ML17347A647
| ML17347A647 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 12/07/1987 |
| From: | Hendrickson J, Marsh G, Perryman J FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17347A646 | List: |
| References | |
| NUDOCS 8712110249 | |
| Download: ML17347A647 (22) | |
Text
FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT UNIT 3 CYCLE XI STARTUP REPORT 8712110248 871207 PDR ADOCK 05000250 P Introduction This report contains the oEicial summary of the Startup Physics Tests performed on Turkey Point Unit 3 at the beginning of Cycle XI.The testing program was conducted in accordance with Operating Procedure 0204.3, Initial Criticality After Refueling, and Operating Procedure 0204.5, Nuclear Design Check Tests During Startup Sequence After Refueling, and meets the minimum requirements of ANSVANS 19.6.1, Revision 0 (12-13-85), Startup Physics Tests for Pressurized Water Reactors.Testing commenced on September 4, 1987, at 0750 and was completed on September 6, 1987, at 0300.The Westinghouse Nuclear Design Report for Unit 3, Cycle XI, (WCAP-11454) is the design data from which deviations were measured for the purpose of verifying that acceptance criteria were met.The acceptance criteria stated are the more conservative of ANSVANS 19.6.1, Revision 0 or Operating Procedure 0204.5.All of the tests included in this report meet their acceptance criteria.The contents of this report provide the documentation required by Technical Specification 6.9.1.a.Author: J.P.Hendrickson Reactor Engineer Reviewed by: G.L.Marsh Reactor Engineer Reviewed by: J.L.Perryman Reactor Support Supervisor Approved by: Vito A.Kaminskas Reactor Supervisor PTN~~-ll-Acknowledgements Introductio n 0 TABLE'OF CONTENTS'PAGE 1.0 Unit 3 Cycle XI Core 1.1 Loading Pattern 1.2 Rod Pattern 1.3 Rod Drop Times 2.0 Initial Criticality 2.1 ICRR Vs.Dilution" 3.0 Summary of Tests 3.1 Nuclear Heating 3.2 Reactivity Vs.Period 3.3 Boron Endpoint, Most Reactive Bank 3.4 Rod Worth (PPM), Most Reactive Bank 3.5 Rod Worth (PCM)3.6 Temperature Coefficient 3.7 HZP Differential Boron Worth 4.0 Shutdown Margin 5.0 Power Distribution Maps 5.1 29 lo Flux Map 14 15 16~~~-nl-A This section presents the as-loaded core configuration (Figure 1);the Control and Shutdovrn Rod pattern (Figure 2);and the Rod Drop Times for all rods as measured in Procedure 3-PMI-028.3 RPI Hot Calibration, CRDM Stepping Test, and Rod Drop Test (Figure 3).All rods met the drop time limit of 2.4 seconds as per Technical Specification 3.2.3.*R l:1-md DATE gPEACTOR FUEL LOCATI(g TURKEY POINT PLANT UNIT NO.3'YCLE NO.Xl FIGURE I Assy.ID Insert XD Legend XX"XX ZZ ZZZZ lS 14 13 12 ll 10 9 4 3 2 1 AA-41 100Z AA"40 106Z 08-27 1142 AA-36 1492 CC-20 2272 CC"50 2262 CC-11 8-10 00-32 1532 88-23 R-11 AA-20 AA-31 AA-23 HF-12 Hf-25 Hf"17 CC-16 8-27 CC-10 18sz 46 20oz 88"56 CC"35 BB"26 R-17 220Z 8-36 CC-38 AA-51 CC-40 192Z R"100 209Z CC"27 AA-37 8-39 1QBZ BB-52 CC-10 1462 1932 88-02 CC-52 R-40 2232 AA-56 1112 68-37 1822 AA-44 107Z AA-34 0152 CC-22 R-33 CC-31 221Z CC-53 2022 88-21 8-38 AA-45 R-21 CC-05 BP17 QMZ CC-02 BP17 SVZ AA-02 1552 08-16 60-19 88-13 R-12'1122 R-25 88-40 88-49 BS-40 161Z 8-42 160Z CC-04 BP10 1NZ AA-16 1512 AA-33 8-20 CC-06 SP10 avz CC-54 106Z 88-24 R"00 CC-12 2142 86-30 152Z AA-53 1052 CC-23 8-97 L K RA"24 Hf-24 AA-10 HF-04 AA-05 HF-00 CC-19 1032 H"52 30 CC-15 2242 CC-09 8-19 AA-52 2042 88-43 8-06 CC"36 SS-1 BS"39 R" 15 88-42 148Z CC-14 2262 AA"39 1032 CC"46 1792 8-37 CC-44 1902 88-10 R-24 CC-55 2162 60-33 2052 AA-42 115Z 88-11 R-35 88-01 137Z 88-06 R-07 CC-07 BP18 3MZ AA"47 8-04 CC-56 1992 CC-30 1912 AA"55 197Z 88-51 208Z 88"46 8-16 88-45 104Z 1102 cc-a0 6P17 7HZ 88-22 88-54 CC"25 8-10 CC-47 88-17 CC-34 106Z 222Z 2072 86-07 H-17 88-12 109Z, R-09 1502 CC-41 BS-14 CC-42 175Z 195Z 201Z 68-28 88-25 88-35 113Z R-05 159Z 88-03 88-10 88-00 8"32 101Z R-29 CC-39 AA-49 CC-33 1702 R-96 210Z 88-53 CC-45 88-44 8-27 2132 8-45 CC-32 H-41 CC-24 2172 52 1692 AA-11 AA-06 AA-03 Hf-26 HF"14 HF-03 AA-30 154Z CC-03 BP17 612 CC-01 BP10 2MZ AA-35 R-03 BBM CC-51 R-01 160Z 88-36 CC"29 105Z 206Z CC-21 AA-38 R-41.177Z 88-55 88-04 1252 R-22 88-31 88" 15 R-26 2112 88-34 SB-09 1002 R-02 CC-48 2192 AA-50 8-14 CC-37 2032 88"20 CC-49 2252 86-47 149Z AA"40.102Z 80-50 CC-43 146Z 00-29 8-43 86-41 1562 CC-13 229Z AA-43 104Z CC-20 AA-26-J 2122 Hf-10 H"37 AA-17-H 26 HF-21 CC-17 AA" 04 1942 HF-19 CC"26 R"18 AA-54 1502 0 Verified by Date (disc: 8-1)...
Om'aOr.Igloo nmX I.OCaxrOV T EY POINT PLANT UNIT NO.CYCLE NO.XI FIGURE 2 15 14 13 12 11 10.9 8 7 6 5 4 3 2'A A 0 S S S'A 0 S 0 0 A A A S S 0 Absorber Naterial Ag-In-Cd'A A FUNCTION Control Bank D Control Bank C Control Bank 8 Control Bank A Control Bank SB Control Bank SA 4 OF CLUSTERS 5 8 8 8&8 ROD DROP TIMES TUOkX POINT PLANT UNIT NO.0 CXCLE NO.XI FIGURE 3 15 14 13 12 ll 10 9 8 7 6 5 4 3 2 1 R 1.32 3.02 1,28 1.92 1,30 1.90 1.28 1.90 1.27 1.93 l.28 1.88 1,30 1,90 1.30 1,92 1.28 1,88 1.33 1,92 1.32 l.93 1.32 1,97 1.32 1.92 1.30 1.92 1.35 1.97 1.32 1.95 1.32 1,92 1,35 1.92 1.32 1,92 1.30 1,87 1,35 1,98 l.35 l.9S 1.28 1.81 1,33 l.92 1.31 2.01 l.28 1.93 1.33 1,98 1.30 1.90 1.27 1.92 l.27 1,93 1.30 1.93 1.53 1.93 1,32 1.95 1.40 2.08 1.28 1.93*1,32 1.92 1.28 1,87 1.30 1.95 l.28 1,88 1.30 1,95 1,30 1,92 1.30 1.92 1.28 1,88 1.30 1,95 l.32 1.90-H (R1:1 tl0)LEGEND Time to Oashpot Time to Bottom 2.0 INITIAL CRITICALITY The approach to criticality began September 4, 1987, at 0750 hours0.00868 days <br />0.208 hours <br />0.00124 weeks <br />2.85375e-4 months <br /> in accordance with Operating Procedure 0204.3, Initial Criticality After Refueling.
Criticality was achieved 1 September 5, 1987, at 0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br /> by withdrawing control rods to 160 steps on Bank D and diluting the RCS with 11,000 gallons of water.Upon attaining criticality the flux level was increased to 1 x 10-8 amps on the intermediate range to obtain critical data.Tavg Control Bank D Boron Flux 5470F 117 Steps 1710 ppm 1 x 10-8 amps TABLE 2.1 FLUX Picoammeter 1 x 10-8 amps N-35 ZOOS N-36 1.5 x 10-8 amps The following graph (Figure 4)is a plot of the ICRR during the approach to criticality. *Rl: l-md
~S ls~ffff~1 f1lffff~~A~s~~~~\s~46!5I(n'Zg ICR R VS.DIL OP 02 UT 04.ION H20 Date: it 3 ycle XI jsj:!AU l Is 2l"t I s.ii sll, s its1:I"'"'.f I 1:lf.Il I:ll:~.9.8.5.4.2.,s, 1;I s f.sj~i!l s 1~!i.t s 1" l s ls s ls ss~1 l.s 1:I f s I s sl t'I;'.1!sfs': 'I sf I!jl i)!1 il li s 1's:I'i:I'1st 1,.', 1~~,',s: I"';": lf.'f.': l l:f.j s",!I till s"'il, s 1 1: I'i ,.st ,'s::I: I:I-'I Ill sti!!C I I.!i I,.;sf'I'..'fs~I 1'",'1'"I;fs'1 I.I: 1'":11'lj"1 I;;t:i!it Ij" 1~'>>I.I.It ii!I'sit>>1 i s~1 f~s sf'I'11 V'i f.Il s I."1::I ts I~s Sl II.!i I" l ts I: 1'i I::.'I>>:tls!I I:sl j!I fjjll j1li:1jf I".I:!j.'1 11 s I..';!'i', fli::)',I I!is l;;:I:I fs.1'.;!:;,!.:.j!s i'l i:.Ij;s~1!~11..'f~'s I:.I;;If ,'1 s ll.Is l sl ljli>>I'I I;I';1" 1'.'ll II!;I'!.".'j,'.s
~'I" fs.s;f1 s'1!sr,'l, ij.tst'.!Ill'l l 1':..I.fs'~l..1;;sf!II'.'.s'.'..its li ll I s's 1'1 s'I'.ls\I 1;, I l I ts I;l,';":: I i'its'i!I~~,l l: I.'1!~jl:: lli: j I I I.:1 I I!'.", I l'j Ss ff's I fs"i fs':It:Itl: lt iill st I!2 I 4 II~0 (Gallons)X l000 10 l2 3.0 Summar of Tests This section provides a summary of the results of the low power physics tests along with the Westinghouse design data.This report compares design and measured data using difference'nd percent difference2.
For each test, the acceptance criteria is listed at the bottom of the table.'The difference
=predicted-measured.2For calculating the percent difference, the equation is: Predicted Value.y Measured Value X 10096 3.1 Nuclear Heatin The point of adding Nuclear Heat was determined in accordance with Operating Procedure 0204.3, Initial Criticality After Refueling, Step 8.15 and Appendix A.This is performed by establishing a small positive startup rate and measuring the point (flux level)at which T<<g departs from its established, steady value.Nuclear Heating was measured to first occur at: TABLE 3.1.1 FLUX LEVEL (AMPS)Picoammeter 4.32 x 10-7 N-36 6.69 x 10-7 All physics tests were conducted at or below 1.0 x 10-7 amps on the picoammeter connected to N-44 to assure Nuclear Heating did not occur.-&-.*R1:1-md 3.2 Reactivit Vs.Period Reactivity Computer checkout was done in accordance with Operating Procedure 0204.3, Initial Criticality After Refueling, Step 8.17 and Appendix B.This checkout is performed by inserting small (<60 pcm)positive and negative reactivities using rod motion, measuring the period generated and the indicated worth, and then comparing design worths to measured worths for the given period.TABLE 3.2.1 Period sec-239+232-288+157 Reactivit cm-36.0+27.0-29.0+38.5 Reactivit desi-36.7+27.0-29.5+38.5 Diff/o 1.9 0.0 1.7 0.0 Acceptance Criteria is+/-10.0 lo.-9-*Rl:l-md 3.3 Boron End pints PPM The Boron Endpoints noted below are determined as per Operating Procedure 0204.5, Appendix A.A just-critical condition is established as near as practicable to the required rod configuration (i.e., ARO).The RCS boron concentration is determined and is then adjusted analytically for the ppm worth of the reactivity (measured in pcm)by which the actual critical state deviated from the design condition.
TABLE 3.3.1 BORON ENDPOINTS (PPM)iARO 2CBC In Measured 1711 1536 Westin house 1592 Com arison 33 PPM 3.65%Acceptance Criteria is+/-50 ppm 2Acceptance Criteria is+/-10%
3.4 ROD WORTH.Rod worths were measured.as per Operating Procedure 0204.5, Appendices D and F.The Reference Bank (highest predicted worth)was diluted into the core.The boron concentration prior to and subsequent to this insertion was determined and the difference in the two boron concentrations is defined as the boron (Rod)worth of the.Bank (Table 3.4).The differential and integral worth of control bank C was measured and plotted (Figure 5).Additionally, the integral worth of banks C and D in overlap was measured and plotted (Figure 6).TABLE 3.4 ROD WORTH (PPM)CBC Measured 175 Westin house 152 3.5 ROD WORTH PCM)The remaining rod bank worths were measured using the rod swap technique,"swapping" negative reactivity'nsertions on the bank being measured with positive reactivity insertions from the Reference Bank.TABLE 3.5.1 CBD CBC'BB CBA SBB SBA Total Measured 682 1325 621 1089 1107 1051 5875 ROD WORTH (PCM)i~i'18 1811 579 1107 1137 1014 5866~iiiff PCMi-14-42 18 30-37-9%Diff+5.28-1.06-6.76+1.65+2.71-3.52-.15 The acceptance criteria for rod worth measurements are: (1)Reference bank within+/-10%of design, and (2)Individual banks within+/-15%or+/-100 pcm of design whichever is greater, and (3)Sum of all measured banks within+/-10%of design.*Rl:1-md HOT ZERO POWER DIFFERENTIAL AND INTEGRAL BANK WORTH VS.BANK POSITION 16 Iy~LLL 1600 l000 UNIT 3 CYCLE XI EXPOSURE 0.0 BANK CBC BANK POSITIONS Nl WD/N(TU R tQ 12 0 z 10 0 z 8 rQ rQ , f4 H'il hj!~~I i.".!I~~!~l!!I I~0 0 I i'ill i'jl!ll(.j.!~'.l t'!!:., I Ll:: Ill~~~~I al I ji~!.;il I ,'.l!I I'"lI 20 00 4~I'jV',!I I~I~I j~'r!(io~l i~',jl~!~j j~i,j',, ji'jlI Ij:;I I!J.'0 R OD ill~~~~j~j lw~pe~~lf~~I!i"..j!l'li Il(i,jl i~~j.!o: I i~I~iL'100 120 100 160 180 BANK POSITION (STEPS)j!ill'l i i~I!-'i t.'ill I,': 200 220 228 1200 1000 800 600 000 200 0 R 0 0 l4 U g z OUT IN SBA~X S88~X CBA X C88.~X C8C CBD X y TEST METHOD DILUTION~X BOR ATION MD~V LJ CV I X itio Cont 1 ro 08 I Bank'C'128 05 n IO 8 168 , INTE 18 G 8 RAL ROD 208 WORT H IN OVERLAP: BOL, HZP, NO-XE 228 Uni 3 ct Cy n Io cl II XI lg F Ur 0 7-6 05-87 JPH 16 15 13 12 10 9 6 3 I-~I s a~)I:.t: 'I::.)I'jl!j!jj~~~IIij I!II I~~~.',}'i I~~-l)~~~I's~~~'l!'ji~T')!I jj:l i.:I lt II i s'!il le),:!t ia ii'J i)jj i'j I i'i'tI):Ij: jill ip!I'f:'..'ll Il'), ii)~'!)j Tf I i'i:I'ji ILLs I i iij r jil sl I j I iij I~a Il I.I Ifi}!ij!f'Ri Ill e)I!.I il lj if II~e t)li:i Jl':I!~a~-Il I~~as ij;Ij)}t!~~4}:ji IIil!tJJ!jil:'.;,:'I)ijl l.,s ll il l l~;I It I l)if il jl I ti)I" jifj ItI Ill!I I)jil!~I!I!I lil III!Ill!II t ijI jljj jtf!sj j li I jf I if'lI jv:!If lite jtfl ,'i.'I;i!I!ilij!!!j ll~~I)Isa I l I i s)i,~~a~I I-'ta'.I~~,'.'I le t)es~~~!.Isl~~el~I I li)jj II!sjj lj:,:!;!l I~~~Ii;':I: ijij I tjtl:,): ill)~)~li.:~il;Is'jf))s,i))I I I e:!':.ij fa~I)I I)i~~~"i'~~li'~I sljl ifil'e e s alt;as s~, ti.l'I)I I!ill'll I J!I.'I;l:.-'!I~!tf Je if sf I I I j!';}I!jl)il'l'I if I!l-i!s ii.e e i-~as lil ill I I I I I)S t,;~t')i~I'I~)}I-f)!II f!II lt!!I li a i I~I i j Ijl lij!!j!il~Ie j".i;il:.st I I I'I'\Il Il'hi I~ll ,Ite'ei~~~~'.Ii~e*t tis t!l a I ,'I,: iji I)i~I Jl!!1 s I I I,'.!I I,"I j;ji ill.}le Il'.i}~s I!I s!t!I'.ll;!}!~JL)I ,:if;if i I-~~~~Ill jj)~Ie i!I I:I j,l~I I))~~~sile"a l I I I!I t~I~I!,lj ll!I~)~~el~fji)}j,l'-jll I!l)~~aT apl i~I I I ls tt j jjl)aj;a))I il'l la el~i i:}I)sll I I tl it t)el!!tiij l~l~I!J}el;".f I I)I.I, j I!I I~J!e sj I.I 15 13 10 I 9~I 05 3 0 20 00 60 80 100 Control Bank'D 1)p 20 osl tlon 100 160 180 200 220 3.6 TEMPERATURE COEFFICIENT 'h.isothermal and moderator temperature coefficients were determined using Appendix 8 in Operating Procedure 0204.5, Nuclear Design Check Tests During Startup After Refueling. The values determined for this testing sequence (in pcm/OF)are: TABLE 3.6.1 ISOTHERMAL TEMPERATURE COEFICIENT (PCM/oF)Rods D/215 Measured l+.96 Design Westin house+1.1 Diff.14 Acceptance Criteria is+/-2 pcm/OF of design.TABLE 3.6.2 MODERATOR TEMPERATURE COEFFICIENT (PCM/oF)Rods D/215 Measured I+2.86 Design>Westin house+2.76 Diff Acceptance Criteria is<+5 pcm/OF.IThis is the average of one heat up and one cool down measurement. 2This value has been adjusted for boron and temperature sensitivity. *Rl:1-md 3.7.HZP DIFFERENTIAL BORON WORTH The Hot Zero Pow'er (HZP)Differential Boron worth was measured using Control Bank C, which had a bank worth of 1325 pcm.The value obtained for this test was: TABLE 3.7.1 HZP DIFFERENTIAL BORON WORTH (PCM/PPM)Measured 7.57 Westin house 8.44 9o Diff 11.49 Acceptance criteria is<+/-15%. 4.0 SHUTDOWN MARGIN The Shutdown.Margin was calculated prior to power escalation to verify adequate shutdown capability. For this calculation, design rod worths were reduced by 10%, and the results show adequate shutdown margin at BOC and EOC.The following is a summary of the results: Control Rod Worth%A~Cele Xl BOC ROC All Rods Inserted Less Worst Stuck Rod (l)Less 10%6.41 6.50 5.77 5.85 Control Rod Re uirements%A Reactivity Defects (Doppler, T~g, Void, Redistribution) Rod Insertion Allowance (2)Total Requirements Shutdown Margin (l)-(2)%b, p Required Shutdown Margin (%b,p)1.69 2.89 1.35 0.50 3.04 3.39 2.73 2.46 1.00 1.77 Source: WCAP 11454 FLORIDA POWER AND LIGHT OMPANY TURKEY POINT PLANT T 3 OPERATING SUM1HA 15 lh 13 12 Xl 10 8-7 6 5~C 3 Z 1~~0~~~~0~~~~~~0~~~5~23klQ Po 0 P3f~~0~0~~~~~~~~~~~~0 1012510~933 10160 10171IO~92h 101T1<<309 100<<0'0~~0~~~~~000~~~~~~10082llol75 1009C 10)2({10$$10)2)'!'.Il':I'.II'I $00)3IOo9$0$oO)3 k:N i:l'os ICE'o 1 11)5 9gl1 lti~~~~~~~~~~~0~~~~~~Oe990 Oe83h lo012 i:pp:pi hp)151 1 Pjll 16]$oO)f Oe)Q$0))0 0'303 5'~~~0~~~~~~~~0~0~~~1 1P3 5!PJ i 1V3l~~~~~~~~~~~~~~0~~~10159 1019C 10169'323'Vk'32)1 Hll'P)'~~~~~~~~~~~0~0~~~Oezhzt00258l002CO 0'35)0'50)0'35 2.8)3.')z.c~~0 0~0 0o 913 1~026<<1100~~~~~~k: jII k,'N$3'Nk lo0$1 k P9)i:II!':III'N3<<006$0200 001~~~~~~1 0235 1~I%3)$o055 0~0~0~003981 0'30j 0~0 0~~10195I lo)9$)'39l k:)Ig ijS!I'83f~~~~~00CC3'-'3'.II 3 3B P 3)3f k:$9"'ift 5:IIiIj 6 j05l2~2$6l~~~~~~~~~~~~1 j5$ll$~4fl~~~~~~0'3C 0'3)002)9<<109 0 945ll Paf~~~~~~~~~~~~kjIIfHIII! f~~~0~~~~~~~~ljPlk:jag':Pil ~~~~~0~~~~~~':Pi':!9l Oo)0990 fe230f<<601<<60lt 4!jl!-:P/1 k:INIf H4kkl le 295I le)90)~~~~~~~~~~~~Ooh63l 00C6~{~~~~~~~~~~0~Oe$(0 006~~~~~~0~979 1~026<<ho 5~~~~~0 10179'-Pf 0~~~~~le130i 1~)00(3jIIj::.IIIj~~~~~~lolhlt 1~08/{$020C~09)i:g 0~0~0~6".Pl foh38 302 0~~~~~1~261 10)3h~~~0~0 1 0032 1~026 006~~~~~~H 8 D~~~~~00COC 0'30<<601~~~~~~lo 212 10)9f':O'.Il pe Oii9l cpIj~~~~~~1~058$100C)j i:pJ':I!II k:I4f leh081 1~hl)j 10283 1~$90 9)30l OFF'HI~0~0~~00C36 0'6)6 j56~~~~~W~390 k:h$1 169l 1 2$4I':III$o308<<002 00C6)<<006'-:IIIt k:jhj i:Pal~~~~~~10282I 10183)80C o.'aii j I:,.iIjj':Nl 44/i 10015 10016<<001~~~~~~00C58 00C61 0~6 D F DCLTA H D P DELTA H NCE~~~~~0 Oo251.00 23)39$002 Ooh)0'$07 j:ii4jf~~~~~~Io235 lo)89 le 003 0~(3%I Hfdf h04jl Oo)35<<001 0~~~~~ROD POSITION SBB CBA Location~in Ste 228 228 228 Classification M2P NO.PM3X12 Power%28.89 Axial Offset 1.08 0.9712 0.9890 INCORE TII T N CBB CBC 228 228 Maxp N 6 8 14659 1.0013 1.0385 CBD 135 Maxp N Q 1.930*Rl: I-md}}