ML20024A548
| ML20024A548 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 06/07/1983 |
| From: | Murray T, Richter L TOLEDO EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| K83-829, LER-83-002-03X, LER-83-2-3X, NUDOCS 8306170429 | |
| Download: ML20024A548 (10) | |
Text
{{#Wiki_filter:NRd FORM 3'66 U. S. NUCLEAR REGULATORY COMMISSION (7 77) LICENSEE EVENT REPORT (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) CONTROL BLOCK: l t l l l l l lh 6 lo l 18 l9 l 0 l H 7 l D l B l S l141 l@l LICENSEE CODE 15 0 l 0 l - l 0LICENSE l 0 l 0NUMBER l 0 l 0 l - l 0 l 025l@l26 4 l 1 l 1 l 1 l 1 l@l57 CAT LICENSE TYPE JO l l@ 58 CON'T lolil 7 6 SC"Ce60 l L l@l 61 0 l 5 DOCKET l 0 l 0NUMBERl 0 l 3 l 4 l686 @l 69 0 lEVENT 1 l 115 DATE l 8 l 743 l@l0 75 l REPORT 6 l0 lDATE 7 l 8 l380l@ EVENT DESCRIPTION AND PROBABLE CONSEQUENCES O'o 2lg l (NP-33-83-03) On 1/15/83, 1/18/83, 4/9/83, 4/10/83, and 5/10/83, the Reactor Coolant ] io ;3 ; ] System (RCS) Dose Equivalent I-131 exceeded the Technical Specification 3.4.8 limit ofl [ o ,4 j l1.0 uCi/gm. The peak levels measured were: 2.67 uCi/gm on 1/15/83, 1.39 uCi/gm on l 2 Jg l 1/18/83 and 4/9/83, 1.95 uCi/gm on 4/10/83, and 1.16 uCi/gm on 5/10/83. There was no l l 016 l l danger to the health and safety of the public or station personnel. At no time did l [ o l 7 l l the specific activity exceed the allowable limit of Tech Spec 3.4.8 which accommodates l io,g, lpossible iodine spiking phenomenon that may occur following a change in thermal power.l DE CODE S SC E COMPONENT CODE SUSCODE S E g l Rl ' Cl@" W@ lC l@ l Fl Ul El Ll El X[@ ]@ ]@
,_ SEQUENTIAL OCCURRENCE REPORT R EVISION EVENT YE AR REPORT NO. CODE TYPE NO.
@ ~"LE u'M _R21I 81 RO3l22 L--j l 0l 01 21 l-l l 0l 3l [xj [_j l2 ;
23 24 26 27 28 M 30 31 32 KN AC O ON PL NT ME HOURS 22 SB ITT FOR 8. SUPPLI MANUFAC RER lZl@ b @ lZl@ 33 34 35 l36 Zl@ lN lN IN I T l 37 40 b@ d@ 43 42 l Nl g 43 lB l0 l1 l5 l g 44 47 CAUSE OESCRIPTION AND CORRECTIVE ACTIONS h l i l O l l The cause was a slight leakage of fission products through the fuel cladding. Some l li;il l leakage is normal following a reactor trip due to RCS temperature and pressure l
, , l changes. The I-131 level was monitored until it dropped below the Technical Specifi- l g l cation limit. l i 4 l l 7 8 9 80 STA S % POWER oTHER STATUS IS O RY DISCOVERY DESCRIPTION 32 R (,,,XJ@ @ l 0 l 0 l@l NA l l A l@l Per Table 4.4-4 of Tech Spec .4.8 l A TIVITY C TENT RELEASED 06 PELEASE AVOUNT OF ACTivlTY LOCATION OF RELEASE R [Zj 7 8 9
@ (3_jglNA 10 11 44 l l NA 45 80 l
PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION l 1 l 7 l l 0 l O l 0 l@l Z [@l' NA l so PERSONN E L INJU IEs 8306170429 830607 i a NUMBER l 0l 0 l 0 l@l NA DESCRIPTION @ PDR ADOCK 05000346 S PDR ,p $ l
'0S,5,OF 7y m OR 0 hAGE TO FACILITY
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i 9 (_Zj@l NA l 7 18 9 to 80 NRC USE ONLY , tSSUE 1,2,,[p,,j [Nf@lDESCRIPTION NA l l[[;[gl;;;;;lg 88 88 805 dVRs*83-006,'007,008,037,056 NAME OF PREPARER Lynn Richter PHONE: 419-259-5000. Ext. %4{
d TOLEDO
%ms EDISON June 7, 1983 Log No. K83-829 File: RR 2 (NP-33-83-03)
Docket No. 50-346 License No. NPF-3 Mr. James G. Keppler Regional Director, Region III Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Dear Mr. Keppler:
Enclosed are three copies of Revision 2 to Licensee Event Report 83-002, including revised supplemental information pages. The revisions to the report are indicated by a "2" in the left margin of each page. Please destroy your previous copies of this report and replace with the attached revision. Yours truly, f0 Terry D. Murray Station Superintendent Davis-Besse Nuclear Power Station TDM/ljk i Enclosure l l cc: Mr. Richard DeYoung, Director Orfice of Inspection and Enforcement Encl: 30 copies Mr. Norman Haller, Director l l Office of Management and Program Analysis Encl: 3 copies , Mr. Tom Peebles l NRC Resident Inspector Encl: 1 copy l l JUN 131983 I THE TOLEDO EDISON COMPANY EOISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43652
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-83-03 2 DATE OF EVENT: January 15 and 18, 1983; April 9 and 10, 1983;
' May 10, 1983 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Reactor Coolant System (RCS) Dose Equiva-lent I-131 Exceeded Technical Specification Limits Conditions Prior to Occurrence: The unit was in Mode 3, with Power (MWT) = 0 and Load (Gross.MWE) = 0 Description of Occurrence: On January 15, 1983 after a reactor trip, the specific activity of the primary coolant exceeded the Technical Specifica-tion 3.4.8 limit of 1.0 pCi/gm Dose Equivalent I-131. The level peaked at 2.67 pCi/gm at 2004 hours on January 15, 1983.
A similar event occurred after a reactor trip on January 18, 1983 with the dose equivalent level peaking at 1.39 pCi/gm at 2301 hours. On April 9, 1983, at 0420 hours, following a power reduction to repair a
~
failed steam generator level transmitter, the Dose Equivalent I-131 exceeded the limit of Technical Specification 3.4.8. The level peaked at 1.39 pCi/gm at 0620 hours oa April 10, 1983. I On May 10, 1983, following a reactor / turbine trip, the Dose Equivalent 2 I-131 exceeded the limit of Technical Specification 3.4.8. The level i peaked at 1.16 pCi/gm at 1323 hours on May 10, 1983. The following information is supplied per reporting requirements: Power History On January 15, 1983, reactor power was approximately 100% until a reactor / turbine trip at 1700 hours. Date Time Reactor Power 1/14/83 0000 hours 99.4% 1600 hours 99.5% 1/15/83 1600 hours 98.7% 1700 hours TRIP 4 r- -- - -- -. , ,, . . ~ ,
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE . SUPPLEMENTAL INFORMATION FOR LER NP-33-83-03 PAGE 2 On January 18, 1983, reactor power was approximately 100% until a reactor / turbine trip at 1925 hours. Date Time Reactor Power 1/16/83 1600 hours 84.3% 1/17/83 0000 hours 87.3% 0800 hours 97.9% 1600 hours 99.2% lfi8/83 0000 hours 99.3% 0800 hours 99.4% 1600 hours 99.6% 1925 hours TRIP On April 8, 1983, a power reduction from approximately 100% was initiated for a short maintenance outage. Date Time Reactor Power 4/8/83 2000 99.1% 4/9/83 0100 48.5% 0700 6.4% 1600 21.7% 2400 42.0% 4/10/83 0300 79.8% 0345 TRIP On May 10, 1983, reactor power was approximately 90% until a reactor / turbine trip at 1028 hours. 2 Date Time Reactor Power 5/9/83 1200 90% i 5/10/83 0000 90% 0800 90% 1028 TRIP Fuel Burnup By Core Region: See attached computer printout. Cleanup Flow History 48 hours prior to the first limiting exceeding , sample, the average letdown flow during this time was: January 13, 1983 - 60 gpm January 14, 1983 - 61 gpm January 15, 1983 - 86 gpm
e TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE . SUPPLEMENTAL INFORMATION FOR LER NP-33-83-03 PAGE 3 January 16, 1983 - 109 gpm January 17, 1983 - 101 gpm January 18, 1983 - 60 gpm April 7, 1983 - 60 gpm April 8, 1983 - 69 gpm April 9, 1983 - 93 gpm April.10, 1983 - 95 gpm May 8, 1983 - 72 gpm . 2 May 9, 1983 - 72 gpm May 10, 1983 - 72 gpm There was no degassing operation. Table 1 lists the specific activity analysis, the time duration the specific activity exceeded the Technical Specification, and the maximum level reached for each occurrence. Designation of Apparent Cause of Occurrence: The cause was a slight leakage of fission products through the fuel cladding. Some leakage is normal following a reactor trip due to RCS temperature and pressure changes. Analysis of Occurrence: There was no danger to the health and safety of the public or station personnel. At no time did the specific activity exceed the allowable limit of Techni-cal Specification 3.4.8, which accommodates possible iodine spiking phenomenon that may occur following a change in thermal power as shown in Figure 3.4-1. Corrective Action: Per the action statement requirements of Technical Specification 3.4.8, sampling of the primary coolant was performed at least once every four hours. Monitoring of the I-131 level continued until it dropped below the Technical Specification limit of 1.0 pCi/gm. Since icdine spikes are typical following a power change, no additional corrective. action is applicable. Failure Data: Previous occurrences of the RCS dose equivalent I-131 exceeding the Technical Specification limit have been reported in Licensee Event Reports NP-33-80-114 (80-088), NP-33-81-15 (81-016), NP-33-81-37 (81-031). LER #83-002
TABLE 1 sEE
- O5dE Approximate # % T' 8 i Specific Activity Analysis - Time Duration Maximum #Em Date of Occurrence Date Time Activity (pCi/gm) Tech Spec Level Level h$$
Dose Equivalent 1-131 Exceeded pCi/gm "8 January 15, 1983
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1/15/83 0810- 0.17 21 hours 2.67 g n g_ 2004 2.67 p i6 1 2155 2.54 g-1/16/83 0102 2.33 @g 0400 2.40 ,,, 0730 1.59 . @ %l 0930 1,58 e4 1330 1.14 N5* 1730 0.73 2 7E January 18, 1983 1/18/83 1354 0.14 8 hours 1.39 Oy 2301 1.39- So o
. YM 1/19/83 0256 1.11 8 ,
0645 0.81 April 9, 1983 4/8/83 1207- 0.09 11 hours 1.39 4/9/83 0420 1.06 0806 1.37 1145 1.39 1531 0.96 April 10, 1983 4/10/83 0130 0.41 15 hours 1.95 0620 1.95 - 1002 1.82 1341- 1.31 1710 1.30 2110 0.89
- May 10, 1983 5/10/83 0811 0.06 8 hours 1.16 1323 1.16 2 .
1600 0.95. 2000 0.85 ,
$/11/83 0820 0.33 1 -
t - 1 _ u 'N a v .,- N ' eh , .,A,. s ,. TOY EDISON-COMPANY DA L -BESSE. NUCLEAR POWR STATION UNIT ONE s SUP21.EMENTAL INFORMATFON FOR LER NP-33-83 J PAGE 5 s t ,
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1 FUEL BURNTIP BY CORE REGION FOR JANUARY 15, 1983 AND JANUARY 18, 1983 EVENTS m The f'uel burnup is given for each fuel assembly as designated by the computer assigned assembly number. For the location of the assemblies, see the attached core map. Units are given in Megawatt Days *
~ x 10 Metric Ton
's w%
' I' FUEL ASSEMBLIES *
- x .
e lt n A .
. t9'42L+t1 f 5 51' 4 t' + 01 37P6?L 41 c u t;p r + e l 21*57(+01 2917?f+31 3905?t+01 1 through 7
- s. l'119 4l + 0 2 T 2 218E + 02 17n t TE + L'2 E U3 0E + C 2' 1119 3T
- 0? 38hS.*t+01 2P741L+01 8 through 14 s N 1:4 '2 0 f + L P 4!13SE+C1 247,1)+0? '> 4 0. ? f , 't ? 1" 1?t+t? 153370+3? IG'?Of+0? 15 through 21 23s79E+b2 D G rvt + 02 444thb+01 13409f+0? Jy 4 H /th01 45411E+01 ?6106t+0? 22 through 28 14 3 7 7 t: + 0 ? 15 4 7t C + 02 16%34f*0? 5 11141 e fil ae5360*L?\19474E*02 14 3 4 9 '. + 0 2 29 through 35 auun91+02 442990+t1 26539L+01 39tL0E+L1 2.,14 4 t + G P '14 4 9'": + t8 2 244Utf+02 36 through 42 I ? 3 0 eif
- 0 2 .t t 0 81 F + 02 ? !11rL + 0? 2109HF+0p 1, ? ? 9 6 t +Y 2 2 4 3 ( 'a r + r:2 14431t+02 s 43 through 49
\ E4681l+b? aP4 ? At + 01. ? ?9a 7t +01 1104sC + tr ? %67f +0? 1 5 t.9 1 E + ' ? 12185f+02 50 through 56 s ' I$6 Y3 fs+1? T Jr 3 6t +0? 15' 41 t + 0 2 26736t+02 13 8 4 4 t ,+ 0 TA 12157E+0? 15551F+02 57 through 63 t
e34T7 Nud 10 Hit +0.* 2 7 e4 L + 01 '5FSIf+01 22635t+0? 1519-E+y? 16 319 5. + 0 ? 64 through 70 PM590+02 269t> 7E + b2 13061E+02 22297E+b2 1.8 5 6 6 f + 0 2 '2 6 9P G E + 0 2 27494f+0? 71 through 77 I t. '. 52/ + t ? IS143E+0? ??!64F+02 ? q H '4 n E + 61 37b67f+di 17P17E'+0F 1530?r+0? 78 through 84 N'5 91 H ot + 01 T8004f+02 13 pat'+0? ? ?2 7 ? E + ti? 15665E+0? ???'44E+n? 13'!17 t + 0 ? 85 through 91
'4170t+L2 L D 4 tA L + C 1 1 % 2 '> G F + 0 ? 1776%F+0? 371490+01 3533?#+01 22574'.+0? 92 through 98 1.> t 2 4 t' + a .' I t.2 a5E + S2 2 7 4 '.8 f + 0 ? ?6941t+n 13'20E+C2 22?47f+3? 13530F+0? 99 through 105 P ro t' l L + 0 ? 27bd6E+02 It310t+02 15137t.+ h 22563E+02 34t42E+31 27244:+01 106 through 112 1 *'9 2 % + 0 ? P 3 4.? 3 L + 0 ? 1 % 3 H t' + 0 ? 1 J r. 8 a E + f, P 13/6EF+09 P 617 /F + n; 13P 7F t + 0? 113 through 119 Pe ISoL +02 13790E+02 12141E+02 15548F + 0? ?34760+02 10917E+0? 269t,1 f + 01 120 through 126 3Pa67t+ul ?5 ??*iE + 02 19377L+0? ?4304L+02 I??3?E+02 ?70?^f+0? 29 0 3 5 t '* 0 ? 127 through 133
.eM3HE*UP 1219Pr+02 2 '+ a f t, t + 0 2 14 4 01E + r r ? % 0 9t + 0 2 3F 22 .f + 31 2Pt431+01 134 through 140 4 ,0 7 t.t + 01 ." 6 031t + 02 1439d+L? 15 4 4 ? E + r.? t*,491L+0? 9015"L+01 I t 4t. 0 L + 02 141 through 147 l 'ue ? 3 L + 2 14 29 /E +0? 2e>0?3E + 0? 4 4 0 s, l t te) ?n479F=01 13 89H + u? 44?601.+01 148 through 154 s
24797L+02 3930E +02 l ') 4 8 4 L + 0 2 l o!,L U + Q -1 ! 4 61 C + 0 2 2 3 92 9 E + 0.2 2f>181E+02 155 through 161 9 4 2 0 2 L + f.1 13 39PE + 02 2 870 SE
- 01 Th6'ti+Pf 11172E+0? 22?C7E+02 17 7'/ 3 t + 02 162 through 168
- ? 21 's 6 f + 0 2 111m3f+02 3860HE+01 28E7pr+dl.27*b7E+01 3534*E+31 37675t+01 169 through 175 176 through 177 SS331E + 01 273?4E+01 S *AS READ IR9M LEFT TO RIGHT s i i '
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DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-83-03 PAGE 6 FUEL BURNUP BY CORE REGION FOR APRIL 9, 1983 AND APRIL 10, 1983 EVENTS The fuel burnup is given for each fuel assembly as designated by the computer assigned assembly number. For the location of the assemblies, see the attached core map. Units ar.e given in Megawatt Days- -3 10 Metric Ton FUEL ASSEMBLIES * . 44936E+01 57712E+01 61204E+01 57816E+01 44983E+01 47002E+01 62491L+01 1 through 7 jf 15825E+02 24556E+02 20118E+02 24577E+02 130460+02 62568C+91 e. 6 7 7 2 E + 01 8 through 14 ' , 14713E+02 72375E+01 26855E+02 26354E+02 18153E402 17396E+92 18151E+02 15 through 21 26274E*02 27256E+02 71974E+01 14675E+02 47347E+01 72681E+11.28439E+02 22 through 28 1705HE+02 17350E+02 18727E+02 82091E+01 187360+02 17362E+02'170480+02 29 through 35 28404E+02 71681E+01 46475E+01 63162E+01 27311L+02 17281E+02 26992E+02 36 through 42 - 15293E+02 29397E+02 '30291E+02 29426E+02.15294E+02 26988E*02 17246E+02 43 thro' ugh 49 , 26851E+02 61934E+01 45356E+01 13502E+02 26025E+02 17535E+0? 150600+02 50 through 56 16763E+02 28583E+02 16523L+02 28587E+02 If>764r+02 15046Et02 17502F+02 57 through,63 25777C+02 13386E+02 44434E+01 57979E+01'24898E+02 17628E+02 18349L+02 64 through 70 , 29679E+02 29402E+02 16332C+02 25019E+02 16342E+02 29431E+02 29779E+02 71 through 77 18341E+02 17580E+02 24849E+02 56999E+01 61106E*01 20082E+02 17341F+02 78 through 84 , 80721E+01 30159E + 02 16454 E+0 2 24963E +02 1833 6E +0 2 ,25 018 E+ 02 16495E+02 85 through 91
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3 023 9E +0 2 81254 E + 01 17337E+02 20037E+02 60362E+01 57401E+01 24829E+02 92 through 98 17527E+02 18289E+02 29756E+02 29373E+02 16?871+02 24966E+02 16304F+02 99 through 105' ' 29412E*02 29815E+02 18349E+02 17571E+02 24823E+02 56923E+01 44577E+01 106 through 112 13373E+02 25665E+02 17444E+02 14955E+02 16671E+02 28517E+02 16454E+02 113 through 119 28498E+02 16730E+02 15031E+02 17518E+02 25773f+02 13367E+02 49283E+01 120 through 126 61737E+01 27403E+02 17149E+02 26882E+02 15190E+02 29310E+02 30204E+02 127 through 133 29186E+02 151H7E+02~ 26919E+02 17183E+02 27172E+02 61634F+01 463531+01 134 through 140 71281L+01 28340E+02 16992E.+02 17318E+02 18659E+02 81061E+01 18628E+02 141 through 147 17278E+02 16983E+02 28363E+02 71310E+01 46315E+01 19663E+02 71529E+01 148 through 154 26980E+02 26271E+02 18128E+02-17356E+02 18105E+02 26259E+02 27341E+02 155 through 161 71503E+01 14641E+02 46628E+01 62239E+01 13791E+02 2455JE+02 20071E+02 162 through 168 24538E*02 13803E+02 62159E+01 46581C+01 44822E+01 57618E+01 61114E+01 169 through 175 57592E*01 4 4 7 76E +01 176 through 177 l
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TOLEDO EDISON COMPANY ,, DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE , SUPPLEMENTAL INFORMATION FOR LER NP-33-83-03 PAGE 7 ' ~ ' FUEL BURNUP BY CORE REGION FOR; ~Y# ' MAY 10, 1983 EVENT ' *
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The fuel burnup-is given for each fuel assembly as designated by the computer assigned assembly number. For the location of the assemblies, see the attached core map. Units are given in Megawatt Days ~ x 10 Metric Ton f
. FUEL ASSEMBLIES
- SGR07i+01 6515CE+01 69C43E+C1 65292E+01 509 0 0 E + 01 t 30 4S E+ 01 70320E+01 1 through 7 14626E+C2 253J2E+C': 2CL91E+C2 S S 3 f. 8 E + ' ' 14716C+C2 7C'ESE+11 52878E+G1 8 through 14 IS145E+02 F1454E+C1 27E74E+02 27139E+02 1'f 035 ;4 0 2 18099E+02 19338F+02 15 through 21 27Jf2E+02 2 79hE +G2 81135 E+01 151C91+C2 534 04 f + 01 F.17 7 2 E + J 1 20218E+0? 22 through 28 17 % " E <- 0 2 IE018E+G2 194 74 E+02 924 74E + 21 lo486E + S2 1803CE+32 17967E+02 29 through 35 29157E*r2 SC214E+01 Sr54?,E+01 710102+C1 23037E+02 1 8 2 1 ': E + 3 2 27872E+0? 36 through 42 lo 0GE+G2 J017]E+32 31018F+02 3 0 0 0 0 E + ::P 16206E+32 27871E+32 18186.+0" 43 through 49 2 2 7f 7t E+C 2 e ? 787/+c1 51227e+01 14315E+62 2 'i B 21 '~ 4 0 2 16263E+02 16026?+0? 50 through 56 177T7t HT '93 E+!? 17J 85E + 22 2925'E+0P 17733_C 2 16C1'd+c2 18213-:+0? 57 through 63 aut:E+02 111 % E + n 5 0C'2 3E + C 1 653"1E+31 2 5 6 4 4 , + J:2 1P.4'7E+02 19038E+02 64 through 70 2 C + ! i c. + l T 2021]E+0F 172PC E + 0 2 2590'C+J2 1723 6 L +0 2 3 0?t 2 E + 02 3 0 550 +0 2 71 through 77 l'034L+bP 18 3 01 E + :,2 2 0 5 $5 E + :* 2 642 7F+;1 (: H F 8 4 ~. + 01 2084"E+02 18n36 M12 78 through 84 9 t. 9 5 7 E + 01 20873E+"? 17339E+02 25P4"E+j2 19122E+02 25907C+02 17356E+02 85 through 91 3 0"t i t'+ 9 2 '215. 74 E + .1 18.3 3 5 E +0 2 23804E+12 6a l 2 6.'+ G 1 5 4 7 43 E + 91 25573;+02 92 through 98 1 334L+0; 1297"En2 3T927E+C2 32162f+92 17176:+02 25F54E+02 17196F+02 99 through 105 '
51J~HEa c 'T _s' EEL +~" 19L4cC+/I 163 elf +02 25566'+02 a4307E+01 50423"+C1 106 through 112 141Elc+C2 3.4 2 ': E + M. If149E+C2 15919E+32 1763 2 E +0 2 P 92P '.E+ 3 ? 17 % 14 :. + 0 2 113 through 119 2026Ev4J2 17 ( 9 7 0 - r. 2 15 0 0 3 : + t. 2 18729C+?" 26f452+D2 1417GE+32 50117?i01 120 through 126 6 ;" 44 r
- J1 761 1E+22 13 'J 8 4 F.+ 0 2 27761E+ 2 15194E+: S 3C081E+12 30c27;+0? 127 through 133 2 - 9 4 4 t. 4 42 l al'? b E + 32 21H02E+02 18122E+52 27P?bi+J2 65-44?C+01 52594E+01 134 through 140 t- C J 5 F E . r.1 2 911 t c + L ,' ;7994r+02 17967E+ 1 9 4 9 5 ,+ '; 71411E+01 19374E+0? 141 through 147 I M 4Fi+G2 178 %i + C 2 2 '3141 E + 0 2 803EJE+!1 52?S5'+~1 15094E+32 80626t+01 148 through 154 2 7 7 0 ". :. + 4 " 7 3 7- 1 E
- C 2 19011E+02 18058E+G2 la?8PC+22 2704aE+32 2 S 0 6 3 + 0 ? 155 through 161 80SS4E+,1 15072E+02 6259hI+01 7 010 7 E + e,1 14557E+02 25327E+02 2C844E+02 162 through 168 2531M.+02 19 6i.V_+f? 70015E+01 52644E+01 50712E+01 65073E+01 CA952E+01 169 through 175 6E041:+31 ' C 62 "E +t 1 176 through 177
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1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 Incore Detector Z O = Total Core Monitor Fuel Assembly Batch ID. (No. in Core) X = Symmetry Monitor yoet Asee biy zD 1 (25) For=er sacch A - once burn =4
@ = Total Core and Symmetry proceeded 3 (60) Former Batch C - twice burned bY NO 4 (44) Formar Batch D - once burned Monitor AllID'sd 5A (8) New Fuel - 3.04% cariched Incore Detector String Number h 5B (40) New Fuel - 2.99% enriched gig g 1
Regenerative Sources at P4 and 812 C001 Control Component / Source ID and Type Q31 1 89 A = APSRA a - Regenerative Neutron Source C = CRA Computer Aseigned Assembly Number _ j Control Component Group / Rod l Prepared By _. , / /b2[>> Approved By ! M y 1 __--_____.-__m_ _ . _ _ _ _ _}}