ML18139A222

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Forwards Control Rod Reactivity Worth Determination by Rod Swap Technique.
ML18139A222
Person / Time
Site: Surry, North Anna  Dominion icon.png
Issue date: 05/12/1980
From: Thomas W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Harold Denton, Varga S
Office of Nuclear Reactor Regulation
Shared Package
ML18139A223 List:
References
NUDOCS 8005140480
Download: ML18139A222 (62)


Text

.

VIRGINIA ELECTRIC AND POWER COMPANY

  • soor514 o'Y~'
  • p RICHMOND,VIRGIN.IA 23261 May 12*,- 1980 Mr. H. R. Denton, Director Serial No. 384 Office of Nuclear Reactor Regulation FR/EJL: ceb Attn: Mr. Steven A. Varga, Chief Docket Nos. 50-280 Operating Reactors Branch No. 1 50-281 Division of Licensing 50-338 U. S. Nuclear Regulatory Commission 50-339 Washington, D. C. 20555 License Nos. DPR-32 DPR-37 NPF-4 NPF-7

Dear Mr. Denton:

~

SURRY AND NORTH ANNA POWER STATIONS.

CONTROL ROD BANK REACTIVITY WORTH TESTS Enclosed for your review are 10 copies of the Vepco Topical Report VEP-FRD-36, "Control iod Reactivity Worth Determination By The Rod Swap Technique."

Currently, control rod bank reactivity worth tests at the Surry~

and North Anna Power Stations are performed using the dilution/boration technique. This report presents an alternate test technique. Included in the report are the results of the two rod swap demonstration programs that were performed during the initial startups of Surry Unit 1, Cycle 5 and North Anna Unit 1, Cycle 2 which are used to validate Vepco's use of the rod swap methodology. It is our intention to implement rod swap as the primary test technique to determine the reactivity worths of the control rod banks starting with the reload physics testing program for Surry Unit 2, Cycle 5.

This report has been reviewed by both the North Anna and Surry Station Nuclear Safety and Operating Committees and the System Nuclear Safety and Operating Committee, Further, it has been determined that the material described in the report does not involve an unreviewed safety question as defined in 10 CFR 50.59.

VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. H. R. Denton  : I We area.ware that a feewill be required for the.review*of this topical repbrt,*i;:tnd we will transmit the assessedfeeupon completion.of the review. If you have any questions on the material in this topical report,* please contact Dr. E. J. Lozito* (804:,..;771:...4375).

Very truly you~.

df-)~7.V~

W. N. Thomas Vice President

.Fuel Resources.

Enclosures cc: Mr. Robert. A.,* Clark,. Chief Operating Reactors Branch Naz 3 Mr .. B. Joe Yotmgblood, Chief Licensing Branch 1 Division of Licensing

a

  • so 0'514 0 ;,'~

VEP-FRD-36

(-)

CONTROL ROD REACTIVITY WORTH DETERMINATION BY THE ROD SWAP TECHNIQUE BY T. K. ROSS W. C. BECK Reviewed By:

llh,w-;.. lSmi/

M. L. Smith, Supervisor Nuclear Fuel Engineering Approved By: Approved By:

JYJdc-1-.

M. L.

~

Bowling, Directr Nuclear Fuel Engineering Nuclear Fuel Section Fuel Resources Department Virginia Electric & Power Company Richmond, Virginia May, 1980

.... e

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

i

,I e

ABSTRACT The methodology for determining control rod reactivity worth utilizing the rod swap technique is presented. Data obtained during the startup of Surry Unit 1, Cycle 5 and No;th Anna Unit 1, Cycle 2, which validates the methodology, is also presented. This methodology is applicable for conducting control rod reactivity worth tests at Surry and North Anna.

ii

ACKNOWLEDGEMENTS The authors would like to acknowledge the cooperation and support of the Surry and North Anna Power Station personnel in performing the tests documented in this report. Additionally, we would like to acknowledge the effort of Mr. M. C. Cheak in providing the North Anna design data. We would like to thank Ms. C. E. Bullock for her patience and accurate typing of the entire report.

iii

,I

  • .- e TABLE OF CONTENTS SECTION TITLE PAGE NO.

CLASSIFICATION/DISCLAIMER i ABSTRACT ii ACKNOWLEDGEMENTS iii LIST OF TABLES V LIST OF FIGURES vi

1. INTRODUCTION 1
2. ROD SWAP REACTIVITY TESTS 4 2.1 Test Description . . 4 2.2 Test Data Analysis Methodology 5
3. CALCULATIONAL METHODOLOGY 13 3.1 Introduction. 13 3.2 PDQ07 Discrete Calculations 14 3.3 FLAME Calculations 15 3.4 Design Predictions of the Critical Reference Bank Positions . . . . . . . . . . . . 16 3.5 Design Predictions of the Integral Worth of Each Test Bank . . . . . . . . . . . . . ... 17
4. TEST RESULTS EVALUATION METHODOLOGY AND REVIEW CRITERIA 38
4. 1 Background . . . . . . . 38 4.2 Rod Swap Test Evaluation and Review Criteria 39
5. ROD SWAP TEST RESULTS 41
6. VALIDATION OF THE ROD SWAP METHODOLOGY 45
7. CONCLUSIONS 49
8. REFERENCES 50 APPENDIX: Impact of the Rod Swap Tests on the Hot Zero Power Startup Physics Testing Program for Reload Cores 51 iv

e LIST OF TABLES TABLE TITLE PAGE NO.

2.1 MEASURED CRITICAL POSITION DATA ADJUSTMENT

SUMMARY

9 2.2 MEASURED TEST BANK INTEGRAL WORTH

SUMMARY

10 3.1 PREDICTED CRITICAL POSITION

SUMMARY

20 3.2 PREDICTED TEST BANK INTEGRAL WORTH WITH THE REFERENCE BANK AT THE PCP . . . . . . . . . . . . . . . . . . . . . . . . 21 3.3 PREDICTED !EST BANK INTEGRAL WORTH WITH THE REFERENCE BANK AT THE MCP . . . . . . . . . . . . . . . 22 3.4 PREDICTED TEST BANK INTEGRAL WORTH

SUMMARY

23 5.1 ROD SWAP TEST RESULTS 42 6.1 SURRY 1, CYCLE 5 ROD WORTH RESULTS 47 6.2 NORTH ANNA 1, CYCLE 2 ROD WORTH RESULTS 48 A.I HOT ZERO POWER STARTUP PHYSICS TESTING PROGRAM 52 A.2 HOT ZERO POWER STARTUP PHYSICS TESTING PROGRAM WITH ROD SWAP . . . . . . . . . . . . . . . . . . . . . . . . . . 53 V

,, *1 FIGURE e LIST OF FIGURES TITLE

  • PAGE NO.

2.1 SURRY UNIT 1, CYCLE 5-MEASURED REFERENCE BANK WORTH, B BANK WITH ALL OTHER BANKS OUT. . . . . . . . . . . . . . . . . . 11 2.2 NORTH ANNA UNIT 1, CYCLE 2-MEASURED REFERENCE BANK WORTH, D BANK WITH ALL OTHER BANKS OUT . . . . . . . . . . . . . 12 3.1 SURRY UNIT 1, CYCLE 5-PREDICTED REFERENCE BANK WORTH, B BANK WITH D BANK IN . . . . . . . . . . . . . . . . . . 24 3.2 SURRY UNIT 1, CYCLE 5-PREDICTED REFERENCE BANK WORTH, B BANK WITH C BANK IN . . . . . . . . . . . . . . . . . . 25 3.3 SURRY UNIT 1, CYCLE 5-PREDICTED REFERENCE BANK WORTH, B BANK WITH A BANK IN . . . . . . . . . . . . . . . . . . 26 3.4 SURRY UNIT 1, CYCLE 5-PREDICTED REFERENCE BANK WORTH, B BANK WITH SB BANK IN. . . . . . . . . . . . . . . . . . 27 3.5 SURRY UNIT 1, CYCLE 5-PREDICTED REFERENCE BANK WORTH, B BANK WITH SA BANK IN. . . . . . . . . . . . . . . . . . 28 3.6 NORTH ANNA UNIT 1, CYCLE 2-PREDICTED REFERENCE BANK WORTH, D BANK WITH C BANK IN . . . . . . . . . . . 29 3.7 NORTH ANNA UNIT 1, CYCLE 2-PREDICTED REFERENCE BANK WORTH, D BANK WITH B BANK IN . . . . . . . . . . 30 3.8 NORTH ANNA UNIT 1, CYCLE 2-PREDICTED REFERENCE BANK WORTH, D BANK WITH A BANK IN . . . . . . . . . 31 3.9 NORTH ANNA UNIT 1, CYCLE 2-PREDICTED REFERENCE BANK WORTH, D BANK WITH SB BANK IN . . . . . . . . 32 3.10 NORTH Al~NA UNIT 1, CYCLE 2-PREDICTED REFERENCE BANK WORTH, D BANK WITH SA B.AJ."l'K IN . . . . . . . . . . . . 33 3 .11 SURRY UNIT 1, CYCLE 5-PREDICTED REFERENCE BAl~K WORTH, B BANK WITH ALL OTHER BANKS OUT . . . . . . . . . . . . . 34 3.12 NORTH ANNA UNIT 1, CYCLE 2-PREDICTED REFERENCE BANK WORTH, D BANK WITH ALL*OTHER BANKS OUT . . . . . . . . . 35 3.13 NORTH ANNA UNIT 1, CYCLE 2-DETERMINATION OF ~~(M) FOR TEST BAI.~ C . . . . . . . . . . . . . 36 3.14 NORTH ANNA UNIT 1, CYCLE 2-DETERMINATION OF ~Rp(M) FOR TEST BANK C . . . : . . . . . . . . . . . . . . . . 37 5.1 SURRY UNIT 1, CYCLE 5-REFERENCE BANK WORTH, B BANK WITH ALL OTHER BANKS OUT . . . . . . . . . . . . 43 5.2 NORTH ANNA UNIT 1, CYCLE 2-REFERENCE BANK WORTH, D BANK WITH ALL OTHER BANKS OUT . . . . . . 44 vi

Section 1 INTRODUCTION The purpose of the control rod bank worth tests, which are performed as part of the startup physics tes_ting program, is to verify selected design statepoint calculations and thereby demonstrate the validity of the results of the calculational models used to predict control rod bank reactivity worths as part of the design process. This is done through a comparison of measured and predicted results for those selected design statepoints. The Vepco control rod bank worth tests traditionally have been performed using the dilution/boration technique. The dilution/boration technique involves exchanging the reactivity associated with the control rod bank of interest with the reactivity associated with the boron in the reactor coolant system (RCS), i.e., as control rods are inserted into the core, primary grade water is put into the RCS so that the boron concentration of the reactor coolant system is diluted. During this process, the core is kept nominally critical. The amount of each control rod bank motion is strictly limited such that the reactivity value associated with each movement is within the reliability range of the reactivity computer, which is used to monitor core reactivity and directly measure the reactivity worth of the control rod banks. The dilution/boration rate is established such that the reactivity exchange rate is compatible with the operational requirements of the reactivity computer. Typically, the reactivity exchange rate is 300 to 500 pcm/hour. For a typical reload cycle, the measured control rod bank reactivity has been approximately 5500 pcm (four control banks successively inserted). This results in a measurement time of between 22 and 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> (measurements are made during control rod bank insertion and withdrawal).

1

.. e The measurement of the reactivity worth of the control rod banks using the rod swap technique is an alternate method that can be used to verify control rod worths. The rod swap technique has been devised in order to reduce the amount of time associated with the measurement of the reactivity worth of the control rod banks without sacrificing any of the essential information that is derived from the performance of these tests relative to the current test methods. The benefits associated with the rod swap technique include:

1) the reactivity worths of all the rod banks (control and shutdown) are determined (in the past, the reactivity worths of the shutdown banks were not measured).
2) the time associated with the measurement of the reactivity worths of the control rod banks is greatly reduced, and
3) the boron recovery processing requirements (associated with RCS boration/dilution) are greatly reduced.

Implementation of this program enhances overall nuclear availability.

In addition to the conventional control rod bank reactivity tests, reactivity tests using the rod swap technique were performed during the initial startup of Surry 1, Cycle 5 and North Anna 1, Cycle 2. These side-by-side demonstration programs were performed in order to establish the technical basis for validating the rod swap methodology. The purpose of this report is to present a description of the rod swap methodology and the results of the side-by-side demonstration programs mentioned above; and show that the results of these programs validate the use of the rod swap methodology in future Vepco physics testing programs.

Section 2 of this report contains a description of the rod swap test procedure and the associated data analysis methodology. Section 3 describes the calculational methods used to predict the rod swap test results. Section 4 contains a description of the rod swap test results evaluation methodology 2

and review criteria.

Section 5 presents the rod swap test results. Section 6 presents the validation of the rod swap methodology through a comparison of the results of the side-by-side demonstration programs, and Section 7 presents the conclusions that can be drawn from the validation of the rod swap methodology.

The Appendix provides a description of the changes to the zero power physics testing program that will occur as a result of implementing the rod swap program.

The applicability of this report encompasses the use of the rod swap methodology by Vepco for the Surry and North Anna Power Stations.

3

Section 2 ROD SWAP REACTIVITY TESTS 2.1 Test Description The objective of the rod swap tests is to measure the reactivity worth of each control rod bank. The first step in the rod swap procedure is to dilute the most reactive control rod bank (hereafter referred to as the reference bank) into the core and measure its reactivity worth using conven-tional test techniques. The dilution rate is selected so that the rate of change of core reactivity is approximately 300 pcm per hour. At the completion of the reference bank reactivity worth measurement, the reactor coolant system temperature and boron concentration are stabilized such that the reactor is critical with the reference bank at or near full insertion. At this point, a boron endpoint determination is made, and an isothermal temperature coeffi-cient test is performed. Initial statepoint data for a rod swap maneuver are obtained by moving the reference bank to its fully inserted position, if neces-sary, and recording the core reactivity and moderator temperature. A rod swap maneuver is performed by withdrawing the reference bank while one of the other control rod banks (i.e., a test bank) is inserted. The core is kept nominally critical throughout this rod swap and the maneuver is continued until the test bank is fully inserted and the reference bank is at the position at which the core is just critical. This measured critical position (MCP) of the reference bank with the test bank fully inserted is the major parameter of interest since it is a measure of the reactivity worth of the test bank. Statepoint data (core reactivity and moderator temperature) are recorded with the reference bank at the MCP. The reference bank is alternately withdrawn and inserted a small amount about the MCP in order to measure the differential reactivity worth of the reference bank over this region. The rod swap maneuver is performed 4

in reverse order such that the reference bank once again is at or near full insertion and the test bank is once again fully withdrawn from the core. Statepoint data (rod position, core reactivity, and moderator temperature) are recorded in order to confirm RCS boron concentration stability. The rod swap process is then repeated for all of the other control rod banks (control and shutdown).

In summary, conventional dilution/boration test data are obtained in order to determine the reactivity worth of the reference bank inserted alone.

Rod swap test data are obtained in order to determine the reactivity worth of each test bank with the reference bank partially inserted in the core.

2.2 Test Data Analysis Methodology The reactivity worth of the reference bank is determined using the standard analysis techniques associated with dilution/boration rod worth test data. The reactivity worth of each test bank is determined from the measured reference bank reactivity worth data and the measured critical position data.

As outlined in Section 2.1, the data that are recorded during the tests include the following:

1) the integral and differential reactivity worth of the reference bank with all other control rod banks withdrawn from the core,
2) the critical RCS boron concentration associated with the reference bank being fully inserted in the core with all other control rod banks withdrawn from the core,
3) the isothermal temperature coefficient associated with the reference bank being fully inserted in the core with all other control rod banks withdrawn from the core,
4) the critical position of the reference bank associated with each of the control rod banks being individually fully inserted in the core, 5
5) the core reactivity and moderator temperature associated with the reference bank being fully inserted alone, and the reference bank being at the measured critical positions identified in Item 4,
6) the differential reactivity worth of the reference bank in the region of the measured critical positions identified in Item 4.

Items 1, 2, 3, 5, and 6 represent data that are obtained and analyzed using the current standard testing and analysis procedures. The measured critical reference bank position data, Item 4, are also analyzed in a straightforward manner. The analysis accounts for off-nominal conditions that may have existed during the test. These may include the following:

A) variations in the moderator temperature, B) variations in the RCS boron concentration, C) deviations from criticality with the reference bank fully inserted alone, and D) deviations from criticality with the reference bank at the measured critical position (MCP) and the test bank fully inserted.

The reactivity effects of Items A and B can be minimized through strict control of the RCS temperature and boron concentration during the test and can be quantified based on the test data. The reactivity effects of Items C and Dare measured directly by the reactivity computer during the test. Equation (1) is used to adjust the measured critical position data to account for off-nominal test conditions.

6

1-(ll~\

\llh/

J ( 1)

Where:

= the measured critical position of the reference bank adjusted for off-nominal test conditions.

MCP = the measured critical position of the reference bank.

llT = the increase in moderator temperature during the test.

= the isothermal temperature coefficient measured with the reference bank fully inserted alone.

= the increase in RCS boron concentration during the test.

= the boron worth coefficient.

= the core reactivity measured with the reference bank fully inse~ted alone.

MCP Pc = the core reactivity measured with the reference bank at the MCP and the test bank fully inserted.

(~~) = the measured differential reactivity worth of the reference bank in the region of the MCP.

These data adjustments were quantified as part of the data analysis of the rod swap tests performed during the startup of Surry 1, Cycle 5 and North Anna 1, Cycle 2, and are summarized in Table 2.1. It can be seen from the information in this table that the data adjustments are usually very small.

The reactivity worth of each test bank is determined from the measured A

reference bank reactivity worth data and the MCP of the reference bank for each test bank using the following basic reactivity balance equation:

7

  • (2)

Where:

= the measured total integral reactivity worth of the reference bank inserted alone.

= the measured integral reactivity worth of the reference bank inxerted alone from the fully withdrawn position to the MCP.

M T~R(M) = the total integral reactivityAworth of the test bank with the reference bank at the MCP .

As described previously, the value of the total integral reactivity worth of the reference bank inserted alone, RM, is determined using the dilution/

boration measurement and analysis techniques. The value of ~RM(M) for each test bank is determined from the .same measured reference bank worth data using the appropriate adjusted measured critical position, MCPA. Figures 2.1 and 2.2 present graphs of the measured integral worth of the reference bank for Surry 1, Cycle 5 and North Anna 1, Cycle 2, respectively, and illustrate the determination of the values of lRM(M). The total integral worth of the test A M bank with the reference bank at the MCP, T~R(M)' is determined from these measured data using the reactivity balance given in Equation (2). The deter-mination of the measured integral reactivity worth of each test bank from the Surry and North Anna test data is illustrated in Table 2.2.

8

TAllLE 2,1 MEASURED CRITICAL POSITION DATA ADJUSTMENT

SUMMARY

Measured Critical Adjusted Measured Reference Bank Measured Data Differential Critical Reference Test Position-MCP Adjustments Rod Wor'th Ban~ Position -

Bank (steps) (pcm) (pcm/step) MCP (steps)

Surry l. Cycle 5 D 186 -8 -5.4 185 C 123 - -9 -6.4 122 A 96 -14 -9.0 94*

SB 138 -14 -6.0 136 SA 171 -6 -5.6 170 North Anna 1, Cycle 2 I

C 164 +l -5.6 164 ll* 228 +16 -- 22b A 189 -10 -11. 4 188 S8 159 -3 -5.3 l 59 SA 200 -6 - 9. 0 199

  • MCPA "' HCP _ (Measured Data Adjustment)

(Differential Rod Worth) 1

'The Hc,asured Data Adjustment for B bank i:3 not applied to the HCP value (228 steps) since the HCPA value can be no greater than 228 steps. This Heasured Data At!justment is the amount of reactivity by which the total worth of B bank, inserted alone, exceeds the total worth of the reference bank, inserted alone.

TABLE 2.2 MEASURED TEST DANK INTEGRAL WORTII SUMMAl{Y I

I Adjusted Measured Reference Bank Refere.nce Dank Test Bank *T Critical Reference Worth to HCPA - Total Worth - Totnl \forth -

Test Bank Position - M RM *Tl*!

A llR (M) 1'.R(N)

Bank MCP (steps) (pcm) {pcm)

(pcm)

Surry 1, Cycle 5 I

D 185 148 1405 1257 I C 122 524 1405 881 Ii A 94 756 1405 ,:,49 I

SB 136 428 1405 977 SA 170 227 1405 1178 North Anna 1, Cycle 2 ---1 C 164 385 1069 68!,

Il

  • 228 0 1069 1085 A 188 226 1069 ~I...,

vpl..)

SB 159 420 1069 6.',9 I SA 199 139 1069 930 M

TllR(M) ., R!-I - llRM(N)

  • As indicated in the note on Table 2.1, the total integral worth of Il bank, i.nsc1:t,!<l alone, is r,r,:,atc,r than the total integral worth of the reference ba*nk, inserted &lone, by the amount of it I s !*lea.sured Data Adjustment (16 pcm). The total integral worth of Il bo.nk, T~\: ( , was determin~d 1~ith th~ rd°'('rcnc:e:

bank at it 1 s HCPA (i.e., fully withdrmm); T~R(M) "'1069 pcm+ 16'1,t, 2 ~ 1085 pcm.

FIGURE 2.1 SURRY UNIT 1 CYCLE 5 MEASURED REFERENCE BANK WORTH B BANK WITH ALL OTHER BANKS OUT 0

0 N ......,:1-'...,:_;-1!-"-+-!-i-  ; i i :  ; i i ;  :  : i :  ; ] 1 ; r  ;  :  ;  : i  ;  ; j j  ; '.-;~...-~1'_;_:- - :

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N ......;-'__,!-+-...,:-+--+--+-~I--o-+-:-+-+-,-+-+'1 ...,1-,., -+--+-f C (MCPA = 122 steps), /::,.RHCI) = 524 pcm  :-T-'.

  • 1 +-+--i-+-,-+-+,-+--'-,--++-t-t,-+-il-t-1-+-+-!'--l *4-1

_ -+--+->--1--+-+--'-:-11-...,1--+-+--+-i-+-_+-+1-+-~SB (MCPA = 136 steps), /::,.R~(~l) = 428 pcm +-

- ttI I I 1 i i I I

! I j ] SA (MCPA = 170 steps), /
:,.RM(':i) = 227 pcm J_

%:O u O I;

-,--+-+;--+-+-+-J,'--+--+-,-+-:+-'-,

i  !  :

...;,-+--i

,-1--1-..1.,-; D (MCPA = 185 steps), /::,.RM(l-1) = 141: pcm IT

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(.

FIGURE 2.2 NORTH ANNA UNIT 1 CYCLE 2 MEASURED REFERENCE BANK WORTH D BANK WITH ALL OTHER BANKS OUT 0

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40 80 120 160 200 2~8 BANK POSITION CSTEPSJ 12

,, L Section 3 CALCULATIONAL METHODOLOGY 3.1 Introduction The design information required to support the rod swap tests consists of individual control rod bank worths, predicted critical reference bank positions, and test bank total integral worths. The design data required to produce this

. f ormation in . are generate d using the Vepco PDQ07 Discrete (1) and FLAME (2) models. The PDQ07 model calculates core reactivity and power distributions in two dimensions (x,y). For data requiring an axial representation (e.g.,

any core configuration with control rods partially inserted), the FLAME model is employed.

The design predictions, which are required for the rod swap test, are determined from the following sets of calculations:

1) the total integral reactivity worth of each control rod bank individually inserted in the core,
2) the critical boron concentration with the reference bank fully inserted in the core,
3) the differential and integral reactivity worth of the reference bank as a function of bank position with all other banks withdrawn from the core, and
4) the differential and integral reactivity worth of the reference bank as a function of bank position with each test bank individually inserted in the core.

Items 1 and 2 are calculated with the PDQ07 Discrete model. Items 3 and 4 are calculated with the FLAME model.

13

' I, The design predictions for the critical reference bank position with each test bank fully inserted in the core and for the total integral worth of each test bank are determined from the above design data and basic reactivity balance equations. The methodologies used to generate these data are described in detail below.

3.2 PDQ07 Discrete Calculations The total integral reactivity worth of each control rod bank individually inserted in the core is required in order to determine the identity of the reference bank. In addition, these bank worths are used in the reactivity balance equations described in Sections 3.4 and 3.5. The total integral worth of a control rod bank individually inserted in the core is calculated by the following equation:

k. - k Bank Worth (pcm) = k.i X k 0

X 10 5 (3) i 0 Where:

k 0

= eigenvalue from a PDQ07 Discrete run at hot zero power, all rods out critical boron concentration, with all rods out.

k. = eigenvalue from a PDQ07 Discrete run at hot zero power, all i

rods out critical boron concentration, with one control rod bank fully inserted in the core.

The critical boron concentration with the reference bank fully inserted, CB (ref), is obtained by performing a poison search with the PDQ07 Discrete model.

The calculation of the total integral worth of the reference bank with each test bank fully inserted requires two PDQ07 Discrete runs per test bank: 1) a run with the test bank fully inserted and a boron concentration of CB (ref); and 2) a run with the reference bank and the test bank fully inserted and a boron concentration of CB (ref). The reference bank worths are computed 14

I ' r.

using the same technique as in Equation (3). The reference bank worths determined in this manner provide normalization for the FLAME model calculations discussed in Section 3.3.

3.3 FLAME Calculations The differential and integral worths of the reference bank with all other banks out, and with each of the test banks fully inserted are calculated using the FLAME model. The same methodology is used for both sets of calculations.

First, a series of cases is run with the FLAME3 code in which only the reference bank moves:

1) reference bank out,
2) reference bank inserted in the top node of the appropriate assemblies,
3) reference bank inserted in the top 2 nodes of the appropriate assemblies, n+l) reference bank inserted in the top 'n' nodes of the appropriate assemblies, last) reference bank fully inserted.

For the reference bank worths with all other banks out, the all rods out critical boron concentration is used. For the reference bank worths with the test banks inserted, the reference bank in critical boron concentration, CB(ref), is used.

The change in core reactivity resulting from each movement of the reference bank is a direct indication of its differential worth.

The second step in the process is the normalization of the total integral worth calculated by FLAME3 to the reference bank worth given by the PDQ07 Discrete model (Section 3.2 above). Based on this methodology, the following equations are used to compute the reference bank worths:

15

Differential Worth at k,] . k.i+ 1 10 5

Node Ii I (pcm/step) = X 2 x SPN X N. ( 4) k.] . - 1 X k.]. + l J Integral Worth at k - k. (5)

Node Ii I (pcm) 0 l. 105 X X N.

k X k. J 0 l.

Where:

k = eigenvalue given by FLAME3 for the reference bank out 0

k. = eigenvalue given by FLAME3 for the reference bank inserted l.

in the ith node SPN = number of steps of control rod movement per node N. = total integral worth of the reference bank from the PDQ07 Discrete J model divided by the total integral worth from FLAME3 for similar conditions of boron concentration and rod configuration For these calculations, there are six (6) normalization factors (Nj). Five of these are for the cases with the reference bank being inserted with a test bank fully inserted. The other is for the reference bank inserted alone.

Equations (4) and (5) are used to calculate the differential and integral worths of the reference bank as a function of bank position.

3.4 Design Predictions of the Critical Reference Bank Positions The determination of the predicted critical position (PCP) of the reference bank with a test bank fully inserted is based on the following reactivity balance equation:

(6)

Where:

RP = the total integral worth of the reference bank inserted alone

= the total integral worth of the test bank inserted alone

= the integral worth of the reference bank from the fully withdrawn position to the PCP with the test bank fully inserted 16

The values of RP and Tp are calculated with the PDQ07 Discrete model as discussed in Section 3.2 and the value for ~R:f(P) is determined using Equation (6). The design prediction of the reference bank worth as a function of bank position with the test bank fully inserted (calculated with the FLAME model as discussed in Section 3.3) is then used to determine the bank position at p

which the reference bank worth equals the value of ~RT(P). This bank position is the predicted critical position of the reference bank with the test bank fully inserted.

Figures 3.1 through 3.10 are graphs of the predicted integral worths of the reference bank with each test bank fully inserted( 3 , 4 ). Also shown is an illustration of the determination of each PCP based upon the value of p

~Rr,(p) for each test bank. Table 3.1 presents a surrnnary of the predicted critical position of the reference bank associated with each test bank( 3 , 4 , 5 ).

3.5 Design Predictions of the Integral Worth of Each Test Bank The determination of the predicted total integral worth of the test bank with the reference bank at the PCP is based on the following reactivity balance equation:

(7)

Where:

RP = the total integral worth of the reference bank inserted alone

= the integral worth of the reference bank inserted alone from the fully withdrawn position to the PCP p

T~R(P) = the total integral worth of the test bank with the reference bank at the PCP 17

  • e The value of RP is calculated with the PDQ07 Discrete model as discussed p

in Section 3.2. The values of tR (P) are determined using the calculations of the integral reference bank worth as a function of bank position with all other banks out (calculated with the FLAME model as discussed in Section 3.3) and the PCP values determined in Section 3.4. Figures 3.11 and 3.12 are graphs of the predicted integral worth of the reference bank for Surry 3

1, Cycle 5( ) and North Anna 1, Cycle 2( 4 ), respectively. The determination of the values of tRP(P) based upon the PCP for each test bank is illustrated on these figures. The total integral worth of each test bank with the reference p

bank at the appropriate PCP, T~R(P)' is determined using Equation (7). Table 3.2 presents an illustration and summary of the determination of these reactivity worth values.

As described in Section 2.2, the measured total integral worth of M

each test bank, TtR(M)' is determined with the reference bank inserted to the adjusted measured critical position, MCPA Whenever the MCPA is not identical to the predicted critical position, PCP, the predicted worth of the test bank, with the reference bank at the MCPA, TfR(M)' must be determined in order to put the design values and the test results on the same basis. The values for Ip are determined from design data using the following reactivity balance AR(M) equation:

(8)

Where:

= the total integxal worth of the test bank with the reference bank at the MCP

= the integral worth of the ref!rence bank from the fully withdrawn position to the MCP inserted alone

= the total integral worth of the test bank inserted alone

= the integral worth of the refirence bank from the fully withdrawn position to the MCP with the test bank fully inserted 18

  • e p

The values of T are calculated with the PDQ07 Discrete model. The p

values of ~Ri,(M) are determined using the calculations of the integral reference bank worth as a function of position with each test bank fully inserted and A

the MCP values. Figure 3.13 is a graph of the North Anna 1, Cycle 2 predicted reference bank (D bank) integral worth with test bank C fully inserted.

This figure provides an illustrative example of the determination of the ~~(M) p values. Similarly, the values of ~R (M) are determined using the calculations of the integral reference bank worth as a function of position with all other A

banks out and the MCP values. Figure 3.14 is a graph of the North Anna 1, Cycle 2 predicted integral worth of the reference bank (D bank) with all other banks out. This figure provides an illustrative example of the determination of the ~Rp(M) values. Table 3.3 presents an illustration and summary of the determination of the predicted reactivity worth of the test banks with the A p reference bank at the MCP, T~R(M). The test bank worths determined for Surry 1, Cycle 5 and North Anna 1, Cycle 2 are summarized in Table 3.4 and illustrate that the test bank worths are insensitive to small changes in the position of the reference bank.

19

I I

TABLE 3.1 PREDICTED CRITICAL POSITION Sill!MARY Reference Bank Total Test Bank Total Reference Bank Worth Predicted Critical Worth (Inserted Alone)- Worth (Inserted Alone)- to PCP (Test Bank In)- Reference Bank RP Tp Position - PCP Test L'IR~(P) (steps)

Bank (pcm) (pcm)

(pcm)

Surry 1, Cycle 5 D 1374 1188 186 181 C 1374 867 507 123 A 1374 631 743 98 SB 1374 964 HO 133 N

0 SA 1374 1149 225 172 North Anna 1, Cycle 2 C 1095 687 408 167 B 1095 1089 6 222 A 1095 789 306 195 e SB 1095 713 382 162 SA 1095 941 154 203

TABLE 3.2 PREDICTED TEST BANK INTEGRAL WORTH WITH THE REFERENCE BANK AT THE PCP Reference Bank Total Reference Bank Worth Test Bank Total Worth (Insei;ted Alone)- to PCP (Inserted Alone)- Worth (Ref Bank at PCP)-

Test R p llRP (P)

Bank (pcm) TllR(P)

(pcm)

(pcm)

Surry 1. Cycle 5 D 1374 165 1209 C 1374 521 853 A 1374 739 635 SB 1374 453 921 SA 1374 215 1159 North Anna 1. Cycle 2 C 1095 458 637 B 1095 7 1088 A 1095 210 885 SB 1095 495 600 SA 1095 131 964 p p p TllR(P) = R - llR (P)

TABLE 3.3 PREDICTED TEST BANK INTEGRAL WORTH WITH THE REFERENCE BANK AT THE :MCPA

. Reference Bank Worth Reference Bank Worth Test Bank Worth Test Bank Worth A to MCPA (Inserted Alone)- Ref Bank at MCPA~

(Inserted Alone)- to HCP (Test Bank.In)-

Tp p p Test L'.RT(M)  !'.RP (M)

Tt.R(M)

Bank (pcm) (pcm)

(pcm) (pcm)

Surry 1, Cycle 5 D 1188 164 147 1205 C 867 520 531 856 A 631 772 766 637 N

925 SB 964 393 432 SA 1149 235 226 1158 North Anna 1. Cycle 2 C 687 L129 479 637 B 1089 0 A 789 393 0

277 1089 905 e.

SB 713 407 520 600 SA 941 192 167 966 p

TL'.R(H) Tp + L'.~(M) - Ml (M)

TABLE 3.4 PREDICTED TEST BANK INTEGRAL WORTH

SUMMARY

Adjusted Measured Test Bank Worth Test Bank Worth Predicted Critical Ref Bank at ~CP- Ref Bank at MCPA-Critical Reference Bank p p Reference Bank Position-MCPA TtiR(P) TtiR(M)

Test Position-PCP Bank (steps) (steps) (pcm) (pent)

Surry 1, Cycle 5 D 181 185 1209 1205 C 123 122 853 856 A 98 94 635 637 SB 133 136 921 925 N

L,.)

SA 172 170 1159 1158 North Anna 1, Cycle 2 C 167 164 637 637 B 222 228 1088 1089 A 195 188 885 905 SB 162 159 600 600 SA 203 199 964 966

FIGURE s.t SURRY UNIT 1 CYCLE 5 PREDICTED REFERENCE BANK WORTH B BANK WITH D BANK IN 0

0

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40 80 I

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160 200 228 BANK POSITION {STEPS) 34

FIGURE 3.12 NORTH ANNA UNIT 1 CYCLE 2 PREDICTED REFERENCE BANK WORTH D BANK WITH ALL OTHER BANKS OUT 0

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2 28 BANK POSITION (STEPS) 35

FIGURE 3 .13 NORTH ANNA UNIT 1 - CYCLE 2 DETERMINATION OF 6R~CMJ FOR TEST BANK C 0

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--! I -- -! 1,--! I I II I 11 I 1*1 I -r-~ i 0 40 80 120 160 200 228 BANK POSITION (STEPS) 36

FIGURE 3.14 NORTH ANNA UNIT 1 cicLE 2 DETERMINATION OF ~R CMJ FOR TEST BANK C

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_, I-0 40 80 120 160 200 228 BANK POSITION (STEPS) 37

e Section 4 TEST RESULTS EVALUATION METHODOLOGY AND REVIEW CRITERIA

4. 1 Background As described earlier in this report, the acceptability of the results of the control rod bank worth tests serves to demonstrate the validity of the results of the calculational models used to predict control rod bank worths as part of the design process. Traditionally, the evaluation of the acceptability of the results of control rod bank worth tests has been based on a comparison of the measured and predicted control rod bank worths. This comparison has typically been expresse.d in terms of the percent difference between the measured and predicted result as shown in Equation (9).

Pmeas - P design X 100 (9)

Pdesign In the past, the measured control rod bank worths were obtained by using the dilution/boration technique. The review criteria (design tolerance) used for this comparison has been +15% for the measurement of the reactivity worth of individual control rod banks as shown by Equation (10).

Itie%) I < is% (10)

For individual control rod banks with relatively low reactivity worths, i.e.,

.::_600 pcm, the difference between the measured and predicted reactivity worth has been expressed in terms of absolute reactivity as shown by Equation (11).

A(pcm) = P meas - Pdesign (11) 38

I .

The review criteria used for this comparison has been +100 pcm as shown by Equation (12).

!A(pcm)J < 100 pcm (12)

Finally, in order to address additional concerns regarding shutdown margin verification, a review criteria has been established that the percent difference between the measured and predicted total reactivity worth of all four control banks be within +10% as shown by Equation (13).

A-D A-D (13)

IA(%) I Pmeas - Pdesign x 100 < 10%

A thru D A-D Pdesign 4.2 Rod Swap Test Evaluation and Review Criteria The measurement of the reactivity worth of the reference bank is performed using the dilution/boration technique. Therefore, the standard test result evaluation methodology and review criteria for individual bank worths using the dilution/boration technique, as described above, are used to evaluate the results of that test. As described in Section 3 of this report, the design predictions of the individual test bank reactivity worths are on exactly the same basis as the measured test results. Therefore, it is appropriate to use the same test result evaluation methodology for the rod swap test results as for test results obtained using the dilution/boration technique. The measured M p test bank worths, TAR(M)' are compared to the design predictions, TAR(M)' and the difference between the two is expressed either in terms of percent difference or in terms of absolute reactivity as appropriate. Additionally, since the individual test bank worth determinations are essentially the same in nature as the individual control rod bank reactivity worth tests using the dilution/boration technique, it is appropriate to use the same review criteria for the individual 39

test bank worths determined through rod swap; i.e.

I M%) I < 15% for bank worths > 600 pcm (14a)

I ti(pcm) I < 100 pcm for bank worths < 600 pcm (14b)

Finally, a review criteria has been established that the percent difference between the measured and predicted total reactivity worth of all of the control rod banks (i.e., the summation of the individual bank worths, control and shutdown) be within !10%; i.e.,

!ti.C.%) I = T

< 10% (15)

Total p design In summary,a test result evaluation methodology and review criteria have been established to evaluate the control rod bank worth test results obtained by using the rod swap technique. The evaluation methodology and review criteria are appropriate with respect to the test procedure, the test data analysis methods, and the design methods; and are identical to those used to evaluate the results of control rod bank worth tests using the dilution/boration technique.

As in the case of the current testing programs, should the results of the rod swap tests fail to meet the established review criteria, the Station Nuclear Safety and Operating Committee will be informed as required by the Vepco Nuclear Power Station Quality Assurance Manual. Based on the results of this review, the Committee may decide to perform additional testing. This additional testing may be a repeat of the original test or the performance of other appropriate confirmatory tests.

40

Section 5 ROD SWAP TEST RESULTS The Surry 1, Cycle 5 and North Anna 1, Cycle 2 rod swap test data were analyzed using the methodology presented in Section 2.2. The design predictions associated with these tests were performed using the methodology presented in Section 3. Figures 5.1 and 5.2 provide a comparison of the measured and predicted integral worth of the reference bank for Surry 1, Cycle 5 and North Anna 1, Cycle 2, respectively. The results of the test bank worth measurements, together with the associated design predictions and test review criteria are summarized on Table 5.1. As can be seen from the information presented on this table, all of the test results met the test review criteria and were acceptable.

41

TABLE 5.1 ROD SWAP TEST RESULTS SURRY 1, CYCLE 5 Bank Worth Review Control (pcm) Criteria Rod Bank Measured Predicted t,,(pcm) "'(%) (%)

B-reference bank 1405 1374 31 +2.3 +15 D 1257 1205 52 +4.3 +15 C 881 856 25 +2.9 +15 A 649 637 12 +1.9 +15 SB 977 925 52 +5.6 +15 SA 1178 1158 20 +l. 7 +15 Total 63Lf 7 6155 192 +3.12 +10 NORTH ANNA 1, CYCLE 2 Bank Worth Review Control ( cm) Criteria

  • Roel :Bank Measured Predicted I',, (pcm) "'(%) (%)

D-reference bank 1069 1095 -26 -2.4 +15 C 684 637 47 +7.4 +15 B 1085 1089 -4 -0.Lf -+15 A 843 905 -62 -6.9 +15 SB 6Lf9 600 49 +8.2 +15 SA 930 966 -36 -3.7 +15 Total 5260 5292 .,..32 -0.6 +10

  • SURRY UNIT 1 - CYCLE 5 FIGURE 5 .1 e

REFERENCE BANK WORTH B BANK WITH ALL OTHER BANKS OUT PK£DICT!D 0

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-0 .to 80 120 160 200 228 BANK POSITION CSTEPSJ 44

e Section 6

. VALIDATION OF THE ROD SWAP METHODOLOGY As mentioned earlier in this report, in addition to the control rod bank reactivity tests that were performed using the rod swap technique, control rod bank reactivity tests were performed using the conventional dilution/bora-tion technique during the reload startup of Surry 1, Cycle 5 and North Anna 1, Cycle 2. The purpose of performing these side-by-side programs was to establish the technical basis for validating the rod swap methodology. The results of these tests are presented in Tables 6.1 and 6.2, respectively, for Surry and North Anna. The design values for these tests together with the test review criteria are also shown.

The data on these tables indicate the basic similarities that exist between the results of these two test techniques with respect to the accepta-bility of the test results, and therefore, the verification of the design calculations. More specifically, for the Surry 1, Cycle 5 test results, the average absolute percent difference for the individual bank worth tests was 2.78% for the dilution/boration tests and 3.12% for the rod swap tests. The percent difference associated with the total reactivity worth of the control rod banks that were measured was 1.2% for the dilution/boration tests and 3.12%

for the rod swap tests. For the North Anna 1, Cycle 2 tests results, the average absolute percent difference for the individual bank worth tests was 3.46% for the dilution/boration tests and 4.83% for the rod swap tests. The percent difference associated with the total reactivity worth of the control rod banks that were measured was -1.7% for the dilution/boration tests and

-0.6% for the rod swap tests. In summary, the results of all of the tests were acceptable since all of the review criteria were met. Therefore, the 45

results of both test techniques demonstrated the validity of the results of the design calculations for control rod bank worths.

Since the reactivity worth of all of the control rod banks is deter-mined as part of the rod swap methodology, and since the same conclusions are reached regarding the verification of the results of the design calculations for control rod bank worths, the results of the side-by-side programs demon-strate the validity of using the rod swap methodology in future Vepco startup physics testing programs.

46

TABLE 6.1 SURRY 1, CYCLE 5 ROD WORTH RESULTS ROD SWAP TECHNIQUE Bank Worth Review Control (pcm) Criteria Rod Bank B-reference bank Measured 1405 Predicted 1374 b.(pcm) 31 b.(%)

+2.3

(%)

+15 e

D 1257 1205 52 +Lf. 3 +15 C 881 856 25 +2.9 +15 A 649 637 12 +1.9 +15 SB 977 925 52 +5.6 +15 SA 1178 1158 20 +l. 7 +15

.p.

Total 6347 6155 192 +3.12 +10

~%)! = 3.12%

DILUTION/BOP.ATION 6

- - - - - - - - - -TECHNIOUE(

  • - - - ~ -)

e Bank Worth Review Control (pcm) Criteria Rod Bank Measured I Predicted b. (pcm) /j (%) (%)

D 1207 1188 1-9 +1.6 +15 C-Bank Din 1082 1056 26 +2.5 +15 B-Banks C+D in 1999 2040 -41 -2.0 +15 A-Banks B+C+D in 1304 1242 62 +5.0 +15 E A-+D 5592 5526 66 +1.2 +10 IM%) I = 2.78%

Table 6.2 HORTH ANNA 1, CYCLE 2 ROD WORTH RESULTS RO_l? SWAP TECHNIQUE Bank Worth Review Control (pcm) Criteria Rod Bank Measured Predicted  !:,,(pcm)  !',(%) (%)

D-reference bank 1069 1095 -26 -2.4 +15 C 684 637 47 +7.4 +15 B 1085 1089 -4 -0.4 +15

-A 843 905 -62 -6.9 +15 SB 649 600 49 +8.2 +15 SA 930 966 -36 -3.7 +15

~

00 Total 5260 5292 -32 -0.6 +10 Iii<%}! = 4.83%

J)ILUTION/BORATION TECHNIQUE (7)

Bank Worth Review Control (pcm) Criteria Rod Bank Measured Predicted Li (pcm)  !:,,( %) (%)

D 1069 1095 -26 -2.4 +15 C-Bank Din 908 873 35 +4.0 +15 B-Banks C+D in 1321 1434 -113 -7.9 +15 A-Banks B+C+D in 1651 1649 2 +0.1 +15 SB-Banks A+B+C+D in 933 907 26 +2.9 +15 N-1 5942 6044 -102 -1. 7 +10 ILi C%)1 = 3.46%

e Section 7 CONCLUSIONS Based on the results of the side-by-side demonstration programs, it has been concluded that it is appropriate to use the rod swap methodology to demonstrate the validity of the results of the calculational models used to predict control rod bank reactivity worths. Additionally, the rod swap tests that were performed during the initial startup of Surry 1, Cycle 5 and North Anna 1, Cycle 2 demonstrated that the implementation of the test procedure was very straightforward and that the data acquisition and analysis were no more difficult or complex than that associated with control rod bank reactivity worth tests using the dilution/boration technique. The potential savings in testing time and boron recovery processing requirements were also demonstrated.

49

e Section 8 REFERENCES

1) M. L. Smith, "The PDQ07 Discrete Model," VEP-FRD-19, July, 1976.
2) W. C. Beck, "The Vepco FLAME Model," VEP-FRD-24, October, 1978.
3) W. C. Beck, "Rod Swap Design Data for Surry Unit 1, Cycle 5," NFE Technical Report No. 73, April, 1978.
4) M. C. Cheak, "North Anna Units 1 and 2 Design Report," NFE Technical Report No. 106, August, 1979.
5) J. G. Miller, S. A. Ahmed, R. T. Robins, H. H. Barker, "Design Predictions for Surry Unit No. 1, Cycle S," NFE Technical Report No. 74 (Parts 1 and 2), May, 1978.
6) T. J. Kunsitis, J. H. Leberstien, "Surry Unit 1, Cycle 5 Startup Physics Test Report," VEP-FRD-30, September, 1978.
7) T. J. Kunsitis, J. H. Leberstien, T. K. Ross, "North Anna Unit 1; Cycle 2 Startup Physics Test Report," VEP-FRD-35, To Be Published.

so

APPENDIX IMPACT OF THE ROD SWAP TESTS ON THE HOT ZERO POWER STARTUP PHYSICS TESTING PROGRAM FOR RELOAD CORES Table A.l identifies the series of tests that have been routinely performed as part of the Vepco reload hot zero power physics testing programs.

Table A.2 identifies the series of tests that will be performed in the future.

As can be seen from the information presented on these two tables, a basic trade-off is taking place. Through the implementation of the rod swap program, more control rod bank reactivity worth information will be obtained in lieu of several boron endpoint measurements. This is justified for the following reason. The boron endpoint data is supplementary to the control rod bank reactivity worth data in that the change in the boron endpoint values is merely another way of measuring the reactivity change associated with a change in the configuration of the control rod banks. Since the rod swap tests provide a mechanism for measuring the reactivity worths of all of the control rod banks, the elimination of selected boron endpoint measurements does not repre-sent a loss of significant information.

In summary, the implementation of the rod swap tests will change the composition of the reload hot zero power startup physics testing program.

However, this change will result in more control rod bank reactivity worth data being obtained. The elimination of selected boron endpoint measurements does not result in the loss of required data.

51

l;I I ) \J TABLE A.l HOT ZERO POWER STARTUP PHYSICS TESTING PROGRAM Reactivity Computer Checkout Boron Endpoint - ARO Temperature Coefficient - ARO H/D Flux Map - ARO Bank D Horth Boron Endpoint - Din Temperature Coefficient - Din H/D Flux Hap - Din Bank C Worth - Din Boron Endpoint C+D in

  • Temperature Coefficient - C+D in Bank B Worth - C+D in Boron Endpoint - B+c+D in Bank A Worth - B+c+D in Boron Endpoint - A+B+c+D in Banks A+D Worth in Overlap
  • Only performed when it is necessary to supply measured data to establish control rod bank withdrawal limits in order to meet the Technical Speci-fication limits for the moderator temperature coefficient.

52

  • TABLE A.2 HOT ZERO POWER STARTUP PHYSICS TESTING PROGRAM WITH ROD SWAP Reactivity Computer Checkout Boron Endpoint - ARO Temperature Coefficient - ARO M/D Flux Map - ARO Reference Bank Worth Boron Endpoint - Reference Bank In Temperature Coefficient - Reference Bank In H/D Flux Hap - Reference Bank In Control Rod Bank Worths (Control and Shutdown) 53