8
NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7 77) | , LICENSEE EVENT REPORT ] .. . . , g CONTROL BLOCX: | | | | | | |h (PLEASE PQlNT OR TYPE ALL REQUIRED INFORMATION) , 1 6 10 | 1 | | G| A| E | I | H| 2 |@l 0 | 0 | -| 0 | 0 | 0 | 0 | 0 | - | 0 | 0 |@| 4 | 1 | 1 | 1 | 1 |@| | |@ 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE JO 57 CAT 68 CON'T 10111 $ "c' | L }@|0 | 5 | 0 | 0 | 0 | 3 | 6 | 6 |@| 1 | 2 l 0 | 6 | 8 | 2 |@| 0 | 1 | 0 | 4 | 8 | 3J@ 7 8 60 61 DOCK ET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 3J EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h 10!2]lOn 12/6/82, with Unit 2 in hot shutdown following a reactor trip, an I g | isotopic analysis for Iodine was performed per T.S. Table 4.4.5-1, item | P I41|4c. The analysis revealed the specific activity of the reactor coolant i 10Isl|to be approx. 0.357 micro-curien per gram dose equivalent I-131, which 1 10161| exceeded the T.S. 3.4. 5 (a) limit. Plant operation was not affected. The i 10171 lhealth and safety of the public were not affected by this non-repetitive | 10 IR 1 levent. I 80 7 8 9 C E CODE SUBCO E COMPONENT CODE SUB ODE S ODE , [ o_loj |R |C |@ | X|@ | Z |@ | Z | Z | Z | Z |Z | Z l@ ]@ [Zj @ ' 7 8 9 10 11 12 13 18 19 20 ,_ SE QUE NTI AL OCCURAFNCE REPORT REVISION LER E'VEN T YE A R REPORT NO. CODE TYPE N O. @ R3Pg'nO |8|2| |_| |1|3|7| | ,, - | |0 |3 | y [._.] g _JI 22 13 24 26 27 N a 30 31 J2 TAK f ACT 0 4 PL NT a T HOURS 22 S8 IT D FOR B. SUPPLI R MANUF CTURER [X J g y g |35Z|g W@ |0|0|0| | g g g g [Z g |X|9|9|9|g 3J '* 36 31 40 41 42 43 44 47 CAUSE DtSCRIPTION AND CORRECTIVE ACTIONS h E~iTil IThe cause 4f the high reactor coolant activity has been attributed to a | 1i ileaking fuel rod. Sampling and analyses were performed every four hoursi |,|2| |per T.S. Table 4.4.5-1, item 4.b, until the reactor coolant activity wasi y |within limits on 12/8/82. Two four-hour samples were missed due to pro- | ii |4 | |graming error in the lab computer. The software has been corrected. | 1 8 9 80 STA 5 % POWER OTHER STATUS IS O RY DISCOVERY DESCRIPTION l ' I S I [Gj@ l 01 01 0|@| NA | |_C_|@| Reactor Water Analysis | ' " ' ' " * A HVITY CC YENT AMOUNT OF ACTIVITY @ I nrLE ASED OF RELE ASE LOCATION OF RELEASE Ii 16 I LzJ @ la_l@l NA I m I 7 8 9 10 11 44 45 80 6'C RSONNE L E XPOGUH ES NUMSER TYPE DESCRIPTION i 1010101@LZ_]@l NA | i 7 ' '' * ' " ' PE n >ONN J' ,~;U,!, E S otSCniPTiON@ Nu mn 1010101@l NA | i a 7 8 9 11 12 80 TOSS OF OH DAMAGE TO FACILITY TYPE DE SCn t P TION La.1@l m I i 9 7 8 9 10 80 costiCn v g3 0301170325 830104 - Ngc t.SE ONLY PDR ADOCK 05000366 issue n@| DESCRIPTION U [yj NA S PDR | |||1||11IIlll:i 2 o 7 8 9 to 68 69 80 E S. B. Tipps pggggj m ) E 4 51 g NAME OF PREPARER

NRC FORM 366 .. LICENSEE EVENT REPORT |h · 10111 $ "c' | L }@|0 | 5 | 0 | 0 | 0 | 3 | 6 | 6 |@| 1 | 2 l 0 | 6 | 8 | 2 |@| 0 | 1 | 0 | 4 | 8 | 3J@ 7 8 60 61 DOCK ET NUMBER 68 69 EVENT

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Page 1: NRC FORM 366 .. LICENSEE EVENT REPORT |h · 10111 $ "c' | L }@|0 | 5 | 0 | 0 | 0 | 3 | 6 | 6 |@| 1 | 2 l 0 | 6 | 8 | 2 |@| 0 | 1 | 0 | 4 | 8 | 3J@ 7 8 60 61 DOCK ET NUMBER 68 69 EVENT

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION(7 77) |,

LICENSEE EVENT REPORT ]...

. ,gCONTROL BLOCX: | | | | | | |h (PLEASE PQlNT OR TYPE ALL REQUIRED INFORMATION),

1 6

10 | 1 | | G| A| E | I | H| 2 |@l 0 | 0 | -| 0 | 0 | 0 | 0 | 0 | - | 0 | 0 |@| 4 | 1 | 1 | 1 | 1 |@| | |@7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE JO 57 CAT 68

CON'T

10111 $ "c' | L }@|0 | 5 | 0 | 0 | 0 | 3 | 6 | 6 |@| 1 | 2 l 0 | 6 | 8 | 2 |@| 0 | 1 | 0 | 4 | 8 | 3J@7 8 60 61 DOCK ET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 3J

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h10!2]lOn 12/6/82, with Unit 2 in hot shutdown following a reactor trip, an I

g | isotopic analysis for Iodine was performed per T.S. Table 4.4.5-1, item |

P I41|4c. The analysis revealed the specific activity of the reactor coolant i

10Isl|to be approx. 0.357 micro-curien per gram dose equivalent I-131, which 1

10161| exceeded the T.S. 3.4. 5 (a) limit. Plant operation was not affected. The i

10171 lhealth and safety of the public were not affected by this non-repetitive |

10 IR 1 levent. I80

7 8 9

C E CODE SUBCO E COMPONENT CODE SUB ODE S ODE ,

[ o_loj |R |C |@ | X|@ | Z |@ | Z | Z | Z | Z |Z | Z l@ ]@ [Zj @ '

7 8 9 10 11 12 13 18 19 20

,_ SE QUE NTI AL OCCURAFNCE REPORT REVISION

LER E'VEN T YE A R REPORT NO. CODE TYPE N O.

@ R3Pg'nO|8|2| |_| |1|3|7| | ,, - | |0 |3 | y [._.] g_JI 22 13 24 26 27 N a 30 31 J2

TAK f ACT 0 4 PL NT a T HOURS 22 S8 IT D FOR B. SUPPLI R MANUF CTURER

[X J g y g |35Z|g W@ |0|0|0| | g g g g [Z g |X|9|9|9|g3J '* 36 31 40 41 42 43 44 47

CAUSE DtSCRIPTION AND CORRECTIVE ACTIONS hE~iTil IThe cause 4f the high reactor coolant activity has been attributed to a |

1i ileaking fuel rod. Sampling and analyses were performed every four hoursi

|,|2| |per T.S. Table 4.4.5-1, item 4.b, until the reactor coolant activity wasi

y |within limits on 12/8/82. Two four-hour samples were missed due to pro- |ii |4 | |graming error in the lab computer. The software has been corrected. |

1 8 9 80

STA 5 % POWER OTHER STATUS IS O RY DISCOVERY DESCRIPTION

l ' I S I [Gj@ l 01 01 0|@| NA | |_C_|@| Reactor Water Analysis |' " ' ' " *

A HVITY CC YENT

AMOUNT OF ACTIVITY @ InrLE ASED OF RELE ASE LOCATION OF RELEASE

Ii 16 I LzJ @ la_l@l NA I m I7 8 9 10 11 44 45 80

6'C RSONNE L E XPOGUH ESNUMSER TYPE DESCRIPTION i

1010101@LZ_]@l NA |i 7' '' *' " '

PE n >ONN J' ,~;U,!, E S

otSCniPTiON@Nu mn

1010101@l NA |i a

7 8 9 11 12 80TOSS OF OH DAMAGE TO FACILITYTYPE DE SCn t P TION

La.1@l m Ii 9

7 8 9 10 80costiCn v g3 0301170325 830104- Ngc t.SE ONLY

PDR ADOCK 05000366issue n@| DESCRIPTION U[yj NA S PDR | |||1||11IIlll:i2 o

7 8 9 to 68 69 80 E

S. B. Tipps pggggj m ) E 4 51 gNAME OF PREPARER

Page 2: NRC FORM 366 .. LICENSEE EVENT REPORT |h · 10111 $ "c' | L }@|0 | 5 | 0 | 0 | 0 | 3 | 6 | 6 |@| 1 | 2 l 0 | 6 | 8 | 2 |@| 0 | 1 | 0 | 4 | 8 | 3J@ 7 8 60 61 DOCK ET NUMBER 68 69 EVENT

r.

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*.. ,

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LER #: 50-366/1982-137Facility: Edwin I. HatchLicensee: Georgia Power CompanyDocket #: 50-366

Narrative Reportfor LER 50-366/1982-137

On December 6, 1982, following a reactor trip, an isotopicanalysis for Iodine revealed the reactor coolant activity wasapproximately .357 micro-curies per gram DOSE EQUIVALENT I-131(DEI-131), reference Deviation Reports 2-82-305 and 2-82-307.This is contrary to Technical Specifications 3.4.5.a. Thereactor coolant activity exceeded 0.2 micro-curies per gramDOSE EQUIVALENT I-131 for a period of 34 hours during theevent. Results of the isotopic analyses are included asAttachment 1 to this report. Technical Specifications 3.4.5,Action 2b was violated when the required analyses were notperformed at 4 hours, and again at 8 hours into the event,reference Deviation Report 2-82-306. The health and safetyof the public were not affected by this non-repetitive event.

The cause of the high reactor coolant activity has been attributedto the leakage of a fuel rod. At 0745 on 12/7/82, the activitylevel returned to within limits; therefore, the 4-hour samplingwas terminated. At 1700 on 12/7/82, the reactor coolant activitywas found to be 0.789 micro-curies per gram DEI-131. Samplingand analysis every four hours was performed until 12/8/82 at1715 when reactor coolant activity returned to within limits.Additional information required per Technical Specifications 3.4.5,Action b.1 is included as Attachment 2 to this report.

The failure to perform isotopic analyses in two cases was due toan error in the computer software. The computer is designed toindicate when a limit is exceeded; however, the printout on the,

initial analysis indicated "No Tech. Specs. Limits Were Exceeded."The software was modifful to reflect the correct limits, andsubsequently to inform laboratory personnel to perform additionalsampling and analyses. The reactor coolant was assumed to begreater than Tech. Specs, limits of 0.2 micro-curies / gram perDEI-131 for the 8 hours of missed sampling in order to assure thelimiting conditions for operation pertaining to Tech. Specs.3.4.5 would not be violated.

.- - ___ _

Page 3: NRC FORM 366 .. LICENSEE EVENT REPORT |h · 10111 $ "c' | L }@|0 | 5 | 0 | 0 | 0 | 3 | 6 | 6 |@| 1 | 2 l 0 | 6 | 8 | 2 |@| 0 | 1 | 0 | 4 | 8 | 3J@ 7 8 60 61 DOCK ET NUMBER 68 69 EVENT

_ - - -

.

. ';.

.

.

ATTACHMENT 1

for LER 50-366/1982-137

Date Time- me/Ygay

micro-Ci/gm. Above Limit.

12/6/82 2015 .357 2 hours12/7/82 0015 * 6 hours12/7/82 0415 * 10 hours12/7/82 0745 .023 14 hours12/7/82 1700 .3743 14 hours12/7/82 2100 .7888 18 hours12/8/82 0100 .214 22 hours12/8/82 0500 .197 26 hours12/8G- 0900 .2447 26 hours12/8/82 1300 .221 30 hours12/8/82 1715 .169 34 hours12/8/82 2115 .0596 34 hours

* Samples were not taken.

_ ______,

Page 4: NRC FORM 366 .. LICENSEE EVENT REPORT |h · 10111 $ "c' | L }@|0 | 5 | 0 | 0 | 0 | 3 | 6 | 6 |@| 1 | 2 l 0 | 6 | 8 | 2 |@| 0 | 1 | 0 | 4 | 8 | 3J@ 7 8 60 61 DOCK ET NUMBER 68 69 EVENT

_ .

;,

.

.

.

T

ATTACHMENT 2.

for LER 50-366/1982-137

1. REACTOR POWER HISTORY

An approximate reactor power history is summarizedin the table below.

PERIOD REACTOR POWER

Prior to 12/5 @ 1300 100% rated ( 2436 MWt)

12/5, 1300 to 1600 Reactor power reduced to 50%

12/5, 1600 to 2300 Rx power varied -(1180 to 1250 MWt),

! 12/5, 2300 tRx power increased to 65%

12/6, 1500 to 1806 Rx power varied (1450 to 1590 MWt)

12/6, 1806 Rx tripped Rx tripped at approximately 1500 MWt.

12/6, 1806 tRx power at 0%12/8, 1400

2. Fuel burnup as of December 1, 1982, by fuel bundle isprovided at Attachment 3 to this report.

3. Clean-up flow remained at approximately 100gpm until 12/6/82at 1806 when a reactor trip resulted in the isolation of the

i RhCU system. On December 7 at 0619 the RWCU system was returnedto service.

4. Off-gas level history is summarized in the table below:

Date/ Time Off-gas Level (micro-Ci/sec)

12/4 1400 18,690.

2230 19,224j 12/5 0728 20,559t 1400 24,670

2230 12,01512/6 0600 9,759

1400 11,7752230 downscale

, 12/7 0600 downscale

) 1400 downscale

._ , _ - , . . _ . . _ . _ _ _ _ - _ _ _ _ _ _ _ . ._ _ _ .__ _ . _ - .

Page 5: NRC FORM 366 .. LICENSEE EVENT REPORT |h · 10111 $ "c' | L }@|0 | 5 | 0 | 0 | 0 | 3 | 6 | 6 |@| 1 | 2 l 0 | 6 | 8 | 2 |@| 0 | 1 | 0 | 4 | 8 | 3J@ 7 8 60 61 DOCK ET NUMBER 68 69 EVENT

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Page 6: NRC FORM 366 .. LICENSEE EVENT REPORT |h · 10111 $ "c' | L }@|0 | 5 | 0 | 0 | 0 | 3 | 6 | 6 |@| 1 | 2 l 0 | 6 | 8 | 2 |@| 0 | 1 | 0 | 4 | 8 | 3J@ 7 8 60 61 DOCK ET NUMBER 68 69 EVENT

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Page 7: NRC FORM 366 .. LICENSEE EVENT REPORT |h · 10111 $ "c' | L }@|0 | 5 | 0 | 0 | 0 | 3 | 6 | 6 |@| 1 | 2 l 0 | 6 | 8 | 2 |@| 0 | 1 | 0 | 4 | 8 | 3J@ 7 8 60 61 DOCK ET NUMBER 68 69 EVENT

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Page 8: NRC FORM 366 .. LICENSEE EVENT REPORT |h · 10111 $ "c' | L }@|0 | 5 | 0 | 0 | 0 | 3 | 6 | 6 |@| 1 | 2 l 0 | 6 | 8 | 2 |@| 0 | 1 | 0 | 4 | 8 | 3J@ 7 8 60 61 DOCK ET NUMBER 68 69 EVENT

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e 4 c1 g a c . r =4 F P +1

P' % f.

F'e- - P ti = ,a *a fi f &' 4*

P W w a C 9 9. % C 4 C % M e== 4 P' ti f* t. P' F P f P == F f .

C e ea w - e. = *

4 G @ c , a y y r, c. t. == a t.

t< f4 r Y r, 6 e e t' i M r F P f.

6- o- r c c u" g f. F. e y f, P t' d *

2 ^

@ e< ti w. J C w fd e- 1 V f-J

J se e. m == .- e ei e. en e- ei

na

[d 4 * S1 e- V y e w e' t 4% W f f 9 ( *d e- 9"' *2 0 @ == WG w P- W fd I wa P, J F P. == re P *

e- &,< ,. .d c,d. en eW P1 P W e 9- F 1 f

a =

[ In kl I @ ( [ 9 1 P< YP 10 F t< 40 9 G .a P', a= 1 @ f'

*- F P< e f* d e fi j g W e ey'

d.- em - - e.i C. e ,. .GJ em t t< .a C

e . . .=

$<

e C h (1 s' t< r f ei P *a *=

- P1+-

ei f< P y G << , e t.

2*

P' b t' P. 4 1 e e P' 4 P*

w

L. P< P1 ei P == P P e C< Gb. . e= t.w.*I2

r t, c h d as .- <J e' P. c? P cJ P9 e - . ri e' F t. F S

J G g C, e' J 1 P F 4 4P' P. =a 4. f'" t< t G b b

** en e- e. e- e.

Ce e-

f4 el @ $ <

d P. P. C F.(e 4 Y Y

'O4

C f. iJ A P t-

40 <=JIn *<P *a

s' mP'e-

c, 4 W Ge F P e= C f5 f F<

= == o= o- * .= aw

A

in r *' *'

f, h t.

e= a ri fi e- Pj M W J F 4 E 4 a Fi an. P' F F f. F .i e e gi P CJ Wi O 4 4I en sa +< += w e-

(4s=

hE., d'"

.= dd4

mP' h e @ fi ~ L

C2

f Q t' F W eS,

=d d & 6, . u C s r. o

@ f & F F Gw e k

c

* r e C C >

| te f t' fd C w - es, 2

et M C C u9 <J

(s. A M P W h >en, en m o< em o= V

jf 431

31>

# di

f'd g h e m =J g h C $ 'd 1 fi Ch h (4 eg == m e= e em 2

ie

'

( ( ( ( t (. C C C 9 9 0 ) ) ) ) ) ) ) ) -) )

,

d

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