ML20062L227

Cycle 1 Startup Physics Test Rept

ML20062L227
Person / Time
Site:	North Anna
Issue date:	12/31/1980
From:	Kunsitis T, Lozito E, Rotella T VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20062L226	List: ML20062L221 ML20062L227
References
VEP-FRD-39, NUDOCS 8101220370
Download: ML20062L227 (125)

Text

. -

VEP-FRD-39 9

NORTH ANNA UNIT 2, CYCI.E 1 STARTi*p PHYSICS TEST Rr* ORT BY T. S. Rotella T. J. Kunsitis Reviewed By: Approved By:

C.IEw C. T. Snow, Nuclear Fuel Engineer r J Lo:ite irector Nuclear Fuel Operation Group ear Fuel Jperation Group Nuclear Fuel Operation Group Fuel Resources Department Virginia Electric and Power Company Richmond, Virginia Decenter, 1980 j'

CLASSIFICATION / DISCLAIMER The data, techniques, information, and conclusions in this report have been prepared solely for use by the Virginia Electric and Power Ccmpany (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 4

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 dee=ed to incorporate the discicimers of liability and disclaimers of warranties provided herein. In no event shall the Company be liable, under any legal theory whatsoever (whether contract, tort, warranty, or strict or absolute liability), for any property damage, nental 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 this report or the data, techniques, information, or conclusions in it.

r i

ACKNOWLEDGEMEh7S The authors would like to acknowledge the time and effort put forth by the North Anna Power Station personnel, and the Babcock and WJcox and Westinghouse Nuclear Operations staffs for their assistance in the successful completion of the tests documented in this report.

The authors would like to express gratitude to Mr. C. T. Snow, 1

and Dr. E. J. Lozito for their aid and guidance in preparing this report.

l We would like to thank Ms. P. L. Cooper for her assistance in the typing '

of this report.

l 11

TABLE OF COhTENTS SECTION TITLE PAGE NO.

Classification / Disclaimer . . . ... ... . .... . i Acknowledgements . . . . . . . . . . . . . . . . . . 11 Lis t o f Tables . . . . . . . . . . . . . . . . . . . . . iv List of Figures . . . . . . . . . . . . . . . . . . . . v Preface . . . . . . . . . . . . . . . . . . . . . . . . viii 2.2 Ince e Movable Detector System . .. . .. . . . . . 2.2-1 3.0 Zero Power Physics Testing .. .... . . . .. . . . 3.0-1 3.1 Initial Criticality . . . . . . . . . . . . . . . . . 3.1-1 t 3.2 Control Rod Bank Worth Measurements and Shutdown Margin . . . . . . . . . . . . . . . . . . . 3.2-1 3.3 Isothermal Temperature Coefficient ... . . . . . . 3.3-1 3.4 Boron Endpoint and Boron Worth Measurements . . . . . 3.4-1 3.5 Power Distribution Measurements At HZP-ARO and D-Bank In . . . . . . . . . . . . . . . . . . . . 3.5-1 4.1 At-Power Physics Testing .. . . ... .. ..... . 4.1- 1 4.1.1 Power Distribution Measurements At Power . . . . . . 4.1.1-1 4.1.2 RCCA Static Rod Drop Test . . . . ... . . ... . . 4.1.2-1 l

4.4.1 Nuclear and Temperature Instrumentation Calibration And Ther=al Power Measurement . . ... . 4.4.1-1 4.4.1.1 Nuclear Instrunentation Align =ent . ... . . .. . . 4.4.1-2 <

l 4.4.3 Incore-Excore Detector Calibration . . .. . . . . . 4.4.3-1 l

4.4.5 Process Computer . . . . . . . . . . . . . . . . . . 4.4.5-1 5.0 References . . . . . . . . . . . . . . . . . . . . . 5.0-1 Appendix B: Initial Startup Physics Test Results and Evaluation Sheets .. . .. . . . . . . . . . . B- 1 Appendix C: Moderator Temperature Coefficient Rod Withdrawal Limits .. . ..... . . .... . C-1 iii

LIST OF TABLES TABLE TITLE PAGE NO 3.2-1 Control Rod Bank Worth Summary . . . . . . . . . . 3.2-3 3.2-2 Rod Swap Test Results Summary . .. . . . . . . . 3.2-4 3.2-3 Shutdown Margin Calculation . . . . . . . . .. . 3.2-5 3.3-1 Isothermal Temperature coefficient Summary . . . . 3.3-3 3.4-1 Boron Endpoints Su==ary . . . . . . . . . . . . . . 3.4-3 3.4-2 Boron Worth Coefficient Summary . . . . . . .. . 3.4-4 3.5-1 Suzanary of Incore Flux Maps At HZP - D Bank In and ARO . .. . . . . . . . . . . . . . . . . . . . 3.5-3 4.1.1-1 Sununary of Incore Flux Maps Taken During Power Ascension . . . . . . . . . . . . . . . . . . . . 4.1.1-2 4.1.1-2 Comparison of Measured Power Distribution Parameters With Their Technical Specifications Limit . . . . 4.1.1-3 4.1.2-1A Summary of Dropped Rod Integral Worth . . . . . . 4.1.2-4 4.1.2-1B Summary of Dropped Rod Flux Map Results . . . . . 4,1.2-4 4.1.2-2 Summary of Excore Detector Response During Dropped Rod Test . . . . . . . . . . . . . . . . . . . . 4.1.2-5 4.4.1-1 Statepoint Data Summary .. . . . . . . . . . . . 4.4.1-3 4.4.1-2 Nuclear Instrumentation Overlap Data . . . . . . . 4.4.1-5 4.4.3-1 Power Range Detector Currents (Expected Versus Measured) for Quarter-Core Flux Maps 16,20, and 21 4.4.3-4 C-1 Calculation of HZP Moderator Temperature Coefficient Limit Curve .. . . . . . . . . . . . C-3 C-2 Moderator Temperature Coefficient ARO Critical Boron Concentrations vs. Percent Power for ac/LTgon = 0 . . . . . ... . . . . . . C-4 iv I

LIST OF FIGURES

, FIGURE TITLE PAGE NO 2.2-1 Incore Instrumentation Locations . . . . . . . . . . . . 2.2-3 3.0-1 Core Loading Map . . . . . . . ... . . . . . . . . . . . 3.0-3 3.0-2 Burnable Poison and Scurce Asser.bly Locations . . . . . 3.0-4 3.0-3 Control Rod Locations . . . . . . . . . . . . . . . . . 3.0-5 2 3.1-1 Inverse Count Rate Ratio vs. Control Rod Position . . . 3.1-3 3.1-2 Inverse Count Rate Ratio vs. Dilution Time . . . . . . . 3.1-4 3.1-3 Inverse Count Rate Ratio vs. RCS Boron Concentration . . 3.1-$

3.1-4 Inverse Count Rate Ratio vs. Integrator Reading . . . . 3.1-6 3.2-1 Bank D Integral Rod Worth - HZP . . . . . . . . . . . . 3.2-6 3.2-2 Bank D Differential Rod Worth - HZP . . . . . . . . . . 3.2-7 3.2-3 Bank C Integral Rod Worth - HZP . . . . . . . . . . . . 3.2-8 3.2-4 Bank C Differential Rod Worth - HZP . . . . . . . . . . 3.2-9 3.2-5 Bank B Integral Rod Worth - HZP . . . . . . . . . . . . 3.2-10 3.2-6 Bank B Bifferential Rod Worth - HZF . . . . . . . . . . 3.2-11 3.2-7 Bank A Integral Rod Worth - HZP . . . . . . . . . . . . 3.2-12 3.2-8 Bank .i Differential Rod Worth - HZP . . . . . . . . . . 3.2-13 3.2-9 Shutdown Bank B Integral Rod Worth - HZP . . . . . . . . 3.2-14 3.2-10 Shutdown Bank B Differential Rod Worth - HZP . . . . . . 3.2-15 t 3.2-11 Bank D Integral Rod Worth Comparisou with Prediction -

HZP . .. . . . . . . . . . . . . . . . . . . . . . . . . 3.2-16 3.2-12 Bank D Differential Rod Worth Comparison With Prediction - HZP . .. .. . . . . . . . . . . . . . . . 3.2-17 3.2-13 Bank C Integral Rod Worth Comparison With Pradiction -

HZP .............. . .. . . . . . . . . . . . . . . . . 3.2-18 b

V i i i l

t _ .___ _ _ - _ _ _ _

f LIST OF FIGURIS (CONT'D)

FIGURE TITLE PACE NO.  !

3.2-14 Bank C Differential Rod Worth Comparison With ,

Prediction - H2P . .. ... . ... . .. . . .. .. . 3.2-19 3.2-15 Bank B Integral Rod Worth Comparison With Prediction -

EZP .... .. . .... . . .. . . . . . . . . . . . 3.2-20 1 L

3.2-16 Bank B Differential Rod Worth Comparison With i Prediction - EZP . .. .. . . .. . . .. . .. . .. . 3.2-21 3.2-17 Bank A Integral Rod Worth Comparison With Prediction - ,

t EZP .. ... . .. . .. . . . . .. .. . . .. .. . 3.2-22 i 3.2-18 Bank A Differential Rod Worth Comparison With Prediction - HZP . ... . .. . . .. . . . . . . . . 3.2-23 >

t 3.3-1 Isothermal Temperature Coefficient EZP, D-Bank In . . . 3.3-4 .a 3.4-1 Boron Worth Coefficient . . .. . . . . . . . . . . . . 3.4-5 3.5-1 Assembl> vise Power Distribution - HZP, D-Bank In . . . . 3.5-4 I

3.5-2 Assemblywise Power Distribution - B"P, ARO . . . . . . . 3.5-5 4.1.1-1 Assemblyvise Power Distribution - Preliminary I/E {

Calibration .. .. .. .. . . .. . . . . . . . . .. 4.1.1-4 r 4.1.1-2 Assemblyvise Power Distribution - Preliminary I/E i Calibration - APDM Map . . . . . .. . . . . .. . . . . 4.1.1-5 l t

t 4.1.1-3 Assemblywise Power Distribution - Preliminary I/E i Calibration - APDM Map - 50% Base Map . . . . . . . . . 4.1.1-6 f

4.1.1-4 Assemblyvise Power Distribution - APDM Map . . . . . . . 4.1.1-7 f

4.1.1-5 Assemblywise Power Distribution - I/E Calibration-APDM

, . Map .. . . .. . . . .. . . . . . . . . . .. . . . . 4.1.1-8 4.1.1-6 Assemblyvise Power Distribution - I/E Calibration-APDM  !

Map . . . . ... . . . . . . .. .. . . . . . . . . . 4.1.1-9 4.1.1-7 Assemblyvise Power Distribution - I/E Calibration-APDM '

Map ... . . . . .. .. . . . . . . . . . . . . . . . 4.1.1-10 t

4.1.1-8 Assemblywise Power Distribution - I/E Calibration Map .. ... . . . .. . . . . .. . . . . .. . . . . 4.1.1-11

'4.1.1-9 Assemblyvise Power Distribution - 90% Map . . . . . . . 4.1.1-12 vi

i 5

LIST OF FIGURES (CONT'D)

FIGURE TITLE PAGE No.

4.1.1-10 Assemblywise Power Distribution - 1007. APDM Map . . 4.1.1-13 4.1.1-11 Assemblywise Power Distribution - 1007.

Equilibrium Map . . . . . . . . . . . . . . . . . . 4.1.1-14 0

4.1.2-1 Assemblywise Power Distribution - Base Case Rod Drop Map . . . ... . . . . . . . . . . . . . . . 4.1.2-6 4.1.2-2 Assemblywise Power Distribution - Static Rod I Drop (D-10) Map . . . . . . . . . . . . . . . . . . 4.1.2-7 4.1.2-3 Thermocouple Map - Base Case . . . . . . . . . . . 4.1.2-8 4.1.2-4 Thermocouple Map - RCCA D-10 In . . . . . . . . . 4.1.2-9 4.1.2-5 Thimble E-11 Axial Power Distribution - RCCA D-10 at 228 steps . . . . . . . . . . . . . . . . . . . 4.1.2-10 4.1.2-6 Thimble E-11 Axial Power Distribution - RCCA D-10 '

at 121 steps . . . . . . . . . . . . . . . . . . . 4.1.2-11 4.1.2-7 Thimble E-11 Axial Power Distribution - RCCA D-10 at 83 steps . .. . .. . . . . . . . . . . . . . . 4.1.2-12 4.4.1-1 N41 Detector Currents versus Reactor Power . . . . 4.4.1-6 4.4.1-2 N42 Detector Currents versus Reactor Power . . . . 4.4.1-7 4.4.1-3 N43 Detector Currents versus Reactor Power . . . . 4.4.1-8 4.4.1-4 N44 Detector Currents versus Reactor Power . . . . 4.4.1-9 4.4.3-1 N41 Detector Currents versus Incore Axial Cffset . 4.4.3-5 4.4.3-2 N42 Detector Currents versus Incore Axial Offset . 4.4.3-6 4.4.3-3 N43 Detector Currents versus Incore Arial Offset . 4.4.3-7

. 4.4.3-4 N44 Detector Currents versus Incore Axial Offset . 4.4.3-8 C-1 Moderator Coefficient Rod Withdrawal Restrictions . C-5 P

vii l

l

6 PREFACE The purpose of this report is to present the analysis and evaluation of the physics tests which were performed to verify that the North Anna Unit 2, Cycle 1 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 North Anna Power Station.

Therefore, only a cursory discussion of these items is included in this i

report. The analyses presented include a brief summary of each test, a comparison of the test results with review criteria and an evaluation of  ;

the results.

The North Anna 2, Cycle.1 Startup Physics Test 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 su= mary -

of the startup test results in a consistent format. The design test conditions and design values were completed prior to startup physics testing.

i For the reactivity tests performed at hot zero power, the entries for the design values were almost exclusively the measured values from the North Anna Unit 1, Startup Physics Test Prograh in accordance with our co==itments to the NRC associated with the i=plementation of the modified Startup

. Physics Testing Program. The exceptions are that design values for reactivity l

v111 l

worths and critical boron concentrations associated with the shutdown banks are based on calculations performed by the Vepco Nuclear Fuel Engineering Group. ( For completeness, the measured results are summarized with the test result review criterion and the design criterion in the body of this report. 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 comparison between the measured and the expected values of the measured parameters, thus enabling a quick identification of possible problems occurring during the tests. Appendix B of this report contains the final completed and approved version of the Initial Startup Physics Tests Results and Evaluation Sheets.

The contents of this report are included in their entirety in the North Anna Power Station Unit 2 Startup Report. The numbering of the sections, tables, and figures contained in this report is the same as their designation in the Startup Report. However, the discussion and figures describing the core loading pattern and the control red locations that are presented in Section 3.0, " Zero Power Physics Testing ", of this report, appear in Sections 1.0 and 2.1, respectively, of the Startup Report. j ix .

2.2 INCORE MOVABLE DETECTOR SYSTEM The incore movable detector system is designed - to permit measurement of the axial neutron distribution within the core. This information is collected by the Unit 2 PRODAC-250 computer and made available for further analysis on and off site. A data reduction program (Westinghouse INCORE computer program) generates axial peaking factors, nuclear enthalpy hot channel factors, nuclear heat flux hot channel factors, radial peaking factors, relative assembly power distributions, radial tilts and axial offset ratios. The system consists of five movable miniature neutron flux detectors (fission chamber detectors) which can be remotely positioned to scan the length of 50 selected fuel assemblies through a guide thicble provided for this purpose. Each detector, designated A through E, is normally inserted in 10 of the chimbles (Detector C traverses 9 thimbles) via a 10-path transfer device. Each detector also passes through a co= mon thimble for cross-calibration purposes. By means of a 5-path transfer I device, the detector can also be routed to the next sequentially lettered detector's 10-path device or to a common 10-path device for all detectors.

These modes provide an "Nystional spare for each detector. A shielded storage area is aW ava latie. The locations of the various incore thimbles are shown in h y 1. , 4 Af ter core loading, the guide thimbles were inserted in the core and the final installation of the flux-mapping hardware was completed.

Following this, the operation of the systen was verified using a "dum=y" cable (i.e. no detector). This initial checuut, which was performed using an instrumentation department procedure, verified the operability of each drive unit and its associated 5-path and 10-path transfer devices. In addition, the lengths of each of the various paths were measured to deter =ine the limit settinge for the top-of-core and bottom-of-core positions.

2.2-1

~

Following the successful completion of the initial system checkout, the detectors and their associated cables were installed. The operability of the system was once again checked with the actual detectors. Throughout this portion of testing no serious problems were discovered, except that 3 thimbles, D3, DS, and D10, used by detectors C, A, and B respectively, were plugged.

The system operated successfully using the 47 remaining thimbles.

Af ter criticality, the determinations of the final top-of-core and bottom-of-core settings for each thimble were made prior to taking the first flux map. During each detector insertion, the recorder traces were monitored for indication of the various support grids on the fuel assembly. The limit settings were then adjusted as necessary to provide for proper detector posi-tion with respect to the top-of-core.

During the first flux map, detectors A and E were found incperable and were replaced following the first D-bank-in flux cap. The limit settings for these two new detectors were adjusted and the final top-of-core settings were verified to be acceptable after the analysis of flux map strip-chart recorder traces from the subsequent all-rods-out flux map.

In summary, the system operated successfully throughout the Startup Physics Testing- Program.

9 2.2-2

Figure 2.2 - 1 INCORE INSTRLMCITATION LOCATIONS X 7 N M L K J R C T E D C B A l

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C - FLUX THIMBLE DETECTOR C T - THERMOCOUPLE D - FLUX THIMBL:: U""::CIOE D 2.2-3 i

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. --- - - - , .>----n , - . , - . . . - - , , - - , , . ,

3.0 ZERO POWER PHYSICS TESTING On April 12, 1980, core loading operations began at Unit 2 of the North Anna Power Station. The actual core loading pattern and the design patameters for e.sa fuel region are shown in Figure 3.0-1. Figure 3.0-2 identifies the burnable poison and source assembly locations. Figure 3.0-3 identifies the core locations and number of control rods.

Following SNS&OC authorization on June 12, 1980, the plant was brought critical at 2148. Immediately thereaf ter, the zero power physics test-ing phase of the startup program began. The purpose of these tests was to verify that the core was properly loaded and to verify the accuracy of the physics models used in the core design and'cccident analysis. The tests also verified that the values used for the hot channel factors, control rod worths, and shutdown margin used in selected accident analyses were conservative. ,

The reactivity measurements were obtained utilizing a reactivity computer.( Flux level signals were obtained from power range channel N44 and processed by the computer to yield reactivity. The reactivity and flux level were then display;d on a strip chart recorder.

The review criteria used to evaluate the test results are primarily based upon the North Anna Unit 1. Cycle 1 startup physics tests results.(1) The core design values used to develop the design criteria for these tests were supplied by the Vepco Nuclear Fuel Engineering Group.( A summary of the results of the test- performed at HZP follows:

1. Individual control rod bank worths for control banks A through D were measured to be within 5.2% of the ellowable expected values.

The results for all of the control banks met the review criterion of 1 7.5%. >

3.0-1

2. Shutdown bank rod worths for shutdown banks A and 3 were measured to be within 3.9% of the allowable expected values.

The results for both shutdown banks met the review critsrion of + 10%.

3. Total rod worth of the control banks was measured to be within 2.57. of the allowable expected value. The result met the re-view criterion of + 5%.

4 Isothermal temperature coefficients at the all-rods-out and D-bank inserted configurations were measured to be within 2 pcm/ F of the allowable expected values. These results met the review criterion. As predicted, a positive moderator te=perature coefficient was measured at the all-rods-out condition. Consequently, rod withdrawal limits were develop-ed for use throughout the first cycle.

5. Critical boren concentrations for seven basic control and shutdown bank configurations were measured to be within 10 ppm of the allowable expected values. These results met the review criteria for each rod configuration and also met the accident analysis acceptance criteria.

6. The boron worth coefficient was ceasured tc be within 0.55 pcm/ ppm of the allowable expected value. This result met the review criterion and also met the accident analysis acceptance criterion.

7. HZP core power distributions determined from flux maps taken at the ARO and D-bank-in configurations were generally with-in 37. of the predicted power discributions. All measured parametcrs met their respective review criteria and accident analysis acceptance criteria.

3.0-2 1

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PS - Pri=ary Source Assembly 12 - Burnable Poison Red Cluster Assedly SS - Secondary Source Assembly 16 - Burnable Poisen Rod Cluster Asserbly 20 - Burnable Poisen Rod Cluster Assed ly

3. 0- 4

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i 3.1 INITIAL CRITICALITY The initial approach to criticality began at 1230 on June 12, 1980 z'. which time the RCS boron concentration was 1649 ppm, all control banks were fully inserted, and all shutdown banks were fully withdrawn. By 1506 on June 12, 1980, all shutdown and control banks were fully withdrawn except bank D which was maintained at 160 steps. Dilution to criticality began at 1530 at approximately 50 gpm rate and boron concentration in the RCS was determined at 15-minute intervals. The dilution rate was changed ,

at 1850 to 30 gpm and later at 2053 to 12 gpm. At 2136, dilution was stopped and the reactor went critical during mixing at 2148. Control bank D was then used to maintain the reactor just critical. After stabilization, the plant conditions were:

RCS Temperature: 546.6 F RCS P. essure: 2235 psig Control Rod Position: bank D at 156 steps  !

RCS Boron Concentration: 1330 ppm Plots of inverse count rate ratio (ICRR) ve rsus control rod

position, time of dilution, RCS boron concentration, and primary grade water integrator reading were made during the approach to criticalicy l in order to predict the onset of criticality. These plots are shown in l

The count rate data were taken from the two Figures 3.1-1 through 3.1-4 plant source range channels, N-31 and N-32. The plateaus existing in these plots were due to a temporary suspension of the startup testing program during the approach to criticality which was implemented because of a ,

Unit I reactor trip which required the full attention of onsite personnel -

at that time. ,

After the achievement of initial criticality, the flux level was slowly increased through control rod withdrawal until nuclear heating 3.1-1

effects were observed (i.e., an increase in RCS Tavg and a decrease in core reactivity). This occurred at a power level corresponding to 2.6 X 10~7 amperes as indicated on the reactivity computer piccammeter (which monitored

~7 power range channel N44), 6.0 X 10 amperes on the intermediate range

~

channel N35, and 6.9 X 10 amperes on the intermediate range channel N36.

The HZP physics testing range was chosen as 1 X 10~9 to 1 X 10-8 amperes as indicated on the reactivity computer picoammeter.

Upon determination of the EZ? testing range, a reactivity computer checkout was performed by comparing the changes in reactivity, calculated by the reactivity computer during positive and negative reactivity inser-tions, with calculations of the change in reactivity using the neutron flux doubling time and the design kinetics data (i.e., the delayed neutron yields and half-lives and the prompt neutron lifetime) in the in-hour equation. As shown in the Initial Startup Test Results and Evaluation Sheets in Appendix B, the average percent difference between the reactivity calculations perfor=ed by the reactivity computer and the in-hour equation was 2.57. and was within the design value tolerance limit of _+ 4.07.. These reactivity calculations were performed for reactivity insertions as large as 55 pcm.

l l

t 3.1-2

1 l 0

0 2

0 T 5 1

0 0

1

%s4hl u4 i

N I' 0

O G i. 5 T I S T E I T S O

S P O C

I D g},a - 0 '

S O 0 Y

l R 2 i

P L D O n k L R 0 n O T 5 a 1 B N 1 B

O .

- I C 1

E.

'6y (

0 1 n 0 )

C v 3 ,

1 S Y

P P

e C O 0 E r I 0 T u - T 2 S g A 0 i

F 2 R q 5 (

T E 0 I T 5 n N A s 1 o J

t R 0 i b t A T f' ^ i N N 0 s 0 C N l o A o 1 k P C 0 n e (y l

i m 0 a d T E p 2 l o R S p 0 l R

O R Il 5

N E 9 l V 1 2 4 0 o N L 3 3 6 5 r I 1 t N N 1 n

- - - 0 o C

0 b1'! OAC B l 01 1

1 B

,, 1 k

4 n a

,d 0" 0 B 5

s o

0 9 8 7 6 5 4 2 -

1

. 0 A 1 0 0 0 0 0 0 0 0 0 k n

a B

.U4r 30 u90 .T.e>d w g'.

Figure 3.1 - 2 NORTII ANNA UNIT 2 - CYCI.E I B01. PilYSICS TEST INVERSE COUflT RATE RATIO vs. DII.UTION TIME 1.0  ;

a i et l l

9 h h 0.9 d , ,

n ,.

rl 0.8 h $

a n

o 0.7 g ()

y n a h o

. 0.6 h 9 o 0 h F E 0.5 0

[

0 .

• 0.4 b y O - H31 fl a

" 0.3 A - N32 q D Bank at 160 Steps o Criticality 0.2 All other Rods out h if 0 O d ti Achieved rt hl 0.1 h A .

0.0 I O 50 100 150 200 250 300 350 400 Time From Start of RCS Dilution (Hinutes)

}

Figure 3.1 - 3 NORTH ANNA UNIT 2 - CYCLE 1 BOL PHYSICS TEST INVERSE COUNT RATE RATIO vs. RCS BORON CONCEh"l* RATION 0.9 '

O.8 e

o 0.7 u

E a e 0.6 -

Y a:

U 0.5 ._

5 u =

$ 0.4 y ..

c Q - N31 0.3 A - N32 -_-

0.2 D Bank at 160 Stepsp-' [ c Hi z;

l All Other Rods Out 0.1 w

0.0 ^- -

1600 1500 1400 1300 I

. l l \

RCS Boron Concentration (ppm) l j

3.1-5 '

1

, ll 4

3 9

l' h

b 2 3

, 9 aU s

T G

).i L

S N E I T D ), '

0 _

A (c,. _

S E 3 C R 9 _

I .

S R )

YI O '} s T

PI A n R o l

l L G O>

L O E l B r (

8 a

4 l f g 1 I 2

- 4 9 0 1

E.

I s

[;, L ~

(

1

. C v 3 Y g C O n e I i

r - T ) l u A ,L i

a g 2 R e i

6 F E R T 2 I

T 9 r IN A phr o I R .,,

t A T a N N r

g N

A U

O C

6  !'

t e

l i

n E

4 I T

R O

S R

[f' 2

E 9 N '

V N

I d

(N 2 2

9 i

0 2

0 9 7 6 5 4 3 2 0 9

a. .

1 1 0 0 0 O O 0 0 0 0 0

,<Jp

,* 3$ 'sSg

• 0e>d u.i*

llll lll l

3.2 CONTROL ROD BANK WORTH MEASUREMEh'TS AND SHUTDOWN MARGLN Differential and integral reactivity worths of the control rod banks were obtained by monitoring reactivity changes associated with RCS boron /RCCA exchanges. Following the establishment of a constant RCS boron dilution /boration rate, the controlling RCCA bank was periodically inserted / withdrawn in order to provide reactivity compensation for the changing RCS boron concentration. The reactivity changes resulting from the (4) control bank movements were recorded continuously by the reactivity computer.

The differential reactivity worth is defined as the ratio of the change in reactivity to the corresponding change in bank position about an average bank position, and the integral worth was obtained by summing the individual reactivity changes between measurement endpoints. Following the completion of the control bank measurements made during RCS dilution, it was determined that the reactivity co=puter strip chart recorder was not calib, rated properly.

The recorder was re-calibrated and' the control bank measurements made during RCS boration were performed in the non-overlap mode.

A su== cry of the results for these tests is given in Table 3.2-1.

As shown by this table and the Initial Startup Physics Test Results and Evaluation Sheets given in Appendix B, the individual measured bank worths for control banks D, C, B, and A met the review and design criteria. The total bank worth (non-overlap mode) for control banks A through D also met the review and design criteria.

The differential and integral reactivity worth of shutdown bank B was obtained by monitoring reactivity changes associated with RCS boron /

shutdown bank B exchanges. The integral worth of shutdown bank A was obtained by exchanging shutdown B with shutdown bank A. Since the worth of shutdown bank A was more than shutdown bank B, the rod swap was completed with shutdown bank A at 47 steps from the bottom of the core. The remaining l

3.2-1 l l

l

. 1 J

worth of shutdown bank A was obtained by monitoring the reactivity changes associated with RCS boron / shutdown bank A exchanges until shutdown bank A was fully inserted. The measured worths for both shutdown banks B and A met their review and design criteria.

The integral and differential reactivity worths for control rod banks D through A (non-overlap mode) and shutdown bank B are shown in '

Figures 3.2-1 through 3.2-10, respectively. The expected values (Unit 1 measured) and the Unit 2 measured data are plotted together in order to illustrate their agreement. Additionally the design predictions and the measured data have been plotted together in Figures 3.2-11 through 3.2-18.

The rod worth measurements are quite exact in defining the shape of the individual differential rod worth curves, as illustrated by the distinct depressions occurring at the assembly grid locations.

In addition to the conventional control rod bank reactivity tests, reactivity tests using the. rod swap technique ( ) were also performed.

The results of these measurements are shown in Table 3.2-2.

The worth of N-1 rods, calculated using the design value of the most reactive rod (3 , was used in the shutdown cargin calculation shown in Table 3.2-3. As indicated in this table, the calculated shutdown margin ,

verifies that the shutdown margin requirements are met and that an excess shutdown reactivity of 1715 pc= is also available.

j All measured rod worths were within their respective review and design criteria. Adequate shutdown margin was verified by all rod worth measurements. In summary, all test results were satisfactory.

I 3.2-2

Table 3.2-1 NORTH ANNA UNIT 2 - CYCLE 1 BOL PHYSICS TEST CONTROL ROD BANK WORTH SLT'.ARY Measured Review Design Bank Value Criterion Criterion (Dem)

D 1437 1463 -110 1354 135 C-Bank D In 1236 1303 ! 98 1168 : 117 B-Banks C+D In 2002 2036 153 1926 193 A-Banks B+C+D Im 1303 1309 : 98 1214 121 IA + D 5978 6111 ! 306 5662 ! 566 SB 1046 1043 : 104 1043 104 SA 1157 1114 2 111 1114 111 S

e

/

l l

3.2-3

Table 3.2-2 NORTH ANNA UNIT 2 - CYCLE 1 BOL PhTSICS TEST ROD SWAP TEST RESULTS SLTARY l

l l

1. Measured Design Value Value Percent Difference tank (pcm) (pcm)

(M-P)

P X 100 D- reference bank 1437 1354 +6.13 C 1001 988 +1.32 B 1343 1302 +3.15 A 628 626 +0.32 SB 1078 1057 +1.99 SA 1169 1120 +4.38 Total Worth 6656 6447 +3.24 3.2-4

Table 3.2-3 NORTH MNA UNIT 2 - CYCLE 1 BOL PHYSICS TEST SHUTDOWN MARGIN CALCULATION Measured Desigr A. Control Rod Worth Data (pcm) value (ocM Total Rod Worth Less RCCA B-8 (N-1 Rod Worth) 7807 7785 Measurement Lteertainty (4%) 312 311 N-1 Rod Worth less Uncertainty 7495 (a) 7474 Most Limiting B. Reactivity Worth Reauirements

• Desien Data (ocm) BOL Data ( }

From FSAR (Dem)

Doppler (Includes 15% Uncertainty) 1400 # 1300 Rod Insertion Allowance 500 500 Variable T 1260 550 MOD Redistribution 850 500 Total Reactivity Worth Requirement 4010 (b) 2850 C. Shutdown Marcin Calculated Shutdown Margin (a)-(b) 3485 Required Shutdown Margin 1770 Excess Shutdown Reactivity 1715 i

These reactivity worth requirements are the most limiting of the BOL and EOL design values. (6)

This value is the design Doppler defect including 15% uncertainty.

3.2-3

! FIGURE 3.2-1 NORTH RNNA UNIT 2 - CYCLE 1 BOL PHYSICS TEST BANK D INTEGRAL R00 WORTH - HZP RLL CfMER RCCS Out

-- En tCTEC funft 1 NEasuREDI M MEASUREC 1

o '

C

, w . , ,

~ . ,. , . .

. i . . > . , . , . . ,

I f 8 3 g .I I 1 i l f i

C , , i . . .i. . . , . ,

o -

w . . . ,

~ , e s ,e , .. . . t j . . ,

i - , , . . , ,

!.I re ' +

- uow . . .

b- . . . , l .

I r

". m'm ze 3 - '

CD w . .

2 ~- , c . . ,

, N1 .. , .

_; , . m , . .

Q i  %\. .  ! . i

. i .Ns . ..e i . . . e i

% * %s , i i

o . a , . . ,

u!o b_ ,

Hw , . v. . .

g m ,. . .

. . u,

.ns I W I . , , i

.N v  !

. . . 1 w . , ,

,. . .w

- , . NT ,

, , . , . , , as , ,

l e

, v w .  % .,

T . . g.

, . . . i .m- ,

m .

. 6 e i ., W .

... . , .s , , , . ., ,

, , , , . , , 2<. ,

i i , , , . . . . ., . . . .. . ,s i , . . . , , , , x .

'i! W - .m I c., . . . . m

' 80 O 40 120 160 200 228 BANK D POSITION (STEPS)

I i

I.

3.2-6

1 F.IGURE 3.2-2 l

NORTH ANNR UNIT 2 - CYCLE 1 BOL PHYSICS TEST BANK D DIFFERENTIAL ROD WORTH - HZP RLL CT*'ER RCD $ OUT EXPECTED tVNIT : MEASURED) m nEnsunEn 1 o o.

a . .

, . , , , , . i . . .

.. i .

. .. i . . , .. . , ,

a . . . , . .,

l j o. e  !

o my . . .

L . .

y . .

Wo e No .  !

ry '

l ,u - .

RF 6 i i

m. , . , .

r .u m . i

- ( Mamm' .

1 ho n. A  !

i *  %.

W g o.

e I

C o R .

s.

4- i i i

3 .

e w

. . i i i , ,

I AW g '

s .

o - ,'

E W o. d ag i i

&o

• R l i M .r" * '

w l ,. . . .  %, .

t <. . .

m i

. . , . =m,, . _ .-

L2 o n; i ~

~ ~n.

g o.

, i n

imT i y / , .

. e,rer e e a c = t % _4 . .s %

,. -rm / . = -m L 8

'_## ANA h i e . .fa - i # # /' , X- .A N Ai I , ,

• /

. # I- i 1

N N N

<s o

I I

! M

_ , _ . r . . , . .

i. .w-

o. 1 is Ew a 7 l

0 40' 80 12' 0 160 20' 0 228 BANK D POSITION (STEPS) 3.2-7

FIGURE 3 2-3 NORTH RNNA UNIT 2 - CYCLE 1 BOL PHYSICS TEST

- BANK C INTEGRAL R00 WORTH - HZP C SANK IN. ALL Cf MEE ROCS C'JT

-- EXPECTED tuMIT 1 MEASURED)

N ff!R$URED e

c

! if 0

. . 6 . . ,. . ,, .

. . 6 . i . . 6 . .

. . a . . . n .. ., . .

e , . .

w . , , , , i. . . .

C4 s , . . . s .

. , , . . . a , .

re .

oc , , . , , .

i .

cL. _.L '

~ , .  ! . , ,

= ', '

H , i .

, , i t

. ~

oc -

s 3N C x

.w x -

i

, i.

LN .. . . .

_J m .

c u.

gs e n. . .

Q i .sh. .

Lu c  ! 'd. .

sve ,

.xx .

z .

.y . . .

i

. , sx .., , . .

u , i ,

i m.m . . . .

.. . . v. . . . . .

. m .

i

. - N' .

) YN e , .w

- , , , .e e . . , , w l . . . .

iw. .

ws l wx .

. . A. N .

.h. .

t

, , , . th .

4 . , . < ,, ,

i i

. ., . m , ,

. i _.

-. i m w . . .

m 0 40 80 120 160 200 228 BANK C POSITION (STEPS) l l

3.2-8 l l

i I,. , , . . . _ , .,- - - - - . - - . . - - - - , . - - - - - - - ~ , - - - - - - - - -- -~ - - - - - - - - - - - - - --" -~~-* - ' - ' - ' ~

l

. 1 1

FIGURE 3.2-4 NORTH RNNA UNIT 2 - CYCLE 1 BOL P"YSICS TEST BANK C'01FFERENTIRL ROD WORTH - HZP i

. C BANK JM ALL CIMER RCO$ CUT I S

-- EXPECTED tVNJI 1 MEASURED)

M MEASURED

i 1

I

. O O.

u .,

. i e .. . ,,

I o. ..

r . .. i .

c . . . . . . . .

m .. . , . . . .

O.- . . . . . ..

l W . . . . . . . , . , , . . . . .

~ , . . .

u, e , .

No .i i . . . . , . , . . .

l rg '

u ._ . . , . .

e , . .

)

l ,a rz o. .

. , . . 4

..-~m..

u ., .

o ._

2

. . .s

.1 . ,

c . . . .

. .~s.

m ,

a . .

w e. . - -- ..

W. .

. /- . i i i .

'~3 i ,

f ,

, a . . k .

W . . . . . . . s. . ,

w .

. .. m-.

>o L, e o i f

= -=,,,5 . , .

a ,- , . .

n -

. . F- I i c,F_!e teac*!si! .

. h . =m% mg.

M- i . .7# / ANN.

, ./ .,r. y ./ e .x . x ., w . .MN'- .

. .,p i . p . .f. A- N. N

/, -, , . m. m.

O . i! . . . t iM_

1. i - ' .  !- "

O. . , ,

, m Q 4 i T 0 4'0 80 120 160 200 228 BRNK C POSITION (STEPS) 3.2-9 1

.w_,- ,,-.-,.-y-, e-,.m g,-rp- - - - , ,-, rw---r-,e,.,---w-, p .e-

FIGURE 3.2-5 NORTH ANNA UNIT 2 - CYCLE 1 BOL PHYSICS TEST BANK B INTEGRAL R0D WORTH - HZP C*C BANH3 IN. ALL CTHER RCOS CUT EM ECTED IVNII I f!!R$URED) l IE ttER$URED ,

I o

C N . . . i . . .

. . 1 . t

, i 4 . , . . . .

. i a , i . .

i , , . >

, i. . .

, i i . . . . .

c .

C .% . ,

v.%w . ., . .. , , . , , . . .

N .ws . , , . . . , a i i . .

, u .. . i . *

.. . .g,_ i , .. . . . .

N'( . . . ,

i 4 ii . . ,,  ! i e i r M _dI . t , I '

ms ,. , . . . .

EC , , ,

vs . . . . i yo s- i .

C. I ' ' '

- , .c . . . , .  !

i- n. i . . .

, . . .s. .. . .

. a. ,

.u. . .. .,

i H ..

i oc e , 't ,

oo ,

.w l ]D -. .

..t 3

i

g. i , i i .

a . . x._

ag

.y . , .

Of

~

W t , , i Q , , . i 1. i, e .

~i.m.

tu e co 7 .

,m.,

- , . ,. . .m . .

, , ,.g. . .

, , , . ~ . .

. 4 . m.

s, l e s

, 1

- , , s Y ,

.\.

.. ~ ,

m ,

I . ~. i l , .

, , . ~. ,

. . i N .

s . . .

. t  ! i . . N i .

. , ~ -

0 4O B0 120 160 2'00 228 BANK B POSITION (STEPS) a l

i t

r I 3.2-10 l

l

, . - . . _ . _ _ _ _ _ . . ~ . . , . . _ . . . . . _ , - _ - - _ _

A 2:

e 1

4 F.lGURE 3.2-6 l

t. NORTH ANNA UNIT 2 - CYCLE 1 BOL PHYSICS TEST l'

i BANK B DIFFERENTIAL ROD WORTH - HZP i C+0 BANKS IM. ALL OTHER R$C$ CUT i 4

-- W ECTED tuMIT 1 t!EASURED) j E ttEA$URED i

l 4

I C

+ C 1

< w -

jl N . +

m. I

, i , , , 4 i . . . . . 6 , * .

j . . 4 = m , . .

. . . v. , . 4 1 i .. . .a i . , , . ,

! , * . , 6 . .= ,,

. . i , . . .

l c i j . . . . , i .

g i C. , . . . , , . . . . 4 o . r. , i i i .

i

. w . .

r i , .

( ..

.. , i . . i 4l (1)

_ . , , . . . . 4- i . 4 gg . i e, . . . ..

p 4 m :a.

. . ,. . s. ii. , , . . i WC

. m

5 ,

N o.

y , , ,

i 2

!j . . .

"c.

Um E- .M , i g , .

! . . . . 1 .

./ e , a . I w . . . . . m ..

.f j 1 i

1

-o L

} Ho . 6 . .

g "= T .

i ,

o jl ,. , .

2 (~

.4 .. , , . , . .

1 i w

. # . . . 37 ,, . .

1 a . . . . . .- .

J, g .

, s . .

i ,

j! mo . . . m, H o.

- w at .

7 e .r. . , . . , , , .

j

f. g 3

i .

s \. } I 4

.! , , . 6 6 , ..m. , . ,

LL.! i i . . i m.. , 6 3 m . .r i . , . mv

- s . M; 4

L:_ e i: , , s m

t. -a c. 4 m

g i I . I A_

.

• st ! t . P P C Y t ema s

, , i. i h . . 8't N 1 P. . _.ff 1. %XX 4 .w w . .f f- '/  %- .X.N ' R. * .

. . , .- .# .i. .x x  %

, , . i . . . , . m ,

g .g . 4, ,

iiw .m I

Q /: i . , ' , ' f e . .  !; , 7 g.

,i . i .

- t

' e, ,

i .

. r

< O 40 80 120 160 200 228 BANK B POSITION (STEP) 1 i '

I 3 3.2-11 1

. _ . _ , _ . . _ ,_- , -_ ,m.. ., _ , . _ , -

i I

i FIGURE-3 2-7 NORTH RNNA UNIT 2 - CYCLE 1 BOL PHYSICS TEST BANK A INTEGRAL ROD WORTH - HZP i

SeC+D 8ANM3 IM, ALL CTHER 9005 CUT

-- EXPECTED (UNJf I f!!R$UREC) 5 m nEnsunEn [

l t s s

1 L

y I E

! C  !

o -*

~ ,, , i, . E N , i , ,

. . . . ,, .. . . . i i .  :

i . . . .. . . . . . [

. . i  ;

i > . . .

CD i , . , , . 1 . . . i . . . I i t C3 . i . i

. w ,, . . . . . .  !

e9 . . , , , , . . . 4 , .. , , , , , . .  ?

. .. . . ,. ... . . i, . . . . r

. i , i . ,

. . . . . t e= , , . . . , .  ;

i re yo

, . ,,4

. I i

' 4 4 . i

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

., . . . i . . .

d- . i , ,

t '

• ge a_ . . i i

.w , . .

i OO Mm- 6 I

3 (N

. . - - -w. . .

l i . . . T ,.. . . 1 .

.. . = i , ,. . .

_j . v , , . .

1 g . .w 1 ct . , L, .  ;

)

Q .

4 i E . .

tu o a w l Y U t 0 l'

e . , m . i . . . .. .

7 , . .... , = ,. . .

- w

, .. ., , 4 . . . . , .

i i 1 M , i . .

i.... . > i ,w , ..

. . w . . . . ,

m. . i

, , a i , e Mk i s i O i i X  !

w . N-

, . . . w . . --

i i . ' , . t . .  %. . i i i i

i . i , .  ! i . . ,. 4 . 4 . N. , , .

.N. . , i 4 l . . . . . i w- .

,,, . . , . w

,i , , . . .  ! , . . *%

t I . . . . ,

i , 1 L

, mNm_ .

m _.

w . .

. m 0 40 80 120 160 200 228  :

BANK R POSITION (STEPS) 3.2-12

, -- e._ ., - - _ , . , - - - - . - , , . , , . , , _ - , , - ,.n.--- . - . _ - ,n.,--,,,w,_.w-w.ea.. ,,,.,-,--m n.,,--sn,,-- , --

I FIGURE 3.2-8 i

NORTH ANNA UNIT 2 - CYCLE 1 BOL PHYSICS TEST BANK A DIFFERENTIAL ROD WORTH - HZP

, SeCeC SANMS IM ALL CTMER R005 CUT

-- EXPECTED (UNIT 1 P.EASUREC1 M MEASUREO i

O C.

v eq . . , , . .. .

, . . , , . . . . , . . .. . . . . i . 2 i . i . . . . * ,

. . , . . i . , i ., . . , .

. . ., ,, , ... . . 1 , .. . ,

e . .

c. , . . . . . . .. . .,., , ... , . . . .

C ' '

g , , .' . '

i , , , . . . 6 . .ii, , 4 . . 4 ,. , . .

W e i . . 1 . i i .

wa .

. i .. .

i i . .

N o. . , ,

i .

4 , i i . i .

l u- e .

e .

=. a I lo i

>-- O .s --

g* vw ur r; . ..

O, N w L= . .

. mg. .w- , ,

2 -

4 . .

i- . t , Vn . i f

_a . . ., . , ..

Q . , . .'E-.

e

. m.

p - O.

K 1*_ e i

z . .. ig . . .

w.

g .

, . i s ,....

Ya ..

1

, i w

1 . . . i 5 , ,

e i . I s 1 u_

C 4

m. -

,,.4y.

e-- e O as * '

o ,- , ,

. r. .

M. . ,t - dR t t t f*

• A ' ? *Je t

. 'N

. . f f- ~W.

l / -ff- ./ '% WW. W.

l as s ' i # # / X 1N- iN N g r a p .p . .I. .g. . .N .

N

/ . , , E e . : _, ,

.- . , . . ~.

o. . i. . . .__.

O, ,

. v 0 40 80 120 160 200 228 l BANK A POSITION (STEPS) I

\

3.2-13 1

rk F

t FIGURE 3.2-9 l NORTH ANNA UNIT 2 - CYCLE 1 BOL PHYSICS TEST SHUTDOHN BANK B INTEGRAL ROD HORTH - HZo I

ALL CYNER RCC$ CUT-.

N MEASURED i

sa e n e o Ow , , . . . #

e .m . .

e . v. . .

- , ,s . . , . . .

6 . . 3 . . . . . .  !

. . .% . , . 6 6

. , . 1 u. . . ,

i 4 . 4 g. i , 6 ,. . . . . . , . ,

. L . . . ...

- , , . , s . , . . ,

i e 6 i A- . j . . 6 .

b . . i M ..

a . .

ue . - .

eC w .

i i i .

. ,\ . . i .

,,,,, . 3a 6 . . . .

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3.3 ISOTHERMAI, TEMPERATURE COEFFICIENT l i

The isothermal temperature coefficient measurements were accomplished by establishing a constant and uniform heatup/cooldown rate, using the steam-dump valves to the condenser, and then monitoring the resulting reactivity changes on the reactivity computer. These measurements were perfor=ed in the zero power physics testing flux decade (ZPPTED) of 1.0 x 10-9 to 1.0 x 10-8

amperes in order to minimize the effects of non-uniform nuclear beating. With-out nuclear heating, the moderator and fuel were approximately at the same J

temperature (between 543 and 549 F) during these measure =ents. To eliminate the boron reactivity effect of outflow from the pressurizer, the pressurizer level '

was maintained essentially constant or slightly increasing during these measure-ments.

Isothermal temperature coefficient measurements were performed at various control rod configurations. For each of these configurations, reactivity measure =ents were made during a RCS cooldown of approximately 3*F, a RCS heatup of approximately 6*F, and another RCS cooldown of approximately 3*F. Reactivity was determined using the reactivity computer and was plotted against the RCS temperature on an x-y recorder. The isother=al temperature coefficient for each core configuration (ARO and D-bank inserted) was determined as the average of the values for the slopes of one cooldown plot and one heatup plot. A representa-tive x-y recorder plot of reactivity changes vs. RCS temperature (the D-bank-in temperature coefficient plot) is shown in Figure 3.3-1.

The predicted and measured isothermal temperature coefficient values are compared in Table 3.3-1. As can be seen from this su==ary and from the Initial Startup Physics Test Results and Evaluation Sheets given in Appendix B, both of the measured isothermal temperature coefficient values met the review criterion and the design criterion. However, as predicted, the isothermal 3.3-1

I i

temperature coefficient measurement performed with the reactor at hot-zero-power and all of the control rods withdrawn failed to meet the accident analysis accep-  ;

tance criterion (this criterion is based on having a negative moderator temperature coefficient)*. Because the North Anna Power Station Unit 2 Technical Specifi-cations (T.S. 3.1.1.4)(7) currently do not allow operation with a positive modera-tor temperature coefficient (except during physics testing), it was necessary to develop, from the measured temperature coefficient values, a rod withdrawal limit curve that would preclude the operation of the unit with a positive moderator temp-rtture coefficient. This operating limit curve, together with i

supporting calculations, is given in Appendix C. The. isothermal temperature coefficient value for the D-bank inserted configuration met the accident analysis acceptance criterion. In summary, all test results were satisfactory.

l t

• Isothermal temperature coefficient = Moderator temperature coefficient +

Doppler temperature coefficient. The Doppler Coefficient equals -2.02 PCM/0F st IIZP. (3)

?

3.3-2 l

l

l Table 3.3-1 N94111 ANNA UNIT 2 - CYCLE 1 BOL PIIYSICS TEST IS011IEIGIAL TEMPERATURE COEFFICIENT StefMARY Bank Position Boron Temperature Isothermal Temierature Coefficient (pcm/"F)

(Steps) Meastired Review Design SDA SDB A B C D Concentration (PPH) Range ( F) Value Criterion Criterion

- 228 228 228 228 22h 218 1312 543-549 -0.63 -0.98 2 -2.03 i 3 228 228 228 228 220 0 1197 543-549 -4.13 -4.29 i 2 -5.10 1 3 t'

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3.4 BORON ENDPOINT AND BORON WORTH MEASUREm'TS Boron Endpoints With the reactor critical at hot zero power, reactor coolant system boron concentrations were measured at selected rod bank con-figurations to enable a direct comparison of measured baron endpoints with design predictions. For each measurement, the RCS conditions were stabilized with the controlling rod bank at or very near a selected endpoint position. The critical boron concentration was then measured.

If recessary, a slight adjustment of the measured critical boron con-centration value was made to account for off-no=inal core conditions, l

1.e. , for rod bank position and moderator temperature.

l

! The results of these measurements are given in Table 3.4-1. As shown in this table and in the Initial Startup Physics Test Results and Evaluation Sheets given in Appendix B, all measured critical boron endpoint values were within the review and design criteria established for these measurements. Additionally, the accident analysis acceptance criterion for these measurements ves met. In su= mary, the test results were satisf actory.

Baron 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 con-structed by relating each boron endpoint concentration to the integrated rod worth present in the core at the time of the endpoint measurement. j 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 1.4-1.

)

3.4-1

The predicted and measured boron worth coefficient values l are given in Table 3.4-2. As can be seen from this sumary and from the Initial Startup Physics Test Results and Evaluation Sheets given in Appendix B, the measured boron worth coefficient value met the review [

, criterion, the design criterion and the accident analysis acceptance i criterion. In summary, the test result was satisfactory.

I 1 t t-I e

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3.4-2 4

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TABLE 3.4-1 NORTH ANNA UNIT 2 - CYCLE 1 BOL PHYSICS TEST BORON ENDFOIhTS

SUMMARY

Measured Control Rod Endpoint Review Criterion Design Criterion Configuration (ppm)* (pom)* (ppm) **

ARO 1332 1322 1 24 1324 1 50 D Bank In 1193 1193 1 24 1203 1 19 C + D Banks In 1080 1075 1 24 1081 1 16 B + C + D Banks In 893 884 1 24 895 1 22 A + B + C + D Banks In 784 781 1 24 785 i 15 Shutdown Bank A In 1225 1232 1 20 1232 i 20 Shutdown Bank B In 1220 1228 1 21 1228 1 21 14;easured endpoints have been adjusted to nocinal conditions: Rods at their endpoints and T avg at 5470F.

• • Predicted endpoints have been adjusted for the difference between the measured and predicted values of the previous endpoint.

3.4-3

1 Table 3.4-2 NORTH ANNA LTIT 2 - CYCLE 1 BOL PHYSICS TE.q ,

BORON WORTH COEFFICIENT

SUMMARY

~

Boron Worth Coefficient (ncm/com)

Measured Review Design Value Crite rion Criterion

-10.87 -11.08 t 0.55 -10.75 1.08 l

3.4-4

FIGURE 3.4-1 NORTH RNNA UNIT 2 - CYCLE I DOL PHYSICS TEST BORON WORTH COEFFICIENT citwornsut ntnsuntnr.wis 6000 -

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~

3.5 POWER DISTRIBUTMN MEASUPIMEYrS AT HZP-ARO AND D BANK IN The core Wher distributions were measured using the movable detector flux mapping system. This system consists of five fission detectors which traverse fuel assembly instrumentation thimbles in 50 core locations (see Figure 2.2-1). 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 deter =ined by

analyzing these data using the Westinghouse computer program, INCORE(6).

INCOPI couples the measured flux cap data with predetermined analytic power-to-flux ratios in order to detemine the power distribution for the whole Core.

Flux maps N2-1-1, U2-1-2, and N2-1-3, were taken just above the

~

zero power testing range between 1.3 x 10' and 1.9 x 10 a= peres on the reactivity computer picommeter (N44).- Flux =aps N2-1-1 and N2-1-2 were taken with D bank fully inserted. Flux map.N2-1-3 was taken at a nominal all-rods-out configuration. During flux map N2-1-b there were abnormally 4

high background values recorded by Detector A. B4 sed on an evaluation cf

.{

this data, it was decemined that the data recorded by Detector A was not 1

reliable. This resulted in the amount of useable data dropping below the value specified in the Technical Specifications for a full core flux map.

4 For this reason, the analysis results for map N2-1-1 are not presented. Table 3.5-1 provides the seasured vslues of the important power distribution para-meters obtained from the twc recaining HZP flux maps. All parameters met their design value tolerances as indicated on the InitiO Startup Physics 1 Test Results and Evaluation Sheets included in .ppendix ,. Although no Technical Specifications limits for F T g, F' , And 7 . try applicable below

57. power, the measured values of these parameters would have met the 5% power limits. The radial power distributions associated with these flux maps are 3.5-1 l

shown in Figures 3.5-1 and 3.5-2. As seen in these figures, the measured relative assembly power values are generally within 2% of the predicted values. In su nry, these power distribution measurement results were satisf actory.

3.5-2

Table 3.5-1 NORTil ANNA UNIT 2 - CYCLE I BOL PIIYSICS TEST StHfMARY OF INCORE FLUX HAPS AT 11ZP - D BANK IN AND ARO MAP MAP POWEP. BANK POSITION F IIOT , FNg Il0T CORE Fg DESCRIPTION NO. (amps)# (STEPS) CIIANNEL FACTOR CIIANNEl. FACT 0f MAX AXIAL AI' C D AXIAL

• Assy Pin POINT F Assy Pin 11 POINT Fg F""* QPTR

% TlIMBLES Zero Power M/D 2+ t.3(10J 228 0 Nll QQ 30 2.376 C11 AQ 1.527 30 L.509 1.609 1.008 40.51 46 Flap - D In

" 7 w Zero Power M/D 3 1.9(10J 228 205 P7 QA 29 2.340 P7 QA 1.475 30 1.529 1.566 1.008 -1.77 46

/, Map - ARO NOTES: llot spot locations are specified by giving assembly location (e.g.11-8 is the center-of-core assembly location),

followed by the pin location (denoted by the "Y" coordinate wi th the seventeen rows of fue] rods lettered A.

through Q, and 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.

All hot channel factor values include measurement uncertainty (1.05 on F9 and Fxy,and1.04onFNg). 1he Ph and Fxy values include an additional 1.03 engineering uncertainty.

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

The analysis for map 1 was aborted.

1. Reactivity computer picoammeter

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4.1 AT POWER PHYSICS TESTING During the power ascension, a number of physics tests were performed.

j The purposes of these tests were to verify the accuracy of the physics models used in the core design and accident rnalyses, to verify that the values used for the hot channel factors and control rod worths in selected accident i

t analyses were conservative, and to obtain calibration data for the Nuclear Instrumentation System. A summary of the results of the physics tests performed during power ascension follows:

1. Core power distributions determined from flux caps taken at power levels of approximately 30%, 40%, 50%, 60%, 75%, 90% and 100% of full power are generally within 2% of the predicted power distributions. For these maps, the hot channel factors were measured to be within the limits of the Technical Specifications. All measurement para =eters met their design 1

and accident analysis acceptance criteria.

2. The rod worth and nuclear enthalov rise hot channel factor associated with'the static dropped rod test were conservative with respect to the accident analysis values. Core power distributions associated with flux =aps taken before and after the static rod drop were generally within 5% of design predictions.

l ,

The measured rod worth was within the design value tolerance of 115s.

1 4.1-1

4.1.1 POWER DISTRIBUTION MEASUREMENTS AT POWER The core power distributions were measured during the power ascension phase of the startup testing program using the incore movable detector flux mapping system. A list of most of the flux maps taken during the power ascension program is given in Table 4.1.1-1 together with a list of the measured values of the important power distribution parameters. The at-power flux map taken with a dropped control rod is discussed in Section 4.1.2.

The flux maps listed in Table 4.1.1-1 were taken over a vide range of power levels and control rod configurations. These flux maps were taken to verify the accuracy of the physics models used in the core design, to measure core power distributions at typical operating conditions, to obtain calibra-tion data for the Nuclear Instrumentation System, and to obtain base data for axial power distribution surveillance. As noted in Table 4.1.1-1, typically forty-seven chimbles were used for the full core flux maps. Flux maps 16, 20, and 21 were quarter co.re flux maps (QCFM) and were used to monitor the axial offset during the incore/excore detector calibration procedure (see Section 4.4.3).

The radial power distributions for the power ascension caps are given in Figures 4.1.1-1 through 4.1.1-11. As seen by these figures, the measured relative assembly power values are generally within 27. of the predicted values.

The measured power distribution parameters are compared with their Technical

. Specifications limits in' Table 4.1.1-2. The power distribution parameters for all flux maps met their design, accident analysis, and Technical Specifi-cations limits (see Appendix B).

In conclusion, all power distribution measurement results were considered acceptable with respect to the design, accident analysis, and Technical Specifications limits. It is therefore, anticipated that the core will continue to operate safely throughout Cycle 1.

1 i

j 4.1.1-1

, _ _ - , -,- - _ _ _ _ . . .---,,- , . , , . - , , . _ _ , -. _ , . - - . _ _ ~ _ _ _ , - . _ , _ , , . . -

Table 4.1.1-1 NORTil ANNA UNIT 2 - CYCI.F. I BOL FHYSICS TESTS St9HARY OF INODRE FIUX HAPS TAFDI IWRING Fm7FR ASCENSION T

BANK POSITI(N F lt07 F"m 180T CORE F DESCRIFflos No. (Il (STEFS) CISN EL FACTOR

• OIANNEL FACTOR

• MAI ARIAL NO.

A KI AI. AXIAL + IU C D ASSY. FIN FOINT F ASSY. FIN FOINT Yg N #"

q F,y t/E Cal. 8 29 228 1 75 F7 Q4 29 2. 359 F7 QA 1.439 29 1.550 1.541 1.007 - 2.90 47 c3 I/E Cal. - ArtM Mei' 11 41 228 1 74 F7 QA 37 2.146 FF QA 1.398 37 1. 44 8 1. 541 1.005 -11.23 47 L

t/E Cal. - AFret - 12 51 228 214 89 AQ 29 1.978 59 AQ 1.416 30 1 . 36 6 1. 4 91 1.006 - 1.42 46 50Z Base Map c'e AFIN MAP 14 59 228 210 89 AQ 37 2.012 F7 QA 1.403 37 1. 3 M 1.487 1.005 - 7.19 47 t/E Cal. - ArtM Mar 15 76 228 228 89 AQ 37 1.974 59 AQ 1.397 37 1. 357 1. 4 74 1.004 - 6.83 47 I/E Cat. - ArtM Mar 18 77 228 196 39 Aq 37 2.030 89 AQ 1. 376 37 1.4n8 1.461 1.004 -10.64 47 t/E Cal. - ArtH Mar 19 76 228 186 89 AQ 37 2.086 F7 QA 1. 3 71 36 1 . 4 42 1.461 1.004 -14.47 47 t/E Calibration 22 75 228 20 3 89 AQ 29 1.975 FF Q4 1. 3 82 29 1. 3 10 1.468 1.001 1.31 47 90s - nap 24 n7 22e 189 s9 Ag 17 2.014 F7 At 1.349 f.423 toog - AFIN nap 37 1.443 1.001 -11.el 47 25 100 228 229 K7 3R I.959 F7 A 1.36 I.454 1.36g 37 1.003 7.60 47 ient - rg, Map 76 Sn 228 210 r1 hIa 17 f.958 F7 <>ke 17 IN{k I B.451 t 004 .

- a_s2 ar le0TES: Hot spot locations are specified by giving eseeably locatione (e.g.14-8 le the center-of-core asse=nbly location),

followed by the pin location (denoted by the "T" coordinate with the seventeen rows of faael rode lettered A through Q. and the "I'* coordinate designated in a eletter manner). In the "Z" direction, the core to devided into 61 estet pointe starting frue the top of the core.

• All hot channel factor values include measurement uncertainty (1.0% on F and F and 1.04 on F ).

The F and F values include en additional I.03 engineering uncertainty.

+ QFTR - Quadrant Power Tilt Ratto. Yhte value to the maximum of the upper and lower core Imlves.

Table 4.1.1-2 NORDI ANNA UNIT 2 - CYCI.E 1 ROL PilYSICS TESTS COMPARISON OF MEASifRED POWER DISTRIBUTION PARAMETERS WIT 11 TIIEIR TECilNICAL SPECIFICATIONS LIMIT F llo t Channel Factor" F llot Giannel Factor ' F flin i mum Margin Margin Axial MarRi n Map Hensured Limit (%) Measured Limit (%) Measured l'oln t Limit (%)

8 1.439 1. 7 74 18.88 2.359 4. 179 43.55 1.541 48 1. 774 13.13 11 1.398 1.733 19.33 2.149 4.200 48.83 1.541 11 1.912 19.40 12 1.416 1.702 16.80 1.978 4.097 51.72 1.491 48 1.702 12.40

~.

> 14 1.403 1.678 16.39 2.012 3.584 43.86 1.487 52 1.678 11.38 E 15 1.397 1.624 13.98 1. 9 74 2.76'3 28.56 1.4 74 52 1. 6 24 9.24 0 18 1. 376 1. 6 22 15.17 2. 0 30 2.739 25.88 1.4 61 52 1.622 9.93 19 1 . 3 71 1.625 15.63 2.086 2.770 24.69 1.461 52 1.625 10.09 22 1. 382 1.626 15.01 1.975 2.773 28.78 1.468 48 1.626 9.72 24 1. 349 1.590 15.16 2.014 2.408 16.36 1.443 11 1.590 9.25 25 1.366 1.550 11.87 1.959 2.102 6.80 1.4 54 10 1.550 6.19 26 1.367 1.558 12.26 1.958 2.154 9.10 1.453 10 1.558 6.74 a The measured value for the enthalpy rise hot channel factor, IE gig , includes 4% measurement uncertainty, b 1he Technical Speci fications( limit for the heat flux hot channel factor, F is a function of core he igh t. The value for FT listed above is the maximum value of F{ in the core 9,1he Technical Speci fications limit listedaboveisevkluatedat the plane of maximum F . TThe minimum margin values listed above are the minimum percent di f ference between the measured values Tnof F (Z) and the Technical Sepcificatinns limit for each map. All measured F hot channel factors include 5% mdasurement uncertainty and 3% engineering uncertarnty.

c All measured F MAX xy values include 5% measurement uncertainty and 3% engineering uncertainty.

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o in t et s te t ts t ts t ss t st 1 ts 111 t ts 1 ts t ss t se 1 ot o ie -

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ees- is ers o u o u ivs tre tes ees o u ert -

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1 I

, HVd NO* NZ-I-ZZ QVI2: 6/C5/80 d0M2H = 45:*

3ON' HOI' HJC d0SIIIONS: d - I'799 bdlE:

U g

Q EVN2 VI Z0C S12dS 3 - I*C8Z M. = I*001 I 7H 3 EVNM VI 228 S12dS 31 = T*6LS N2 = I*OOT b

.-3* = I*CLO ' S4. = T*OCC V*0* - I*CTC SI = 0*665 [

EnHNnd = Z8S E.C/EQ

?'I*I-II 1

Figure 4.1.1-9 NORTH NNA L'JI! 2 - CYCI.E 1 ASSEMI.L'ISE PC'JER DIS'1IEtt0N 90* MAP f P N M 1 E J N 4 F 1 0  : 4 a ntelerto e.sr . i.7s . s.s? . nest:7:s

. numis

. e.st . s.77 o.s . rm.i t :. . 1 ,

. t.: .

.rct curtstret. 2.2 , 1. 5 . .r:t e n rt m .:t.

. o.se , e.s7 e.97 . e.97 . a.97 . s.s7 . e.ss

. s.se . 8.e9 s.Se . S.9e. e.97 3.a7 e.s , t

. e.7 s.3 . 0.6 e.6 . 3.1 e.6 c.6

. 0.65 . 8,91 . 0.99 1.11 . i.17 . 1.11 . 6.99 . C.91 . 8.63 .

. 9.6 3 . 0.91 . 1. 08 . 1.10 . 1.1$ . 1.19 . 6. 99 . 9.92 . 0.66 . 1 4.1 . .t. 6 . 9.4 . t . 7 . 1. 6 . 1.1 , 8.6 , 4. 3 . 9.5

. 9.63 . e.86 . 1.as .1.12 1.16 .1.19 1.16 . 1.12 . 1.00 . C.t6 . 0.63 .

. 4.45 . S.85 . 1.80 . 1.13 . 1.16 . 1.19 . 1.14 . 1.1* . 1.C5 . 8.t6 . 4.66 6 4.4 . .e.4 . .t.1 3.3 . .t.5 . 0.7 . 1.6 0.3 . 6.3 . 0.6 6.0 .

. 0.8% . 9.41 . 1.00 . 3.12 . 1.16 . 1.22 . 1.15 . 1.2S . 3.16 .1: . 1.83 . .....a.91 0.53 .

. 6.57 . 8.90 . 0.99 1.16 . 1.19 . 1.16 4.12 , 1.C C 0.98 . c.60 . 5

. 1.5 1.5 . .C.9 . 1.11 4.7 .. 1.19 .t.4 .. 1.19 .o.9 1.9 . 1.1 -0.2 .O.1 9.e *.S 6.1 .

0.e7 0.99 . 1.12 . 1.16 . 1.19 . 1.29 . 1.21 . 1.23 . 1.19 S.47 .

. 8.47 . s.99 . 1.12 1.16 . 1.19 . 1.20 . 1.19 . 1.16 1.14 . 1.12 . f.99 . 4.89 . 6 6.5 . 0.5 . 4.1 . 4.4 . 6.3 . 0.4 , .1.21 t .5 .. 1.19 1. 0 . 6.6 . .t . 2 .. 1.12 8.3 .. 1.23 1.6 .1 .

. 4.57 . 9.9F . 1.11 . 1.16 1.:2. 1.:3 . 3.16 1.11.... C.9? . 0 57 .

. 8.60 . 4.99 . 1.1 * . 1.16 . ;.10 . 1.t t .. 1.231.19 .. 1.28 1.21 . 1.15 . 1. . 4.:3 . 1.16 . e.12 3.98 . 0.58 7 3.7 , 1.8 1.8 . .O.6 . .t .1 . 1.6 . 4.9 .1.16 4.4 . . 1.22 4.6 .. 1.23 .t. . 0.2 . .t.1 0.4 . 1. 6 . 1.6 .

. 0.75 . 8.97 , 1.1 ? . 1.19 . 1.15 . 1. 21 . 1.15 . 1. l e . 1.15 . 1. :1 1.15 1.19 . 1.17 . t . *? . 0. 75 .

. 8.74 . 9. ** 1.17 . 1.19 . 1.13 . 1.1; . 1.14 1.18 . 1.16 1.t* . 1.16 . 1.19 1.17 S.** . 0.77 . 4 3.6 1.6 . 0. 7 . .e. 3 . 1.5 . 1.1 . 0. 6 . -c . 5 . 4. 3 . .s > 0. 7 . .t . 2 . o.7. i.e . 2.*

. . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . - . . . . , . . ..e . . . . . . . . . . . . ..... .....................

. 0.87 , 9.97 1.11 . 1.16 . 1.23 . 1.19 . i. 11 . 4. * $ 1.21 . 1.22 . ... . 1.16 . 1.11 . 0.97 . 0.57 .

. 8.66 . 0.99 *

. 1.11 . 1.16 . 1.19 . 1.19 . 1.19 . 4.1. f. 1.29 . 1.19 . . 11 . 1.16 , 1.1r C.*9 8.59 .

• 3.7 . .5. 0.3. 0.5..i.3. k.9 . 1.1 . 1.3 0.9 1.2 1.2 4.3 . 1.* , 2.1 . 2.9

. . . . . . 0.99

... . . . ... 9.07 . . . . .. .1.1*. . . ...1.16

. . . . . .1. 14. . . .. 1.20

. . . . . . . .1.21. . . ... .1.:t

. . . ... .1.19

. . . ... .. . 16. . ... .. 1.12 . 0.95 s.87 .

0.08 . 1.39 . 1.13 . 1.17 . .s19 . 1.18 . 1.19 . 1.10 . . 1*

.1. ; 1. . . 1. 2 3 0.89 18 1.6 . 1.3 . C.7 0.6 . .t . % . 2.1 . 1. 7 . .t . 2 , 1.6 1.9 . .c.3 1.4 t.6 .

. 8.5 8 . 0. 91 . 1. c o 1.17 . 1.16 . 1. 2 0 . 1. 2 5 . 1. 2 0 . . . le . . .2 1.82 ....... 0.81 2.53......

. 0.59 . 0. 9 3 1. t 1 . 1.11 . 1.15 . 1.14 . 1.12 1.17 . 1.15 1.13 . 1.82 . C. 0.f9 ..

1.6 . 1.6 . 1. 3 . s.4 . 9. 9 . .t.t . .t .2 4.4 . 1.6 S.= . 1.s t3 1.L

. 8.63 . 4.46 1.00 . 1.12 . 1.16 . 1.19 . 1.16 . 1.12..... ..C3 . C.46 . 3.63 .

. 4. . 0.8 7 , 1.9 ; . 1.11 . 1.1+ . 1.17 . 1.14 . 1.11 1.:: . C.67 . C.et . 12 1.9 1. 3 . 8.? . .e.0 , .:.6 . .t.6 . .t.s 1.1 8. 3 , 2.0 2.7 8

. 9.6 3 . C . 91 . 8. 99 . 1.11 . 1.17 1.11 . e . *9 . 0.91 . 0.63 ,

. 0.61 . 0.4* . 4.s t . 1. 0 9 . 1.15 . 1.10 0.93 . 3.e) . C.6 5 . 11 t.3 . C.7 . 8. 3 . .t .1 . 1. 7 . 1.1 . = 0.5 . 2.0 2.4

. 4.$s . 0.47 . 6.97 . C 97 . c.97 . 6.8? . c.f t .

. 8.89 0.90 . 0.93 . S.96 . 4.'6 . 3.46 8. S$ . 16 2.1 1.6 . 1.1  ; 1. 0 . .d . 6 0. .

37110a7C 3.5? . avNC........ .

.. .P..5.7 o.7. . 0. 75 0. 57 . .r:t enum:1 tl

. Ct.v:m.

0 :i 6.. 1. 7 . . . a .. - 1.:

MAP NO: N2-1-24 DATE: 10A 3/80 Power = 87*.

CONTROL ROD POSITIONS: F = 1.443 OPTR:

Xy 6 N

D BANK AT 189 STEPS F =

1.349 NW = 0. 997 4H T

• C BANK AT 228 STEPS F = 2.014 NF= 1.002 Q

Fg = 1.423 S*J = 1. 003 A.O. = -11.810 SE = 0.998 BURNUP 1 645.0 L'D/MTU 4.1.1-12

1 1

I Figure 4.1.1-10 l

NORTF. ANNA L%IT 2 - CYCLE 1 ASSEM3LYWISE POWER DIS *RIBUTION 100*'-APOM MAP

1. e N M L R J n 6 F t a C 6 A pettlefte . ..se . e.76 . 8.se . reto:: ten

. real. In . . 0.59 . 8. n . 0.ss . . enr.n: . 1

.ra strnettet, t.7 . 2.7 . 1.2 .r:7 czrnsvet.

1.as

. . . . . . .. .0 ...................

. 0.57 . 0.46 . s.t. . . s.86 . a.57 0.5s .s.u . 8 u .1.se. 0.9e.s.u . a.s7 2 e.7 . 1.6 . .6. 0.6 . -e .1 . -e . ) . -e.3 ,

. 9.61 . 6.91 . 0.98 . 1.11 . 1.17 . 1.11 . 6.9S . 0.91 . 4.62 .

. 0.62 . 0.99 . 8.98 1.12 . 4.16 , 1.18 . 0.99 0.91 0.62 . 3

. 9. ? . - 0. 6 4.1 . 0. 5 . *0. 7 . 9. 6 , 9.2 0.2 . =0. 3 . *

. 6.62 . 4.45 . 5.99 . 1.12 . 1.16 . 1.19 . 1.16 . 1.12 . 0.99 . 9.45 . 9.62 .

. 0.62 . 8.to . s.99 1.12 . 1. l e . 1.19 . 1.15 . 1.13 . 1. 0 2 . 8. 8 5 . t .6 3 . *

+4.4 . *0.4 . -0.2 , 0 . 2 . -0. 3 . -0 . * . = 0. 4 . 0.9 8.9 . 1.8 . 0.7 . *

. 0.S7 . 0.91 . 0.'9 . 1.12 . 1.17 . 1.23 . 1.13 1.20 . 1.17 . 1.12 . 0.*9 . C.91 .57 4

. *1.4 5.56 . 6.ti . 0.9* . 1.11 .

. *1.4 . -1.8 , -0. 7 . 1.16 . 1.20 . 1.!* 1.20 . 1.18 . 1.17 1.80 . B . 91 . 0.5 8 . 5 i

. -4. 5 , -0. 5 . 0.6 . =0. 3 . 4.7 . 0.7 . 1.0 , 0.7 . 4.7 .

, 4.46 . 8.*S . 1.12 . 1.17 . 1.22 . 1.21 . 1.21 . 1.21 . 1.22 . 1.17 , 11: . 8.*6 . 9.46 .

. O.47 . 0.99 1.1: 1.17 .1.!: . 1.01 . 1. 1 . 1.21 . 1.33 . 1.17 . . 11 . 1.93 . 0.47 . 6

4. 7 . 8. 7 . 4.2 -0.4 . 0. 0 . -0. 2 . -0. 3 .

• s .6 . 0.6 . c.1 -3.1 -0.1 8.* .

8.5* . 8. *e . 1.11 . 1.16 1.t1 .1.25 .1.t1 . 1.21 . 1.22 1.16 . 1.11 . 0.98 . 0.53 .

1.59 0.99 1.12 . 1.16 -. 1.11 1.20 . 1.21 1.20 1.21 . 1.16 7 f.1 . 1.5 1. 3 . - 0 . 2 . - 1. 6 -1.0 -0.3 . -0. 6 . +0.3 1.11.. 1.21 6.0 .. 1.29

-e.5 .. 4.15 -1.0 . 1.11 9.6 .. 8.99 .3.. 0.59 2. 3 .

. 0.76 . 1.00 . 1.17 1.19 , 1.15 . 1.11 . 1.15 . 1.19 . 1.15 1.21 . 1.13 . 1.19 . 1.17 . 1. 22 . 8.*t .

. s.?f . 1.61 1.16 . 1.19 1.14 . 1.21 . 1.15 . 1.19 . 1.19 . 1.21 . 1.16 . 1.19 . 1.19 . 1.t2 . 0.78 . 4

.1 . 1. * . 1.0 , C.2 . 0.7 0.4 , 0.2 8.1 -a.3 . .a.5 -1.0 -1.0 9.7 . 2.2 3.1 .

, 0. $ a . 3. 9 3 . 1.11 . 1.16 . 1.21 . 1.t1 1.21 1.!* . 1.21 1.21 . 1.;S....... 1.16 . 11 . f. 99 ,..................6.56 .

4.59 . 0.98 , 1.19 . 1.15 . 1.*0 . 1.28 1.22 , . 15 . i.21 . 1.21 . 1.11 . . 1.9 1.1* 1.33 . 0.59 9 2.1 , 6. 5 , - 0.+ - 4.5 . -0. b . - 0.4 , -1.4 . -0. 3 . -C . ) . 4.5 -1.0 - 3. 7 . 1.2 , 1.9 . 3.4 8.26 . 9. 9 5 . 1. ! ! . 1.17 . 1. ' t . 1.21 . 1. 21 '

f. . 1..Z . 1.!? , . 12 . 9.9: , D.*6

. 9.26 . 0. 7 3 . 1.1 . 1.14 . 4.23 . 1.1* . 1.23 ..;3 . 1.22 . 1.16 . 1.13 . C . 95 . 4.44 - 10

-0.1 .t .1 . v.7 1.1 9.2 . -1. 8 .

• 1.1 1. 3 , -0.6 , -0.9 . 9.9 -0.2 1.4

. 9.57 . 0.91 0.99 . 1.12 1.!? 1.29 . 1. i 1.29 . 1.17 . 1.12 c.'9 . f.91 0.57

. 8.57 0.91 1. C 6 . 1.1 * . ; .16 - 1.18 . 1. ! t 1 ;5 . 1.16 . 1.1: 1.51 . 0.9: . 8.58 . Il 4.2 S.! 0.7 1.6 . 0.5 - 1. ' - 1. 9 . 2.2

• 0. 7 . 8.6 , 1.7 1.4 . B.6

.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... .. ..... ...... ............ j

. 0.62 . 6.!1 . f.99 . 1.lt . 1.16 1.19 ..46 . 1.12 0.99 . s.e3 8.4 .

j

. 8.43 . 0.45 . 1.31 1.11 . 1.14 . 1.17 . i. 9 1.11 . 0.99 . 0.:. 9.66 . 12 i 8.5 1.1 . 1.6 . - 0.1 . -1.1 , . . 1.9 . -4. 4 . 8.2 1. 8 . 2.1 .

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...... .. j

. 0.62 . 0.91 . C.*3 1.11 . 1.!' 1.11 . S.62

. . 1 . . 9: 0.... 1. 9 . . 15 3..9,7 G 9 .. 8.0.'.1

! . e.6- . ui 1.8 . 1.6 9. 2 ,

• 2 . 8 . -1.7 1.39

-1.6 . -1.1 8.9 .  :.2

. 0.57 . 4.86 . 0.80 . 1.30 . 8. 95 . C .4 9 . 6.37

. 8.54 . 0.44 . 0.9t 1.*1 0.96 . 0.05 . 4.57 14

1. * . 2.6 1.0 6.2 -1.= . 1.1 .A.1 Ma'Ose? 6.38 . 4.76 . (.99 . . avreast 8.60 . C . 77 6.6? . 15 li.vlaf

. 72 8t?f 3. . I s . 1.3 .r:7 C.IFF 0.9ERDCI MAP NO: N2 25 DA2E: 10/12/80 POWER = 100*

CONTROL ROD POSITIONS: F = 1.454 QPTR:

D BANK AT 228 STEPS FN LB

= 1.366 NW = 1.000 C BANK A! 22S STEPS FT = 1.959 NE = 1.003 Q

_.F

- 1.'370 SW = 1.001 A.O. -7.601 SE = 0.996 3URNUP = 701 F.JD/EJ 4.1.1-13

37S ma ;'I*I-II NOEIH YNNV SNII ; - DDI*2 I i

VSS3XEIN.?ISI dO.f2E CISIBIEn 'ION

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4.1.2 RCCA STATIC ROD DROP TEST An RCCA Static Rod Drop Test was performed in order to demonstrate the response of the incore and excore instrumentation to a power maldistribu-tion caused by an RCCA moving below its bank position, to verify the accuracy of the physics models used in the analysis of the dropped rod accident, and to verify that the rod worth value and the nuclear enthalpy rise hot c,hannel factorvalue,FfH,usedintheaccidentanalysisareconservative.

With the reactor at approximately 507. power, a measurement was made for one dropped rod, RCCA D-10. This control rod was chosen because calculations had predicted that it would cause the most restrictive hot channel factor value(9) . For this test, a base case flux map (N2-1-12) and thermocouple map were taken with all control banks approximately fully withdrawn. Upon completion of the base case flux cap, the selected RCCA was then inserted from its bank position to O steps during a slow RCS dilution. The core reactivity changes that occurred during this RCCA insertion /RCS dilution were continuously recorded by the reactivity-computer in order to obtain the rod worth. Periodically during the RCCA l

insertion, the axial flux shape was measured by making a single pass through selected chimbles with the movable incore detector syste=. With the selected RCCA fully inserted, a movable detecter flux map and a thermocouple map were taken. Upon completion of thi.: flux map, the -

dropped RCCA was then withdrawn during a sic RC5 boration until it vas realigned with its bank. Again, the core reactivity changes that occurred

during this RCCA withdrawal /RCS boration were monitored via the reactivity 1

i computer.

I 4.1.2-1

Table 4.1.2-la su::carizes the dropped rod reactivity worth measured during this test. As shown in this table and in the Startup Physics Test Re-sults and Evaluation Sheets in Appendix B, the =easured reactivity worth cf RCCA D-10 was within the 115". design value tolerance of its design prediction and is very conservative with respect to the value used in the accident aralysis.

The results of the analyses of the flux =aps are shewn in Table 4.1.2-13 and in Appendix B. As indicated, the values of the nuclear enthalpy tiae hot channel factor, (H, were satisfactory with respect to the design predictions and the value used in the accident analysis. Figures 4.1.2-1 and 4.1.2-2 show the resulting radial power distributions and the comparison to design predictions determined fro = the base case and dropped rod flux maps. As indicated in these figures, a highly asy x:stric radial flux distri-bution was produced during this test. The deviations of measured power distri-bution data from design predictions are somewhat higher for the dropped rod flux map than for the base case flux =ap, but are typical for such highly asym-metric power distributions. Figures 4.1.2-3 and 4.1.2-4 provide an illustrative aa=ple cf the thermocouple data obtained during the test. "he thermocouple map in Figure 4.1.2-3 was obtained prior to dropping RCCA D-10 and the ther=o-couple =ap in Figure 4.1.2-4 was obtained with RCCA D-10 fully inserted.

Taese figares c.lso indicate an as rusetric power distribution resulting frc=

a dropped RCCA.

Figures 4.1.2-3, 4.1.2-6, and 4.1.2-7 provide an illustrative sa=ple of the axial flux shape r.easure=ents taken from Thimble E-11 during this test.

These figures illustrate axial fluz shapes with RCCA D-10 at 228, 121, and 83 steps, respectively, and indicate the incere detector response to a gross red misalignment.

4.1.2-2 1

A streary of the excore detector response during the d:cyg,ed rod test is shown in Table 4.1.2-2. As indicated in this table, the excore detectors were able to detect the asy :cetric power distributions associated with the abnomal rod configurations.

4.1. 2-3

NORTH ANHA INIT 2 - CYCI.E 1 BOI, PIIYSICS TEST

SUMMARY

OF DROPPED ROD CASE Table 4.1.2-1A Integral Worth Power Bank Position RCCA Integral Reactivity level (eteps) Worth (pen)

(%FP) RCCA C D Measured Predicted Di f ference(M-P) Accident Analysis Value 51% D-10 228 213 110 107 3 250 Table 4.1.2-1B Flux Hap Pesielts Power Rank Position Eg . Nuclear Enthalpy Rise Flux Imvel (Steps) liot Clutnnel Factor Map (%PF) C D Measured ' Prc,11 c r o,1 Di f feren ce (M- P) Accident Analvain Value

, D-10 Bane Case 51% 228 214 1. 41 6 N/A N/A N/A

, (N2-1-12)

D-10 Dropped 51% 228 209 1.675 1.70 -0.03 1.69 (H2-1-13) a N N F,=Fg x 1.04 where 1.04 - Heasurement Uncertainty Factor b

• Westinghouse predicted value , letter FP-VR-140, June 15, 1978.

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4.4.1 NUCLE AR AND TEMPERATUPI INSTRUMENTATICN CALIBRATION AND THERV.AL PO'4ER MEASUREMENT This tes t was actually a collection of several tests which required extensive data collection during plant startup. The various tes ts were therefore . combined into one large tes t for ease of data collection and control of the various alignment procedures which were included. This tes t covered the initial alignment of the nuclear ins tumentation, process temperature ins tru-mentation, and the feedwater and steam flow instrumentation either prior to critica-

. lity or at hot zero power conditions. During power escalation, steady state ,

performance (statepoint) data required to calibrate the various systems mentioned above was collected at the 30%, 50%, 75%, 90% and 100% power plateaus.

This data included thermal power determinations, plant pressures, feedwater flows, primary loop temperatures, nuclear instrumentation readings, and the related process instrumentation signils for the above parame ters. In addition, following the s tatepoint data ceasurement, 4 full core flux map was taken to verify core performance during power escalatitu (refer to Section 4.1.1).

A summary of the statepoint data obtained from this tes t is given in Tab le 4.4.1-1.

4.4.1-1

4.4.1.1 NUCLEAR INSTRUMEh' RATION ALIGNMDTI Prior to initial core loading, the operating plateaus for both source range detectors were obtained and the operating voltages were established. This measurement was repeated following the trip from 507.

power to verify no shif ts had occurred in the detector characteristics.

Just prior to initial criticality, a final alignment check was performed. Overlap data was first tfren during initial criticality when the intermediate range channels reached approximately 10-11 amps. The intermediate and power range overlaps vere monitored during the initial portions of the power escalation. Hewever, due to the conservative gain settings used for dhe power ranges, a realistic overlap was not obtained until 307. power following plant calorimetrics and the subsequent gain adjustments of the power ranges. The everlap data is presented in Table 4 . 4 .1- 2 .

From the statepoint data collection, the detector currents for each power range were plotted versus power to verify linearity. These plots have been provided in Figures 4.4.1-1, 4.4.1-2, 4.4.1-3, and 4.4.1-4. The results indicated that all four power range detectors responded properly.

4.4.1-2 l

Table 4. 4.1-1 STATEP0lNT DATA StHtARY Platean 30% 50% 75% 90% .100%

Calorimetric Power (%) 30.9 49.8 75.0 87.3 98.6 4

CD Position (Steps) 146 180 227 198 228 '

Tavg ( F): Ioop A 554.1 561.9 571.6 575.0 '579.4 Inop B 553.9 561.3 569.9 574.7 578.9 Toop C 554.1 560.7 570.6 574.1 578.4 AT ( F) Ioop A 21.5 33.2 47.9 54.8 61.1 Ioop B 21.3 33.9 51.3 55.4 61.8 Inop C 19.5 35.3 48.1 55.I 60.9

), Steam Generator Pressure Toup A 896 880 867 340 836 (pS18 )

loop B 893 900 870 840 832' foop C 893 883 867 840 830 4

Feedwater Temperature ( F) loop A 171.1 376.3 414.7 424.1 436.2 4

Inop B 171.2 376.4 415.0 424.6 436.I l Inop C 171.3 376.4 415.0 424.H 436.I 6

Feedwater Flow (1h/hr x 10 ) I op A 0.92 1.86 2.97 3.48 4.02

. loop B 0.87 1.87 2.93 3.46 3.98 foop C 1.01 1.88 2.95 3.48 3.98 l

i

Table 4.4.1-!(con'd.)

STATEP0lNT DATA SIMtARY F1ateau 30 % 50% 75% 90% 100%

Turbine Impulse Pressure (psia) 169.6 301.7 478.7 489.7 571.0 Power Range IV t ector Currents (namps)

N41U 75 121 185 210 235 N41L 120 175 258 296 335 N42U 82 135 205 232 259 N42L 114 165 244 280 316 N43U 75 122 184 208 232 N43L 115 170 253 290 327 n

c N44U 82 136 209 236 264 w

1 N44L 116 172 254 291 330

Table 4.4.1-2 NUCLEAP, INSTRLHENTATION OVERLO DATA Source Range Critical 30* Power Plateau N31 1.2 X 10 cps OFF N32 1.3 X 10 cps OFF Intermediate Range N35 5.1 X 10-11 a=ps 4. 9 x 10 ' amps N36 6.5 X 10' amps 4.3 x 10 ' amps Power Range N41 0% 32.7%

N42 0% 32.7%

N43 0% 32.0%

N44 0% 32.0%

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4.4.3 INCORE - EXCORE DETECTOR CALIBRATION The nuclear power instruments contain a nu=ber of isolation ampli-fiers which produce an output proportional to the currents obtained fro = upper and lower neutron detectors. These signals are used for axial flux difference (LI) indication, upper and lower quadrant power indication, LI monitoring by the process computer and the genaration of the f(iI) function incorporated in the overtemperature LT trip setpoint. Because of differences in detector sensitivity, placement, and the detector-to-core coupling, each detector =ust be calibrated to produce an excore indicated axial power distribution which accurately reflects the incore conditions.

Prior to the perfor=ance of this test at 757. power, an initial cali-bration was performed prior to exceeding 507, power using data obtained from previously obtained flux maps. This was done to co= ply with Technical Specifi-cation requirements and to provide at least a rough calibration prior to esca-lating to higher power levels. The measurements carried out at 75% power were performed af ter an evaluation of the T,yg progra= at 507. and 757. power was completed. The initial implementation of the T,yg program was satisfactory and further adjustments were deemed unnecessary at 507., 757, and 907, power.

The Incore - Excore Calibration test consisted of taking a series of flux maps at different values of AI. Concurrent with each flux =ap, plant calorimetric and power range detector current data was obtained. In order

, to obtain a wide spread of AI values, rod position was varied to obtain a 157. range of _I values. A reference full-core flux =ap was taken at approxi-mately the target aI value, then rods were inserted until LI decreased to its negative limit where an additional full-core flux map was taken. The results of this flux map were used to establish a new target al value which was approximately 47. more negative than the previous target value.

The rods were again inserted until AI was wichin 17. of the new negative 4.4.3-1

i ihmit where it was maintained for approximately four hours. Following this period, a third full-core flux map was obtained. The control rods were then withdrawn in order to induce a positive AI swing. The AI then increased and slowly approached a positive peak due to a xenon oscillation created by the rod movements. Special Test Exception 3.10.2 of the North Anna Unit 2 Technical Specifications was invoked in order to allow LI to exceed the positive lh=it fcr the purpose of obtaining a wide spread of AI values. At the positive peak, a final full-core flux map was taken.

Analysis of the flux maps yielded values of the actual core axial offsets (AO). The axial offset, which is a measure of the relative powers in the upper and lower halves of the core, is related to LI by:

LI = AO x fractional power. Therefore, the LI at 1007. power is equal to the axial offset. By plotting the measured axial offset values versus the ,

detector currents normalized to 100% for both upper and lower detectors, the incore-excore calibration curves are obtained. Figures 4.4.3-1 through 4.4.3-4 are the curves obtained for this test.

For each detector, the data fram the four full-core maps were fitted to a linear function by the least squares method. The currents obtained by evaluating these functions at zero axial offset yielded the calibration currents. Evaluation of the relative detector currents at different axial offsets yielded the voltage differences between the upper and lower detectors seen by the process instrumentation. This data was then used to align the f(II) function for the overte=perature iT trip setpoints.

During the aI changes, a series of quarter-core flux maps were taken to provide data for comparison with the full-core flux map results.

The AI values from the quarter-core maps showed good agreement with those frem the full-core maps. Table 4.4.3-1 illustrates the agreement between 4.4.3-2 l 1

1

the expected detector current values and the measured values for quarter-core flux maps 16, 20, and 21.

i I,

l 4.4.3-3

Ta m 4.4.3-1 P0k'ER PJdGE DETECTOEJU?..*jNT$ (EXPECTED VERSUS MEASURED)

FOR OUARTER-COP.E FLUX PJJS 16,20, A'!D 21 Normalized Measured Expected '

Map Detector Detector Currents (uaeps) Detector Currents (;. asps)

Number I.D. Too Bottom 1 Top i Bottom N41 247 348 247 346 N42 272 329 273 328 N2-1-16 N43 246 341 246 340 N44 279 344 278 342 N41 241 333 248 344 N42 267 315 274 326 N2-1-20 ,

N43 240 327 247 339 N44 272 329 280 340 N41 248 327 254 337 N42 276 310 281 319 N2-1-21 N43 246 322 252 332 N44 280 324 287 332 1

4.4.3-4 I

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4.4.5 PROCESS COMPUTER During power escalation, comparisons were made between process signals and those assessed by the PRODAC-250 plant process computer. At the 307. and 507.

I ' power plateaus, selected computer addressable points were obtained and compared to the equivalent control room indication. All values obtained were found to be within the instrument accuracy guidelines furnished by Westinghouse.

At the time of the writing of this report, the process computer evaluation had not been completed at the 100*' power plateau. A description of t

this test will be included in the overall Startup Report to be written by North Anna Power Station personnel.

e s

}

I 4.4.5-1

F

5.0 REFERENCES

1. T. K. Ross and J. E. Leberstien, " North Anna Unit 1, Cycle 1 Startup Physics Test Report," VEP-FRL-31, September,1978.

2. North Anna Units 1 & 2 Final Safety Analysis Report.  ;

3. M. C. Cheok, " North Anna Unit No. 2, Cycle 1 Design Report," VEP-FRD-NFE-106, February, 1980.

4. " Technical Manual for Westinghouse Solid State Reactivity Computer," [

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

6. D. J. Miller, "The Nuclear Design of the North Anna Power Plants (Units 1 b and 2, Cycle 1)," WCAP 8747, March, 1976.

7. North Anna Power Station Unit 2 Technical Specifications.

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

9. Letter, Vepco (C. M. Stallings) to NRC (Earold R. Denton), North Anna Power Station-Unit 2, Modified Startup Physics Testing Program-Supplenental Information, Serial No. 314, May.2, 1979.

i

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5.0-1

.-._...__m_.____

1 APPENDIX B NORTH A'iNA UNIT 2, CYCLE 1 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEETS e

v --y

b3 2-SU-17 rA.Al.Ir,h 'I

.% h" *i*v%4 . :- ! ." -

03-24-20 Page e, c_, 6 A"';AC-CC::T 6.2 e

s

!!cith .u... l'ast.;; 5:::Irm tl:1: 2 Cycis .t 0:artup .

f F

C::::up Thysics 7:s:s T.c ul:s and Evalu:1 * = Shes: ,

t

! Tes: D::::1?:icn: Re:c:ivity C =7u::: Check:u:

Referenec  ?:scedurc !! uric /Sectica: :.s -17/ App. 3 Sequence S:cp I;ua'ac

• 9 0 5 t

i U  !.:=h Posi: ions (::np=) KZ Tc= par::ure (*2'):5f.7

~3 7::: Power Level (27.P.): 0 Conditi::: C/.: 2*S 003: ::S CA::3 C:her (:pe:ify):

(Oasi;:) C: 2*8 CO: 23 C: e 3elow ticciaa: Esa:1 ; .

• A: :Me f r.s: e ' ::31 - e. i tt -.- .*

I l

ZI 2 ..h ?::i:i=ns (s::;s) Z:3 T =7e:2:: e (*7) : 61/[ '3 [

! Tes:  ?:va: I.cv:1 ( 7.?.): O Coadi:10.s "A: 225 C3: 2.1 S CA: ~2.11 . C:ha: (:pe:11;):

(A :::1) C3: 2.1 i CO: 1 J.1 C: /.$"(,

m ux Brw Wvu2At na!'Ar>WG- 7

• • t y 0::e/Ti=c Tes: (.,//3/TO' .

?: for==d: o 32 7. o 3 33 -

": - Y.easured ,reae:1ri:7 csi:s :he :tactivity c==:u:a J Messur:d ?:::=.::e (d::::1p:1:=)

, Ac; - I:!c: ed reac 1ti:7 froa reactor ea:1od l IV nassu:=-1 ve:.=

ap,--s)r e -

c,, o 2 g -

1 J 6 /r i j i-

,Tes: :esign V:1:e A8e ~ 4# l '

-< C.04

. T.e s c'.:s (i.ctu:1 Condi:icas) .

ca.

Oesi;: Value ~.A? 7905, Zav. 1, isi. 3.6 (De.:i;n Cs:di;ie:.s) 1 Kefc:4=:e NA +

r V 752.!:c:h $ pac KA '

l.:: cp .:::c Cri:r.:ia ,

F.c feren:e .

I V: ALCs/TAvce c / *T 3*A l s . a11a? Y. l k Ca-= *st: f", g / gass f;.c1 Ab W66 $!?tgisoW20 pudtW6 Thg f(EAcfo/ITY '

l l c,,,,,,,7et .-Ec o v7 15 : 55' fL!!. .

C:eple:ed By Gn . ,ej q 3,yi.,,g 3y [ j, gj[

f { /

B-1

~ '

ENAL RESULTS 2;= = ,

AO'*ACZXI:r" 6.6 Page 1 of,10 1:or:h A.: .s l' aver 5:::ima tal: 1 Cye.le 13::::up Startup 7hysics Tests Rasults and Evalustics Shee:

I Test Descrip-ion: CZICCAL 3:20N C.:C:':iTEA-.:N - AAc . t Reft cace Pr=cedure Nuader/Sectima: 2-50-l!/ App. A sequer.ce step Numbc : 4 / , fJ, , i O, Essir. Posi:1:ns (::e rs) . 705 Temperatu;= (*T): 47 "

Tes: Power Level (27.7.): 0 ~I l Condi:Lons CA: 22 3 3:3: *23 CA: 2:3 C:har (speciP f):

(:esi;;:) C3 223 CC: 223 C **5 RCCA: Ni ' ' .M13 ,

C Za=k Pc i: ions (st ss) 103 Te_perature (*7): 54.3 i Tes: Power Lave.1 (:7.?.): o i l

Co r.di:1:c.s CA.: 121 C3: 2. 2.9 CA: '22.7 C:har (specify):

(A ::al) C3: 22.S CC: 2.29 C: 2. , y a::.A: NA ,, *'.

. . Sil.w Muelaa. . r- neax ng ,

ta:e/Ti=a Tas: '/ / F/FC ,

Perf:::ad: //2 3

• Eaasu:ed ? ara':::a (C3 ) b; Cri:1:a1 Eerra Conce==;a:1es J.u (des = rip tio n) . .

27 v .

.~~

P.aasured 7alue - " . -

j # 5 2.

r (7)ARD ((#" .

Te_s: resi:n Talus M

lasui

s (A:::a1 C di:1ons) 110' / 32 1 -- 2 Y ojj o rrt ,

l w

resis: Talue (C3 )" =132:  :: y;a (Desi~ C:=Li.1==s)

,7epco Repos 7t?-TI:>-31. Seste-ber 1873

, y ,g,,,,,, .lartar from C Y. 5 ="' ts(7epco) to E.1. Oe:: n(NIC),

dated *c 2. 19'9(Serial No. 314). _

7 TIA"./ Tech $;ec ( xC3 1 21.,C00 pe= .

Acce;::: e l Cri: ria r.e ,, ,,_. , j :A27 se..i== 13.2.4 - . -

l  ; .

V: h cc.e c, r\ +e r '. a. cr.e t

.pt.tnc.c 0:r.. ::s Usa g .;;,gg 7,=j ;2 14 ;teli=isary a=alysis. I e

d.3

• Q * -tos ?? f *l,,_ n's ase;l 4.e ha.l amlys;s i A

mbb C:=;ie:ed 27 e-3, vie,ee 37 r- j 2. 5

/ 7 6' ...

f

. B-2

v _. . .- _ _. . . . . . _ . .

~

\

i F NA' RESUL ,1b 2-Sc-u l

C3-24-80 A* AC*-2'.I:.*T 6. 6 Page 2 cf 10 l 2: orth * .: l'ovc 3:. : ions t'. sit _2 Cycle _? St.7: up . . . .

I Star: p Physics Tes:: Assui:: cnd Ivaluti:n Shee:

I  !=s: D :::1ption: CRITIO.A'.101:N C:::*. - RATION - E...r4 3 IN .

Xcf==:nce Procedure Ih.:=Lc:/Se:: en: 2-SU-13/ App. A, Sequer. = S:cp !! umber: fl. 22 p F.CS 7er:per::ure (*7): 547 *o3 '

II 3 cat Tosi:imas (::es=)

Te : . ?cv:: Level ( 7.P.): C Condi:Lons S A:**S S:3: *:Sg CA: 2:3 C: hor (specify):

( esics) C3: 223 C ,123 13 C3: 13 I*I " N"*1* " I***1*3

• P. COA: NA . C~ +C .

III 3:=k Posi: ice.s (s:eps) P.02 7spera:u e (*T): S.?5.9 Tes: . Power Level (37.?.): o Cenditi =.: SOA: 223 5::: 2 .S C.' : 27.S . C:har ( ptcf.fy):

(A:: cal) C3: 2'17 CC: 22.3 CO: 3 ,

IA *

. .Sejew . fdoc. lear NNir g,.

~

Cate/Ti:e Te.s: f./J 7 / Pd -

Perf===ad: 2 o/ /

Esamured 7 ara ::n.: v -

. . . . . )

(C3 ) *; Cri:1c.aL*2c :s Csmen=::stier. - Bank D 1:

(.acs.. . ,p.,. . .

IV i v -

3:aasured Valua .

// 0* O

~ -

l (C3)D ffm .. .

. Te.= : Desi n Value M, - -

Zesults (f.::u.a1 Cor.di:i .s) gg3)D / / i . ,3 .

a 2 */~~ ggm ,

~

Desi;n Value 4 (Desi:. Co=ditions)

(c }Uv. 11334:

• 77a

. 7epco ?.epor. 7I?-F70-31, Septa =he 1878 ,

l

• • "'** 14::e ft:u C.M. 3:= rs(Vepco) :: I.7.. tenten C3C) ,

. ' dated May 2, 197?($crial No. 21a).

Y ISAI./ Ipth SP4c iA:::;::,:: (h C3 g a0,0C0 pe=

lCri: crit. j .

FcfcC3CC j T5A1 See:1cc 15.*.4 -

l VI -.I ~~ @. ? ?

,,7,., is used f. firv l pa.l y s;s

• Cer:=en:: 6 Ce Cse A - -;1.:S ;c=/;7= f:: pre' * ' u:7 ::alys'.s. -

, ?C3 A c * = et * . .* r -.br e; r w ek G' y / 0

= Plated 3- [ S W.end Ef / l y.

B-3

.a, . - .. __

-- - ---. - ~

b.. .. .. ... .-

. p. , ,

p . . 2-50-lS

• .  : C3-24-80

.. . \ L '

nO' A w .. 6.6 Page 3 of 10

. /

!!c :h / ms l'ese; :::: iou '.*:i: -

2 Cycle -

• S:st:vp .

5::::vp Physic: Tests K::ul:: a:d :.1u::1:n heet .

I 7est nest:1ption: CZ::::A'. 2 K t :NC=.;7c N 3cK e ,0-nt i

Reference:

Procedure 1:us:k:/3ection: 2-57-13/4p. A Sequene: Scep Numbc;: .f f,27, e

.a II tack Posi:1.s (::r.p ) . 7.0 T =per :ure (*T): 547-5 Tcs: . Power Level (%F.7.): O C:nditic:.s (De:1; )*

CA: ~

3 C3:..S ..

CA: S Other (specify):

C3:

,gy13 C

0 +0 -

13 C:0 Below Suciaar Easti:3

- F. *.A: HA III 3:=k Ps i: ices (steps) 105 Te=pera:ure (*F): 54..O

] Tet: Powa: Level (27.7.): o * '

!Ceedi:10:s SOA: 213 =3 : *12 y CA: 227 . C:har ( pacify):

i (Actual) C3: ;,, # 3 C:s o CD: o ,

l ECA: NA

- Gelb Alvelew deseas -

c.=e/:i=a : : ' / ". / ro. *

?::fc;=ed: o 93 g -

neasurea 72:a=====

(4: c:1p: tea) (S)=,0!Ciusd2*::C*:*:

? 2^:1== - 3 *-1 C 'I=

v U****: d M ' (5)3,3- /O FO ppm , ,.

.!cs: Ocsits V:lue (C3 )C,0

=

/ O Tg e 2 d.. ggro

. Results (A :ual C0:41:10.:) - a v

resi;: Value *

• • P F *

(0:sig: C :di ians)

(C3 )C'*"

. Tepeo Rm;=:: T*T7.%21, Se::c:ler 1975

,14:: : ::= 0.M. Stalli:ss(Tento) to E.?.. Se:::: G7.0),

t':f t:e a-Lated Ezv 2. 19 79 (3eria*., '.~o . 314) .

y 73.'.'.!7c h Spe (N) 4:3

C. --e :l.,000 pe=

• Acce ::::: -

[ T.:fc:ence FIAR Sec:1== 15. .4 .

y, hece t c f.+e d u mek G = nt:

U" h~s.11.0a

= f;c=/; ute p !=  ;:al< e a:,7 ,=2:ysis.

is t: sed fev- fi a.k .1aa.ly s. 5 g * *l0 13 p o,o c==;1e 0 a n / ] ~/ f! A w .e. a n 9 . / w.,

t .

k B-4

. m_.-- .- .. s -r.,_ -- -- .

2-53-18 EiNAL RESULTS  ;;;0 1 ...

Page 4 ci' 13 2: orth /.an: l'a.rc: :::: iou l'..it 2, Cycle ,L,, 5:n :tp 1 , ,

star:up Phy::ics ests 7.esui:s and Ev lu :'s: Shent I Test Oc:::1ption: CII :".A:.

lieference 1*::cedure Numi,a:/:ec Jon 3:10:1 CONCCIT.'.A!;=03 2 5,;-13/ - 3/445 App. A ,, :;uence S::p3,C,r-pi

..wmac e y/,22, II ,

! =h ?osi:1:ss ( :=ps)  ?.05 Teeperature (*7): 547 Te : .

4 Pave: 1.evel (27...) : 0 Condi:icna SOA: ::3 3:3: ::3 CA:023.g3 Cce (specify):

(Oasi s) 5 9  : 0 ****h4

• C2:.0~0 7.00A: 5A -

III 2:sk fo:i: ices (s::: ) 203 Te=perz ure ('T): 5'.56.5" Tes:  ? cue: 1.:vcl (27.?.): o Ccadi: ions SOA: 2 2.? I:3: 2.28 CA: 2a3 . C her (spe:1fy):

(l.c::al) C3: o CC: o C:: C , .

R00A' UA . .,.

• &s l,e J k.1 Clew N;este us3 2 telitze ~es: &fr?l?C '

?c:for= d: o / .t. f-1:easu:cd Par :a:e: v -

(descriptier) IU3 )h",c,1 C:15:213erru C:::as:rs:ica - m 3,0,3-Is IV *

• 2:stsured V 1ue (c3)M . go3 1 s,C,3 '

/YM ..

• Tes: D e s i**a. V:lua "- 1:

. Rascits (i.:.*.=1 C ndi:10:s)

(s,3)M 3,C.D

= Q f .d..

w -

• f /'/' M .

Desig: Yalue

(*. }M Z 3.0,[ ,., 27' (Cesi- . Condiciens)

. .Tepes Ka;c : T ?-i?."-31, Septe=ber 19 73 gg *, ,;,,"," , latter f:c= C.M. 5:2111:ss(Te;c=) to 2.3. Ie===nCG.0) ,

. da:ad Ma7 :. 1979(Serisi re. 3!a) .

s.

• V T!!a/7c:'.. Spec * * (%) x C3 3 24,000 pcs Ac: p::::: 9 C:ite:L:. .

7.=fc;ence TSA7.Sec den 15.2.4 .

y; S c u p % rsc e er-s te rk na Cc.-:. nts Use 13, = -;1. ,3 i:: preli=1:ar7 sea;7 sis.

SC3

• IC.?! P/ l3 o gg) f,, f,,,j 34,3 e- ,:. ec ,r A* &. &m. c w ....a ,, ,

/ /^- n

/.

B-5 p

?

l r

j.,NA1'.

• • 9" ESUL i b, 2-se-u C3-24-50 l

"ATTAC2:2:r: 6.6

... - -- .. . . - - . . .. ._. ...

• se 5 ef M ..

1:o: h Aan Povc :::: ion L'ai: ,;,, Cycle _1,, Startup . .

Startup Physie.s Tc::s tesults :=d beh::1:n Shee

! Tas: Dc::::1ption: I's Procedure Nu=be:/$st:1:a: cy,: Cla 30?.03 C:: ICE 3a-*IC4kc 0't 3 ANXSCC .*-},3.C p I ca- p bt::' .4/, 2 2 g 18(trance  :-SU-18/4p. A

!! Ocak Po.*i:imns (3:ers) RC "ceper::ure (*T): 347+03 Tes: .,,o g3 Pove: Level (27.P.): O Conditions 5::A: ::3 3 :: 2 :S 13 CA:0,0 C:he: (speci.*y): ,

(Desi;:) C1: O CC O C: 0 3elow Nuclaar Easting .,

.' ?.00A' NI . ,

Ea=1 Fo:i:io .s (s::;s) 7.C5 Te= para:ure (*T): E/S". 2 .

Tas: Pows: LeveZ (T7.7.): d Condirions 5:A 2:3 5:3: 217 CA: 9 . C:'as: (specify):

(Actual) C3: 'o . . . C": o C: o .

. . 7=A:::A 6elao 4 eIda*- L E.na#

• a:e/Tiza Tas: '/ #'. / 80 ~

7c:Cc ::d: / y4 *- .

Eeasured Per==a:e 2 1,3,C, I (descriptisa) IES)M A,3,C,0. 1

&- 3 m Cac,ct: :a-do

- D IN IV v f l'.aa.sured 7:he (C)],3,g,3 3

=

yp j,),,,,

. v . .

Desig: 7.*.us Tes: (c,)-~ **3'C'D

1. pj - -+ 74. /'/"

' ?.asu'.:s (A::ual Ccadi:1.s) .

v tesi;: Yahe (C,){'~,,.3= 781C:.p;=

~

(Otsi; C: diti=.s)

. . . Tepeo la;or. C-T?.:-31, Sep:rther 1973 g ,.,. , ,

14::er fren C.Y. St "* !s(re;eo) to E.F.. ::ectenCr?.:),

dated May 2.1979(Se:1a11:c. 314) .

t.

V TSA"!/7cch pec (g x C3 ,1 24,C00 pe=

Acce;.:n=e Cri:::it. *

• Ecferenec TSA15actice 13.2.4 .

v: fece p mo c r ;ter-;a. n,e t CC:24:08 ' = -11.03 pe:/;;= f er pra-' .ary a airsis.

= ~10. ? ; Q,,,,, ;s used 4~ar- ha./ a r, a. ly s ,'s 0.-..pla ted 27 d,,A - ' bn W/ P4 viewed 2y C. d ed, w

. / V f -

B-6 g -- - p 4 --,--,,,.g.-e v ~

g :T 6.6 7 age 6 of 10 Rorth A:nza rewer ::::lec ' Uni: .,,2,, Cycle 1,,_,  :::::vp

i:i:13:h::vp ?!:yui:s Te :s :tenul:= and Ev:1 cation C7 :nt.A:.1; A;;i C;;i:7.:. A:;;;i - 5.w:cavn Je s 3 ;a .

I Tes: D::crip:1zn: .

. A Calc:c ce  ? ocedur: !!ur.he / cs' tion: ,2-57 ,8/1;;. A . . Scquene:ll5 C:her Asds cut

p :.umoc;:

Al .3 e

C

' 3 r.h Posi:1on: (s: ;s) RCS Terrper::ure (*?): 347' -5 Test , . Posee: Level ( 7.r.): Z2 Conditice.s CA: ;;3 C3: ,o- CA: da Cther (specify):

(:esien) C3: , C3 C::  : 3:

C: , ::3.+$3 Belod Nucisar v aating

.. .gc:A: -

l

• ank 7 :itiens (steps) . RCS ::rpers:ura (*7): 645 9 Tes: . Power Leve.1 ( 7.P.): o Candi:ic=s SOA: 2 ::-8 C3: O CA: 2. : 8 c:her (specity):

(A :nal) C: 7- - 3 CO 0. -8 C: 2 0 T.

7/L N k 3CA: N4 . S6t DW .NUctGh'R h N '%- -

Late / ise Tes b(19]CJO .

?arfar:sd: O '2. o *L.

Esasured 7 ::===== (g )M CIIC A:. 3;RON CON m .A ION- Sh : deva (dese:1ptics) 3 48 -e *** 3 ,.

l 3a=k .B .

3 .

' ' ~

E. sured ve za 1.E 2. 5 FM -

re.s: rest == valta Iasv.1:s (A::.:21 cec 11:1::.s) l 132, j 2 O P P.M -

%f -

Eesign 721ca 1:24 + (*g)*g - 2.3:a

• 20 pys -

(:esi;: ::di:is:s)  ; _

., . .Tepco F72 Repc : No.1 6, 7ev. 1, Fahr a.f. 193:

Laference .la::e f in c.E.5:4*lisas(Teoca) to I.R. :e::=uCG:) .

. , dated M.av 2. 1979(Se:141 !!s. 214) 80 .

7 T:A3/ ech Spe **

Ac: p.: ce 7q x C3 g .24,000 pcm Cri:::1.1 '

, . Refc:::: T:A1 See.'_:= 13. 2.4 .

yz -

A CC E.FIhN (. E C R,IT O R g MET. -

coraenes :seis. - u.03 pen/pp= for pre 1< e-. 7 ar.c3.sts, b dy s.  :: io. 87 % PFM is vsgp Feat F#at W'f .lif *.

c==,:e=a or E '. A - -e,yf . L d-

/ -

e i

, , .H.2. _ . . . . - _ . . . _ . .

- ---- - = -- -

V . . . ..L._ . . - . . _ . . - - . - - - - - . - - . - . ..-.-- - - --

- ^ 2-=-c

-fj ML RFSUD 3b -

A ":'AC*f.v.I::T 6.5 03-30-80 North Aruin Power 5::: ion I:ai: 2 Cycic _1 S: rtuPPage 2 of 7 -

I itial 3:artup Phyuies "c=:s Results and Evaluation

":.'C E 30R N C .NC.' 7./C0;i - 5 :u:=cvc sann. A ;n.

I Tes: Descrip:fon: . . .

A 1 Other Reds Cut Ecference P;ocedurc !!u:abc:/ cc:Lon: 2-30-47/4.1 ,, , .Sequence S:cp ::u n ce: g ,

+0 ,

II * ' 3:nk Positions (s:ars) RCS Temperature (*7): 547' -3 Tese .. Power Level (IT.P.): E::7 Condition: CA: :.0 C3: 223 CA: 28 Cther (specify):

~

(Desics) C3 2T3  ; 223: CD: _=36 3,;,, y,,3,,, g,, i=,

III -

Bank Paci:1 ens (s ps) RCS Te=perature (*1"): 5%+ <

Tes: Power Level (*.T.P.) : ,, e i condi: ions CA: o 5:3: t.L8 CA: us c:her ( pecify):

(Ac:ual) C3: EIS , CC: 2.24 CD: c:8 ., i F/L: M RCCA: ,,fA o '

Dw. essxt.rg. Mrprm4 . . .

, Date/ Time Tes: C//f/h Perfer=ed: ogeg

. Measured P ::= ster (c3)Eu--^"3 A _

c2.; cf * , sca:N C ::CC?A 10N - 5'r:::dow:

. (da.criptics) .

-- Bank A

!7 Eassured valua -

l u., , C) PR-s Tes: resi 2 Value .

24 sui:s (A::usi Cendi:1ess) 1Z29 t El fp.  :

. Desig: Valua 2.**3 + C) - 1324 0 ::: ppe (Design Conditio:s) 3 L _

Vepco :iTI Reper: :so. MS. w . I, rec :.ary. 1980

- ~~

.j ,,,,g, Istter f:e3 C.F...S:stM gs(vesco) to E.?.. ::enten(nc) , .

. dated P.my 2,1979(5 trial 2:o. 314) .

V TIA2/ Tech Spec fxC3 b 1 24.C00 pen Ac:cpt:nce

'Criscri.: . I

. . Refere::e TSAR See ion 13.2.4 .

VI g /hc:* $7Att i'4W MET , ,

Cornen:s Use 4:3 =-11.C3pe=/ ppa for preli:1:ary a alysis.

7E > - /.= 87

• m o ows de nw k cu pie.ee my epC-// Md / as. eve. sy Cd ~j C_. . - -. l. '

e l

B-S m.-. --.r ---

, y_,y , . - ,

~ .

- - ..  : sy- Cfto nNA_ RESUL1b, ca-:4-w c--ni ATTACO!I2;T 6.4 gg Paga 1 Cf f g f*. ~" , r,.cti

. .. e Z .

flerth t.a .: l'=ver 5::: ion ::1: 2 Cycle 1 Startup Startup thysics Tests Resu*.:s a:d Ivalus:ia: Shee:

)

. I Test De=cri;:ba: CONTRO: 310; D *.4172 !"AS"RD'. INT Refer:nct: Procedure N.ataf/ 4ction: * -% ' +2*T2-

. , Sequcace $ cp Nu=ber: 41JZ .*

o r ,vrar,= .2, f 12 vz.vN l +

C* 4 2:=k ? :1:1:ss (:::*=) . RCS  :=? :::*.::: (*?) : 547 .03 Tes: I 7cwc Levt! (l'T.P.): O Conditic=s 51u :3 S:3: 2:3 CA: 2*! C her (spctify):

(Design) 03:,, 2 3 CO: 223 C : =cri:3 3elow Nuclear Hea:1; .

70 ".A: Ei .

IC 3ack Fo:i:ie:s (s:::s) ACS Te. perature (*7): 540.S T Tes: yover Level (..7.y.): , , ,

Condi: ions C.u 2 ZB 3:3: ZZS CA:7. S . C:her (spe.cify):

(Ac:ual) C3: 2.,23' C:: q C3: e.,wn:r.,

m. H* .. W sia: 2s # W '4

~ fa:e/*i=a Te.s (,//SBo /

Perfer=ad: g3) ,

Eaasurad Parz=a:e .#

(dc.gerip tics)  !) ; :::egral c o::h of caat:31 !a .k D I7 Eaa.sured7.Cde.

• l 3 l4*M -* B*/'7

!ss: Desit: 7:lue ,

7.e sults (A :u.a1 Co:ditiens) '3 " f % 3 7.//C p ,

ssig 7alue I) = p632110 pcm

( esi;n Cc:di:1==.s)

Tepco 14;=r: 7I?-720-3 * , Se s t a=t e r 19 73 g,f,. ,, lat:e: fre= C.M. 5:alli ;s(ve;co) to 1.1. Ce====C 20),

da:ed Mry 2. 197*(Serial No. 314).

L* Oest;; A::e;:a:.:e C;1:eric is ex:eeded, assure ade-7 75A'JTech Spec qua:e shu d .= Ws &/or evalu.a:e other at:ide::s, Accept:::: 12 m e-e s sa n .

Criteri: 1,e::e from C..r. 5:al:i=gs (ve;co) to E..G. C :e g.;R:)

?.alerence dated May 1.1, 1973 (serial so. 272). .

VI Amenw.E cc rr.A mey-

• • • ~~~****

Im,g>, e;ss wecr> wer.t cer'r. ~c sur:NG 2CS,r m +cvarr W usuas ,_

.$9.zo mrzm ec putre ,wrrew us Ho 2-60-81. Ims cnwst as pactosw m

%ses .^ !s I c-t 7- To- 20 1.:ed n -}f e /.e/- 2e, . n c..j/

B-9 . ;- . .

e m-

J

." O

%, p]? 1 2-SO-it D6*** *

= 03-24-30 fp" s rJ.:f, A= ACE.W : (.4 Lf 4!20

' Page 2 cf -+-

s S North t.r.: P:ver 5::: iou Uni: -

• Cycle 'l -

5:artup 4

S:artup Thysics Tests Kasui:s a:4 Ivaluation Shee:

i . .

Test Dc cri-tion: C::: 20:. 32"4 C ".C4 MZAS*."F.Cd: 7 - 3A*.*4 'O - IN Raft encu Procedu = h her/see: ton: *-3C N h em Seqvtace .J = o %3:sp *.5 .,Waber:4j. .a 7'

• o It:. f m .

• II 3 k ?esi:i=ns (s:ers) RCS Te=peratur: (*7): 247 +03 Tc.= = 2ever Level (27.P.): O Condit.imes .T.: 2*S 5:3: 22S CA: *03 . Other (specif/):

(Desi;:) C3 2*3 C mvi 3 C: 0 Below suciaar Esa:1:3 .

P.C A: :W .

12 k 7:si fess (s:c;s) RCS Te=pera:::a (*7'):5 *rb-3 Test Power Level ( 7.P.): o.o Condi:i::s CA: A~s 5:3: 2*E CA: M ~

. Cther (specify):

(A:::al) C3: :'.: f5

~

CC: MoviN A C: C

• NA* how woe. .cAe uxTW4 k Ca:elri:n iss: bl'2l% -

i .

?erfex ade Io 3 5' *

• l Esasured 74:ame:e: Ig ; :::egral '.*cith of Cen:rol 3ack C *

(descrip:i:=)

I  ;

):c.asured Yalue' I C

• 3b b** '

i ..

. Cas: Desi:. 741ue I C

13 C '3* Y N b"

• Rasalts (t. :: 1 C :di:1:ss) *

< a l.

• resi; Value !g - W3 S3 ;c:

(Oes1:;r. Conti:icas) vepco Reser: c-T7_%31. sesta.:bar 1973 l*

• gg , ,,.,,, '.4:ter fees C.S. S ta111:ss(vesco) to E.1. Oe :en(nc) ,

A:ad May 2.1979(serial !:o. 314) .

Cast = Ac

• e;::::e Criter:ca *.a exceesec, assure aca-j 7 '

FSA.L/ Tech Spet qua*e s M dr.m 22:36 Mor eval:a a o-her assida *s, as neussa:-r.

3 ,p;gge, ,,,

, Crite *- ' e:: : ft : C. M. Stalli.:ss ( epco) to I. C. Case (:.'20) 7.aferc= c dated P.ay 11,1975 (Serial No. 272). .

y; M c. E.FT PrNC.E c.R r G.e, i A ge y, W'* .

) 02::'- :*: Ik:Ds vi 3 v % s.sw g, wec: ng g, w en,g o gmg Qg g g;,3 R,o u M::s trio 4 U.t. m a. =.. so . :.e s w s.,s e e,. h E. % b u rio N \LS14 6 2-4 0-9 <

WIS OW c 15. Xse-c. e,Ccp m Oswrys,J we. t m o n ::. ..Su - 2 o .

pn e W . . -'

i

=pleted 3y s) k

• C W .

• 7.evirsed ?y C. Nwe d

i B-10 i

i C y/%  ;\ ' M-Q} "" C :o s., ,i* m e $0 1 J..) t JMvV- d 1,'

2-SU-7+

03-24-2: tG,  !

Ar:Ac m : 6.4 Page3 ef=6.5~

6 /a/e.- <

. . .  ?

Nor:A !.w. 7:ver ::::ica Usi: - 2 Cycle 'l S:. . :up .

5tartup Physic.s Tests Kasults and valuatima Sh'ee: ,

. t

• * . t

, I Test te:=ription: c32:*.3&43*M 2MT.u F " - IAM C, D - 3 , l' Xcf : tace F ncedure Numht;/see:lon: 2-S~-M f*T3

.:L o DewimSequesteo.4 S:cp Number:NS i..#5 st w w . 4 . ~= Q ,

j . f RCS Te=per::ure (*T): 347 I taak Positiens (5:e-=) f Tcs: yover Level (:7 P.):O h candi: ions 5:A: 2:3 s:3: :*5 CA.: 2 1 C:her (spacify):

( esi;=) C3: movd :s CC: O c:0 3elow Nu 1sa: Esa:1:3 .

1 RCCA: NA . ,

r i

C* Bank Posi:fo:s (s:cos) 7.03 Ta=pers:ure (*7):.545*8 Tas: Power Level (27.?.): O  !

Canditioca s:A: ?79 s:3 's.: 8 CA: 7. : T . C:hs: (specify):  !

(Actual)

• C3 M *8' N (1 CCi d C3: e  ;

3.::A: gr, Seto9 w uc c.ac. ,Be** A - -

l

4

e/Ti=s Tes: D/W -

Perf=:.ad: C.:.225 '.  !

i Haasured Pararater I3 ; !s egral 'Jorr.h of Con :a13ank 3 .

(descrip:13 ) _

r,'

? P.sasu:ed v 1um i3= A co't f c wi . ' . ,

t Tes: :esign Value I3* g.o jQ, g .15.3 Yr" M -  !

Zesul:s (Actual Condi:1:ns) - .

i t

t Design Value I 3

= 2036 ! 133 pcs (Desi;: C :di:1 css)

- Vepcs Raper- f:7-T"'.D-31, Septa =ber 1971 g,g,_,gg, latter f ca C.M. 5:alli=gs(Tapco) :: E.1. Oe:::s('?K ) ..

- ' dated May 2.1**9 (Serial No. 314.

L! Ger.Ns A::aptance Criterion is exceeded, assure ade-

• Y ygap,,v e:h Spec qcate shu:dow: =argin &/or evalua:e a:har accide::s, '

Accep:::. as mes*an.

C.-iteria Le::e f:ca C. t'.

. 5::111:ss Ciepco) == T. c. Case (:C)

~

• y ge;,.,ge dated May 11,1978 (Serial No. 272). ,

T- bC ( E ~F"I'b*dCiE. CR. TE a:. t8 , M EI' .

(c ... I N DI V LDu f.q,, _% g ggLTH S wtthat6 OE.T"As s44p, ytJe:g % RC-S b%W N ' N 'd W'M . -5 0-10 * ** G r.":frp DF Djafew3 De t.Wo ta $ 1*%

1

• SV

• I9 NIS C*e a .r f 15 p vol&Eb i e >ead i ATio N e45. I 58 pet. "i *.S O - 2."D .

C_ ,:e d 27 N bin . 7 ,ne,ed ir c.f L a B-11 y - -- - # r +--e c w 'T 7. --- " -v m

. .. . j e 2-sy.yf "  % *.L de.1 C { 03-24-80 .# 82

' /' .#-

k-. A"' TAC"CC.*"' 6. 4

• F' Peet 4 of Ed*

~

North t :.ns Power 5:::1cu Cat: 2 C ycle *1 5::::hp -

Start p 7hysics Tas' s Rasul:.s and Iialcati:n Sheet A

I Test Dest:1ptiarc C*:: ?O' ZA:7. A : OR H .W:IIrr.:T - En.T.3 3. C, D - IN Referenco Procedu = N d er/Sectis=: 2-SO 'A sequence Step Ku:aber: f/, g 20 De v. 4 1 ?? c t t:s i s 1 II 3a=k 7asi:1:ns ( :e ) .*

• RC:: Ta=pers:.::= (*7): St.7 O3 Tes: ,

7=vc Level ( 7.P.): o  !

Conditism.s SMt 223 3:3: :3 C.t: mov:s C:her (specify):

(Desi;:) C3: 0 CO: 0 C:0 Below Nuclear Hea:ing -

M3: M .

L

Za=k ?ositic=.= (s:c;s) 20: Ta=pera:ure (*7): 545. 2. [

Tes Power :. eve.1 ( .7.y.): o l Condf: ices SOA: 1M 303: "l.17 CA: , ..,;g . Ocher (syacify): l (Actual) C3: o CO: o C: o

• 30CA: f/4 ,. .

• l Ba.le w L Je a .Ma d :.d.

. Date/Ti== Tes: 6/t6/fo.

• Perfer=ad: /92 /

Ueasured Para: ster IA ; I::egral *.torth of Cost :1 la-k A -

(dese:1ptics) . i 1*.*

+ '

e Maasured Valus IA= ./ 3 [3 m

• Test esign 7:1um I *

/3 CCJ +

7.esul:s (f.:::a1 C-9'-'"s)

A ~

c)g [0M .

esign value 23 - 13C9 1 98 Pen (Oasi;. Cc=di:1c s) veten p.e;e:: TI?-T?O-31, se::etse 1973 latter ft:n C.E. It* !s(Te;co) s 2.1. Oes::sCG:),

, .sfe =ince i.

dated E:' *.1979(3eri:1 tio. 311.) .

If Oestgs Accep ts.=ce C:1:eries is exceeded, assure ade.

I V TSAR /!cch Spec quate sh ::d=i.o =ar;is &/c e M ua:e o:ha: accide=:s, A::cptance as ne essan.

Cri: crit.  :.atter fro = C. M. 5:al'11=gs (ve;co) :: I. C. Case 131::)

7.efc===ce dated May l'.,1973 (Serial No. 270) .

M A iwce. crohr-;a m Cc-a-'s

~"

%dMa'u./ . ha.n aoa.-ti,s s.se m oht1lneel duro's,- ACS b c

• or, cw'da% a sar,.  :-s u - 2.o i., s t J of 4,.,,, a;/.,k,, v$ny 1-so-19. 75,L,

-/,,... f. .-6: t, J z. %, 4. .. d,. ! . e -qi u . t

., (-

) ON.- JJ. Pae awed f C=;1etee my 7 .

Zy d / #sm*

7 '.N .

i B-12

- . . . _ _ . - . . - - - - . . - . - - - - ~ _ _ - --- - - - - ~ ~ - - - - - - - - - * -= -

l 2-SU-2.0 03-24-80

~

r}w%-

2 u N. i WSULTS

. \a- A "rACEMI .* 6.4 ,

r. .

North A.:. . l' aver ::stion 1;si: 1 Cycle L St=rtup 5:artup Physica Tas:s Rasul:.s and Evs1'uation Shee:

I I Test

Description:

IS ICRA:. UC2:2 0F CC:.":RC . RAW.5 A, 3, C, D IN C?I3.LA?

Rcler:nce Procedure N==her/Section: -5U-20/4.4 Sequence 5:cp Number: g,gg J

• II Back Posi:1:ss ( :e*>s) 15 c=per ture (*7): 347 +0 Tes: -5 Conditions Power Level (*.T.P.): 0  ;

SOA: 2:3 S;3: 228 Cta moving Other (specify):

(Desi;=) C3:. surving CO: r.aving CD: movi=g Below Nucisar hea:1:3 .

EC;A: 5i - -

III Ban *c Positices (s: cps) RCS Te=pera==re (*7): .545.B 9" i Tas: Power I.cvel (:7.P.): , ,, g Conditiocs 5:A:228 323: Z28 CA: ~wm.5 . Other (specify): >

(Act al) C3: w x, CC: acea#., CD: e.x, 100A: NA . . Eca ! mcEn,c ,[st.wG .

Date/Tisa Tast k/S[80.IT2/ 7?A M # .

, Perforzad: 6/pg/no c430 *

• Esasured Para:ater I In:egral North of Centrol b.ks A. 3, C,D !

(description) A. 3t C +D ; In Nor=al 3askWithdraval Seques==

yy _.

I 2:aasured Value I A.,. 3 + C + p . g *

• Tes: Eesign Value I A4 3 + C+ D =

Results gfj J (Ac:ual Candi:Lons) Fm* -

Desi;: value A+3,C+D. illi 306 pcm (Dest;= Canditions) *

- Vepco Report VD - 31, festesser 1973 I 3,,,,,,,, tetter frc= C.x. 5:=ni:ss cvepeo) to n.r.. cen:enceRe),

da:ed May 2,1970(Serial No. 314) . .

If testgs Acceptance Cri:er-Jn is exceeded, assure ade-

. V iSA't/ Tech Spec quate shutdown margis &/or evaluate other accidas:s, Acceptance as ne-essarv. t Cri:cria Le :ar from C.* M. 5:allings (Vepco) cu E. C. Case lhRC)

Refercace da:ed May 11,1975 (f erial No. 272). .

f VI betstrw:: lirst.

Cornants & y w,gyg g:A,-

t= tit.Q u % s k rodssM O wM.>4:v py tr.vevuovu 2.,A*,c v.2-N vhuf3 m nsur:0 psaDa6 RC$ ccf.ca ACCaro!. l rtemen oy pp ,

wr:T NeY"m11%AE9 m M!.'sfmat. Nrs caAshtis x3chfC tat higsms W,,( p,g 2 -lW - W. ft

. ccepleted 3y M '. -.

• w ..wed my C.I d ,

/

r B-13 l

l

. i f

• *L F'NAL R' ESULTS AT"'AC*C'I:.7 6. 4 7 age $ c' 6 1: orth /. rum :'ower ::a:1ea Uni: ;?_ Cycle ,1, :::::vp Initial 5::::up Thynics Tect: P.cuul : sad Evaluative,

'"

• 3 7es: Dencrip.isn:[*

• TE' *7 C ' C'?

~~'C

! I Ecle: nce Procc h :o Nezhcr/ N NE'2-3 -LP/ .%quence S: p tuber: yl.7.3 I!

3:nk Fo=1:1=.s (:::p:) ECO Tczperature (*F): 347' " ~3 i hs: , .

Pwer I,cvel ( 7.P.) : Z:2 C: hor (s;ccifp):

conditie.s SOA:  ::3 S:3: .ovie g CL- as (0 si , ) C: :3 CO: *:3- C::j3+0 ~

3elev Nc: lear Eeatias A 01: .

,'  !!! 3a=k P:sitions (s: ps)

• RCS Tc:speraturc '(*7): S& 2 'f'

. Tes: Power Level ( 7.P.): " ,

Cctfi:in'ns Cther (speci'y):

SDA 2 5 5:3f m e,m:4 CA: 718

) (Ac: cal) C3: 12S C: ttS C 113

. P/L: NA EOCA: NA

• Qq Alcy.4..pt. A CADA4 .

. Osts/Tiza Tes: d,//B/6o * .

e Pa.rf orzad: m3* .

Massured Para:eter (descriptic ) I:3s "*" ',T?3 C7 .=:..i 3 A.7,. 3

=

K.asured Value -

7

. /O % 16~-

l Tes: Ossi : 7alue f ,

Rosui:s (1::::1 Conditions) /O.jf3?./Cf,j>j . -

3 4

Oesi:: Talue . :043 3 :04 7 p.

4 (ta:i;; 0:nditists) .

• Ta;co S*TI Re;er No. 1 6,747 1, Teh: arf, 194:

'atter fr : C.M. Stalli:ss(Te;co) to E.F. 04 ::n(570),

i F#"rc' ' s da:ed May *. 1979(Serizi :*:. 314) 1 .

11 test; . Value Laf.ge' is ex:seded, tus: assure r.:cqua:

shutte. =arp: :nd/or o-lua te o-J.e 4::1de::s, as 1 V Tia?./ c:h Spec ,

-*"S"r-

. A:::;:::::

. 'Criscri: . tetter f r:m C. M. 5: 111ags ,(Vepco) to I. C. Case (::10)

T.cfer:.:: dated May 11,1973 (Se:isi *to. 27 ).

f C:. :n:s

i. .

J

-:e.ed n O/AP ~'/ V.  ? ../ .

-1.- n r d /.~

' d

-' 4 ee e

. --em e

....__ B-14 . .

. e _m. .q .

e.

_m , . . - - . - - - _ . - , , . -r- - - - - - _ ..-,c -. _ .. . , - - ,n ..y , i.- -3, - g

2-w~

r" NA'u RESULib ._ . C:__. _,_ s . 3

m. ..

C3-30-BO - .

r north !.r.:ia l'ow: S::::!vn t.>1t 2 Cyclu ,1, 0:s;r.u? Page 1 cf 7 Iui:1,.1 S:ar:up rl:ysics Oc.::ts ::::ul:= .tud Ev:lu::cf un I Tes: De scrip:Lon: as ..C-3 2A::I / '.;C.'C3. .C.St?.N!:.' , All C"'EIR 3ANK3 CC""

acference Proc =dute Mumber/ Scc:Ics: 2-E:* ' / 4.1 Fequence S:cp Nur!. u: yl,y

+0

L.n i ,P :ici:n: (s:sps) ECS Tc=Pera:t.. c ('T) : 547 -5 Tc==. .

Po.*cr Level (::T.P.): E ".3 .

Conditio: s SDA: ::cnri .x 503:noving C.u :*3 C:he: (specify):

(Oc:Ign) C: 2y3 CC: ~ ;3 C: ,23.$ 3al:v Nuclear Heating -

.ROCA: .

~

. I!! E:nk Posi:icas (steps) RCS Tc=persture ('?): .915.7 *[

Te:: Power Level (27.?.): 'o.og Condi:1ons 50.A:Nowd6 SL : wowc6 C.h 7 :S C:he.: (specify):

(Actual) C3: 1:8 CC: 2.29 C: 248 -

• a j ,**

. g--.

EC.LM/ NL.zLt/f NhW'.

Data /Ti.a Tes: f-//YM .

Ps:fo:_-cd: o3po - = .

• aga.....s v ~ ~ ~ ~ ~>..a ~:a '

(des. g..,cs). ..

I,.,A 2.*:"ICRA*, *='CF.7. CI SI: :CL's IA:7I A IV W .serad Value c, lls t M

• Tes: 04si:;= Vclue '

2ssults (t.::c=1 Cendi: ices) lll.f 1 lll g I Desi., Value (Deui;; Condi:ier. ) lil' 2111 Pc:

Yepco N7E Repor: No.1:5, 7.e r.1. Febr:s.:7,1980 .

. Latter fren C.M. S:2111:ss(Tepe:) to E.1. Dent:n(N?.C'.

. Oated May 2.1979(Serial No. 314)

If Design Value Lange is excescoc, :nen ssc:e :cque:c V Tidn/Tc:hSpec shutdet.m =argi= and/or evaluate other a: cide::s, as ersa n.

Ac:cp::n=e Cri:cri Letter from C. M. 5:allinss.(Ve;ce) to E. C. Case (NF.C)

Reference dated May ll,e 1973 (Serial No. 272). y si vi r:c::,Ta: Cb::CCIA M'i' Ce=:.:es:s f / C. // du e c:=plesea 3y / - a //c____ / P.eviewed sy l

t k i B-15

. . . ~ . . . . ~ +. I

' ' 2-go l

_d

,NAL RESUOd E'D A':'rAC"-EMI:C 6.4 "~~./.:,;,6 AZ t

• SJ

/

Nor:h .*.:n: I'over ::::ic:a Cai: 2 Cycle 1 5:n :up Startup Physics Tes:s F.est.1:s and Ivalu.a: ion Shee:

I

~

Test Desc 1 :1 7 :: 1010'I 0E~.! MIASURIMET Refe:cace hccedur Nuea:/get:fon: 2-$7-20/4. 3 Ocques e Scep Nu=her: a.g,p-II Zack Po:iri: .s (::q ) 0 Tc : RCS Tae per::u:= (*7): 547 +5 -

?:n.c; I.evel (*"T.P.) : O Conditi s ."..J.: 223 5:2: ::3 CA: =evi:3 C:her (specify):

(Design) C3: :oving CC: r.oving Q: =ce. g Salow Nuclear Esati:3 .

?.CCA: NA -

• II' 3: k Pcsi:ie s (s: cps) R S Te= pert:ure (*7): 545.F Tes:

Power Level (".T.?.): e.o M C.onditions SDA: 22S SO3: 27.8 CA:~m 4 .

C:her (specify):

(A:: cal) C3: wy.4 CC: a u.x, C:a=o w

~~~

AS' , , &~2.%r HUtt Y"At $s~hT**

• .ga:ef:i=a :es: C.llf/ao , IBW Tn/-von' .

Per:orued: (jgho, gly **

Measured ?zra a:e: ( j,s , ) ; gryygy,n, 7,3 , 3c.eg gg:,

(descriscio=) iC, a

17 h 1*aasured 7:1ue

( ) . jo, g pm. "

Tes: Design Value (JE! ) .

Resul:s (A=:ual Cs dizio. ) 85 - //.CO 1 0.Sf >- f ,

Lesig: '.'alue (Desi.~, .Cenditier.s) ( 4 ) . .?.1.08 0.55 pc=/pp=

44 *

" Tepco Report VE?-TR>31, Septe=3e 1973

,,, "I'I'" C " . letter f := C..v.. 5 s"' gs("epco) to E.R. Den:en(N20),

dated May 2,1979(Se:121 No. 31t.) .

V TIAX/ Tech Spec *

• Accep::r.ce ( So - ) X C3< 2.,,000 pcm Cri:cric FIAa'Section 15.2.4 -

?.e f e r:r.e c -

, Cc - .. .3

- N#'d 0/S / }/'

c:._ pie:e4 sy / #/ A. - -  ?.viewea sy C-.1 s dv B-16

,,,-g -

.~. _ _ . . _ . . . _ ._ ._. _. . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ , _ _ _ _

p A - 6  ;-50-18 7kl i /"bl .

• IIi l' g,, 03-24-90 A"""'AO*'.Mr.'T 6. 6 Page 7 cf 10 t b

Nor:h A. .. l':ver 5:::icn Utti:

2C ycle - i s ::: p Startup 2hysi:s Tasts Pasults and Ivsluati:= shee: I i

f I Test Dc ::1ption: *$

. s...;.r.*.C ~I*.?m2.I COIu . . . - A7.C Rafer:.cz .5 cedc:: Nu=b o r/S e e: ice: 2-SU-12/A;p.1 sequer.cc S:cp w ah==:4,;y,, g II 34:k ? si:12:s ($:e s) 105 "*c=pers:ure (*T):*4775 Pever Level (27.7.): o .

Cor.ditic s S 'A: *23 . 5:2:23 C.'.: 23 C:her (s;ecify):

(:eci: ) C2: *23 CC 2:3 C::

.:3 %~~ 3elow Nucitar Esa 1:3 -

. y;:,A: 3A

. -4

3 =k Fo:i:ic:s (s:: s) 103 Te=perature (*T):5 *E Tas: ?over Level (27.Tr.): c) . "O >

Cecditi=.s 5:A: AA3 3:3: A A S' ,CA: AA8 - C:ha: (specify): *

(A:::al) C3: Aa 2; CC: A Af6 C:: 1.13" ,

. 10:A: N6 BE: w Ndc.uGAR. *dch sw6i .

a/ i== Tas: b/st / % .

. Perfer:ad: \159-  ;

v.......> i..._.... n. ISO (2.,s._.p ",t,..  :) (p.}Ago  ; IS0""'C -

D"?II.C 7.5 C a.d. r : - u.o

.s

.; naa : d ::.:s. (g)un

3 - - o- 6 s Pcw j/ ; . ,

'50 '

.Tes: resig: Value (y')& . g , g g +"e pa .

Re s ul.s (A:::a1 C di:1: s) *

. Oasis: Yalue (by " -0.*S A : ;c=/ *T

( esi:= C :di:10:s) *

• MO

. 7epec Reper: VI?-??.-31, Septa =he: 1578 Le: e f;;= C.... S:m gs (vepe ) :e 2.2. :e=::=C:y;) ,

g, ,-'

da:ed v.a7 :. le79(Serial No. 314).

0 C*

<-2, : pe=/ 7

? TIA."t/ Tech 5;ec ,

(M).50

• ' ~reppler g** . -24: 'p=/Tl -

AC:cpts :e C~~*'e *: -

~

,afe:c=ce IEAR able 4.3-2, VI?-T!.'.-b'?I-105l ?I .'. l' VI  ! is as:icihated :. hat a ; sitive ::darster ta=; era:::e ccedficie== . rill he Corse::s =ea ss: ed . Red 01 r.d:r.a'. l'-its vill be instituted is ace:: dance with Tech i=.zl 5 ; e ' ---- 2. * .1. *. . 7::h ical !;ecifica::: 3.10.3 elle.rs .

operati .~. : a p-*'- ve ecdera::r :c perature coeffi:ie:: helet,r 5 pevar.

.. } - --

C=pleted 3y !h 1^1 . Rarieved 2y b J c< % :. _ c . (e, 3 g ;s.:wa n A") . - 4 . o .:. C.po P FL.6%'.) ,

r i- ==#1 A. /= f* .

[t Poss riv s McDERW 2. PEr.4,Tud.C. C C E M Id8EN 7~ W AS ME R

': ""' A vum a en c.m % e 3 eea me u os. Pa% dTEy Doesq PH*Ssc S MS'T3"N

'N M DJ E. 3 G,'y S7ccia Ko

• x h uiv ers wit.t.TEs.T EMEP s.'. .N 3 10 ye a cc a c ec %,w gu~.*Eca wic A Shic. Won 3 LM.

l 3,. L k. c R.DW-6 WiTH l s c i., se g q w,w g l POS gri,/E NCPcMTec T'SmedoTuc.c 'c d6,~*cie~7 B-17

- 2-SU-3E

/\ DC e{- C3-24-80

. I A [g! ,n...-,--v_-.

% . =..c.,

Page 6 cf 10 1.',:1: 2 Cycle 1 ~5:.. :up

!!cr.h A.tns P:r.rc ::-: f r.,n 5:s; =p ?hysics Tes:s Iesul:s a:d Iv:1ca:ics Chect  !

I Tee:

Description:

13,,..:  :.X. 32I?.A ;7.I C rTT:en : - 3/s.: D - :::

Ref::ence Procedu: N;;6c:/Se::icn::.3.,13/ C App. 3 Sc(ue .=="5-i.ip :w:nher: 4f::k I' +4

2:=k Pos1:1:=s (=== ) . RO: !==per::::: (*T) : 5:.-

Tc:: Powc Levc2. (27.P.): o .

Condi:1:ns 50/.: 223 5:3: 20! C.u 2:3 C:hc (specify):

(Cesi;:) CZ: 223 CO:. 2:3 CO: Oh Zelow Nuclear Ema:i=g .

ROCA: yr I!! 3sek ?::i:ie:s (s:::s) R:S Tc=per::ure (*7) : MS.f Tcs: , 7e . e.: Level ( 7.?.): 0;o Conditic:: SOA: 28 5:3: 2 2.( CA: 118 - Cther (specify):

(A:::all C3: . 3 2.? CO: ::o C: o , ,

• ** NA- . .Se/aw *~

/Ja ele., y ~ //.u &n, Da:e/!!=e Tes: S//7/ 80 *

?::for=ad:  : t / :.

Ee2.scred Parz:t:e -

(dest.ripti::) (4 D

) n..o'  ; Ishther:a1 Tc=;ers:ure C effieles: - 2ar.i.

'>-T: I IV f.

gem /cg , "

1 .

(g) Iso j

!.'ea.sured h iue .

.g f 3 _

t 7 ts: Ocsig: 7:12e ISO ,

.,E.

b

. lascul:s (A:::a' c-- J '-3 ns) D's D . " Y- -

E 1

( (. ISO " 4 I

4.09 - 2;=/ *r 1

Oesi: hiu:

( esign C ndi: lens)

(o.:) s

- Tepco Reper: TI?-TU-21, Sep:e:eer 19 73

..,3.,,,,,,

14::e- f;:= C.M. 5:alliass(7epco) to E.7. Centen CU 0).

^'" * "'

. dated M27 2, 137?(Seria.1 No. 31+}.

, " 30 du ,.

7 TSA't/ Tech Spec

. F.*.)3 o.

<-0.*: p:=/ I Oc;pls:(g ) = -2.02 p'c=/ ~ T A :c; :nce Cri:cria geye.e3.e 73 Al 761e '. 5-2, TI?-TP. -NTI-10!., P.IV. 1 -

• C - --- s

• mtf

[cce[ance Cf*g ra'a C=pleted 2y p'f......A e M w-

/ A ~ >> r

//1. />.M ;

_ _ 74rieved 3Y /. _

{ // / / - /.

i I .

r l

• i l B-18 i

I

--. ~

4 F

._ . = _ .,..._

i:

f J :AL RCSL,7*

1=

i 03-24-80 A . _,, ,..n .. .5 Wo .h Aar.s ? cwa S sti:= t; 1: .,2,,,,, Cycle ' Sur: p Page 9 ef 10 .

. Startup Physics Tests Resu.1:s and Irel.stien Shee: .

I Tes: Oescripti:n: t/D TI$~~ l'A?- AF.O .

Refe ence f 7:steds;e k=3e:/ sac:ics: 2 5U-13 / A77. C 3*tv'*** 5:*7 3*h':2 4 l. S r

f i

I: *

[

Iask P:siti::s (ste;s) l 7.03 e perature ('7) : 5'7'5 Tes: ?cwer Level ( .T.?.): 0-4

• One: (s pecify):

• C8"diti8 ^8 s:A: I S STS: 22S CA:223

( esiga.)

. c3: 23 CC: 223 C a y13.' a: ' g g s 're a 1 33 t"I.-M- as .

g NA III 2a:k 7:siti=r.s (steps) Z:S e=perature ('7): IN . 4 Test

• 7:ver Level ( 7.7.): O Cond.~.ie s 7;p : 3; 7.;. 2 CA: 7.28 C ce: (s pecif y): '

g;3 *

(A:11) cs: gg C*.: 32.7 C: A e l-

• Y Q t bo'rvt,ht] *

. Cate/T1=e Tes: 6 //2/fo ,

Perf ::ed: / 9 / 3 .- / ff-[ .

\

EOt. III.. ,,

A33T. P A. T*,* 1.* 11'J. If, TOT 1* EIA"' QUA:7.,*4;"

ET.AST?.I3 ? ARA'T I"i ,

(dese:i;:.ian)  : Oi!f. , *. - . . . , , . . , , . 7.....,s ..

w s.. ...y.,

~ . . - .

g,7) CEJa*.;C IAC 0t. TA0701 MTN (y?"E 2 t 17 + }.?$ I'ry :l.0I

'l , Q o l'.casured value 4 py,f, p , ,,4 f gyjg q}

l

• so.f.forft2,.9 Tes: Desi::. Talue

.f /,((o /

~~ 4, g o f /. a 2.

Resul:s (Actral Co-di:imes'i * ' f '[* "," II '

• A

- 1

+ 10: fc .g

. P., 20 . 9 ns.- .-- . , .-*

• e '-. .p :a11 r .t.'.aa unin % s

- 4 5.. Ier P,<0.9 - c- ,  ;,a:

I tesi*a '/alue - .

x {t.n p p~~ 3*

~~

' "d 8 d *8 Gesi s 04:diti :s? (P = As s y ; J--) '~c l

OAP-7 90 3 ' 3 3.2.0 3 3,3,; *'OA?-79*!

a Refere ce =

7.77.1

, . LIV.1 '

f I

v TSAO !ach $;ec n ' ,y -- ,

.:A m A::e p tance l

Cri:eria '

1efe:e:ce h T3 3.2.2 .,

.a , a....,

,;A 6

. VI ~

C' 8 * *

• 8 M c C e.p b't e c t. C r.' NTI A .. m d ]*

c. 3:.:ee sy /c.. . . . %- D 7.=e.. .a sy . / / L'K l

/ f JE 4

i B-19 _. ._. _ _ . _ _ _ _ . .

, ,- r - - -

m

~

~

clNAL RESULTSC3-24-50 2. . 1,- .

2:e:th A=r.a 7:ve *::: ion U:1: 4 C ycle - - Startup ATTAC",'MIOC 6. 6 Page .O c,. ,.3 .

t Startup Physir.s Tests F.asults ar.d Ir:lue:1:n,5 hee: .

I Tes: Descriptier.: l'J3 T"*.'" . . h?- 3;_q t-n' I i

?.a!erecce  ?:scadu:e G.=.ber/54 :io:: *-3;;-13/ App.O Sepe ce Step Mer* 4' /, / 2 II lad ?osi:1==s ( :eps) l RCS Te=pers:u e ('T): 547:5  :

Tes: 7:v4: 1.evel ( 7.7.) : 0-4 Ca ndi:io r.s . a-o - 7*e CA:39* C:her (specify): . .

I. .

(Oesi;:) } ((j };{j;?13 c3;g M=s have ,13 -

t '#"las -

2Ca:u ,

III 3au Posi:locs (s:eps) 7.03 'Te :pera:ure (OT): E4 7. #-

. Tes:  ?:ver Laval (*.7.2.): o .

Cat.ir'io:s 33 ..p ~

g,3;  ;. } CA: 31/ C:her (s;esi'y):

I (ACE 221) C3: .[. y p CO: ,. f CD: o EEUA8 A/4 .

$6 4deM[,/d 5,

, ate /._,.a .. .es. 6//?/so Per's::ed: ' o /fo - c 3 4 o .

r t

l'.AX. RI"_. ,,

!CU.50?.D ?A?.J.'C I?. ASST. F'.~A. -

T .' , !..;C*.I.\T. T,*,, TC TA:. 'dTAT q~ JOT,N.;T  ;

n (dns .< ..r.. . o n) . D.as..u. .-

r, . A. ,,,. ,.., y _

.a..... T,., . ..._ r.w .Cli.,,, ....s.

s .. s ....

g ,,')

p CO.'0"u* FA0".*1 FAO:07. 11.!!O (VF*.1:

M.:cl. P,, = u? 1. S 'i 3 .

7. . , t.co?3 (fo/E37) 1 * *c. ""

!".easured Value a ,g t ro + f.1 f; : e.9 >

Its: Cesigt. Value 4

~

., 4, . f. /, (( o . f, 4, /[ 0 6 /,02 T.asults (A us! Car.ditier.s'i *

, +

10: for ? i20.9 e: .* e . e a l t

7 u a ri :2 **

• kt*3/* 5 '"* 2

.esi = Value

- . > - ,3- 3 ec 9 g ** g.*~~~~**sz

, . ti. 2 (1-7)l ~

1.... -.

'(:esign Ca ditions. (y . Assy 7..;) .

- f',, t * * * * : .s P.a .< o r e... . e WCa?-7905 .,.3

. s... .c. ,... ...,

VCA?-79:5 7.rt.1  ?.~ *' 1 ,

r TEA?JTect 5;ec M ,g ,

r.A n Acceptance C:ite:ia Ee!e te r.c a .M :s 3.2.2 s 3.+,; M

. TI ' '

C* " ****

kCCtf2tCt k CY&n>. WR A A /9/ -

.ple* ed 5y we- - I $' . /

- .t.svie-ed Ey j 8 /%,12,s S V / .

. /

B __ _ __ -. _ - . ._ - _ _ _

t l .

p r- A j 2-SU-47 ND ATTACZME'.C 6.5 03-30-30 i

. Page 5 of 7

/

~

Nor:h .*.r.: Power 3::: ion ,Usi: 1 Cycle 15::::=p ,

Startup ?hysics Tests i.esul:s and Evaluation Shee:

I Test Decr. rip:Lon: QTROL 3MM C WCETH MEAS *"EC.*! - ROD S**AP Reference  ? ocedurc Nu=.ber/See: ion: 2-St i.7/4.2 Sc ucsce S:cp Numbc : .//,3/

3

!! E nh Positions (=:cp ) RCS Tc=per::ure (*7): 5A7 +5 -

Oce: Fever Level (T?.P.): O Conditier.s S:1.: 223 S;Z: ::S CA: 2:3 Other (specify):

(Desigs) C3: 225 CO: Moving C:M=vi:g Below Nuclear Hea"sg RO A: NA' .

'I!! Ensk Pcci:1ons (s: cps) RCS Te=:erature ('F):6Yf.9 Tes: Power Level (TT.?.): C)

Conditions SOA: 7 E2 503: 228 CA: P.2 8 - Other (specify):

(A:::al) C3: 32.8 CO: /A ede3 C: /%evinj ROCA: gf , $gjo g,g M,odev . gegff7 Date/Ti=e Tes: 4/IT/80 ,-

- Perfor.ed: lo 'd 1 -- // 2 o Measured Para =a:er -

(descripcion) I ; INTI:3.C. WORTH of C'".' TROL 3XG C Iv

( Critical. 2derece S&

,'aa

.. sure d V ,_ ue -

1, = l O O} pc.th fo g ,,g g.gn : ll 2 $f qp$)

Tes: resign Value (C.r-[h/Ca) kehste. SM Resul:s (Ac:tal Co:di:icas)  : ~. 9 88 ' O 7 p'C.m f,3;p;m 2 l G g.js)

. Design Value (Critical Reference Basic (Desigr.Condi: ions) I = Sal 2 99 pcm ?ociti:n = 112 steps) e Vepco 57I Technical Emper: No. 106, P.evision 1,7ebruary)

Reference 1980 and se=omde f := C. .T. Snow to E. J. Lo:1:o, da ted Teb tr- 2L 10 %.

7 75APJTech Spec No: Applicable Acce-C '

?.efc cace No: Apslicable * -

_04.o 6.qc C.t-[d*Md VneD .

Cor -

• s C pleted 27 / Reviewed By C- J

. , O e

B-21

2-SU-47 RNAL RESULiS g g;= e.5 Page 4 of 7 j

!! orth .t:r.: l'over 5:stion , Uni: ,2,,,, Cycla A S:::::up ,

5:artup Physics Tes:s Resul:s and Ivalua:ica Shee:

I' Test

Description:

COET?2 327 3 h*0 RTE ?EASUPJ.5CT" - RCD SUA?

P.cre:: ce Procedurc l'u=ber/See: ion: 0-SU-47//. 2 Sequence S:cp Number: '-y,/. 3 /

II Bash ?csi:iens ( :ep ) RCS Terper::ure (*T): 547 +3 3

Tes:

Condities.s SOA: 2:3 S03:228 CA: 2 3

?cuct Level (IT.P.): O Other (specify):

(Desi :) C3: ?!avi:3 CC:2 3, C3: If=nri g RCCA:NA hisu Ndear Hea-in -

I!! Ea=k Po:i: ices (s:aps)  ?.05 Te=perature ('T):6*fi . f '

Tes:

Condi: ices 5:A: 223 s:3: 22.2 CA:2.23 ?over Level (27.P.): o c:he= (specily):

(Actual) C3: hl:vluj CC: 2,2,3 CD: /devi,tj ICCA' AlA

. . bG Nt.D 0Cear* hog",ta -

Da:e/Ti=a Tes: le[I'i / 3o '

Perfor:ad: .

//3o - /23 f.- .

l'easured Para: ster .

(dese:1ptio ) j I 3; In:egral t!<. :h c' Co::rol 3a .k 3

!?

l

..easured ,3.-.ue

( (ri1!:iO.af. k"hJcMe.dd 13 = /.3 g, Pd.m fo3;6/% = f 70 stys) .

i Tes:

Resui:s DesiS: Value ( k i W h k enee 8a4!c (A : cal Condi:1e.s) 13- /3 2 I /30pc~. P,3;gim: 17o,qs)

Ce it Value (Cri:1 Refere=ce Bank .

(Design Conditions) I3 = 1297 120 pe: Posi:ica = 180 steps)

. Vepco m Techni:al F.epor: No.106, E.evision 1, Fao' :c.ary .

Referenec 1950 and =escrandu= f =n C. T. Snow to I. . . L::1:c ,

dated .ebrua:/ 21.1920 Y TSMt/*"ech Spec No: Applicabla *

. Accep::nce Cri:cria

• Reference tic: Applicable , .

,.o......

$ C.tep0N b[deri A 'd i CO Pleted ?y b Review *d By r e .d B-22

____w

l 2_m_c "N1A I"a RESU -i3 ^ = = = = ' '

03-30-60 Page 3 of 7

., /

Nor h I.;, ..-2 Power St..:iott L't.1:

• Cycle 5 Startup .

i S:artup Physics Tests .tesults a:d Evalua:to: Shee:

• I Test De:dription: CO:.~7.0L 31.NK A tiOR*H SEAS':7.OE:C - RCD SWA?

Reference Procedu: Nu:r.1,er/See: ion: 2-S G-47/4. 2 Sequence S:cp Nu: bc : 4. .!. 3 /

, II' Es=k Posi:1:ns (c:cp ) K)

RC Tc=per::ure (*T): 347 Te : .

-5 Conditions Power Level (*.*P.?.): o S":/.: 22 S S:;3: 223 CA: !'.svi:g C:her (specify):

(Desi:--)

.C3: 223 C h 223 C: 3$sving 3elev Nuclear Eea:1:g ECCA: NA'

• I!! 2ar.i Poci: ions (s: cps) P.C Te=pera:tre (* F) : 5 M.7 Tes:

Conditier.s SOA: 243 CA:,% dma Poue: Level (T7.P.): c)

.SD3: 222 . Other (specify):

(Ac: cal) C3: 2.Z 3 - CC: 22 F C:Md $,

P. COA: N/t he.hy hocde4.r.Nea4[g '

Da:e/Ti=a Tes: 0/M/20 -

Perfor:ad: /2r5 - /33o

• l'easured Para:e:e .

(descrip tion) IA;,In:egral W :th of Cen:rol 3ank A 17

( ,:zasured Value (C.r itiea.f. kNIent d.t 1 Ig = 4g p> fogjg, , ~79 ggp)

Tes: tes1:= Talue (C f-ibC8.l. 8I'JC%Ct d"I<-

i Rasults (f. : .:.1 Co di:1cas) Ig. 626 i 63 pcm pe ;37 m 7 7 u g Desig: Value (Critical Reference 3ack (Desi; Condi:fons) IA = 617 : 62.p== P:si:1:n - 84 s:eps)

,epco di; ;e enr.:. .a. :.epor: do. 1wo, hav2.s.:n A,Ie::2a r .-

IdI*T* C' 1980 and te=orandu= f::= C. T. Sn:V te E. J. Lozi:o,

. dated Februa:y 21,1950

~

Y ISAT/T*:h Spec Accept:nce Not Applicable

• Cri cria

• Refere:ce Nec Applicable

• wC =0n*s I

l$tf

"T.ASUEFTIT - RCD S 'A? Reference  ?:ocedurc Nu=hc:/Section: 2-53-47/'.2 Sequence S:cp Kundcr: g[.3[ II 7,cch Posi: ices (::cp ) RCS Te=per:ture (*T): 547*3 ~I Tes: . Powc Level (IT.P.): 0 Condi:lons S":A: 223 S::3: .v.ovi=g CA: 22S Other (specify): (Desig=) C3r 228 CC: 2:S CD: '2:rri=g Below Nuclear Etati=g . . Ec"'A: NA' III Sank Positions (s: cps) 7.05 Te=,arature (*7): f%. 7 TeS: . ?ever Level ( 7.7.): o Conditions SDA: ZZ3 SD3:[dcVm3 CA: ?.L3 . C:her (specify): (Actual) C3:"2,"l, P CC: 7.2.2 CD:,Wvie3 l KCCA:AJA 6e.lCw IMe. lev He&- ~ Da:e/Ti== Tes: 6 /l'i / 7F . Te:for=ad: . 13 9.g. It;-z q . 2'.easured Pa:a ace . (desc:1p: ion) Ig:;3; In:egral .io::h of Shutdeun Zank 3

v - '

i 1:easured slue ( c.r-ible.c4 E*.h:e Ja .k. ,

S:s

• ID I2 Pc

• Pesian = lel st-e:es)

I . 'Tes: resig: Value [Ct-[5ical ,kebt*:e 88M4 l Resul:s (A=::al Condi:io.s) S . f OS71 /04 pc.m P s;6m = 12I s@) Desigs Yalue *(critical 7.eference 3ack (De'si;: Condi:imns) Ig;3 = 1057 2 1C5 p,cm Fosition = 129 steps) . Vepco NTI Technical ?apor: ;o.106, Rav.sion 1. Ta's: aa 7 1950 and ce=crand_-s f :m C. T. Sncv to E. J. l.o:ito, Reference da:ed Febr.:ary 21, 1950 - V FSAR/ Tech Spec Not Applicable 1 A::eptance v Criteria '! Refe:cn:c No: Applicable . t Co .,,. .. , .,., . @ J, b 2.Af.6 d A M P.b. i . cc:.pletea ny 7k' u r,e.evee sy C. j A, d B-2 /. i _. .__-- , . - , 4 . _ - . _ . . ,,m_. , , 2-CU-47 A'ACEME:T 6.5 b3 1 03-30-30 ~) \ L- I Page 6 cf 7 i Nor:h Aans l'over S:sticu ,t: si: ,,2,, Cycle 1 S:nr:up , Startup ?hysics Tests Ra'sults ,and Ivslua:ica Sheet I Test

Description:

SF.6;;CIG SA'.'I A WOR"".4 12M;'?."Z::~ - RCD SL'A?

Reference P cedurc !?u.ic /Se::icn: 2-50-47/4.2 Sequences:cpNu.ber:y,3l .

l II Ic:k Positi:ns (::=ps) a3 Tes: RCS Te=p= sture (*T):317;5

" Power Level (27.P.): O Coaditions .J.: l'oving S::3: 2*S CA:223 C:her (specify):

(Design) C3: 228 CC: 2:S c: 3fovi=g .

RCCA*- NA

. 3elev Nuclear Heating III Esak Fo:i: ices (s:ces) RCS Te=perature (*F): SM.S Tes:

Conditions Power Level (TI.?.): o SOA:/AcWU3 SO3: 222 CA: 22F . c:her (specify):

(Ac: cal) c:2a6 CC: a a F c :/Aevi=3 ECCA:A1A below hdf # hM.S Es:e/Tisc Tes: G/A7/80' .

Perie::ed: . ]9 3 q. j,$ //

Mea.surci Para:c:e I 3;A; In:egral Morth of Shutdevn 3ank A -

(description)

IV a

1:easured Value Oribi:.d $t5tfCMt 0*E ISOA " / f f ej h 0-M (kgfh = /3% 5%3)

Tes: Lesir,n Value . . (biNC..*I.N8b^N-I3 ;A= f/dC I NC [W Results (.t:::.:1 C di: ions) fosm.-n. . /J .5%s)

Desis:: Value (critical Reference 3ank (Design Coedi:fons) Is3A = 112: : 112 pcs Position = 139 s:eps)

Vepco NTI Tecndical P.epc:: ':o.106, Revision 1,7ebrua:7 Reference . 1980 and =c orandum f := C. I. Snov to I. J. Lo:i:c, 8sted Tabras-, 21, 1930 V TSAR / Tech Spec 'No: Applicable -

, . A:ceptance C 1:crin Referc=cc No: Applicable .

Co.___.,.,,.,.,,

.. C y E c A c.e_ br-[deM4,Pae.t.

C= pleted ry '

Reviewed 3y C . .I w B-25

Aln1 ii \ nI ocell I \ L.V v R-v 2-SU-31 03-30-80 Earth Ar.na Power Station tinit Cycle L Startup A*":A%C 6.9 Pa 1M6 L

startup Physics Tests Rasults and Evaluation Sheet I

l fast

Description:

M/D Tm MAP- AT P0;,T.R NI CALIB. , R DAT/ MAP Reference Procedure Succar/Section: 2-SU-31 Sequence Step E:aber: yy i II hak Positions (steps) 105 Temperature ('T): Traf 2 1 Tast Power Level (IT.P.): S3()

1. *I 3,[gg* SnA: 228 sDa: 228 CA: 228 Oth** C8P*'ifY)

, ca: 228 cc: 228 G:AR Must have 1 38 *k M les M NA l

III Bank Positions (steps) ACS Temperature ('T): J7 3.0 Tes t Power Level ( T.P.): 2,7 y g Cond.~. ions gnA: tt3 gns: Et8 CA: EES Othar (specify):

N E"'1) C3: 12 8 CO: t.'t.8 CD: @~

1 *A:

Date/ Time Test 9/10[60 Performed: f gf o

. l'AX. RC.. ,. .

MTASJ723 PARA. T R ASST. P'.'E. qg, N;;;;.r.AR T,'2, TOT.C. REAT QTua 1" (description) I Diff.

(p.p3 CT.;AI.PT RIST. EDT TU".C ECT Cd,V :EL Pr. ? TILT CE.'X;C. FACOP. FACOR FATIO (QPu:

p

['

Iv 4.n e. Pg7. e4

' - ured value g,g ,,, 3, , e. c $ l.i .39 2. 359 l.occ 7 Test wY. sen h t o.1 Design Value Rasults (Antal cenditi6ns ) IIII ***. Es * *'l N/& NA t I' 0 7-

10

for P 10.9 g RA gA Design Valuu  ! 13% for P g<0.9 g 1, :

(Design Can:*.tions) (p . A,,7 g )

Raference UCAP-7905 NA a VCAP-790 RIV.1 y_-*; .1 f

F

• Y TSAP/ Tech Spec EA # 8*l.S$x [1+ .: (1 r, ::.to e tw/et W.5 h Acceptance J x (1-RBp (80$ ., f ga.:s a w a ,,e.s

, Criteria .

,e.en.e .. TS 3.:.3 5 3.2.2 ,

, VI Cowenes .

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B-26

2- PT-zt i FINAL RESULTS Cycle 1 e ATTACID'.E IT 6.5 1* orth Anna Power S:stic: 1:nt: ") Startup Page 1 o.,I tr.rtup Physics Tests Results and Evsluccion Sheet I Test

Description:

/D T1.t /. ar- AT TO'o'U., - R DATA M.*J Re f e r t t.c c Precedurc !!ur.ber/Sc ioc: 2-?T-21.1 Sewence Step ilt=ber: g 3 4

!I Estk Post:icnc (::eps) RCS Tempera:ure. ('T): Tref 2 1 Tes: Power Level (7.T.?.): s ti0 "d M" 5 other (specify):

SOA: 228 SDS: 22S Cl~228 (Def.3) cs 22S CC: 228 CO: /.R Mus:i h ve > 3S Chi: bles

• ROC'\ NA III Eack Positions (steps) 7.CS Tc.=per.a. ure (cy) ggeo g Tes: reva: Level (~;T.P.): 4, c'e/

• Cond.7.io ns SD3: 2.2 8 CA: EtB 0 hr r (specify):

SDA: 7.2. S IACd) CT.: 228 CC: (.16 CD Ip//pg ECCA:

~7 f T'rflMSLES Dar.c/ Tin: Tesc 'L[ff[OO Ferfo:= c': .2/29 - t 2.y 7 -

. l'.AX. LEL. ,. .

MCA*L77.3 Pt.R/.::ITrt. /.55Y. r ;.

7{.,, 2:itCtr3y. r,',, TOTat. Hr.r,,- y;j,vc;,;7 (h.scriptic=)

• Diff.

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CrL\;i. EL TACTO?. F.u ~0R  ?;,T c. (q?;;;

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l F NAL RESULTS  !

2-SU-31

orth Anna Power Station Unit 1 Cycle L Startup 03-30-80 A'

TACm C;T 6.9 Startup Physics Tests Results and Evaluation Sheet

.s PE2d6 I

f Test

Description:

!!/D TLUX EAP- AT P7a~c.R. NI CAI.IB. , !! DATA MAP Refereoce Procedure Sur.ber/Section: 2-SU-31 Sequence Step Ihnber: Q II Lant Positions (steps) RCS Te=perature (OT) : Tref 2 1 Test

• Power Level (:T.P.): %50 g SDA: 228 3DS: 22S CA: 228 0*** (*P'*1fY)

.C3: 228 CC: 228 CD: AR R:st have 3, 38 thimbles RCCA: g III Bank Positions (steps)

Test RCS Temperature (OT): 54 3. .f CondC ions Power Level (IT.P.): .:r::'-

• SDA: 22S S;3: L 2 2r CA: 2.2g Other (specify):

(ACCual) N #

CB: 2.2 p CC: 217 CD: 2./ k RCCA: MA um - + G J h . J ,t a Used Date/T1:e Test J yf 4r y Perfor:ed: 9lt yjfp l/[;7 j

q,gjg ,

• .M:. REL. ., .

MEA $i; RED PAPA CETER ,ASSY. Pk"A. T',

N TOTAL m i T*,'g,  :.*JCLEAR QCr ?.A..T (description)  : Diff.

E ;TiiALPY RISE EDT TLUX HOT C C;IL g,p)

CE.W.;IL FACTOP.

20C7 !!LT p FAC!un PL w e. . . :. ;

IV 77/

of,1)y R lis 5 b M *R3 Eeasured Value +U $ b f.[ /- /h /- kN /*00 N

• Test Cesign Value tsc a 4. R P o.9 F.esults (Actual C:nditians) D f + b f e O d t

p A/[t 4

- j.0 ~

+ IC: for P g 20.9 Design Value 1 15: for P gco.9 NA a 3 g,0, (Dest;n Coeditions) (P = Assy pvr)

. e i

, i Eeference WCAP-7905 MA g VCAP."d!

TIV.1 c.

N T <

V TSAR / Tech Spec KA A8"1.55x 1+.2 (1-P3 -

r* :2.Lo a sta3ht t'd 5 KA Accep tanc e p r h-R5P(m]  ; rf 16.2 8 W8 7:4.3 Criteria ~

Reference NA TS 3.2.3 TS 3.2.2 gr

. VI CC  % CC. (rrYe r"5A $Cb f *

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. NA_ RESULTS

!*o:th Ann.1 rov.c ses:ios t:r.it _2_ Cycle 1 S t.s t:u p m A=n. - s.s p yg3 tar:up thysir.s Test: P.e:ults and Evalu . tics Shee t I Tes: c.:3.c ri p c ion: ::/n rt; . !ar- AT PO'.CPJ, E. DATA MAP P.c le r e r.c c Pro:cdu:e !.u .b c:/!cetion. 2-PT-21.1 sequence step Fu=ber: pg -

II t.:r.h Po:itio .: (::cp:) ECS Tc=pers:ure (CT) : Trcf 2 1 Tes: Tower Level (" T.P.): sg Co..dizions ccher (specify):

sD/ 228 533: 22S CA: 223 IU#5I ") C:: 228 Cc: 223

, CD: /.r. Ibst have > 38 Chitbles,

. nrc.'.: ya III  ::ri Pr.i:i:ie.no (:teps) ECS Tc=perature (CT): Sd.s-f *[

Test rover Level (*4T.P.): .58.c -4 C~r!O ID:s san;22S :D .: KZB CA:2Zg Oth : (r.pucif y) :

(ACE1) Cc: 4zs CC:zi.B CD:los n.

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(1c'e**<pt<~"-) p h,[<<*

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B-29

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~

F.INAL RESULTS North Anna Power station Unit ,,Z,,, Cycle 1 Startup 2-SU-31 03-30-80 7' Startup Physics Testa Easults and Evaluation Sheet A.=;ACEMI27 6.9 S. *

'Page 4'cf 6 I Test Cescription: ::/D TLO:". MAP- AT POhT.E, NI CA1.IE., 5 DATA MAP Reference f Procedure Eumber/Section: 2-S U-31 Sequence Step h er: gy II lack Positions (steps) RCS Temperature ('T): Tref 2 1 Test Power Level (:T.P.): %75 C**diti*** other (specify):

sDA: 228 sDn: 228 CA: 228 IU**18'} CD:

Cs: 228 CC: 228 AR , Must have > 38 thi=bles Rc:A: NA III Rank Positions (steps) RCS Temperature (OT): 5 72./ *f Test Con &. ions CA: ZZS Power Level (IT.P.): g'7 g .

SLA: 22 8 SDB:22 S Other (specify): .

(Actual) C3:22S CC: z.16 CD:czB 17 w ,an cuenu. T.st 9/u/~ -

Perfor=ed: O y go_ ofy l'AI. RC.. .,

MIASURID PARAM.ETER AS3Y. P'.R. Fg,h*JCLEAR T', IO!AL EEAT QUM;;A ;

(descriptioni*  : D ** *

• S -

(3_pj C:THALPT RISE ECT TLUI liOT Cu,A.;;;gt pg m 7;g7 p Cita:GC. TACIOR TACT 0R RATIO NP~R)

IV .

J.9f.M lh 84#

l l'easured Value iIIM .hf'  !' ' ~

Test (A:'",,kstf;EOd P.esults Design Value (Actual Canditions>;IlfIe M '9 g 4

~ Log

10 for P tC.9 g RA Design Value  ! 131 fc r P <0.9 g; 3 g,ca l (Dest n Ccuditions) (p Any y) i Refareace WCAP-7905 NA g rCAp.;93 REV.1 c' . ;

. y TIA2/ Tech Spec NA EA Acceptante 7 x [1-R3P(BOG  ; f :..as a was e:c.s criteria Reference , RA T3 3.2.3 TS 3.2.2 gg

. VI

@M C.[IR$/A . set"7 l

,pleted By -t Reviewed BY C. J f .

B-30 l

l I

-. . . ~ . . . . . .

. FINAL RESUL~3 2;g;g, Earth Anna Power Station Uni: A ycle C . Startup gi; A N C 6.9 Startup Physics Testa Kesults and Ivaluation Sheet Page C a' *- 6 I

Test

Description:

it/D TLC MP- AT PC*a?.R, NI CAI.IS. , E DATA MAP Reference l Procedure Number /Section: 2-SU-31 Sequecce step N e er: g, [

II Eenk Positions (steps) R S Te=perature ('T) : Tref Test Condi*d ons Power Level ( T.P.): 490 SDA: 228 stb: 22S CA: 228 Other (sPecify):

IU** 8*) C AR ca: 228 C8228 Must have > 38 thin:bles RCOA:

NA III' Bank Positions (steps) 103 Temperature (CT): 57.5".3 Test Cond.T ons Powr Level ( 7.P.): 17.2

$2A: gag 3:3: %:.F CA: 223 Other (specify):

IACE ) CC: 213 CB: 2Zf CD: /$9 RC A: p/A .

~

Dete/Tisa Test Yf dn t!sLT

/o//o/80 Performed: 22 2/ - e e 3 p 2'JL RC..

MIASL*P.t3 PAPWiEUR (description)

A$$T. P'."A. T*,*g, J

N'CLIAR y',

N Tc;.AL HIA; gj_g,,7

-: Diff.

g_ p) C !HALPT RISE ECT TLC HCT Cilx :EL Pe* T.: TIi.!

, cz.ucC. rA=ca r.'CTom rano (nruu 1r +n 6 f;.; o.se r.eesuree ve:ue *% 4.,; e 'o /.349 2.o / 4- /. eo.rz 107. he & 2 c.9 Test Design Value . .

.ssLits (Actual Conditiend) ?I w 4 0.9 t/A AA/

l. c 2.

10 for P 20.9 Design Value 3^

15

forPg0.9 , ga g 1,02 (Destge Conditions) (p . g,,y pg) ,

Reference L W -7905 XA g t;A? %$

RIV.1 ,, . 1-'; .1 N - .

T e y TSAX/ Tech Spec NA M*l.55x +.2 (1-P)l r * .10 = kW/n W.s

• NA Atteptance  ; ( 6.2s a sw : c c.)

{ x [1-MP [3Ch Criteria .

Leference NA TS 3.2.3 TS 3.2.2 g VI

• • ~ .

Accykce Q;/eria Me 6 .

ce m .:ce or J J 7.z d~ nns. .e er c.A L ,

i B-31

FINAL RESULTS 2-SC-3*'

i T. orth Aana Power Station Unit 1 Cycle L Startup  !

Startup Physics Tests Rasults ar.d Evaluation sheet A*'!ACEMI:?T 6.9 Pace 6 of 6 I Test

Description:

UD Ti. r. .".AP- AT PCTJER, NI CAI.IB. '

Procedure :su=ser/Section: 2-SU-31 Sequence Step J' umber: C)$

Reference ll i

II &ank Positions (steps) l IL s Ier.parature (*T) : Tref C 1 Test Power Level (%T.P.): s100 C**C1 i"*8 s:A: 223 son: 228 CA: 228 Oth*r (5*Cif7 ):

I# " *8"I C3: 228 CC: 228 CD: AR RCCA:

NA -

III Bank Positions (steps) RCS Temperature (OT): 579.6 Test '-

Power Level ( T.P.): 99.9 Condftions SDA: 2.13 sos: ~22.7 CA: 4.tv other (specify):

(Actual) CC: 1tg CD:2 21.f-W CB: n$ ECCA:

Date/T1.s Test Perto ened a

/*/'8/8 /

74.go ,, , ;y j 2*>X. RIL. ,, -

Mr.AS*.75D PAM.".PR AS3Y. P.L F{, !CC" JAR T,*3, TOTAL EEAT C.'Ah.i

(#'** *

E'TUALPY RISE ECT TLC. HCT C1LA ::EL *' O !!LT p

CLA.N'.;EL FACTL .' TAL!wr. !AT10 ( ;F"R; IV - 2.E io.- (,= 1.I F reasured value 3 I Er I

• o '*

s.c

/*3bb /- /* 0 0 r ecT iw fi2o.1 l Test Design Value gA gg F.esults (Actual Conditier.s)I'S ,* ,' is 4 o A ,l 1g /' C 2

. + lo: for P g10.9

• ;;A g 1.C:

Design value 2 13% for Pg<0.9 (0esign Conditions (y . g,3y pyg)

Reference L'O.P-7905 NA g  ; G.? ~yM RIV.1 Cl .1 T

• M*1.55x (1+.:(1-P)) rj ::.to e usth: r .1 e M

y TSAPJtech spec n -

Acceptance [* b'# II i c .a.:s a aw a ,;- 1 f~

Criteria -

Reference a TS 3.2.3 TS 3.2.2 n

' v Ceme$'ts ccept(ance C,,. e,, *a ef ,

... . . . . . . . . B-32 l

FlNAL RESULTS2-su-29 A"'TACHMnc 6.8

. Page 2 cf 3

~

orth Ar. a Fower Statica Unit ,2_, Cycle 1 startup 03-25-80 startup Physics Tests P.esults and Evaluation Sheet

. )

Test

Description:

/D TL::1; MAP. ARO 2-Si*-29/ (BASE CASE FOR DROPPED RCCA D-10; 50~.

PO?.T.(

Feferencel Procedure ::ueber/Section: Sequence Step ;;s=ber: 73.3 -

l 1 katk Positions (steps) l RC Temperature ('T): 'Iref 1 j T*tt Power Level (*T.P.): 50:5 Cor.itions spa: 228 SDs: 228 CA: 228 other (specify):

(.:a si-a) C2: 228 CC: 228 CD:213:15 mst have y,33 :hi=bles RCCA:

TII Car.k Positions (steps) RCS Temperature (CT): 54'S.S~

Test Tower Level (TT.P.): ,5/f 774 f// f/SO ConJftior.s SD3: 2.t? CA: 2.'2 P Cther (specify):

SOA: '22.7 *

(Ac ual) C3: 2.2. g CC: 2.2. 8 CD: 2.1 +~

RC*A:

/ (,2 4 - h e'm h[f S 8/ 5 Date/Ti:e Test pg yg, ECTICr=*d: 9// 7l3o a'a' 1~~~ 77d1//f/WO 4

1:AI. RIL. ,.

MIA$t*PID PARA.*%!IR ASSY. ?".R. T*.'v. la:CLEAA T,'l, TOTAL EIAT Qt;mK-(T t (cescription)  % Diff. s..c.C.PY RISE ECT TL "E ':0!

r CEA:C;EL P0;tTR TILT

(--

p p)

, CEr.:C:r:. rAcTer. rAC on u lo (oP n ir_ 17x +111.kp"'= c.n slitbo 41 #

,,4,(, . ,* y ;:y

_ ,,oogy

easured Value +.r$?,' A .To / 'c 8G 2'd. E *" O E

• 4

. Test Design Value M M $ /.02.

Fascits (Ac tumi Cen'itio ns )f d A f.' 4 0 9

/

+

1CC for F,10.9 s

g,,,g;3 y,1,, + 11: ger r co.9 NA u $1.02

(*esign Co=ditices (7 i 43,7 p r) 20AP 7905 taference VCA.P-7905 NA EA Rev. 1 RIT.1 r AM1.55x(1+.1(1-p)]

< r .:.is . 6t.3/n ed.s r TSAK/ Tech Spec KA .

n Acce;ts ce g

• h*K3P(3L*d , f'e :' *

• d'8 ' '." 8 Cri:eria Reference EA TS 3.2.3 TS 3.2.2 NA ti j Cem ents-A Q'g'4 g/g

• cewietee ny 1. p/ fa/L u view 4 sy dI/ E j

~

/

B-33

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. . . . ~ .. . .. . . . . _ ...-. . .

~ '

NAL RESULTS Page ras3 of_ 3...

l Worth t.ans Power Statiott Unit 1 Cycle L Startup l Startur Physics Tests Results and Evaluation Sheet l . ..  !

I Test

Description:

INtEORAL IdD WCE 11 TOR DROPPE5 ECCA D-10; $0: POWER Reference Procedure Numicr/See: ion: 2-SU-29/ Sequence 5:cp 1: umber: 7g II 2,s=k Fesition.s (s:en:) RCS Terperature (*T):*ref : 1 Tes: Power Level ( T.P.): sets Conditions 50/.: 228 SDE: 228 CA: 228 Other (specify):

(Design) CB: 22s CC; 2:s CD: 213:15 RC"A: D-l'O moving III Bank Po itions (steps)

Test ROS Temperature ('T): g(,4,9 Conditlocs SDA: 22S Power Level (IT.P.): g g SD3: 7.za CA: At3 .

Other (specify):

(Actual) CB: 11 S CO: ELS CD: 2.s 3 O D.so -ovmc, , ,

Date/ Time Tes: 9//S /80 .

Perfor:::ed: .o35o -

F.casured Para eter ID-10; INTI RAL WORTE CT ROCA D-10 *

(description) g IV 1 , .

' F.easured Value ID //o. </ > .

Test DesiEn Value Results (Actual Condi:icas) ID-10" /07 !/(s M

• Desi;:n Vclue (Desig.Condi:icas) D-10= 107 2 16 pcm .

P.cf erenc e Vepec NTI Technical F4por: No.106, Revision 1, Tehrcary to-V TSAR / Tech Spec "(I D-10) I 1.0I. f,250 pcm .

Acceptance Crit eria Reference TSAR See:1on 13.2.3 .

VI Cor=ents CC&~PTAned' LLC / TECTA MET Ccepleted B '

• Reviewed By .

M

. / . ..

I i

E-31

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A"': AOMEN"* 6. 3 l 5, .

Page 1 of 3

\ '

orth Anna Powir 5:scica L'ni: 2 Cycle 1 Star:up 03~'5-80' Startup Physics *asta Results and Evaluacian Sheet ,

I Test :escription: : /: TL*:% SP- vi inferenca Procedure ::6. bar/Sec: ion: 2-SL*-29:h Dropped. ROC;. E-10: 50: P ver seguence $:ap iumoer: g ,g-II har.k Positions (steps) fR:3!a=perature ('T) : Tref 2 1 Test Power Level (17.P.): 50:5

• d i " * *

• other (specify):

• 5 A: 223 508: 228 CA: 228 l C2: 223 CO: C:

a: 0 212:13 ist have > 38 thi=bles I 10:A: 72 D-1 0 i

III 1.nk Positions (steps) RCS Tc=peratu== (CT): 563*3 i' Tes: Power Level (:T.P.): f o, 72

• 34 a.ie r.s

'.Ac t ual) 5A: 218 5:3: 2.1[ CA: 2. A f Cther (spec.ify):

• C3: 22p C:: 2.27 CD: 287 IEEA* M-to et o oseetu=e 1e,: t//f*/Po 0 U' U V Per f o r= e d : 0 7 /0 a pg.f

• 2*M. F.I:.. .

(',': *'^'*""~'**

{d e sc rl; tie r.)

^'~^' '

'"-** "' 'i' ' * ~ ^ * * ' ' * ' ***"'*'-

• *1ff. ._,,, ._,. _ , ,,,, , , , , ,

,- crxcer_ rA=:r. rAca urze(crzz t r* 9.c+ M,.; 'n

aasured Value 1. 6 l$~ 2.4 L3 /./f20 I 2.f.{cef Af ,  ;

e 3 tep fer Pg Ic.7  ;

7est lesults Dest:n Value (Actual Conditie s i a

W* b I #'d f'70 NA

• gA l+ 10: !or P 120.9 l

s :esig. Value  ; 15 for P g*:.* 1,7c' n p

(:esign Cg:ditiens'; (y . ;,,, y p. .;) .

i Reference V A?-7?05 VCAP 8717 l

. Er.~.1 M ^ '

N -- .

r T5AR/ Tech Spec n TH <1.!$m

- +.:(1.p;3 +*.:.ise

• u w , e=.a n '

l Acca;:a:ce

[x(1-?m20G  ; { :..u a u.3 ,,<.2 Criteria Leference n is 3.2.3 TS 3. .: , g WCT I y; Accef*tMCt. c rMe rik r

. c-e..s ..

• In:1udes 15: unc ertaa.::y: referected to SC: sever. Se value used in :te <

accace..: **.alysis is 1.69: refere :ed to 1000 pcver.

t c:=plesee ry b1 , b F.eviewed Iy /. ImA -

l I

B-35 t

~

F NAL RESULTC2-=-'" A"'IA3MEIC 6.11 Eorth Anr.a Power 5tation L' nit Cycle ,1, Startup Page 1 of 4 C3-25-80 5tartup Physics Tests Results and Evaluation Sheet I Test

Description:

't/D TLL: EAP- AT PC'aTR, NI CA .If, RATION Reference Procedure !!unber/Section: 2-SU- 30 sequence step :<=ber: gt3,2 II I.ac.i Positio:s (steps) RCS Te.:perature (OT) : Tref 2 1 Test Power Level ("T.P.): a.73 Conditier.s (Design) s3A: 228 sDs: 228 CA: 228 other (specify):

C3: 228 CC: 228 CD: AR

• Pcts: have > 38 thit61es ECCA: NA -

III Rank Positions (steps) RCSTe$perature(OT): I~72 / 'F Test Cond.71ons Power Level ( T.P.): h,f-g-scA: 426 3DB: ZIS CA: Et# Other (specify):

(Actual) C3: IZ6 CC: gas CD: Its

• • '^' " 4 7 m.-,em Date/ Time *est f/ZJ/A' Perfor.ed:g34c o ggo 2*.;F.. REL. ,,

MIASL7,ID PARKC IR ASST. P'."R. I,'.T.W.

T.'g,

' T['n IC M M @m..T (descri; tion)  : Diff.

g. .g

. E::T!!ALPY RISE F.0T TLC: 1!CI C M *::El Pot!.* *:LT p CH.C;C. TACTO?. FACE?. PA!!O i'; FIR;

(- '

n- 3.4 6 :(gcoM

/.597

.:easured value 4gg ,ygg f.974 1.cc3s -

Test !ct 4 c li zo.4

?.e: ult s Design value (Ac:ual Cenditions)I/d M/g4I g g 6 f,02

+

_ 10 for P 10.9 i testgr. Value

• 15 for P <0.9 NA

,  ::A g 1,0; (Cesig: Ccaditice.s) ( p . A3 g y p.r) 4 1

Refere=ce LTAP-7905 XA a ECAP- Z 5 Tiv.1 F.". *. :

N -l .

LE"l.55x 1+ .2 (1-Pili ri 22.te * *td/ri *.s

' T e V TSAPJ!ach Spec MA EA Accep amee

[2[1-F2P(BOh q (:s.:a a Mal a p:

. 8.3 Criteria Lal e r e e.c e xA T3 3.2.3 IS 3.2 gA

, VI Carments gy,cy)tsW' C$/[bA WT I m

[M I/ Q"

' completed ay Revie cd ay M>

l/

i B-36 1

( -

e<

i .'

FINAL RESOLTC,.,,_,,

A':"ACOCC 6.11 Eorth t. as Power Station Unit 1 Cycle 15tsetu?

. ,K Pap 2 e 4 03-25-C0 Startup Physics Testa Eesults and Evaluation Sheeg I Test

Description:

PJD 7'4*% P.AP- AT PC'*ER, NI CA1.IERATION Reference Procedure Eu=.ber/Section: 2-SU-30 seguence step Number: 25 3 II

• hack Positions (steps) RCS Temperature ('T): Tref 2 1 Test Power Level ( T.P.): s75 -

Coswittion* s:n: 228 CA: 228 Oth** (*P*Cif7 ):

• sDA: 28 (D**182) Ca: 28 CC: 228 CD: AR lt2s: have - > 38 thi bles RCa: NA .

~'

pas 6t/a>

III Rack Positions (steps) RCS Ter.perature ('T): 571. 25 *1~

Test Power Level (:T.P.): 74,. M Cond :1ons SDA:126 sDB: 428 CA: 2.zB Other (specify): .

(Actual) C1:Z26 CC: Z28 CD: M i %

'="' *

. 47 ru-eus Deta/ Time Test 9/A i[8' Perfor=ed: M _ 0655  !

l'JI. R L. ,, -

msuD mxcn Asst. m . rg,.c:C:.uR r . Te!.u. m- x.m -

(description)

• Diff. g 7

" ' " ' ' ' " ' ^ * " " ' " "

O ,, .

m - a, a n

,,,,,,e, ,,z,e s's ~ G " w I,3 76 2. 03 o i.co37 tw" M f;

• M P.e ts ual C ditt:ns) M .0L

. + 10 for P g20.9 Design Value R g

! 1.5% for Pi c .9 g 1,0; (Design C.nditions) (p 43,7 pyy}

Reference V".J.P-7 905 NA  ;;g VC -7 5 *,3 RIV.1 Art.;

TSAR / Tech Spec T"N"1.5 A< 5 x [1+ .2 (1-p ' :2.t*

• unth s *d 8 Y KA

• yA Acceptante (* bl'E8P (80)] , r, p.as

• Hos a r? 3 Criteria .

Reference KA TS 3.2.3 73 3.2.2 ya

. VI Ce m nts .

fiff M 4U" & Y lA N W

() . ..

R#[

c =p:.t.e my a wi.v.e my c.d M B-37

FINAL RESULT 3 2-SU-30 Morth Astaa Power Station L' nit

. ATTACFJEN'" 6.11 Cyclel Startup p,9, 3 og 4 cartup Physics Tests Rasults and Evaluation Sheet 03-25-80 I Test Descriptions !!/D TLC. .'*AP- AT POL'ER, NI CALIBPJsTION Reference Procedure Nunoer/Section: 2.st;_30 Sequence Step Nu=her: 3g.4 II ' &ar.L Positions (steps) I 2CS Temperature (CT): Tref i 1 Test Power Level ( T.P.): N75 Conditions CA: 22g Other (specify):

SDA 228 SD3: 228

( esirs) CD

.Cs: 228

• CC8 228 AR MusC have > 38 thirbles

• RCCA. yg i

og, Bank Positions (steps) RCS Temperature (OT): 5 7/.4 'f .

Tes CondCtions Power Level ( T.P.): 7f, SDA: 218 SD3: 2%8 CA: 424 Other (specify):

(Actual) CE: Lt6 CC: A16 CD:th .

RCCA: ,

$ ? W'm au's Datente. est slule -9/ w forforced t z.;"f3 pgg J

2*I. RIL. ,, .

NIASURD PARA!l ITER (description)

AS$Y. P".%.

Diff.

T{K, tc m

• y t'I, ;c g g gg.g (3 p) C."11ALPY RISE ECT TLCI HDT CHA*:::EL P0tt TIL; p C&u~.;C. TA0TCF. FACTOR pa;:0 (qrty,;

k- 17 47:inc Q, = o.99 r7 #'#P /' 7 AF # at

}*easured Value

. + 'd e O N /' 4z '

Tcst Design Value t10 % **nt R Eo.4 as/1 Rosults (Actuni Cenditi:r.sS !/5"f. p.or ? 4o.1 NA e

- f,o g

10

fet P gt0.9 Design Value  ; 15% for P g<0.9 NA gA g t,c:

(Design Co=d'.tions) (p , g,,7 g )

1 Reference VCAP-7905 NA g vcAp.7905 -

EEV.1 L:7.1 r,w :ec.s ,,ec 0 2 55 4 2<1-P! 4 :> " - ~ o Acceptance ,2 (l*P2 P (30)] ( .6.k a H4s e e?.3 Criteria .

Reference xA TS 3.2.3 IS 3.2.2 y

. 71

. Cormen ts .

rp W's' C fs&F D A W

( ...

Cc::'pleted By [ / Revleued By b h.

• U B-36

I

\

l l

'q' Ar-. R.,_SJ, t LTs  ;

2-su-20  ;

. . Berth Anna Power Statie Unit 1 Cyclel Startup AT'I'ACEMENT 6.11 l

/

.. . Page 4 of 4 startup Physica Tests teaults and Evaluation Sheet 01-25-80 I

I Test cascription: :t/m TLI:= n?. AT POWT.R, NI CA!IEF.ATION, i DA*A F.A.P ,

Reference Procedure haber/Sectian: 2-SU-30 sequence step N eber:

g l l

II &ank Fositions (steps) 105 Temperature ('T): Tref a 1 [

Test Power Level (:T.F.): s73 i

--

• 0'h*' ("Petif 7):

ssA: 228 sDs: 22S CA: 223 D: 228 C: 228 88 AR hat have > 33 thi bles l sc:A. -

NA  !

ITI Raak Positions (steps) EC3 Temperature ('T): S7/.o*F Tes t Power Level (IT.F.): 77* 3 -g .

cand.rtion' smA:n B s a: Zzs CAs r.zs other (specify): l (Actual)' CB:1.28 CC: 228 CD:**9/Faf W **

k } r:1:~,stes t.,me Teec e/es/-

Performed /=/-/J22 2*J..

J REL. .

EIASL'KI: PAP.A."I~IR AS$Y. F'."A. . T*h, tlll:CLIAR T', T0*4 EE.C Qt:A27A.:7 E

(c a.s crip tic a)

• Diff.  !

, g.p g . . ZW'.ALFI RISE EOT TLL"" ECT CUA::::IL

. F0;"l7 TILT l

[.,

p

".t'?;I:. FACT 0r. TA :ct RAT:0 (grTI) I zy 3hggosz  !

Maasured Value l 382 I.975 f. cozy i 4.ffresh s042 i

WT,#.st f3 F04 I Test l Design value Rasults (Ac tual condit*.onsN/TI.F.* h 'd7 Nd M SlM i 3 ic: for P 10 g 9 .

+ 15: for i eo.9 8A Desig. Talue g gA 3 g,g: [

(Design Ccrditions) gy . A,,, 7,y) t Reference VM-7905 MA gg vcAF.;M5 I

. RIV.1 F."".1 TLAZ/ Tech Spec TM **1.55x [1+.2 (1.g 3 r* *2.te e ua)/*: ** 8  !

y NA EA i Accep tance [* (l~887 N  ; i:6.as a nas a ,:e.s ,

Criteria .

Lafarasea . KA TS 3.2.3 T3 3.2.2 g g

. Coments . t W$AWff f/Wk C-.iletedty b m I I

~

Reviewed sy U.3. M [

/ v-

. 'B-39 '

1 l

l .

Flb.l AL RES U,._.--,!b 2-su- 39 5erth Amma Power Staties Cate a Cy.la y Startup heartop Physica Test.: Raoults and Evalaation Sheet I

Test

Description:

M/D TIEI MAP- 100% POWER (Equilibrium Condition)

Re f erence Procedure habar/Section: 2-SU- 39

• seguance step Em6er: /04' II Bank Positions (steps) 205 Tourperature ("T) : Tref Test

'* *dI '1* ** Power Laval ("T.F.): 100 .

• sm: 228 sns: 228 CA: 228 Other (sP*cify)*

Q: 228 G AR

• CC: 228 tc::A: Nst have 3,,38 thimbles NA III Bank Positions (steps)

T***

ACS Tamperature ('T): 577.6 C* N "* Power Laws 1 (IT.F.): 97.5 N#} s:Ar 228 EDS: 228 CA: 228 othar (specify):

Q: 228 CC: 228 2: 210 BCCA: NA 47 Thimbles Dece/ Tina Test 10/31/80 /

Forformed: 1112 - 1341 -

!".AI. LI;..

MIASL~ RED FARAMITIR A33Y. Pk'R. F*' . IC.TCI.ZAR T',

N TOTE IIAT FA.;;A* T (dascriptien) I Diff.

3 p,. p ) C.T11ALFT 113I ECT FLC ECT CEA:::IL .ac- y 7ti.

p CECCC. FACTom FACTot pa;;a (qrig;

( D' -3.9for P=0 94 C-$

Taasured Yalue 1.367 1.958 1.0037

+4.7forP=0.p9 y ,

Test Design value -10%for P*>0'0 '

!asults (Ac tual Cenditierur15*!forP)<0.9 NA NA , 1.0.3 2 102 for Fgt0.9 Design Valua  ! 15 for F g*0.9 EA (Dest;n Conditions) EA g 1.02 (p . g,,7 py7)

Reference W.AF-7905 EA y Ltap-7305 1Ev.1 3, i ,1 Y TEAR / Tach Spec ' * (' I' ^* * "

EA EA A m ., tan . r e-m c.=g  ; ,3... . .m i .:..a critaria Rafarence EA TS 3.2.3 T3 3.2.2 g

. YI Coveents Acceptance Criteria Met. .

i i

Costpleted By _ d. . [ 3eviewed gy C, j 3 t

B-40 .

1

. - - _ - - ~

J

4 APPENDIX C i MODERATOR TEMPERATURE COEFFICIENT ROD WITHDRAWAL LI> FITS '

~ Prior to the startup of North Anna Unit 2, Cycle 1, the occurrence ,

of a positive moderator temperature coefficient of reactivity for the )

North Anna 2, Cycle 1 core had been predicted ( at the HZP, ARO condition. i The startup physics testing program verified the existence of this posi-

tive moderator temperature coefficient. Because the North Anna Power Station Technical Specifications (T.S. 3.1.1.4)(7} currently prohibits l the operation of the unit with a positive moderator temperature coefficient during normal operation ~, it. was necessary to develop a set of operating restric-1 1

tions in terms of rod withdrawal limits as a function of RCS boron concentration and power level to insure that North Anna Unit 2 would be

) operated with a negative moderator temperature coefficient.

I The rod withdrawal limit curves were developed by using the measured ,

HZP temperature coefficient data obtained during the startup physics test i program. A 0% power base limit curve was first developed using equation 1 '

with an additional 0.5 PCM/ F (s40 ppm) added to the measured data to ,

l insure conservatism in the calculations. *

+

1). CB0 "

BM T

E i

R -

i where; CB0 Critical Boron Concentration for Sp/6T = 0 PCM/ F.

Cfg = Critical Boron Concentration _ (Measured) in PPM. '

T[ ~ = _ Measured Temperature Coefficient, 6$/57 in FCM/0F, f TE =

Uncertainty Factor in T[ Measurement (0.5 PCM/0F.)

• l

' t C-1

^

l

'\

R = Rate of Change in 60/6T with Respect to the Change in Boron Concentration (= 0.0152 PCM/0F/ PPM) .

i = Denotes Specific Rod Configurations.

Table C-1 su=sarizes the data used to develop the E2P base limit curve. Then, several;at-power conditions were developed relative to the 0% power " base" limit curve. Tbese additional power level curves (257.,

507., 757., and 100%) were obtained by applying the change in boron con-centration *. negative reactivity effects (power defect) to the base, 0% power le mondition. Table C-2 sumcarizes this infonnation and also includes the relative 07. power level points.

The final coderator coefficient rod withdrawal limit curve is given in Figure C-1. Figure C-1 is specific only to North Anna 2, Cycle 1 and it applies throughout the entire first cycle of the unit or until a negative =0dcrator te=perature ceffic'ient for the ARO configuration is verified by measurement.

C-2

Table C-1 NORTH A'!NA 2 - CYCLE I BOL PHYSICS TEST CALCULATION OF HZP MODERATOR TEMPERATURE COEFFICIENT LIMIT CURVE r

.. . Bank Position C (Steps) BM M B0 1 A B C D (PPM) (PCM/gD F) (PPM) 1 228 228 228 228 1332 +1.39 1208 2 228 228 228 0 1193 -2.11 1299 (Overlap Positions are: D/30 and C/158)

C = C +

B0 BM ~ m E R

j where; C =

Critical Boron Concentration for 6c/6T = 0 PCM/ F.

B0 1

C BM

=

Critical Boron Concentration (Measured) in PPM.

T = "easured Tempe.rature Coefficient, 6c/6T in PCM/ F.

T E = Uncertainty Factor in Tf Measurement (0.3 PCM/ F).

l 2 =

Rate of Changc in 60/6T with Respect in Boron Concentration (= 0.0152 PCM/goF/ the PPM). Change i = Denotes Specific Rod Configurations.

J 4

i 4

i i

4 C-3 1

__, _ . - - . . - . _ _ . . __ - . , . . - _ , , . _ . _ _ _ _. , , . . . , ,-- y

i Table C-2 NORTH ANNA 2 - CYCLE 1 BOI. PHYSICS TEST MODERATOR TEMPERATURE COEFFICIENT ARO CRITICAL BORON CONCENTRATIONS vs. PERCENT POWER FOR 40/4T393,= 0 PORER TEMP Design C Design a C Level (L) ( F) (PPMf (PP..) (hhM) 0 547 1174 0 1208 25 555.7 1246 72 1280 50 564.4 1336 162 1370 75 573.1 1424 250 1458 100 581.8 1511 337 1545 i

C-4

i l

l Figure C-1 NOR'.H ANNA UNIT 2 - CvC'2 1 l

l ue ts,s. p g aw e. #m A.,v.,=

n.imvT.o g Pg M9***9

4. a G r u . .gme=v E-w.p'*9.%'.=s. *t s.** w -%99 A87,?>d n a- rM h.a *r_*'e*.c,=*4* o . r_ *'* vw d=88*T .

t i*

ea 1600

f. _. . . . .- ~- ..

..._......f

.__ . - . . . . . . . ~

N-1c0g p

ITPO POD INS,_.R. E, , I.v., . .S . . ._

~.' u w._ . . -*- n & ~--:._. -< -W  %

. _ _.._.._ __f_ . _ _ . _ _

5%

1400

_f _

m -- _

205 w.._...

__=

3 p -

r.-

3200 .._. ,.

ag 1 .

2:

w r '

NOTE : OPETdTICM NOT PEFXITTED -

@S t g ------S__.__ n30\r .nr c..r._ _h uA r.S --

~

ts 1000 _ . . .

O

_.: h.. .: - r --- _ .. .._ -

t t;. .._.__... .

.._._. ..~._ _

v ......._..._...._

m 830

_ .. . . _ . _ . . .. t.__..._._._._.

..t.._..______._.__..

. . _ . . ..t. _.t. . .._.._...

.__._ m_._._._.

. . .. r I .

. .... ~ ....... . . . .._ . __.

. _ . . . . ... .~. ...._.6.....

l.

t. i I

I t' t

I 1

6f r.

. 't I

BANK C 100 140 180 228 BANK D n ,

• ** vn C,'# w

, . , , ,y . , . , , ..,

14. U ACv 4VU d6D cvErJt.AP 3ANK POSITION (S EFS)

C-5 l

1 1