ML19308D436
| ML19308D436 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/10/1977 |
| From: | Stewart W FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML19308D416 | List: |
| References | |
| NUDOCS 8002280748 | |
| Download: ML19308D436 (19) | |
Text
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LICENSEE EVENT REPORT
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[pLCASE PRINT ALL RCOUIRED INFCRT.1AT;07r, 1
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8 AME LCENSE NUMOCR TYPE lFlL lCl Rl P } 3l l__0 l 0-l-l 0 l 0 l 0 l 0 l 0 l-l 0 l 0 l l 4l 1l 1l 1l1l l0 l3 l 7 09 14 15 25 26 30 31 32 CATECORY TP DOCKET NUMOER EVENT oATE REPont CATE QCON'T l l - l d lL l l0l5l0l-l0l3l0l2l l 0 l 7 l 1. l 7 p l7 l l 0 l 8 l1 l0 l7 l 7[
7 8 57 50 59 60 61 68 69 74 75 80 EVENT DESCRIPTION l Following a Reactor trip, the Reactor Coolant Dose Equivalent I-131 was 1.428 uci/ gram j
c2 7 09 g [ contrary to Tech Specs 3.4.8.
Redundancy NA.
Second occurrence of this event. Refe r j
s g[fLER77-67. The DE I-131 returned to acceptable level at 1325 on 17 July 1977.
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7 89 05 l (LER 77-91) l 7 o9
@l 80 7 89 1
- SEE Yo"o*e*
uES"[AEER couPoranT ceCE vot4TcN O
lC lG l lFl lZ lZ lZ lZ lZ l2 l lN l l Z l 9 l9 l9 l lNl 4
7 89 10 11 12 17 43 44 47 48 g
CAUSE DESCRIPTION
',s l The increase of DE I-131 was due to expected spikes following a Reactor trip and ic2cwn le'alcir(g as 7 89 0s l fuel pins. The Reactor Coolant was cleaned via the demineralizers.
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80 7
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% POWER UTHER STATUS DISC /ERY D!SCoVERY CESCA:PTioN g
pl l 0l 0l 5l l NA l
lB l l
NA l
78 9
10 12 13 44 45 46 80 L
W lZlE *SE l LOCATON OF RELEASE NA l
l NA l
7 8 9
10 11 44' 45 PERSONNEL EXPOSURES 80 NUMBEP TYPE CESCArPTON Q l 0l 0l 0l 0l Zl l
NA l
7 89 11 12 13 SO -
PERSONNEL INJunlES NUMDER DESCRIPTON
$ l0l0l0l l
NA l
7 09
.11 12 1
60 OFFSITE CONSEQUENCES lII5l l NA l
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7 09 LOSS OR OAMAGE TO FAC:UTY 80 TY DESCRIPTCN
@ @PE l
NA l
7 89 10 PUBUCITY 3l NA j
7 89 L:0 02 2807MI OITIONAL FACTORS 0U Lad
]l SEE ATTACHED TECH SPEC REQUIRED DATA AND SUPPLEWNTARY INFORMATION
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NAME.
- u. p. se ware Cit n ONE: (813) 866-4159 e
e CP O A fi l. ' f. 7
SUPPLEMENTARY INFORMATION Report No.:
50-302/77-91 2.
Facility:
Crystal River Unit #3 3.
Report Date:
10 August 1917 4.
Ctcurrence Date:
17 July 1977 5.
Identification of Occurrence:
The Dose Equivalent I-131 was greater than 1.0 pei per gram of primary coolant contrary to Technical Specification 3.4.8.
6.
Conditions Prior to Occurrence:
Mode 1 operation.
7.
Description of Occurrence:
At 0940, in the process of plant startup, the Chem / Rad department actified Operations that the primary coolant Dose Equivalent I-131 was 1. 428 pei/ gram. Action statement 3.4.8.a was entered and clean-up of the Reactor Coolant was immediately initiated via 5'
the demineralizers. The DEI-131 was reduced to.8 pei/ gram at 1325.
8.
Designation of Apparent Cause:
O This event was caused by known leaking fuel pins and expected spikes fo Reactor trip.
9.
Analysis of Occurrence:
There were no safety implications as sampling demonstrated reducing levels of DE I-131.
10.
Corrective Action:
No corrective action deemed necessary as Reactor Coolant cleanup returned the DE-I 131 to acceptable levels.
11.
Failure Data:
This was the second occurrence of this event, refer LER 77-67 dated 15 July 1977.
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I REACTOR POWER HISTORY OF PRIOR FORTY-EIGHT HOURS ITEM I S
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O-DATE 7,17,77 O.
HOUR MWHT NI RATIO (N753)
(P723)
NI/MT i
O.
/ FP
- /=FP
- /+FP 1:00 85.4t+0
- 0.. __._ 1. 016 0.
2:00 85.1640 0
1.048 OT 3:00 85.440 0
1.048 4:00 85.685 0
...1.040 5:00 28.100 0
.918 O
6:00 2.284 0
0.300 I.__..
7:00..
1.794 _..
0._.. 0. 0 0.0.
O'.
8:00 2.243 0
0.000 l
9:00 8.687 0
.783 l
10:00.
9. 7t6 7 _.
0._.__.._. 8 31__..
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11:00 10.522 0
.874 63 12:00 11.664 00
.883 13:00.. _ _1 1. 7 16 6 0 0....
,8.60 14:00 12.072 0
.853 O'
~15:00 12.561
,0
.860 f.
16:00 12.6t&3 0 _
- .,_,. 8 3 1 __ _ _ __,.__ _. _ __
17:00 12.316
.0
. 8 016 O
18:00 itt. 8 0 tt 00
.871
_ _.. 1 9..:.0 0...__
2 7. 8 9.6 0
la_15.1 20:00 37.316 0
1.171 21:00 48.817 0
1.123
. 22:00 71.Ol+tt 0... _... 1,075 23:00 74.796 0
1.079 O
24:00 80.139 0
1.018 3
__ sVERAGE DAILY MWTH POWER __...._ _...___ __. 316. 717. = /
- F P AVERAGE DAILY NUCLEAR INST. POWER
- 35. t+83 */*FP
' RATIO OF NI TO MUHT = 1.022 G-O 9
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' DATE 7.16,77 O
2.
Q HOUR MWHT NI RATIO (N753)
(P723)
NI/MT
~ */*FP
^
- FP-
- * /
- F P ' - -- --
O.,
1:00 90.0e0 0
1.027 T(,
2:00 90.131 00 1.027 ji
~ 3 r 0 (T -
90'049 0
1.02r
~~-
- - - =
g{3 4:00 90.334 0
1.025 5:00 89.967 0
1.024
. -. 6 ': 0 0 ~ - 8 9. 8 G 4 ~ -- -
0 -- - - 1 ~. 0 24 '-
Oc 7:00 89.478 0
1.025 g
8:00 90.171 0
1.024 1
'9T0u 90 ~70 0
1.023 3.T 10:00 94.984 0
1.022 e
11:00, 96.615 0
1.015
~ 12 ': 0 0 - - 97T 0 23' -- --
0' r:012 g;!
13:00 97.308 0
1.010 14:00 97.471 0
1.011 2
15 :~0 0--
97.553 0-i:-01-1 gg 16:00 97.390 1.011 17:00 97.390 1.012 f-q-- 7 8 r 0 0-97.790 17012 19:00 97.431 0
1.014 g
E 20:00 97.227 0
1.014 arTUO 97734V u
I Vro 22:00 97.553 0
1.017 g.
23:00 95.065 0
1.016 24100-937638
--1.020
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OE z-6 g4 AVERAGE DAILY MWTH POWER 94.255 */*FP AVERAGE DAILY NUCLEAR INST. POWER 95.967 */*FP
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G --j RATIO OF NI TO MWHT = 1.018
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DA-TE 7,15,77 o(r -
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(P723)
NI/MT
- /.FP
+/*FP
-/*FP g
1:00 97.064 0
? 016 2
2:00 96.900 0
1.015 3:00 - 97.064 ---
0 0 ----- 1. 016 - --
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4:00 97.553 0
1.015 g'
5:00 91.436 0
1,019 6:00 50.408 0
1.115 g.,
7:00 38.785 0
1.119 1_.-.8:00 54.976 0
1.113 9 : 0 0~~ '~' 55.17 9 -~ -- -
0-
- t 7182 ---
=
g3 10:00 54.976 0
1.108 11:00 55.873 0
1.106
- - 12 : 0 0-72.145 0--
-- 1 r 0 0 0 ----
07.
13:00 86.542 0
1.042
--,.g 14:00 86.909 0 81 1.033 15 : 0 0 --
- 87. 0 31- ---- -
0--
1 T 018---
g.]
16:00 88.622 0
1.013
'I 17:00 89.396 0
1.025 6
18:00 90.294 --
0 -- ~ 1. 0 19 - - - - -- --- - - - - - - - -
g 19:00 90.049 0
1.018 20:00 90.253 0
1.019 q:_-. 21. 00
--90:253 - - -
0 1r020 22:00 90.253 0
1.023 g
"3:00 90.253 0
1.024 s
24:00 90.090 0
- - -- 1. 0 2 6 - - - - - - - - - - -
'D g'
AVERAGE DAILY MWTH POWER 80.513 */ FP AVERAGE DAILY NUCLEAR. INST. POWER 83.721 */ FP 9-RATIO OF NI TO MWHT = 1.040 l,
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FUEL BURNUP BY CORE REGION ITEM 2 1
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The Burnup was calculated at 85.6 EFPD for the three enrichment regions.
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REGION NO. of FA BURNUP i
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56 2805 MD/MT B
61 2968 MD/M C
60 1836 MD/MT AVE 2533 MD/MT i
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CLEAN-UP FLOW HISTORY PRIOR FORrY-EIGHT HOURS ITEM 3 I
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- e DATE
'i1ME DEMIN IN SERVICE LETDOWN FLO',{
1 July '77 2:10 B
98 spm f
i 15 July '77 9:45 B
50 gpm I
-.' B 60 spm j
15 July '77 15:00 I
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16 July '77 No data 17 July '77 3:45 B
100 gpm 17 July '77 8:15 B
100 gpm 17 July '77 12:10 B
100 gpm.
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i HISTORY OF DEGASSING OPERATIONS ITEM 4 l
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HISTORY OF DE-GASSING OPERATIONS t
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i 15' July 197 20:17 se.sived Hi Radiation alarm Vented M!r! when aver pressurized.
a on RMA-2 and RNA-3 and closed vent innsdiately.
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TIME DURATION WHEN DEI-131 EXCEEDED 1.0 uci/ GRIM AND I-131 ANALYSIS RESULTS ITEM 5 5
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0F FORM 912932 RCS LTDH I-131DE AFTER >15%/HR 92% REACTOR PWR DATE:L tit 1E OF SAMPLING:
7/ 17/ 77 595 DATE a TIME OF COUNTING:
7/ 17/ 77 445 SAMPLE VOLUME:
5.00 ML SAMPLE GEOMETRY CODE:5 AMP-2 COUNTING TIME =
1000 SECONDS SAMPLE LOC.: CE-119 ELAPSED TIME =
1 HOURS QUANTATIVE ANALYSIS QUANTITY ~
2 SIGMA STD. DEV.
2 SIGMA
/
ISOTOPE UCI/ML UCI/ML
% ERROR I-131 0.0347265
+- 2.25950E-04 1.301311678 CS-128 0.0102613
+- 9.49882E-04 18.51387251 I-133 0.022363
+- 2.04758E-04 1.791173512 I-132 1.28975E-03
'- 1.10986E-04 17.21046714
/ ^ ~}4 2.78693E-04
+- 5.61764E-05 40.31418084 r
J4 8.03355E-04
+- 1.56692E-04 39.00940431 N35 4.57665E-03
+- 2.95552E-04 12.9156479 HA-24 0.0113406
+- 2.16056E-04 3.81030986 RB-88 0.143948
+- 7.69852E-03 10.69625142 Jo.L3ULATED F-18 ACTIVITY =
0.06350944 UCI/ML B MU DEMIN OH SERVICE LETDOWH FLOW PATE GPM:
100 1
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FORM 912932 j -
6-0F P;:
j RC5 LTDM I-131DE AFTER >15%/HR 92%. REACT.OR PWR i
ACTIVITY SUMATIONS 1
1 TOTAL MEASURED SUM = 2.301E-01 UCI/ML t,.
TOTAL LLD ACTIVITY-SUM
= 5.023E-02 UCI/ML I
DOSE EQUIVALENT I-131 =
4.147E-02 UCI/ML I-131/I-133 RATIO = 1.519 UCI/ML
~
I-133/I-135 RATIO = 4.996-UCI/ML 1,
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OFg FORM 9:2932
' ' '. POWER CHANGE 01: REACTOR PWR DATE & TIME OF rAMPLING:
7/ 17/ 77 815 DATE & TIME OF-COUNTING:
7/ 17/ 77 915 9 AMPLE VOLUME:
5.00 ML SAMPLE GEOMETRY CODE:5 AMP-4 COUNTING TIME =
500 SECONDS SAMPLE LOC.: CE-119 ELAPSED TIME =
1 HOURS 4
QUANTATIVE ANALYSIS QUANTITY 2 SIGMA STD. DEV.
2 SIGMA ISOTOP2 UCI/ML UCI/ML
'; ERROR
.e
---e.----
--e.-----
-e.---
--e.--
a.-
I-131 0.89213
+- 5.78318E-03 1.296488180 s
I-133 1.72768
+- 8.72974E-03 1.010573717 CS-137 4.62759E-03
+- 1.47741E-03 63.85224274 MO-99 0.0521652
+- 0.011918 45.69329745 I-132 0.401554
+- 6.76863E-03 3.371217819
( MJ TP 0.0433491
+- 2.15906E-03 9.961267939
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0.0131314
+- 2.69592E-03 41.06066375 v5 0.617831
+- 0.0127164 4.116465506 Un-24 0.0181996
+- 1.97838E-03 21.74091738 CALCULATED F-18 ACTIVITY =
0 UCI/ML B MU DEMIN OH SERVICE LETDOWN FLOW RATE GPM:
100 i
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FORM 912932
. 3% POWER CHANGE 0% REACTOR PWR ACTIVITY SUMATIONS 1
i TOTAL MEASURED SIJM = 3.771E+00 UC ! "1L TOTAL LLD ACTIVITY SUM
= 7.395E-01 UCI/ML 4
i DOSE EQUIVALENT I-131 = 6 42W +rd UCI/ML
~
I-131/I-153 RATIO = 0.51c-uCI/ML i
l I-133/I-135 RATIO = 2.796 UCI/ML 4
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FORM 912932 31 DE >1UCI ML SAMP.
5% REACT 0'R PWR DATE & TIME OF SAMPLING:
7/ 17/ 77 1210 DATE'& TIME OF COUNTING:
7/ 17/ 77 1310 SAMPLE V0'UME:
5.00 f.L SAMPLE GEOMETRY CODE:5 AMP-3 L
COUNTING TIME =
500 SECONDS SAMPLE LOC.: CE-119 ELAPSED TIME =
1 HOURS QUANTATIVE ANALYSIS QUANTITY 2 SIGMA STD. DEV.
2 SIGMA ISOTOPE UCI/ML UCI/ML
% ERROR I-131 0.538133
+- 2.57313E-03 0.956317490 I-133 0.889983
+- 3.67266E-03 0.825332619 CS-137 2.43072E-03
+- 5.67634E-04 46.70500922 MO-99 0.0158054
+- 3.70077E-03 46.82918496 I-132 0.097S068
+- 2.31682E-03 4.73754381 1A E5 5.94111E-03
+- 6.90183E-04 23.23414311 j9 5.93565E-03
+- 9.87379E-04 33.26944816
,oS 0.245408
+
4.72248E-03 3.848676490 HA-24 6.47694E-03
+- 7.14317E-04 22.0572369 CALCULATED F-18 ACTIVITY =
3.45160E-03 UCI/ML B MU DEMIN OH SERVICE LETDOWN FLOW RATE GPM:
100
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FORM 912932-
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4 31 DE >1UCI/ML SAMP.
5'4 REACTOR PHR I
i-ACTIVITY SUMATIGHS j
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t TOTAL MEASURED SUM = 1.808E+00 UUI/ML 4
i i-TOTAL LLD ACTIVITY SUM
= 2.686E-01 UCI/ML i
1 DOSE EQUIVALENT I-131.=
8.035E-01 UCI/ML I-131/I-133 RATIO = 0.605 UCI/ML i
I-133/I-135 RATIO = 3.627 UCI/ML i
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