ML20010C993
| ML20010C993 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 08/05/1981 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| LAC-7732, RO-81-02, RO-81-2, NUDOCS 8108210355 | |
| Download: ML20010C993 (11) | |
Text
~
"t poblLER io,,
D DA/RYLAND h
[k COOPERAT/VE Po BOX 817 LA CROSSE. WISCONSIN $4601 2615 EAST AV south (608) 788-4000 August 5, 1981 4
In reply, please refer to LAC-7732 DOCKET NO. 50-409 Mr. James G.
Keppler, Regional Director
,\\
U.
S.
Nuclear Regulatory Commission k.
((
I Directorate of Regulatory Operations i
Region III h
- (
\\0 7999 Roosevelt Road l-
'% 201001A ll)
Glen Ellyn, Illinois 60137 u.s. %
N,jgaren
SUBJECT:
DAIRYLAND POWER COOPERATIVE Q
h di %
f3 LA CROSSE BOILING WATER REACTOR PROVISIONAL OPERATING LICENSE NO. DPR-4 SPECIAL REPORT 81-02 i
REFERENCES:
(1)
LACBWR Technical Specifications Section 4.2.2.22, Action g.
(2)
DPC Letter, LAC-7486, Linder to Keppler, dated April 23, 1981
Dear Mr. Keppler:
l In accordance with the provisions of Reference (1), a Special
-l Report is submitted. covering results of sampling and analysis j
actions together with additional operaticnal information for i
five separate occasions when reactor thermal power changed by l
more than 15% of Rated Thermal Power within one hour while in Operational Condition 1 or 2.
f The separate occasions are discussed in sections as follows:
SECTION 1 ------- May 7, 1981 i
SECTION 2 ------- June 15, 1981 SECTION 3 ------- June 19, 1981 t
SECTION 4 ------- June 20, 1981 4
i SECTION 5 ------- July 6, 1981 Each section provides a summary of operating data and radio-logical data for the time period prior to the thermal power change along with the results of the additional sampling re-p-) 3 quired.
3 1
/ I AU6 1 5 gggp -
8108210355 810805 PDR ADOCK 05000409.
S PDR
Mr. James G.
Keppler, Regional Director LAC-7732 U.
S.
Nuclear Regel.atory Commission August 5, 1981 The first special re' ort in 1981 on power changes exceeding 15%
per hour was submitted in Reference (2).
This report should have been numbered Special Report 81-01.
If there are any questions concerning this report, please contact us.
Very truly yours, DAIRYLAND POWER COOPERATIVE c
Frank Linder, General Manager FL:LSG:eme Attachments cc:
Director, Office of Inspection and Enforcement (30)
U.
S.
Nuclear Regulatory Commission Washington, D.
C.
20555 Director, Office of Management, Information and Program Control (3)
U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555 Resident Inspectors SPECIAL' REPORT 81-02 i
4 INTRODUCTION LACBWR Technical Specifications, Section 4.2.2.22, Action g, requires sampling and analysis for Iodine-131, -133 and -135, as well as gross beta and gamma activity between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a thermal power change of greater than 15% of rated thermal power within one hour.
This special report is required to contain~the information regarding reactor power history, fuel burnup, cleanup flow history, offgas activity levels and gross alpha activity levels.
4 SECTION 1 On May 7, 1981, at 1013, the reactor automatically shutiown from 88% rated thermal power, wh-n the reactor operator returned the scram teet switch to " NORMAL" prior to resetting the scram during the monthly Oafety System Channel No. 1 Power-Flow Technical Specification Test.
GROSS 6-y AND 70 DINE ANALYSIS Time of Sample:
1340, May 7, 1981 i
Sample Results:
Gross 8 y ------ 0.204 pCi/ml I-131 ---------- 1.181 x 10-3 pCi/ml I-133 ---------- 1.948 x 10-3 pCi/ml I-135 ---------- 1.802 x 10-2 pCi/ml ADDITIONAL INFORMATION (1)
Reactor Thermal Power Level Starting 48 Hours Prior to Thermal Power Change:
1000, 5/5/81 1013, 5/7/81 88%
i 1
(2)
The approximate fuel burnup of assemblies in & symmetrical region is shown in Figure 1.
(3)
Cleanup Flow History Starting 48 Hours Prior to Thermal Power Change:
Primary Purification Flow Rate 1000 - 1600, 5/5/81 ------------- 40.0 gpm 1700, 5/5/81 -------------------- 41.0 gpm j
1800 - 1900, 5/5/81 ------------- 40.0 gpm 2000, 5/5/81 0700, S/6/81 --- 40.5 gpm 0800 - 2300, 5/6/81 ------------- 40.0 gpm 2400, 5/6/81
- -1013, 5/7/81 --- 40.5 gpr;. t i
e-y-.-my v.
y y
E SPECIAL REPORT 81-02 Primary Purification Decontamination Factors (S-y) 0116, 5/7/81 -------------
1159:1 0138, 5/11/81 ------------
758:1 (4)
Offgas Activity Levels Starting 48 Hours Prior to Thermal Power Change:
0800 - 1600, 5/5/81 --------------- 150 Ci/ day 1600 - 2400, 5/5/81 --------------- 158 Ci/ day 0000 - 0800, 5/6/81 --------------- 154 Ci/ day 0800 - 1600, 5/6/81 --------------- 152 Ci/ day 1600 - 2400, 5/6/81 --------------- 158 Ci/ day 0000 - 1013, 5/7/81.--------------- 154 Ci/ day (5)
Gross Alpha Activity Starting with Sample Prior to Thermal Power Change:
0112, 5/7/81 ---------- < 2.604 x 10-8 pCi/ml 1013, 5/7/81 ---------- Thermal Power Change 0132, 5/11/81 --------- 5.29 x 10-7 pCi/.1 r,
SECTION 2 A spurious spike on Nuclear Instrumentation Channel No. 8 caused a corresponding high signal on Power-Flow Channel No. 2, which resulted in an automatic shutdown from 31% on June 15, 1981 at 2344.
GROSS S-y AND IODINE ANALYSIS Time of Sample:
0336, June 16, 1981 Sample Results:
Gross B-y --------- 2.71 x 10-2 pCi/ml I-131 ------------- 1.146 x 10-4 pCi/ml I-133 ------------- 1.954 x 10-3 pCi/ml i
I-135 ------------- 3.391 x 10-3 pCi/ml ADDITIONAL INFORMATION (1)
, Reactor Thermal Power Level Starting 48 Hours Prior to Thermal Power Change:
3 2400, 6/13/81 0525, 6/14/81 ------- -
Shutdown 0524, 6/14/81 ---------------------------- Reactor Critical 0956 - 1142, 6/14/81 --------------------- Shutdown 1142, 6/14/81 ---------------------------- Reactor Critical 1142, 6/14/81 1300, 6/15/81 --------- 0.4%
1300 - 2344, 6/15/81 --------------------- 0.4% - 31%
SPECIAL REPORT 81-02
-(2)
.The approximate fuel burnup of assemblies in a syhmetrical region is shown in Figure 1.
~
(3)
Cleanup Flow History Starting 48 Hours Prior to Thermal Power Change:
1 Primary Purification Flow Rate 2400, 6/13/81 0851, 6/14/81 ----------- Shutdown 0851, 6/14/81 ----------------------------- Purification Started 0957 - 1327, 6/14/81 -----------------------Shutdown 1327, 6/14/81 ----------------------------- Purificatioa Started 1400 - 2200, 6/14/81 --------------------- 41 gpm 2200, 6/14/81 2344, 6/15/81 ----------- 41 gpm Primary Purification Decontamination Factors (8-y) 0026, 6/15/81 -------------~123:1 0044, 6/18/81 ------------- 629:1 1
(4)
Offgas Activity Levels Starting 48 Hours Prior to Thermal Power Change:-
0000, 6/14/81 1600, 6/15/81 --------- No Significant Offgas 1
Generation 1600 - 2344, 6/15/81 -------------------- 38.6 Ci/ day (5)
Gross Alpha Activity Starting with Sample Prior to Thermal i
Power Change:
0022, 6/15/81 --------------- 5.67 x 10-7 pCi/ml
/
2344, 6/15/81 --------------- Thermal Power Change 0336, 6/16/81 --------------- 3.65 x 10-7 pCi/mi SECTION 3 At 0844 on June 19, 1981, the rea'ctor shutdown automatically from 60% rated thermal power due to low voltage at Reactor Building Motor Control Center lA.
The control power transformer for the Decay Heat Pump Starter had shorted.
The resulting ionization flashed over, causing a high amperage short.
GROSS 8-y AND IODINE ANALYSIS Time of Sample:
1135, June 19, 1981 i
l 1
1 i l
1 m
~.
SPECIAL REPORT 81-02 Sample Results:
Gross B-y ---------- 2.34 x 10-4 uC1/ml I-131 -------------- < l.54 x 10-5 pCi/ml I-133 -------------- 6.41 x 10-4 uCi/ml I-135 -------------- < 9.45 x 10-5 pCi/ml i
ADDITIONAL INFORMATION (1)
Reactor Thermal Power Level Starting 48 Hours Prior to Thermal Power Change:
0800 - 2400, 6/17/81 ----- ------------ 41% - 47%
0000 - 2400, 6/18/81 ------------------ 47% - 56%
0000 - 0844, 6/19/81 ------------------ 56% - 60%
(2)
The approximate fuel burnup of assemblies in a symmetrical region is shown in Figure 1.
I (3)
Cleanuo Flow History Starting 48 Hours Prior to Thermal Power Change:
Primary Purification Flow Rate 0800, 6/17/81 - 0844, 6/19/81 ------------ 41 gpm Primary Purification Decontamination Factors (6-y)
)
0044, 6/18/81 -------------- 629:1
}
0149,.6/29/81 -------------- 648:1 1
(4)
Offgas Activity Levels Starting 48 Hours Prior to Thermal Power Change:
0800 - 1600, 6/17/81 -------------- 64 Ci/ day 1600 - 2400, 6/17/81 -------------- 60 Ci/ day 0000 - 0800, 6/18/81 -------------- 70 Ci/ day 0800 - 1600, 6/18/81 -------------- 82 Ci/ day 1600 - 2400, 6/18/81 -------------- 82 Ci/ day 0000 - 0800, 6/19/81 -------------- 87 Ci/ day (5)
Gross Alpha Activity Starting with Sample Prior to Thermal I
Power Change:
1 0040, 6/18/81 -------------------- 3.97 x 10-8 pCi/ml 0844, 6/19/81 -------------------
Thermal Power Change 0111, 6/24/81 -------------------- 1.69 x 10-7 pCi/ml i
4 L _
~
SPECIAL REPORT 81-02 N
s l
l SECTION 4
. At 0140 on June 20, 1981, a reactor shutdown commenced from 22%
rated thermal power due to leakage from the mechanical seal of Upper Control Rod Drive Mechanism in position No. 20.
The reactor was shutdown at 0202.
I GROSS B-y ACTIVITY AND IODINE ANALYSIS Time of Sample:
0516, 6/20/81 Sample Results:
Gross B y -------------- 5.49 x 10-2 pCi/ml I-131 ------------------ 4.108 x 10-5 pCi/ml I-133 ------------------ 7.96 x 10-5 pCi/ml I-135 ------------------ 7.206 x 10-4 pCi/ml 1
ADDITIONAL INFORMATION (1)
Reactor Thermal Power Level Starting 48 Hours Prior to Thermal Power Change:
0200, 6/18/81 - 0844, 6/19/81 ------------ See Section 3 0844 - 1239, 6/19/81 --------------------- Shutdown 1239, 6/19/81 ---------------------------- Reactor Critical l
1239 - 2400, 6/19/81 -------------------- 22%
0000 - 0140, 6/20/81 --------------------- 22%
(2)
The approximate' fuel burnup of assemblies in a symmetrical region is depicted in Figure 1.
(3)
Cleanup Flow History Starting 48 Hours Prior to Thermal Power Change:
l Primary Purification Flow Rate 0200, 6/18/81 - 0844, 6/19/81 ---------- See Section 3 0844 - 1618, 6/19/81 ------------------- Shutdown 1618, 6/19/81 -------------------------- Purification Started 1700, 6/19/81 - 0202, 6/20/81 ---------- 41 gpm Primary Purificatica Decontamination Factor (B-y) 0044, 6/18/81 --------------- 629:1 0149, 6/29/81 --------------- 648:1 (4)
Offgas Activity Levels Starting 48 Hours Prior to Thermal l
Power Change: _,.
. ~. _
c.;
- SPECIAL REPORT 81-02 0200, 6/18/81 - 0844, 6/19/81 ------- See Section 3 0844 - 1600, 6/19/81 ---------------- No Significant Offgas Flow 1600 - 2400, 6/19/81 ---------------- 23 Ci/ day (5)~ Gross Alpha Activity Starting with Sample Prior to Thermal i
Power Change:
0040, 6/18/81 ---------------- 3.97 x 10-8 pCi/ml 0140, 6/20/81 ---------------- Thermal Power Change 0111, 6/24/81 ---------------- 1.69 x 10-7 p'Ci/ml SECTION 5
~
- The reactor automatically shutdown from 85% rated thermal power at 1137 on July 6, 1981 due to a spurious spike on Nuclear Instru-mentation Channel No.
8, which caused a corresponding spike on Power-Flow Channel No. 2.
GROSS B y AND IODINE ANALYSIS Time of Sample:
1353, 7/6/81 Sample Results:
Gross S-y --------------- 0.217 pCi/ml I-131 ------------------- 9.48 x 10-4 pCi/ml I-133 ------------------- 4.54 x 10-3 pCi/ml I-135 ------------------- 2.04 x 10-2 pCi/ml I
ADDITIONAL INFOPMATION (1)
Reactor Thermal Power Level Starting 48 Hours Prior to Thermal Power Change:
1100 - 1500, 7/4/81 -------------- 83%
1600 - 1800, 7/4/81 -------------- 84%
1900, 7/4/81 - 1137, 7/6/81 ------ 85%
i (2)
The approximate fuel burnup of assemblies in a symmetrical j
region is depicted in Figure 2.
(3)
Cleanup Flow History Starting 48 Hours Prior to Thermal Power Change:
i Primary Purification Flow Rate 1100 - 2400, 7/4/81 ------------- 40.5 gpm 0100, 7/5/81 - 1137, 7/6/81 ----- 41.0 gpm i,
)
-v m
g q
m
..m
.a
.,,.4c.
,s.,...
,-m
- - - _ _ - ~. -
e.
q 1
- SPECIAL REPORT 81 '
Primary Purification Decontamination (6-Y) 0044, 7/6/81 -------------- 795:1 0114, 7/9/81 -------------- 600:1 (4)
Offgas Activity Levels Starting 48 Hours Prior to Thermal Power Change:
0800 - 1600, 7/4/81 ------------- 117 Ci/ day 1600 - 240,, 7/4/81 ------------- 123 Ci/ day 0000 --0800, 7/5/81 ------------- 119 Ci/ day 0800 - 1600, 7/5/81 ------------- 105 Ci/ day-1600 - 2400, 7/5/81 ------------- 112 Ci/ day 0000 - 1100, 7/6/81 ------------- 105 Ci/ day (5)
Gross-Alpha Activity Starting with Sample Prior to Thermal Power Change:
0040, 7/6/81 -------------- < 3.46 x 10-8 pCi/ml 1137, 7/6/81 -------------- Thermal Power Change 0115, 7/9/81 -------------- < 3.04 x 10-8 uCi/ml 4
i i
j.
y
-w
.v-
-w-em - -
c
e a i+...;sua s g.:
-u
. ~.
'.* p A
B C
D E
F G
H K
L
/
1 2( C 2
/4 ~l l
/f C _ l
/dL l@ FIT I
3 I ~
G
'_I 7.'
I@ P 8 J
4 I
PM i
I 2.
IhP3 I
I
/B l
ll
~
S l
~
hl h7
~i
_?7 L
fy lhF /.
I l
9 i
6 l0 52 223
_ ll2l 2 02 131 n
a qw.s 4
1 _ t_ ;
I n
u 7
252 ll.33 Zff 855 q)1
~
@n n>
1 l
n ir, 1
8 Il3 2 52 l2.7'l 4.77 1
1
>rm g
u 9
~
'2.22 13 31 /o3 M'07 u
I I
JfD 10 1]f
/N CORE FLUX MONITORS Q h
PLANT M
NORTH Y
FIGURE 1 QUARTER CORE FUEL EXDOSURE ESTIMATION (GWD/MTU)
AN INDICATION OF REGIONAL EXFOSURE AS OF MAY 31, 1981 TlaE AVERAGE EXPOSURE: 8.41 GWD/MTU
ra,,,,
4 m --
9
./'
A B
C D
E F
G H
K L
~
/
I
_ L N'i k/(D_t IS"7
_ C=="1
/c,-
)@r-frM L
I 3
~
,_ f '6. 9
_' 7 3Hg 4
~
I
're ig r3 g,
,j===.;
r 5
1 L
i T?'
we
_q_ f j _ug 4,
j 8
/02 232 ll.N 7./4 73g
},
i
~
L_2n@L.5
~
1 _g i
g fa 7I 242 II.Yr z9(
73,tj t
- -W, '
teD _ wn guic
~
w ll'IS 2.4I j 12.22 lp.03
~
I N
ii pm i@
sn
_L2 4
g
?.30
_ /3#
/0.32 N//
L 2EQ jg
'I.22 IN CORE FLUX MONf TORS Q p
NORTH FIGURE 2 jj QUARTER CORE FUEL EXFOSURE ESTIMATION (GWD/MTU) f AN INDICATION OF DEGIONAI, EXPOSURE AS OF JUNE 30, 1981 TiiE AVERAGE EXPOSURE: 8.48 GWD/MTU j
J w.