ML20023C302

Revised LER 83-002/03X-1:on 830115,RCS Dose Equivalent I-131 Exceeded Tech Spec Limit of 1.0 Uci/Gm.Caused by Leakage of Fission Products Through Fuel cladding.I-131 Monitored Until Level Dropped

ML20023C302
Person / Time
Site:	Davis Besse
Issue date:	05/05/1983
From:	Richter L TOLEDO EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20023C295	List: ML20023C294 ML20023C302
References
LER-83-002-03X, LER-83-2-3X, NUDOCS 8305170171
Download: ML20023C302 (8)

Text

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NRC FORM 386 U. S. NUCLEAR REGULATONY COMMISSION (7 77)'

• LICENSEE EVENT REPORT CONTROL BLOCK: l 1

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EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES lg l (NP-33-83-03) On 1/15/83,1/18/83, 4 9/83 and 4/10/83, the Reactor Coolant System (RCSI)

[g l Dose Equivalent I-131 exceeded the Technical Specifiation 3.4.8 limit of 1.0 uCi/gm. l g l The peak levels measured were: 2.67 uCi/gm on 1/15/83, 1.39 uCi/gm on 1/18/83 and l lg l 4/9/83, and 1.95 uCi/gm on 4/10/83. There was no danger to the health and safety of l lg l the public or station personnel. At na time did the specific activity exceed the l lg l allowable limit of Tech Spec 3.4.8 which accommodates possible iodine spiking pheno- l glTll menon that may occur following a change in thermal power. l E CODE S BC E COMPONENT CODE SUB ode SU E O 9 l Rl Cl@ ]@ g@ lF lU lE lL lE lX l@ g@ ]@

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41 l l@ lB lYl3 lg 40 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i O l The cause was a slight leakage of fission products through the fuel cladding. Some l i i l leakage is normal following a reactor trip due to RCS temperature and pressure changes l.

i 2 l The I-131 level was monitored until it dropped below the Technical Specification l i 3 l limit. l i 4 I l STA  % POWER oTHER STATUS OSO RY DISCOVERY DESCRIPTION 32 i s

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TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE

SUPPLEMENTAL INFORMATION FOR LER NP-33-83-03 DATE OF EVENT

January 15 and 18, 1983 FA,CILITY: 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 NWE) = 0 Description of Occurrence: On January 15, 1983 after a reactor trip, the 1 specific activity of the primary coolant exceeded the Technical Specifica-tien 3.4.8 limit of 1.0 pCi/gm Dose Equivalent I-131. The level peaked at 2.67 pCi/gm at 2004 hours0.0232 days <br />0.557 hours <br />0.00331 weeks <br />7.62522e-4 months <br /> 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 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.755305e-4 months <br />.

On April 9, 1983, at 0420 hours0.00486 days <br />0.117 hours <br />6.944444e-4 weeks <br />1.5981e-4 months <br />, following a power reduction to repair a 1

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 hours0.00718 days <br />0.172 hours <br />0.00103 weeks <br />2.3591e-4 months <br /> on April 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 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />.

Date Time Reactor Power 1/14/83 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 99.4%

1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> 99.5%

1/15/83 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> 98.7%

1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> TRIP On January 18, 1983, reactor power was approximately 100% until a reactor / turbine trip at 1925 hours0.0223 days <br />0.535 hours <br />0.00318 weeks <br />7.324625e-4 months <br />.

l l

Date Time Reactor Power 1/16/83 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> 84.3%

l 1/17/83 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 87.3%

! 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> 97.9%

1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> 99.2%

l l

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TOLED0 EDIS0N COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-83-03 PAGE 2 1/18/83 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 99.3%

0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> 99.4%

1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> 99.6%

1925 hours0.0223 days <br />0.535 hours <br />0.00318 weeks <br />7.324625e-4 months <br /> 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%

1 4/9/83 0100 48.5%

0700 6.4%

1600 21.7%

2400 42.0%

4/10/83 0300 79.8%

0345 TRIP Fuel Burnup By Core Region: See attached computer printout.

Cleanup Flow History 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 January 16, 1983 - 109 gpm January 17, 1983 - 101 gpm January 18, 1983 - 60 gpm I April 7, 1983 - 60 gpm

, April 8,1983 - 69 gpm l

1 April 9,1983 - 93 gpm April 10,1983 - 95 gpm l There was no degassing operation.

Table 1 lists the specific activity analysis, the time duration the l specific activity exceeded the Technical Specification, and the l 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. -

l

TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-83-03 PAGE 3 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 I

until it dropped below the Technical Specification limit of 1.0 pCi/gm.

Since iodine spikes are typical following a power change, no additional corrective action is applicable.

Failure Data: Previous occurrences of the RCS dose equivalent I-131 er.ceeding 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 i

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TABLE 1 l

Approximate kb ONdg Time Duration *-

Date of Specific Activity Analysis Tech Spec Level Maximum Level 4o Activity (pci/gn) .

3g Occurrence Date Time Dose Equivalent I-131 Exceeded pCi/gm fgy January 15, 1983 "z@

1/15/83 0810 0.17 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> 2.67 ggn 2004 2.67 gCo 2155 2.54 gg4 2.33 amb 1/16/83 0102 go 0400 2.40 zh 0730 1.59 g, 0930 1.58 po y 1330 1.14 ea 1730 0.73 $g January 18, 1983 1/18/83 1354 0.14 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1.39 h 2301 1.39 y8 1/19/83 0256 1.11

$0 gm 0645 0.81 w April 9, 1983 4/8/83 1207 0.09 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> 1.39 4/9/33 0420 1.06 0806 1.37 1 1145 1.39 1531 0.96 April 10, 1983 4/10/83 0130 0.41 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> 1.95 0620 1.95 1002 1.82 1341 1.31 1710 1.30 2110 0.89

TO c.D0 EDISON COMPANY .

DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-83-03 PAGE 5 FUEL BURNUP BY CORE REGION FOR JANUARY 15, 1983 AND JANUARY 18, 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 are given in Megawatt Days -

• x 10 Metric Ton FUEL ASSEMBLIES

• rm l : A :i .e 2154?E+U1 3551*E+01 37h0?E+01 354caf+01 27457E+01 ?917?E+01 39053E+01 1 through 7 11194E+02 P2218E+02 17617E+02 22230E+0? 11193E+0? 38853E+01 ?H741E+01 8 through 14 15450E+b2 4513SE+01 2 4701E + 0? P4023E+32 ISS1?L402 15337E+0? 15S20f+02 15 through 21 23979E+b2 ?S082f+02 44478L+01 13904E+02 294H7L+01 45411E+01 2610 6 t. + 0 2 --22 through 28 14377E+02 1547bC+02 16534E*0? $1114L+01 16536E+02 15474E+02 19349E+02 29 through 35 20059E+02.44299E+01 28539L+01 39650E+01 2bl44E+0? 14499E+02 24406E+02 36 through 42 12306f+02 27081E+02~?all2E+02 27098f+02 12?96E+02 243f8E+02 14431E+02 -43 through 49 24681E+02 3H423L+01 27937E+01 11046E+0? 2'667E+02 15591E+92 12185E+02 50 through 56 13653E+02 26?36E+02 13941 t:+ 0 2 26236E+02 13H44E+02 121S7E+02 15551E+02 57 through 63 z3477E+02 10931L+02 270n4E+01 3SH37E+01 22635E+0? 15195E+0? 16319t+0? 64 through 70 27439E+02 26967E+02 13db1E+02 22297E+02 13566E+02 26989E+02 27494E+02 71 through 77 16303E+U2 15143E+02 22564E+02 34890E+01 37867F+01 17817E+02 15302r+02 78 through 84 50180E+01 PH009E+02 13HbHf+02 ??27?E+0? 15965f+0?-22?94E+0? 13917t+0? through 91 2h070L+02 5 0 4 64 E + 01 15290f+02 17769E+0? 37149E+01 35332E+01 22574E+0? 92 through 98 Id124C+ud 16265E+02 27458E +02 26941L+02 13520E*02 22247E+3? 13530E+0? 99 through 105 2e98 7E+ 0? 27506E+02 16310t+02 15137L+02 22563E+02 34h42E+01 2 7 24 4 t + 01 - --106 through 112 19929L+02 23423L+02 IS50HE+02 12086E+0? 13168f + 02 ? 6177E + 02 13R78E+02 113 through 119 26153E+b2 13790E+02 12141C+02 15548E+02 23476E+02 10917E+02 26961E+01 120 through 126 3Ha57E+01 25225E+02-14377t+0? 24304E+02 ! ??3 ?E +0 2 27 020E + 02 28 035 t + 02 -127 through 133 2 t.9 3 H f + 0 2 1219HE+02 24330E+02 14401E+02 25009E+02 382?hE+31 28543E+01 134 through 140 44076L+01 26031E+02 14309E+02 15442E+GP 16491L*D2 50159L+01 16460E+02 141 through 147 IS9?3E+02 19 297E +02-2h0? b E + 02 4 4 0 th l E + o t 2H479f+D1-13399E+0? 4 4 26 0 E + 01 -148 -through 154 24 797E + 02 23939E +02 15484E+02 lb300E+02 15461L+02 23929E*02 25181E+02 155.through 161 44202L+01 13398E+02 28705E+01 38691E+01 11172E+0? 22207E+02 17793f+02 162 through 168 22196E+02 11163E+02-3860HE+01 28678E+01 2 7 3 5 7 E+ 01--35 2 9 9 E + 01 - 3 7 67 3 f + 01- -169 through- 175 3b331E+01 27324E tqL 176 through 177

• AS READ FROM LEFT TO RIGHT

w

. TOLEDO EDISON COMPANY ,

DAVIS-BESSE NUCLFAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-83-03

PAGE 6 i

! 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 nusber.

)- For the location of the assemblies, see the attached core map. Units are given in Megawatt Days x 10

~

Metric Ton FUEL ASSEMBLIES

• 44936E+01.57712E+01 61204E+01 57816E+01'[44983E+01 47002E+01 62491E+01 1 through 7 13825E+02 24556E+02 20118E+02 24577C+02.13846E+02 62568E+01 46772E+01 , 8 through 14 14713E+02 72375E+01 26855E+02 26354E+02 18153E+02 17396E+02 18151E+02 15 through 21

'2

$6274E+ 02 27256E+02 71974 E+01 14675E.+02. 4 734 7E+01 72681E+01 28439E+02 22 through 28 17058E+02 17350E+02:18727E+02 82091E+01 18736E+02 17362E+02 17048E+02 29 through 35 28404E+02 71681E+01 46475E+01>63162E+01)27311E+02 17281E+02 26992E+02 36 through 42 15293E+02.29397E+02 30291E+02 29426E+02i15294E+02 26988E+02 17246E+02 43 through 49 26851E+02 61934E+01 45356E+01 13502E+02'26025E+02 17535E+02 15060E+02 50 through 56 i

16763E+02 28583E+02 16523E+02 28587Et02.16764E+02 15046E+02'17502Et02 57 through 63 25777E+02.13386E+02 44434E+01.57979E+01 24898E+02.17628E+02 18349E+02 64 through 70 29679E+02 29402E+02 16332E+02 25019E+02i16342E+02 29437E+02 29779E+02 71 through 77 18341E+02.17580E+02 24849E+02 56999Et01i61106E+01 20082E+02 17341E+02 78 through 84 80721E+01 30159E+02 16454E+02.24963E+02118336E+02,25018E+02 16495E+02 85 through 91 30239E+02 81254E+01 17337E+02 20037E+02 60362E+01 57401E+01 24829E+02 92 through 98 i

17527E+02 18289E+02 29756E+02 29373E+02'16287E+02 24966E+02 16304E+02 99 through 105 j 29412Et02 29815E+02.18349E+02.17571E+.02124823E+02 56923E+01 44577E+01 106 through 112 13373E+02 25665E+02 17444E+02 19955E+02316671E+02 28517E+02 16454E+02 113 through 119 28498E+02 16730E+02 15031E+02 17518E+02(25773E+02 13367E+02.44283E+01 120 through 126 3

61737E+01'27403E+02 17149E+02 26882E+D21.15190E+02 29310E+02 30204E+02 127 through 133 1 29186E+02 15187E+02'26919E+02 17183E+02)27172E+02 61634E+01 46353E+01, 134 through 140 i

71281E+01 28340E+02 16992E.+02 17318E+02 18659E+02 81061E+01 18628E+02 141 through 147 i 17278E+02.16983E+02 28363E+02n71310E+01c46315E+01 19663E+02 71529E+01 148 through 154 I

26980E+02 26271E+02 18128E+02 17356E+02518105E+02 26259E+02 27341E+02 155 through 161 71503E+01 14641E+02 46628E+01 62239E+41(13791E+02.24550E+02 20071E+02 162 through 168 24538E+02 13803E+02 62159E+01 46581E+01h44822E+01 57618E+01 61114,E+ 01 169 through 175 57592E+01 44776E+01 176 through 177 i' -

• AS READ FROM LEFT TO RIGHT 4

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. - TOLEDO EDISON COMPANY ~

DAVIS-BESSE NUCLEAR PdWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-83-20 i

PAGE 7 l

March 18* 1982 DAVIS-BESSE UNIT 1. CYCLE 3 I

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