Text

Cycle 7 Startup Physics Test Rept. W/830801 Ltr
	ML18141A071
Person / Time
Site:	Surry
Issue date:	07/31/1983
From:	Hartsfield T, Snow C, Stewart W; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, Varga S; Office of Nuclear Reactor Regulation
References
	434, VEP-NOS-5, NUDOCS 8308080209
	Download: ML18141A071 (62)
	v • d • e

' 1* -* -* VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 w. L. STEWART VxcE Pl<ESXDENT

'NucLEAl<

0PE1<ATION9 August 1, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation ATTN: Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Denton,

SURRY POWER STATION Serial No. 434 NOD:TCH/hca Docket No. 50-280 License No. DPR-32 UNIT 1, CYCLE 7 STARTUP PHYSICS TEST REPORT For your information, enclosed are five copies of the Vepco Topical Report VEP-NOS-5, "Surry Unit 1, Cycle 7 Startup Physics Test Report. Should you have any questions, please contact us. Enclosures cc: Mr. James P. O'Reilly Regional Administrator Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station Very truly yours \J /-*-, ! L ( ( \ ....... ,-----..,.---

1--, \ ' i -... ::, 's;..'l.,~~""1

' ' W. L. Stewart

- VEP-NOS-5 SURRY UNIT 1, CYCLE 7 STARTUP PHYSICS TEST REPORT BY T. C. Hartsfield Reviewed By: Approved By: C. T. Snow, Supervisor Nuclear Fuel Operation Subsection E. N Subsection

,---830808-0209830731---~

PDR ADOCK 05000280 p PDR Nuclear Fuel Operation Subsection Nuclear Operations Department Virginia Electric and Power Co. Richmond, Va. July, 1983

--CLASSIFICATION/DISCLAIMER The data, techniques, information, and conclusions in this report have been prepared solely for use by the Virginia Electric and Power Company (the Company), and they may not be appropriate for use in situations other than those for which they were specifically prepared.

The Company therefore makes no claim or warranty whatsoever, express or implied,as to their accuracy, usefulness, or applicability.

In particular, THE COMPANY MAKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING OR USAGE OF TRADE, with. respect to this report or any of the data, techniques, information, or conclusions in it. By making this report available, the Company does not authorize its use by others, and any such use is expressly forbidden except with the prior written approval of the Company. Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of .warranties provided herein. In no event shall the Company be liable, under any legal theory whatsoever (whether contract, tort, warranty, or strict or absolute 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. i

ACKNOWLEDGEMENTS The author would like to acknowledge the cooperation of the Surry Power Station personnel in performing the tests documented in this report. Also, the author would like to express his gratitude to Mr. C. T. Snow, and Dr. E. J. Lozito for their aid and guidance in preparing this report. ii SECTION 1 2 3 4 5 6 7 APPENDIX ----TABLE OF CONTENTS TITLE PAGE NO. Classification/Disclaimer..................

i Acknowledgements...........................

ii List of Tables... . . * . . . . . . . . . . . . . . . . . . . . . . . iv List of Figures. . . . . .. . . . . . . . . . . . . . . . . . . . . . . v Preface....................................

vi Introduction and Summary .................. . Control Rod Drop Time Measurements

........ . Control Rod Bank Worth Measurements

....... . Boron Endpoint and Worth Measurements

..... . Temperature Coefficient Measurement

....... . Power Distribution Measurements

........... . References

................................ . Startup Physics Test Results and 1 10 15 20 24 27 34 Evaluation Sheets..........................

35 iii

LIST OF TABLES TABLE TITLE 1.1 Chronology of Tests ............................... . 2.1 Hot Rod Drop Time Summary ......................... . PAGE NO, 4 12 3.1 Control Rod Bank Worth Summary.....................

17 4.1

Boron Endpoints Summary............................

22 5.1 Isothermal Temperature Coefficient Summary.........

25 6 .1 Incore Flux Map Summary............ . . . . . . . . . . . . . . . . 29 6.2 Comparison of Measured Power Distribution Param-eters With Their Technical Specifications Limits...

30 iv

LIST OF FIGURES FIGURE TITLE PAGE NO. 1. 1 Core Loading Map. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 1.2 Beginning of Cycle Fuel Assembly Burnups.................

6 1.3 Incore Instrumentation Locations.........................

7 1.4 Burnable Poison and Source Assembly Locations............

8 1. 5 Control Rod Locations. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 2.1 Typical Rod Drop Trace...................................

13 2.2 Rod Drop Time -Hot Full Flow Conditions.................

14 3.1 Bank D Integral Rod Worth -HZP ..........................

18 3.2 Bank D Differential Rod Worth -HZP......................

19 4.1 Boron Worth Coefficient..................................

23 5.1 Isothermal Temperature Coefficient

-HZP, ARO............

26 6.1 Assembly Power Distribution

-HZP, ARO...................

31 6.2 Assembly Power Distribution

-51% Power..................

32 6.3 Assembly Power Distribution

-HFP, Eq. Xenon.............

33 V

---* 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 1, Cycle 7 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 includes a brief summary of each test, a comparision of the test results with design predictions, and an evaluation of the results. The Surry l; Cycle 7 Startup Physics Tests Results and Evaluation Sheets have been included as an appendix to provide additional information on the startup test results. Each data sheet provides the following information:

1) test identification, 2) test conditions (design), 3) test conditions (actual), 4) test results, 5) acceptance criteria, and 6) comments concerning the test. These sheets provide a compact summary of the startup test results in a consistent format. The design test conditions and design values of the measured parameters were completed prior to startup physics testing. The entries for the design values were based on the calculations performed by Vepco's Nuclear Fuel Engineering Group 1* During the tests, the data sheets were used as guidelines both to verify that the proper test conditions were met and-to facilitate the preliminary comparison between measured and predicted test results, thus enabling a quick identification of possible problems occuring during the tests. The Appendix

to this report contains the final completed and vi

approved version of the Startup Physics Tests Results and Evaluation Sheets. vii e e e e SECTION 1 INTRODUCTION AND

SUMMARY

On February 7, 1983 Unit No. 1 of the Surry Power Station was shutdown for its seventh refueling.

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

The seventh cycle core consists of 12 sub-batches of fuel: four once-burned sub-batches from Cycle 6 (8A2, 8A3, 8B2, and 8B3), one twice burned sub-batch that was carried over from Cycle 5 (6C3), three twice burned sub-batches that were carried over from Cycle 6 (7A2, 7B2, and S2/6B4), one thrice burned sub-batch from Cycle 4 (4C3), and three fresh sub-batches (9A, 9B, and S2/9B). 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 7. Figure 1. 5 identifies the location and number of control rods in the Cycle 7 core. On May 30, 1983 at 0350, the seventh cycle core achieved initial criticality.

Following criticality, startup physics tests were performed as outlined in Table 1.1. A summary of the results of these tests follows: 1. The drop time of each control rod was confirmed to be within the 1.8 second limit of the Surry Technical Specifications 2* 2. Individual control rod bank worths for all control rod banks were measured using the rod swap technique and were found to be within 14.4% of the design predictions.

The sum of the individual control rod bank worths was measured to be within 5. 3% of the 1 e e e e design prediction.

These results are within the design tolerance of +/-15% for individual bank worths (+/-10% for the rod swap reference bank worth) and the design tolerance of +/-10% for the sum of the individual control rod bank worths. 3. Critical boron concentrations for two control bank configurations were measured to be within 34 ppm of the design predictions.

These results were within the design tolerances and also met the accident analysis acceptance crite:rion.

4. The boron worth coefficient was measured to be exactly the design prediction, which is within the design tolerance of +/-10% and met the accident analysis criterion.

5. The isothermal temperature coefficient for the ARO configuration was measured to be within 0.25 pcm/°F of the design prediction.

This result is within the design tolerance of +/-3 pcm/°F and met the accident analysis acceptance criterion.

6. Core power distributions at HZP indicated that several measured assemblywise relative power values exceeded the established design tolerance.

This was accompanied by a quadrant power tilt ratio (QPTR) which at hot-zero-power, was measured to be approximately 2.5%, but decreased to 0.6% at full power. Core power distributions for various at-power conditions were generally within 6.8% of the predicted power distributions.

These deviations of power distribution at HZP had no adverse consequences since, for all maps, the hot channel factors were 2 e e e e measured to be within the limits of the Technical Specifications.

In summary, all startup physics test results were acceptable.

Detailed results, together with specific design tolerances and acceptance criteria for each measurement, are presented in the appropriate sections of this report. 3 e e -Table 1.1 SURRY 1 -BOL CYCLE 7 PHYSICS TESTS CHRONOLOGY OF TESTS Test Date Time Power Hot Rod Drop-Hot Full Flow 5/28/83 2120 HSD Reactivity Computer Checkout 5/30/83 0805 HZP Boron Endpoint-ARO 5/30/83 1303 HZP Temperature Coefficient-ARO 5/30/83 1333 HZP Bank D Worth 5/30/83 1615 HZP Boron Endpoint-D In 5/30/83 2226 HZP Bank C Worth -Rod Swap 5/30/83 .2244 HZP Bank B Worth -Rod Swap 5/30/83 2329 HZP Bank A Worth -Rod Swap 5/31/83 0021 HZP Bank SB Worth -Rod Swap 5/31/83 0215 HZP Bank SA Worth -Rod Swap 5/31/83 0523 HZP Flux Map-ARO 5/31/83 0909 HZP Flux Map -Power Distribution 6/17/83 2215 51% Verification Flux Map -NI Calibration 6/19/83 0640 61% Flux Map -NI Calibration 6/19/83 1252 73% Flux Map -NI Calibration 6/19/83 2008 84% Flux Map -HFP, Eq. Xenon 7/06/83 2015 100% 4 e Reference Procedure PT-7 PT28. ll(B) PT28 .11 (C) PT28 .11 (D) PT28. 11 (E) PT28 .11 (C) PT28 .11 (F) PT28 .11 (F) PT28. ll(F) PT28. ll(F) PT28. ll(F) OP-57, PT28.2 OP-57, PT28.2 OP-57, PT28.2 OP-57, PT28.2 OP-57, PT28.2 OP-57, PT28.2 R , N " e L e Figure 1. l SURRY UNIT 1 -CYCLE 7 CORE LOADING MAP K J H G F 9A 19A 19A I 107 I 001 I 105 I [ 4cJ I 8Al :~:Tc]:~:

8A3 I 4C3 I I D48 I 189 I 4RO I 039 I 3R2 I 01111 I 027 I e D , ___ , ___ , ___ , ___ , ___ , ___ 1 ___ 1 __ _ 1"6iiij"'"1 9A I 9A I 8B2 I 8B2 I 882 I 9B I 9A I 7A2 I I W14 I 203 I 208 I 1C8 I 5C1 I 5C5 I 509 I 3DO I 1A7 I e C ___ , ___ , ___ , ___ , ___ , ___ , ___ , ___ , ___ , ___ , __ _ I 7A2 I 4Cl I *9e I 4Cl I 9B I 8A2 I 9A I 4Cl I *9e I 4C3 I 7A2 I I 1A6 I 050 I 1R4 I 014 I 408 I OB4 I 206 I 049 I 1R2 I D06 I 1A3 I 8 -r:-;::--'---'---'---'---'....,...,.,.-'---'---1--'---'---'---'---

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1 __ 1 FUEL ASSEMBLY DESIGN PARAMETERS SUB-BATCH 4C3 6C3 7A2 7112 8A2 au 882 8113 9A 91 S2/6B4 S2/91 INITIAL EHRIClll1£HT*W/0 U235 3.325 2.902 2.901 3.393 3.217 3.217 3.399 3.399 3.589 3.605 3.203 3.$99 BURHUP AT BOC-7 (HWO/lffll) 26,620 24,809 24,420 29,499 20,575 20,202 19,417 15,689 D 0 26,342 0 ASSDIBLY TYPE 1SX1S 1SX1S 1SX15 ' 1SX15 1SX15 15:&15 lSX1S 15:&15 15X15 lSXlS lSXlS 15:&lS NUKIIEJt OF ASSEMBLIES 22 a 10 6 4 a 21 12 36 24 2 4 FtlEL ROOS PEil ASSDIBLY 204 204 204 204 204 204 204 204 204 204 204 204 5 2 3 5 6 7 a 9 10 11 12 13 14 15 R p e e e e Figure 1.2 SURRY UN IT 1 -CYCLE 7 BEGINNING OF CYCLE FUEL ASSEMBLY BURUNUPS H M L K J H G F E 1D7 OD1 I 1D5 I O I O I O I 1 ___ 1 ___ 1 ___ 1 -D"'4~8-"'"I

-1"'e"'9,-1 4RO I D39 I 3 R2 ,-o""e"'8-"'"I

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I 259791 202021 0 I 260381 0 I 200741 261411 , ___ 1 ___ 1 ___ , , ___ , ___ 1 ___ 1 I 007 l~I 207 I 1---1-*> ASSEMBLY ID I O I O I O I I I**> ASSEMBLY BURNUP 1 ___ 1 __ . _1_* __ 1 1 ___ 1 6 2 3 4 5 6 7 8 9 10 11 12 13 14 15 R N e e e Figure 1.3 SURRY UN IT 1 -CYCLE 7 INCORE INSTRUMENTATION LOCATIONS " L K J H G F E D I I I I MD I TC I ______ 1 ___ 1 ___ 1 ___ 1 __ ..,...-~ I I I I I e C a ,. I I ITCI ITCIHDI I 2 ___ 1 ___ 1 ___ 1 ___ 1 ___ 1 ___ 1~~1 ___ , __ _ I HD I I I I HD I I I I HD I ITCI ITCIHDITCI ITCI ITCI 3 ___ , ___ 1 ___ 1 ___ 1 ___ , ___ , ___ 1~~'---'---'---

1 I I I I I I I I I I I ITCI IMDI I IHDI IHDITCI ! I 4 ___ 1 ___ 1 ___ 1 ___ 1 ___ 1 ___ 1 ___ 1 1 ___ 1 ___ 1 ___ 1 __ _ I I I I I I I I I I I HD I I HD I I I HD I I MD I TC I HD I TC I I TC I HD I TC I I TC I 5 1 ___ 1 ___ 1 ___ 1 ___ , ___ 1 ___ , ___ 1 ___ 1~~'---'---'---'---'

I I I I HD I I I I I I I I I I I ITCI ITC! I IHDITCIHD I I I I I 6 ___ 1 ___ 1 ___ 1 ___ 1 ___ 1 ___ 1 ___ 1 ___ 1 ___ ,~~1 ___ 1 ___ 1 ___ 1 ___ 1 __ _ I I I I I I I I I I I I I I I I I TC I TC I MD I I I I MD I I HD I I TC I HD I I HD I I 7 1 ___ 1 ___ 1 ___ 1 ___ 1 ___ 1 ___ 1 ___ 1 ___ 1 ___ 1~~1 ___ , ___ 1 ___ 1 ___ 1 ___ 1 I I I HD I I HD I I I I I I I I HD I I I IMDITCITCI ITCITCI ITCITCIHD ITC! ITCIMDITCI 11 , ___ , ___ , ___ 1 ___ , ___ 1 ___ 1 ___ 1 ___ 1 ___ ,~~1 ___ 1 ___ 1 ___ 1 ___ 1 ___ , I I I I I I I I I I HD I I I I I I I I I ITCIMDI I ITCIHDITCI I I I IHDI 9 1 ___ 1 ___ 1 ___ 1 ___ , ___ 1 ___ , ___ 1 ___ 1 ___ 1~~1 ___ 1 ___ , ___ 1 ___ 1 ___ , I I HD I I I I HD I I I I I I I HD I I I TC I I I I TC I I I I TC I HD I I TC I 10 1 ___ 1 ___ 1 ___ 1 ___ 1 ___ 1 ___ 1 ___ , ___ 1~~1 ___ 1 ___ 1 ___ 1 ___ , I I I I I I I HD I I HD I I I I I I I I TC I MD I TC I I TC I I TC I HD I I I I 11 1 ___ , ___ , ___ 1 ___ 1 ___ 1 ___ 1 ___ , ___ ,~~1 ___ , ___ , ___ , ___ , I I I I I HD I I I ! I I HD I I HD I I TC I I TC I I I I TC I HD I TC I 12 1 ___ 1 ___ 1 ___ , ___ , ___ , ___ 1 ___ 1~~1 ___ , ___ 1 ___ , I I I I I HD I I HD I I I I I I I I TC I I TC I I I 13 1 ___ , ___ , ___ 1 ___ , ___ 1 ___ 1~1 ___ 1 ___ 1 I HD I I I I I I I I TC I I I I HD I I TC I 14 1 ___ 1 ___ , ___ 1 ___ , ___ 1~~1 ___ 1 MD

Movable Detector" I I I I TC

Thermocouple I HD I TC I-TC I 15 1 ___ 1 ___ 1 ___ 1 7 e e e e Figure 1.4 SURRY UN IT 1 -CYCLE 7 BURNABLE POISON AND SOURCE ASSEMBLY LOCATIONS R P N M L K J H G F E D C B A SP 4P 16P ss SP 16P 4P SP 16P 16P 16P SP 16P 16P 16P 8DP SP 16P 16P 16P 16P 4P SP 16P SP 16P 4P 16P ss SP S --DEPLETED BURNABLE POISON RODS 608 --FRESH BURNABLE POISON RODS SS --SECONDARY SOURCE SP 16P 4P 16P SP SP 4P 16P 16P 16P 16P SP 16P 16P 16P SP ss 16P 16P SP 4P 16P SP 16P 4P SP 8 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 t I e e Figure 1.5 SURRY UN IT 1 -CYCLE 7 CONTROL ROD LOCATIONS R P N M L K J H G F E D C B A l80D LOOP C INLET Absorber Material Ag-In-Cd LOOP C OUTLET ' N-41 C A B SA D SA A B C N-44 LOOP A/ OUTLET SB SP SP SB I A D SA SA B SP SP D C SB SB C SB SB D C SP SP B SA SA A D Function Number of Clusters

Control Bank D Control Bank C Control Bank B Control Bank A Shutdown Bank SB Shutdown Bank SA SP (Spare Rod Locations) 8 8 8 8 8 8 8 9 LOOP B INLET A / N-43 B C SB D B A SP SA C D SP SA D B A SB B C N-42 A 'LOOP A INLET 1 2 3 4 5 LOOP B 6 OUTLET / 7 -270a 8 9 10 11 12 13 14 15 e e e e SECTION 2 CONTROL ROD DROP TIME MEASUREMENTS The drop time of each control rod was measured at cold and at hot RCS conditions in order to confirm satisfactory operation and to verify that the rod drop times were less than the maximum allowed by the Technical 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 withdrawing a rod bank to its fully withdrawn position, and then removing the movable gripper coil fuse and stationary gripper coil fuse for the test rod. This allows the rod to drop into the core as it would in a normal plant trip. The data recorded during this test are, the stationary gripper coil voltage, the LVDT (Linear Variable Differential Transformer) primary coil .voltage and a 60Hz timing trace which are recorded via a visicorder.

The rod drop time to the dashpot entry and to the bottom of the dashpot are determined from this data. Figure 2. 1 provides an example of the data that is recorded during a rod drop time measurement.

As shown in Figure 2.1, the initiation of the rod drop is indicated by the decay of the stationary gripper coil voltage when the stationary 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 dashpot. Subsequent variations in the trace are caused by the rod 10 e bouncingo This procedure was repeated for each control 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 2 specifies a maximum rod drop time from loss of stationary gripper coil voltage to dashpot entry of 1. 8 seconds with the RCS at hot, full flow conditions.

All test results met this limit. 11 Table 2.1 SURRY UNIT 1 -CYCLE 7 BOL PHYSICS TEST HOT ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME B-6, 1.31 sec. K-4, 1.22 sec. 1.26 sec. ROD DROP TIME TO BOTTOM OF DASHPOT SLOWEST ROD FASTEST ROD AVERAGE TIME B-6, 1.75 sec. K-4, 1.59 sec. 1.68 sec. 12 o* *** * ...... . . .. . --.***-.-*-:-----.* .. . : ... -;-*** --;--* -.--4 -***------;--SURRY UNIT 1 -CYCLE 7 BOL PHYSICS TEST TYPICAL ROD DROP TRACE . . . . .. , .. ;: ... :--. -. Tu1i~~-TR~c.E~ ~itrqoN: Bu5 fR-~QUE~-lc~

. -. . . . .... * -** -

R p N e e e Figure 2.2 SURRY UNIT 1 -CYCLE 7 BOL PHYSICS TEST ROD DROP TIME -HOT FULL FLOW CONDITIONS M L K J H G F E D C I I I I I I 1. 27 :---:-1-.-2-5-:---:--:-1

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l ___ l--~~T~O~FT~~H~gT(SEC.)

14 e e e e SECTION 3 CONTROL ROD BANK WORTH MEASUREMENTS Control rod bank worth measurements were obtained for all control and shutdown banks using the rod swap 3 technique.

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

The reactivity changes resulting from the 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 D). At the completion of the reference bank reactivity worth measurement, the reactor coolant system temperature and boron concentration were stabilized such that the reactor was critical with the reference bank near full insertion.

Initial statepoint data for the rod swap maneuver were obtained by moving the reference bank to its fully inserted position and recording the core reactivity and moderator temperature.

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

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

This measured critical position (MCP) of the reference bank with the test bank fully inserted is the major parameter of interest and was used to determine the integral reactivity worth of the test bank. Statepoint data (core reactivity, moderator temperature, and the differential worth of the reference bank) were recorded with the reference bank at the MCP. The 15 '

e e e e rod swap maneuver was then performed in reverse order such that the reference bank once again was near full insertion and the test bank was once again fully withdrawn from the core. The rod swap process was then repeated for all of the other control rod banks (control and shutdown).

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 all of the control and shutdown banks were within 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 5. 3% 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 D) are shown in Figures 3.1 and 3.2, respectively.

The design predictions and the measured dat-a are plotted together in order to illustrate their agreement.

In summary, all measured rod worth values were satisfactory.

16 J e

e e Table 3. 1 SURRY UNIT 1 -CYCLE 7 BOL PHYSICS TEST CONTROL ROD BANK WORTH

SUMMARY

MEASURED PREDICTED PERCENT DIFFERENCE WORTH WORTH BANK (PCM) (PCM) (M-P)/P X 100 D-Reference Bank 1325 1293 2.5 C 610 672 -9.2 B 996 1164 -14.4 -A 445 492 -9.6 (47 pcm) SB 817 827 -1.2 SA 1072 1113 -3.7 Total Worth 5265 5561 ---5.3 17 0 0 e e Figure 3.1 e e SURRY UNIT BANK BANK D D 1 CYCLE PHYSICS TESTS 7 BOL ROD WORTH INTEGRAL WITH ALL OTHER PREDICTED ll( MEASURED HZP ROOS OUT ... ****-***---***

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I .. . . ... . . ".' . :* . **: .. *-* .. 80 120 160 fSTEPSl BANK POSITION 18 ***--i. .. i. ; .;. ... !**** 200 228 0 0 e e e e Figure 3.2 1 CYCLE 7 BOL SURRY UNIT BANK D BANK DIFFERENTIAL ROD D WITH ALL OTHER PHYSICS WORTH ROOS TESTS HZP OUT 40 PREDICTED JI MEASURED 60 l 20 BANK POSITION 19 160 (STEPS) 200 226 e e 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, i.e., 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 Test Results and Evaluation Sheets given in the Appendix, all measured critical boron endpoint values were within their respective design tolerances.

All measured values met the accident analysis acceptance criterion.

In summary, all results were satisfactory.

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

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

The value of the boron coefficient, over the range of boron endpoint concentrations, is 20 e e e e 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. 44 pcm/ppm. The measured boron worth coefficient is exactly the predicted value of -8.44 pcm/ppm and is well within the design tolerance of +/-10%. The measurement result also met the accident analysis acceptance criterion.

In summary, this result was satisfactory.

21

... ARO e e e Table 4.1 SURRY UNIT 1 -CYCLE 7 BOL PHYSICS TEST BORON ENDPOINTS

SUMMARY

Measured Predicted Control Rod Endpoint Endpoint Configuration (ppm) (ppm) 1301 1335 e Difference M-P (ppm) -34 D Bank In 1144 1153* -9

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

22 2400 .2000 " " I: 1600 N u l,.) " 0.... >-I-1200 .._ > .._ I-u a: w 800 a:: 400 0 1060 " I Fi~ure 4. 1 SURRY UNIT 1 -CY~LE 7 BOL PHYSICS TEST BORON WORTH COEFFICIENT l!I ENDPOINJ nEASUREnENJS = -8.44 pcm/ppm B ', "m I'... I'-. " "'l's. 'I',. "r-..... " " ....... ' " I"-.. " "'-~ -1120 1160 1200 1240 1280 1320 1360 BORON CONCENTRATION lPPMl 1400 ei I ' e e e e e e e SECTION 5 TEMPERATURE COEFFICIENT MEASUREMENT 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 nuclear heating, thus, the moderator and fuel were *approximately at the same temperature (between 544-548 °F) during this measurement.

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

An isothermal temperature coefficient measurement was performed at the ARO configuration.

Reactivity measurements were taken during both RCS heatup and cooldown ramps during which the RCS temperature varied approximately 4°F. Reactivity was determined using the reactivity computer and was plotted against the RCS temperature on an x-y recorder.

The temperature coefficient was then determined from the slope of the plotted lines. The x-y recorder plot of reactivity changes versus RCS temperature for the measurement is shown in Figure 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 design tolerance of +/-3 pcm/°F and met the accident analysis acceptance criterion.

In summary, the measured result was satisfactory.

24 BANK POSITION ALL RODS OUT e e e e Table 5.1 SURRY UNIT 1 -CYCLE 7 BOL PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

ISOTHERMAL TEMPERATURE COEFFICIENT TEMPERATURE BORON (PCM/°F) RANGE CONCENTRATION (OF) (ppm) COOL DIFFER. HEATUP DOWN AVER. PRED. (M-P) 543.8 to 1301 -5.66 -6.04 -5.85 -6.10 0.25 547 .5 25

1. -a p.. -e

e * *-VERTICAL Figure 5.1 SURRY UNIT 1 -CYCLE 7 BOL PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT HZP, ARO -.. .. llll.. 1"11 ' .-,,, ,. "" b t';:i1lo.,.,," -IA , . *--...... . .........

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(°F) 26 .... .... R ! ,-I 1-:-..... I I I ---

e e 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 strip chart recorder.

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

Full core, three-dimensional power distributions are then determined by analyzing this data using the 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 2 was taken at zero power. This flux map serves as the base case design check. Figure 6.1 shows the resulting radial power distribution associated with this flux map. This map indicated the presence of a quadrant power tilt (2.5%) and several assemblywise relative power values in excess of the design tolerance, but all measured hot channel factor values were within the Technical Specifications limits. Flux Maps 3 and 7 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 27 e distributions at various operating conditions.

These maps also provide incore/excore calibration data for the nuclear instrumentation system. 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 6.8% of the predicted values, and that the quadrant power tilt ratio decreased significantly during power ascension.

In conclusion, all 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 7. 28

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

TABLE 6.1 SURRY UNIT 1 -CYCLE 7 BOL PHYSICS TESTS INCORE FLUX MAP

SUMMARY

1 2 BURN F-Q(T) HOT F-DH(N) HOT CORE F(Z) 4 UP BANK CHANNEL FACTOR CHNL. FACTOR MAX 3 QPTR AXIAL MAP MAP DATE MWD/ PWR D F(XY) Off DESCRIPTION NO. MTU (%) STEPS AXIAL AXIAL SET ARO PWR HFP, ASSY PIN POINT F-Q(T) ASSY PIN F-DH(N) POINT F(Z) MAX LOC (%) -----------------------( 5) 2 5-31-83 0 2 221 ROB Ml 14 2.939 ROB Ml 1.712 12 1. 712 1. 794 1.025 SW 40.33 DIST. VER. 3 6-17-83 6 51 180 ROB Ml 34 2.150 Nll ML 1.540 24 1.260 1.578 1.010 SW -0.07 EQ. XENON (6) 7 7-6-83 435 100 226 ROB Ml 43 1.827 G06 IH 1.479 34 1.155 1.421 1.006 SW -0.26 NOTES: HOT SPOT LOCATIONS ARE SPECIFIED BY GIVING ASSEMBLY LOCATIONS (E.G. H-8 IS THE CENTER-OF-CORE ASSEMBLY), FOLLOWED BY THE PIN LOCA Tl ON ( DENOTED BY THE "Y" COORDINATE WI TH THE SEVENTEEN ROWS OF FUEL RODS LETTERED A THROUGH RAND THE "X" COORDINATE DESIGNATED IN A SIMILAR MANNER), IN THE 11 2 11 DIRECTION THE 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, MAP 1 WAS DESIGNATED AS THE PRE-CRITICAL GAMMA BACKGROUND MEASUREMENT.

6. MAPS 4,5 AND 6 WERE QUARTER CORE MAPS USED FOR CALIBRATION OF THE EXCORE DETECTORS.

't

NO. OF THIM BLES --38 e 45 48 e e e e Table 6.2 SURRY UNIT 1 -CYCLE 7 BOL PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR TECHNICAL SPECIFICATIONS LIMITS * + F-Q(T) HOT F-DH(N) HOT CHANNEL FACTOR* CHANNEL FACTOR+ MAP NO. MEAS LIMIT MARGIN MEAS LIMIT MARGIN (%) (%) 3 2.15 4.27 49.6 1.54 1. 70 9.4 7 1.83 2.18 16.1 1.48 1.55 4.5 The Technical Specifications 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 Specifications limit listed above is evaluated at 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 Specifications limit for each map. All measured F-Q(T) hot channel factors include s,~ total uncertainty.

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

30

... * ' e e Figure 6.1 SURRY UNIT 1 CYCLE 7 BOL PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION HZP, ARO " " L It .,

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l,lJ , 1,QS

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l,Ot

1,lZ , o.,s , O,ll , U * -1,7

0 J.I, "4,l, *6,0 * *6,t, *6,0 , ~.7 ,-10.7 , -7.6 o *******:*i:is*

0*0:;s 000 i:z;*:*i:oi*:

0 i:i;0:*o:,s*:*o:;;*:*******

1.1 ** o.u

1.11 . a.,s

1.10

o.u

o.n

1* , 0 J.a. *J.t. *5,l. *S,S , -..., , ~.7. ~.7, 0***********000000********************************

ooa*************

Sf1.lijJADO G&VUIICH aJ,OH MAf NO: Sl-7* 2 CONTROL ROD POSITIONS:

D BANK AT 221 STEPS

1.az 1.01. o.ez.

1.11. 1.az. a.11. * ...... ---.z ..... 7 , 00000000000000000*****

SUMMARY

DATE: 5/31/113 F-QI T) "'2,939 F*OH(N I "' 1. 712 F(ZI

1. 712 F(XY) 1. 794 BURNUf 0 MWD/MTU 31

4V[IIAG( , ,l'CT Dl,,[llfHCE.

POWER: 2S QPTR:

S,ll NW 1.001 I NE 0.9116 ----------,----------

SW 1.025 I SE *0.91111 A.O"' 40.JJIS) H i I e e Figure 6.2 SURRY UNIT 1 CYCLE 7 BOL PHYSICS TESTS ASSEMBL YWISE POWER DISTRIBUTION 51% POWER , N II . L K J " ' , I D C:

PREDICTED

o.aa. 1.01. a.ea.

IIHSUIED * .PCT DIFFEIIEICI.

1.78

l.DD

D.71 * -z.,. -z., -z.1. PREDICTED IIUSURED * ,PCT DlfFEREHCI,

1.36 , 1.H

1.zo

1.9'

1.zo

1.66

o.>> .

1.35

a.,J

1,16

1,91

1,16

0.6 ** D.35 * * -J., * -1., * -l.5 * -J.5 * -l.J * -J.I * -J.Z * ... .. ............

..... .. . . . ... . .. . .. ....... .. . . ........ ........ . 1.36

1.11 1.111

1,16

l.1J

1.111

1.18 , 1,11 D,3' *

1.15

1.17

1.1,

1,12

1.09

1.11

1.lJ

1.07

D,35 * * -1.a. -J.,. -J.,. -1.5 .... z. -1.,. -1.,. -s.7. -1., *

1.36

o.n

1,11

1.05 1.z5

1.10

1.25

1.05

1.11

1.n

o.s. *

O.l5

O.H

l,lD

1.01

1,ZO

1.0.

l.ZD

1,01

l,zt

0,68

0.35 ,

0 1.a. -z.s. -J.1. -J.7. -s.a, -J.J. °"'*' .... , . -1.,. *J.J. -1.1 * *.............*.........................................**................. .*............* , 0.11. 1.11. 1.11. 1.oz. 1.11 o.9'. 1.1a, o.9'. 1.11. 1.oz. 1.11. 1.11. 0.11.

0,36

1,09

l,Jl

1,99

1,ll

0.90

1,16

0.91

1,16

l,DO

1,ZII

1,11

1,3& , * -1.1 , -1.11 * -z.J * -s.o * -1., * -1.11 * -1.1 * -o., * -1., * -1., .... 1 , -1.11

J.1

o.,,. 1.111. 1.05 1.1, 1.111 1.21 a.a, 1.z1 1.1a 1.1, 1.05 1.111 o.,,.

0.,1, 1.zo. 1.0,. 1.1,. 1.1,. 1.1,. o.91. 1.25. 1.1,. 1.15. 1.01. 1.1,. a.,,. l,a. 1,8. -0,5. -1.l, -J.J. -1.]. Z,1. :s.,. o.,. -o.t. -Z.l. o.,. ,.1. A , o.a1

1.zi

1.1,

1.zs

o.n

1.zo

1.10

1.10

1.10

1.zo

o.n

1,z5

1.1,

1.n , 0.111

1 I J

5 '

o.811

1.z,

1.zz

1.u

a.ti . 1.111

1.12

1.15

1.11

1.zs

o.9' , 1.zs

1.zi

1.211

D.115

7 ,.s. ,.1. s.,. 1.1. -1.,. -z.o. z.:s. ,., * ,.z. ,.a. 1.z. -0.1. ,.1. s.,. ,.o .

1.a. '*". 1.1,. 1.0,. 1.1a. 0.119. 1.oa. 1.21. 1.oa. 0.11,. 1.1a. 1.0,. 1.1,. o.96. 1.0,. , 1.1,

1.os

1.zo

1.15

1.zz

o.9Z

1.oa

1.10

1.n

o.,z

1.zo

1.12 , 1.zo , 1.as

1.11 * * ,.,

1.1. 1.,. 1.1. s.,. s.,. a.,. ,., . 5,o. :s.7. 1.a. 1.5. s.z. ,.1. *** *

0.111 1.n

1,16

1.zs

o.n

1.zo 1.10

1.10

1.10

1.zo

o.n

1.zs

1.16

1.z1 , 0.111 *

o.811

1.z11 , 1.21

1.:so

a.,, . 1.ZJ

1.10

1.1,

1.16

1.n

1.n

1.zs

1.n

1.zt

1.86

t ,.1. s.,. ,.1. ,.a. 1.,. 1.1. D.5. ,.a. 5,J. 1.1. 1.1. a.a. ,.1. ***. ,.s .

o.66

1.1a

1.05

1.16

1.111 1.21

o.H

1.21

1.111

1.H

1.os

1.111

a ....

o.n

1.zo

1.01

1.111

1.1t

1.21

o.9o

1.zz

1.111

1.1,

1.01

1.1t

0.10 *

1.0. 1.,. 1.1. 1.1. 1.5, 0.1. o.,. 1.z. 0.1. -1.a. -s.,. 1.1. ,.o *

o.n

1.11

1.11

1.oz

1.11 D,9'

1.111

o.M

1.11 1.oz , 1.:s, 1.11 0.11 * , 0,17

1.12

1,lJ

1.00

1.16

1,92

1,16

D,91

1.1,

1,00 , 1,H

1,10 , 0.38

1.,. o.,. -o.,. -1.1. -1.J. -1.,. -1.0. -z.a. -:s.o. -1.1. -1.,. -1.1. 1.,. , o.36

1.n

1.11

1.os

1.zs

1.10

1.z5

1.05 1.11 o. n . o.J6 *

1.16. 1.10, 1.:sz, 1.01. 1.zz. 1.01. 1.z1. 1.01. 1.za. 0.,1, o.:s5 * * -1.1 * -1.1 * -1., * -1.1 * -z.s * -z. 1 * -:s., * -1., .... 1 * -1., * -z.J *

1,36

1,11

1,111 1,16 , 1,1J

1,111

1,111 1,11 D,36 ,

1,36

1,11

1,16

1,lJ

1,10

1,lZ

1,lZ , 1,05

0.3' * * -0.1 * -1.J * -1., * -z.a * -1.0 * -1.s * -5.1 * -,., * ""'*' * .........................

- - - - 6*********

..*. * *D.J6

1,66 l,ZD

0.9' l,ZO

1,6'

1,36 *

1.36

1.65

1.16

1.,z

1.11 * , * .,

o.:s. * * -1,J. *D,I. *J,Z. -z.,, -z.z. -J.6. -5.J * **.**.......**.*

STAMIARD DlVUTlllN

l.HJ 0.10

1.oJ

a.ea * , 0.10. 1.01, 0.711. * -0.1 * -1., * -1.1 * , AVERAGE *...............

..... .

SUMMARY

14AP NO: S1-7-3 DATE: 6/17/113 CONTROL RDD POSITIONS:

r-Q(T) = 2,150 D BANK AT 111D STEPS r-DH(N) 1.511D rcz1 " 1.260 rcxv1 . 1.5711 BURNUP .. 6 MWD/MTU 32 .PCT DIPFEREHCI!,

J,O POWER: 511 QPTR: NW D,9911 I NE 0.9911 ----------*-----------

SW 1,010 I SE 0.9911 A.O " -0.067(1) 1D 11 11 u 1, u

.,. ',' R * ' e e Figure 6.3 SURRY UNIT 1 -CYCLE 7 BOL PHYSICS TESTS ASSEMBL YWISE POWER DISTRIBUTION p " ****PRtoicrto**: , MEASURED , ,PCT DIFFERENCE, H HFP, EQUILIBRIUM XENON L K J H G F E **********************

0.80

1.02

o.eo. , 0.76

0.98

0.78 * , -3.9 , -3.9 * -2.4 , :*o:ii*:*o:ii*:*i:;i*:*o:ii*:*i:,i*:*o:ii*:*o:ii*:

0.35

0.64

1,14 , 0.95

1.16

0.66. 0.37 * . -6.5 . -2.4 , -3.4 * -3. 7 * -2.3 * -o.o . -0.9

D C 8 . . PRtoicrto'.:

MEASURED , , PCT 01 fFERENCE, :*o:ii': *,:or: *i: i4': * ;: i4': *;:ii':* ;: ;4*: * ;: ;4*:

i:oi': *o:i,*: A 2 , 0. 34

1. 00

1. 08

1. 11

1

09 , 1. 11

1. 13

1. 06

0. 36 . 3 , -6.6 . -7.3 , -4.7 . -2.7 * *3,9 * -2~4 * -0.7 , -1.3 * -2.1 * ..............................................

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

0.37

0,71

1.29

1.04

1.23 , 1.09

1.23

1.04

1.29

0.71

0.37 ,

0.35. 0.67. 1.20, 1.00. 1.20. 1.06. 1.20. 1.03

1.27 , 0.69. 0.36

4 , -4.3 , -5.3 * -7.1 * -3.6 * -2.2 , -2.8 * -2.7 * -1.3 , -1.8 * -2.6 , -1.7 , ............................................................................................

0.37 , 1.07

1,29 , 1.02

1.19 . 0.96 , 1.19

0.96 , 1.19 , 1.02 , 1.29

1.07

0.37 . , 0.36

1.04 . 1.25 . 0.99 . 1.17 . 0.96 . 1.18 . 0.96 . 1.20 , 1.01 . 1.23

1.06

0.38

5 * -2.8. -2.8. -3.1 * -2.3 * -2'.3. -o.o. -0.4. -0.1

0.3. -0.4. -4.2, -1.4. 2.1 , :*o:ii*:*;:i4*:*i:o,*:*i:ii*:*i:i;*:*i:i,*:*o:ii*:*i:i,*:*i:ii*:*;:;i*:*;:04*:*;:;4*:*o:ii*:

0. 66 . 1. 14

1. 03

1

17 , 1. 25

1 . 25

0. 94

1. 28 , 1. 29

1

18

1

02 . 1. 1 3

0. 6 7

6 0.0 . o.o . -0.7 . -1.1 , -0.9 , 0.9 . 1.9 . 3.2 . 2.3 * -0.2 . -1.8 . -0.3 . 1.9 * :*o:io*:*;:ii*:*;:i4*:*i:ii*:*o:ii*:*i:ii*:*i:ii*:*i:ii*:*;:;i*:*;:ii*:*o:ii*:*i:ii*:*;:;,*:

i*

*o

io*: , 0,83

1.23 , 1.17

1.25

0.94

1.22

1.15 , 1.17 , 1.18

1.27 . 0.97 . 1.23 . 1.16 . 1.22

0.82

7 3.5. 3.2. 2.9. 1.9, -1.1. -1.1. 1.7. 3.7. 4.8, 3.5. 1.4. 0.11. 2.0. 2.1. 2.5. :

i: oi * :

i: oi *:

i: ii*:

i: oi *:

i: ii*:

o: ii*: *;:;; *: *;: i4 * : *;: ; ; * :

o: ii*:*;:; a*:*;: oi * :

i:; i *: *;: o; *: *;: oi *:

1.07. 1.011, 1.17. 1.12. 1.21. 0.95. 1.12, 1.30. 1.16. 0.95, 1.21. 1.11. 1.17. 1.04. 1.06. 8 3.5

3.3 , 3.2

3.0

2. 7

2. 7 , 0.3

5.0

4.2 , 3.3 . 2.3

1.6

2.8 , 3.2

2.6 * ..................................

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

.. ********

0.80 , 1.19

1.111 . 1.23

0.95 . 1.23

1.13

1.13

1.13

1.23 . 0.95 . 1.23

1.14

1.19 . 0.80 , , 0.83 . 1.22

1.16 , 1.25

0.98

1.25

1.13

1.16

1.18 , 1.26

0.96 . 1.211 , 1.17

1.23 . 0.62

9 3.5 , 2.5 . 2.0 , 2.3 , 2. 7

1.8 , 0.3

2.8 . 4.1 . 3.9 . 2.6 . 1.11 . 2. 7 , 3.1 , 2.4 * *******:*o:ii*:*;:;,*:*;:o,*:*;:;i*:*;:i,*:*;:i4*:*o:ii*:*;:i,*:*;:ii*:*;:

ii' :*;:o,*:*;:;4*:*o:ii*:*******

0.67 . 1.14 , 1.05 , 1.20 . 1.27 . 1.24 . 0.93 . 1.25 , 1.26 , 1.19 , 1.04 , 1.16 . 0.68 , 10 0.7. 0.7. 1.0. 1.1. 0.8. 0.1. 0.3. 1.3. 1.3. 0.11. 0.3. 2.0. 3.5 . .........................................................................

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

0.37

1.07

1.29 . 1.02 . 1.19 . 0.96 . 1.19

0.96 . 1.19 , 1.02 . 1.29 . 1.07 , 0.37 . . 0.37

1.07 , 1.28 , 1.01 . 1.19 . 0.95 , I. 16

0.911 . 1.17 . 1.01 . 1.27 . 1.07 . 0.36 . 11 . -0.4 , -0.4. -0.11. -0.11 . -0.7. -1.11, -2.0, -2.3. -2.0. -0.6. -1.3 * -0.11. 1.9. *******:*o:i,*:*o:i;*:*;:ii*:*;:04*:*;:ii*:*;:bi*:*;:ii*:*;:o,*:*;:ii*:*o:i;*:*o:ii':*******

0.36. 0.70. 1.28 . 1.02. 1.20 . 1.07 , 1.20, 1.02 , 1.26 . 0.66

0.36 . 12 , *1.5 * *1,1 . *0.11 * *1.5 . -2.2 . *2,4 , *2, I * *1,11 . *2,0 . *3.5 . *1.3 . * * * * * * * :

o: ii':* i: o, * :

i:; 4 *: *;: i, *: *;: ; i * : *;:;, * : *;: i, * : *;: oi * :

o: ii*:** * * * * *

0.37. 1.08. 1.12. 1.11

1.10. 1.12. 1.12. 1.05. 0.36. 13 . -0.7

0.1 , -1.0 * -2.11 * -2.6 . -2.0 . -1.11 . -2.5 . -2.9 * . . . ' ... : . o: ii. : . o: ii. : . i : ii. : . o: ii. : . i : i e. : . o: ii. : . o: ii. : ...... .

0.37

0.66 . 1.17

0.97

1.16 , 0.65

0.37 , 14 0.1

0.3 * -0.8 , -1.7 , -2.1 , -1.7 , -1.3 . ****;ii~oi~o****

DEVIATION

=1.446 HAP NO: 51*7* 7 CONTROL ROO POSITIONS:

D BANK AT 226 STEPS

0.80

1.02 . 0.80 * , 0.80

1.02 . o. 76 , 0.11 , -0.6 , -2.2 *

SUMMARY

DATE: 7/ 6/83 F*Q( T) 1.827 F*OH(N) 1.479 f(Z) 1. 155 F(XV) 1.421 BURNUP = 435 MWD/HTU 33 , AVERAGE .

PCT DIFFERENCE.

= 2.1 POWER: 1001 QPTR: NW 0.990 NE 1,002 SW 1.006 SE 1.002 A.O = *0.26(1) 15 e e SECTION 7 REFERENCES 1

C. B Laroe, "Surry Unit 1, Cycle 7, Design Report," NFE Technical Report No. 294, Vepco, April, 1983. 2. Surry Power Station Technical Specifications, Section 3.1.E, 3.12.C .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. 34

,* ' e e APPENDIX STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEETS 35 e e --e SURRY POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Reference Test

Description:

Reactivity Computer Checkout / Pree No /Section:

1-PT-28.11/APP.B Sequence Step No: I:, II Bank Positions (Steps) RCS Temperature

(°F): 547 Power Level(% F.P.): 0 Other (specify):

Test Conditions SDA: 228 SDB: 228 CA: 228 (Design) CB: 228 CC:. 228 CD:* Below Nuclear Heating *At the just crit. position III Bank Positions (Steps) RCS Temperature (0:F): r'l-7. l Power Level(% F.P.): O Other (Specify):

Test Conditions SDA: 228 SDB: 228 CA: 228 (Actual) CB: 228 CC: 228 CD: '2.01 Below Nucle~ Heating_*

c-:-. *:-IV

Test Results V

Date/Time Test Perfoxmed:

~-..

s-/30/83 . :: a*s(')S'" . * .. :-.: .. --:* Measured Parameter

(Desc.ription)

Pc= Meas. Reactivty

~sing -p-computer pt= Inferred React from react period Measured Value Design Value (Actual Conditions)

Design Value p = C p = t :I>= + Jf2,..0 + Z7.0 -3'1. O + 112. lo zto., -3'1.r" -,. t.5' -1.3 (Design Conditions) = [(pc-pt)/pt]

x 100% S 4.oi Reference WCAP 7905, Rev. 1, Table 3.6 FSAR/Tech Spec Not Applicable Acceptancei--------------------+-----------------------------------

Criteria VI Commen'ts Reference Not Ap~lica~le Design Tolerance is met Acceptance Cri'teria is met : .,/YES _NO : LYES _NO Allowable Range = +/- 3 9 p ctn Evaluated By: Recommended for Approval By : A.l c . ..f.~ NFO Engineer lrlAY 'I 1983

'. .* ) . e e e* e SURRY POWER STATION UNIT 1 CYCLE 7 . STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Reference II Test Conditions (Design) III Test Conditions (Actua.l)

-IV . Test Results V Acceptance Criteria VI Comments Completed Test

Description:

Critical Boron Concentration

-ARO 7 Pree .No /Section:

1-PT-28.11/APP.C Sequence Step No: Bank Positions (Steps) RCS Temperature

(°F): 547 Power Level(% F.P.): 0 SDA: 228 SDB: 228 CA: 228 Other (specify):

CB: 228 CC: 228 CD: 228 Below Nuclear Heating Bank Positions (Steps) RCS Temperature

(°F): 5'1{,.o Power Level(% F.P.): 0 SDA: 228 SDB: 228 CA: 228 Other (Specify):

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

... 5/30/83 13 0~ Meas Parameter (Description)

M (CB)ARO; Critical Boron Cone -ARO Measured Value M (CB)ARO = } 30*1 ppm Design Value 13 3 5 + so p fl,.,,, (Actual Cond) CB= -Design Value** . (Design Cond) CB =1335 +/- 50 ppm Reference VEP-PSE-NFE-294 . FSAR/Tech Spec ac x CBS 15,115 pcm p Reference UFSAR Section 14.2.5 Design Tolerance is met : ~YES _NO Acceptance Criteria is met :* ..c:..YES

__NO ac = -8.44 pcm/ppm for preliminary analysis B o<c,s = -fj. 'l'I Pc M / ff' ,.,.. /lo,. .f il'lt1 I qno.lysis By: ~\,[p~~ (/~tingeer Evaluated By: Recommended for Approval By * ( .,). P)U_ c>Y.~ NFO Engineer A.2 MAY 'l 1983 e e SURRY POWER STATION UNIT *1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Reference II Test Conditions (Design) III Test Conditions (Actual) *"* --... . -.. *-.. -* .. -IV . Test Results .. V Acceptance Criteria VI Comments Completed Test

Description:

Isothermal Temperature Coefficient

-AR~ Proc No /Section:

l-PT-28.11/APP.D Sequence Step No: Bank Positions (Steps) RCS Temperature (OF): 547 Power Level (% F .P.): 0 SDA: 228 SDB: 228 CA: 228 Other (specify):

CB: 228 CC: 228 CD: 228 Below Nuclear Heating Bank Positions (Steps)

RCS Temperature (OF): S" -¥-st. 'I Power Level Cl F.P.): 0 SDA: 228 SDB: 228 CA: 228 Other (Specify):

CB: 228 CC: 228 CD: 2.19 Below Nuclear Heating ' . Date/Time Test Performed:

-. :.* *: ;::::-* --: :* --!'--* .. *---s-/10/13 1333 .. . : -:--. -* . .. Meas Parameter

--***--* *-(Description)

ISO -(a; T ) ARO Isothermal Temp-Coeff

-ARO Measured Value (a;IiO) ARO = -S: BS-pcm/DF (CB =/30/ ppm) -Design Value (Actual Cond) (a;IiO) ARO = -6. /0t3pcm/aF (CB = /30/ ppm) ISO (a; T )ARO= -5.68 +/- 3.0 pcm/DF Design Value --------------*-------------*-------(Design Cond) (CB= 1335 ppm) Reference VEP-PSE-NFE-294 a;IiO S O .41

pcm/°F Dop pcm/°F FSAR/Tech Spec a; T = -2.09 Reference TS 3.1, VEP-FRD-NFE-294 Design Tolerance is met : v'n:s _NO Acceptance Criteria is met : .J::::::YES

__NO

Uncertainty on~ = 0.5 pcm/°F (

Reference:

memorandum MOD from C. T. Snow to E. .J. Lozito dated June 27, 1980). Evaluated By: {: Recommended for .J. 0 Appro.vd By : _C._. __

NFO Engineer A.3 MAY 7 1983

'. . ,, e e i e SURRY POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Cntl Bank D Worth neas.,Rod Swap Ref. Bank Reference Proc No /Section:

l-PT-28.11/APP.E Sequence Step No: II Bank Positions (St.eps) RCS Temperature (OF): 547 Test Power Level (% F. p.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): (Design) CB: 228 CC: 228 CD:Moving Below Nuclear Heating III Bank Positions (Steps) RCS Temperature

(°F): Sl/'/.J/ Test Power Level (% F .P.): 0 Conditions SDA: 228 SDB: 228 .CA: 228 Other (Specify): (Actual) CB: 228 CC: 228 CD:Moving Below Nuclear Heating ' -* Date/Time Test Performed:

..: *., _._ --* -. .. . . _.*--.... , ... -. . . . .. ,. -*-* -* . s/30/e3* . i,15'. -. .. -.. __ ,.,--. -~~. .. __ :.... *}'; -. .:.*--. ,. __ -Measured Parameter I~ ;Integral Worth o~ Cntl Bank D, (Des!=ription)

All Other Rods Out IV , Test Measured Value IREF _ D -/ 3 J.. 5 PCM Results Design Value I J 13 12 (Actual Conditions) 1 REF _ --;-pc. I'll . D --Design Value 10 (Design Conditions)

I~F = i293 +/- 129 pcm -* ------**--.. Reference FSAR/Tech Spec V Acceptance Criteria Refer enc~ Design Tolerance is VI Acceptance Criteria Comments Completed By:~~~ ,s ng eer VEP-PSE-?'-."n:-294 If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on safety analysis.

SNSOC may specify that additional testing be performed.

VEP-FRD-36A met : *YES __NO is met : _YES __NO Evaiuated By: Recommended for Approval By: A.4 . c.5.~ NFO Engineer

/ e e e e SURRY POWER STATION UNIT *1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Reference II Test Conditions (Design) III Test Conditions (Ac1:ual)

-IV Test Results V Acceptance Criteria VI Comments Test

Description:

Critical Boron Concentration

-D Bank In// Pree No /Section:

l-PT-28.11/APP.C Sequence Step No: Bank Positions (Steps) RCS Temperature

(°F): 547 -* Power Level (% F .P.): 0 SDA: 228 SDB: 228 CA: 228 Other (specify):

CB: 228 CC: 228 CD: 0 Below Nuclear Heating ~ank Positions (Steps) RCS Temperature

(°F):5q1.7 Power Level (% F.P.): 0 SDA: 228 SDB: 228 CA: 228 . Other (Specify):.

CB: 228 CC: 228 CD: 0 Below Nuclear Heating .. Date/Time Test Performed:

... . .. ... .. , . s /50/: 3 :i.2i, .. . Meas Parameter (Description) (CB)g; Critical Boron Cone -*D Bank In Measured Value (CB)~= /J'f'f ppm Design Value i I 5 3 + JS (Actual Cond) CB= -ffm . Design Value_** (Design Cond). CB= 1187 + bC~rev +/-(10 + 129 .3/ I ac I )ppm .

B Reference VEP-PSB.:NfE-294 FSAR/Tech Spec aCh x CBS 15,115 pcm Reference UFSAR Section 14.2.5 . .. Design Tolerance is met : *LYES _NO Acceptance Criteria is met : ..£n:s _NO -ac = -8.44 pcm/ppm for preliminary analysis B ~c:rev = M (CB)ARO 335 c 6 -8, 'I 'f PU" I ff' ,r. fr,r /;"t11,a/

4r11Q(ys:~.

Evaluated By: Recommended for Approval By: A.5 f _). 1)/.;t__ C.-J-~ NFC Engineer MAY 7 1983 e e e e MAY 'I 1983 SURRY POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Reference II Test Conditions (Design) III Test Conditions (Actual) .. -. .J.V Test Results V Acceptance Criteria VI Comments Completed Test

Description:

Cntl Bank C Worth Measurement-Rod Swap I Pree No /Section:

l-PT-28.11/APP.F Sequence Step No: Bank Positions (Steps) RCS Temperature

(°F): 547 Power Level (% F.P.): 0 SDA: 228 SDB: 228 CA: 228 Other (specify):

CB: 228 CC:Moving CD:Moving Below Nuclear Heating Bank Positions (Steps) RCS Temperature (OF): S'lt/, 3 Power Level (% F .P.): 0 SDA: 228 SDB: 228 CA: 228 Other (Specify):

CB: 228 CC:Moving CD:Moving Below Nuclear Heating . Date/Time Test Perfo:rmed:

_ --.-. .. *' .. S/30/5~ *'J.:J.ff

. -. Meas Parameter

.. . -* * (Description)

I~S;Int Worth of Cntl Bank C-Rod ~wap . (Adj. Meas . Crit. Ref Bank Measured Value IRS_ (;;JO C -pcrn Position =.JO 'f steps) Design Value (Adj. Meas. Crit. Ref Bank (Actual Cond) I~s= C, 7). :!: IOI fc.m Position = /o', steps) Design Value .. IRS_ 657 +/- 100 pcm (Critical Ref Bank C -(Design Cond) . ----*-** Position=

132 steps) ,. Reference VEP-PSE-NFE-294, VEP-FRD-36A, NFO-TI-2.2!

If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on FSAR/Tech Spec safety analysis.

SNSOC may specify that additional testing be perform~d.

Reference VEP-:FRD-36A Design Tolerance is met : £n:s _NO Acceptance Criteria is met By~.C'.wJN,)

..r( t lf.ngt)eer

LYr:S __NO Evaluated By: Recommended for Approval By: A.6 t .1.* 1M c.:J. L,J NrO Engineer

-:'.. ,-~-e e -e SURRY POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Reference II Test Conditions (Design) III Test Conditions (Actual) ---. _ ........ : . . -~--.... *.: . -***. .. ... --~:. ~: . -IV Test Results .. --** V Acceptance Criteria VI Comments Test

Description:

Cntl Bank B Worth Measurement-Rod Swap/~ Pree No /Section:

1-PT-28.11/APP.F Sequence Step No: Bank Positions (Steps) RCS Temperature

(°F) :* 547 Power Level (% F.P.): 0 SDA: 228 SDB: 228 CA: 228 Other (specify):

CB:Moving CC: 228 CD:Moving Below Nuclear Heating Bank Positions (Steps) RCS Temperature

(°F): Sl/3

t;, Power Level (: F.P.): 0 SDA: 228 SDB: 228 CA: 228 Other (Specify):

CB:Moving CC: 228

CD:Moving Below Nuclear Heating -* *.",:Date/Time_

Test_ Performed:

-::* *. . *---~-..* *-. . .. -'*.-. ..:..~;: _ . ..:,.. '. -.. ... * :. :-:-.* --* sr~/a3 -* :i.~1 c, . -. ... . .. *--**. --* -. '. " ----... .. Meas Parameter* . -* . . . --***::**;.

' .. . . --*,* ... ~r;Int.Worth

~f .. .. (Description)

Cntl Bank ~-Rod Swap (Adj. Meas. Crit. Ref Bank Measured Value IRS_ qq, pc"' P~sition = 170 steps) B -Design Value (Adj. Meas. Crit. Ref Bank (Ac'tual Cond) IRS= 11 b'I .! B ) 7 .5 P'"' Position = / 70 steps) Design Value I;s= 1151 +/- 173 pcm (Critical Ref Bank ----------(Design *cond) -------***--*----

-.. --Posit.ion-;;

199 steps) . , Reference VEP-PSE-NFE-294, VEP-FRD-36A, NFO-TI-2.2A If Design Tolerance is exceeded, SNSOC shall evaluate impac't of tes't result on FSAR/Tech Spec safety analysis.

SNSOC may specify that additional testing be performed.

Reference VEP-:FRD-36A . Design Tolerance is met : LYES _NO Acceptance Criteria is met : LYES _NO Evaluated By: Recommended for Approval By: . A. 7 {J.1.LA_ c~.)-~ NFO Engineer . MAY 7 1333 e e e SURRY POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Cntl Bank A Worth Measurement-Rod Swap i Reference Pree No /Section:

1-PT-28.11/APP.F Sequence Step No: II Bank Positions (Steps) RCS Temperature (OF): 547 Test Power Level (% F .P.): 0 Conditions SDA: 228 SDB: 228 CA:Moving Other (specify): (Design) CB: 228 CC: 228 CD:Moving Below Nuclear Heating III Banlt Positions (Steps) RCS Temperature

(°F): 5 '13. 7 Test Power Level (% F .P.): 0 Conditions SDA: 228 SDB: 228 CA:Moving Other (Specify): (Actual) CB: 228 CC: 228 CD:Moving Below Nuclear Heating Date/Time Test Performed:

.. . . " . . . *-*. . . -. .. 002 I 05 /31 / 83 . Meas Parameter

-.. . (Description) 1!5;Int Worth of Cntl Bank A -Rod Swap . . IV (Adj. Meas. Crit. Ref Bank Test Measured Value r!S= tit-5 Position = .8 8 steps) -Results Design Value (Adj. Meas. Crit. Ref Bank (Actual Cond) r!5= 1.f C,2.,:! JOO Position = B steps) ---* ---------Design Value .. . IRS= 489 +/- 100 pcm (Critical Ref Bank A (Design Cond) -----Position=

109 steps) *-. .,. Reference VEP-PSE-NFE-294, 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 ./ . _YES _NO VI Acceptance Criteria is met : v""YES _NO Comments Complmd BytfiY~ t~ ng* r Evaluated By: Recommended for Approval By : ?J¢~*t.. / 2 c. .:J 4curw NFO Engineer A.8 MAY 7 1983 . __ :.~* ..

e e* --e .. -' .. 1 .. SURRY POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Reference II Test Conditions (Design) III Test Conditions (Actual) .. -. --IV Test Results Test

Description:

Shutdown Bank B Worth Meas. -Rod Swap // Proc No /Section:

l-PT-28.11/APP.F Sequence Step No: /b Bank Positions (Steps) SDA: 228 SDB:Moving CA: 228 CB: 228 CC: 228 CD:Moving Bank Positions (Steps) SDA: 228 SDB:Mcving CA: 228 CB: 228 CC: 228 CD:Moving Date/Time Test Performed:

_ .. .--:--.5 j3 i 1a*'3 02.*, s**_-,-* *c

RCS Temperature

(°F):* 547 Power Level(% F.P.): 0 Other (specify):

Below Nuclear Heating RCS Temperature

(°F): 5 LtLt. 8 Power Level (% F. P * ) : 0

Other (Specify):

Below Nuclear Heating Meas Parameter (Description)

RS .. -ISB;Int Werth cf Shutdown Bank B-Rod s~ap Measured Value Design Value (Actual Ccnd) Design Value (Design Cond) Reference (Adj. Meas. Crit. Ref Bank Position = /"II steps) (Adj". Meas. Crit. Ref Banlt IRS= 827: \2..'"t Position=

II.fl steps) SB IRS= 825 +/- 124 pcm (Critical Ref Bank SB -----------------Posi'tion

= 156-**st-epS)

__ _ ,. VEP-PSE-NFE-294, 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 VI Comments Completed Reference VEP-FRD-36A . Design Tolerance is met : /YES _NO Acceptance Criteria is met : ~S ~NO Evalua"ted By: Recommended for Approval By : A.9 ~22~r::: C . .:J. NFO Engineer MAY 7 1383 . :..:.. --; -~-. -.... * .. :. .. --------------*

e e e r-* ** *~ SURRY POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Shutdown Bank A worth Meas. -Rod Swap/ Reference Proc No /Section:

1-PT-28.11/APP.F Sequence Step No: 7 II Bank Positions (Steps) RCS Temperature (OF): 547 Test Power Level (i F .P.): 0 Conditions SDA:Moying SDB: 228 CA: 228 Other (specify): (Design) CB: 228 CC: 228 CD:Moving Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (OF): 5"f5 .'+ Test Power Level (% F .P.): 0 Conditions SDA:Moving SDB: 228 CA: 228 Other (Specify): (Actual) CB: 228 CC: 228

CD:Moving Below Nuclear Heating -* .. . Date/Time Test Performed:

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

.. --*** ' 5 /3 i /95 --._**:...:* 052.'5 -. -**r . ** ..

Meas Parameter

.. .. .. .. .. . .. . . -RS * ----*--(Description)

ISA;Int Worth of Shutdown B~ A-.Rod Swap *IV (Adj. Meas. Crit. Ref Bank Test Measured Value IRS= SA /07e. Position =-/82 steps) Results Design Value (Adj. Meas. Crit. Ref Bank (Actual Cond) IRS= // / 3 +/- I~ 7 SA Position = 18 2.. steps) -----------

.. IRS= Design Value SA 1102 +/- 165 pcm (Critical Ref Bank (Design Cond) **----------

Position=

193 steps) Reference VEP-PSE-NFE-294, 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 : ./YES _NO VI Acceptance Criteria is met : ..LYES _NO Comments Completed Byof.~~ .' es .Eng r Evaluated By: Recommended for Approval By A.10 ~7?43/ c . .J.~ ~TO Engineer f/iAY 7 1983

-:.; .-~. ** :;: e -.. SURRY POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Total Rod Worth -Rod Swap Reference Pree No /Section:

l-PT-28.11/APP.F Sequence Step No: II Bank Positions (Steps) RCS Temperature

(°F):

547 Test

Power Level (% F .P.): 0 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 (OF): 5i+'lt.3 Test Power Level (% F.P.): 0 Conditions SDA:Moving SDB:Moving CA:Moving Other (Specify): (Actual) CB:Moving CC:Moving CD:Moving Below Nuclear He*ating r*. . .. .. ,* :."Date/Time .Test Performed:

-;:\:~*:*~::/.~-~~~?.:

.. * *. *: ;~3::~~ .* ... ..* . . . -* .... .. --. .-:.,:** ~, . --*.*:: .::.*** \~ .~ '* .* ..... ,.-.. . .. , ~: :,_. . . . .. -:; .. . *: .. \*,5 /30--J s '5 * :i.z)l'i:j?\:

. . :.: . -~--:.r;.-: I':*::* . . . . . *:~:, :_, -. -; *:** . -* .. ':: _, :~)-*-:-~;::~.<--

'-. h. Meas Parameter

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

-** -... ---~ :*.:* _*, .. . (Des cripticn) 1 T~tal;]nt Worth cf All Banks Red Swap -*., .. . .:*:* .. . IV Test Measured Value !rotal = 52~5 Results Design Value 55b (Actual Cond) ITotal = S5<o I :t Design Value ITotal *= 5517 +/- 552 pcm (Design Cond) -----------------

.. ----*--. ----------------*-------* **-** -------------

Reference VEP-PSE-NFE-294, VEP-FRD-36A, NFO-TI-2.2!

If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result en V FSAR/Tech Spec safety analysis.

SNSOC may specify that Acceptance additional testing be performed.

Criteria Reference VEP-FRD-36!

.. Toleranc;e is /. _NO Design met :.~S VI Acceptance Criteria is met : _YES _NO Comments MAY 7 1983 ----*-. .* ::;_* .. :-' -* .*:::,-. -~ ... --... **-* --*:-... *-****--.~-

Completed Bytfi~Cw~

e t/Eng eer Evaluated By: P~C?~V: Recommended for Approval*

By A.11 NFO Engineer e e --* *

SURRY POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Reference II Test Conditions (Design) III Test Conditions (Actual) -IV . Test Results V Acceptance Criteria VI Comments Test

Description:

HZP Boron Worth Coefficent Measurement Pree No /Section:

l-PT-28.11/APP.E Sequence Step No: Bank Positions (Steps) RCS Temperature (0.F): 547 Power Level(% F.P.): 0 SDA: 228 SDB: 228 CA: 228 Other (specify):

CB: 228 CC: 228 CD:Moving Below Nuclear Heating Banlt Positions (Steps) RCS Temperature (0.F): 5 'f C,.O Power Level (% F .P.): 0 SDA: 228 SDB: 228 CA: 228 Other (Specify):

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

S/30/53 /303 .. Measured Parameter (Description) ac , Boron Worth Coefficient B Measured Value -P~;n/ff~

ac = -9.J./f B Design Value -B . '1 'f e, ,n /t I' If') (Actual Conditions) ac = B Design Value (Design Conditions) a:c = -8.44 +/- 0.84 pcm/ppm B ... Reference VEP-PSE-hTE-294

,. FSAR/Tecb Spec a:C x CBS 15,115 pcm

B Reference*

UFSAR Section 14.2.5 Design Tolerance is met : Ln:s _No Acceptance Criteria is met : ..c.....YES

_NO Evaluated By: Recommended for Approval By: c . .J.~ NFO Engineer A.12 MAY 7 1983 e -e *¥ I ... SURRY POWER STATION UNIT 1 CYCLE 7 STARTUP .PHYSICS TEST RESULTS AND EVALUATION SHEET I Test Description

M/D Flux Map -HZP, ARO i Reference Pree No I Section: 1-PT-28.2, OP-57 Sequence Step No: II Bank Positions (St.eps) RCS Temperature

(°F) :TREF +/-1 Test Power Level (% F .P.): -0 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):

Test Power Level (% F .P.): Conditions SDA: 228* SDB: 228 CA: 228 Other (Specify): (Actual) CB . 228 cc . 2~8 *CD: . . ::*-. 3e.* 'o\ .*.* _, e..s , . .: . e---: .... Date/Time

Test:.'

,.,,;:~~:\~:s:~:::

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

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

-:, ~-.. ----. --*-**-:* ... Performed:

S-pl /83 _-*.: *o90B * . : .. *: . :..*~**:..:-~

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

.. . . * .. . -MAX. *REL NOC ENTHAL TOTAL HEAT QUADRANT IV Meas Parameter ASSY PWR RISE HOT nux HOT POWER TILT -(D_es cription)

% DIIT CHAN FACT CHAN FACT RATIO (M-P)/P F-dH(N) F-Q(T) QPTR a",6~ 1 .. IJ., or/...2' /. 712 2. q39 I. 02'1 Measured Value IL st .r.,. I!.-,, =03 Test Results Design Value as* tw ,, a e., rlf .,.u..ss1:i...2U.P>I JI JA .. ,, CI.I r.ci> * ... >>

sm (Design Conds) ", * ..,.Ills.)

Q -s 1.03 ** .. WCAP-7905 WCAP-7905 Reference REV.l NONE NONE REV.1 ... --. -*-----*-----------------------* --. --*. ---. V FSAR/Tech Spec NONE NA NA NA Accep-cance

,. Criteria Reference NONE TS 3.12 TS 3.12 TS 3.12 Design Tolerance is met : YES /No Acceptance Criteria is met : 2YES _NO VI Comments

As Required **The design value of QPTR is the sum of the 1.01 design prediction tilt and the 1.02 uncer"tainty identifie'!J-:1.

WCAP-7~~~-,d ,/I * ..L. ,/ .:If: T"l. -*::..t-~-*--' ... --~ .. ,:.. -. .. + I. ,.,j ""'---I-*--* ... --I!' e1ee-. ;tie. e,,. S'11 rr jP"1 f 7 PoJoCrStat,o,., deY1af,an

/ri or/ #I,. 8:J-2S'G, MAY 7 1983 -* ,:: *:_~. . *. Completed By: ~M4A:'it1Q,aj t Eng~eer Evaluated By: PY J .c:z::?~ Recommended for Approval By A.13 c . .:!~ l\"FO Engineer e e e .... I .,. SURRY POWER STATION UNIT *1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Reference II Test Conditions

(Design) III Test Conditions (Actual) -IV Test Results V Acceptance Criteria VI Comments Completed Test Description

M/D Flux Map-At Power,NI Calibration Proc No/ Section: l-PT-28.2, OP-57 Sequence Step No: Bank Positions (Steps) RCS Temperature

(°F):TREF

+/-1 Power Level(% F.P.): -50 SDA: 228 SDB: 228 CA: 228 Other (specify)

CB: 228 cc: 228 CD:

lrust have~ 38 thimbles Bank Positions (Steps) RCS Temperature

(°F) : TREF Power Level (% F .P.): S'O. <a 1o SDA: 228 SDB: 228 CA: 228 Other (Specify):

CB: 228 cc: 228 CD: , cao. . 'f ,' ,h:rrtbfes Date/Time Test: Performed: ,j,7/i3 2.2.1 S"' MAX. REL NOC ENTHAL TOTAL HEAT QUADRANT 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 '-' '7, f.,. f,., l./lf ~-8 I. 5' 'f 0 z., ,o* Measured Value 'l.5'"~ f#I' P: O. n I. oo 9 R-'I Design Value :t Ill -P, I l.t (Design Conds) :t u, ** , , c a., NA NA +/- 1.02 "' * ..,. Pw.) W.CAP-7905 I 1. WCAP-7905 Reference

.. REV.l NONE NO?--."E REV.l FSAR/Tecb Specl 1 * ,'I _y11.n1~.lU*Pll rgcz,a.ia/P a a:ui ,-,aa.J NO?--."E ~Cl) S *.>&

SCI) NA f..-p c D.S Reference NONE . Design Tolerance is met Acceptance Criteria is met

As Required TS 3.12 TS 3.12 TS 3.12 : /. :ZYES _NO : YES ___NO Evaluated By: °[!(. #d7~ Recomme~ded for C .::1 Approval By : -.a:..*

NFO Engineer A.14 1'.AY 7 t9SZ e e 4J e .( I I .f SURRY POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test Description

M/D Flux Map-At Power,NI Calibration. Reference Proc No/ Section: l-PT-28.2, OP-57 Sequence Step No: '/ II Test Conditions (Design) III Test Conditions (Actual) -IV Test Results V Acceptance Criteria VI Comments Comple'ted Bank Positions (Steps) RCS Temperature

(°F):TREF

+/-1 Power Level (% F. P.): -60 SDA: 228 SDB: 228 CA: 228 Other (specify):*

CB : 228 cc : 228 CD: ** Bank Positions (Steps) RCS Temperature(°F):

IREF Power Level(% F.P.): 6, I

Jr "It, SDA: 228 SDB: 228 CA: 228 Other (Specify):

CB: 228 cc: 228 CD: f7! -t'A:Mbles ZI Date/Time Test: QlJo.r-4er--

~re. -f \l.)x rr.o.p Performed:

t;/,'1/'{J

/J,Jfo MAX. REL . NUC tNTHAI. TOTAL HEAT QUADRANT Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT (D~scription)

DIFF CHAN FACT CHA.~ FACT RATIO (M-P)/P F-dH(N) F-Q(T) QPTR ru,o FH-P= l.13 1 1 1 M~asured Value It-! N/r... t.J/A. N{I\ '-:L -,. f;,. P .. ~.t1, 11,_q Design Value t 1Gi -P 1 It D.t t 1J1. fer P 1 C 0.t (Design Conds) ", ... .,. ...... , NA NA 1.02 WCAP-7905 IWCAP-7905 Reference REV.l NONE NO~"E REV.l FSAR/Tech Spec NONE r",..si.Ul>+.2U*Pll

~(Z)S2.11/P a &{Z) NA . Reference NONE TS 3.12 TS 3.12 TS 3.12 Design Tolerance is met : ~S __NO Acceptance Criteria is met : _n:S __NO

Must have at least 38 thimbles for a full-core flux map, o at least 16 thimbles for a quarter-core flux map. m"r As Required 1 "1"hese. f'*"-e."ter-s A'"e. ,..0't ../e,.:.f:eA

~,:"~ ._ Po-~-t-...R.-core

,.. .. p o\.+.._:.,e4 t"or !Iii eJ. Evaluated By: ~f, f JL Recommended for f"f 2 Approval By : _C---"~_J_. NFO Engineer A.15 r MAY 7 1SS3 e e * ..(1 J I ~) SURRY POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVA!-UATION SHEET I Reference II Test Conditions (Design) III Test Conditions (Actual) -IV Test Results V Acceptance Criteria VI Comments Completed Test Description

M/D Flux Map-At Power,NI Calibration L/. Pree No/ Section: l-PT-28.2, OP-57 Sequence Step No: Bank Positions (Steps) RCS Temperature

(°F) :TREF +/-1 Power Level (% F.P.): -70 SDA: 228 SDB: 228 CA: 228 Other (specify):*

CB : 228 cc : 228 CD: ** Bank Positions (Steps) RCS Temperature(°F):

7ilEF Power Level (% F. P.) : 72.~ 7 7o SDA: 228 SDB: 228 CA: 228 Other (Specify):

CB : 228 cc : 228 CD: \ qt,, Date/Time Test: 2.3 -f'l,,*,.,1,/

es Performed:

~l,~k'3 . I 2.5""2: Gua.r-+er-Core. tTta..P MAX*. REL NUC ENTHAL TOTAL HEAT QUADRANT Meas Parameter ASSY PWR RISE HOT FLUX }:IOT PO\..'ER TILT (Description)

% DIFF CHAN FACT CHAN FACT RATIO (M-P)/P F-dH(N) F-Q(T) QPTR 7.9i ,..,,_ f'*/,3/ 1. 1 H-1 1 Measured Value "*" ,, /,. f'.c. r, N /A !'J/A t-J/A li-9 Design Value :t JIii ffl P, I D., :I lJl. fw pf C 0., (Design Conds) (PS*.,,_,, ..... ) NA NA S 1.02 .. WCAP-7905 I I WCAP-7905 . Reference REV.l NONE NONE REV. l FSAR/Tech Spec NONE ~1-SS1)4.21J*P)J 1cz,sz.n/P a :i:cz> NA ; -Reference NONE TS 3.12 TS 3.12 TS 3.12

Design Tolerance is met /. : 7 n:s _NO Acceptance Criteria is met : _YES _NO

Must have at least 38 thimbles for a full-core flux map, o at least 16 thimbles for a quarter-core flux map. ** As Required 1 ~ese. f41'D-.~ on,,..+ <1er:F:eJ v,:,,~

f&r+-:.J.c.re. ,i-.p oH .. :..ed -r ... 1'1:L e,..!:bra..f:on.

Evaluated By: Recommended for Approval By : A.16 /~ °r!!. Ila) 5'fi' I c>.1. L NFO Engineer ~.ey 7 1333 r e "4

r ll>J * ** ur.v ll°'llt\l SURRY POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Referenc.e II Test Conditions (Design) III Test Conditions (Actual) . IV Test Results V Acceptance Cri'teria VI Comments Test Description

M/D Flux Map-At Power,NI Calibration .t/. Pree No/ Section: 1-PT-28.2, OP-57 Sequence Step No: Bank Positions (Steps) RCS Temperature

(°F):TREF

+/-1 Power Level (% F.P.): -70 SDA: 228 SDB: 228 CA: 228 Other (specify):*

CB: 228 cc: 228 CD: ** Bank Positions (Steps:) RCS Temperature(°F): -r~£F SDA: 228 SDB: 228 CA: 228 Power Level (% F. P.): Blf. 3 "lll Other (Specify):

CB . 228 cc: 228 CD: 2..00 . Date/Time Test: z, th: I"\\:, le.s Performed:

(;/J'l/'1'3

.2..tJOS

cQiJo.r-tu.:..eore f \u t.. t"'\a..p MAX. REL NUC Eh"THAL TOTAL HEAT QUADRANT 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 h.¥?. .p,,. f .. /.0~ i i i f-.'i! ~/A Measured Value ,., ~r-P..~.rS' t-J / A N (A 11-q Design Value S 1111 fw Pf t O ., au,,_,, co., (Design Conds) ",. MaJ'. hr.) NA NA S 1.02 WCAP-7905 I IWCAP-7905.

Reference REV.l NONE NONE REV.I FSAR/Tech Spec NONE . , r" ,rl.SSIJ*.J(J*P))

~CZ)S:.ll/1

l(Z) I NA Reference NOJ>.."E TS 3.12 TS 3.12 TS 3.12 Design Tolerance is met /, : _YES _NO Acceptance Criteria is met : VYES _NO

Must have at least 38 thimbles for 1 a full-core flux map, o at least 16 thimbles for a quarter-core flux map. r ** As Required 7 .... I'll'.. e.l:br *. +~o 1 "T"~ese. p..ro.A61'c*S a.re l\o t 11er:"f':E!L

"$:"'~ o-fo.ri:;..(.

col'e rtva.r d,4-.._:,,eJ l'I. Evaluated By: Recommended for Approval By : ~(. c . .d. NFC Engineer A.11 'l 1S33 e * *

SURRY POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RES UL TS AND EVALUATION SHEET I Reference II Test Conditions (Design) III Test Conditions (Actual) . IV Test Results V Acceptance Criteria VI Com.'!lents Completed Test

Description:

M/D Flux Map -HFP, ARO, Eq. Xe Proc No_/ Section: l-PT-28.2, OP-57 Sequence Step No: Bank Positions (Steps) RCS Temperature

(°F):TREF

+/-1 Power Level (% F.P.):95 +/- 5 SDA: 228 SDB: 228 CA: 228 Other (specify):

Eq. Xe. CB : 228 cc: 228 CD:

Must have~ 38 thimbles Bank Positions (Steps) RCS Temperature(°F):

,-REF Power Level (% F . P . ) : / 00 % SDA: 228 SDB: 228 CA: 228 Other (Specify):

CB: 228 cc: 228 CD: Date/Time Test: Performed:

7/~/YJ zo1S-* 1/8' ;/itmb~ MAX. REL Meas Parameter ASSY PWR (Description)

% DIFF (M-P)/P -7.3 rec-p .. \.00 1.,.-3 Measured Value -*** .;.r f', .. 0.3'f f/\*3 esign a ue ,:m_, .,., D . V 1 I "IOI -,,

D.t (Design Conds) ", * -,.' ...... >

Reference

- iWCAP-7905 REV.l FSAR/Tech Spec! NO?-."'E ; I Reference NONE

Design Tolerance is met Acceptance Cri~eria is met

As Required NUC ENTHAL TOTAL HEAT QUADRANT RISE HOT FLUX HOT POWER TILT CHAN FACT CHAN FACT RATIO F*dH(N) F-Q(T) QPTR /,-'f7f /, '!2 7 /. OOCP NA NA I s 1.02 \rlCAP-7905 NONE NONE REV.l ~1.ss11*.1U*Pll

~(Z)s:. J.1/P

ICCZ) I NA TS 3.12 TS 3.12 TS 3.12 : ~S_NO : _YES _NO Cv!~(uL# Evaluated By: rf. ?1 i/2'f7 . 7 Recommended for l"1 9 Approval By: ~.~. NFO Engineer A.18 f!AY 7 1983

ML18141A071

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ML18141A071

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Dear Mr. Denton,

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Description:

Description:

Description:

Reference:

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