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Cycle 9 Startup Physics Tests Rept. W/870514 Ltr
	ML18150A088
Person / Time
Site:	Surry
Issue date:	04/30/1987
From:	Farley M, Pierce N, Stewart W; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	87-254, VP-NOS-31, NUDOCS 8705210247
	Download: ML18150A088 (60)
	v • d • e

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e VIRGINiA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS May 14, 1987 U. S. Nuclear Regulatory Commission Serial No.87-254 Attn: Docket Control Desk NOD/NSP:dof Washington, D.C~ 20555 Docket No. 50-281 License No. DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 CYCLE 9 STARTUP PHYSICS . TESTS BEPORT For your information, enclosed is a copy of the Virginia Electric and Power Company Topical Report VP-NOS-31, "Surry Unit 2, Cycle 9 Startup Physics Tests Report."

Should you have any questions, please contact us.

Very truly yours,

&)~1 W. L. Stewart Enclosures cc: U. S. Nuclear Regulatory Commission Region II lCH Marietta Street, N.W.

Suite 2900 Atlanta, GA 30323 Mr. Chandu P. Patel NRC Surry Project Manager PWR Project Directorate No. 2 Division of PWR Licensing-A Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station

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~urry* Unit 2, Cycle .9 Startup Physics Tests

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e e VP-NOS-31 SURRY UN IT 2, CYCLE 9

,: ~ . *: : . '} STARTUP PHYSICS TESTS REPORT

!ii by N. S. Pierce ff~~~ and M. K. Farley

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Reviewed By: Approved By:

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T. A. Brookmire, Associate Engineer c ..::1. ~

C. T. Snow, Supervisor Nuclear Fuel Operation Nuclear Fuel Operation Operations and Maintenance Support Subsection Nuclear Operations Department Virginia Electric .and Power Company Richmond, Va.

April, 1987

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. ' . :_, ." i CLASSIFICATION/DISCLAIMER

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.* :-.i, The data, techniques, information, and conclusions in this report have

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

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TABLE OF CONTENTS SECTION TITLE PAGE NO.

Classification/Disclaimer.................. i List of Tables. . . . . . . . . . . . . . . . . . . . . . . . . . . . . iii List of Figures. . . . . . . . . . . . . . . . . . . . . . . . . . . . iv Preface.................................... v 1 Introduction and Summary .................. . 1 2 Control Rod Drop Time Measurements ........ . 9 3 Control Rod Bank Worth Measurements ....... . 14 4 Boron Endpoint and Worth Measurements ..... . 19 5 Temperature Coefficient Measurement ....... . 23 6 Power Distribution Measurements ........... . 26 7 References ................................ . 33 APPENDIX Startup Physics Tests Results and Evaluation Sheets ......................... . 34

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e e LIST OF TABLES TABLE TITLE PAGE NO.

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,;,~ 1.1 Chronology of Tests .....*.......................... . 3 2.1 Hot Rod Drop Time Summary ......................... . 11 3.1 Control Rod Bank Worth Summary .................... . 16 4.1 Boron Endpoints Summary ........................... . 21 5.1 Isothermal Temperature Coefficient Summary ........ . 24 6.1 Incore Flux Map Summary ............. i ************** 28 6.2 Comparison of Measured Power Distribution Para,-

meters With Their technical Specifications Limits ... 29 iii

e e LIST OF FIGURES FIGURE TITLE PAGE NO.

1. 1 Core Loading Map ........................................ . 4 1.2 Beginning *of Cycle Fuel Assembly Burnups ................ . 5 t,ri~ 1. 3 1.4 Incore Instrumentation Locations ........................ .

Burnable Poison and.Source Assembly Locations ........... .

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7 8

2.1 Typical Rod Drop Trace .................................. . 12 2.2 Rod Drop Time - Hot Full Flow Conditions ................ . 13

3. 1 Bank B Integral Rod Worth - HZP ......................... . 17 3.2 Bank B Differential Rod_Worth - HZP ..................... . 18 4.1 Boron Worth Coefficient ............... ; ................. . 22 5.1 Isothermal Temperature Coefficient - HZP, ARO ........... . 25 6.1 Assemblywise Power Distribution - 30% Power ............. . 30 6.2 Assemblywise Power Distribution - 50% Power ............. . 31

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. ~: ~-i PREFACE The purpose of this report is to present the analysis and evaluation of the physics tests which were performed to verify that the Surry 2, Cycle 9 core could be operated safely, and to make an initial evaluation of the performance of the core. It is not the intent of this *report to discuss the particular methods of testing or to present the detailed data taken.

Standard test techniques and methods of data analysis were used. The test data, results and evaluations, together with the detailed startup procedures, are on file at the Surry Power Station. Therefore, only a cursory discussion of these items is included in this report. The analyses presented include a brief swmilary of each*test, a comparision of the test results with design predictions, and an evaluation of the results.

The Surry 2, Cycle 9 Startup Physics Tests Results and Evaluation Sheets have been included as an appendix to provide additional information on the startup test results. Each data sheet provides the following information: 1) test identification, 2) test conditions (design), 3) test conditions (actual), 4) test results, 5) acceptance criteria, and 6) comments concerning the test. These sheets provide a compact summary of the startup test results in. a consistent .format. The design test conditions and design values of the measured parameters were completed prior to the startup physics testing. The entries for the design values were based on the calculations performed by Virginia Electric and Power Company's Nuclear Engineering Group 1

During the tests, the data sheets were used as guidelines both to verify that the proper test conditions were

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met and to facilitate the preliminary comparison between measured and predicted test results, thus enabling a quick identification of possible

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problems occuring during the tests. The Appendix to this report contains

-~-:~)-/_~) the final completed and approved version of the Startup Physics Tests

Results and Evaluation Sheets.

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e SECTION 1 INTRODUCTION AND

SUMMARY

.

On October 4, 1986 Unit No. 2 of the Surry Power Station was shutdown for its eighth refueling. .During this shutdown, 52 of the 157 fuel assemblies in the core were replaced with fresh fuel assemblies. The ninth cycle core consists of 7 sub-batches of fuel: two once-burned batches, one from Cycle 8 (batch 10), and one from Surry 1 Cycle 7 (batch S1/9B5),

two twice-burned batches from Cycles 7 and 8 (batches S1/9C and 9), one thrice-burned batch from Cycles 6, 7, and 8 (batch 8), and two fresh batches (batches llA and llB) . The core loading pattern and the design parameters for each batch are shown in Figure 1.1. Fuel assembly burnups are given in Figure 1.2. The incore instrumentation locations are identified in Figure 1.3. Figure 1.4 identifies the location and number of burnable poison rods and source assemblies for Cycle 9, and Figure 1.5 identifies the location and number of control rods in the Cycle 9 core.

On November *30, 1986 at 0800, the ninth cycle core achieved initial criticality. Following criticality, startup physics tests were performed as outlined in Table 1. L A summary of the results of these tests follows:

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1. The drop time of each control rod was confirmed to be within the

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1.8 second limit of t~e Surry Technical Specifications 2

Individual control rod bank worths for the control rod banks were measured using the rod swap technique 3 and were found to be within 7.1% of the design predictions. The sum of the individual control rod bank worths was measured to be within 1. 7% of the design prediction. These results are within the design tolerance of +/-15%

for individual bank worths (+/-10% for the rod swap reference bank 1

e e worth) and the design tolerance of +/-10% for the sum of the individual control rod bank worths.

3. Critical boron concentrations for two control bank configurations were measured to be within 43 ppm of the design predictions. These results were within the design tolerances and also met the accident analysis acceptance criterion.

4. The boron worth coefficient was measured to be within 5.7% of the design prediction, which is* within. the design tolerance of +/-10%

and met the accident analysis criterion.

5. The isothermal temperature coefficient for the all-rods-out configuration was measured to be within 0.4 pcm/°F of the design prediction. This result is within the design tolerance of +/-3 pcm/°F and also meets the accident analysis acceptance criterion.

6. Core power distributions for at-power condition-::. were within established design tolerances. Generally, the measured core power distribution was within 5 .6% of the predicted power distribution.

The measured parameters were within the limits of the Technical Specifications and met their respective accident analysis acceptance criteria.

In summary, the startup physics test results were acceptable.

Detailed results, together with specific design tolerances and acceptance criteria for each measurement, are presented in the appropriate sect1ons of this report.

2

e e Table 1.1 SURRY 2 - CYCLE 9 STARTUP PHYSICS TESTS CHRONOLOGY OF TESTS

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Hot Rod Drop Timing Test 11/28/86 0500 HSD PT7.2 Zero Power Testing Range 11/30/86 0822 HZP PT28 .11 Reactivity Computer Checkout 11/30/86 1158 HZP PT28. ll(B)

Boron Endpoint-ARO 11/30/86 1349 HZP PT28 .11 (C)

Temperature Coefficient-ARO 11/30/86 1359 HZP PT28 .11 (D)

Bank B Worth 11/30/86 1457 HZP PT28 .11 (E)

Boron Endpoint-B In 11/30/86 2308 HZP PT28. ll(C)

Bank D Worth - Rod Swap 12/01/86 0215 HZP PT28. ll(F)

Bank C Worth - Rod Swap 12/01/86 0304 HZP PT28 .11 (F)

Bank A Worth - Rod Swap 12/01/86 0347 HZP PT28. ll(F)

Bank SB Worth - Rod Swap 12/01/86 0414 HZP PT28. ll(F)

Bank SA Worth - Rod Swap 12/01/86 0451 HZP PT28. ll(F) rt1~ Flux Map - Power Distribution Flux Mai:, - Delta I Target Measurement 12/03/86 12/05/86 0101 0952 30%

50%

OP-57, PT28.2 OP-57, PT28.2

}<fit Flux Map - I/E Calibration 12/06/86 0352 70% OP-57, PT28.2

}j{J Flux Map - I/E Calibration 12/06/86 0627 70% OP-57, PT28.2 Flux Map - I/E Calibration . 12/06/86 1041 70% OP-57, PT28.2 Flux Map - HFP, Eq. Xenon 03/30/87 1020 100% OP-57, PT28.2 ti~.~ 3

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, ____ , _ _ , _ , ___ , _ _ , _ _ , _ _ , _ _ , ____ , _ _ , _ , _ _ , _ _ 1_._ _ ,_,_.- ' 9 I I HD I I I .I MD I I

I I . I MD I I MD I I I TC I I I I TC I I I I I TC I I TC I 10

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6

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Figure 1.4 SURRY *uNIT 2 - CYCLE 9 BURNABLE POISON AND SOURCE ASSEMBLY LOCATIONS R p N M L K *J H G F E D C B A I

I I I I I

I I 1--1--1--1 I 8P* I I 8P* I I I

I 2

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I I I 16P I !JP I I I I 8P I I I I 4P I 16P I

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-1--1--1-1--1--1--1--1--1--1--1--1--1-- 1 I I 16P I I 16P* I I 16P I I 16P I I 16P* I I 16P I I 10 1--1--1--1--1--1--1--1--1--1--1----1-.-.

I I 12P* I 16P I I 16P* I I I I 16P* I I 16P I 12P* I

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1 I I I I

-- 15 1_ _ 1_ _ 1_ _ 1 4P -- . 4 BURNABLE POISON ROD CLUSTER SP -- 8 BURNABLE POISON .ROD CLUSTER 12P -- 12 BURNABLE POISON ROD CLUSTER 16P 16 BURNABLE POISON ROD CLUSTER SP* 8 DEPLETED BURNABLE ROD CLUSTER 12P* 12 DEPLETED BURNABLE ROD CLUSTER 16P* 16 DEPLETED BURNABLE ROD CLUSTER ssx SECONDARY SOURCE 7

- ... ;.:

.****_;

... .:.:... .:

-:* *.....* ... *;**~*:** )-c***. -~-. . :* ~ _:: .:-.-... :.:-. _:::*...* ....;*/_. ... :_::.:.. ::-:1* ~-~_:;~t *( / .~. }*;.:~_:**:/:___:-;: ._:*'.-: :*r:-=-}\*~ ~yr,-_:\;r:~-:?\*: *.***.~°\:.}:*.:** =_,/..... ~-~ \.~-*~~-~~*::*:~-=-~::':.~::?: :: ~!~..~~-:?;. . ?-~~~ . : .~*~--~-~::.- */.>~ * : .. *:.- .=.~*.-:* .* *::: **** .

7* ,.:.~:.,~:_.-.-;- '; .... --,:- ~

e e Figure 1.5 SURRY UNIT 2 - CYCLE 9 CONTROL ROD LOCATIONS R p N M L K J H G F E D C B A 180 o I

,:.. ::; Loop C I I I Loop B 1

._ ...***. ;*~ Outlet I__ I I I Inlet

-::*., :. (~

I AI ,-0-1-1 AI I./

~

.

2

~ _:::*~-- ~ _I_I_I_I_I_I_IK_

- .-_-*:~

N-41 I I SA I I SA I I 'I I N-43 3

_1_1_1_1_1_1_1_1_1_1_

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

_ l __ l _ l _ l _ l _ l _ l _ l _ l _ l _

I _ .I _

I I I SB I I SP I I SP I I SB I I I I 5 1_1_1_1_1_1_1_1_1_1_1_1_1_1 IAI IBI IDI ICI IDI IBI IAI 6 Loop C _ _ I _ _ I _ _ I _ _ I _ _ I _ _ I _ _ I _ _ I _ _ I _ _ I _ _ I _ _ I _ _ I _ _ I__ Loop B Inlet I I I SA I I SP I I SB I I SB I I SP I . I SA I I I ~ Outlet 7 0~1_1 __ 1__ 1__ 1_1_1_1 __ 1__ 1__ 1__ 1_1 __ 1__ 1__ 1 o 90 - I I D I I I

I c I I I I c I I I I o I - 270 8 1_1_1_1_1_1_*_1_1_1_1_1_1_1_1_1_1 I I I SA I I SP I I SB I I SB I I SP I I SA I I I 9 1_1_1_1_1_1_1_1_1_1_1_1_1_1_1_1 IAI IBI IOI ICI IOI IBI IAI 10 I _ I _ I _ I _ I _ I _ I _ I _ I _ I _ I _ I _ .I _ I I I I I SB I I SP I I SP I I SB I I I I 11 1_1_1_1_1_1_1_1_1_1_1_1_1_1 I I C I I B I I I I B I I c I I 12 1_1_1_1_1_1_1_1_1_.1_1_1 I I I I SA I I SA I I I I 13 N-44

1--I-I-A-l--l-o-l--l-A-l--l--1 N*

42 14 Absorber

,)-

Loop A 1

1-1 1- ,

I _ I_ _ I _ _ I Loop A 15 Materia I Outlet Inlet Ag-In-Cd I 00 Function Number of CI uste rs Control Bank D 8 Centro I Bank C 8 Control Bank B 8 Control Bank A 8 Shutdown Bank SB 8 i

Shutdown Bank SA 8 SP (Spare Rod Locations) 8

. *;:~

.' ~';!

...:.: :-:.;

. -*~

...., 8

.*.

r-r * .J.-;' ' . , ,.-. '* , . ): ~ .. .: I ",*,:* ~.-.::

...* .:

- e SECTION 2 CONTROL ROD DROP TIME MEASUREMENTS The drop time of each control rod was measured at hot full-flow RCS conditions in order to confirm satisfactory operation and to verify that the rod drop times were less than the maximum allowed by the Technicai Specifications. The hot control rod drop time measurements were run with the RCS at hot, full flow conditions ( 547°F, 2235 psig) and are described below.

The rod drop time measurements were performed by first w~thdrawing a rod bank to its fully withdrawn position, and then removing the movable gripper coil fuse and stationary gripper coil fuse for the test rod. This allows the rod to drop into the core as it would in a normal plant trip.

The data recorded during this test are the stationary gripper coil voltage, the LVDT (Linear Variable Differential Transformer) primary coil voltage, and a 60 Hz timing trace which are recorded via a visicorder. The rod drop time to the dashpot entry and to the bottom of the dashpot are determined from this data. Figure 2.1 provides an example of the data that is recorded during a rod drop time measurement.

As shown in Figure 2.1, the initiation of the rod drop is indicated by the decay of the stationary gripper coil voltage when the stationary coil fuse is removed. A voltage is then induced in the LVDT primary coil as the rod drops. The magnitude of this voltage is a function of the rod velocity. When the rod enters the dashpot section of its guide tube, the velocity slows causing a voltage decrease in the LVDT. coil. The LVDT voltage then reaches a minimum as the rod reaches the bottom of the 9

.....

, .

. **:*** .."*.

. .. :

-

- dashpot.

bouncing.

Subsequent variations in the trace are caused by the This procedure was repeated for each control rod.

rod The measured drop times for each control rod are recorded on Figure 2.2. The slowest, fastest, and average drop times are summarized in Table 2.1. Technical Specification 3.12.C.1 specifies a maximum rod drop time from loss of stationary gripper coil voltage to dashpot entry of 1. 8 seconds with the RCS at hot, full flow conditions. The test results met this limit .

.,....:. ;*~ ~:)

... '

10

-

Table 2. 1 SURRY UNIT 2 - CYCLE 9 STARTUP PHYSICS TESTS HOT ROD DROP TIME

SUMMARY

... , ... * ,1

: ~ .. *

. : -*., ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME F-14 1. 27 sec. P-10,K-12,M-12 1.16 sec. 1. 20 sec.

ROD DROP TIME TO BOTTOM OF DASHPOT SLOWEST ROD FASTEST ROD AVERAGE TIME J-7 1.90 sec. N-7 1. 74 sec. 1. 82 sec .

...

- **.,-:*

- - - - .

....... *:-_-1

. ... .*. * :~--

11

.. \ .* !*

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)

.'

. *:i

.i FIGURE 2.1

.,: .*. ~ TYPICAL ROD DROP TRACE

',*d

.. ;.

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5lATIONJI\~ GRIPPER COIL \JO-.:T:...:..:i,,~_ _..

I-'

N

.

ENlR"< INTO t>N:iitt POT

.

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Figure 2.2 SURRY UNIT 2 - CYCLE 9 STARTUP PHYSICS TESTS ROD DROP TIME - HOT FULL FLOW CONDITIONS R p N M L K J H

G F E D C a A I___ 1 I ___ 1 I___ ' II 1 ,

I 1. 19 I I 1, 17 I I 1. 21 I I I 1,84 I I 1. 78 I I 1.84 I I 2 1------1----1----11.201----11.24"" 1------1------1---*---1

___ 1 I_ _ I_ _ I1___ 1

.1 I 1_* 751I_ _ 1 I ___

1* 79 1 I_ _ 1 I_ _ 1 I _ _*11_ _ 3 I I 1. 22 I I 1. 21 I I I I 1. 23 I I 1. 23 I

I I I 1. 82 I I 1. 85 I I I I 1. 84 I I 1. 86 I I 4 1~l----l-l17i9l-~-+-~~1----1_;_1- "TI9l----l--l-1 1 I1_ _ 1 I _ ,I _ _ I1_ _ I1__._1I _ _ I1_ _ 1 1,83 I _ 1I _ _ 1 11._ 791I _ _ 1 I _1 I _ 1I 5 11.191 11.181 11.211 11.181 11.221 11.211 11.231

_ 1 _11.841

.___ 1___ 11.191 1_ _ 1_ _ 11.821 1_ _ 1_ _ 11.81.1 1_ _ 1_ _ 11.811 1_ _ 1_ _ 11.841 1_ _ 1___ 11.891 1_ _ 1 _ 6 I I I 1.19 I I ** I I 1.24 I I 1.20 I I I I 1.21 I I I Ii _ _ Il__ I_

1 1. 74

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1 1. 78

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, :**'.,--.-* ;~.* ~ 11.161 11.181 11.231 11,201* 11.201 11,Zll 11.231

. ,:. .: .;~ **.) I_

1 1. 84

_1 I_ _ 1 I_1. 82

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_1 I , o.

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,I _ _ 1_1...........,...1_1 I I I 1. 76 I ___ 1 I_ _1 I_ . _1 I_ _ 1 I _ _ I1_ 1. 84

_ I1___*I1_._1I _ _ 1 I 11 I 11,lol 11.161 I I 11.221 11,191 I I _ ,I _

, 1. 81

_1 I_ _ 1 I_ 1. 80

_1 I_ _ 1 I_ _ 1 I ___ 1 I_ 1. 82

_1 I _ _ ,I _ 1. 82

_1 I_ _ 1 I 12 I I I I 1. 23 I I 1. 21 I I I I

. I, _ _ 1 I_ _ 1 I___ 1 11,821

_ 1_ _ 11.781 1_ _ 1___ 1 I_ _ 1 I ___ 1 I l3 I I 1.22 I I 1.20 I I 1.21 I I I I 1, 87 I I 1. 79 I I 1. 86 I I 14 1- 1 - -- 1 I _ 1I____ 1 1 I_ _ 1 I 15

,--l--ROD DROP TIME TO l l DASH POT ENTRY( SEC.)

l_l-*ROD DROP TIME TO BOTTOM OF DASHPOT(SEC,)

. *- ~ .- . ~

~ .*;=~*~

'\*,:/

13

e SECTION 3 CONTROL ROD BANK WORTH MEASUREMENTS Control rod bank worth measurements were obtained for the control and shutdown banks using the rod swap technique. The first step in the rod swap procedu~e was to dilute the most reactive control rod bank (hereafter referred to as the reference bank) into the core and measure its reactivity worth usin$ conventional test techniques. The reactivity changes resulting from the-reference bank movements were recorded continuously by the reactivity computer 4 and were used to determine the differential and integral worth of the reference bank (Control Bank B).

At the completion of the reference bank reactivity worth measurement, the reactor coolant system temperature and boron concentration were stabilized such that the reactor was critical with the reference bank near full insertion. Initial statepoint data for the rod swap maneuver were obtained by moving the reference bank to its fully inserted position and recording the core rea~tivity and moderator temperature. At this point, a rod swap maneuver was performed by withdrawing the reference bank while one of the other control rod banks (Le., a test bank) was inserted. The core was kept nominal_ly critical throughout this rod swap and the maneuver was continued until the test bank was fully inserted and the reference bank was at the position at which the core was just critical. This measured critical position (MCP) of the reference bank with the test bank fully inserted is the major parameter of interest and was .used to determine the integral reactivity worth- of the test bank. Statepoint data (core reactivity, moderator temperature, and the differential worth of the reference bank) were recorded with the reference bank at the MCP. The rod

_-****

..

... ',.

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14

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. 7.#",'.' .'*.'."/' ;..:* .*

.*.~-.

e e

swap maneuver was then performed in reverse order such that the reference

-. : _; bank once again was near full insertion and the test bank was once again fully withdrawn from the core. The rod swap process was then repeated for all of the other control rod banks (control and shutdown).

A summary of the results for. these tests is given in Table 3 .1. As shown by this table and the Startup Physics Tests Results and Evaluation Sheets given in the Appendix, the individual measured bank worths for the control and shutdown banks were wit~in the design tolerance (+/-10% for the reference bank and +/-15% for the test banks). The sum of the individual rod bank worths was measured to be within 1.7% of the design prediction.

This is well within the design tolerance of +/-10% for the. sum of* the individual control rod ' bank worths.

The integral and differential reactivity worths of the reference bank (Control Bank B) are shown in Figures 3.1 and 3.2, respectively. The design predictions and the measured data are plotted together in order to illustrate their agreement. In summary, the measured rod worth values were satisfactory.

,- -*,

15

.... *. .- *-*- . :-:~---- .. '

...

e Table 3.1

.,

., SURRY UNIT 2 - CYCLE 9 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH

SUMMARY

..

'*, *: -*

. - .* j MEASURED PREDICTED PERCENT DIFFERENCE WORTH WORTH (%)

BANK (PCM) (PCM) (M-P)/P X 100

.....

.:** *.:-..; B-Reference Bank 1342 1427 -6.0 D 1034 994 4.0 C 877 838 4.7 A 380 406 -6.4 SB 1098 1087 1.0 SA 1007 1084 -7.1 Total Worth 5738 5836 -1. 7

',

16

~.*. **-*.*: ~ .* ..~.,-_..-..._-,. *:: *-*~->***

. : ' ... ;,- ,*, .' .. :* ,:_ -:~:

..

FIGURE 3 SURRY UNIT 2 CYCLE 9 BOL PHYSICS TEST BANK B INTEGRAL ROD WORTH HZP BANK 8 WITH RLL OTHER ROOS OUT PREDICTED llE MEASURED

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

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.; -- ~-. -:~ .. *.-.'. *. *-.,.** ..

.

FIGURE 3.2 SURRY UNIT 2 CYCLE 9 BOL PHYSICS TEST BANK B DIFFERENTIAL ROD WORTH HZP BANK B WITH ALL OTHER ROOS OUT PREDICTED

,IE MEASURED

,;

- .:_-;

0 0

'<:f" ..........................,...,,...,.......................................................--..................................,.....,....,...,...,...._,....,...,.....,.....,...,-,.....,...1-,............,....__,..,-,-- 1,-,

N µ.-1--1-+-+-+-l-....+--l-l-l-........,-l-....+--l-1-i-4-4-1-.J....4.-l-.......~....+-+-+-l-....+--l-l.-+....-.-I-....+ ,--1-1-1--l-1--i,-+-*,4;-.-.,...,+,-;,-~

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- - - 00 40 80 BANK POSIT I ON. (STEPS) 120 160 200 228 18

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..

SECTION 4 BORON ENDPOINT AND WORTH MEASUREMENTS

~Boron Endpoint

_**.. ~

'

With the reactor critical at hot zero power, reactor coolant system boron concentrations were measured at selected rod bank configurations to enable a direct comparison of measured boron endpoints with design predictions. For each measurement, the RCS conditions were stabilized with

. . .~- .

the control banks at or very near a selected endpoint position. The critical boron concentration was then measured. If necessary, an adjustment to the measured critical boron concentration was made to account for off-nominal core conditions; that is, for rod position and moderator temperature.

The results of these measurements are given in Table 4.1. As shown in this table and in the Startup Physics Tests Results and Evaluation Sheets given in the Appendix, the measured critical boron endpoint values were within their respective design tolerances. The measured values met the accident analysis acceptance criterion. In summary, the boron endpoint results were satisfactory.

Boron Worth Coefficient The measured boron endpoint values provide stable statepoint data from which the boron worth coefficient was determined. A plot of the boron concentration as a function of integrated reactivity can be constructed by relating each endpoint concentration to the integrated rod worth present in the core at the time of the endpoint measurement. The value of the boron 19

.*. ..*. :- - - .. *. ::-**. --.~.r.y . ::**:****** . ---.*.:.*;:f*:*. ':_. :: -:~ :! ;*. :'".*: . *.~* .*** .

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

The boron worth plot is shown in Figure 4.1. As indicated in this figure and in the Appendix, the boron worth coefficient of reactivity was

.. measured to be -8.34 pcm/ppm . The measured boron worth coefficient is

.: ..._~

within 5.7% of the predicted value of -7.89 pcm/ppm and is well within the design tolerance of +/-10%. The measurement result also met the accident analysis acceptance criterion. In summary, the measured boron worth was satisfactory .

.. ,

.;

. -.. **=. -~

.*.****;..

. **- . . 1 20

,**.**,:-**.,* .~... ~_***;_ .::* *""::_:-:.:*~-:~ . .**-.:~ .. *r

. ; '; . ,: .- ~ ***, **. "* ,','.*

- :*-.:*

e Tab.le 4.1 SURRY UNIT 2 - CYCLE 9 STARTUP PHYSICS TESTS BORON ENDPOINTS

SUMMARY

.:. .~.:

. *i

..

,*,*

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

ARO 1609 1652 -43 B Bank In 1448 1429* 19

The *predicted endpoint for the B Bank in configuration has been adjusted for the difference between the measured and predicted value~ of t~e endpoint taken at the ARO configuration as shown in the . boron endpoint Startup Physics Test Results and Evaluation Sheets in the Appendix .

. : . '. ~

.** '*

I 21

-.*-*/ ,,.~--~~--- ,--*--~ _.-_. ***~*~**: .~.--.- ;*: ~~ .. ; .. *:' .*.:.**.*

. ,*":* ..*. .::** -~*~ __ ......

. 1

. *-**** *... ; '

FIGURE 4,1

. : -.~ SURRY UNIT 2 - CYCLE 9 BOL PHYSICS TEST BORON WORTH COEFFICIENT l!J E~OPOINT ME~SUREMENTS

--f----ll---f--+---l----+--+-1---11---l----f--l----+--+--t--ll--+---+--l---+--l *---- ---- * - ~-- ---:l--+---+--1--+---I 2000

-t--t>--t-*1--l---1----'--l---+--t---l--+---+--l----+--+---1----11---1--- - - --- .......

-+--+--+--+---l~+--+--+--+--+--+---ll-+--+--l--+--+--+---l~+---1---1--l---l--+---ll--l--+--1--l--l---+-t

--** - - ---1----l----l,---l-+---+--I e

1---1---4---+----1-- ~J--+--4--+--+---+---l--'--I---I----I--I----+---+--+- *I---+--- ----- ~ ~-~--1---J--l---f---+---l--l l - - - l - - - - - - - - l - - - + - 1 - - - - - - l - - - l - - - - l - - - - - ' - - - - - ---- - * * - - - - ---- - - - - *---- --1-1----1-- ...--

l: 1600 u

N a...

N

>- ""- ...

1200 I-*

,_,

>

"

4 ---+--l--+--ll--l--+.>...-i~l--+---l--+--+--+---l~l--+---+--l---+--+--+-l---+---t--+--+--+--l-~l--+--+--I

~-+-----f--4--f--4---+"~--l--t-,,-l--+--1--4---1--1---+-1--+---l--l--~------~--1--l-~--1-~~-I

1----1--* * - - - - - --+-l---le---1 ... ~ C-- ~--t----+-*--1-1-----4--- <-- ~-1--1--+---l---t---f---f------l----l~--+--t---l u

a: -- 1-- --1-1--1---1--~- " "

~ 000 - 1 - - + - - - + *--+--+--+--+--+---l""'"'--t---+--1--l---+--+--+--+---1---1---'l--+---+--+--+---l--t---ll-+---t-l I'-

--*1-*

op= -8.34 pcm/ppm oCB 400

l----11--,1-- ,___ --l---1--i'--1--1---+--li--l---1--1--I--Po...--1---1 I"'-. t----** - ~ 1 - - - - l - - l - - - - ___,___ __,

"""- __,__.

0 1400 1440 1480 1520 1560 1600 1640 1680 1720 AnRnN rnNrFNTRATrnN rPPMl

.

T SECTION 5 TEMPERATURE COEFFICIENT MEASUREMENTS

. . :.i The isothermal temperature coefficient measurement was accomplished by controlling the RCS heat gains/losses with the steam dump valves to the condenser; and/or steam generator blowdown establishing a constant and uniform heatup/cooldown rate, and then monitoring the resulting reactivity changes on the reactivity computer. This measurement was performed at a very low power level in order to minimize the effects of non-uniform nu-clear heating, thus, the moderator and fuel were approximately at the same temperature (between 544-547°F) during the measurement. To eliminate the boron reactivity effect of outflow from the pressurizer, the pressurizer level was maintained constant or slightly increasing during the measure-ment.

An isothermal temperature coefficient measurement was performed at the all-rods-out contiguration. Reactivity measurements were taken during both RCS heatup and cooldowr1 .r.,.mps during which the RCS temperature varied approximately 3°F. Reactivity was determined using the reactivity com-puter and was plotted against the RCS temperature on an x-y recorder. The temperature coefficient was then determined from the slope of the plotted lines. The x-y recorder plots of reactivity changes versus RCS temperature for each measurement are shown in Figures 5.1.

The predicted and measured isothermal temperature coefficient values are compared in Table 5.1. As can be seen from this summary and from the Startup Physics Test Results and Evaluation Sheets given in the Appendix, the measured isothermal temperature coefficient value was within the de-sign tolerance of +/-3 pcm/°F and met the accident analysis acceptance cri-terion. In summary, the measured temperature coefficient was satisfactory.

23

..

- - -.. **- *. :--** .... ~ .. ' - *. ,, . ~- :-*

. ~' :* *~- .:-.

-

'.

_***

Table 5.1

. *.. ***.

SURRY UN IT 2 - CYCLE 9 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

ISOTHERMAL TEMPERATURE COEFFICIENT

. **,, BANK TEMPERATURE BORON (PCM/°F)

POSITION RANGE CONCENTRATION1--~---,-~~-r-~--,~~-,--~~---1

(°F) (ppm) COOL DIFFER.

HEATUP DOWN AVER. PRED. (M-P)

.. * .*'

.::*:.:\:;. :* 543.9 D/217 to. 1616 -2.50 -2.21 -2.36 -2~73 0.37 547.3

.* *.. .. ,_;

.- . ***1

. -- ... :*

.::**

- :J*.

24

.*.*~---_ ...-*.*-** .... - .. --,~--,~ ******: **-.-*:*.-.:-* \ ....... ;

e Figure 5.1 SURRY UNIT 2 - CYCLE 9 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT HZP, ARO I -1 HI

.* :* <*.......

..;.:!. . .i .

. * . '

~

.~ **')

.*-::.*

I .,

. :': . :::~.. ~

_:;__. . . *.\~*~1

-""* - . I

I+ . .

. -~ .... **:: ** .. I~ ii 1. : :r -

-

,. t*

-~ :~*

'

-

.

. **

.'**,

0 m+H++H++H++H++l+l+++!+!+!+l+H-H-,

. I*~-

.I :

..

J + i.

.

-: *.-= . . . . -~~ *

I M :f I

~j:j:.~~il+l+H .

I I .... :j

. ....*::

. . .* ~- ll+H++++H-H+I-H+ll+H,;H-H-l+l+H++H-HH-1-1 I : . ~.

r::l

~ t* *; 1 i:.:I ,.

... 1 .:

~

1.. . i-

1 .l ft...

..

. 1l ... . f .if * : ~ il L .,

~-;

,;

~~*

tt++tt-ttt+Hf+H+tltl+ttl-t+t,'++f,f+t+ttt.!*"-. .... ( I .. I .

1 VERTICAL SCALE 2°F/inch .I; J I . : *:j .*:

} ' l HORIZONTAL SCALE 10 pcm/ inch tt_ttttt+/-ttlHtrttt.H:f+/-rH+/-ffl+/-l-fftH+/-tf+/-H:1-HflEH+lrtttl-ttHf.+!ti_,ttf

'!

. }. .f

. I :

1. REACTIVITY (PCM)

.- -

.

...*.- .

'

.

..: . : '-~:

.. **:

25

.. :;:-/:' ::.:-.: ~. --~- ....... *.*""'.~

- ',.... ** * * ..... 1~ * .::

'~ .. ... ..... *,

SECTION 6

._ ~

POWER DISTRIBUTION MEASUREMENTS

... :._ .: _;

-

. ).

The core power distributions-were measured using.the incore movable detector flux mapping system. This system consists of five fission detectors which traverse fuel assembly instrumentation thimbles in 50 core locations (see Figure 1.3). For each traverse, the detector output is

.*.. , .....

__

continuously monitored on a str_ip chart recorder. The output is also scanned for 61 discrete axial points by the PRODAC P-250 process computer.

Full core, three-dimensional power distributions are then determined by analyzing this data using the Westinghouse computer program, INCORE 5

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

A list of all the full-core flux maps taken during the test program together with a list of the measured values of the important power distribution parameters is given in Table 6 .1. The measured power distribution parameter values are compared with their Technical Specifications limits in Table 6.2. Flux Map 1 was taken at slightly less than 30% power to verify radial power symmetry according to the American National Stand~rds Institute standard on power reactor startup physics testing (ANSI/ANS-19.6.1-1985). Figure 6. 1 shows the resulting radial power distribution associated with this flux map.

Flux maps 2 through 6 were taken over a wide range of power levels and control rod configurations. These flux maps were taken to check the at-power design predictions and to measure core power distributions at various operating conditions. These maps also provide a cross- calibration 26

,.~ :*:- -.:- **. _:,:: -:* :: ~.::** .. *' ...-,-_. ,,

- . "'."'-:. - . *.....

e between the incore and excore nuclear instrumentation systems. The.radial power distributions for these maps are given in Figures 6.2 and 6.3. These figures show that the measured relative assembly power values are generally

. **,,*.* within 5.6% of the predicted values .

In conclusion, the power distribution measurement results were considered to be acceptable with respect to the design tolerances, the

.* *-,

accident analysis acceptance criteria, and the Technical Specification

limits. It is therefore anticipated that the core will continue to operate safely throughout Cycle 9.

_:. =.-:**:.! ;-~,

_,;::.,-/;~*: );

--: ._._:_.

' **** --~! -

27*

.*-... ...., *,

-.,. <~- _\ *.,. :* _.....

I

I:.

I ,\ TABLE 6. 1

- SURRY UNIT 2 - CYCLE 9 STARTUP PHYSICS TESTS INCORE FLUX MAP

SUMMARY

I I I I 1 2 I I I e

;~

I BURNI I . I F-Q(T) HOT F-Dll(N) HOT CORE F(Z) I 4 I . I I I UP I IBANK I CHANNEL FACTOR CHNL.FACTOR MAX I 31 QPTR AXIAL! NO. I MAP IMAPI DATE MWD/IPWRI D I IF(XY)I____ OFF I OF I DESCRIPTION INO.I MTU 1(%)1STEPSI I IAXIALI I I I I-AX-IA~L~l--1 I I I SET ITHIMI I I I I I IASSY.IPINIPOINTI F-Q(T)IASSYIPINIF-Dlt(N)IPOINTI F(Z)I I MAX !LOCI (%) IBLESI

1-1 POWER DIST. ( 5) I 1112- 3-861 1--1-1--1-1-1--1---.1-1-l 31 301 147 I NAI NAI N/A I N/A I N/AIN/AI N/A 1--t--1--1--1-1--1-1 I N/A I N/A I N/A 11.0091 NWI -2.801 36 I I I I I I I I I I I I I I I I I I I I I DELTA I TARGET I 2112- 5-861 301 501 155 I J141 LMI 31, I 2.028 I MlOI ELI 1.533 I 32 ll.29211.43511.0061 NWI -3.661 40 I I I I I I I I I I I I I I I I I I I I I HFP, EQ. XENON (6)1 6103-30-871 4281 991 197 I K061 LEI 23 I 1.792 I K041 LJI 1.445 I 33 l1.190ll.390ll.0071 NWI -1.041 45 I N

CX>

NOTES: IIOT SPOT LOCATIONS ARE SPECIFIED BY GIVING ASSEMBLY LOCATIONS (E.G. H-8 IS THE CENTER-OF-CORE ASSEMBLY FOLLOWED.BY TIIE PIN LOCATION ~DENOTED BY THE 11 ¥. 11 COORDINATE WITH TIIE FIFTEEN ROWS OF FUEL RODS LETTERED11 A THROUGH RAND TllE 'X" COORDINATE DE~IGNATED IN A SIMILAR MANNER).

IN TIIE 2 11 DIRECTION TIIE CORE IS DIVIDED INTO 61 AXIAL POINTS STARTING FROM THE TOP OF THE CORE.

1. F-Q(T) INCLUDES A TOTAL UNCERTAINTY OF 1.08

2. F-DH(N) INCLUDES A MEASUREMENT UNCERTAINTY OF 1.04

3. F(XY) IS EVALUATED AT THE MIDPLANE OF THE CORE.

4. QPTR - QUADRANT POWER TILT RATIO.

...

,*:

5. FLUX MAP 1 DID NOT HAVE ENOUGH THIMBLES TO VERIFY F-Q(T), F-DH(N), F(Z), OR F(XY) .

6. FLUX MAPS 3 THROUGH 5 WERE QUARTER-CORE MAPS TAKEN FOR INCORE/EXCORE DETECTOR CALIBRATION AT 70%

Table 6.2 SURRY UNIT 2 - CYCLE 9 STARTUP PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR TECHNICAL SPECIFICATION LIMITS

.*..... F-Q(T) HOT F-DH(N) HOT

.*.

CHANNEL FACTOR~': CHANNEL FACTOR+

MAP NO. MEAS LIMIT MARGIN MEAS LIMIT MARGIN

(~~) (%)

\

- *.**

__..*.

2 2.03 4.36 53.5 1.53 1. 78 14.0 6 1. 79 2.14 16.4 1.45 1.55 6.5

The Technical Specification's limit for the heat flux hot channel factor, F-Q(T), is a function of core height. The value for F-Q(T) listed above is the maximum value of F-Q(T) in the core. The Technical Specification's limit listed above is evaluat~d cit the plane of maximum F-Q(T). The minimum margin values listed above are the minimum percent difference between the measured values of F-Q(T) and the Technical Specification's limit for each map. The measured F-Q(T) hot channel factors include 8% total uncertainty.

+ The measured values for the enthalpy rise hot channel factor, F-dH(N), include 4% measurement uncertainty .

.*:*

.:_/:\.

- *;

29

* .J * .*~ ' ...

, .. * ..*.-- .-. .u . -*~~.. :-.~* . . .**** ~

1.*.-.*.*.;'

~* e -

1%9 Figure 6.1 SURRY UNIT 2 - CYCLE 9 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 30% POWER R p H M I. K J H C F E D C B A

.... i>ili:oicri:o ...

MEASURED *

- o:2i***o:2i***o:2i**

0.29. 0.29. 0.28.

.... PREOicri:o"*:

MEASURED *

PCT DIFFERENCE. * *0.8. *0.7. *1.B *

PCT DI FFERENCE.

*0.36.

o:iii": *0:12* :*;:or: *0:10*: *;:06*: *0:12 *: *o:iii":

0.72. 1.05. 0.69. 1.04. 0.71

0.34. 2 4.6. -0.9. -o.a. -o.6. -1.4. -2.0. 0.2.

*o:iio*: *;: ;; *: *;:2,*: *;:2e* :*; :20*: *; :2a* :*; :2, *: *;: ;; *: *o:iio*:

0.41

1.14. 1.25. 1.26. 1.18. 1.26. 1.23. 1.12. 0.41 , 3 4.2, 2.9, *0.1. -1.1 * -1.1 * *1.6. *1.6. 0.7. 3.8.

, *0.41 o:iio **, *0.93.

o: i; ***;:ff**;: i6 ***Gr**; :2r **; :2a ***;: i6 ***;: ,;; ***;,:ii*** o:iio **

1,32. *1,37. 1.28. 1.22. 1.26. 1.35, 1.31

0.93. 0.41 , 4

, 4.6. 2.2. 1,4_. 0,9, *0.5. *2,3. *1.8. -1.1 , 0.1 , 1.8. 2.8.

,

iii*:*;:;;*:*;:,;;,*:*;:,;ii*:*;:2;*:*i:it*:*;:2,*:*o:i1*:*;:2;*:*;:,;ii*:*;:,;;,*:*;:;;*:*;,:,;ii*:

0,34. 1.11. 1.31. 1.34. 1.23. o.99. 1,25. o.96. 1.20. 1.32. 1.29. 1.u. o.J5. 5 0.1

0.3. 0.7. 0.6, 1.6. 2.0. 0.1 * *1.3. *1.2, *1,2. -1.2. 1.8. 1.8.

, *;,:0.72.

12 *: *;1.25.

2, *: *;:1.36, i6 *: *;1.22.

2; *: *;:1.15. w: *;:iii*:*;:

2 *: *;:1.20, ;1*: *;:ii*:* i:ii*:* i: ,;6*: *; :i, *:*;,:ti*:

1.26. 1.16. 1.09. 1.19, 1.34, 1,26. 0,74. 6

0.2. 0.2. o.3. o.6. 2.1

2.5. 1.4. -0.1. -2.8. -1,4. -1.3. o.J. 1.9 *

..* o:ii***;:06*** ;:is*** ;:ir **o:w **;:w **,:o;** *;: ,i .. *,:a,***;: w **o:w **,:ie' **,:ia"* ,:06* **o:ii=:

0.29

1,06. 1.28 , 1.27 , 0.95

1.19, 1.05

1,23

1.00, 1.15 , 0.95

1.26. 1.26. 1.07

0.30

7 o.5. -0.2. 0.1 * -0.1. -1.6. 2.0. 4.1

_2.s. -o.9. -1.9. -1.4. -1.6. -1.2. o.6. 3,5.

*;,:ii': *;,:10 *: *;:io *: *,:2,*: *;:iii*:* ;:iii':*;: ,i*: *;:;,1*: *;: w: *;:iii*:*; :iii*:* ;:2;*: *; :20*: *0:10*: *o:2i*:

0.29. 0.70, 1,18 , 1,25

1.23

1.26, 1.25. 1.12

1.20, 1.22

1.23 , 1.22. 1.16

0.71 , 0.30. 8

-o.9. -0.1 * -1.0. -o 2. -0.9. 1.5. 4,7. 3,9. o.4. -1.0. -1.1 * -2.1. *2.8. 2.1

3,3.

,

2i*: *;:;,6*: *; :2e*: *;:ia': *;,:ir: *;:11*:*;:;,; *:* ;: w: *;:;,i *:*;:ff: *;,:w: *;:is*:* ,:is': *;:;,6*: *;,:29*:

, 0.29. 1.05, 1.26. 1.29, 0.99, 1,17. 0.99. 1.21. 1.03. 1.16. 0,95. 1.24. 1.26. 1.07. 0.30. 9

-1.1. -1.1. *1.3. 0.6. 2.6. 0.3. -2.1. 1.1

2.0. *0.5. *1.5; *3.6. *0.9. 1.1 , 2.8 *.

*** *** *:** 0:12*: *;:is":*; :i6.: *;:i, *: *;: ;r: *;: w: *;:iii":* ;:w: *;: ;2*: *;:ii*:* ;:,;6*: *;:2r: *;,:12*: *******

0,71

1.24. 1;41 , 1,25. 1.11

1,14. 1.24, 1.19. 1.12. 1.19. 1.32. 1.24. 0.13* . 10

-1.3. -1.3. 3.3. 3.3. -0.9. -2.3. o.o. 1.1. -o.o. -1.5. -J.2. -o.8. 1.6.

,

,;ii*:*;:;;*:*;:,;;,*:*;:iii*:*,:2;*:*;,:i1*:*;:2,*:*o:91*:*;:2;*:*;:iii*:*;:i;,*:*;:;;*:*;,:iii*:

0.35. 1.12. 1.32. 1.38, 1.18. 0,95. 1,22. 1.00. 1.23. 1.31

1.28. 1.11

0.35. 11 1.1. 1.1

1.1. 3.3, -2.2. -2.1. -2.1. 2.9, 2.0, *2.3. *1.7. 0.1. 1.7.

- - - - ,
        
        ,;,*:*o:i;*:*;:i;*:*;:i6*:*;:2e*:*;:2,*:*;:2a*:*;:i6*:*;:,;;*:*o:i,*:*;,:iio*:*******

0.40

0.92

1.32

1.33 , 1.25

1.22

1.29

1.35 , 1.29

0.90

0.40

12 1.0

1.0 ~ 1.1 * -2.4. -2.4. -2.4 ** 0.2. -0.1 * -1,3 * -o.8 . 1.6 *

.... ***: *;,:,;,*: *;: ;r: *;:2r: *; :ir: 'Go*:* ;:ia*: *; :ir: *;: ;; *: *;,:,;,*: .... ***

0.40. 1.12. 1.22. 1.25. 1.17. 1.25. 1.22. 1.09. 0.40. 13 1.0. 1.1. *2.4, *2,4. *2,4. *2.4. *2.6. -2.0, 0.2.

- - - - **;,:,;, ***;,: 12* **;:;,r "&:t;,* .. ;:;,6* **;,: 12 ***o: iii*********

0.37. 0.79. 1.15. 0.76. 1.04. 0.70. 0.33. 14

................... 0.29

............................. .

8.6. 8.6, 8,6, 8.6. *2.2. -2.5. *2.6

0.29 0.29 :..** Ave:i!Aoe:*'.:

STANDARD

PCT 01 FFERENCE.

DEVIATION 0.31 0.32 0.31

=1.785 8.6 8.6 8,6 " 1.9

SUMMARY

,.*-: HAP NO: S2*9* 1 DATE: 12/ 3/86 POWER: 30%

CONTROL ROD POSITIONS: F*Q(T) = N/A QPTR:

D BANK AT 147 STEPS F*DH(N) = N/A NW' 1.009 I NE 0.992 F(Z) = N/A -----------1-----------

sw 1.002 I SE 0.997 F(XY) = N/A BURNUP = 3 HWD/MTU A.O = -2.soci) 30

.. ", : **~.:"!.;~ . ~ *.-.* 1- :.~~-/

(*.*. .;

-

Figure 6.2 SURRY UNIT 2 - CYCLE 9 STARTUP PHYSICS TESTS i

1-*.

ASSEMBLYWISE POWER DISTRIBUTION 50.0% POWER R p N M L K J H G E D C 8 A

................

PREDICTED * . 0.29 . 0.30 . 0.29. PREDICTED

MEASURED * . 0.29 . 0.29

0.30. , MEASURED ,

PCT DIFFERENCE. . -0.7 . -2.3 . 0.4. , PCT DI F.FERENCE *

*o: j4 *:

o: 12 *:

i: 06 * :

o: 1i * :

i: 06 *:

o: 12 * :

o: j4 *:

0.37 . 0.72. 1.05

0.70 . 1.05. 0.72 . 0.35 . 2 1.2 . -o.e . -1.4 . -1.1 . -0.1. 0.2

1.0 .

................................................................

. 0.40, 1.10. 1.24, 1.27, 1.19, 1.27, 1.24. 1.10. 0.40 .

0.42, 1.13 . 1.23 . 1.25 , 1.17 . 1.24. 1.22 . 1.10 . 0.41 .

6.3 . 2.6, -1.3 . -1.2 . -2.2 . -2.1 . -1.6 , 0.1 , 2.3 .

. o: 40.:. o: 90.:. i: 29.:. i: j5.:. i: 28. : . i: 25. : . i: 28.: . i: j5. : . i: 29.:. o: 90. : . o: 40.:

, 0.42 , 0.92

1.28

1.35

1.27 , 1.22 . 1.24 . 1.31 . 1.27 , 0.91 , 0.40 ,

7.2, 1.5 . -1.1 , -0.2. -0.3 * -2.3 , -3.0. -3.3 . -1.9 , 0.1

2.4 .

*o:j4.:

i: io' :* ;:29*: *i:ii" :*;:2;*:*0:91*: *;:25*:

0:91*: * ;:2;*:

i :ii":* i:29*: * ;: io*: *o:i4.:

. 0.34 , 1.08, 1.27. 1.31 , 1.22. 1.01

1.26. 0.96. 1.19. 1.29 . 1.24 . 1.12 . 0.35 , 5

, -1.0. -1.8. -1.5 . -1.6. 0.3 , 3.3

0.7. -1.0, -1.7 . -2.9 , -3.4

2.5 . 2.5 ,

o: 12 *:

i: 2ii *: *;: ir:

i: 2i *: *;:;;*:*;:is* : *;: 2r : *;: i8 *: *;:; 5*: *;: 2i *: *;: 35 *: *;: 24 * :

o: 12 *:

. 0.71

1.23 , 1.33. 1.20, 1.16, 1.22

1.27 , 1.20. 1.15

1,19 , 1.30 , 1.23 , 0.74 , 6

, -0.9. -0.9, -1.0. -0.8. 1.3

3.4. 1.8 . 1.7 , 0.1 . -1.7. -3.7. -0.7 . 2.6 ,

o: 29 *: *;: 06 *: *;: 21 *: *;: 28 *:

o: 91 *: *;: ;8 *: *;: 02 *: *;: 2i *: *;: 02 *:

i: i8* : *a: 97 * : *;: 28 * : *;: 21 *: *;: 06 *: *a: 29 * :

, 0.29 , 1.05 . 1.26

1.26 . 0.97 , 1.20 . 1.07

1.25

1.05 -* 1.20 , 0.96 , 1.23 . 1.24 , 1.07 . 0. 30 . 7

-0.1 . -1.5. -1.1 . -1.2. -o.6. 2.0. 5.1

3.4

2.6

1.4. -1.3 . -3.9 . -2.0 . o.6 . 3.2 .

a:ia*:*o:1;*:*;:;i*:*;:25*:*;:2§*:*;:2§*:*;:2;*:*;:09*:*;:2;*:*;:2i*:*;:25*:*;:25*:*;:;9*:*o:1;*:*a:30*:

. 0.29. 0.70. 1.16 . 1.24

1.25. 1.27, 1.28

1.14. 1.23 . 1.25 . 1.24 , 1.20

1.16 , 0.73 . 0.31 . 8

. -2.s . -1.6 . -2.4. -o.6. -o.o. 2.2. 5.7

4.5

2.1 . o.6 . -o.9 * -3.7 . -2.6 . 1.9 . 3.o .

o: 29 *: *;: 06 *: *;: 21 *: *;: 28 *: *o: !i1 *: *;: i8*: *;: 02 *: *; :2i *: *;: 02 *:*;:is*:* o: 91 *: *;: 2a *: *;: 21 *: *;: 06 * : *a: 29 *:

. 0.29. 1.03 , 1.24. 1.28 , 1.00. 1.20 . 1.02 , 1.24

1.05

1.19

0.97 . 1.24 . 1.26 , 1.06 , 0.30 , 9

. -2.6. -2.1. -2.1. o.4. 2.5. 1.2. o.3. 2.6. 3.1 . o.6. -o.6. -J.1 . -1.1 . o.3. 1,4.

* * * * * * :

o: 12 *: *;: 2ii *: *;: j5 *:

i: ii*:*;:;;*:*;: is* : *;: 25 * : *;: ia* : *;:; 5* : *;: 2i *: *;: 35 * : *;:iii*:* o: 12 *: * * * * * * *

. 0.70. 1.21 . 1.36. 1.22. 1.15. 1.19. 1.27. 1.20. 1.15. 1.19. 1.31 . 1.22. 0.72. 10

, -2.8. -2.8. 0.5 . 0.5. 0.0. 0.1 , 1.8 . 1.7. -0.2 . -1.6 . -2.9. -1.7 . -0.5 .

<- :*o:jii*:*;:;o*:*;:29*:*;:ii*:*;:2;*:*o:91*:*i:25*:*o:!i1*:*;:2;*:*;:ii*:*;:29*:*;:io*:*o:iii':

*.! . 0.35. 1.13. 1.29. 1.30, 1.19, 0.96, 1.24 , 0.97 . 1.21 , 1.29. 1.26 , 1.09, 0.35.

3. 1 . 3. 1 . -0. 0 * *2. 0 . -1. 4 ,

1. 0 . -0, 9 . 0. 0 , *O. 4 . *2. 5 .

1. 9 . *O. 6 , 0. 6 .

11

. . . . . . . : . o: 40':. o: 90.:. i: 29.:. i: 35.:. i: 28.:. i: 25.:. i: 28.:. i: 35.:. i: 29.:. o: 90.:. o: 40.: ...... .

. 0.41 . 0.91

1.26, 1.32. 1.25

1.22 . 1.26 . 1.33 . 1.26

0.89 . 0.40 , 12 3.1

1.0. -2.1 . -2.3 *.-2.4, -2.4. -1.2, *1.6. -2.1 . -2.0. 1.6 .

..............................................................................

0.40, 1.10. 1.24. 1.27. 1.19. 1.27. 1.24. 1.10. 0.40 .

0.41. 1.14. 1.25. 1.24. 1.16. 1.24. 1.21, 1.07. 0.39. 13 3.2. 3.4, 0.5. -2.4 * *2.4 . -2.3 . -2.4. -2.5. *0.7 .

. . . . ' .. : . o: iii. : . o: 72. : . i :06. : . o: 1i . : . i: 06. : . o: 72. : .o: 34. : ' ..... .

. 0.36, 0.76 . 1.15 . 0.77 . 1.04

0.70 . 0.34, 14 3, 4 , 5. 4

8. 2 . 8. 1 * *2. 1 * *2. 4 , -2. 5 .

<:~ '*... . ' *. s'rANDAilo'. * * * * * * * ** * * * * * :* o: 29 * :

o: :io * :

a: 29 * : * * * * * * * * * * * * * * : . ' *. AVERAGE.' ' :

OEVIAT I ON , 0.32 . 0.33 . 0.32 * .PCT DIFFERENCE. 15

=1. 721 8.2 . 8.1 . 8.2 * = 2.1

SUMMARY

MAP NO: 52 2 DATE: 12/ 5/86 POWER: 50%

CONTROL ROD POSITIONS: F-Q(T) = 2.028 QPTR:

D BANK AT 155 STEPS F*DH(N) = 1.533 NW 1.006 I NE 0.996 F(Z) = 1.292 -----------1-----------

sw 1.006 I SE 0.992 F(XY) = 1.435 BURNUP = 30 MWD/MTU A.O = -3.66(%)

31

\/.: ...* ,4 *

_ : : ,' *' ** '; ~: *

e -

Figure 6*.3 SURRY UNIT 2 - CYCLE 9 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION HFP, EQUILIBRIUM XENON A , N N L K J H G F E D C 8 A

. "' i>iti:i, icri:i,' ' :

MEASURED ,

i>:iii,'.i4i,:ii

, 0.32, 0.34. 0.32.

- - - iti
      
      i,ii:fi:i,'"'

MEASURED *

PCT DIFFERENCE, * -o.4. -1.5. -0.1. ,PCT DIFFERENCE.

'i,:i6°:. i>:H*: *;:oi': 'i>:1i*: *;:i,i' :: o'.ii.: 'i>'.i6°:

0,37. 0,73. 1.07, 0.78. 1.07. 0.72. 0.36. 2

. 3.a. -o.6. -o.a. -0.9. -1.0. -o.9. -o.5.

*o:iii": *;:i,i' :* ;:2i>':. ;:24 *:* ;: ;i' :*; '.24':. ;:20*: '; :i>1': 'o:4;.:

o.42. 1.D8. 1.19. 1.23

1.11. 1.22. 1.18

1.D6

o.41

3

3.3. 1.2. -0,9. -o.8. -1.4. -1.6. -1.6. *0.8. 0.2.

*o:o.42 4; *:* *iD,90

>: iii* :* *;1.23

2i *:* *;1,31

ii>* :* *;1.25

2i *:* *;1.21

ii* :*

1.22

: 2i *:*;:io *:*;:2i *:*ci: a9 *:*ci: 41 *:

1.27

1.21

o.88 . o.40

4

3.8. o.8. *0.8. 0,4. o.3. -1.2. *1,9. -2.1 * -1.8. -1.9. -1.4.

, 'i>'.ii': *;:01* :* ,:2r :*;:29*: *; :2; *: *o:9r: *;:2r: *0:99*: *,:21*: *;:zi*: *;:2r: *,:01*: *o:i6.:

0.35. 1.06, 1.23, 1.28. 1.22. 1.03. 1.27, 0.99, 1.21

1.27. 1.19, 1.04. 0.36. 5

*0.6, *0,3, *0.5, *0.4. 1.1 , 3,7. 1.3, D,1

0.0. *1.2. *3,7. *2,2. *0.2,

, o:ff :*,:20*: *;:;o* :* ,:2; *: *;:22*: *; :2, *: *; :21*: *; :2r: *;:22*: *;:2; *:* ,:io*: *,:20*: *i>:*H":

0,73. 1.19. 1.30. 1.21

1.24. 1.26, 1,29. 1.24. 1,24. 1.lO, 1,26. 1,17. 0.72. 6

-o.5. -0.5. -0.2. -o.o. 1.9. 3.6. 2.0. 2,5. 1.9. -0.1. -2.8. -2.4. -1.5.

, *0,32 i>:ii*:, *,:oa* :* ,:24* :* ;:2;* :*a:99*:* ;:2; *:*;:or :* 1:24* :*; :oi*: *;:21 *: *o'.ilil': *1:2r :* ;:24*: *; :oa *: *o: ii':

1.07. 1.24

1,24

0.99. 1.24, 1.11 , 1,29, 1.10. 1.24. 0,99. 1.21

1.22

1.06 , 0.32

7

*0.3, *1.0, ~0.7, *0,7, *0.3. 2.1

4,8. 3.4, 3.0, 2,2. -0.2. *2.7. *1.6, -1.9. *0.4.

- o:i;***o:1a***;:1a***1:2i***;:2;*:*1:21***1:24***1:;i***,:24***;:21***1:2;***;:2i***1:1a***o:1a***o:i;**

0.34. 0.78. 1.16, 1.22. 1.25, 1.29. 1.31

1.17. 1.27. 1.28. 1.25. 1,19. ~.16. 0.79. 0.35. 8

, *2.0. *1.2. *1.8. *0,3. -0.1

2.P, ,.3, 4.4. 2.4. 0.9. *0,2. *2.8. -2.0. 1,0. 0.6.

o:H*: *;:oa*: *1:24': *;:2;*: *0:99*: *; :2;*: *;:or:* 1:24*: *;:06*: *; :2; *: *0:99*: *; :2;*: *;:24*:

0.31 , 1.05. 1.21

1.24

1.D2. 1.23

1.07. 1.28

1.10, 1.23

0,99, 1.22 ~

oa*

*o:ii':

1.23

1.08 . 0.33

9

*3.5 * -2.8. -2.9 * -o.4. 2.4. 1.2 .* o.7. 2.8. 3.3

1.4

o.3 * -2.0 * -o.8

o.3

0.1 .

.. .. ***:* *o:ff: *;:20*: *i:ia* :* ;:21 *: *; :22*: *;:i, *:* ;:21*:* ,:i; ~:*;:22*: *;:2; *: *;: ici': *,:20*: *a:H *: *******

0,70. 1.15, 1.29. 1.22, 1.23, 1.22. 1.28, 1.24, 1.24. 1.21. 1.28, 1.18. 0.72, 10

, *3.7. -3~J, *1.1

0.9. 0,5 0.5, 1.1. 1,8. 1.4, 0.1 * *1,l * *1,5, *1.3 ,

o:ii*:*;:01*:*;:2i*:*,:29*:*;:2,*:*o:99*:*;:2;*:*o:99*:*;:2;*:*,:29*:*,:2;*:*,:01*:*o:ii':

, 0.35 , 1.05

1.22

1.28

1.20 , 0.99

1.25

1,00 , 1.22

1.29

1.22

1.05 , 0.35

11

, *1.5. -1.5. *1.3. *1.0, *0,6, *0.4. *0,5. b,5, 1,2. *0.3. -1.0, -1.1 * -1.0,

....... :* *a:4; *: *o:ar: *;:2r: *,:io*: *;:2i': *;:2r: *~:2;* :* ;:ia*: *;:ff:* a:iil': *0:4;*: ***.. **

0.41 , 0.89 , 1.22 , 1.28 , 1,23 , 1.21

1.24 , 1.30 , 1.23 , o.u , 0.41 , 12

0.1. -o.o. -1.1 * -1.3. *1.3. *0.9. *0,3 * -o.3 * -o.8. -1.4. -0.2 *

.. ".: 'o: 4;.:. i :w: 'i :20':.; :24':. i: ii.:' i :24':.; :20.:' i: 07.:. o: 4;.:. '. ..

o.41

1.oa. 1.19. 1.23. 1.11. 1.22. 1.11

1.05

o.40. 13

o.9. 1.1 * -0.1 * ~1.4. -1.4. -1.9. -2.0. -1.9. -1.1 *

.. **.... *o.36. o: i6' **o:o.75.ff** 1.12.

,:oi *.. o:0.81.

ii*** 1.06. ;:oa ***o:1i *: *o:i6' ********

0.12 '. o.35. 14 STAICOARD

..............,..0.33 .......0.34.

1,1 , 2,4. 4.0, 3.6. *1,7. *1.9, *2.0 *

.. . ....0,33 ........ ....... ..... *............... AVERAGE

.*

OCVIATIOII 0.34. 0.36. 0.34. .PCT DIFFERENCE. 15

1.142 3.9. 3.8. 3.9.

1.5.

SUMMARY

HAP NO: S2-9* 6 DATE: 03/30/87 POWER: 99%

CONTROL ROD POSITIONS: F-Q(T) = 1. 792 QPTR:

D BANK AT 197 STEPS F*DH(N) = 1.445 NW 1.007. I NE 0.994 F(Z) = 1.190 -----------1-----------

SW 1. 000 I SE 0.999 F(XY) = 1.390 BURNUP = 428 MWD/MTU A.O = *l. 04(i) 32

_*, '?!-~~ *: :*.:.~*-:-* 1::....**. *::y.**.-.-~~~-, : '_.: - , * : --~'.: ~-. = -~ \~;~/;.~ _,i./t2~.:::

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

'

-

.* ... :-.

SECTION 7 REFERENCES

1. D. A. Trace, M. E. Paul, "Surry Unit 2, Cycle 9 Design Report," NE Technical Report No. 550 ~ Virginia Electric and Power Company, October,1986.

2. Surry Power Station Technical Specifications, Sections 3.12.C.l and 3.12.B.1.

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

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

Westinghouse Electric Corporation.

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

33

. * . ::*.< :* .*-* .. ** .......

-~~ !*'

,.*.**

' '

........

:,r:I: ,* * '/***

.*

.. *:.*.*.,:

.;* -*

, .

- -

..

,*

-...

. ** .. -.*.

..........

APPENDIX STARTUP PHYSICS TESTS RESULTS AND EVALUATION -SHEETS 34

'*.: ',.. ~; . i

., ....

~ -. ".-.. - . *: *.'-**'.' . . -

. : ~ . *-*.

-

_ _ ..c_:_______:_,___ **_. -~*,,:_;__:.:..:_**,.

. ;;,.:* -----------'--,---~---

O;-'*: *-

2-PT-28.11 Attachment 1 Pagel of 19-SURRY POWER STATION UNIT 2 CYCLE 9 NOVO 4 1986 STARTUP PHYSICS TEST .RESULTS AND EVALUATION SHEET I Test

Description:

Reactivity Computer Checkout Reference Pree No /Section: 2-PT-28.11 Sequence Step No: 3 II Banlt Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design) CB: 228 CC: 228 CD:

Belew Nuclear Heating

'

III Bank Positions (Steps) RCS Temperature (°F) : 543.3 Test Power Level(% F.P.): 0 Condit ions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB: 228 CC: 228 CD: 199 Below Nuclear Heating Date/Time Test Performed:

11/30/86 11:58 Measured Parameter Pc = Meas. Reactivty using p*computer.

IV (Description) Pt= Inferre,!'React from react period p

C

= +66 pcm -39 pcm Measured Value +6.8 pcm -39 pcm p

t =

Test %D = -3.03% 0%

Results Design Value (Actual Conditions) 100% S 4.0% '

'YJl = [(pc-pt)/pt] X Design Value (Design Conditions) %D = [(pC*pt)/pt] X 100% S 4.0%

Reference WCAP 7905, Rev. 1, Table 3.6 V FSAR/Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met : ...!..YES _NO VI Acceptance Criteria is met : -X...YES _NO Comments

?

. ~ ..

At The Just Critical Position Allowable Range=+/- 39.0

.

Completed B y , ~ ~ ~ Evaluated By: ~1.~~

.

Test Exfgineer Recommended for Approval By c.>1~

NFC Engineer 35

--~ *~ _.* *. *..:

.. *..-. :. *... ~= *; .: :.- *"' * **. . **: ........ ,* ....... '. **..*

~* ~ " .. , .. .;::**. .. -.... . *~~ -. :::,-:*_( '; .. : ...

-*~:.'!:*:----,..---------

.e* e**

.2-PT-28.11 Attachment 1 Page 2 of 19 NOV O ( .1986 SURRY POWER STATION UNIT 2 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND EVALl,JATION SHEET I Test

Description:

Critical Boron Concentration* ARO Reference Proc No /Section: 2-PT-28.11 Sequence Step No: 4 II Bank Positions (Steps) RCS Temperatur~ (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design) CB: 228 CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature .(°F): 543.5 Test . Power Level(% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB: 228 CC: 228 CD: 228 Below Nuclear Heating Date/Time Test Performed:

11/30/86 @ 1349 Meas Parameter (Description) ( M.

IV CB)ARO' Critical Boron Cone - ARO

. M Measured Value (CB) ARO = 1609 ppm Test Results Design Value (Actual Cond) CB= 1652 ::!: 50 ppm Design Value (Design Cond) CB =1652 +/- 50 ppm Reference NE Technical Report No. 550 V FSAR/Tech*Spec CICB x CB~ 15,115 pcm Acceptance Criteria Reference UFSAR Section 14.2.5

Design Tolerance is met : -1...YES __NO Acceptance Cri~eria is met : _LYES __NO VI

... ,._-.'

Comments CIC = -7.89 pcm/ppm for preliminary analysis

... ;:.' B

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

.* *.""-. aCB = -8. 34 pcm/ppm for final analysis

'

Completed B y : ~ Evaluated By: ~_L.,<<2~

~est Eng¥er Recommended for Approval By : c_2~

NFO Engineer 36

-:* .. *t* .. ... -. -* .. *. *; *;.::!.~.-:*;_.*,;,**

.:~. **: :* :. **.- --~ >:: .. :, _ *../.' *_:_. : n ... *. *.-* * ~ . '.' *.. * *, ::.~ *:~-./ ~:.*-~.....:_*_: ._.:_ * '-.~ *:, ;\ :* -~ * ,_.

(' ..

-

-

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

2-PT-28.11

.*.";,*- Attachment l

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

. '

Page 3 of 19

SURRY POWER STATION UNIT 2 CYCLE 9 "UV O 4 1986

....*,.

.~

STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

HZP Boron Worth Coefficent Measurement Reference Proc No /Section: 2-PT-28.11 Sequence Step No: 4 II Bank Positions (Steps) ..

RCS Temperature (°F): 547 Test Power Level (i F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design) CB:Moving CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (°F): 543,5 Test Power Level (1 F.P.): o*

Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify).:

(Actual) CB:Moving CC: 228 CD: 228 Below Nuclear Heating Date/Time Test Performed:

11/30/86@ 1349 Measured Parameter IV ..(Description) ac Boron Worth Coefficient B '

Measured Value ac = -8 .34 pcm/ppm B

Test Results Design Value (Actual Conditions) ac -. -7.89 + 0.79 pcm/ppm B

Design Value (Design Conditions) ac = -7.89 +/- 0.79 pcm/ppm B

Reference NE Technical Report No. 550 FSAR/Tech Spec aC x CB S 15,115 pcm B

V Acceptance Criteria Reference UFSAR Section 14.2.5 Design Tolerance is met : JLYES _NO VI Acceptance Criteria is met : .L.YES _NO

, ~ -: .: : _. Comments

~

,.

.*.*

.....:_:.--*,1**,

.:

.*

/

.

Completed By Evaluated By: ae:;L ,,e;;;D<If:.~ e Test Engineer .

Recommended for Approval By: C:1~

NFO Engineer 37

- . ..

~ ,* ;* *;,,. . .. :,* ...

-

*. *.,*_::I * ..**_.._*. *,. . *- . . ~ .

.

. _*-: :,;..---------

e

.'_;**; *1:\

..

.- ,**

2-PT-28.11 Attachment l

.... **.,, Page 4 of 19 SURRY POWER STATION UNIT 2 CYCLE 9 NOV O , 1986

- - - - ,*

., STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET

- .:..,

I Test

Description:

Isothermal Temperature Coefficient - ARO Reference Pree No /Section: 2-PT-28.11 Sequence Step No:5 II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design) CB: 228 CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (°F): 543.90 F Test Power Level(% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB: 228 CC: 228 CD: 217 Below Nuclear Heating Date/Time Test Performed:

11/30/86 1359 Meas Parameter (Descript_ion) ISO Isothermal Temp Coeff - ARO IV (a T )ARO Test Measured Value ( 11 ISO) _ pcm/°F (CB= 1616Ppm)

T . ARO - -2.36 Results Design Valu~

(Actual Cond) ( ISO) .

a T ARO= -2~73_::: 3pcm/°F (CB= 1616ppm)

ISO (a T )ARO= -2.37 +/- 3.0 pcm/°F Design Value (Design Cond) (CB = 1652 ppm)

Reference NE Technical Report No. 550 aI;o S 0.82*pcm/°F Dop _

V FSAR/Tech Spec a T - -1. 68 pcm/°F Acceptance Cr'"i.teria

Reference

TS 3.1, NE Technical Report No. 550 Design Tolerance is met : LYES _NO VI Acceptance Criteria is met : JL.YES _NO

. ::*:

- - - .. : .*

':-:

Comments

Uncertainty on Cir * = 0. 5 pcm/ °F (

Reference:

memorandum MOD

. *-: :. <'

.*.. * ***.,:*

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

Completed B~~ Test Engine .

Evaluated By:

Recommended for Approval By : C - ~ ~

NFO Engineer 38

*.-: : -. ::--*.:-:** ~ --.,* '-1.* . : ,: :-~j\l. ~ '.:.:~ :.::.-*:*,:: *~ .': *-:::;*. *::. ~:-** , .. *.* ..

..... f . . ~

-. ..

...~.

.

. : :~.' . :*' *. ~-

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

'*

I ' * :.,. ' *

- - *.-.'

2-PT-28.11

'.,%.

Attachment 1 Page 5 of 19 SURRY PO.WER STATION UNIT 2 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Cntl Bank B Worth Meas. ,Rod Swap Ref. Bank Reference Pr.cc No /Section: 2-PT-28.11 Sequence Step No: 6 II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power .Level(% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design) CB:Moving CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (°F): 546.4 Test Power Level(% F.P.): 0 Conditions SDA: 228 SDB: 228

CA: 228 Other (Specify):

(Actual) CB:Hoving CC: 228 CD: 228 Below Nuclear Heating Date/Time Test Performed:

11/30/86 1457 Measured Parameter I~F;Integral Worth of Cntl Bank B, (Description) All Other Rods Out IV Measured Value IREF _ 1342 pcm Test B -

Results Design Value (Actual Conditions) IREF -

B - 1427 + 143 pcm Design Value (Design Conditions) I~= 1427 +/- 143 pcm Reference NE Technical Report No. 550 If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result

>*-:.:~*:*- ~; :; FSAR/Tech Spec on safety analysis. SNSOC may specify V that additional testing be performed.

Acceptance

'.~:~t1

'\'.~~:\~f:'-i

.*{.-\/)/~]

Criteria Reference Design Tolerance is met VEP-FRD-36A

..x_n:s _NO VI Acceptance Criteria is met : _x.__n:s __NO

' Comments

//

Evaluated By: t:at;;L,, ~Aifr-c...tL..

Recommended for Approval By : c.--1~

NFO Engineer 39

- - - - , *;.*-.* , ... ~*, D:::, ~ .:-

.,* <,. * * - * ' * * * * **** ~ *

,_.~:_* -.. ,*

e 2-PT-28.11 Attachment l Page 6 of 19 SURRY POWER STATION UNIT 2 CYCLE 9 NOV O 4 1986 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Critical Boron Concentration - B Bank In Reference Proc No /Section: 2-PT-28.11 Sequence Step No: 7 II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level Ci F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design) CB: ' 0 CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (°F): 545.2 Test Power Level(% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB: 0 CC: 228 CD: 228 Below Nuclear Heating Date/Time Test Performed:

11/30/86@ 2308 Meas Parameter IV (Description) M, (CB)D, Critical Boron Cone - B Bank In Measured Value (CB)~ = 1448 ppm Test Results Design Value (Actual Cond) CB= 1429 +/- 26 ppm Design Value '

(Design Cond) CB= 1472 + AC~rev +/-(10 + 142.7/lac I )ppm B

Referenc*e NE Technical Report No. 550 V FSAR/Tech Spec ac x CBS 15,115 pcm B

Acceptance Criteria Reference UFSAR Section 14.2.5 Design Tolerance is met : -1LYES _NO Acceptance Criteria is met : _x_YES _NO VI Comments ac = -7 .89 pcm/ppm for preliminary analysis B

ACPrev - (C) M - 1652 B - B ARO aCB = -8.B4 pcm/ppm for final analysis A

Completed By: ~/ ti ./

Test Engineer

,I \

Evaluated By: ar...L~

-

Recommended for 40 Approval By: c.1~

NFC Engineer

"!, * -* . . * . * *~ ' ....,

...::*.:...._

.. :

- - ** 2-PT-28.11 Attachment 1 Page 7 of 19 SURRY POWER STATION UNIT 2 CYCLE 9 N_OV O 4 1986 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET*

I Test

Description:

Cntl Bank D Worth Measurement-Rod Swap Reference Pree No /Section: 2-PT-28.11 Sequence Step No: 9 II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level (I F.P.): 0 Conditions SDA: 228 SOB: 228 CA: 228 Other (specify):

(Design) CB:Moving CC: 228 CD:Moving Below. Nuclear Heating ill

- i~.-:.,\;.*::.:.:,:

??t\i Conditions (Actual)

III Test Bank Positions (Steps)

SDA: 228 SDB: 228 CB:Moving CC: 228 CA: 228 RCS Temperature (°F): 546.7 Power Level (% F .P.): 0 Other (Specify):

CD:Moving Below Nuclear Heating Date/Time Test Performed:

,;\*s\: i 12/01/86 @ 0215

,>{~:\'~! Meas Parameter

-.>~~::.:.*:;_i/1 (Description) I~5 ;Int Worth of Cntl Bank D*Rod Swap IV. (Adj. Meas. Crit. Ref Banlt RS_

Test Measured Value 1D- 1034 pcm Position = 173 steps)

Results Design Value (Adj. Meas. Crit. Ref Bank (Actual Corid) .r~5= 994 +/- 149 pcm Position = 173 steps)

Design Value rRS_ '993 +/- 149 pcm (Critical Ref Bank s)r~::;:'.1 (Design Cond)

D-Position= 157 steps)

Reference NE.Technical Report No. 550, VEP-;FRD-36A, NFO-TI-2.2A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed.

Criteria Reference VEP*FRD-36A Design Tolerance is met : .JLYES _NO

'_(.}>.\j VI Acceptance Criteria is met : ..L..YES __NO

.<\:y.:*;J Comments

/?

-

Completed By: ~/7 Test'Engineer Evaluated By: ¢l'l:::,.J. L:7-?-4Uz.

I Recommended for

.

t1 9 Approval By : _;::C:;;....;..'..:J.'---~---

NFO Engineer 41

., ... *-- ****,**;' ...... *:

--..-------------- -

2-PT-28.ll Attachment l Page B of 19

. SURRY POWER STATION UNIT 2 CYCLE 9 NIJV O 4 1986 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Cntl Bank C Worth Measurement-Rod Swap Reference Proc No /Section: 2-PT-28.11 Sequence Step No:

II Bank Pas i tions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design) CB:Moving CC:Moving CD: 2.28 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (°F): 544 .6 Test Power Level(% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB:Moving CC:Moving CD: 228 Below Nuclear Heating

>j)?/~J Date/Time Test Performed

~Xi:if'

/,. ~./t.:r

\ 12/01/86 @ 0304 Meas Parameter

/;{//~,~

. ,,, .*' ::*'-:.. ~ (Description) I~s; Int Wortll. of Cntl Bank C*Rod Swap IV (Adj. Meas. Crit. Ref Bank Test Measured Value IRS_ 877 pcm Position = 149 steps)

C-Results Design Value. (Adj. Meas. Cri t. Ref Bank (Actual Cond) IRS_ 838 +/- 126 pcm::iosition = 149 steps)

C-

.. **-*.:._:/<;

Design Value I~S= 836 +/- 125 pcm (Critical Ref Bank (Design Cond) Position= 132 steps)

Reference NE Technical Report No. 550, VEP-FRD-36A, NFO*TI-2.2A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed.

Criteria Reference VEP-FRD*36A ti}{?

,,~ **: .. . Design Tolerance is met : _LYES _NO VI Acceptance Criteria is met : _LYES _NO Comments

.. '.**,.*

- - -;.*

/

~. *. f": :..-:

Evaluated By: ot'CL .:2?~12.

-

Recommended for Approval By: c~.:1~

NFO Engineer 42

- e 2-PT-28.11 Attachment 1 Page 9 of 19 SURRY POWER STATION UN IT 2 CYCLE 9 NOV 0 4 1986 STARTUP PHYSICS TEST RESULTS AND. EVALUATION SHEET

... ~ : ' ....

I Test

Description:

Cntl Bank A Worth Measurement-Rod Swap Reference Proc No /Section: 2-PT-28 .11 Sequence Step No: 11 II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level (i F.P.): 0 Conditions SDA: 228 SDB: 228 CA:Moving Other (specify):

(Design) CB:Moving CC: 228 en:* 228 Below Nucle.ar Heating III Bank Positions (Steps) RCS Temperature (°F): 545.4 Test Power Level(% F.P.): 0 Conditions SDA: 228 SDB: 228 CA:Moving Other (Specify):

(Actual) CB:Moving CC: 228 CD: 228 Below Nuclear Heating Date/Time Test Performed:

12/01/86@ 0347 Meas Parameter (Description) RS IA ;Int Worth of Cntl Bank A - Rod Swap IV (Adj. Meas. Crit. Ref Bank 5

Test Measured Value r! = 3ao pcm Position= 85 steps)

Results Design Value (Adj. Meas. Crit. Ref Bank

. (Actual Cond) I!S= 406 +/- 100 pcm Position = 85 steps)

Design Value I!S= 396 +/- 100 pcm (Critical Ref Bank (Design Cond) Position = 77 steps')

Reference NE Technical Report No. 550, VEP*FRD-36A, NFO-TI-2.2!

If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/Tech Spec safety analysis. SNSOC may specify th.at Acceptance additional testing be performed.

Criteria Reference VEP*FRD-36A Design Tolerance is met : iYEs _NO VI Acceptaace Criteria is met : _LYES _NO Comments

.,,

Evaluated By: !21'C..L ?Z?~.e Recommended for Approval By: c_-2~

NFO Engineer 43

.....

.............. ,..

.,*:*- ..... . .. *:*-1:1.. -*:-.: ~ ~-- :*. *': :"> .~ *; ; .' ....-. ;: ' *.". :- : :~:* ~-':..- *..* *. : .=-.~ ..~ -~. << * .'. .***.;' :.-...

. : ,: ... ~.'*. ~ .. .: :, ,: .. ',* _

.,.; r~. - e*

2-PT-28.11 Attachment 1 Page 10 of 19 SURRY POWER STATION UNIT 2 CYCLE 9 NOV' 0 4 1986

~ ..-::-: . .

STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Shutdown Bank B Worth Meas. - Rod Swap Reference Pree No /Section: 2-PT-28.ll Sequence Step No: 12 II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: 228 SDB:Moving CA: 228 Other (specify):

(Design) CB:Moving CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (°F): 545.1 Test Power Level(% F.P.): 0 Conditions SDA: 228 SDB:Moving CA: 228 Other (Specify):

(Actual) CB:Moving CC: 228 CD: 228 Below Nuclear Heating

/;~::*.~:*., ~?}

./:.:.:.:::;:j Date/Time Test Performed:

/h~\:;...j 12/01/86 @ 0414

Df.:)\ Meas Parameter RS (Description) IsB;Int Worth of Shutdown Bank B-Rod Swap ii IV (Adj. Meas. Crit. Ref Bank Test . Measured Value IRS= 1098 pcm Position= 182 steps)

SB Results D~sign Value (Adj. Meas. Crit. Ref Bank

":).??~ IRS_ 1087 (Actual Cond) SB- +/- 163 ix:m Position = 182 steps)

/~\)};t\

.!_~.-:::;')

t:ff/M

. ~~- : ~ *....<:,

'"**,-*.,*

1 Design Value IRS= 1085 +/- 163 pcm (Critical Ref Bank SB (Design Cond) Position= 171 steps)

Referenc~ NE Technical Report No. 550, VEP-FRD-36A, NFO*TI-2.2A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed.

Criteria Reference VEP-FRD-36A

~--~<...::, *.: :J Design Tolerance is met : ,X_YES _NO

/\ ~:_:.-.*.~ \ VI Acceptance Criteria is met : .LYES _NO

"\.-*. ;~-~)>.; Comments

/

Completed By:

~A ~ :::.1

. /,*

~

Y1' Evaluated By: t::JY.J.~~

.

/ Test Engineer /

Recommended for Approval By: c.2'~

. NFC Engineer 44

...

.....

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2-PT-28.11

-:*-~***'.

.::*:-****.

Attachment 1 Page 11 of 19 SURRY POWER STATION UNIT 2 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET NOV O 4 1986 I Test

Description:

Shutdown Bank A Worth Meas. - Rod Swap Reference Proc No /Section: 2-PT-28.ll Sequence Step No: 13 II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): 0 Coriditions SDA:Moving SDB: 228 CA: 228 Other (specify) :

(Design) CB:Moving CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (°F): 546.0 Test Power Level(% F.P.): 0 Conditions SDA:Hoving SDB: 228 CA: 228 Other (Specify):

(Actual) CB:Moving CC: 228 CD: 228 Below Nuclear Heating Date/Time Test Performed:

12/01/86@ 0451

. )

Meas Parameter (Description) I:!;rnt Worth of Shutdown Bank A-Rod Swap IV (Adj. Meas. Crit. Ref Bank Test Measured Value IRS_ 1007 pcm Position = 169 steps)

SA-Results Design Value (Adj. Meas. Crit. Ref Bank (Actual Cond) I:i= 1084 +/- 163 pcm Position = 169 steps)

Design Value IRS_ 1085 +/- 163 pcm (Critical Ref Bank SA-(Design Cond) Position= 171 steps)

Reference NE Technical Report No. 550, VEP-FRD-36A, NFO*TI-2.2A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed.

Criteria Reference VEP-FRD-36A Design Tolerance is met : ...LYES _NO VI Acceptance Criteria is met : ...LYES _NO Comments

/J Completed By: Evaluated By: ~4c:;;;odP::7-c_ L Recommended for Approval By: c~2~

NFO Engineer 45

!* .*.. -,*.-*.

*.}** :.**:** .

---------

-

. *_ .. : ....* .

e

- - * .,J. -*--* ,_

-~. .*.. , :

2-PT-28.11 Attachment 1 Page 12 of 19 SURRY POWER STATION UNIT 2 CYCLE 9 NOVO 4 S88

:*-\'

,-**

STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Total Rod Worth - Rod Swap Reference Proc No /Section: 2-PT-28.11 Sequence Step No: 15

~ ::~~:

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

(Design) CB:Moving CC:Moving CD:Moving Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ( 0 f): 546.4 Test Power Level Ci F.P.): 0 Conditions SDA:Moving SDB:Moving CA:Moving Other (Specify):

!!Wi (Actual) CB

Moving CC:Moving CD.:Moving Below Nuclear Heating

~~~i

.*. * ... ** :'.

Date/Time Test Performed:

11/30/86@ 1457

_ -'*.*1/~:* Meas Parameter

. :~* *~~...\} ~\ (Description) ITotal;Int Worth of All Banks - Rod Swap

~::*/:X:\;~

IV

)~i]

'. ~*;...\:

.*:;: :~*-:..::*~;

Test Results Measured Value Design Value (Actual Cond)

!Total= 5738 pcm

!Total =

5836 + 584 *pcm

').{({

r:1~ Design Value (Design Cond)

!Total= -5822 +/- 582 pcm

-~;-~~\:-~:~~;.

.. -

Reference NE Technical Report No. 550, VEP*FRD-36A, NFO-TI*2.2A If Design Tolerance is exceeded, S~SOC ifJ{l Acceptance V FSAR/Tech Spec shall evaluate impact of test result on safety analysis. SNSOC may specify that additional testing be performed.

Criteria .......---------------------------------------------------

Reference VEP~FRD-36A Design Tolerance is met : .....!.YES __NO VI Acceptance Criteria is met : _l.YES __NO Comments

.. ~~ ; . ., :

Completed B y e ~ ~ Evaluated By: ~__./..::;;z;__.~

T~t Engineer \

Recommended for Approval By: c:.J.~'

NFO Engineer 46

... *-..-:*.* .. *;

,.,.,. L* ; .. *.:: '"~ ; * : * '":, * ' -: * * ..

I'* . :.-.*;.-*,** ..........

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,.*-:*.*. 2-PT-28.11

. ~--\ Attachment l SURRY POWER STATION UNIT 2 CYCLE 9 Page of 13 o*f 19 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET ""' O 4 1986 I Test

Description:

M/D Flux Map - Low power Reference Pree No/ Section: 2-PT-28.2, 2-0P-57 Sequence S.tep No: 41 II Bank Positions (Steps) RCS Temperature.(°F):TREF +/-1 Test Power.Level Ci F.P.): <30 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify)

(Design) CB: 228 cc: 228 CD:

Must have 2 38 thimbles III Bank Positions (Steps) RCS Temperature(°F): .J"..;,.s-Test Power Level ci F .P.): :ie, q ~

Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify): * *

(Actual) CB: 228 cc: 228 CD: /1./-7 (}l,'f111',,t>r:/ 3,- r J , 1 ~ 'fJ,~,~~Hf!

J.c, w,,.,,

1

,,f cJ.*,,,,,/ -'-,6,~ e*,,,._f

.,.._ .. ;

- ,*-:.!

.. Date/Time Test: J,1d 1u*-'r-f FJ-IIW,,. ,!,;/f IHtp' I~

... ~-~ *.. :,:.a

,:: **?-,, '~ Performed: /?/O:J/'S' 0/01 ,e~/,,ttl~t:/.

MAX. REL ?-.'UC ENTHAL TOTAL HEAT QUADRANT IV Meas Parameter ASSY PWR RISE HOT FLL'X HOT POWER TILT ' I

!~%1 (Description) i DIFF (M*P)/P CHAN FACT CHAN FACT F*dH(N) F-Q(T)

RATIO QPTR

!

'*'"$ ,.,,,

tI;* Test Results Measured Value Design Value (Design Conds)

~f ~ OJI P,., * .:,,~,.

'*"" ().q

tea ,... ,, a o.~

I 1'I fw , C 0,1 1

*

Auy . ...... ,

WCAP-7905 NA-NA NA NA

/. ~t?85 S 1.02 WCAP-7905 Reference REV.l NONE NONE REV.l V FS.AR/Tech Spec NONE .,:'.,s1.9[1*.l(1*P)J *i1n *.._.

IUZJ NA Acceptance Criteria Reference NONE TS 3.12 TS 3.12 'I'.S 3.12 Design Tolerance is met . .LYES _NO Acceptance Criteria is met . L.-YES _NO VI Comments **As Required

-

Completed B y : ~ Evaluated By: ak. / .uP~

"'Te.st Engineer Recommended for Approval By . C. _)

NFO Engineer (

47

~ .... .. -...... :' *-........-: .. :

.

-

-* .

.*

.._.**.:-*. ::

2-PT-28.11 Attachment 1 Page 14 of 19 SURRY POWER STATION UNIT 2 CYCLE 9 STARTUP PHYSICS. TEST RESULTS AND EVALUATION SHEET NOV O 4 1986 I Test Description :M/D Flux Map-At Power Reference Proc No/ Section: 2-PT-28.2, 2-0P-57 Sequence Step No: 43 II Bank Positions (Steps) RCS Temperature (°F):TREF +/-1 Test Power Level (% F.P.): - 50 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify)

(Design) CB : 228 cc: 228 CD:

Must have~ 38 thimbles III Bank Positions (Steps) RCS Temperature(°F): .s~o Test Power Level (: F. P.) : $~. t'f; Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB: 228 cc: 228 CD: I.S-.5 4o +h\ ......\,ks Date/Time Test:

Performed: /-.2./()S/8" O'fS:z.

MAX. REL NUC ENTHAL TOTAL HEAT QUADRANT IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT (Description) I DIFF CHAN FACT CHAN FACT RATIO (M-P)/P F-dH(N) F*Q(T) QPTR

,. :z ,. ,{'. ,

'j,,. ~ 17,'I()

Measured Value '1,:;;i" ~or /,S"33 '2. 02g Test I.OOS7 PC.Ir < ().lflJ Results t lOI ,_. 111 it 0.*

Design Value t 1,Z fw Ill C 0,1 (Design Conds) ,.., ***..,. "'"'*> NA NA S 1.02 WCAP-7905 WCAP-7905 Reference REV.1 NONE NONE REV.l P~(ZJ a UI

It(~

V FSAR/Te~h Spec NONE ~Hsl.55(1*.l(l*l'l) P~(Z)G.1111' *. ll(Zl NA Acceptance Criteria Reference NONE TS 3.12 I TS 3.12 TS 3.12 Design Tolerance is met : ~YES __NO Acceptance Criteria is met : ...;L,.YES __NO VI Comments

As Required

/

Completed B y : ~ Evaluated By: ~ . /. ..c:::7-:> ~

. T~t Engineer Recommended for Approval By c.-1~ NFC Engineer ,

,(

48

.* ; ,**.* -*. , * .,-t_:: **. : . *, *. .. ' *

~ . :

... .

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

.*

'. *' ., '

.

e e

'*'.. .*

2-PT-28.11

Attachment l Page 15 of 19

'. :

SURRY POWER STATION UNIT 2 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET NOV O 4 1986

. I ,/ Test Description :M/D Flux Map-At Power,NI Calibration Reference Pree No/ Section: 2-PT-28.2, 2-0P-57 Sequence Step No: 44 II. Bank Positions (Steps) RCS Tempera;ure (°F):TREF +/-1 Test Power Level (I F.P.): - 70 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):*

(Design) CB: 228 cc :. 228 CD: **

III Bank Positions (Steps) RCS Temperature(°F): S6l, Test Power Level (l*F.P.): 70./,%

Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB: 228 cc: 228 CD: /(,:J t!Juq,fh - GtJrt: 1"4f' - ~I) 71,;,,.,J,.

Date/Time Test: obT<Tlne~

Performed: 1,/0~/SG' 0"35':Z.

MAX. REL NUC ENTHAL TOTAL HEAT QUADRANT IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT (Description) i DIFF CHAN FACT CHAN FACT RATIO (M*P)/P F-dH(N) F-Q(T) QPTR

~,.,_ ~.,.

P,,, ~ ().~()

Measured Value 9,,,.,, ~ NA Test lt'A NA Po,~ ~ P. 'II! .

Results

1111* fw P1 a a.~

Design Value I 1ft fw pl C 0.1 (Design Conds) *

Asay. Pw.J NA NA S 1.02 WCAP-7905 WCAP-7905

Reference REV.1 NONE NONE REV. l

~~1.55(1*.S(t*Pll

,~ma.u * *m V FSAR/Tech Spec NONE NA

-

Acceptance Criteria Reference NONE TS 3.12 TS 3.12 TS 3.12

.

Design Tolerance is met : ..LYES _NO Acceptance Criteria is met : ...::::LYES _NO VI Comments

Must have at least 38 thimbles for a full *core flux map, o r at least 16 thimbles for a quarter-core flux map.

- As Required

,,,,;;:?

... j Completed B y ~ Evaluated By: ~L.L:7-)~

Test Engineer Recommended for Approval By : c ...:1~

NFO Eng ineer 49

.. **; ,1*- --*-*-.*- ***-***. *:,..*: .--.~-.-. ,* .. ....... :~ -*~ ': *:/f-_,-:

2-PT-28.11 Attachment 1 Page 16 of 19 SURRY POWER STATION UNIT 2 CYCLE 9 NOV O t 1986 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET

. I Test Description :M/D Flux Map-At Power,NI Calibration Reference Pree No/ Section: 2-PT-28.2, 2 -OP-57 Sequence Step No: 45 II Bank Positions (Steps) RCS Temperature (°F):TREF +/-1 Test Power Level(% F.P.): - 70 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):*

(Design) CB: 228 cc: 228 CD: **

III Bank Positions (Steps) RCS Temperature(°F): .5'~t; Test Power Level (% F. P. ) : (, 'I. 1 ~

Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB: 228 cc: 228 CD: l'f S 0 werf,,-

Ct?"'t' M6'1' - 2/) ~,:W1,/t"s Date/Time Test: o6 r 4!? , - ; , ~ /

Performed: 1"2./IJ~/g~ 0(.,,2 7 MAX. REL NUC ENTHAL TOTAL HEAT QUADRANT IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT (Description) \ DIFF CHAN FACT CHAN FACT RATIO (M-P)/P F-dH(N) F-Q(T) QPTR l,.'f;,, +or Measured Value P,., 2 (),'Ti?

fo. q_t ~DI' N,,4 AIA /VA Test Pon, 'd.f'()

Results Design Value

1111 I 1,S

'°" ,j it (or ,, C o.~

0.1 (Design Conds) c,, * ,bay. l'wr.) NA NA :S 1.02 WCAP-7905 ~CAr-7905 Reference REV.l NONE NONE REV.l

~ HS1 .55(1 * .3(1*')] ,,(%JG. 1&'P

IUZJ, V FSAR/Tech Spec NONE NA Acceptance Criteria Reference NONE TS 3.12 TS 3.12 TS 3.12

.

Design Tolerance is met : LYES _NO Acceptance Criteria is met : LYES _NO VI Comments

Must have at least .38 thimbles for a full-core flux map, or at least 16 thimbles for a quarter-core flux map.

- As Required

/7 Completed By: ~ -

B'AA I Evaluated By: av,.L,.L7>~

~ Test Engineer Recommended for -.

Approval By C.::/ ~ .

NFO Engineer 50

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

'* *- * * ' 'I, ::- ' ~ ~ I

,i ~

**

.

I.I!,

.~*

..

e e

2-PT-28*. ll

.

Attachment l Page 17 of ;I.9 SURRY POWER STATION UNIT 2 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET NOV O 4 1986

. I Test Description :M/D Flux Map-At Power,NI Calibration Reference Proc No/ Section: 2-PT-28.2, 2-0P-57 Sequence Step No: 46 II Bank Positions (Steps) RCS Temperature (°F):TREF +/-1 Test Power Level(% F.P.): - 70 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):*

(Design) CB: 228 cc: 228 CD: **

III Bank Positions (Steps) RCS Temperature(°F): s~~

Test Power Level(% F.P.): 70~

Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB: 228 cc: 228 CD: l,2' Ov.,,.,,..,.,,_ro~ M",P - ;zp

-/1,;~,b/es Dbtq,,'nf/!'/.

Date/Time Test:

Performed: 1'2jo~/8~ /()'I/

MAX. REL NUC ENTHAL TOTAL HEAT QUADRANT IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT (Description) I DIFF CHAN FACT CHAN FACT RATIO (M*P)/P F-dH(N) F*Q(T) QPTR

'1.#:( ~t:)j Measured Value ,:,, z d. f/()

Test ,-.o,r ro, !VA lYA IIA P- - .e. dJ!/J Results

1os fer , 1 ;a o.~

Design Value S 131 fer ... C 0.1 (Design Conds) c,1 * .Auy. llwP.) NA

NA S 1.02 WCAP-7905 WCAP-7905 Reference REV.1 NONE NONE REV.1

..:~1.55(1*.J(MJJ ,;ma.tW a IC(ZJ V FSAR/Tech Spec NONE NA Acceptance Criteria

Reference NONE TS 3~12 TS 3.12 TS 3.12 Design Tolerance is met. : ...LYES __NO Acceptance Criteria is met : ..LYES _NO VI Comments

Must have at least 38 thimbles fer a full-core flux map, or at least 16 thimbles for a quarter-core flux map.

"*: -: . *-~ *.

- As Required

=*~-. *f.. ,/7 -

. *... :* .-. Completed By: d/M

-~sit'"!'ngineer \

Evaluated By: QR:'./.~

..

Recommended for c.:J~

Approval By:

NFC Engineer .

51

\/)\\)\*-. *,** ..

-~. -:/ :)

~--* .'.

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_:*_~ ;*~--~:*.5* ,.--.. -, .. ~. . *:....*:""',"::'*."

e e 2-PT-28.11 Attachment l

.*.***

.

SURRY POWER STATION UNIT 2 CYCLE 9 Page 18 of 19 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET NOVO 4 1986

.

I Test

Description:

M/D Flux Map - HFP, ARO, Eq. Xe Reference Proc No/ Section: 2-PT-28.2, 2-0P-57 Sequence Step No: 47 II Bank Positions (Steps) RCS Temperature (°F):TREF +/-1 Test Power Level(% F.P.):95 +/- 5 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): Eq. Xe.

(Design) CB: 228 cc: 228 CD:

Must have~ 38 thimbles III Bank Positions (Steps) RCS Temperature ( °F) : .$7 't "

Test Power Level(% F.P.): 'If!.~

Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB: 228 cc: 228 CD: 1'17-/ft, lfS Th/,nl>le.s 01,r,vh~

Date/Time Test:

Performed: '3/'30/V7 10'20 MAX. REL NUC ENTHAL TOTAL HEAT QUADRANT IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT

. . -~-- ' . *; * (Description) % DIFF CHAN FACT CHAN FACT RATIO (M-P)/P F*dH(N) F-Q(T) QPTR S:3 ~ .f.o,

~ ~(}.'/()

Measured Value 35"1.. ~~ 1,¥~.S /, 79'2. /. oot,, 9 Test Pt.is ~ (), f(}

Results t ,ca fw , 1 a o.*.

Design Value I 1ft far'* C 0.9 (Design Conds) (P

Aaay, ,-,)

1 NA NA S 1.02

..

WCAP-7905 WCAP-7905 Reference REV.1 NONE NONE REV.l

.

~tc'1.55{t*.J(1*P>J P~(ZJG.11/11

IUD V FSAR/Tech Spec NONE NA Acceptance Cr~teri~

Re~erence NONE TS 3.12 TS 3.12 TS 3.12

.

Design Tolerance is met . ...LYES _NO Acceptance Criteria is met*: -L..YES._NO VI Comments

As Required Co~leted

By:q \ll .J~,.,l,,

Test Engineer

.,,i,. Evaluated By: a£(',./. CZ?~

Recommended for C.

Approval By : - - - - -

J ~ .' **

..............

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NFO Engineer

~ **. *. /;

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ML18150A088: Difference between revisions

Revision as of 01:46, 21 October 2019

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ML18150A088: Difference between revisions

Revision as of 01:46, 21 October 2019

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SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

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Description:

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Description:

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