?.

2.9.

4.1

A 0.42, 1.04 1.19

1.19 1.04 1.19, 1.10 1.17 1.10 1.19 1.04 1.19 1.19 1.04 0.42 0,43. l.04. 1.19, 1.18. 1.02. 1.18, 1.10. 1.17. 1.11. 1.18. 1.04. 1.21. 1.£1. l.07. 0.43.

1.6

o.6.

o.z. -o.7 * -1.9. -1.1 * -a.1 * -o.z

o.5. -a.5

o.4

1.a.

z.o.

z.1.

Z.6.

0.74. 1.07. 1.18. 1.10, l.ZO, 1.12, l,17. 0.91. !.17. 1,12

l.tO, 1.10. l.!8. l.07

0.74.

0.75. 1.08, 1.18, l,09. 1.17, 1.10. l.17, 0.91. l,18. 1.12, 1.:1. l.lZ. 1.19. 1.09. 0.77.

1.5. o.s. -1.0. -0.9, -z.s. -1.4. 0.1.

0.6.

o.s.

0.3.

0.5.

1.4.

1.2.

1.8.

4.0.

0.42. 1.0*

1.11 1.19 l,04 1.1?. 1.10 1.17 1.10 1.19 1.n~

1.19 1.19 1.04 0.42 0,43, l.05. l.20, l.19

1.03. l.17, 1.08

1.17. 1.10. l.l~. l.04. l.ZO. l.ZO. 1.07. 0.45.

l.6,

1.2.

l.O * -0.3. -0.9. -1.5, -1.6. -0.3.

0.4. -o.:. -0.Z.

0.3.

1.0.

Z.9.

5.9 *

. 0.94, 1.14. 1.17. l.OZ. l.la. 1.19. l.lZ. 1.19, l.lD. l.CZ. 1.17. 1.14. 0.?4.

. o.96. 1.11. 1.11. 1.00. 1.lb. 1.11. 1.10. 1.18. 1.1a. 1.02. 1.11. 1.1s. o.q6

z.o

z.o. -a.4. -Z.l. -z.3. -1.a. -1.1. -o.,. -o.6. -o.6. -o.3.

o.s.

1.,.

, 0.42, 1.02 l.lS l,24 l.OZ. 1.04 1.20 l.04 1.0.

1.24 l,15 1.oc 0.42

, 0.42. l,03, 1.14. 1.19, l.00, l.02, 1.16. l.OZ, l.Ol. 1.23. 1.16, 1.03. 0.43,

1,2,

l,Z, -1.l. -4.0 * -2.6, -2,l * -3.l, -z.z, -1.0, -0,7,

0.6.

1.3,

l.S,

o.56 o.92 1.1s 1.11 1.19 1.10 1.1, 1.11 1.1s o.,~

o.56

, 0.57, 0,91. l,10, 1.14, 1.17, l.07, 1.18, 1.18, 1.16, 0.93. 0.57,

0.3. -1.3. -4.0 * -C.4. -1.8. -Z.9, -1.3,

0.4,

0.7,

1.8,

l.8,

. 0.56, l,02. 1.14. 1.19. 1,18. 1.19, l.14, I.OZ. 0.56,

, 0,57, l.05, 1.16, 1.16. 1.14, 1.19, 1.17, l.04, 0.58.

, 1.9, 3.5. l,l * -2.6. -3.Z, -o.o,

2.6,

Z.S

2,0,

STANDARD DEVIATION

l.091 MAP NO: S2-5-12 0,42 0.94 1.04 1.07 1.04 0.94 0,42

o.43. o.9e

1.04

1.01. 1.04

o.,~

o.43 *

3.s. 3.7. 0.1.-0.3. o.7. 1.a. 2.8.

, 0.42, 0.74

0.42.

, 0.44, 0,76, 0,43.

3.5,

2,5,

1,0.

CONTROL ROD POSITIONS:

DATE: 9/1/80 FT = 1. 790 Q

D BANK AT 190 STEPS N

F llli = 1.398 F = 1.234 z

A. O. = +1.257 BURNUP ::: 175 MWD/MTU 40 AVERAGE

,PCT OIFFEREIICE.

= l.4 POWER::: 88%

QPTR:

NW 0.996 NE 1.005 SW 0.991 SE - 1. 008 4

5' i I 6/

10 ll 12*

I 13!

14

I I

I

?

N Figure 7.10 SURRY UNIT 2 -

CYCLE 5 BOL PHYSICS TEST ASSEMBLYWISE POWER DISTRIBUTION HFP, EQ. XENON i'1 L

K J

H G

0 C

6 PREDICTED t":CASU~ED

.PCT O!FFE~ENCE.

0.43 0.75 0.43

0.43

0.75

0.42

O.l

O.l * -0.4.

i=REDICTED ME~SU:t:!J

.PCT DIFFERENCE.

o.42 o.93 i.o4 l.ll i.o4 o.93 o.~2

0.41

0.93. l.04

l.10

l.03. 0.92. 0.41 *

-0.2 * -0.6 * -0.7 * -0.8 * -1.0 * -1., * -0.7.

0.56 l.Ol l.14 l.18 l.18 l.15 l.14 l.Ol 0.56

0.56

1.01

l.13. 1.17

l.16. l.16. l.l~. l.00. 0.:,.

. -o.z * -0.1 * -o.3 * -o.a. -1.6 * -1.4. -1.1. -o.6.

0.1.

0.56 0.91 1.14 l.16 1.19 1.09 l.19 l.16 1.14 0.91 0.56

. 0.56, 0.90. l.13

l.15. 1.17. 1.03

1.17. l.15. l.13. 0.9l, 0.57.

0.4. -o.5. -o.4. -1.1 * -l.3 * -1.5. -1.4 * -o.9. -o.4

o.z

2.7

0.42 l.Ol l,14 l,23 l.03 1.04 1.20 l.04 l.03 l.Z3 l.14 l.01 0.42

. 0.4Z. l.02. 1.13. l.20. 1.01. l.02. I.IS. l.02. I.Cl. 1.:1. 1.:3. 1.05. 0.~4.

0.9.

0.9. -0.7. -2.J. -1.4. -1.5 * -1.5. -1.5. -1.6. -l.l.

0.9. 4,0.

6.D.

0.93 l.14 1.16 1.03 1.23 1.:1 l.l2 1.21 l.23 l.03 1.16 l.14 0.93

. 0.94, l,14. 1.15. 1.02, l.Zl. l.19

l.ll

l.19. l.19, l.C2. l.17, 1.17. 0.96.

Q.3

0.3. -0.6. -0.6. -1~1. -l.O * -l.2 * -1.2 * -z.s. -0.5.

0.3.

J.4.

S.3.

0.43 1.04 l.!8 1.19 l.04 1.21 l.!l l.!S l.ll 1.=1 l.C4 l.l?

l.lS l.C4 0.43

. 0.43. 1.05. l.13. l.18. l.02. 1.19. l.11. 1.17. l.ll. l.1~. ~.04. l.Zl. l.:o. 1.08. 0.44.

1.a.

o.s. -o.z. -o.7. -1.6. -o.9. -0.2. -o.4. -o.z. -1.2.

o.~...,.

1.s l.l.

z.7.

0.7S l.ll l.18 1.09 l.ZO l.lZ 1.:a 0.11 l.lS 1.1:

1.:0 1.:9

!.la l.ll 0.75

. 0.76. l.ll. l.!3. l.:s. 1.17. 1.11. 1.13. 0.92. !.!S. l.lZ. 1.:0. l.:l. 1.19, l.lZ. 0.78.

1.a.

o.6.

0.3. -o.a. -1.&. -1.J. -0.1.

a.z.

0.1. -0.1.

o.;.

1.~.

c.7.

!.4.

~.0.

0.43

.c.;. 1.:.a. 1.19. 1.c!+

1

~,

1.:.1. 1.1e 1.11

~...,

1.04 l.l?

!..:..s 1.0~

o.-+3

. o..:.3. l.;;:>. :.:a,,!_.:.:?. 1.04. 1.19. l.-cq. l.!3. 1.:1. 1..:0. :..:3. :.:a. !.la. 1.07. :)..:.5.

1.s.

!.~.

1.5.

a.1. -o.3. -1.:. -l.6. -o.3.

o.4. -1.b. -o.~. -o.b.

a.3.

.7.

b.J.

0.?3 l.14 1.16 l.CJ l.2l 1.21 1.12 l.Zl 1.23 l.03 l.l6 l.14 0.93

. 0.16. 1.1&. 1.16. l.01. 1.~o. 1.1s. 1.10. :.19. 1.:2. 1.c:. 1.:~. 1.13. a.;;.

2.s. z.s. 0.1. -1.1. -1.7. -1.a. -2.0. -a.1. -o.;. -o.a. -r.z. -0.1.

1.1.

0.42 l.01 1.14 l.~3 1.03 l.04 1.20 l.C4 1.03 1.23 1.14 l.Ct 0.~2

. o.~3. 1.J3. :.:4. 1.10. 1.on. 1.02. 1.1s. l.c:. :.J2. 1.~z. 1.1s. 1.c~. o.4~.

2.3.

2.l * -o.z. -3.5. -2.3. -%.3. -3.6. -Z.l. -~.3. -J.6.

C.5.

l.Z.

1.3

a.so o.91 l.!4 1.16 1.19 1.09 1.1?

1.16 1.14 o.;1 o.so

. o.s1. o.91. 1.10

1.14. 1.11. 1.06. 1.1a. 1.11. 1.:s. o.93. o.57.

2.2. -0.l * -3.5. -2.l. -l.6, -2.7. -0.9.

l.O

l.2

2.5.

l.d *

. 0.56, l,Ol

l,l4. 1.18

l.18, 1.18. l.14, l.Ol. 0.56.

0.57. l.04

l.15, l.16

l.15, 1.19. l.17. l.C4. 0.57.

2.9

3.7. l.3 * -2.a * -2.4.

o.4.

3.o.

3.l

z.s.

0.42 0.93 l.04 l.ll l.04 0.93 0.42

, 0.43, 0.97

l.06, l.ll

l.05. 0.95, 0.43.

3.7,

4.l.

l.6

O.l,

0.6.

2.0.

3.2

0.43 0.7S 0.43 STM!CA~O OEVIAT!CN

=l.226

, 0.45. 0.77. 0.43.

4.4. 2.9.

0.6.

.?CT O:rFr'El(E~~::E.

= l.4 MAP NO: S2-5-13 DATE: 9/12/80 POWER CONTROL ROD POSITIONS:

N Ft.H = 1.387 QPTR:

FT = 1. 716 NW Q

D BANK AT 215 STEPS F = 1.171 NE z

A. o. = +1.130 SW

100%

0.9946

1. 0019 0.9981 BURNUP

== 450 MWD/MTU SE - 1. 0053 41 4

0 7

e

c l3 14 15

I I

I Section 8 REFERENCES

1.

M. C. Cheok, R. T. Robins, and S. A. Ahmed, "Surry Unit 2, Cycle 5, Design Report," NFE Technical Report No. 107, Vepco, December, 1979.

2.

Surry Power Station Units 1 and 2 Technical Specifications.

3.

Surry Power Station Units 1 and 2 Final Safety Analysis Report.

4.

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

5. *T. J. Kunsitis, "RXFLOW, A Computer Program to Calculate Reactor Flow and Thermal Output," NFO-CCR-8, Vepco, December, 1979.

6.

"Technical Manual for Westinghouse Solid State Reactivity Computer,"

Westinghouse Electric Corporation.

7.

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

42

I I

.1 I

I I

11 APPENDIX STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEETS

I erence II l~itions (Design)

Ill

'Test caiditions Sct:ual)

I I

I IV l

est e.sults I

I V

ept2.nce riteria I

SURRY POWER STATION UNIT 2 CYCLE 5 STARTUP STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET JUL 3 1 1980 Test

Description:

Reactivity Computer Checkout Procedure Number/ Section:PT28.111~PP* B Sequence Step.Nu:nber:

Bank.Positions (steps)

SDA: 228 CB : 228 SDB: 228 cc : 228 CA: 228 CD:

RCS Te:c:iperature (°F): 547

~o~er Level (% F.?.): 0 Other (specify):

Below Nuclear Beating

, r r-{

i ior:

Bank Positions (steps)

SDA:2.28 a:22.g Date/Time Test Pe~!or.z?ed.:

SDB: 2c.8 CC:2. 2. 8 CA: 22.8 CD: /lf-'f-8 / /~ - IS" / 80 2..39--S -

OO'r-0 RCS Terenerature (°F) : S'f-7 Po-wer L~vel (:Z F.P.): 0 Other (specify):

6e:low Nv~ear He.a.i:h-,8

Me.asilred P ar2.l!le"t.er (description)

Pc = Measured Reactivity using p_:-computer Pt* Inferred Reacti~-ity from reactor period He.asured Value

~e:sigu Value (ActuzJ.. Conditions)

Design Value (Desig.i. Condi~ions)

Pc = +*2 3.c.

-2.S,O pt = +

2 2. *.5"

-c.S,O

~;~ = + 3. /

o.o I

Pc -Pt I

<.04 j:it I

Pc -

Pt I ~.

04 Pt

+1-3-5

+"f-3.8

-0.7 Refere:1ce WCAP 7905, Rev. 1, Table 3.6 FSAR/Tech Spec Reference Not Applicable Desi£!! Tolerance is met

R' :""ES D !W Acceptance Cri ter::..a :Ls met: ;Et YES O NO i-, S"""

+fz.S-. S"

-+.s: 6'",3,5

-2.2.

-r 3, 2

-~o.o

-~o.s-

- 0.2 Con:pleted

~ 1 11 7 ::4w a ua tea...,y: ___

.....__i:.-0=.=.__._~--=-=->==----

Revie~ed By: __ C:-=-_-_:J'_._'_~_,~~---------

.I A.l lfr'O Engineer

1*

I teference II Cest

~<,dit:i,ons esign)

I III Test:

~onditions lctual)

I IIV I

l est t

ultS I

I

~cceptance lriteria I

Co~pleted I

SUR.RY POwER STATION mniz 2 CYCLE 5 STARTUP STAR fUP PHYSICS TESTS RESULTS M""D EVALUATION SHEET Fl JUL 3 1 1980 Test

Description:

control Bank B Worth ~asurenent Procedure Number/ Section: PT28.ll/App *.E Bank Positions (steps)

SDA: 228 SDB: 228 CA: 228 CB : Moving CC : 228 CD: 228 Bank Positions (steps)

. SDA: 2 Z.B CB: M O"INC:i SDB:Z.Z.8 CC: 22.8 Date/Time Test 8/1S/80*

CA:U.S CD:ZZ.8 Per for.med: s~o 133'/

co1-1p1..~

162.0 Sequence Step Nm::ber: //

RCS Temperatu~e (°F): 547 Power Level (% F.P.): O Other (specify):

Below Nuclear Heating RCS Te~per2.ture (OF):

S4Ca,Z r Power Level (% F.P.* ) : o.o Other (specify):

Measured Parameter (description)

Integral Worth of Control Bank B Measured Value Design Value (Actual Conditions)

Design Value (Design Conditions)

Reference FSAR/Tech Spec

.Reference I ;2.. 8 4 PC/P7

/Z,z.5 +/- I Z3 [)C,M 1225 +/- 12 3 pcm VEP-FFD-1,E'E: 107 ; \\'E?-??.:r-36 ; Letter ::rom Hr. W.

Tnoffi:l.s (Vepco) to !>~r.E-:.

?... Senton (NRC) ci::.ted June 25, 1980 (Serial No. 569)

Not Applicable Not Applicable Design Tolerance is met. : {gJ. YES D HO Acceptance Criteria is met: 0 YESONO A.2 yr,,

/

Evaluated By~, /J 1

(l

/

Revic,;.:ed By:

C. ~,..d~iJ NFO Engineer

I I*

ference rI st nlions D

gn) t II est onditions Alual)

I I

.I I

.cceptance

,iteria

.,:i::..

STAR ruP PHYSICS TESTS RESULTS.M""D EVALUATION SHEET JUL 3 1 1980

.FINAL RFSl JI T~

Test

Description:

Control Bank D Worth Measurement -

Rod Swap Procedure NU!:lber / Section: PT28.ll/App. F Bank Positions (steps)

SDA: 22B SD:S:

228 CA: 228 CE : Moving CC :

228 CD: Moving Bank Positions (steps)

SDA: 22B CB: MO\\/INY Date/Time Test PerfoTI!led:

SDB: 228 CC: ZW CA: ZU3 CD:,-.ov,l'Ju Sequence Step Number:

1:5 RCS Te~perature (°F): 547 Po~er Level (% F.P.):o Other (specify):

Below Nuclear Heating RCS Terr.per2.ture (OF): s1c.:.. 4 'f" Power Level(% F.F.):o Other (specify) :

Measured Parameter (description)

Integral Worth of Control B;:a..nk D -

Rod Swap

~ie2.sured Value

Cesig:i. Value (Ac: tU2.l Condi ti.ans)

Design Value (Design Conditions)

Reference J 2. 14 1209:: 181 pen (Critical Re.fe:cenc::: B2.r.L Position =

216 ste?s)

~?-Fri:-NFE 18/ ; \\..=.F-FF.Z.--36 ; iR.i:.-:.e.:- z=o;:: !.....=. '.. :. *,.

'Iho;;;.es (Vepco) to ~'.:::.H. ?.. :::e~t.cn (~RC) c:c.ted J:.:.-ie 26, 1980 (Se::-ial No. 559) ;.Me::s.o=-a..'1t...T.1 =:-o::i Mz. T.. K. P.:,ss to C":".

~ J. Lozito c.a~eC July l, 1980.

FSAR/Tech Spec Not Applicable Reference Not Applicable

-Ji---}-----1--------~--

VI Design Toler2.nc:e is met

JZl. YES O NO

!rrts I-I I

Acceptance Criteria is met: rg) YES D NO

~

Evaluated s;,~ ~/

Revie..,cd By:

C.,_1. z:.~..,.-0-~~1/

,;Fa.E.n~inecr

.I SURRY POWER STATION UNIT 2 CYCLE.5 STARTUP STAR rw PHYSICS TESTS RESULTS.Ahl) EVALUATION SHEET flNAL RESULTS JUL 3 1 1980 I

Test

Description:

Control Bank C Worth Measurement - Rod Swap lerence Procedure Nur:iber I Section: PT28.ll/App. F Sequence Step Number:

10 II Bank Positions (steps)

(OF): 547 I

t RCS Teu::perature Clditions SDA: 228 SDB:228 CA:228 Power Level (% F.P.): 0 esign)

CB : Moving cc :Moving CD :228 Other (specify):

Below' Nuclear Heating

-I III Bank Positions (steps)

RCS T e.n?.p era t ur e (°F) : S45, Co "/:'

Test.

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

lditions SDA: z.-z..8 SDB: Z.Z.8 CA: Z.Z8 Other (specify):

ctual)

CB :,-.., ~

""'6 CC: MO'l/1"',(:;

CD: U.6 BtrUMJ Nl.)C.Lt!A~ HEPtTJI.J6 I

Date/Time B/tc./~

~

Test PerfarI!!ed:

1113 I

Maasured Para.meter (description)

Integral Warth of Control Bank C -

Rod Swap IV I

Neasured Value B4r

( ADJU,Slc() M=rl.sue.ro

?:J--.

c.Zmc.Ac.. faj I rto>-1 :

J4C.:. STc.PS) lest Design 1.'alue I

?,esults (Actual Cm::.ditions) f BSD 'I-I 28 ?"-"'I

( At).)()$i'c0 1--1cf1:s~f!£D c.Jli~ICAL. fb~mON = /4{.,, s~

I Design Value (Design Con:iitions) 851 +/- 128 pcm (Critical Ref e:::: c:cE r:~:-.;.!:

I Position = '160 s ~e:-*~ ::

"'0w*!'.,.:-:~:i= ~ 107 ; *vE?-::"?..:-35 ; L-e-:-:.e===::=-. ~.=. \\i....

Reference

'!11=::-.as (Ve?CO} to !-:=.E.

r ** Ce:i-;:::i (::?.:) &tee J*.!..-;e 26,

1920 (Se:=i.a::.. No. s*c) ;,.~.......... -ar..:.~--

.:. ___ '-'-.... K.

F:oss 0-.

to Dr. --..,, Lo=~~o ~~~e= Julv '

!.9£0

V 1e~t2.n7e FSAR/Tech Spec Not Applicable ri teri2._

Reference Not Applicable VI Desi.'?;!l Toler2n'ce is met

~ 'YES0 HO fen~s Acceptance Criteria is met: 0. YES 0 NO I

I I Cc~pletedBd.J 9,M~

le. '- Ens;:i eer Evaluated A,4

I nc iol gn)

I st !I

1 I

I

. I

s I

I tale te a

I

~s1 I

SURRY POWER STATION UNIT 1... CYCLE..2.. STARTUP STARrUP PHYSICS TESTS RESULTS AND EVALUATION SHEET JUL 3 1 1S3J FINAL RESULTS Test

Description:

Control Bank A Worth* Measurement - Rod Swap Procedure NUI!lber I Section: PT28.ll/App. F Sequence Step Number:

/7 Bank Positions (steps)

RCS Temperature (OF): 547 SD.A: 228 SDB: 228 CA:Moving Power Level (% F.P.): 0 CB : Moving cc : 228 CD:228 0th.er (specify):

Below Nuclear Heating

Bank Positions (steps)

RCS Tei:q>er2.ture (OF): s4s.s or Po..-er Level (.., F.P.* ): 0 lo SDA: 2'2..8 SDB: 2.2.8 CA: f--.0\\/IN6 Other (specify):

CB: M.ovtJ.J6 CC: 'Z.2.8 cn:zze

~

NC.X:.LE:13,e ;IEA,1}.16 Date/Tilne Test a(l~jBo Performed:

J7So Measured Para.meter (description)

Integral Worth of Control Bank A -

Rod Swap Measured Value b50 f,c.1-i ( ~ tJjLJ ~ i21' i--i cf:!> u eE1) cz., r.:!h<. ~sir1cr-.J: 1/4 5rt:Ps)

. Design Value (Actual Conditions) 5t1 +/- /00 ~

( A D.Ju.s1EO M£rr:1.)e.ea cemc.A-L fc,5/r/CN== I 14 ~T?P5 i

/

Design Value (Design Conditions) 578 100

( Cri tic:a1

~

+/-

pcm r,! erer.c:::.:iE:"".:.:

Posi<:ion :

121 Si::.?S, V::?-: FD-!,FE 107 ;. * *.:..?-F:"..:-36 ; :.o:-:.-:e= ----,.....

Reference

-:"nor..as (Ve?CO) u, !-'.r.E. ?.* r:"=;-,:.~~ ~~~:.:;

""**-.e,~,

1980 (Se::ial }lo. 569) '*

r,'~.... --=- ~*-.: roi *.'-. -. K.

?..:>SS to Dr. E. ~. L°'.::i. ":.O -== te.:. :".!l ~*.

1920.

FSAR/Tech Spec Not Applicable Reference*

I Not Applicable Design Tolerance is met

rn. Y1:s o NO Acceptance Criteria is raet :@ YES0 KO A.5

SURRY POwu. S'I8.TION UNIT 2 CYCLE 5 STARTUP STA.1ITUP PHYSICS TESTS RESULTS.Ahl) EVALUATIO'N SHEET JUL 3 1 \\980 FJNAL RESULTS I

Test

Description:

Shutdown Bank B Worth Measurement - Rod Swap Ee nee Procedure !-lumber I. Section: PT28.ll/.App. F Sequence.Step *Number:

IB I

Bank Positions (steps)

RCS Tempe.:-a ture (°F): 547 st SDA: 228 SDB:Moving CA: 228 Po..ier Level ("' F.P.): 0

id ions De~ign)

CB : Moving cc : 228 CD: 228 Other (specify):

Below Nuclear Heating Ill Bank Positions (steps)

RCS Te~perature (°F): 545-S t)F

'st Power Level. (% F.P.* ): c, n

tions SDA:ZZ8 SDB: J-.4o'l1iJ6 CA: Z?.8 Other (specify):

Act.-ual)

CB: MO\\JJ/116 CC: Z.28 CD: zzs Z,~ N r.x.u:A-~ tt EJ4TJIJ 6 Date/Time Test e;1,/eo Performed:

l?o8 I

Measured Parameter (description)

Integral Worth of Shutdown Bank B -

Rod Swap I

Measured Value 952.

( AOJu~reo I 63

\\

lt

~

HEAs0£EO C../llilcAL ?o~ me,../ =

s~,.:

Design Value

.e.lts (ActU.2.l Conditions) q~q t /45 A:M (Ao.lr..>5Tm MEf'6(.)fU!) CJZ,IHcAi. fo!, J rJ i:w.- It., 3 jJ!?.S)

Design Value I

(Design Conditions)

'9 78 +/- 147 pcm (Critical F.i:.f ere::-.ce..::a r!::

Positicr.. =-

17~ steps~

'\\rc.?-F;':.D-'.l?E lOi ; '\\=.:-':F.:r-30 ; i..e-:-:.e~ =r~~ !-'....=. w. "*

I' Reference

~c:::-.as (Vep=o) to !-'.=. P..

? ** Cen~on {:;'2*::) c.a -:.ec:. Jc.."le 2 6, 1980 (Se:::ial !lo. 569)

~mc~a..-id.~~: ro::-, !-~. ~-

1'..

Ross to D:::.

~ J. Lc::i'to..=~:==d J...:l*: l, l9SO.

-v 1.c.1~tan7e.

FSAR/Tech Spec

Not Applicable 1.ter1.a I

Reference Not Applicable Jvr Design Tolerance is met

IB!-YESO 1:10

,.-.ents Acceptance Criteria is met: 00 YES ONO 1-I Completed q J. Q~

T t ~P*ineer A.6

I erence II rlt..

ditions esign)

III Test.

,-* di tions ctual)

I I

.I IV I

.. est

?._ ults I

I I

'I SURRY POWER STATION UNIT 2 CYLE 5 STARTUP ST.AR.TUP PHYSICS TESTS RESULTS Ai.'\\"D EVALUATION SHEET JUL 3 1 1980 Test

Description:

Shutdown Bank A Worth. z.leasurenent -

Rod Swap Procedure Number/ Section: PT28.ll/App. F Bank Positions (steps)

SDA: Moving SDB: 228 CA: 228 CB : Moving CC : 228 CD: 228 Bank Positions (steps)

SDA: Mov,A/6 CB:,-.,ov,A.>6 Date/T:i.lne Test Perforned:

SDB: z.z.e, CC: ZZ8 8/!c./ea 1945 CA: ZU3 CD: Z.2..8 Sequence Step Number:

/9 RCS Temperature (°F): 547 Power Level (% F.P.): O Other (specify):

Below Nuclear Heating RCS Te~per2.ture ( 0 F): 5"'1S.G. "f' Power Level (% F.P.* ): o.t:>

Other (specify):

Measured Parameter (description)

Integral Worth of* Shutdown Bank A -

P.od swap Measured Value Design Value (Actual Conditions)

Design Value (Design Conditions)

Reference FSAR/Tech Spec Reference 1055 +/- 15 8 pcm (Critical Refere~ce :ank Pos*iticn = 189 steps;.

v~P-.:'F~~;::.... JI ; *\\~?-Fi.U-36 ; Le'C~::--.::-or;:!'"~. ~. ;,:..

Tno:=-.as (Ve;:co) to ~!'°.H. ?... D:ntc:. ~!!?.Ci c.1ted.Ju:1e 26,

~980 (Se=ia~ No. SE9j ; t-~e::1ora.."1C.u..~==-:;:: !-"~. ':. 1:.. k:,ss to D=. ~- J. I..o=it~ C..:~ed :ulv l, 19SC.

Not Applicable Not Applicable Design Tolerance is niet. : ~ YES D HO Acceptance Criteria is met : ~ YES O NO A. 7

I -Ir

'!.ifrence

11*

'.litions sign)

,I III Test

,~;~)s I

I IV I

kt ts I'

1*

\\'

1 cptm1ce

-i~erln

.... siJt~Y -I*mrn: ST1~1'IO:f Ul;.i'I i:_ CYCl.2 5... S1:AR11JP STARTL1' PliYSlCS TESTS KESULTS AKO.!:.'VALUATION SHEET JUL 3 1 1980 FINAL RESULTS Test

Description:

Total Rod Worth - Rod Swap Procedure Huobcr I Section: NA Sequence Step Number: NA B~nk Positions (steps)

RCS Te-r::perature (6F): 547 SDA:Moving SDB:Moving CA:Moving Po*wer Le'.~el (% F.P.): O CB : Moving cc :Moving CD:Moving Other (specify):

Ilelo-.* Nuclear Heating Bank Positions (steps)

RCS Te=.perature (Of):.o~

Power Level (% F.P.): 0 SDA: Movin ~

SDB: MoviV'I~

CA: Mo\\fir.~

Other (specify):

CB: MoviY\\!) - C:: Movi~j CD: Mov_iY\\<:;

Below Nvc..lea..r HtW:.1~

Date/Time Test

<t,/ts--1" /80 Perfor.:::r:c.:

/?,39

/9'1-~

!-~easured Paral:!.<2.ter (description)

~otal ' Integral Worth of All Rod Banks - Rod Swap

}ieasured Value I

~II 2.

=

ff!AY'l Total Le sign "vc.lue

(.!.ctu.2.l Conclitic:is)

T

= S-8'1/. S8'?

-Total

-r-pc..m Design Value (Desib11 Conci.itions)

T

= 5896 +/- 590 pcm

~Total I

VS?-:"?.:-~.;::: 107 ; \\.:..?-Fr.::-36 ; Let.:e-!" i=o:. ~-=. "*

Ref ere.nee

'::-ior.-..:.s (Ve_;:,:::o) tc !".:.H. !"... Den 't.CZ"'1

(!*:~::). c.a te C J~e., -

.c, I

lSEC-(S:=ial. No. 56?)

,..~.....,...-a: -~**- ~---,. __

~ K.

?.:::>SS I

to D:. -* J. Loz.i~

C2. ~e:: ""~l*.*

~,c:--

f-__;~;:.=...:~.:.....::..:.....=:.::...::.0::_::=..;.:.=....=..:;.:~~.,;;-~*;:.;""~---~---~~~------=-*-

J __

N_O_t_Ap_p_licable FSAR/Te.:h

-:11.**.t------;'----i:-:e_r_e_r_t_.r_,_(_:P_. _____

l, __

N_o_t_A_.p_p_1 __ i_* c-ab--le ______________ _

l,

D~si;n Tol£-r.::ince is,::-c:t

~ *::rs O HO

~

l,ccc:;:: t.:::.;, cc. Cz-i t c r i2 is,.let: )'8:: Y ::S 1J i*iCl I

I I

A.8 l',::: - J f( ~

,.-1' r?

__ C.J Lr~..;. __

I I -

SURRY POWER STATION UNIT 2 CYCLE 5 STARTUP JUL 3 1 1980 STARTUP PHYS It fWAES1:?t~( JIVT~~TION SHEET I

'l'est

Description:

Critical -Boron Concentration -

ARO eference Procedure Ntll!lber / Section: PT28.ll/ App. C Sequence Step Nt!l!lber:

7 II Bank Positions (steps)

RCS Te::::perat:ure (°F): 547 I Test SDA: 228 SDB: 228 CA:

Po1,;1er Level (Z F.P.):O nditions 228 CB. 228 cc. 228 CD: 228 Other (specify):

(Design)

Below Nuclear Heating I-III Bank :Positions (steps)

RCS Te.:c::pe:r-at:ure (OF): S'f,. ~

Test Po'wer Level (::: F.?.):0 tnditions SDA: 2.2.8 SDB: c2.8 CA.: 2e.8

other (specify):

(Actual)

CE: 2.2.8 CC:2,2.8 CD:228 Be.low Nuu~a_r He.a.:ti'-ri~

,I Date/Time Tes-c 8fs-/ao Perfon:i.ed:

031--0 I

Measured Para.meter (description)

(CB) ARO ' Critical Eoron Concentration - ARO I

IV Measured Value

H

/1--37 (CB)ARO=

pprn lest Design Value CB=

=tesults (Ac.tu.al Conditions)

/ 3 9Lf + 5"0 ppm I

Design V2.lue I

(Design Conditions)

CB= 1394 + 50 ppm I_

Reference VEP-FRD-:NFE 107 V

FSAR/Tech Spec ac X CB.£_ 15 i 1,15 pcm

'eptanc.e B

rit.er:ta I

Reference FS.AR Section 14.2.5 VI Design Tolerance. is met. : l YES O HO

,nnn~nts

Accept2.nce Cr:!..te.ria is met:

YE.SO NO I

uc

= -8.6 pcrn/ppn for preliminary an2lysis.

B

°'~e = - t:t *./1 p~/ppM for. fina) ~a.ly~is.

I Evaluateq By:

I A,9 Reviewed By: ----'C_. _J_,_k_,

I--I I

~ference I

I!

I Test fnditions Design)

I III Test-.

'nditions (Actual)

I I IV I

I Test esults I

I I

V

.cceptance Criteria I -VI

,~ents SUP.RY PO"WER STATION UNIT.1 CYE:LE 2. STARTUP ST.ARTUP PHYSICS TESTS RESULTS Ah"D EVALUATION SHEET

'JUL 3 1 1980 FINAi RJ:"~111 T~

Test

Description:

Critical Boron Concentration - B f)ank In Procedure NUI:J.ber / Section: PT28.ll/App. C Sequence Step Number: /Z Bank Positions (steps)

RCS Temperature (°F): 547 SDA: 228 SDB: 228 CA: 228 Power Level (i~ F.P.): 0 CB : 0 cc : 228 CD: 228 Other (specify):

Below Nuclear Heating Bank Positions (steps)

RCS Ten::per2.t:ure (OF) : 5"¥-S. CJ Power Level (%. F.P.* ) :O SDA: 22.~

SDB:22.~

CA: c.e.8 Other (specify):

CB:0 CC: c:.2.i CD: 2.2.8 Bel ow fJ., cJ e.a.A""

Hea.tihj Date/Time Test

_8/t(p/80 Perfonied:

0'/--17 Measured Parameter (description)

(CB)B; Critical Boron Concentration - B Bank In Heasured Value (C"Q)M =

., B

/2?0 ppm Design Value (Actu.21 Conditions)

'"'B

=

1301 + c.3 pp'<<)

Design Value 1258+[(CB)~0-1394]

[10+122.s/Jo.c !]

(D~sign Conditions)

CB

=

+/-

P?T'i B

Reference I

VEP-FRD-NFE 107 FSAR/Tech Spec

a.

X CB CB 2 15,115 pcrc Reference FSAR Section 14.2.5 Design Tolerance is met

~-YES 0 HO Acceptance Criteria is met :R YES-0 NO a.cB = -8.6 pc~/pprn for prelimir.ury ~nalysis.

I o<.c.B = -CJ.II ptM!p fYY\\ ttir tino...l 0-,V\\ a....1 y :s; 5.

Cci:.pleteo Evaluated By:

I A.10

*::; u RRY POWtR ::;TATION UNIT :L CYCLE -' !:iTAKTUr'

.I Ir efercnce onditions

<l:~gn)

I ID

'Test

cncii ti.C':!S rtutl)

I Irv I

I I

I lvr O::ll!!e!l.tS.

I I

STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET t" 11\\. I /\\ I n r-rq II T 0 JUL' 3 1 1980 j Ii '111 -u_

I \\ L v U l.. I v Test

Description:

HZP Boron Worth Coefficient*

Procedure Number/ Section:

NA Bank Positions (steps)

SDA:

228 SDB: 228 CA: 228 CB :

Moving CC : 228

CD: 228 Bank Positions (steps)

SDA: 22.i CE: Movi"r'!,?J Dat:_e/Ti.me Test:

Performed:

SDB: 2.c.8 CC: 22.8 gj,s-- 16/80 03'1-S- -

0~/ 7 CA: 2.c.8 CD:2a8 Sequence Step Number:

NA RCS Temperature (°F): 547 Po-1er Level (i: F.*P.) : 0 Other (specify):

Below Nuclear Heating RCS Ten:per2.ture (°F): 5'f-7 Po"Wer Level (7. F.? * ) : 0 Other (specify):

Measured Parameter

( description) a.Si, Boron Worth. Coefficient Measured Value ac

=. -.::..* 9.-/ I p~m /ppm B

Design Value I

(Actual Conditions)

Design Value (Design Conditions)

Reference Reference t

ac

= - 8.~o.+

B ac

= -8.60 +/- 0.86 B

VEP-FRD-NFE 107 FSAR Section 14.2.5 Design Tole.ranee is met. : ~,YES O:No

- Acceptap.ce Criteria is met:,E::'rr*s O NO 0.8(c pc.,m I PPM per.:.

p~m I

I Completed Evaluated By: b:M~::\\:<:py....!'\\('Q.1,~

G Reviewed By: C-:J ~'1'..A_;

A,11 NFO En0ine("r

1.

ltII

onditions resign)

III 1

Test.

ditions (Actual)

I...

Te.st I

I I

V ceptance Criteria I

I VI

.o *..!!:!e.nts I

I I

I

,uJ:UI.Y J:'UWJ::K ::iTATlUN UNlT "L.

CYCLE

i1AKlUJ:'

JUL 3 1 1980 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET 111\\1 f\\ 1 r"\\11'"9 II 1("\\

J JA \\lr\\L. !\\C...)U LI v Test

Description:

Isothermal Temperature Coefficient~ ARO Procedure N=bcr / Section! PT28.ll/ App. D

. Sequence Step NUI:J.ber:

Bank Positions (steps)

SDA: 228

. CB :. 228 SDB: 228 cc: 228 CA: 228 CD: 228 RCS Temperature (°F):

Po~er Level (! F.P.):

Other (specify):

Below Nucle~r Beating B

547 0

Bank Positions (steps)

RCS Temperature (°F): S"\\3 - s4 Co Po~e.r Level (k F.P.): o SDA: 22.8.

SDB: Z..28.

CA: 22.8 Other (specify):

CE: 2.28 CC: Z28 CD: Z.c,C/

Date/Time Test 8/IS /eo Perfonne:d.:

o rSS- 0825 Measured Pa:=Emeter (description)

(a

)

Isothermal Te.=iperature Coefficient - ?_~o Trso ARo

}.ie.asured Vtlue Design Value (Act1.:.2.l Conditions)

Design Value (Design Cond:..~ior.s)

Reference FSA?/Tech Spec l

I aT

=

ISO

- 2,50 C!

=

'T'

-3.05

-rso (I

= -3. 69 +/-

T ISO E-;,-fi'J)-11:?E 107 a

TISO

~F

~rF

.3. 0 pcm/"'F Reference TS 3.1, VEP-~NFE 107 Design Tolerance is 1:1et

~

1..!:.S D HO Acceptance Criteria is r;:ie.t: l)l' Y~S0 NO

¥ Uncertainty on C!T

-:;:- 0. 5 pcm/OF (Re ferenc~: r.emorandum froIP

~OD (C

=139~ ppr,)

B C. T. Snow to E. J. Lozito U516N Vl/1..J.1c, {te..Tt)fr<- ~pmow5 dated June 27, 1980)

Ex.~f):)LtrT£D F/2.DM

'Dfn11 1N NF£ Tc--ct+N,u.L

/07

5vfZP-'/ C, Cvc..LE 5

~~/ G,.V. k!!"Fb~,

Evaluated A.12

I.

I D

er2.nce II ditions Ilt esign)

-I III Test:

8,ditions ctual)

I I

IV I

le.st l:::,ults I

I

-I-V

~,e~t2.n~e riteri2.

1 -VI fe.n_ts I

-1 I

l

. SURRY POw"ER ST.A.TION UNIT 1. CYLE ~ ST.ART@

STARI!P.' prtNALTS R~';::u Af,'I) EVALUATION SF.EET

\\L0 LTS JUL 3 1 \\980 Test

Description:

. Isothermal Temperature Coefficient -

B Bank In Procedure Number I Section: PT2.8. li/ App. D Sequence Step Number:

/3 Bank Positio1:2s (steps)

RCS Terr.peratu:re (°F): 547 SDA: 22~

SDB: 228 CA: 228 Power Level ('"

,~ F.P.):O CB : 0 cc : 228 CD: 228 Other (specify):

Below Nuclear Heating Bank Positions (steps)

RCS Te.!I!.p era tur e (OF): 51-(:,

Po1.-1er Level (% F.P.. ): 0 SDA: 22.f SDB: 22.~

cA: ccS' Other (specify):

CB: 2.1 CC: 22;:i CD:22.~

f3e{ow AJ vc...l ear He.a.+/-i~--

Date/Time Test 8f~/8o Perforl!led:

01/,St - OW J Measured Parameter (a.Trs~) B

( des cripticn)

Isothermal Temperature Coefficient -

B Bank In Heasured Value

a.

=

TISO

- S-,., 3? pe,rn /°F (c8 = /303 ppm)

Desig;:: Value aT.

=

(c 6 :J3o3 (ActU2.l Conditions)

ISO 6-.. 0 / :t 3.o pc.,m /op p,orn)

I Design Value (Design Conditions) a

= -6.17 3.0

/or:-

( CB = 1258 p;:,~.)

Trso pcm Re.fe.rence VEP-FRD-NF::: 107 I

..:S.. 0.53pcm,"' t 1

FSAR/Tech Spec a

a

=o.

-a

<3 oPCIP T1100 Trso Toop-

op 1 Tiso Op a

=-1 97pcm Toop OF Reference TS 3.1, VEP-FRD-luE 107 Design Tolerance is met

R-r.'ES D NO Acceptance Criteria is met : g(YES ONO

~,o~

Un cc rte. in ty en a.,,

~ 0.5 p..... P1, r

( Pe fe rer, ce::

rn:~ nor <'"l n :i um from

-~-*

1*:0D

c. T. Sno~...,, to E-J_. w::ito dat~d June 27, 1980)

Evaleated By:

Reviewed By:

A.13

I SURRY POWER STATION UNIT 2 CYCLE 5 STARTUP JUL 3 1 1980 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET 1----,--~.,.............~~~-----

I.

erence II r..

l~itions fflesign)

III Test 1

ditions ctual)

I I

I IV l

<>sr ults I

I V

~=~=:~:

.---~c;.--G.

I I

Test Z, ARO Procedure Number/ Section: PT28.2, OP-57 "Sequence St:ep Number:

/ ()

Bank Positions (steps)

SDA: 228 CE : 228 SDB: 228 cc: 228 Bank Positions (steps)

CA: 228 CD: 228.

RCS Temperature (°F):

Po~er Level (Z F.P.):

Other (specify):

TRef

'\\-0 Must have> 40 thimbles SDB: 1..2lr CC: 1:l..~

CA: :2.. :2.~

CD: "2..1 l:.

RCS Temperature (°F): -.SY1° F

?o;.;er Level (7. F.P.):..... ~ '70 Other (specify):

41-n:..... ble...S Date/Ti!lle Te.::-t Perfonned:

Me.a.sured Parameter (description)

Measured value I)esiE::l ve..'.i..ut::

(Actual-Cond~tions)

Design Value (DeEign Conditions)

Re£erence

FSAR/Tech Spec Refer~ce

~.o 7o -fo,. ~-" ~ 1.02 IO.::i7o fa..- ~s:o.\\-l3 t I~ lo. +o-P.*z -~

+/-.1s'Z-for r.-~.q ilOI for 11 1.!.

9 il.5: !or ii <.9

(? :1. - A.arr,. ?v::.)

WCAP-7905 Rev. 1 None None

~R~ _NUCLEAR ENTHALPY RISE ROT CHANNEL FACTOR l.L/Co2 rN 'l 0 ;,-(1~ 2(1-~))

t.~ --=-

.~

'. \\.-

NONE

.NA TS 3.l2 Design Tole.:::-~ce is me::

D YES 0 HO S,_e Cc=~-:7 &J..:.,"

Acceptance Criteria. is met:: 0 YES D NO Evelt12ted 3y:

Revie;.:ed By :

A.14 FQ, TO~.L EE.AT QUADR.~~T FLu..Z HOT POHER TILT CE...t..NNEI.. :FACTOR RATIO (QPTR.;

_T '~)

[},~

< 4. 36 NA

/.022 !

L-1.0=-

X K (Z) I <

1-1.02 1 i I I

',* 1 -:.P-7Cr-,-:-

I ?*.s *.-.

NA TS 3.12 ~nC o.e~cra~du=.

1 1

from E. J. Lozl~O to

'r. A. Peebl1:::s d.otc~

TS July 15, 1~80.

3.l2 l\\FO Enginee:-

.I I

rence I.1 ttions sign)

-I III Te.st 1:~)

I I-IV I

Jest

..llts I

I

*v leptance

iteria I

VI,~:s I

I I

I SURRY POWER STATION UNIT 2 CYCLE 5 STARTUP STARTIJP PHYSICS TEST RESULTS.AND EVALUATION SHEET JUL 3 1 1980 C'll\\l/\\1 nc01 11 TC.

J u ~' \\L.

1\\1-VUI-i--0 Test

Description:

M/D nux Map -

BZP, B-Bank In Procedure Number / Section: PT28.2, OP-57 Sequence Step Number: 14 Bank Positions (steps)

RCS Temperature (°F): TR; SDA: 228 SD:B: 228 CA.: 228 Pov er Levtl (% F. P.) : '\\.Q,e CE :*o cc. 228 CD: 2)8 Other (specify):

Must have> 40 thimbles

Bank Positions (steps)

RCS Temperature (°F): --SL/7 °F Po-..er Level (% F.P.):-.0°70 SDA: 1. 1 '2 SDB: 1.2i CA.: '2.. '2. $?'

Other (specify):

~: ~'-1/3~

CC: ?..2.~

CD: '1..°22 S0 T~.~ble..S Date/Time Test iln.l~o 0,13 Pe::-for.::cd:

Measured Para:!leter MAX. REL. ASSY

Eh, NUCLEAR

~Q* TOTAL HEAT QUA.DP..Al\\T (description)

Pw"?... ~-DTu-"T.

EN'l1ll,.J.PY RISE HOT FLUX ROT POi,ER TILT

(~

CHANNEL FACTOR CF..PJilE.L FACTOR RATIO (O?TR)

Measured Value t' f'or r..* a o.q </

l"l..Sbr Bi-9: 0.$2.

1. ioeo J... ~o '7

/.00(:,2_

. Design V2lue I +/-io"%. r. P> ~ I I

Tor ;-.

I / Jo~

(Actual Conditions) iJSh hr-P.*L.~

NA Nt Design Value

~C:: !.,,r l' 1 !_

9 (Design Co::::idi ti.ens)

~: fer l'i <.9 NA

.!.. 0..::

Cl' i -

Aa:rry. Pvr.)

Re:fe.re!:lce WCJ...?-7905 I

~*7t:J..:P-79 :, :

Re.v. l NONE

!;ON~

Re\\-. -

I FSAR/Tech Spe C None.

NA"

.NA NA I

Reference*.

I I

None

TS 3.12 TS 3.12 TS 3.11 Design Tolera.nce :is.::i.et

~-ITS0 HO A_ccepta.nce Criteria is me=: IB.l YESO NO Evaluated By:

~

... ti.. & 2,c::'Y-yt~

-'o... * ~:::...:.._~...c::::c=..J~-""""=-_,__-

Revi eimd By:

(. :f ~..;--.,J

_.::_~ ___

=-.::.;:::..._~--,---

A.15 NF O Engineer

-I I 1 erence II

~est

lditions esign)

I III Test:

Onditions lctual)

I IIV I

lest

~

ults I

I I V

,cceptance lriter:la

-.VI i,e.n_ts I

I I

SURRY POWER STATION UNIT 2 CYCLE 5 STARTUP BO STARTUP J=1Tf\\{s TEST RESULTS AND EVALUATION SHEET JUL 3 l 19 Al RJ:"~111 TC

- ---&...1'\\,J Test

Description:

M/D Flwc Map -

At Po-wer, NI Calib.

Procedure Number/ Section: PT28.1, OP-57 Sequence 5-tep Number: 44

Bank Positions (steps)

RCS Temperature (OF):

TRef SDA: 228 SDB: 228 CA: 228

'Po'wer Level o: :F. l" * ) :...,40 CB : 228 cc :* 228 CD:

Above Otbe.r (specify):

Insertion Limits Must have > 40 thimbles Bank :Positions (steps)

RCS Temperature.(OF): ~ef+/-l*

Po-wer Level (7. :F.:P.): 'f-3 SDA:228 SDB: 228 CA: 22.~

Other (specify):

CE:2.28 cc:2.a8 CD: /70 s-o t:h irnb\\e.s Dat.e/T:b.e Tesr:

2./20/80.

PerforI!led:

0'121- /2.c..l Measured Pa:.:-2'.!!)eter MAX. R.EL. ASSY ~. NUCLEAR FQ, TOL.U. 1IT.A.T I.QUADRA.1\\T (description)

,~~Dux.

ENTilAI.PY RISE HOT FLUX BOT POWER TILT CHA..1-"'NEL F.ACTOR CF.J._""lliEI. FACTOR RATIO(OPTI:

Measured value 6 /1 o/o J ~-~ ~1. oz

/

0 l/-~

lo'1?S

/,0/01 5".1?o I fa-!: ::a,'H Design Value 1 +/- to% for f; -;,,e; I

I (Act't!.21 Cond~!:ic~s)

NA.

NA

+/-1s-'fo +t,r-P; ~. ~

~loo?..

Design Value

,ic: for P1 ~.9 NA NA (De.sign Condit:ions)

il.5% for Pi <

9

< l. 02 0'1 *.ury. h-r.)

P" e. f e:;:e:n c::.

WCAP-7905 NOKE NON.t.

WCJ.2*- 79 C*.:

Rev. 1

!<Ev. '

.FN

< 1.55(1+.2(1-p))

F~(Z)*.::_ 4.36 ~ K(Z)

FSAR/Tech Spec None NA ti.H -

IS J.12 and ~t~ocandc::::i Reference None TS 3.12 froQ E. J. Lozito co

!. A. Peebles dateC TS 3.12 July 15. l9SG.

Design Tole~2:1ce is met

. : )3:.1::s D HO Acceptance Criteria is me.:: fil:°YES 0 NO Evaluated By:

A.16

--*----- -.:,uiU\\.i -.[Ut',.C..1'1.

.:lJ..t'..J..LU11 U!\\.LJ.- L 1.,i1.,.1..,.c.

..J

.:JJ.~.I.U.C I

~III

Onditions sign)

III J

Test tlitions (Actual)

I -

I tv I

Test I

I I

v ept:ance Criteria I

I i

I:

STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET JUL *3 1 1980 t:"11\\ I/\\ I Mir-1'1 I! -:-r-.

_. _u 'JJ-\\1.. f\\I.:.0 UL j ~

'Iest

Description:

M/D Flux Map -

At Power, IU Calib.

Procedure Number / Section: PT28.2, OP-57 Sequence Step Number:

4S Bank Positions (steps)

SD.A.: 228 CB : 228 SDB: 228 cc: 228 CA: 228 CD: Above

. In~,ertioI: Limits SDA: 2~~

CB: 226 Bank Positions (steps)

SDB: 2. '2.8

CC: 2'2.8 Dat.e/Time Te£~ (f8/2. I /f3:1:y Performed:

00 '3:. I_ 0 e..i~

CA: '2 28 CD: 183.//6 'i RCS Temperature (°F):

TRef.

"Po..ier Level (.! F.l'.) : "'.50 Other (specify):

Must have> 40 thimbles RCS Temperature (°F):i,~~

l'o'Wer-Level (% :F.P.): SO.

Other (specify):

t l Measured Paxa:oet.er (description)

~

NUCLEAR MAX. REL.. ASSY

-E, F6, TOT.AL EElJ QUADRANT Measured Value

'Desig-:i v ci. ue (Actu.2.l Conditions)

Design Value (Design Conditions)

Reference FSAR/Tech Spec Reference

!'WR. i Diil'.

ENT!~ UPY RISE EDT

(~~~)

CE..ANNEL FACTOR 1

-1,.S."'?S:Or P::.\\,10

+7,S )"ct" fl, o,t..tt; (l'i

Any. Pv:.)

WCJ..?-7905 Rev. l None None NA I

i:; I r~H ~ 1.ssc1+.2(1-?))

TS 3.12

FLUX ROT PO~*.ER TIL'I CH..A..NNEL FACTOR RATIO(QPT?-.

1,909

\\.oo<;l~

~ 1.02.

NA.

< 1.02 I

'*'C"P-7-9i*=

.l""-

?~-"*.

=-

I

?

I FT(Z) < __ le, X X.(Z)l 1

Q p

I TS 3.!2 and oe=:=oranduc fro~~- J. Lozi[o to T. A. Peebles carec July 15, 1SBO.

NA TS 3.l2 Design Tolerz..nce is met

Il:g ::ES D HO Accept:a.nce Criteria is ::::iet:: ~YE.SD NO r*..

.. r-By: b- 'M V,0.. 9-,. ~l'.:h..,~.

By:-:-r /(,+Z-u. c.

Evaluated Revie..;ed NFO Engineer A.17

.I 1

e rence II liticns

(

sign)

I III Te.st

ili"tions

(

tual)

I I

IV I

I Jr ts I

I Iv cceptznc.e fteria VI T*t.s I

SURRY POWER STATION UNIT 2 CYCLE 5 STARTUP STARTUP "PHYSICS TEST RESULTS AND EVALUATION SHEET

[""1\\\\.11\\ 1 DC~I 11 T~

i jj \\,I/.a...

I\\L-'-"--'

Test

Description:

M/D Flux Map - At Po.;,er, NI Calib.

JUL 3 1 1980 Procedure NUI:lber I Section.: 1'T28.2, OP-57 Sequence Step NUI:Jber:

4-fo

Bank Positions (steps)

(OF):

T P.CS Te.Dperature

. Ref SDA: 228 SDB: 228 CA: 228 Po,.,,er Level (! F.1'.): '\\,60 CE :2is cc : 228 CD:

Above Other (specify):

Insertion Limits Hust have > 4*0 thimbles Eank. l'ositioI!.S (steps)

RCS T e!:!p era t: ur e. (Of): T\\"')- +/-l (7. F.:P.): 61 Po-wer Level SD.A:<-'<-2>

SDB: 'l. "2. 2, CA.: 2._2.8.

Other (spec.ify):

q.: 1.2..~

CC: 'L'2..3 CD: 190 Y9 t~~""~\\es Date/Ti:me Test og/2,i IB6 J:'erfor.ned:

'2.\\01

c. ?:,07 Me.2Sured ::?ar2!l!eter MbX. REL. ASSY NUCLEAR

. ?Q. TOTAL EEA.T I QUADR.Al~T (description) 1i;~ DI=:.

~'TB...A...Ll'Y RISE BOT FLUX ROT ro:rrn TIL':

CEAN"NEL "FACTOR CE.l~-Nil. "FACTOR I RATIO (QPTR;

+.S,o S-e.(

~ =. l,oo

He.as-cred valu.~

1,Y lb l,65Lf

\\, 00~ L/

H,,l ~~ P-:.. O,l;'i Desig::i vc..l ue l

s:o t \\0%

t> ~ o.9 l (Actuzl Conditions) t 15 °/c, <;o"(" ?.c.o.~

N'

.tl.

NJ.

L. l, 0*'2..

Design Value tlO! :fer ?' 1.!.

9 I~

(Des:i.g::i Ccnd..:i.tiou.s) il..5: for :P 1 <.9 NA NA l.O:

(Pi - ~*Y* :Fv..)*

I l

wLl.P-7905.

Refe.:r-ence

\\~?Ci~-7?*:.:.

Rev. 1 NOl-t"i:

NO~i.:2 F-.e *.-.

1 FSAR,/Tech Spec None

~ F:H ~ l. 5 5 ( 1 +

2 (l-p) )

F~(Z) < 2.18. "!Z)

NA p

X..,

r I

TS 3.12 anc c,c::ioca~e= I Refer~c.e

.from ::. J. Lozi:o to None TS 3.l2

!. A. Peebl~s date~

7S 3.1:

July 15, 1960.

Desi~ Tole.r2=1.ce :i..s :;:::ie,:

=El ~so NO Accept:2.nce Cri.t:eria is met:: W YES0 NO I

! I Completed* B)d J. (1 )./1,L"'rr~

I Ies;/ Lng*v' eer Evaluated By:

I.

Revie,;..*ed By:

A.18 NFO J::ngineer-

.I I

P,ef ere.nee II Test lnditio-:is Design)

I III Test

~Dditions I.Actual)

I I IV I

'Ies~

fuits I

I

I I V Acceptance

ICriter~a VI

0 c:::! en ts.

I I

Co~pleteci SURRY PO"l-.7ER STATION UNIT 2 CYCLE 5 STARTUP STARTUP PHYSICS TEST RESULTS P.ND EVALUATION SHEET

,,.... i.,,- ---*.. ---

Test*Description: M/r V1~l\\kp _KJ:i~-JJ~1n! ~ Calih.

JUL 3 1.\\SBO Procedure 'NUI:1ber I Section: PT28.2, OP-57 Sequence Step Number: 47 Bank Po-si tions (steps)

(OF):

TR ~-

RCS Temperature e...

SDA: 228 SDB: 228 CA: 228 Po-wer Level (: F.:P.): 1\\,70 CB : 228 cc. 228 CD: _* Above.

Other (specify):

Insertion Limits Must have~ 40 thimbles

Bank Positions (steps)

RCS Te11:perature (OF): 'Ref :t I l'o-wer Level (7. F.P.): 7/

SD.A..: 2.22 SDB: 2.28 CA: 22.8 Other (specify):

~:B: 228 CC: ?28 CD: /~S "LJ-6 t1) *1Mb/~

Date/Time 'Iest 8/~/ao

Performed:

JS38- /757 Me.asured "Par2::ieter

~t....""'{. REL. ASSY

~ NUCLEAR F~? TOT.AI. EAT QUADP-6.NT (description)

PWR. ~ DIIT.

ENTHALPY RISE HOT FLUX ROT PO:l:C:R TILT e1; GaA.. NNEL FACTOR

~"lliEL FACTOR RATIO(QPTI, S.J 'Jo J P6_, = 1.00 r

Measured Value

/o'/-/0

,

8'fc.

I.005" 2..

,., % J PB-6" =.lf-lJ-1'esi~ value I+. q, A

(.A.c'tt*:,., Conc:i-.:ions)

-10 0

) i ~ * '1 NA

!.\\A L... 1.0.::

+/- 15"%) P,*~. "f Desig:i Value ilC: for ? 1 !...9 (Desi.g:1 Conditions)

.U: !c-:: l'1 <.9 F'

NA

< l. o::

=-

Cl' 1

J.uy. ?-.-:.)

ltef e.:-e=ice WCAP-7905 It,~~:..~-- 7-=- -,=

J' Rev. l NOkt.

NOIE I -:.o,,

f ;,,.,. ~ 1.5.5( 1+. 2(1-p)).

I FSAR/Tech Spec

. None FT(Z) ; 1..:.J& x K(Z)

NA Q.

p TS J.!2 and ~enora~d""'I Refere..""1ce frot:.i :... J. Lo:::.to to None TS 3.12

!. A. Peebles catec TS 3.12 July 15, 1980.

Desi~ Toler2.nce is met

:2(YES D 1W Acceptc:..!lce Cri-z:eria is met::.S:,YES 0 NO Evaluated By:

A.19

I.

I

'Refe-rence II 1'est lnditious Design)

I III Te.st Conditions

'Actual)

I I

IV I

Test:

fuits I

I.

V cceptance Criteria I..

I VI Co=ents I

I I

I Co:::Dletec SURRY POWER STATION UNIT 2 CYCLE 5 STARTUP JUL 3 1 1980 STARTUP PCTif)\\ psT RESULTS AND EVALUATION SHEET f'"\\r-nl II --r,,

Test 1 u '.inL J \\C~UL i ~

Descript:ion: H/D Flux Map -

At Power, NI Calib.

Procedure NUI!lbe:r I Section: PT28.2, OP-57 Sequence Step N=ber: 48 Bank J?osi tions (steps)

RCS Tempe-rature (°F): TP.ef SDA:228 SDB: 228 CA: 228 Po...,e:::: Level (Z F.P.):""90 CB : 228 cc : 228 CD:

Above Other (specify):

Insertion Limits Must have > 40 thimbles I

Bank Positions (steps)

RCS Temperature (OF): °TieJt /

Po...,er Level (i: F.P~): ~~

SDA: 2.~'8 SDB: 2.c.8 C..A..: 228 Other (specify):

CE: 2. 2.8 CC: 228 CD:/ CjO 4-J) i:h;mbleo Date/Tfu.e Test 1 /1/ 8.o Performe~:

/OS'f -

/332..

Meas.urerl Pa= aE e. t er MAX. REL. ASSY F;!

1'.uC'"LEA.R F'T', TOTAL EEA.7 Q'JJ..DRA,\\"'..

lill, (description)

(r1;f1 DIIT *.

Q.FLUX liOT EIT'.d.A.LPY RISE E.OT

?OlJER TIL':"

CR...;Nl.tL FACTOR G1-~\\'"NEL FACTO:i:{. R!,TIO (Q?TI;:

Measured Value L/-. / ?o J P6_,:.18 I 1>318

/ o 7CJO

/. 0075° 5,CJ ?o 1 PA-., =.1-5 Iies::..g:r V<UUE:

I..:..,on. p

c; I

(Act::.2..2. Conditions) 10 ) i ~

NJ.

l.",.

+/-. ISf.:, p..:::_

C J.1....-..

LJ,02.

J I

, I Design Value

.l.O! fo:: "11 !..5 (De.sig::i Conditions)

..:....:s:: !c= ]4 <

9

< 1. 02 N..!,.

l\\.n

(?i

JJ.a;. P-..-:.)

Re:ferEnce WCJ...P-7 9 05 I

I I

1**--:..-=o-7ar,:

Rev. 1 NO}~

NG:~

--=,*.

I i

i FSAR,/Tech Spec None f~H j_ 1.55(1+.2(1-P))

FT(Z)' 2.18

K(Z) I NA Q

p I

I",.n,oO ceamoO,, i Refere..:ice frn:: E. J. !..c:i:c co I None TS 3.12

~-

A. Peehles d::i:cc!

7S

_j. ---

July 15, 1g130

Desi£!:. Toler2.nce is net

=A~.:.S 0 EO Accept:2J.Jce Criteria is ~et:: 'A YES D NO Evaluated By:

Revie..... ed By: _"'_er_.!"'~* K....:: ~/~---=*

~rn E:1ginee:-

A.20

I I t _I ence

.st f,1tions ign)

I l

I I

I

I

~

ts Iv

ceptance lite.ria VI T*ts

1 I

SURRY POWER STATION UNIT 2 CYCLE 5 STARTUP STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET JUL 3 1 1980 i <.)

7est

Description:

Flm:: Map -

HFP, ARO, Eq. Xe. Map Procedure Number/ Section: PT28.2, OP-57 Sequence Step Number:

4,q Eank Positions (steps)

CA: 228 SDA:223 C:B : 228 SDB: 228 cc: 228 CD:

Above Inserti'on Limits RCS Temperature (°F) :* TRef Fove.r Level (! F.P. )-: 100 Other (specify): Equil. Xenon Must have> 40 thimbles Ea.nk Positions (steps)

SDA: 2.'l.l/

CB:"').. 2~

Date/Time Ter.r

Performed:

CA.: '2..'2. ~

CD: 2.JS MAX. REL._ ASSY RCS Te.Eperature (°F):T*.fF+/-I

'Po'w'er Level (% 'F.i?.): /oO Other* (specify):

Y q T~,*""h/e.5 Jt:1°ci3:

NUCLEA... -q, F'.J;, TOTAL EE.AT QU,'.DR..',!'iT Me2SUI"ed Pa:.:2!!e.ter (description) 111;/) DIIT.

ENTrl.£...1.PY RISE HOT I.('. FLUX B.OT PO:*:£?, TIL7 Measured Value i) esign

~ 2....:.. U:

(AC 't 1:.2.l Cm:1di t:i.ons)

Design value (Desig-;::i Couc.i t:ions)

S.3%1 P5 _" ;, -~~

C~7::i 1 PQ.-s L

. '-)i.{

!_ /Cl /~

't"='r i-I

. ~ r r,

15 !, --+er ~ L. 9

-t" -

~o: !or :r 1 ~.9

~: for r 1 <

9 (1'1

J..asy. ?=.)

C:BANNEL FACTOR CRJ..NNEL FACTOR! RATIO(O?TR'.

J. 3~7 1.7/(=,

l1.00S.3 I

j NA K!

1~

~.

/. :1-_

NA NA I~ l.02 I I !

WCA?-7905 I ;*, c;.::- - 7 s c =

Refe-r-e::ice.

NONE NOl:I.

Rev. l I ! :*= *:. -

1.55(1*.2(1-P)) ~ F~(Z)

FSAR/Tech None Jl

,: 2.18 X K(Z)

NA Spec

C AH ~

p TS J.12.and :oe:::ura:'\\cc:::: I Re.£ ere.nee f:-oe: E. J. Lo=l:-.o to Nor1e TS 3.12

. A. Pe~blcs dateC

..,..~

J'"ly 15, 19SO.

.:; *.l.-

Design Tole:-2nce is me.t

i8i -:=.S 0 NO Accept2..:J.ce Criteria is r:et: 19 YES0 NO Evaluated By:

Reviewed By:

A.21 NFO Engine£"r

I

[

e:.nce:

II

~,ticms Test

.Slifi"!.Y rm:rn. SL\\TIO:~ u~a~: ;2_ CYCL:S ~ ~';:]J,.:rur STJ>Jt~fU:f> l'HYSICS n.:~;rs RES1JL1'S Alm EVALU/1TlON SHEET FINA[ RESULTS.

De scrip tJ.on: RCS Flow Measurement JUL 3 1 1980 Procedure !*lu,-:,ber / *section: ST-52 Se::qucnce Ste.p Number:

-5'0 Bc:.nl: Position~ (s tcps)

.. RCS Ten:pcra ture (dF): TRef SDA:228 SDB:228 CA:228 Pm-ier Level (7. F.P.):100 Other Jesign) en :228 cc :228 CD:Above (specify):

Insertion Limits tLfo~ ih:,e3..ee! Heet:j: *. h ::n\\L 9/18/80 tr Bank Positions (steps)

RCS Te!!'.peraturc (°F) :TR.eF":!:. I Test Power Level (% F.P.): 100

iltions SD.P.: '2.:2..8 SDB: 1.""2 <a CA: 1. "'l. ~

Other (specify):

~-

ual)

CE: 2.1<a CC: 11~

CD: '1..IS 9 I 11. I So Date/Time Test Pcrf~rn.ed:

.O'it/0 -

/OL/0 I

Hecsu!."ed Parair.eter (description)

FTOTAL

' Total RCS Flow Rate IV RCS I

2-Icc.si..rred V2.lue FTOTAL = 193) 5yq 5f rr-.

RCS It I.:e:sigu V2.lu~

I

-**i 't-Co (Actual Ccnditicns)

Not Applicable I

Design Vah.1e

.I (Design Con:ii tic=.s)

Not Applicable L

l I~e.ferenc.:e Not Applicable I l

-n.s V

FTOTAL /1. 02.:'... 265 '500 ltan~e FSAR/Tech Spec gpm t2r1a RCS r~AR ~ection 4.1.j; Let~er :re= C. H. ~t~.L 1ngs l*epco)

P'"e.ft2rence to H. R. Denton (!;;:'.C) cated ~lay 31, 1979 (S.,,::-ial,;o. 383);

Letter from C. ~*

Stallings (Vepco) to E.. G. Case: (1";:C)

I dated Nove~ber 16. 19i7 (SC?,i"1 Nn. 516)

I Desif.11 Tc*lcr.:c.r,ce is wet

l8i YES D ;;o

~Cs I Acccet_~_.r:_:~_~_~_c_¥_~_i_t_e __ r_i_2~i-s~~-*~_t_=_~~-1-*~_s_o~_~_;c_J~~~~~~~~~~~~~---~~~~~~~~~

I I

I-I

~C'c:p11.'t('.(;* J;yd, ~

I _

1~~t

-~-

l:\\.*.:~ 1. :..:;4 t ~J A,22 I****

~J:

I~\\" :

ML18139A785

Contents

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Navigation menu

ML18139A785

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Navigation menu

Search