05000302/LER-1981-036-03, /03L-0:on 810618,during Reactor Coolant Sampling, Primary Coolant Dose Equivalent I-131 Exceeded Tech Spec Limits.Caused by Leaking Fuel or Tramp U & Anticipated Dose Equivalent Iodine Transient Following RCS Transient
| ML20009F030 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/15/1981 |
| From: | Hernandez V FLORIDA POWER CORP. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20009F024 | List: |
| References | |
| LER-81-036-03L, LER-81-36-3L, NUDOCS 8107280617 | |
| Download: ML20009F030 (31) | |
| Event date: | |
|---|---|
| Report date: | |
| 3021981036R03 - NRC Website | |
text
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r. i. :::::.3 At 1155 on 6/18/81, at 0450 on 6/27/81, and at 0930 on 7/1/81 during Reactor Coolant
- -.-- i sampling, it was. discovered that primary coolant Dose Equivalent I-131 exceeded the
, limit of T.S. 3.4.8.
Redundancy NA.
There was no effect upon the health or safety ofJ the gederal public.
These are the twenty-first, twenty-second and twenty-thi d events
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C.~iii=,l The cause of tfie events is attributed to leaking fuel or " tramp uranium" (i.e., uranip
- aus1:ts:xime:u n:::xa ncnvi:.c :c.:s Q1;
!,i j [ um in the cladding within <me recoil radius of the surface) and an anticipated Dose,
,., t. Equivalent Iodine transient following a Reactor' Coolant Syst.es transient.
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I purification flow was increased; Dose Equivalent I-131 was less than 1.0 microcuries,
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per gram at 0130 on 6/19/81, at 0357 on 6/28/81, and at 1350 on 7/1/81.
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SUPPLEMENTARY INFORMATION
- - Report No.:
50-302/81-036/03L-0 Facility:
Crystal River Unit ?
Report Date:
July 15,1981 Occurrence Date:
June 18, 1981 Identification of Occurrence:
Primary Coolant Dose Equivalent 1-131 was greater than 1.0 microcuries per gram contrary to Technical Specification 3.4.8.
Conditions Prior to Occurrence:
Mode 1 (power operation 97%)
DAscription of Occurrence:
At 1155 after Reactor startup, it was discovered that Dose Equivalent I-131 exceeded 1.0 microcuries per gram. At 0450 on June 27, 1981 after a Reacror trip and again at 0930 on-July'1, 1981 after a Reactor trip, it was discovered that Dose Equivalent I-131 exceeded l'.0 microcuries per gram.
Designation of Apparent Cause:
The cauce_of these events is attributed to leaking fuel or
" tramp urrsium" (i.e., uranium in the cladding within one recoil radius of the surface) and an anticipated Dose Equiva-lent Iodine t ransient following a Reactor Coolant System tran-sient.
Analysis of Occurrence:
There was no effect upon the health or safety of the general public.
Corrective Action
The Reactor Coolant System flowrate through the Makeup and Purification System was increased.
Dose Equivalent I-131 was determined to be less than 1.0 nicroc.uries per gram at 0130 on June 19, 1981, at 0357 on June 28,'1981 and at 1350 on July 1, 1981. We are also conducting an evaluation to determine if failed fuel is present.
Failure Data:
These are the twenty-first, twenty-second, and twenty-third events reported under this Specification.
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Zaac:c Power Eistory of Prior
?orry-eight Ecurs Item I
(
Ivent Daca:
6/27/81 I
N 4
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DATE 6,25,81 [I. O
=1 HUUR GMWE TURB G PWTH NI RATIO RATIO E
E7-1-0-)
' T8564 ff9559
- F-7-2 3 '
i!I, ;;T*
l1 ERIT W *e5@$
1_7
/aFP BTU /KWH o/aFP o/aFP o/aFP
=/*FP
-+
,'T 4 1
9o.26 10125 79.84 100.00 1.002
.964 2 - --9 6. -2 6 10-125 9-9 rB4 1410--O O 1.30-2
.964 7----
3 96.26 10125 99.84 100.00 1.002
.964 I'1 4
96.26 10125 99.34 100.00 1.002
.964 t
3 --96.-26 19-1-2-5 o?.2" 1- & 0 1.40-2
.o6" 7-6 96.26 10125 99.84 100.00 1.002
.964
(..c5 7.
96.26 10125 99.84 100.00 1.002
.964 9
96.26 i n i, c:
oo mt inn on 1 no' o gtt 5
9 96.26 10125 99.84 100.00
'1.002
.964 f.rE 10 96.~ 53 10125 99.92-100,30 1.004:
.966 n.-
1-1 e. o.r-s.o 4 n.,,~.-
m -
n nn~
- - n ee n
<nn e r,. -
.... ~
s _.
m 12 96.49 10141 100.04 100.30 1.003
.965 f t 2 13 96.50 10147 100.08 100.40 1.003
.964
..r 4.
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. n. 4. e,_
00 -.
t 4
.nn.-.
- 4.. n Le o, z.,
4 n
.m L
- - i-15 95.42 10134 98.82 99.60 1.00S
.966
( r.{
16 95.72 10132 99.10 99.70 1.006
.966 g
1.-.
ge --
t g_i n g ee n,
30 en 4
ny mm N
18 95.51 10141 99,31 100.00 1.007
.965 (f H 19 95.74 10132 99.14 99.80 1.007
.966 2
- - 20 95-,-8-0 1-01-1-5 00 02 00 50 1.003 of' i
21 95.50 10117 99.06 99.60 1.005
.967
+.weare-ee 53 22 96.50 10102 99.67 100.10 1.004
.968 J
- -23 06-57 1-0-1-42 oo."1 ISO
- n 90" o5S U
24 96.61 101799 99.T1 100.10 1.004
.969
'/ ~~
/
AVERAGE DAILY GENERATOR GROSS 822,30 MWH(E)
A V E R A G E--D A-IL Y THERMAL ROuEP 2 W.-G 7-->1 W H ' "
/VERAGE DAILY TURBINE GROSS HEAT RATE 1012T BTU /KWH
.T A'/ERAGE' DAILY NWTH POWER 99.628 */oFP
' - -- A V E R A G E-D A Iin-NU C LE A R-I-NS-T r-FOW ER 1 0-O d 0-0
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, - R A T-I O--OF N-I-T HW T: !
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(., 3 DATE 6,26,81 L.
(.~
HOUR GMWE TURB G MWTH-NI'
' RATIO
' R AT I'0 -
[
(E7_1.01 (T956Y (P753Y (P723)
NT/MT MF/MT T
a/aFP BTU /KWH a/aFP a/aFP a/aFP a/aFP
( -3 1
96.55 10098 99.67 100.00
- - 1.003
.969
~
_ 2.___9_6s_6 2 10099 99.76 99.90 1.001~
._969 3'
96.58 10102 99.80-
- - 100.10-1.003
.968
($
4 96.58 710102
- 99.80
- - 100.20 1.004
..968
- s
.,_5-96.59 10n99 o9.7A 1nn.1n
.t i n n, oAn MW Mi 6
96.62 10097 99.80 100.10 1.003
.968
(~ $
7 96.62 10096 99.76 100.10' 1.003
.969 L
_1 94 57 10097 9.9.71 100.10 1.004 069 li -
9 96.64 10087 99.71-100.10
- - 1.004
.969
(-
10 96.62 10096
.99.80
' 100.10 1.003
.968' 7
._1.1 __ _.9 6_ 6 4 10103
- - 99/98 - 100.20 1:003-Joss -
12 96i64 10108 99.92 100.30 1.004
.967
( '$
1-3 96.65 10115 100.00 100.50 1.005
.967 E
14 96.47 19130 99.96 100.50 1.005 065
'l 15 96.26 110150
- 99..96 l00.40
- 1'. 0 0 4; J9631
~
($
16 95.71-
~ 10155
~ 99,39
= 100.00-T.0061_
.963 4
TF 1 ~[
95J8 10161 99.35
'99i90:
S E 0 0~6
.962 "
2 it 18 94.97 10131 98.33 99.20 1.009
.966
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~-- ( 3 19 95.65 1008S 98.61 99.30 1.007
.970
~
~E 10 95.65 10095 98.65 99.30 1i007
,970 s:
. 4 21 95.74 10090 (98.74 99.50
~1.008
- . 970.
c$
22 96.18
- - 10084 99.10
- 99.30
- - 1.007
.970
- -. m ~
r 5
23 94.9R 10090
'99.19 90.90 1 lnn?
.'o71
'~ ~
5 24 48.18 10075 49.59-99.90 2.014
.971-tha
.2 v=WU AVERAGE DAILY GENERATOR GROSS
'806.06'MWH(EL
- - wasAnmcM R
AVERAGr nArt y THFRMAl. PnUFR MAA A7 MUEl f T) 6 AVERAGE DAICY. TURBINE GROSS HEAT RATE 10106 BTU /KWH l
C$
AVERAGE DAILY MWTH POWER 97.426 */aFP AVERA.GE__DAI.LY NUCLEAR _IlGT. POWER 99.079 a/=FP y
=.
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RATIO._OF_Jg r Tn fiwIH _= 1 n?A L !.
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DATE 6.27,81
(-.
HOLIR GMWE TURB G MWTH NI RATIO RATIO
( --
(E710)
(TG36)
(P753)
(F723)
NI/MT ME/MT
~
- /aFP BTU /KWH
- /oFP a/aFP._
- /=FP _
a /_o F P 4
1 54.41-0 83.65 S1.80
.978
.650
('t 2
0.09 0
.00 0. . 0 0.000 0.000 T
3 0.00 0
00 0.,, 0 0.000 0.000
- WM 4
4 0.00 0
.00 0,00 0.000 0.000 (M
5 0.00 0
.00 0.00 0.000 0.000
~~.
6
- 1.00 0
.00 0.00 0.000 0.000 7
0.00 0
.00 0.00 0 000 0.000 (3
8 0.00 0
.00 0.00 0.000 0.000 9
0.00 0
.00 0.00 0.000 0.000 10 0.00 0
.00 0.00 0.000 0.000
(~ =;f 11 3.06 62818 12.40 16.30 1.315
.408 12 20.56 13858 26.14 29.70 1.136
.787 13 20.74 12443 2ti.06 29.20 1.214
.862 f
14 22.55 12250 25.98 31.40-1.209
.868
(' T-15 31.36_
11524 3u.. c 5 41.30 1.182
.897-2 16 39.3G 10853 43.31 30.90 1.175
.921 h
17 59.67 10141 61.91 70.30 1.136
.964.
(~ 2 18 63.77 9914 64.9<
<4.10 1.141
.982
(
Z 19 69.11 9799 69.70 77.80 1.116
.992
(- :i 20 30.28 9707 80.14 86.60 1.081 1.002
~;
21 90.34 9713 90.05 94.80 1.053' 1.003 5
2'2 91.16 9693 90.58 94.40 1.042 1.006
($
23 73.74 9759 74.23 80,00 1.078-
.994 7
24 67.46 9963 69.45 7E 70 1.090
.971 was./. Am @ 9_;.
AVERAGE DAILY GENERATOR GROSS 281.47 MWH(E)
( N AVERAGE DAILY THERMAL POWER 869.96 MWH(T)
AVERAGE D4,ILY TURBINE GROSS HEAT RATE 8643 BTU /KWH AVERAGE DAILY MWTH POWER 35.480 */*FP
(..-
AVERAGE DAILY NUCLEAR INST. POWER 33.929 =/aFP
(,
RATIC 0: NI TO hWTH = 1.097 L
i
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6/27/81 a
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Item 2 The burnup was calculated at 248.1 EFPD for the four (4) enrichment regions.
Region Number of FA Burnup-B 9
25,037 MWD /MTU C
60 23,041 MWD /MTU D
52 13,145 E
56 6,438_
Av.
14,982 l
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'5s O(_
en CLIANUp 7L017 E 3;ogy ITIX 3 EVINT DATI:
6/27/81 O
f 3
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r V.
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4 t
i i.
Item 3 Cleanup flow history starting-forty-eight (48) hours prior to the first sample in which the limit was exceeded is as follows:
E Date Time Lerdown' Flow
{
6/26/81 0015 47 6/27/81 0315 46 l
i e
i 4
4 b
i 4
f I
i s
J f
.L e
0 ;
E
6/27/81 I
Item 4 Event Date:
6/27/81 @ 0450 Date T1=e Location 6/26/81 1700 PZR 6/26/81 1750 PZR l
l e s r,
s.
C T1:na Dura:1cn 'Jhen DEI-01 Needed 1.0 n C1/g :n:t and I-U1 Analysis Hasul:s I:em 5 Ivant Data:
6 /27 /8 1 C.
i m
0
?
. /U"
6/27/81
- - o.
Item 5 As per Technical Specification 3.4.8.
The four (4) hour sampling frequency was initiated at 0647 on 6/27/81 and the Dose Equivalent I-131 was 1,64 microcuries per gram.
The four (4) hour sampling frequency was terminated at 0218 on 6/28/81 when the DET-131 was de-termined to be.772 microcuries per gram. DEI-131 was $1,uci/ gram at 0218 on June 28, 1981 when the sample results were.772)vCi/ gram.
Date Time Ci/ gram 6/27 0647 1.64 6/27 1050 2.43 6/27 1445 2.08 6/27 1845 1.51 6/27 2245 1.03 6/28 0218
.772
?
c Reactor ?cuer History of ?rior i
y Forty-eight Iours
-(b Item 1 Event Date:
6/18/81
'l\\(
(
-D A TE - 6,16, 81 -- ---H
(.
p
]
HOUR GMWE TURB G MWTH NI RATIO RATID (E710)
(TS56)
(P753)
(P723)
NI/MT ME/MT s
,~;__._
> / a F P.--._ B TU/1( W H-
- /aEP o/oFP
= / > F P_.
a/->FP 7
1 96.54 10124 99.96 100.30 1.003
.966 I
2 96.54 10123 99.88 100.20 1.003
.967 3
96.56 10123 99_.79 100 2n 1__Q07 966 4
96.35 10121 99.83 100.20 1.003
.967 I
I 5
96.51 1012S 99.92 10.0.20 1.003
.966 6
96.56 101'7 0 c_.94 ina_ 2n 1.nno
. oaf J
7 96.50 10131 99.92 100.30
- 1. 0 0 tt
,966 I
S 96.09 10131 99.47 100.10 1.006
.966
.gygg 9
96.-0.7 1-0141 9-9 " '
90 'O 1 W' o66 10 95.80 10142 99.31 99.50 1.002
.965
(
5 11 95.88 10127 99.23 99.60 1.004
.966 --96,08 LD126 9S Jk3 9o '"
1 0 0 ~1 966
~
~'
fi 13 95.64 10143 99.18 99.50 1.003
.964 I E 14 89.92 10234 93.96 95.90 1.021
.957
--- - - 15
--80.16 100S.7
- - 8 2._tB 9WO 1 -- g tg7._
o75 16 82.84 10101 85.15 37.60 1.029
.973 I
17 85.39 10097 87.55 89.50 1.019
.972 LSJ- _S6 60 1Q124
??_ k n on An 1 n1L
.9A9 E'
19 94.25 10161
'97.88
'98.00 1.001
.963 I.2 20 95.08 10157 98.74 99.00-1.003
.963 2 9542 inAng og og os_5 n 1 n06
- 964 tb 22 95.56 11034 99.10 100.10 1.010
.964
( 2 23 95.63 10135 99.10 100.40 1.013
.965
{
24 6 9,-0-1 n
76 1
- - 3 _ as 95, o_an
(
Wn 5
AVERAGE DAILY GENERATOR GROSS 7?1.26 MWH(E)
~
I Z AVERAGE DAILY THERMAL POWER 2334.42 MWH(T)
S V E R A G E--D A I L,Y-TU R BI.N E-G R O S S-H E A T--R A '4 T;'A-TU/KWH
-+
AVERAGE DAILY MWTH POWER 96.020 +/*FP kN$
I AVERAGE DAILY NUC'_AR INST. POWER 96.646 =/*FP
~
~ ~
(
RATIO OF NI TO MWTH = 1.007 i
(
(
l A8 G'g.
e
_...v....
~
- .,e" l
(
DATE 6,18,81
{
(
n.
HOUR GMWE TURB G MWTH NI RATIO RATIO
_( E71.0J (T356)
/ P252]
LP7i MT/MT MEBfT
( '--
a/aFP BTU /KWH
/>FP
- /aFP
- /*FP
- /*FP 1
0.00 0
.00 0.00 0.000 0.000
- - _- 2 0.00--
0
.0.0 0_.00 0 0gn n gnn b.--
3 0.00 0
.00 0.00 0.000 0.000 4
0.00 0
.00 0.00 0.000 0.000
.._5
--- 0-, D G 0_..
.00 0.00 0.000 0 0.00 i
6 0.00 0
.00 0.00 0.000 0.000 (3
7 0.00 0
.00 0.00 0.000 0.000 E _..- - - 3_.
- 0. 00 0
1.0 92 15:4.0 1 404 0.0a3
.f g~. g 4ty;
(._ -t 9
0.00 0
11.34 15.80 1.394 0.000 K
10 0.00 0
11.05 15.40 1.393 0.000 4.__
11
- - 0.00 0..
L1_ 1.7 15.60_
1 7 9. A 0 000 12 0.00 0
11.17 15.60 1.396 0.000 (1
13
.75 52669 11.26 15.90 1.413
.067 14 _ _2 5..J 9 12527 3JL 33
" ?n 1,m?
o74 15 47.93 10907 52.20 59.00 1.130
.a9
( _I 16 76,76 10302 80.42 84.00 1.044
.954
~~
17 92-G3 1.0.19-3 o5 80 06 Lo 00' o.60 E
18' 93.36 10216
- - 97.55
~
97.00
.994
. 9.' i (I
19 94.18 10200 93.33 97.00
.986
.958
_.2 0 04._3.7 in20m om iu 97 7n Z
- - ons oMA 21 94.62 10214 98.94 98.00
.991
.956 (2'
- - 23 95,_51 10 L23 CS_.32 oS 30 093--
o65 22 95.32 10781 98.82 93.60
.998
.965
+-.
24 95.38 10140 98.90 99.40 1.005
.964
=
( E C
AVERAGE DAILY GENERATOR GROSS 322.80 MWH(E) f A V E R A G E._I) A I L Y___TH E R M A L__P_Q W E R 10 %. 63._MWi-L(_TJ W
AVERAGE DAILY TURBINE GROSS HEAT RATE 7020 BTU /KWH
~
- N.
( -!
AVERAGE DAILY MWTH POWER
'42.358 */*FP 27.
3__ AVERAGE __ DAILY NUCLEAR _.IRST POWER 4 4. 0 31_a./
- F P a
R A T I O. _O F...N I_J O _.M W T.B = L0 4 0 c _u
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mm
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A L
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Fuel Bunup by Core Region Item 2 C
Event Date:
6/18/81 i
i I
(
l f
l l
1 r
C
6/18/81 I
.! p%
- tj I
l Item 2 1
The burnup was calculated at 239.4 ETPD for'the four (4) enrichment regions.
Region Number of FA Burnup B
9 24,790 MWD /MTU j
j C
60 22,787
]
D 52 12,848 "
E 56 6,204 Av.
14,722 I
e f
l f
^
i I
i' t
i s=.
i l
l
C'.
's Clean-up Flow History Item 3 C
Event Date:
6/18/81 M
6/18/81 O
b Item 3 Cleanup flow history starting forty-eight (48) hours prior to the fire t sample in which the limit was exceeded is as follows:
Date Time Letdown Flow 6/16/81 0000 47 gpm I 6/17/81 I'1020 55 gpm O
4 e
.j
%)
' Item 4 Event Date:
6/18/81 Date Time Degas Point 6/17/81 2208 Pza
(.
r i
r
,5
r Time Duration When DEI-131 Exceeded 1.0 u C1/ gram and I-131 A,nalysis Results Item 5 1
Event Date:
6/18/81 t
o 4
.~.
6/18/81 4
A l (NJ 4
Item 5 As per Technical Specification 3.4.8 The four (4) hour sampling frequency was initiated at 1020 on 6/18/81 and i
the Dose Equivalent I-131 wa's 2.23 microcuries per gram.
The four (4) hour sampling frequency was terminated at 0125 on 6/19/81 when the DEI-131 was determined to be.285 microcuries per gram.
DEI-131 was5 1p Ci/ gram at 0125 on 6/19/81 when the sample results were.285 vCi/ gram.
Date Sample Time DEI-131 (sci / gram) f 6/18/81 1020 2.23 6/18/81 1330 1.70 f
6/18/81 1732 1.31 6/18/81 2130 1.01
'(-
6/19/81 0125
.285 i
4
't N'
~
Reactor Power History of Prior Forty-eight Hours Item 1 Event Date:
July 1, 1981 i
l ie f
c.
n
(..
fh 2
I 7_
6 ATE-~"o,29 al.
ce
=
t te (p
HOUR GMWE TURB G MWTH NI RATIO RATIO i
(E710)
(T856)
(P753)
(P723)
NI/MT ME/MT 3
mr/vr 44u/fWh a/=FP
- /aFP-~
- /=FP a7.TP
~
($
1 69.86 9977 71.74 77.40 1.079
.974
+
2 69.85 9977 71.70 77.50 1.081
.974 C.I'11Z z _.73d I.
69.d5 1010&
(4.J7 to.dU 1.U(i-
.Yo2 a
(E 4
69.98 10031 72.19 77.70 1.076
.969 4
5 69.91 9914 71.29 76.70 1.076
.981
['
&~-~7 0T35 9839
?1.62 t i TTU 1.0/9
.ysi (4
7 80.12 9496 78.10 82.60 1.058 1.026 8
85.04 9542 83.24 87.40 1.050 1.022 9
90739 yu r4 wa.ao 12.20 1.uau 1.uou E
10 94.62 9960 89.72 96.50 1.076 1.055 11 96.68 9960 91.60 98.60 1.076 1.055 12 7'7.13 79&fs d5.3o 99-20 4. A 6-2
.A.Aa6 r r.
(- E 9960
.85.36
.99.20 1.162
- - 1.139 13 97.18
~
14 97.20 9970 199.10 99f.30 1.002
_. 9 81..
3 Aa 50.95 youu sv.Au 77.ou 1.uux
. alt-d 16 97.15 9977 99.10 99.30 1.002
.980 17 97.15 9977 99.10 99.30 1.002
.980 C#._
16 93.0c luo u yy.uo yy.+u 1.uvo
.y+<
p IE 19 97.12 9977 99.10 99.60
'1.004
.980 20 97.03 9985 99.10 99.50 l1.004
.979
- E A1 7s.lo 7 IA y>.uo 7'i. 9 u 1.uvo
.101 E
22 97.11 9968 98.98 99.60 1.006
.981 4
23 95.02 9961 96.70 97,60 1~.009
.983 24 75.51
??55 73.62 Fo.2U A.ule
.784 unmonown fu R I
r
- 'L.
(3 AVERADE DAILY GENERATOR GROSS 749.97 MWH(E)
- -AVERAGE DAILY THERMAL POWER 2159.29 MWH(T) 2 sVERAGE D'AICYNYUINE7ROSS TiEA : xn i t-y>G1 s.0/KwH
(' p AVERAGE DAILY MWTH POWER
'88.062 */=FP l
AVERAGE DAILY NUCLEAR INST. POWER 92.033 a/*FP 1
(,
P RATIO OF NI TO MWTH = 1.045
(
esse *,,
wee w w me.-
we
(
e-enume.
e-*'<O+
?i. & +:y I
x
(
- - DATE' 6,30,81
( -.
f'
(,
HOUR GMUE TURB G MWTH NI RATIO RATIO (E710)
(T856)
(P753)
(P723)
NI/MT HE/MT
~
a / ~iF P BTU /KWH a/aFP
- /aFP a/>FP
=/*FP
(' E 1
?3.42 9960 95.02 95.90 1.009
.783 2
93.50 9955 95.0T 95.90 1.009
,984 3
73T43 3702 95.07 96,00 1.010
.983
(_
4 95.23 9962 76.94 97.30 1.004
.982 5
77.3?
9965 99.23 99.00
~i
- - 6 97737 9964 97.T8 98.90-
.798
.982
.997
.982 f
7 97.77 9956 99.51 99.00
.995
.982 (3
8 97.98 9957 99.76 79'.40
. 99&
982 4,6Nviw1:4
~-7 38.00 9950 99.71 99.70 1.000
.783
_i (p
10 97.99 9948 99.67
??.70 1.000
.983 11 G.00 9947 99.67 99.90 1.002
.983
_ ~~
12' yc.94 y952 99.57-100.20 1.005
.983 13 97.98 9990 99.67 100.30 1.006
.983
( -
14 97.98 9952 99.71 100.10 1.004
.983
- - 15
--~9 3-7o 9We 99.7o 100.20 1.004
.98.3
(- @$
16 77.95 9763 99.80 100,30 1.005
.982 17 98.06 9958 99.S4 100.30 1.005
.982 Id yd.4y yyb0
?4.f4 9c.10 1.012
.985 2
19 24.46 9950 25.61 27.10 1.~058
.955 h
20 0.00 0
.00 0.30 0.000 0.00G-JI J7ID 0
.00 0.00 0.000 0.000 r
(E 22 0.00 0
.00 0.00 0.000 0.000 4
23 0.00
~0
.00 0.00 0.000 0.000
(
s u.ou u
.00 0.00 0.000 0,000
~
r
=
Tc 5
AVERAGE DAILY GENERATOR GROSS 629.12 MWH(E)
( ti AVERAGE DAILY THERMAL POWER 1836.79 MWH(T)
Ti XVER3GE~DhTL.Y TUR~LINE GROSS HEAT I4 ATE 7883 BTU /KWH (9 f AVERAGE DAILY MWTH POWER 74.910 a/+FP
,,,u E
AVERAGE DAILY NUCLEAR INST. POWER 75.221 */aFP e.:
(*
=
RATIO GF NI TO MWTH = 1.004 k
k. _
L L_
t-L-
?W$g$lhd
+a
'$dk5%SS
(
Fuel Burnup by Core Region Item 2 Event Date-July 1, 1931 i
I
't
/
i I
i l
I
-.e.
July 1, 1981
]..
a i
1, 1
.i i
Item 2 i
The burnup was calculated at 250.5 EFPD for the four (4) enrichment regions.
REGION NUMBER of FA E7JUP B
9 25,104 MWD /MTU 1
C 60 23,111 MWD /MTU-4 D
52 13,227 MWD /MTU E
56 6,502 MWD /MTU 1
1 1
l Av.
15,054 MWD /MTU i
I i
f I
I i
l F
W l.
l i
i
CLEANUP.EC'/ HISTORY
~
s Item 3 Event Date:
July 1, 1981
+
y c_
July 1, 1981 Item 3 Cleanup flow history starting forty-eight (48) hours prior to the first sample in which the limit was exceeded is as follows:
DATE TIME LETDOWN FLOW 6/29/81 0113 65 A
'j
July 1, 1981 Item 4 Event Date:
July 1, 1981 @ 0930 Date:
Time Location 6/29/81 1816 PZR 6/29/81 1153 MU Tank
~
l o e e Time Duration When DEI-131 Exceeded 1.0 uCi/ gram and I-131 Analysis Results Item 5 Event Date:
July 1, 1981 9
July 1, 1981
. ve.
i i
Item 5 As per Technical Specification 3.4.8 l
The four (4) hour sampling frequency was initiated at 0750 on 7/1/81 j
and the Dose. Equivalent I-131 was 1.06 microcuries per gram.
The four i
hour sampling frequency was terminated at 1235 on 7/1/81 when the DEI-131 was determined to be.762 microcuries per gram. DEI-131 was 1 1 uC1/ gram at 1235 on 7/1/81 when the sample results were.762 pC1/ gram.
1 DATE TIME uC1/ gram 7/1/81 0750 1.06 7/1/81 1235
.762 l
I a,vey r---
+ w-t t r~u
- - y
=--e+
.,r