ML20086U132
| ML20086U132 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 12/31/1983 |
| From: | WISCONSIN PUBLIC SERVICE CORP. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-84-35 NUDOCS 8403070169 | |
| Download: ML20086U132 (110) | |
Text
-
O KEWAUNEE' NUCLEAR POWER PLANT ANNUAL OPERATING REPORT 1983 o
o i
WISCONSIN PUBLIC SERVICE CORPORATION WISCONSIN POWER 8
LIGHT COMPANY M A DISON G AS 8 ELECTRIC COMPANY
'O n r us r a gassas R
~..
L13 -1.0 i
T
['d TABLE OF CONTENTS t
i-Page No.
1.0 Introduction 1
2.0 Sunnary of Operating Experience 3
3.0 Plant Modifications, Tests and Experiments 13 1
4.0.
Licensee Event Reports 23 5.0 Fuel Inspection Report 38 d
6.0 Challenges to and Failures of Pressurizer Safety and Relief Valves 39 7.0 Steam Generator Tube Inspection 40 8.0 Personnel Exposure and Monitoring Report 47 9.0 Environmental. Technical Specifications (Appendix 8) 51 I
10.0 Radiological Monitoring Program 52 4
i t
h l
l i
i M
- O o
l
L13-1.1
^
1.0 INTRODUCTION
The Kewaunee Nuclear Power Plant is a pressurized water reactor licensed at 1650 MWt.
It is located in Kewaunee Count 3 along Lake Michigan's northeast Wisconsin shoreline and is jointly owned by Wisconsin Public Service Corporation, Wisconsin Power and Light Company and Madison Gas and Electric Company.
The nuclear steam supply system was purchased from Wefciaghouse Electric Corporation and is rated for a 1721.4 MWt output.
The turbine-generator was also purchased from Westinghouse and is rated at 535 %e net.
The architect / engineer was Pioneer Service and Engineering (PSE) from Chicago.
The Kewaunee Nuclear Power Plant achieved initial criticality on March 7, 1974.
Initial power generation was reached April 8,1974, and the plant was declared commercial on June 16, 1974.
Since being declared commercial, Kewaunee has generated 35,858,100 MW hours of electricity as of December 31, 1983, with a net plant capacity factor of 76.3% (using net DER).
1.1 Highlights During the year, the Kewaunee Nuclear Plant was primarily base loaded.
The unit was operated at 82.7% capacity factor (using net MDC) with a gross efficiency of 32.8%.
The unit and reactor availability were 83.7% and 84.8% respectively.
Table 2.1 is a compilation of the monthly sumaries of the operating data, i
Table 2.2 contains the yearly and total sumaries of the operating data, and Figure 1.1 provides a histogram of the O
V average daily electrical output of the Kewaunee Plant for 1983.
1
p.
L13-1.2 On March 17, 1983, the unit was removed from service for its eighth annual refueling.
Thirty-six fresh assemblies were
-loaded for cycle-IX.
The unit was returned to service on
^
May 15, 1983.
i 1
i 1-Lo I
- l i
t l
l P
O 2
L13-1.3 Or V
2.0 SU M ARY OF OPERATING EXPERIENCE J anuary Normal power operation continued through the entire month of January.
PLANT SHUTDOWNS: There were no plant shutdrwns during the month of January.
February
, Normal power operation continued through the entire month of February.
PLANT SHUTDOWNS: There were no plant shutdowns during the month of February.
March
)
On March 17, the unit was shutdown for end-of-life physics testing and refueling.
PLANT SHUTDOWNS: March 17, scheduled shutdown 337.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Commenced Cycle VIII-IX refueling outage.
April
-In April, the. Cycle VIII-IX refueling outage continued.
On April 22, the core reload was completed.
PLANT SHUTDOWNS: April 1,
scheduled shutdown 719.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.
Continued Cycle VIII-IX refueling outage.
May On May 14, the unit was first placed on-line for the turbine warmup i
run in preparation for the overspeed trip test.
3
L13-1.4 O'u/
On May 15, the Cycle VIII-IX refueling outage was concluded when the unit was -returned to power operation following the sch'eduled turbine overspeed trip testing.
On May 25, the unit was tripped when a reactor trip circuit relay was inadvertently bumped causing a reactor trip breaker to open.
The unit was returned to service on the same day.
PLANT SHUTDOWNS: May 1, scheduled shutdown - 325.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Continued Cycle VIII-IX refueling outage.
The outage was concluded on May 15.
May 15, scheduled shutdown - 9.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
A short outage was taken to perform turbine overspeed trip O,
tests.
C/
May 25, forced shutdown 8.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
A reactor / turbine trip occurred when a
Reactor Protection Circuit relay was.accidently bumped causing the IB Main Reactor Trip breaker to open.
June On June 26, generation was reduced to 385 lei to complete the monthly turbine stop valve test.
On June 30, generation was reduced to 260 MW to inspect Feedwater Pump 1A speed increaser.
I PLANT SHUTDOWNS:
There were no plant shutdowns during the month of p
June.
V 4
L13-1.5 f
V-July On July 27, the unit tripped as a result of an instrument bus inverter failure.
On July 28, during unit recovery from the trip described above, two unit trips at low power occurred due to a main feedwater regulating valve control problem.
The unit was returned to power operation later the same day.
PLANT SHUTDOWNS: July 27, forced shutdown - 19.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Failure of an instrument bus inverter and an associated electrical transient 'on a second instrument bus resulted in a reactor / turbine trip.
I July 28, forced shutdown 2.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
A reactor / turbine trip occurred during plant startup and was attributed to normal feedwater control tran-sient behavise whi!3 transferring from manual to automatic S/C ' ectal control.
The actual cause was later determined as described below.
July ' 28, ferced shutdown - 3.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />.
Mechanical damage to the feedback linkage oc a feedwater regu-lating valve operator resulted in improper operation of the valve.
This caused a reactor / turbine trip during plant startup while transferring from manual to automatic S/G level control.
L
r L13-1.6 m
. Q August On August 28, unit. load was reduced for the performance of the monthly turbine stop valve test. The unit was returned to full power the same day.
PLANT SHUTDOWNS: There were no plant shutdowns during the month of August.
September On September 25, unit load was reduced for the performance of the monthly turbine stop valve test.
The unit was returned to full power the same day.
PLANT SHUTDOWNS: There were no plant shutdowns during the month of p
September.
- m. J October On October 23, unit load was reduced for the performance of the monthly turbine stop valve test.
The unit was returned to~ full power the same day.
PLANT SHUTDOWNS: There were no plant shutdowns during the month of October.
November On November 20, unit load was reduced for the performance of the monthly turbine stop valve test.
The unit was returned to full power the.same day.
PLANT SHUTOOWNS: There were no plant shutdowns during the month of November.
6
L13-1.7 t
c
+
December On ' December 18, unit load was reduced for the performance of the i
monthly turbine stop valve test.
The unit was returned to full power i
the same day.
?
PLANT SHUTDOWNS: There were no plant shutdowns -during the month of j
December.
a 4
l, '-
S 6
i i
f a
4 l
d'
)
7 P
e'm=-
- <-y-e g-m w s--m-, -- t v g - we m we =gw+ +y gre,-=gr-
-- - e. w
, e -e wyew,+ e mww www w -.
.. we--g ww, amen ww me w -
_.., eew w we _
nis e
n (3
m is m
i l
6n
,. a, a._...4..__.._-
......... n.......
..~....... -......
.... a.,...
a.. _.. _
1
)
.I..
~,.
i
.g
.t.
5 A
p p
+
_...... n....
..t
._..t.......
... v....
...... _.. _. _.. ~.. _..
.1 m i-ti m.u. a.n.a., w p
.- in.. ad.-ir mic =ii-.
- ic -. im vr p"-- 'hW ;
p~vu vvyr-h r. :
500 _
- 2..
.r
._......r.
.. r
.. o..
..t........
.t............ _...
n......
.t.__
.. t _..
i..
1..
.t
....t.
.l... a4
._..t........ _... _.....
...4 a
....r....... _..... _ _.
. r._.........
._..._.m_._.._.._. _...
a..
..a.
.. t.
....a....
400_-
..._a.......
- a....
o
.a. t....1..
...=...z_....._.........
. _....a
..t...
- a...
r.
+.
.. +.. _..
- t...
- 1. _. _...
1...
4....
...t.....
i a.
1..
.r.
L.
a
.....a..
..i..
_..a.
..r_.._.
t.
i
..t.
.._....t_.....
a t
. n
......... t..
w r.
i
.. _.. o.
.. _.9.
.a.....
.........t......
.......a......
i.
_.... _. ~.. _
.a J
....i..
4..
.,p
......+.
+..._..
....m..
.4....
....g...
g e.
. I...._.,. _
.I...... 4
...4......I'.
a
.......+....
I
..4..........4..
..T........
4.
e e
e.
...9
..+....
l_
......... +
200 -
4
..+.4.....
4.+.
4.....
....+... -.. +.
,. +.-
6.
4,..
4.....
.............4..,
....T..
.. -... 4.4._.
9 9
._..4.,..... _...
4
......w....
..l._.......
- 4..
.p.
4...
4
...{.
.....l....
.4.....
e 1'
.6
.. t...
t
+
. -.. + -
...............)..
.+.....4.
j y.
4.
.......... _... 5.........
4
....s 1
.4.
.1
.e,.
.+
.e....
l.
4
..t............
..!...6......-p_.._........
.c..
...=4 g..
1 a
m3
,UU a
4
_......4..__
...4...,
4,
^
9, ++.
+...T.......
. +.......9....+........
. 1..... <
.4 e.e*.***'...4****-
g.
. * * +
.e-...*4..*.***=.o
.+......
+.
'=....... -. -. * -...
......... =
&*.a.
-+*a****M**
.p
... 4
.......+.
.. \\ _..
s a
f.
_.,4.,..-..
....6.
q
._....+
.i..
{
.h.
J,.
i 4...
9 9
9 y
9....
.... a. -... =.
4
..,...,..*d
+... _..
.o s...
. o.
.i.
t..._.. _....
9...
.. + _.
o
.t.
.......i......._.t._.._..
1
{
.i 3
i t
i
.a O_
a JANUARY FEBRUARY MARCH APRIL MAY JUNE f
Figure 1-1 (Page 1 of 2)
KEWAUNEE POWER HISTORY AVER AGE DAILY MWE -NET
.g...
...j..
l jgg.
4,.,~ggg.....
.. 3
'..3 *. I.
I...
3Il.
.' '.1 *t**'.. t.'
..I 3
3I,.
l
..g.
.. t t_
j
..i !
..i.I
.II 4..
l- - -...i
+...
1
...t...,.....!
1 l
.1 t.
- 1..,.~.t.
g
,+,
++
!! !, M.
1.M..}t+....
.. W
,+
. - ~\\-
,i.
..+
4.,
1......!
., I
. +.
...+
.....+.
.4.
9 tog
.I
, tit
.,. i.
. l.,.
f
- 1. t. 6..I
.., 1 1
- o..
- i.., j o
...I
. l..,. !...!.,
W g
)
.-. + 9 3., !.
+1
.L
..,... ce,
- 4... +.. +.
...+ 1...I..
2 ct: F
- +44 s,,,,
t..,
.i.. (
.i.. t.,i 1.
O W
.i
.t.
,.. I !,1.. (l.. I.t l
1.
- i..
W
.t...
1 I..
()
F Z i
- j.,..
6 4l..
l.
..l...g}
,.1, g.,
.. l..
..j.
W g)
,1. 3.
.g
. g.
..g
-- g
.g.
i.
)
l-1..
g: LLJ
- t.. I).t 4.,.,.
}..,
...t.....I..
..! !(.... !.
i. !,
1
... 1..!.!
t
- 1..
..t.
-...t,.-.
.r..
+...
og
. t...
1..
.+
. t..I.i
- t.......
. h..
W 2
..i
... r. !. ! l. i..
4 4.
>.-,.., -:4
.I
.I
.., 1..
t.
..,! u!
.~.
..1
.t.
,l
.1..
t.
O J g
..j.I t...
...._.m....
. t,.......t
... L......
1....,.
.4..
... +.......
.t!!
' l,' '...'...
i t,...
,'. '. 'il
.' ' ' 1 ' '.,.
- 1' W
- C t.' '.!
4 g..,...
4.
..!g 4.,
t_.._..
gg.
p,
.t......
g;3 99
. i.
03 gj
.l.
2 tt) Log
.I
+..
.t..,.,.,
...t.
i..,..!
.1.!.1._...
.. t.
t,. i.t.
. I...
.. 1.,11 W
2 0
.L.
.. f 4
t,....
4,
....J....
O q i..
.. l.-
...o... i.! !..
~.
.i O.,,
<g og
..f.,
...6._..
..L
..i...
. ~.
.b g...
W
.......l.
.t.
.p.
.1,.
.i 1 1.
,..4.......
bJ >
1.
......, 4
.. ~.
. (...
t..
.=.
I...
M 4
.l..t ji.
1.
.t
.l
.I.
6 6
..i 1.... t.
~. -
,.e 3..
..F..
1.,....
.b
...r
... ~..
g
.1. 1. -
4.
6 a:
l.
9
.i.
- 3..
.4 yJ pg L....&.
~....
).
_.......... ~..,...
~.. _....
...,g
..t. +
a..
l.1,
..l.
.....,l 4a 1
.1 O.
O
.,. t.
g
... ~.
....)
,. +. -.
4, 4. 4.
9...
- t M
..).
I...
i.,. +.
e
... I. e... 4.!..
.I.
.t.
.. (
...,t.
()
04
.t.
'. I
..g.
- ~
()
.. I 1.,
.i..
,.. 1
.t.
bc
.l
.. 4 c
......l..
.i g...
. ~
i..). 1.
..1.
. ~..
m m
t......
+.
r
.t.
..l....n
.,..i CE)
+. 1 1
t....
,.4
...t-
%........... ~
..m......
.t 1......-
+
/
s.
l
.t.
.l.
........ 11....!
+. -
ac x.
.o...
..t
.. F(..
.t.,...
.l.
uj g
s
. t.
t.-
.t.
^.
O u
..t.'.
t.
...4,.
E 3
1.
tgg
,oo
.1
.t.
4
. ~,.
.+
H p.
1,.
a
.. i.
t...~.
L.,.....
E.
- 1.........,~.
.... L.
w
. 1..
4,.
g) t.
.l l
,1..
2..
4 t.
i
- t.... +
z.
4i 6_
- 3 g
1
..6
.i.
[.
-i
.L 4
1.
l i
- 1..
i l
..1,.
.i;.
t
.i.. ~......
cgp p.
I
- _ _.........._... _i...
i.
i
.....).
t i
3
- i..i.
.,g..
.t
..e.,
O g
j
<g)
.1
- d, s
I....
- I.
,i l.
t I
r
.~. 1
.s.
1 1
- t..... _...,.
. I..
s.
r l.
- g...
..9 I..
_.4
~ ~ * ~
- m.....,..
...f*'-
.~}... 3,.. r
'~"~r
' 'e ' ~ ~" ' ' ' f s.
I
.,. g 9
. _..g 2'...._._'
l i
't.
t
.I t
J j
l' l
.l-t.
3 1
r 4.
1 6
p.._ !.._..
3
.. i
}
}
g-
.g
,""S
.k g
.g h
g g
.I s
t
- i -
f
/
g l
4
.i l
'}
[
l l
l l
l l
l O
O O
O O
O O
O O
O O
,O O
D q
m N
~
3 M MI 9
~
5 TABLE 2.1 (Page 1 of 2)
L13-1.5 ELECTRICAL POWER GENERATION DATA (1983)
MONTHLY January February March April May' June Hours RX was critical 744.0 672.0 422.7 0.0 471.9 720.0 RX Reserve Shutdown Hours
_0.0 0.0 0.0 0.0 0.0 0.0 Hours Generator On-Line 744.0 672.0 406.9 0.0 400.9 720.0 l
Unit Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 1
Gross Thermal Energy Generated (MWP) 1,218,455 1,102,759 649,484 0.0 526,179 1,174,626 Gross Elec. Energy Generated (MWH) 398,000 360,000 210,100 0.0 169,700 387,100 4
g Net Elec. Energy Generated (MWH) 379,962 343,751 200,326 0.0 160,233 368,639 RX Service Factor 100.0 100.0 56.8 0.0 63.4 100.0 RX Availability Factor 100.0 100.0 56.8 0.0 63.4 100.0 Unit Service Factor 100.0 100.0 54.7 0.0 53.9 100.0 Unit Availability Factor 100.0 100.0 54.7 0.0 53.9 100.0 Unit Capacity Factor (using MDC net) 99.4 99.5 52.4 0.0 41.9 99.6 Unit Capacity Factor (using DER net) 95.5 95.6 50.3 0.0 40.3 95.7 Unit Forced Outage Rate 0.0 0.0 0.0 0.0 2.2 0.0 Hours in Month 744 672 744 719 744 720 Net MDC (Mwe) 514 514 514 514 514 514 4
a TABLE 2.1 (Page.2 of 2)
.L13-1.6 ELECTRICAL POWER GENERATION DATA (1983)
MONTHLY July' August.
September October November December Hours RX was critical
'724.7 744.0 720.0 745.0 720.0 744.0 RX Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0-0.0 Hours Generator On-Line 719.0 744.0 720.0 745.0 720.0 744.0 Unit Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 Gross Thermal Energy Generated (MWH) 1,159,011 1,223,940 1,184,200 1,224,069 1,183,857 1,224,505 Gross Elec. Energy Generated (MWH) 382,800 398,500 388,700 403,300 389,700 402,600 0 Net.Elec. Energy Generated (MWH) 364,432 379,318 370,223 384,160 371,360 384,524 RX Service Factor 97.4 100.0 100.0 100.0 100.0 100.0 RX Availability Factor 97.4 100.0 100.0 100.0 100.0 100.0 Unit Service Factor 96.6 100.0 100.0 100.0
.100.0 100.0 Unit Availability Factor 96.6 100.0 100.0 100.0 100.0 100.0 Unit Capacity Factor (using MDC net) 94.0 97.9 102.2 102.5 102.5 102.8 Unit Capacity Factor (using DER net) 91.6 95.3 96.1
%.4 96.4 96.6 Unit Forced Outage Rate 3.4 0.0 0.0 0.0 0.0 0.0 Hours in Month 744 744 720 745 720 744 Net MDC (Mwe) 521 521 503 503 503 503
L13-1.7 TABLE 2.2 ELECTRICAL POWER GENERATION DATA 1983 Year Cumulative Hours RX was critical 7,428.4 71,180.0 RX Reserve Shutdown Hours 0.0 2,330.5 Hours Generator On-Line 7,335.7 69,812.3 Unit Reserve Shutdown Hours 0.0 10.0 Gross Thermal Energy Generated (MWH) 11,871,085 108,971,086 Gross Elec. Energy Generated (MWH) 3,890,500 35,858,100 Net Elec. Energy Generated (MWH) 3,706,928 34,132,036 RX Service Factor 84.8 85.1 RX Availability Factor 84.8 87.9 Unit Service Factor 83.7 83.5 Unit Availability Factor 83.7 83.4 Unit Capacity Factor (using MDC net) 82.7 78.3 Unit-Capacity Factor (using DER net) 79.1 76.3 Unit Forced Outage Rate 0.5 3.9 Hours in Reporting Period 8,760 83,665 1
llO 12
7 1
p L13-1.7A 3.0 PLANT MDDIFICATIONS, TESTS AND EXPERIMENTS
~G c
This section ' is provided. in accordance with the requirements of Part~ 50.59 (b). to Title 10, Code of Federal Regulations (10CFR50.59(b)). -This regulation allows licensees to make changes in
~
the facility' as described in the Safety Analysis Report, make changes in procedures as described in the Safety Analysis Report, and conduct tests and experiments not described in the Safety Analysis Report without prior NRC approval provided the change, test or-experiment does not involve a change.in the Technical-Specifications or an unre-viewed safety question.
10CFR50.59(b) requires that such changes be reported on an annual basis.
t.
3.1 Plant Modifications, 10CFR50.59 i',
There were-no modifications during 1983 which introduced an unre-F L..
viewed safety. question and, therefore, prior NRC approval was not requi red..
The following summary of modifications includes those significant modifications completed during 1983 and not previously reported.
f Many of these modifications are not specifically required to be i
reported by 10CFR50.59(b) since they do not constitute a change l
in the facility "as described in the Safety Analysis Report,"
l howev'er, they are-considered to be of significance, warranting
-mention in this report.
Chemical and Volume Control
' Suction stabilizers were installed on each of the three positive displacement charging pumps.
(DCR 748) 13 L
L13-1.14
)
Sumary of Safety Evaluation Pulsations caused by the reciprocating action of the pumps are dampened which reduces the probability of fatigue cracking of the pump cylinder block.
Reactor Coolant Several tubes were plugged in each steam generator (S/G) due to tube degradation detected by eddy current testing.
Also several tubes imediately adjacent to two foreign cbjects on the top of the tube sheet in S/G 1A were plugged with small diameter holes drilled in the plugs. (DCR 1362)
Sumary of Safety Evaluation The plugs will prevent primary to secondary leakage if the degra-(./
dation continued through the entire tube wall.
The tubes adja-cent to the foreign objects would allow telltale leakage if these objects break loose and cause a break of these tubes.
Reactor Coolant Pressurizer instrumentation lines compression type fittings were replaced with welded fittings to reduce leakage potential.
(DCR 1251)
Sumary of Safety Evaluation Reducing the leakage potential increases the accuracy and reliability of the associated instruments.
Containment Electrical connections, piping, and valves were provided to allow the O,
capability for connection of an ex ternal (to containment) Hydrogen Lj Recombiner. (DCR 1235) 14
L13-1.15 Summary of Safety Evaluation This capability to connect and operate a hydrogen recombiner will serve to help mitigate the consequences of a severe reactor acci-dent.
Main Steam The steam generatnr secondary side tube lane blocking devices were modified to provide greater assurance that they could not break loose during plant operation.
(DCR 1252)
Summary of Safety Evaluation The more secure fastening technique reduces the probability of these objects coming loose and potentially causing a tube rup-ture.
O X)
Internal Containment Spray The solenoid valves for the Caustic Additive Valves (CI 1001A & B) operators were changed from a fail open to a fail closed design. (DCR 942).
Suninary of Safety Evaluation The original design allowed release of caustic into the ICS piping upon momentary loss of power or failure of a solenoid valve.
The new design alleviates this problem while maintaining redundancy and single failure protection.
DC Supply and Distribution Instrument bus transformer BRA-106 was replaced with a higher capacity transformer and certain non-essential loads were removed from this non-interruptible power supply.
(DCR 1245) 15
L13-1.16 q
Sumary of Safety Evaluation The probability of a malfunction of this transformer is reduced by better sizing and load distribution.
Reactor Control & Protection / Engineered Safeguard The ends of the R1 bus, R2 bus, J1 bus, and J2 bus (relay power busses) on both train ' A' and train 'B' were connected to make a loop power supply versus the old chain arrangement.
(DCR's 1338, 1339)
Sumary of Safety Evaluation The loop bus provides two paths for power from the source to the relay. This increases reliability of all the associated relays.
Turbine The' original LP turbine rotors were modified and a new spare universal
'ul rotor purchased to eliminate disc keyway crack potential.
This modi-fication also provides for interchangeability of these rotors.
(DCR 1201)
Sumary of Safety Evaluation Elimination of a disc cracking mechanism decreases probability of failure and subsequent damage to other equipment.
Turbine The single channel overspeed trip system (SCOT) was replaced with a redundant overspeed trip system (R0ST).
(DCR 1008)
Sumary of Safety Evaluation This is a third backup turbine trip system. The ROST system will 5
provide more reliable operation than the SCOT system.
16
L13-1.17
-Control Room Ventilation 2
Control circuitry was modified and anoth'er damper was added to provide
- redundant isolation from outside air.
(DCR 1060)
Sumary of Safeti,0 valuation 4
-With this ~ modification the system design is in compliance with the single failure criterion ~ for isolation of the control room from the outside environment and for operation in the post acci-
. dent recirculation mode.
Primary Sampling a
A multi-ported sample cave was added in the High Radiation. Liquid Sample Panel and a Gama Spectroscopic system was added in the Radiological Analysis Facility.
(DCR 1259)
Sumary of Safety Evalsation
- These modifications are not safety related.
They greatly increase our capability to obtain samples and categorize the con-tent of highly l radioactive liquid streams.
This is an en-hancement of a previous TMI_ modification.
i Meteorological / Environmental ~
A new meteorological data acquisition system including new towers and new instrumentation on the towers and within the plant was installed
' in support of the Emergency Preparedness effort.
(DCR 1133)
Sumary of Safety Evaluation The new system provides meteorological data required to support s
the associated areas of emergency operations.
w 17 w-ty+ - - - - -=-
eY -
y wwec-
+yvve=*-
y www y - ' yy,-r
--v.,yy v.g w-p y y-v mg e - yw-&-----mwpp,w---,gcge..w g.m w.w-..hs
-eW.--r w -,s w + w w n --ww -
e-~wP'tre*wsm-e lv 'wun w = w e==ww=ve
L13-1.18 rx (v)
Cranes A redundant trip signal from the geared rotary limit switch to the paddle switch in the raised control circuits of the main and auxiliary hoist motors was added to the Turbine Building, Auxiliary Building,
-and Reactor Building Cranes.
(DCR 1065)
Sunnary of Safety Evaluation This provides redur.dancy on the upper limit of hoists for preven-tion of a *two-blocking" event.
Building The relay room was er.panded into a former locker room area to provide additional space in the relay room.
(DCR 125/)
'~}
Summary of Safety Evaluation s./
This expansion provides additional space for equipment such as I/O cabinets for the new computer system.
Building / Training An existing warehouse / training building was expanded and remodeled into a training facility.
The expansion provided space for the new Kewaunee Plant Simulator which was installed in December.
Sunnary of Safety Evaluation This modification is not safety related.
Facilities and equip-ment are now available for vary comprehensive on-site training.
Computer 7_s The plant accepted delivery of and started up the new Plant Process 1v) 18
L13-1.19
(
)
Computer / Safety Assessment System to replace and greatly expand the v
capabilities of the old PRODAC-250 computer. Although additional work is required to obtain full capability of the new system, the old and new systems are operating in parallel.
(DCR 1174)
Suninary of Safety Evaluation When completed this modification will greatly expand the infor-mation available to operators during both normal and abnormal operating conditions.
Fire Protection Significant work was completed on many modifications required by 10 CFR 50, Appendix R,
The Dedicated.
Shutdown Panel is in place and some controls have been transferred to this panel.
Installation of new electrical ductwork (tunnel) from the D/G room to the screenhouse, a new 480V MCC for Pressurizer Heaters, and new AC/DC fuse panels have been completed.
Numerous cables (approximately 300) have been rerouted, several MCC's were repowered, DR-118 was relocated, and the Service Water backwash panels were relo-cated and repowered.
(DCR's 1194-1198)
Summary of Safety Evaluation These modifications enhance both automatic and operator control of the plant in the event of fire related damage.
They preclude a fire from preventing safe shutdown of the plant.
Miscellaneous Numerous equipment cha'iges were required due to obsolescence caused by 19
L13-1.20
()
vendors dropping out of the nuclear market or technology advances.
(DCR's 1289, 1325)
Summary of Safety Evaluation These changes involve finding equivalent or better replacement equipment and update of the associated documentation, therefore, there are no adverse safety consequences.
ALARA Increased effort was spent on various DCR's addressing ALARA concerns.
This was made possible mainly because the NRC has begun to allow its licensees to schedule mandated changes, with consideration of many other' licensee generated modifications.
Summary of Safety Evaluation These modifications are for personnel safety and are not nuclear safety related.
3.2 Plant Procedures, 10CFR50.59 There were no procedure revisions during 1983 which introduced an unreviewed safety question or which changed procedures as described in the USAR.
O v
20
L13-1.21 3.3 Tests And Experiments, 10CFR50.59 Pcwer Coefficient, Power Defect and Xenon Tests Power coefficient, power defect and xenon tests were performed
-on March 17 and 18, 1983.
The power coefficient test was performed at approximately 85%
of full power. equilibrium conditions.
The power coefficient test developed by WPS consists of making ' small ' changes (5%) in reactor power at nearly constant reactor temperature.
Corresponding small changes in reactor temperature are made at nearly constant power.
Core power level is controlled by use of. the turbine governor 1,)
valve position, 'and temperature is controlled through the use'of the center control rod cluster.
Following completion of the power' coefficient test the power
' defect test was performed.
The power defect was measured.by shutting down the reactor in a controlled manner from 85%
to 0% by closing the turbine governor valves at a rate of 3%/ minute.
Critical reactor conditions were maintained at the start and finish of the power backdown by usin;; control rods.
A xenon worth test was performed after the reactor was shutdown.
This test measures xenon worth by withdrawing or inserting control rods to maintain the reactor critical.
Xenon was O'.
followed in this manner for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reactor shutdown.
21
L13-1.22
.Sunmary of Safety Evaluation for These Tests The safety. evaluation performed included analyses of core peaking factors expected during the test and a shutdown margin evaluation to assure that Technical Specification limits would be maintained.
In addition, an engineering evaluation of ' the impact on plant parameters-and systems was completed.
This evaluation resulted in written test procedures which were reviewed and approved by. the Plant l
Operations Review Committee (PORC).
i 4
4%
5
- O 22
. _ ~ _ _,. _ _ _ _.,. _. _. _.. _
.,...... _ _ _.. _ _ ~. _. _. _ _.. _ _ _ _
i L13-1.8 4.0 LICENSEE EVENT REPORTS v
This sectior. is a summary of the 38 Licensee Event Reports (LER) sub-mitted to the NRC in 1983 in accordance with the requirements of Technical Specifications.
None of the LER's in 1983 posed a threat to plant operation or public safety.
LER 83-01 During full power operation, an Electrician performing corrective maintenance, pulled the fuse to deenergize SV33379 thus failing CV31394, caustic additive to Containment Spray System Isolation Valve, in the open position.
This allowed caustic additive to drain from the tank to the suction of the containment spray pumps and the tank level to fall below the required Technical Specification limit.
A plant A
shutdown was initiated.
The tank was refilled to its required U
Technical Specification level and the Plant was returned to full power. A design change was completed during the 1983 refueling outage which will prevent this from happening in the future.
LER 83-02 During full power operation the lA Diesel Generator was taken out of service to repair leaks in the diesel generator cooling system's heat exchanger.
The tubes were leaking due to corrosion on the service water side of the cooling water heat exchanger.
Two of the tubes were plugged and Belzona Molecular Metal was applied to all four tube sheet faces.
As a retest, the diesel was run for one hour; no leaks were found.
m 23
-,.___..--.,..---..._,m_
-rm
=_._ _ -.
4 9
L13-1.24 c-LER 83-03
~
-During full power operation the containment air sampling line feeding Rll and R12 was manually isolated due to a failure of one of the
. sample isolation valves to cycle from the control room. The alternate means of leakage detection was in service and the containment sampling line was returned to service within the Technical Specification time limits.
The cause of the event was determined to be a solenoid valve on the sample isolation valve which was stuck in the open position.
l The solenoid was replaced _and the control valve cycled normally.
-LER 83-04
. Investigation of a battery ground fault condition on Battery 1A led to the discovery of water dripping into the controller for valve AFW-10A.
The water was the result of wet rags which had been stuffed in newly I-dEilled. holes in the concrete wall above the controller in preparation for grouting.
To correct the ground fault, the valve was deenergized in the open position to ensure proper AFW flow to both steam genera-tors if required.
The rags were ' removed _ and the valve controller-
. cabinet was dried out clearing the ground fault..
The valve was f
retested and placed back into service.
LER 83-05 During. full. power operation, while performing a surveillance test on the IB diesel generator, the service water outlet _ valve (SW-3018) from the diesel generator oil cooler failed to open fully when the diesel
- was. started.
The IB ' diesel was taken out of service to perform corrective maintenance on SW-3018.
The valve failed to open due to 24
,=
P L13-1.25 erosion of. the' ball causing it to stick when being cycled.
The valve
' was replaced and the diesel generator returned to servite within. Tech-o
.nical Specification time. limits.
LER 83-C6 During full. power operation, Train
'B' of the Internal Containment Spray (ICS) system was ' inadvertently activated when a technician depressed a test lamp in preparation for the monthly Safeguards Logic
. Test.
When' the lightbulb was depressed, the combination of a missing resistor in the test circuit and less than nominal resistance of the test lamp resulted in a current flow sufficient to lift the CSB relay,
~
O activating the ICS system.
The ICS pump operated for about 15 seconds i
prior to being stopped, pumping caustic additive ' from the caustic additive tank into the discharge piping, resulting in a decreased tank level below ' Technical Specif: cation limits.
In addition, a small amount of water was sprayed into the containment.
The containment was t.
visually _ inspected to verify that no damage had occurred; the ICS piping was flushed and the caustic additive tank was refilled.
To prevent recurrence, the surveillance procedure was revised, the test L
. lamp was replaced, and a current limiting resistor will be installed in the test circuit during the 1984 refueling outage.
l:
LER 83-07 l
During full power operation, after completing a containment vent, the sample point for Radiation Monitors Rll and R12 was not switched from the vent position to the containment position.. This caused the reac-tor coolant leak detection system which is sensitive to radioactivity 25 l
-,.._--._-._--.__._.,.._.-_,,____._---,,,m..,____.__....~_-.-_..
L13-1.26
-G'Q to be inoperable for longer than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Insnediately after this discovery, the operator realigned the system to monitor containment atmosphere.
All shift supervisors reviewed the-procedures associated with venting. and were reminded of the need to be more attentive to control board indications and switch positions.
LER 83-08 During full power operation, surveillance testing on the containment pressure transmitters indicated several transmitters out of specifica-i tion.
The safety injection actuation signal provided by these transmitters would have occurred slightly later than required.
Transmitter drif t has been determined to be the cause of this event.
The transmitters were recalibrated and returned to service, fv).
LER 83-09 During routine shutdown operations two fire water hose stations (located in each of the diesel generators) and the screenhouse corri-dor sprinkler system were taken out of service in preparation for modification work.
This was a
violation of the Technical Specifications caused by the operating shif t's lack of familiarity with the Fire Protection Technical Specifications.
Management review of the tagged-out systems at the start of the day shift determined the Technical Specification violation and backup fire protection was inene-diately provided.
Training was provided for all shif ts on Fire Pro-tection Technical Specifications.
Ov 26
--. -.. ~.. -
L13-1.27 3
LER 83-10
-(~'
)
During hot shutdown, surveillance testing found the leakage rate of the personnel airlock inner door in excess of Technical Specification limits. (The door seal had be= succes'sfully tested less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the discovered failure.)
Failure of the gasket seal on the inner door allowed the increased air leakage.
It is suspected that the failure occurred during surveillance testing.
The outer door was immediately danger-tagged and locked to prevent loss of containment integrity.
However, containment integrity was momentarily lost when the door was opened to allow personnel access to restore the inner door integrity.
The inner door seal was replaced and successfully tested.
LER 83-11 p.
U During a scheduled shutdown, the TDAFW pump was declared out of ser-Vice because the measured bcaring temperature exceeded the sur-veillance procedure action level and because valves AFW10A and AFW108 failed to fully close upon demand.
The pump's technical manual revealed that the measured bearing temperatures were within the normal range and that the procedural limits were too restrictive.
The valves failed to fully close because of high differential pressure across the valve crifice.
Although the valves are correctly rated for accident conditions, the test differential pressure exceeded the dp that would be p*esent. under-those conditions.
The turbine-driven AFW pump test pror.edure has been revised to give guidance for operating the valves under' thth conditions.
~
C 27 1
i 9-y e-
L13-1.28 i
LER 83-12 During refueling operations, the Containment Vent Activity Monitor
-(R-21) was discovered out of service. R-21 had been taken out of ser-vice when. the.480V Bus 1-52 was isolated to perform Appendix "R" modi-fications to the safeguards power supply.
Upon discovery refueling operations were _insnediately suspended until R-21 was returned to ser-vice and verified operable.
The redundant channel for automatic iso-lation (RM 11/12) and manual isolation were available to terminate any release exceeding Technical Specification limits.
The cause of the 3
incident was attributed to an inadequacy in the implementation of administrative and procedural controls.
- LER 83-13 During the, refueling shutdown, tne Appendix J type B and C local h
leakrate testing-identified six con tainment isolation
- valves, affecting a total of four penetrations, with unacceptable as found leakage. Repairs to the valves were_ required.
The design function of 4
containment isolation for. the affected lines. was not impaired as l
redundant valves and system capability remained functional.
The final j
retests after repairs were all satisfactory.
l LER 83-14 e
During full power operation, while performing the monthly RHR pump and i
valve surveillance test, con tainment sump ' B isolation valve SI-350B would not operate as required.
The redundant train was available when SI-350B was taken out of service.
Valve SI-3508 failed to operate as required because the mechanical interlock on the breaker was sticking f
s, 1
28
L13-1.29 in the open position.
The mechanical arm was exercised, and the valve V,
returned to operation with no further problems.
LER 83-15 During full power operation, after adj us ting the packing on valve MS-1008 (main steam header 18 to the T0AFW pump), a ulve timing test was attempted.
The valve closed but failed to open until it was manually operated.
Failure of the valve to open electrically was due to a faulty torque switch and the tripper cam being out of adjustment.
The valve operator was rebuilt, the tripper cam reset, and the torque switch replaced.
The valve operator was then reinstalled, tested, and returned to operation.
LER 83-16 During full power operation, while performing the monthly shield v
building ventilation system (SBV) surveillance test, the 1A SBV filter assembly heater failed to energize.
Train 'B' of the SBV system was operating at the time and was thus demonstrated operable.
The heater failed to energize due to a blown fuse in the control circuit.
The fuse was replaced and the required ten hour run for train 'A' was suc-cessfully completed.
I LER 83-17 During full power operation, a routine quality assurance (QA) review of completed maintenance work request (MWR) packages disclosed that a local leak rate test was not performed on containment isolation valve RC-422 following repairs.
During the 1983 refueling outage, work was planned for RC-423, in the meantime, repair work was required on
, V(3.
29
L13-1.30 RC-422 and the post-repair leak rate testing schedule was not revised.
(m)
When the error was found a PORC approved revision to the local leak rate test and an engineering evaluation was performed to provide assurance that leakage was within acceptable limits.
LER 83-18 During full power operation valve MS-100A, main steam header lA to TDAFW pump, would open from the control room but could only be closed manually.
Failure of the valve to close was due to electrical insu-lating material which had worked loose and was on the contact of the torque close switch.
The material was removed and the contact cleared.
The timing test was successfully completed and the valve returned to operation with no indication of further problems.
LER 83-19 During full power operation the 1A component cooling water pump was taken out of service on three separate occasions to perform corrective maintenance on the inboard bearing oil seal leak.
However, the oil seal leak in itself did not preven t the pump from performing its intended function.
The oil leak is suspected to be due to a scored shaft caused by misalignment of the motor to the pump.
The entire l
rotating assembly including oil seals, bearings, and mechanical seals were replaced.
The pump was realigned, tested, and returned to service.
O
\\,)
l I
30 L
L13-1.31 LER 83-20 g
During full power operation transmission line R-304, the 345KV line from North Appleton, tripped due to a failed dead end insulator on tower 88 which in turn, broke a pole on the H-frame of structure 101.
Transmission lines Q-303 and F-84 were available to provide offsite power in addition to the diesel generators.
The exact cause of the failure is undeterminable although the dead end insulator failed during a period of scattered thunderstorms.
The line was repaired and placed back in service within the Technical Specification time limits.
LER 83-21 Dur ing full power operation, the 1A1 service water (SW) pump breaker was racked out to troub,le shoot the service water strainer.
The other three service water pumps were in service and the 1A1 service water
(/
\\
t pump would have been fully operational once the breaker was racked in.
The electricians examined the strainer, found nothing wrong and racked the pump breaker back in.-
The pump was out of service for a total of seven minutes.
It was tested operable and placed back in service.
LER 83-22 During full power operation, the train 'B' isolation valve, SI-208, on the Safety Injection pumps recirculation line to the RWST was deenergized in the open position prior to demonstrating the opera-bility of the train 'A' isolation valve, SI-209, which is in series with SI-208.
Valve SI-208 was deenergized to allow routine preven-tative maintenance work. Once the discrepancy was noted, the operator reenergized the breaker for 51-208 and performed a valve timing test on both SI-208 and SI-209 to demonstrate operability.
31
L13-1.32 n
LER 83-23 During full power operation train
'B' of the Shield Building Vent System (SBV) failed to switch over to the recirculation mode during its monthly surveillance test.
The unsuccessful attempt to switch over to the recirculation mode was due. to a failed static pressure controller; in addition, a leaking hydraulic actuator was discovered on the modulating check damper.
The static pressure controller and hydraulic actuator were replaced; the system was tested and back in service within the allowed time.
LER 83-24 During full power operation, a technical review of Maintenance Work Requests (ma's) disclosed that the 182 service water pump had been removed f om service to perform corrective maintenance.
The pump was removed from service due to a noisy motor.
The motor was removed and replaced with an in-stock spare.
Further inspection of the motor revealed that the output radial guide bearing was faulty.
The radial guide bearing was replaced, the pump was tested and placed back in service.
LFR 83-25 During full power operation the IA2 service water pump was removed from service to perform maintenance on the lube water line flow indi-cator.
The check flapper on the lube water line flow indicator was
~ frozen in position due to crud buildup and was indicating restricted lube water flow.
The flapper was replaced and the instrument housing cleaned.
The pump was placed back in service within the Technical Specification time limits.
32
L13-1.33 m
LER 83-26 During full power operation, surveillance testing revealed the status light on the 1A RRR pump failed to light when the pump was started.
The status light did not come on because the stationary auxiliary switch in the breaker failed to fully close.
The pivot arm on which the switch is mounted was found to be cracked.
The pivotal arm was cleaned and rewelded, in addition, the pivot arm bl.shings were replaced.
The pump was retested and placed back in service, with the light responding satisfactorily.
LER 83-27 During full power operation, the 1A component cooling water heat exchanger was removed from service to repair a leak on its service water temperature controlled bypass line. The leak was caused by sand OV errosion due to the water turbulance created on the discharge side of the throttled temperature controlled bypass valve, SW-1306A.
The line was patch welded, tested under operating conditions, and the component J
cooling water heat exchanger was returned to service.
LER 83-28 During ful: power operation, the IB charging pump was removed from service due to a hairline crack discovered in the area of the pump's discharge head.
The affected section of piping was cut out and a new section welded in place.
A study is undarway to find a solution to reduce the amount of vibration in this system.
t 4
t.
I 33
L13-1.34 o
LER 83-29 During full power operation the 1A AFW pump was placed in pull-out for maintenance work on the controller of AFW-2A, the 1A discharge flow control valve.
Local control of AFW-2A would not allow the valve to open greater than 90%.
The volume booster which aids the solenoid was recalibrated and the valve was satisfactorily tested in both local and remote control.
The 1A AFW pump was retested and placed back in ser-vice.
LER 83-30 During full power operation the sampling pump for the containment gaseous and particulate radiation monitor (R-11) failed to operate.
The backup detection system sensitive to radiation (R-21) was aligned for sampling.
Investigation of the problem revealed that the paper drive fast speed motor had shorted out due to bare wires.
The motor shorting out caused the control power fuse to blow which in turn caused the pump to stop.
Both the fast and slow speed motors were replaced.
The system was placed back in service with no further problems.
LER 83-31 During full power operation the IRPI channel for Rod J-10 was removed from service for maintenance.
Instrument maintenance was required because the IRPI for rod J-10 had failed high.
Investigation revealed that the conditioning module was good, but the remote indicator span had drifted high.
The indicator span was recalibrated and the module returned to service.
A spot check on the calibration points was per-()
formed with acceptable results.
34
L13-1.35 fm LER 83-32 During full power operation, the IB containment spray pump breaker failed to close when called upon during the monthly pump and valve surveillance test.
An inspection of the pump motor and br1 taker found no evidence of damage.
The pump was started from the Control Room and current, vibration, and flow readings were all found acceptable prior to the pump being returned to service.
The pump will continue to be monitored as a part of the existing surveillance program.
LER 83-33 During full power operation, surveillance testing found valve SI-2A, (the boric acid suction line to the SI pumps) failed to open as required.
Failure of the valve to open was due to a broken finger on the open contact in the auxiliary contact block.
The auxiliary con-tact block was replaced and the valve tested satisfactorily.
LER 83-34 During full power operation, the ID containment fan coil unit was removed from service to repair service water leaks.
The leaks were caused by sand and water erosion of the return -bends in the service water cooling coils.
The affected bends were cut out and replaced, the cooling coils passed an inservice hydrostatic test and the fan coil unit was returned to service within time limits.
LER 83-35 With the reactor at 100% power operation, all rods out and in manual, f
the operators noticed that all Rod Position Indication (RPI) was gra-
.,.3 dually drif ting downwards.
The common drifting of all RPI was due to b
35
L13-1.36 m
a voltage regulator failure, thus the RPI system was at no time declare' inoperable.
Based on excore indications, which remained nor-mal the entire time, and that there was no change in bank demand posi-tion, it was concluded that there was no actual rod misalignment.
Drifting of the RPI's was due to a tarnished contact point in the voltage regulator which was attributed to age and wear causing a lower output voltage.
The voltage adjust pot was wiped through the bad spot, the voltage readjusted, and all RPI returned to normal.
Long term actions include adding the output voltage readings to the annual surveillance test and replacing the power supply.
LER 83-36 While at full power operation the 1A SBV recirculation fan failed to start during its monthly surveillance test.
The surveillance test was k
performed following a test on the charcoal filter heat detectors and deluge system.
The recirculation fan failed to start because the deluge system was not reset following the charcoal filter heat detec-tor test.
The deluge system was reset and the fan tested satisfac-torily.
The charcoal filter heat detector test procedure is being revised to ensure that the deluge system is reset.
LER 83-37' During full power operation the IA2 service water pump was taken out of service to repair a packing leak on its service water strainer.
- The strainer was repacked, and the pump was tested and placed back in service within time limits.
O V
36
L13-1.37 LER 83-38
'O.
While at full power operation, a maintenance procedure to replace a relay in RPS rack 133 caused an inadvertent start of the TDAFW pump.
The maintenance procedure directed lif ting leads in a sequence such that the TDAFW pump received a Bus 1 and 2 undervoltage signal and started.
The pump was stopped and tagged out of service to allow completion of the work.
Since the procedure was generated as a result of this work request and will not be used in the future, no procedure revision was required.
i O
F O
37 v
n>
,. - +,
p
,,m
-.-,-,..,-n
--..---we<
r,-
e.--r--,.
-en,.~,
ee
,,m, w.v,-
r.
...n.
L13-1.38 5.0 FUEL INSPECTION REPORT During Refueling #8, thirty six (36) fresh Region K assemblies were loaded for Cycle IX.
Startup physics testing was performed and reported in Cycle IX Startup Report.
The irradiated fuel inspection was performed with an underwater TV camera.
All peripheral fuel rods were examined using one-balf face scans.
Seven assemblies were inspected, including one each of regions B,
F and G, two region I, and two region J.
All assemblies exhibit rod slippage to various degrees.
Numerous scrapes to the rodlets, grids, and top and bottom nozzles were also noted.
However, no damage to the cladding or supporting structures was observed.
All assemblies exhibited axially varying crud deposits. One F region assembly showed minor rod bowing. Overall condition of the fuel was ey.cellent with no (Q
evidence of fuel cladding degradation on the fuel rods examined.
Video tapes were made of all examinations, t
l i-L v
\\
38
L13-1.39
[
6.0 CHALLENGES TO AND FAILURES OF PRESSURIZER SAFETY AND RELIEF VALVES Following -the reactor trip on July 27, 1983, (in which an instrument inverter bus failed) the pressurizer heaters were placed in manual.
With the pressurizer heaters in manual, the pressurizer continued to heat up.
This eventually led to the pressurizer pressure exceeding the pressure setpoint of the pressurizer relief valve, causing one relief valve to open momentarily as required.
The operator sub-sequently turned off the heaters, preventing a reoccurrence.
i n
v f
(_f 39
L13-1.40
.fj
(
7.0 STEAM GENERATOR TUBE INSPECTION 7.1 Eddy Current Testing An eddy current inspection of the'Kewaunee steam generator tubes was performed during April, 1983 in accordance with Technical Specifications and Section XI of the ASME Boiler & Pressure Vessel Code (Inservice Inspection).
Multifrequency techniques were utilized to cancel background interferences.
The initial inspection prograr:: was designed to inspect the Row I
- Row 2 U-bend areas, the peripheral tubes for possible foreign object wear, and a statistical sampling of the remaining tubes for general degradation and anti-vibration bar fretting.
Seven tubes were added to the program for IA generator since they had shown some non-progressing indications in previous inspections.
Identification.of the initial defect in lA generator dictated a program expansion (1st expansion) as required by Technical Specifications.
When more data became available from both generators, a management dacision was made to inspect 100% of the tubes in both generators.
The extent of inspection in each tube was determined by the relative,iosi tion of the tube in the generator and probable degradation mode of that tube.
Eddy Current Result of Steam Generator lA A total of 3377 tubes were inspected as a result of the three expansions required by.the C-2 option of the Technical Specifica.
- tion,
')
i J
40 h
s L13-1.41
)
Of the total tubes, 620 tubes were inspected full-length, 763 were inspected through the U-bend to the top support plate in the cold leg side, and 1994 were inspected through the first tube support plates, hot leg side.
A total of 190 tubes had indications, 155 tubes had less than twenty percent (<20%) indications, of which one was an anti-vibration bar (AVB) indication, four tubes with distorted tube signals in the hot leg, 14 U-bend indications, 17 tubes were degraded (20% through 49%), and four tubes had indications of
> 50%.
The above numbers do not include an additional 19 indica-tions found on tubes with multiple indications since the highest indication on any tube was used in determining the breakdown of (N
the indications.
Three (3) of the total indications (209) were
\\
at v9 port plate locations, in hot leg only. Many copper indica-tions were noted on top of the tubesheet.
Most of the copper indications were found in the banana region of the cold leg.
A few dents were found on the seventh tube support plates of some of the peripheral tubes in the hot leg side.
All relevant data i
l in included in Table 1A.
Eddy Current Results of Steam Generator IB l
A 100% inspection (3388 tubes) was performed as a result of the two expansions required by the C-2 option of the technical speci-fication.-
Of the total tubes, 582 were full-length, 1426 were U-bend inspection through the seventh tube support plate in the cold leg 41 I
L13-1.42 (7
side, and 1380 were inspected through the first tube support U
plate, hot leg side.
A total of 199 tubes had indications, 111 tubes with less than 20% indications, 60 tubes were degraded tubes (20% through 49%),
18 tubes had indications of > 50%, ten (10) squirrels,'and three (3) tubes with distorted tubesheet signals in the hot leg side.
These indications did not include multiple indications as men-tioned earlier.
This would have included an additional 22 indi-cations.
Three of the total indications (221) were at support plate locations, found in the cold leg only.
Many tubes with copper indications were also noted at the top of the tubesheet.
Some dents were also found at top of the tubesheet and on the seventh tube support plate of some of the peripheral tubes.
Nine m
b of the indications were located at the anti-vibration bars (AVB),
mostly Row 37 through 43 in Columns 55 through 63. Four tubes of the nine (9) affected are in Column 55.
Most of the reported indications are inside the tubesheet crevice region.
All relevant data is included in Table 18.
Mechanical Tube Plugging A total of 23 tubes were plugged in Steam Generator IA.
Twenty of the tubes were plugged as a result of the eddy current indica-tions.
Three tubes were also plugged due to unretrievable foreign objects in the secondary side.
These are R43C32, R43C33, and R44C33.
These three (3) tubes were plugged mechanically on Qb the hot leg but R43C32 and R44C3 were mechanically plugged with 42
-v.
e
L13-1.43 2
sentinel plugs in the cold ic to monitor for the possibility of I );
N tube leakage during operation.
R43C33 was mechanically plugged in both legs.
A total of 49 tubes were plugged due to eddy current indications in Steam Generator 18.
One tube (R24C30) with no detectable indication was mistakenly plugged in the cold leg and lef t open in the hot leg side.
This tube was also marked with a different color paint in the hot leg for a future reference, t
l l
l l
e I
OV c
L 43 a
-r
+yri--,,---%v-e, w-ww-,-
,-m-m-
C.,v.,we n,
--w-r-,
avm-
,e3 r-vw ww - w e
- w----=*-m--*w-w%--e-r--+--o-3e-r---=-.=ar-s==-w-=--==--
TABLE lA L13-1.19A 1983 KNPP/WPSC REFUELING OUTAGE STEAM GENERATOR EDDY CURRENT TEST RESULTS
~
)'
' DATA INDICATES WHICH TUBES WERE PLUGGED IN STEAM GENERATOR 1A ALONG WITH A SHORT DESCRIPTION OF WHY THEY WERE PLUGGED.
DEFECTIVE DEGRADED PREVENTIVE R0W COLUMN TUBES
-TUBES
- PLUGGERS DEGRADATION GENERAL INFORMATION 18 47 X
96 1.
Total number of tubes in 19 49 X
90 S/G 1A = 3377 20 48 X
62 19 48 X
55 2.
Total number of tubes 2
5 X
TYPE 1 degraded found in S/G 1A =
2 6
X TYPE 1 17 2
13 X
TYPE 1 2
14-X TYPE 1 3.
Total tubes plugged in S/G 2
17 X
TYPE 1 1A = 23.
1 19 X
TYPE 1 1
22 X
TYPE 1 4.
Defective tube-contains 1
23 X
TYPE 1 imperfections > 50% of the 1
30 X
TYPE 1 nominal wall tEickness 2
48 X
TYPE 1 caused by degradation.
1 46 X
TYPE 1 i
1 41 X
TYPE 1 5.
Degraded tube-contains 2
2 50 X
TYPE 1 imperfections 20% < x < 492 2
49 X
Tirt 1 of nominal wall thickness 18 48 X
47 caused by degradation.
N 33-25 X
35
. ~
43 32 X
TYPE 3 6.
Degradation means a s
43 33 X
TYPE 3 service-induced cracking, 44 33 X
TYPE 3 wastage, wear, or general SUB10TAL 4
2 17 corrosion occurring on either inside or outside of a tube.
7.
Preventive Pluggers Type non-quantifiable indication in U-Bend Type 2 - non-quantifiable indication in tube sheet i
Type 3 - Adjacent to bolts found on top of the tube sheet
-,---. ~,+,-,-
n -
-,-,,,e n,
,,..-u
TABLE IB L13-1.198 1983 KNPP/9PSC REFUELING OUTAGE STEAM GENERATOR EDDY CURRENT TEST RESULTS 3 ~s DATA INDICATES WHICH TUBES WERE PLUGGED IN STEAM GENERATOR 18 ALONG WITH A SHORT
(_ )
DESCRIPTION OF WHY THEY WERE PLUGGED.
DEFECTIVE DEGRADED PREVENTIVE RCW COLUMN TUBES TUBES PLUGGER 3 DEGRADATION GENERAL INFORMATION 31 46 X
52 1.
Total number of tubes in 28 49 X
62 S/G 18 = 3388.
37 41 X
65 37 60 X
59 2.
Total number of tubes 41 55 X
94 degraded found in S/G 18 =
43 55 X
58 64.
T 3
X 61 24 41 X
50 3.
Total tubes plugged in S/G 37 55 X
72 1B = 49.
37 63 X
63 23 59 X
73 4.
Defective tube-contains 28 53 X
77 imperfections > 50% of the 11 48 X
68 nominal wall tEickness 24 47 X
88 caused by degradation.
24 44 X
53 23 38 X
56 5.
Degraded tube-contains 4
37 X
58 imperfections 20% < x < 492 25 37 X
51 of nominal wall thickness 41 58 X
48 caustd by degradation.
41 47 X
47 42 55 X
48 6.
Degradation means a
,_s
(
1 34 48 X
42 service-induced cracking,
\\~ /
31 47 X
46 wastage, wear, or general 23 54 X
49 corrosion occurring on 24 51 X
46 either inside or outside of
, 13 45 X
49 a tube.
27 44 X
48 29 44 X
49 7.
Preventive Pluggers 26 43 X
45 24 42 X
48 Type 1 - non-quantifiable 27 42 X
47 indication in 29 42 X
47 U-Bend
- l 23 39 X
45 Type 2 - non-quantifiable 25 38 X
40 indication in tube 25 36 X
42 sheet 24 35 X
r 45 Type 3 - Adjacent to bolts 26 35 X
46 found on top of 26 34 X
42 the tube sheet 23 30 X
49 23 51 X
TYPE 2 24 46 X
TYPE 2 28 44 X
TYPE 2 24 43 X
TYPE 2 26 42 X
TYPE 2 23 -
35 X
TYPE 2 24 36 X
TYPE 2 16 35 X
TYPE 2
-,()
22 35 X
TYPE 2 24 56 X
TYPE 2 SUBTOTAL 18 21 10 45 f--
.y
L13-1.20
()
7.2 Sludge Lancing Tubesheet cleaning was performed on both steam generators during the Kewaunee Nuclear Plant outage in March,1983, using the full recirculation method in accordance with Westinghouse Procedure MRS 2.2.2 GEN-9.
L Sludge lancing began on March 23, 1983, after all water balance measurements were completed.
Steam Generator 'B' was completed during the night shif t of March 23, 1983. The equipment was then moved to Steam Generator ' A' and sludge lancing was completed on
' A' generator during the night shif t of March 24, 1983.
- O 4
w O.
46
L13-1.47 8.0 PERSONNEL EXPOSURE AND MONITORING REPORT i
O' Pursuant to 10CFR20.407(a)(2), and 20.407(b), a tabulation of the number of individuals for whom monitoring was provided is shown on the following tables:
f 1983 NUMBER OF INDIVIDUALS FOR WHOM PERSONNEL MONITORING WAS PROVIDED Contractors Exp. Range (mR)
No. of Personnel No Measurable 167 100 98 100 - 249 45 250 - 499 26 500 - 749 34 750 - 999 31 1000 - 1999 39 2000 - 2999 0
3000 - 3999 0
Total 440 v
t 47
L13-1.48 WPSC Plant Staff Exp. Range (nR)
No. of Personnel No Measurable 82 100 45 100 - 249 26 250 - 499 27 500 - 749 8
750 - 999 7
1000 - 1999 8
2000 - 2999 0
-3000 - 3999 1
Total 204 Utility (WPSC Non-Plant Staff)
Exp. Range (mR)
No. of Personnel-No Measurable 40 100 31 100 - 249 7
250 - 499 5
500 - 749 3
750 - 999 2
1000 - 1999 2
2000 - 2999 0
i 3000 - 3999 0
Total 90 i
4e l
l
~.,.. _ _ _,
L13-1.49 Total Statistics
- O Exp. Range (mR)
No. of Personnel No Measurable 289 100 174 100.- 249 78 250 - 499 58 500 - 749 45 750 - 999 40 1000 - 1999 49 2000 - 2999 0
3000 - 3999 1
Grand Total 734 A tabulation of numbers of personnel exposure and man-rem received by work and job function is - shown on the following table' in accordance with Section
- 6. 9.1. b of the Kt:waunee Nuclear Power Plant Technical Specification.
The table sh ws the total man-rem exposure for the year was 164.947 L
49 vv--
v.-
,-w..,...~,-,
,,ee.-.m
_n.,,,--,y..,n-,,%,,_._.mp..,w,~.,--,_,mm._
m.,-,.,,.m~__..
Y E
E NUAW E
T 1
7000 30372 36000 09085 06000 92000 40357 9
K C
84000 74846 49000 03072 69000 27000 77826 3
A
- 0. t 000 02903 84000 20064 35000 96000 51 9.L 2 3
78 3
R 8
T 30000 2t721 70000 0001 1 10000 60000 7
1 4 9
9 N
1 2
5 0
1 O
1 C
1 1
FO M RE' AR E-YNY 00000 0000 00000 80007 90000 30900 1
AT 00000 30000 00000 90002 40000 60000 4%002 1
)
07 8
NMI 00000 80000 06000 60005 00000 40000 00663 O
L LI 00000 40000 00000 00001 00000 1 0000 70001 H
HAT DTU I0 T1 C
N U
F N 45002 40080 60023 11 463 22040 9640H 62HH6 0
O 98007 1 271 00020 201 48 35050 80606 51243 4
1 H
I
- 47001, 47712 30020 201 00 41 000 21500 1 7. ;. 2 5 0
4 O
T J
A 22000 71900 00000 30000 03000 20000 671t 0 1
T N
D S
3 1
1 O N I
A T
A K
N R
R O'
T O
W) C F
MA 41 001 84023 6701 0 3t 043 71 000 2000 96017 9
N YER 1
1 5
11 5
0 1
41 11 9
I BPT 1
H1 2
2
-y f
G M 0 N E0C I
R0 T
1 A
t4
)
R AT E
HG f
P
(
O D
Y NLT F
AEI 00001 500O1 00000 20004 70000 1 0000 5O006 O
NL 1
1 1
'L N I 1
4 5
G EOT N
tSU 4
I NR T
OE R
SO-O R'
P EF E
PO t k
t FR0 OEI 69054 09033 2001 1 6251 3 6251 0 03301 6531 2 7
BT 3
2 3
1 RMA 2
2231 0
1 6
EUT 1
2 DNS 1
M 1.
U N
E D
G I
N U
I G
T N
R O
Y O
I L
L L
L L
L L
R P
T E
L i
N N
N
- H t t l
E E
E E
O E
C N
N t
1 T
H N
L.
NLL L '
ll LL L
s#. L. L
! L? H ;t l
"t.: N lhI L
N1 L.
l' hLL L
N..
l' A.
O 0LL Oif u
L! t l l'
r,.
. i Ft ii e M i.
iHl SHe Ol t
l t
i 1 L i i
.l Uit R
F
'n L.1 i
D iN s
i s
dwl ; io a
v h
- r t
O E
F s
S r t IHt l O t'fO0t T0ilLu0 iHHEOO ONiOO 0HLUO 0NE Od if I;
Fih h 'i L R N N iNL i. N N t
f RHlt 4 ERNih t
t t
N ONI O0 r
N l
T u
O SNPSS ASJiPSS C5tPSS ASNPSS GS1 FSS SJtPSS SNPSS R
T J
I RO RR fR0 RR ERU RR NRO RR NR0 PR R0 RR RO RR 4
1 A
T ESSEE CE3SLE PESSEE EESSEE IE5SEE E1SEE ESSEE M
D A
- RCPP PRCPP SPRCPP TPRCPP SPPCPP l' RCPP PRCPP I
I C.
l R
t RF EI N
EI N
EI N
EI S
EI LI EI O A ECEPSYG I E P S Y G' IEPSYG IEPSYG EEPSfG LPSfG EFSYG L
R.
F PNC YRN AC Y fN C
YRN C
YRt A
K OANGHOI H.N G H O I EtiGHOI MNGHOI ONGHOI GNGHOI NGHOI T
t 4
N.
D R
LANPSR ANPSR CANPSR ANPSR RAI SR NANPSR ANPSR O
4 P N D l'
R O
RLtI IE ENI IE INI IE LNI IE S.
A W OIEIH V 4 IL IHI IE NI IE T
J ETHVE VETHVE AETHVE ElHVE LETHVE ETHVE t
D TLTATRt ITATRN RTATRN ITATRN U
N CVNRLEI TNRLEI ENRLEI CNRLEI E T A T R.1 l
ET ATRN LTATRN D
t TiRLI UNRLEI ANRLEI N
A ARIEAPG UI EAPG SIEAPG EIEAPG SlEAPb FI E (i PG TIEAPG A
t T
EUAPEUN OAPEUN NAPEUN PAPEUN AAPEUt EAPFUN OAPEUf R
i J
b, S
FSNOHSE PNOHSE IMOHSE SiOHSE WMOHSE RNOHSE TMOHSE G
ivC
L13-1.24 9.0 ENVIRONMENTAL TECHNICAL SPECIFICATIONS ( AFPENDIX B)
O The Environmental Technical Specifications (Appendix 8) t-the Kewaunee Nuclear Plant's Technical Specifications were deleted by Amendment 47, November 29, 1982.
This information is reported monthly to the State of Wisconsin under the Wisconsin Pollution Discharge Elimination System (WPDES) Permit Number WI-00001571 issued by the State of Wisconsin, Department of Natural Resources for the Kewaunee Nuclear Power Plant.
O
/
O 51
L13 -1. 52 i
10.0 RADIOLOGICAL MONITORING PROGRAM Attached is the report from Teledyne Isotopes on the Radiological M'nitoring Program for Kewaunee Nuclear Plant for 1983.
t t
O t
6 I
l l.
~
52 l
- - -. _ =..., -....,..,.. _. -
- -.. -.,= - -....._.
"RTELEDYNE ISOTOPES I
MIDWEST LABORATORY
,n.,
1509 FRONTAGE **0.
NORThB' ROOK. IL 60062 (312) 5S4 4 700 REPORT TO WISCONSIN PUBLIC SERVICE CORPORATION WISCONSIN POWER AND LIGHT COMPANY MADIS0N GAS AND ELECTRIC COMPANY RADIOLOGICAL MONITORING PROGRAM FOR THE KEWAUNEE NUCLEAR POWER PLANT KEWAUNEE, WISCONSIN ANNUAL REPORT - PART I
SUMMARY
AND INTERPRETATION s
(v) -
January - December 1983 PREPARED AND SUBMITTED BY TELEDYNE IS0 TOPES MIDWEST LABORATORY PROJECT N0. 8002
/1 Approved by:
- m L.G.Hueb%r General MYnager
!v) 1 February 1984
6 PREFACE
. The staff. members of the Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environmental -Sciences) were responsible for. the. acquisition of data presented in this report.
Assistance in sample collection was provided by Wisconsin Public Service Corporation personnel, f
-The report was prepared by L. G. Huebner, General Manager. He was assisted in report preparation by L. Nicia, Group Leader, and other staff members of the laboratory.
0; s
4 D
i o
ii l
s--
r;
- t.4 p
l.y 9,
-~
s s
x 3
.j
- N
.y s
TABLE OF CONTENTS
_3 Page
.....~
-Priface.'............................
11
- w.. '.,,
List ~of Figures........................
iv e-
.3 t-
?
List of Tables'f........................
v
1.0 INTRODUCTION
1 w.
2.0
SUMMARY
..'.'..... w....................
2
-3.0 RADIOLOGICALSORVEILLANCEPROGRAM 3
?'1 Meth odo l ogy..' ','.....................
3
>.3.1.1 The Ai r Progrd[..................
3
-3.1.2 ThecTerrestrial Program..............
4
^3.1.3 The Aquatic Program................
5 3.1.4 Program Exscution.................
6
~ Q( m ~
3}1.5: Program Modifications...............
7 4 ~ '
as 3.2 Resuli.s and. Discu.ssion..............
7
+
g s 3.2.1 Atr.ospheric Nuclear Detonation-7 3.2'2. Thi' Air,Eksikonment......
8 3.2;3 L.The-Terrest, ial Environment............
9
,3.2.431h0 Aquatic Envir,onment..............
12
?-
s
_-. s 4.0-FIGURES AND T,A3LES. ;.....................
15 N
5.0 k REFERENCES...........................
32 kAPP5NDICES
-s..
~
w' c' A.
Crosscheck Program Results.................
A-1
?.
Statistical Notations.,..................
B-1 C.
Maximum; Permissible Concentra.tions of Radioactivity in Air and Water above Natural Background in Unrestricted
~
N Areas'..
m.
C-1 k
'k N.
\\
3 4 (
g 1
.A3 1
y
.iii
'a__
.c 1
O LIST OF FIGURES No.
Caption Page 4-1 Sampling locations, Kewaunee Nuclear Power Plant..
16 l D' I
l l
a J
l
' O iv
(~'g -
U LIST OF TABLES No.
Title Page 44. 1 Sampling locations, Kewaunee Nuclear Power Plant.
17 14. 2 Type and frequency of collection.................
18 4.3 Sample codes used in Table 4.2..................
19 4.4 Sampling Summary.........................
20 4.5 Environmental Radiological Monitoring Program Summary.......
21 In addition, the following tables are in the Appendix:
Appendix A A-1 Crosscheck program results, milk and water samples, 1975-83.... A-3 A-2 Crosscheck program results, thermoluminescent dosimeters (TL0s).. A-9 j-Ns'.
Appendix C
.C-1 Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas... C-2 V
- p.
U 1.0 INTR 06UCTION The Kewaunee Nuclear Power Plant is a 535 megawatt pressurized water reactor located on the Wisconsin shore of Lake Michigan in Kewaunee County.
The Kewaunee Nuclear Pwer Plant became critical on March 7,1974.
Initial power generation was achieved on April 8,1974, and the Plant was declared commer-cial on June 16, 1974.
This report sumarizes the environmental operation data collected during the period January - December 1983.
Wisconsin Public. Service Corporation, an operating company for the Kewaunee Nuclear Power Plant,. assumes the responsibility for the environmental program at the Plant and any questions relating to this subject should be directed to L
them.'
2 i
l l'
L
! G-LU l
l 1
l-
i
.U+
2.0
SUMMARY
Results of sample analyses 'during the period January - December 1983 are summarized in Table 4.5.
Radionuclide concentrations measured at indicator locations are compared with levels measured at control locations and in preoperational studies.
The comparisons indicate background-level radio-activities in all samples collected with the following exceptions:
1.-
Trace amounts of cobalt-58 and cobalt-60 were detected in one of ten periphyton samples, and trace amounts of cobalt-58, cobalt-60, and Cs-134 were detected in
{i/ -
several bottom sediment samples.
The presence of these isotopes in these samples is probably plant related.
2.
One water sample collected at the discharge.(K-Id) on November 1,1983 and one sample collected at Two Creeks Park (K-14) on October 3, 1983 had tritium levels of 3140 and 1000 pCi/l above the background ' level of 280 pCi/1.
The elevated level in sample collected at the discharge is attributable to the Kewaunee Nuclear Plant Operation, but' constitutes only 0.1% of the maximum permissible concentration of 3,000,000 pC1/1 established in the.10 CFR 20' Document.
The source of the elevated level in the sample collected at K-14 is not clear since this point is equidistant from the Kewaunee and Point Beach-Nuclear Plants, either one of which, or both, could have been the source of the elevated tritium level.
(
L).
2 1
-~,,.m.
n n,
,,n----w.--w
,-w.,.
l.
.3.0 RADIOLOGICAL SURVEILLANCE PROGRAM Following _ is a description of the - Radiological Surveillance Program and its execution.
L3.1 Methodology-The : sampling locations.. are shown 'in Figure 4-1.
Table '4.1 describes sthe locations, lists for each its direction and distance from the reactor, and indicates which are indicator and which are control locations.
G-v The sampling program monitors the air, terrestrial, and aquatic environ-ments-.
The types.of-samples collected at each location and the frequency of collections.-are presented _in Table 4.2 using sample codes defined in Table J4.3.
The - collections. and : analyses that comprise the program are
. uescribed. below.
' Finally, the execution ~of the program in the ' current-reporting year is discussed.
3.1.1:
The Air Program Airborne'Particulates The airborne particulate samples are collected on 47 mm diameter glass' fiber: filters at a volumetric rate of approximately one
^
-cubic foot per minute.. The filters are collected weekly from six locations-(K-1f,~K-2,_K-7, K-8, K-15, and K-16), and dispatched by mail to TIML for. radiometric analysis. The material on the filter is counted -for-gross ' alpha and beta activity approximately five days after receipt to allow for decay of naturally-occurring f
.short-lived radionuclides.
Quarterly composites from each sampling location are analyzed for gamma-emitting isotopes by a germanium detector.
9m_
J.
3-
3
=-
1; i
,l. "
\\
Airborne Iodine Charcoal filters ar located -at locations K-1f, K-2, K-7, K-8, K-15, and K-16.
The filters are changed bi-weekly and analyzed for iodine-131 immediately after arrival at the laboratory.
Ambient' Gamma Raaiation - TLDs The integrated gamma-ray background is measured at air sampling locations (K-1f, K-2, K-7, K-8, K-15, and K-16) and at four milk sampling locations (K-3, K-4, K-5, and K-6) with thermoluminiscent-dosimeters (TLDs).
CaF :Mn bulb TLDs are exchanged quarterly 2
and annually.
Precipitation Monthly composites of precipitation samples collected at K-11 are analyzed for tritium activity by liquid scintillation technique.
3.1.2 The Terrestrial Program Milk V
Milk samples are collected weekly (one gallon from each location) from May through October and monthly (two gallons from each location) during the rest of the year from four herds that graze within four miles of the reactor site (K-4, K-5, K-12, and K-19) and from two herds that graze between four and ten miles from the reactor site (K-3 and K-6).
The milk samples are analyzed for iodine-131, strontium-89 and -90, cesium-137, barium-140, potassium-40, calcium, and stable potassium.
Well Water One gallon water samples are collected quarterly from four off-site wells located at K-10, K-11, K-12, and K-13.
Monthly one-gallon water samples are collected from two on-site wells located at K-19 and K-lh.
The gross alpha and beta activities are determined on the total residue of each water sample.
The concentration of potassium-40 is calculated from total potassium, which is determined by flame photometry on all samples. The tritium levels in quarterly composites of monthly on-site samples from K-1g are determined by liquid scintillation technique.
Qua.-terly composites of monthly grab samples of water from one
,3 on-site well (K-1g) are analyzed for strontium-89 and strontium-90.
Q.;'.
4
-f
e Ql
-Domestic Meat G
_ Domestic meat samples '(chickens) are obtained annually (in the
~
third quarter) at locations. K-20, K-24,. K-25, and K-27..
The flesh is separated ~ from the bones, gamma scanned, and analyzed
=
for gross al pha, gross beta, _ strontium-89, and strontium-90 activities.
- Ems, Eggs ' are. collected 'quacterly at Location K-27.
The samples
- are gamma t sca_nned.and ' analyzed for gross alpha, gross beta, strontium-89, and strontium-90 activities.
-Vegetables
~
Vegetable samples _ (5 varieties) are collected at locations K-17 and K-26, and two _ varieties of grain, if available, at location
(
K-23.
The samples are gamma scanned and analyzed for gross
'. al ph a, gross beta, strontium-89, and strontium-90. activities.
Grass and Cattl'e Feed 5
Grass samples are collected during the second, third and fourth
~
quarters ' from two on-site locations (K-lb" and K-lf) and from six dairy f arms (K-3, K-4, K-5, K-6, K-12, and K-19).
The
. samples are gamma scanned and analyzed for gross alpha, gross N
beta, strontium-89,. and strontium-90 activities.
During the first quarter cattle feed is collected _ from the same six dairy farms,.and the same analyses-'are performed.
Soil
-Soil samples are col.lected ' twice a year on-site at K-lf and from the six dairy - f arms (K-3, K-4, - K-5, - K-6, ~ K-12, and K-19).
4 The samples arei gamma scanned and analyzed for gross alpha, gross beta, strontium-89, and strontium-90 activities.
h 3.1.3 The Aquatic Program e
-Surface Water One-gallon water samples are taken monthly f rom three locations g,1
.on Lake Michigan:
- 1) at the point 'where the condenser water is
. discharged -into Lake Michigan - (K-Id); 2)_ at-Two Creeks Park
-(K-14) -located 2.5 miles south of -the reactor site; and 3) at
.the Rostok water intake (K-9)' located 11.5 miles north of the reactor _ site.
Additionally, one-gallon water samples are taken f -
monthly from three creeks that pass through the site (K-la, K-lb, and K-le).
Samples from ' North and Middle Creeks (K-la, s-K-lb) are collected 'near the mouth of each creek.
Samples from the. South Creek (K-le) are collected about ten feet downstream from the point where the o tflows from the two-drain pipes meet.
5-
V The water samples are analyzed for gross alpha and gross beta activity in the total residue, dissolved solids, and suspended solids.
The concentration of potassium-40 is calculated from total potassium, which is determined by flame photometry.
The tritium activity in the Lake Michigan samples is determined by liquid scintillation technique.
Quarterly composites of monthly grab samples from Lake Michigan are also analyzed for strontium-89 and strontium-90.
Fisn Fish samples (2 species) are collected in the second, third, and fourth quarters at Location K-1d.
The flesh is separated from the bones, gamma scanned and analyzed for gross alpha and gross.
beta activity.
Ashed bone samples are analyzed for gross alpha, gross beta, strontium-89 and strontium-90 activities.
Slime Slime samples are collected during the second and third quarters from three Lake Michigan locations (K-Id, K-9, and K-14), and from three creek locations (K-la, K-lb, and K-le), if available.
The samples are ar alyzed for gross alpha and gross beta activi-ties. If the quantity is sufficient, they are also gamma scanned f
and analyzed for strontium -89 and strontium-90 activities.
L]j Bottom Sediments Bottom sediments are collected four times a year from five locations (K-1c, K-1d, K-lj, K-9, and K-14).
The samples are analyzed for gross alpha and gross beta activities and for strontium-89 and strontium-90.
Each sample is also gamma scanned.
Since it is known that the measured radioactivity per unit mass of sediment increases with decreasing particle size, the sampling procedure is designeo to assure collection of very fine particles.
3.1.4 Program Execution Program execution is summarized in Table 4.4.
The program was executed as described in the preceding sections with the following exceptions:
(1) Precipitation sample was not collected in November 1983, because it was a dry month.
(2) No buckwheat was collected at location K-23 because it was not grown there in 1983.
(Q (3) Only one species of fish (trout) was collected in the third
/
quarter. The bottom feeders could not be obtained because of adverse lake conditions.
6
.,q Q
3.1.5 Program Modifications There were no program modifications during 1983.
3.2 Results and Discussion
.The results for the reporting period January to December 1983 are presen-ted in summary form in Table 4.5.
For each type of analysis of each sampled medium, this table shows.the annual mean and range for all
~
indicator locations and for all control locations.
The location with the highest annual mean_ and the results for this location are also given.
The discussion of the results has been divided into three broad cate-gories: _ the air, terrestrial, and aquatic environments.
Within each category, samples will be discussed in the order listed in Table 4.4.
Any discussion of previous environmental data for the Kewaunee Nuclear Poer Plant refers to data collected by Hazleton Environmental Sciences, NALC0 Envirc.' mental Sciences, or Industrial BIO-TEST Laboratories, Inc.
The tabulated results of all measurements made in 1983 are not included in this section, although references to these results will be made in
-,]
the discussion.
The complete tabulation'of the 1983 results is contained
- \\s -
in Part II of the 1983 annual report on the Radiological Monitoring Program for the Kewaunee Nuclear Power Plant.
3.2.1 Atmospheric Nuclear Detonations There were no reported atmospheric nuclear tests in 1983.
The last reported test was conducted by the People's Republic of China on October 16, 1980.
The reported yield was in the 200 kiloton to 1 megaton range.
O 7
- O,
.L);
3.2.2 The Air Environment Airborne Particulates For air particulates, both gross alpha and gross beta measurements yielded annual means that were nearly identical for.the indicator and centrol locations. Mean gross alpha activity was slightly
. lower than in 1982 while mean gross beta activity was nearly indentical to'.that in 1982. The highest annual means for both gross alpha and gross beta were measured at co.ntrol location K-16,-26 miles NW of the station.
Gross. alpha and beta activities at all locations were also analyzed by quarters.
The activity rose slightly by the end of the year.
There was no clear cut evidence of the spring peak, which has been observed almost annually (1976 and 1979 were exceptions) for many years (Wilson et al.,
1969).
The spring peak has been attributed to fallout of nuclides from the stratos-phere-(Gold et al., 1964).
Gamma spectroscopic. analysis of quarterly composites of air particulate filters yielded similar results.for indicator and
-O) -...
control locations.
Berylium-7, which is produced continously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih, N,_
1955), was detected in fourteen of twenty-four samples and was-the only gamma-emitting isotope detected.
There was no indica tion of.a station effect on the data.
All other gamma-emmitting isotopes were below their respective LLD limits.
Airborne-Iodine Bi-monthly levels of airborne iodine-131 were below the lower limit of' detection (LLD).of 0.01 pC1/m3 at all locations.
Thus, there is no indication of an effect'of the plant operation on the local air environment, Agrbient Gama Radiation - TLDs Ambient gama radiation was monitored by TLDs at eleven locations:
four indicator and seven control.
4 f/T u.
8
- ,-.4
\\
The quarterly TLDs at the indicator locations measured a mean dose equivalent of (50.4i7.2)* mR/365 days, in agreement with the mean at the control locations of (51.316.2) mR/365 days, and were slightly lower than the means obtained in 1980 (72.0 and 75.8 'mR/365 days, respectively), in 1981 (61.2 and 63.1 mR/365 days, respectively), and in 1982 (55.2 and 56.1 mR/365 days, respectively).
The quarterly measurements agreed with the annual measurements which were (51.516.7) mR/365 days, for the indicator and (55.518.2) mR/365 days for the control locations.
All these values are slightly lower than the United States average value of 78 mR/ year due to natural background radiation (National Council on
' Radiation Protection and Measurements, 1975).
The highest means for the quarterly and annual TLDs were 60.2 and 67.5 mR/365 days and occured at control locations K-3 and K-8, respectively.
Precipitation Precipitation was monitored only at an indicator location, K-11.
Tritium was detected in four samples and averaged 200 pCi/1. 'This level of activity is expected in the precipitation and is attribut-able to the nuclear tests explosions.
tO V
3.2.3 The Terrestrial Enviror. ment Milk Of the 192 analyses for iodine-131 in milk all were below the LLD level of 0.5 pCi/1.
Strontium-89 activity was below the LLD level of 1.7 pCi/l in all samples.
Strontium-90 was found in all scmples.
The mean values were identical for all indicator and control locations (2.0 pCi/1).
Barium-140 activity was below the LLD of 10 pCi/l in all samples.
Cesium-137 activity was also below the LLD of 10 pCi/l in all samples.
Potassium-40 results were near ly ' identical at both the indicator and control locations and were essentially identical to the levels observed in 1978, 1979, 1980, 1981, and 1982.
- Unless otherwise indicated, uncertainties of average values are standard deviations of the individual measurements over the period averaged.
Uncer-q tainties of individual measurements ~ represent probable counting errors at the 95% confidence level.
9
i g!
i J Due to the chemical similarities between strontium and calcium,
~and cesium and potassium, organisms tend to deposit cesium-137 in the soft tissue and muscle and strontium-89 and -90 in the bones.
Consequently, the ratios of strontium-90 ~ activity to the weight of calcium in milk and cesium-137 activity to the weight of potassium in milk were monitored in order to detect potential environmental accumulation of these radionuclides.
No statis-tically significant variations in the ratios were observed.
The measured concentrations of stable potassium and calcium are in agreement with previously determined values of 1.50f0.21 g/l and 1.16i0.08 g/1, respectively (National Center for Radiological Health,1968).
Well Water Gross alpha activity in weil wLter was below the LLO level of 2.9 pCi/l in all but one samples. Thc detected activity was 3.9 pCi/1.
Gross beta activity in well water was 2.2 pCi/l in samples from the control location.
The mean value for all indicator locations was 2.9 pCi/l and was nearly identical to the values observed in 197,
1978,1979,1980,1981, and 1982 (3.3 pCi/1, 3.4 pci/1, 3.0 pCi/1, t'l 3.0 pCi/1, 3.6 pCi/1, 3.2 pCi/1, respectively).
L j',
Tritium activity in the on-site well (K-1g) was below the LLD of 100 pCi/l in all samples.
The ' activities of strontium-89 and strontium-90 in well water were below their respective detection limits.
Potassium-40 levels were quite low (under 3.0 pCi/1), in agreement with the previously measured values.
Domestic Meat In meat (chickens), gross alpha activity was similar at both indicator 'and control locations (0.17 and 0.21 pCi/g wet weight, respectively).
Gross beta activity averaged 3.11 pCi/g wet weight for indicator locations and 2.84 pCi/g wet weight for control locations.
Strontium-89 and strontium-90 activity was below the LLD level of 0.006 and 0.004 pCi/g wet weight, respectively, in all samples. Gamma-spectroscopic analysis showed that most of the beta activity was due te naturally occurring potassium-40.
All other gamma-emitting isotopes were below their respective LLD limits.
10
,----m 4w.,
e t
-~wt e e e ve t ---
f
\\
V Bn In egg samples, the gross alpha activity averaged 0.070 pCi/g wet weight. Gross beta activity averaged 1.21 pCi/g wet weight, about equal to the activity of the naturally occurring potassium-40 observed in the samples (1.E8 pCi/g).
The levels of strontium-89 and strontium-90 and all other gamma-emitting isotopes were below their respective LLD's.
Vegetables In vegetcbles, alpha activity averaged 0.20 and 0.16 pCi/g wet weight in indicator and control samples, respectively.
Gross beta activity was slightly higher at the indicatc location than at the control location and was due primarily a the potassium-40 activity.
Strontium-89 activity was below the LLD of 0.004 pCi/g wet weight in all but one sample. The detected activity was barely above the LLD and was 0.007 pCi/g wet weight in a control sample.
Strontium-90 activity was lower at the indicator location than at control locations (0.004 pCi/g wet weight and 0.008 pCi/g wet weight, respectively).
All other gamma-emitting ' isotopes were below their respective LLD levels.
The sample of oats was of
[]
similar composition but the activity was slightly higher due to the v
lower water content of the grain in comparison with the vegetables.
Grass and Cattle Feed In grass, gross alpha activity was essentially identical at both indicator and control locations (0.6 and 0.5 pCi/g wet weight, respectively). Gross beta activity was slightly higher at indica-tor locations (5.8 pCi/g wet weight) than at the control locations (5.4 pCi/g wet weight) and in both cases was predominantly due to
. naturally occurring potassium-40 and bery111um-7. All other gamma-emitting isotopes were below their respective LLD's. Strontium-89 was detected in one of twenty-four samples and was 0.082 pCi/g wet weight.
Strontium-90 activity was detected in fifteen of twenty-four samples and was higher at indicator than at control locations (0.032 and 0.016 pCi/g wet weight, respectively).
Presence of radiostrontium in some of the samples is attributed to the fallout from nuclear tests.
For cattlefeed, the mean gross alpha activity at indicator loca-tions was 0.40 pCi/g wet weight and 0.49 pCi/g wet weight at cont:ol locations. Mean gross beta activity was higher at control locations (9.95 pCi/g wet weight) than at indicator locations (8.C6 pCi/g wet weight). The highest gross beta level was in the sample
{g) from indicator location K-4 (13.67 pCi/g wet weight), and reflected the high potassium-40 level (11.40 pCi/g wet weight) observed in 4
9 11
(~
\\_- -
the sample.
The pattern was similar to that observed in 1978, 1979, 1980, 1981 and 1982.
Strontium-89 levels were 0.068 pCi/g wet weight at indicator locations, and 0.036 pCi/g wet weight at control locations. Strontium-90 activity was essentially identical at both indicator and control locations (0.079 and 0.078 pCi/g wet weight, respectively).
The presence of the radiostrontium is attributable to the fallout from the previous nuclear tests.
All other gamma-emitting isotopes we.e below their respective LLD levels.
Soil No significant differences were found between indicator and control values in soil samples.
The difference of 0.6 pCi/g dry weight in mean gross alpha activity between indicator locations and control locations is not statistically significant because the counting uncertainties of the individual measurements are typically 3-5 pCi/g dry weight.
Mean gross beta levels were similar at both indicator and control locations (21.7 and 25.4 pCi/g dry weight, respectively), and is primarily due to the potassium-40 activity.
Strontium-89 was below the LLD level of 0.10 pCi/g dry weight in all samples.
Strontium-90 was detected in all samples and was
(~ ~N identical.at both control and indicator locations, 0.11 pCi/g wet
\\_/
weight.
Cesium-137 was detected in most of the samples and was slightly higher at control locations than at indicator locations (0.52 and 0.38 pCi/g dry weight, respectively).
All other gamma-emitting isotopes were below their respective LLD's. The levels of detected activities were similar to those observed in 1979, 1980, 1981,'and 1982.
3.2.4 The Aquatic Environment Surface Water In surface water, the gross alpha activity in suspended solids was detected in three of seventy-two samples and averaged 1.0 pCi/1.
In dissolved solids gross alpha activity was below the LLD of 5.5 pCi/l in all samples.
Mean gross beta activity in suspended solids was below the LLD of 2.7 pCi/l at all locations.
Mean gross beta activity in dissolved solids was higher by a factor of two at indicator locations (5.1 pC1/1) as compared to the control locations (2.6 pCi/1) and was nearly identical to the activities observed in 1978 (5.4 and 2.7 pCi/1),1979 (5.7 and 2.7 pCi/1),1980 (5.1 and 2.7 pCi/1),1981 (4.3 and 2.7 pCi/1), and 1982 (4.9 and 2.4 pCi/1).
The control sample is the Lake Michigan water which varies very little in (f- )
activity during the year, while indicator samples include two creek locations (K-la and K-le) which are much higher in activities and 12
i k
L) exhibit large month-to-month variations in gross beta activities.
The K-la creek drains its water from the surrounding fields which are heavily fertilized and K-le creek draws its water mainly from the Sewage Treatment Pond No.1.
In general, gross beta activity levels were high when potassium-40 levels were high and low when potassium-40 levels were low indicating that the fluctuations in beta activity were due to variations in potassium-40 concentrations and not to plant operations. The fact that similar fluctuations at these locations were observed in the pre-operational studies conducted prior to 1974 supports this assessment.
Annual mean tritium activity was slightly higher at the indicator locations than at the control location (980 and 280 pCi/1, respec-tively). The elevated mean activity at the indicator locations was primarily due to the activity in two samples as compared to the activity level of 280 pCi/l in Lake Michigan; one collected at discharge on November 1,1983 (3420 pCi/1), and one collected at K-14 on October 3, 1983 (1280 pCi/1). The elevated annual mean of 980 pCi/l (or 700 pCi/l above background level) in the discharge water is attributable to the plant operation but constitutes less than 0.03% of the maximum permissible concentration of 3,000,000 pCi/1 established in the 10 CFR 20 Document. The highest level of 3,140 pCi/1 above background _ level detected in the sample collected p)
November 1, 1983 constitutes 0.10% of the permissible level.
q Strontium-89 activity was below the LLD of 1.6 pCi/1 in all sam-ples.
Strontium-90 activity was detected in eleven of twelve samples and was slightly higher at indicator locations than at control location (1.0 and 0.7 pCi/1, respectively).
Fish In fish samples, gross alpha activity averaged 0.18 pCi/g wet weight in muscles and was below detection limits in all bone
' fractions.
In muscle, gross beta activity was primarily due to potassium-40 activity.
The average beta activity of 2.80 pCi/g wet weight was near the average of the 1973 range of 2.26 to 3.62 pCi/g wet weight. _The cesium-137 activity in muscle averaged 0.14 pCi/g wet weight and was nearly identical to the level observed in 1979 and 1980 (0.12 pCi/g wet weight in both years), 1981 (0.15 pCi/g wet weight), and in 1982 (0.17 pCi/g wet weight).
The strontium-89 level in bones was below the LLD of 0.44 pCi/g wet weight in all samples, while strontium-90 averaged 0.30 pCi/g wet weight.
This activity was near the lower limit of the 1973 range of 0.40 to 1.09 pCi/g dry weight and was similar or lower to the level found in 1980 (0.31 pCi/g-wet weight), in 1981 (0.58 pCi/g wet weight), and in 1982 (0.58 pCi/g wet weight).
O N.)
13
.o
)
Periphyton (Slime)
In periphyton (slime) samples, gross alpha activity. was nearly identical at both indicator and control samples (0.7 and 0.8 pCi/g wet weight, respectively).
Mean gross beta activity was lower at indicator than at control locations (2.4 and 4.9 pCi/g wet weight, respectively).
Strontium-89 activity was below the LLD level of 0.11 pCi/g wet weight in all samples.
Strontium-90 levels were slightly higher at indicator locations than at control locations, 0.046 versus 0.021.pCi/g wet weight.
Trace amounts of cobalt-58, and cobalt-60 were detected in one of ten samples.
Presence of
'these isotopes in slime is probably plant related.
All other gamma-emitting isotopes except naturally-occurring beryllium-7 and potassium-40 were below their respective LLDs.
Bottom Sediments In bottom sediment samples, gross alpha levels were below the LLD of 4.2 pCi/g dry weight in all samples but two.
The mean detected activity was 6.2 pCi/g dry weight.
The mean gross beta activity was slightly higher at indicator
' (~h locations than at the control location (6.5 and 6.1 pCi/;; dry
-V.
weight, respectively) and was due mostly to potarsium-40.
The difference is not' statistically significant.
Cesium-137 was detected in twelve samples and averaged 0.16 pCi/g dry weight.
The level was similar to the levels observed in 1979 (0.12 pCi/g dry weight), in 1980 (0.19 pCi/g dry weight), in 1981
.(0.18 pCi/g dry weight), and in 1982 (0.13 pCi/g dry weight).
Strontium-89 and strontium-90 levels were below their respective LLDs (0.030 and 0.021 pCi/g dry weight, respectively) in all samples.
Trace amounts of cobalt-58 (two samples), cobalt-60 (seven samples), and cesium-134 (one sample) were detected near the condenser discharge.
Presence of trace amount of these activation products in bottom sediments is probably plant ialated.
N.]\\.
14
y
,,.+,
.. - - + -
n
--u-.-
s.
aa
---a a,-
-a.
s.
,z.--
-.-e-nmm.-
+ -
-s
- --. _. : aa m s um n_.
a
4.a._--
a
-.._r>
d J
I i
I-i I
i 1
l 4.0 FIGURES AND TABLES t
e i
i I
k f
n l
l 9
J 15 l
l l
[
--,_.._-_-.-,.m_-__
I
- K-9' f
KEWAU\\EE e.:. -
NUCLEAR POWER PLANT j#.
..f
,:.K2 4s 4
., i.::.: M'.
f.
Kewaunee
..i
/
a 9
. East Krok
.==
y l
K-15 I Green Boy (K-16)
K **
26 Miles K-24%
- t. A eg
\\
k2b
,':lT MICHIGA N lu l
m g/
K-21(
stangeMile K-O K-5*
S k'$
m
_ :(_,,
U 3
U
\\
f' K-10 K 11 l
I O'
K-17
~
/ /'
j y v
's y N-27
~ K-23 islTE (e) a
'/ K-l 1,
s i
j K-12.'
h IK 7/,Jisch Mills \\ g-25 K-22 F g
Kewounee Co.
~
Manitowoc Co.
- V V
K-6 K-8
./.,
K-7 w
\\
N C$ksI 5 Y, d
K-13 I
N f**
g
- K-18 (K-2 6) k2)
A lo.7tni SS W 4.,
/
. i' SCALE IN MILES O
I 2
3 4
Figure 1.
Sampling locations, Kewaunee Nuclear Power Plant.
16
p
\\
s v '
j Table 4.1 Sampling locations,'Kewaunee Nuclear Power Plant.
Distance'(miles)b Code Typea and Sector Location K-1 Onsite la I
0.62 N North Creek Ib-1 0.12 N Middle Creek Ic I
0.10.N 500' north of condenser discharge
'Id I
0.10 E -
Condenser. discharge le 1
0.12 S South Creek If I
0.12 S Meteorological tower lg I
0.06 W South Well th I
0.12 NW North Well lj I
0.10 S 500' south of condenser discharge K-2 C
9.5 NNE WPS Operations building in Kewaunee K-3 C
6.0 N Lyle and John Siegmund farm, Route 1, Kewaunee K-4 I
3.0 N Dan Stangel farm, Route 1, Kewaunee K-5 I
3.5 NNW Ed Paplham farm, Route 1, Kewaunee K-6c C
6.5 WSW Leonard Berres farm, Route 1, Denmark K-7 I
2.75 SSW Earl Bruemmer farm, Route 3, Two Rivers K-8 C
5.0 WSW Saint Mary's Church, Tisch Mills X-9 C
11.5 NNE Rostok Water Intake for Green Bay, Wisconsin two miles north of Kewaunee K-10 I
15 NNE Turner farm, Kewaunee site K-11 1
1.0 NW Harlan Ihlenfeld farm K-12 I
1.5 WSW Lecaptain farm, one mile west of site K-13 C
3.0 SSW Rand's general store K-14 I
2.5 S Two Creeks Park, 2.5 miles south of site K-15 C
9.25 NW Gas Substation, 1.5 miles north of Stangelville K-16 C
26 NW WPS Division Office Building, Green Bay, Wisconsin K-17 I
4.25 W Jansky farm, Route 1, Kewaunee K-18 C
7.0 SSW Schmidt's Food Stand, Route 163 (3.5 miles south of "BB")
K-19 I
1.75 NNE Wayne Paral farm, Route 1, Kewaunee K-20 1
2.5 N Carl Struck farm, Route 1, Kewaunee K-23 I
0.5 W 0.5 miles west of plant, Kewaunee Site K-24 I
5.45 N Fectum farm, Route 1, Kewaunee K-25 C
2.75 WSW Wotachek farm, Route 1. Denmark K-26d C
10.7 SSW Bertler's Fruit Stand (8.0 miles south of "BB")
K-27 I
1.5 NW Schlies Farm, 0.5 miles west of K-11 a I = indicator; C = control b Distances are measured from reactor stack.
c The K-6 sampling location was changed on October 17, 1980 because the operator of Berres Farm retired.
Berres Fanm has been replaced by Novitski Farm, located 0.2 miles West of Berres Farm.
d Location K-18 was changed because the.Schmidts Food Stand went out of business and was replaced by j
Bertler's Fruit Stand (K-26).
1
M.
f k)
'm O -
^
. Table 4.2 Type'and frequency of. collection.
Frequency I-Location Weekly !Bi-weekly i Monthly Quarterly Semi-Annually l Annually!
K-1 f
lK-la.
SW l
- K-lb SW GRa.
SL '~
4
- K-1c i
.BSb
- K-Id
}SW BSb pia 3L
!K-le -
i SW i
SL l
-GRa TLD.
S0 TLD
- K-1f AP'
- Al -
i
.K-1g WW 3
- K-lh WW
!K-lj I
BSb i
,K-2 I
MIc GRa TLD CFd.
'K-3 S0 TLD
!K-4 l
'K-5 t
! -6 i
Mic j
.TLD K
- K-7 AP A1 j
i
+
TLD TLD
.I K-10 WW K-11 PR WW i
i K-12 MIc GRa CFd WW l
WW j
K-13 BSb K-14 St K-15 AP AI I
TLD TLD
!K-17 DM,VE i
I.K-18e i
i VE MIc l
GR8 CFd i
50 l
'K-19
- K-20 DM
.K-23 i
GRN K-24 DM l
K-25 DM K-26 VE K-27 EG a Three times a year, 2nd ( April, May, June), 3rd (July, Aug., Sept.), and 4th (Oct., Nov., Dec.) quarters.
b To be collected in May, July, Sept., Nov.
c Monthly from November through April; weekly from May through October.
d First (January, February, March) quarter only.
e Replaced by K-26 in sununer of 1982.
.- ~
2:
Table 4.3 Sample codes used in Table 4.2.
. Code Description AP' Airborne Particulate AI Airborne Iodine TLD Thermoluminescent Dosimeter PR Precipitation
.MI Milk WW Well Water DM Domestic Meat i-
.EG.
Eggs VE Vegetables
! p.
GRN Grain I
\\'-
GR Grass CF Cattlefeed l-SO Soil SW Surface Water FI Fish SL.
Slime BS Bottom Sediments l
i i
[..
(:
19 l:
_.. _. -, - - ~ _. _. _ _.,. _.. _ _ _ _.. _ - - _.. _.. _ _
. ~
r
~
Table 4.4. -Sampling summary, January - December 1983.
Collection Number of Number of
' Sample Type and Nurrber of Samples Samples Type Frequencya Locations Collected Missed Remarks Air Environment Airborne particulates C/W 6
312 0
Airborne iodine C/BW 6
156 0
TLD's C/Q 10 40 0
C/A
-10 10 0
Precipitation C/M 1
11 0
See text Page 6.
Terrestrial Environment Milk (May-0ct)
G/W 6
156 0
(Nov-Apr)
G/M 6
.36 0
Well water G/M 2
24 0
G/Q 4
16 0
m Domestic meat G/A 4
4 0
-Eggs G/Q 1
4 0
Vegetables - 5 varieties G/A 2
6 0
Grain - oats G/A 1
1 0
- buckwheat G/A 1
0 1
See text Page 6.
Grass G/TA 8
24 0
Cattle Feed G/A 6
6 0
Soil G/SA 7
14 0
Aquatic Environment Surface water G/M 6
72 0
Fish-2 varieties G/TA 1
5 1
See text Page 6.
Slime G/SA 6
12 0
Bottom sediments G/FA 5
20 0
a Type of collection is coded as follows:
C = continuous; G = grab. Frequency is coded as follows:
W = weekly; M = monthly; Q = quarterly; SA = semi-tunually; TA = three times per year; FA = four times per year; A = annually; BW = bi-weekly.
.s 7.
)
'O
\\j Table 4.5 Environmental Radiologica1' Monitoring Program Sunenary.
Name of facility Kewaunee Nuclear Power Plant Docket No. 50-305 Location of facility Kewaunee County, Wiscor. sin Reporting Period January-December 1983 (County, state)
Indicator
. Location with Highest Control Sample Type and Locationg Annual Mean Locations Number of Type Nisaber of Mean(F)
MeanU}
(Units)
Analysesa LLDb RangeC Locationd Range
' Mean(F)
Non-routine e
Range Results,
i.
I Airborne t GA 312 O.003 0.0032 (71/104)
K-16, Green Bay 0.0047(49/52) 0.0037 (166/208) 0 i particulates (0.0010-0.0093)$
26 mi NW
.(0.0010-0.0125) (0.0009-0.0125)
! (pCf/mJ) 0.018(95/104)ll K-16, Green Bay 0.021 (52/52) 0.019(199/208)l t
G8 312 0.004 O
(0.005-0.051) 26 mi NW (0.005-0.063) ! (0.004-0.063)
! GS 24 I
I I
j Be-7 0.054.I 0.085 (6/8)
K-8, St. Mary's Church 0.102 (3/4) 0.093 (8/16) 0
+
(0.061-0.110) !
5.0 mi WSW
.(0.060-0.127)'
(0.060-0.127)
I i
Nb-95 0.0046 '
<LLD I
<LLD 0
2 i
l_
{ Zr-95 0.0076
<LLD j
<LLD 0
i Ru-103
! 0.0053
<tLD l
(LLD 0
Ru-106 0.016
<LLD 0
<LLD f
Cs-137 0.021
<LLD l
<LLD 0
f Ce-141 0.0068l
<LLD
<LLD 0
Ce-144 0.012 ~l
<LLD l
<LLD 0
Airborne I-131 156 0.01
<LLD
. LLD O
i lodine I
i
- (pC1/m3) i Gansna 44 ! 5 12.6 (16/16) i K-3, Siegmund Farm 15.0 (4/4) 12.8 (28/28)
,TLD -Quarterly 0
4
, i (mrem /30 days) l (9.7-15.5 )
6.0 mi N (14.2 15.9)
(10.4-1C.2) 0 TLD-Quarterly l Gamma 11 5
50.4 (4/4)
K-3, Sieomund Farm 60.2 (1/1) 51.3 (7/7) 0 (mrem /365 days)
(42.5-59.8) 6.0 mi N
'(44.8-60.2)
TLD-Annual Ganea 11 5
51.5 (4/4)
K-8, St. Mary's Church 67.5(1/1) 55.5 (7/7) 0 (mrem /365 days)
(46.3-61.4) 5.0 mi WSW (45.1-67.5) r
_ f^
s
(,/
b' V
Table 4.5 (Continued)
Name of facility Kewaunee Nuclear Power Plant Indicator.
Location with Highest Control Sample Type and Locationg Annual Mean Locations-Number of Type Nunber of Mean(F)
Mean(F)
Mean(F)
Non-routine (Units)
Analysesa LLDb RangeC Locationd Range Range Resultse 1
f200(4/11)
Precipitation H-3 11 100 K-11, Inlenfeld Farm
.200(4/11)
None 0
(pCi/1)
(110-250)-
1.0 mi NW (110-250) t s
Milk I-131 192 0.5
<LLD None 0
j (pCi/1)
Sr-89 72 1.7
<LLD None i
0 e
Sr-90 72 0.5-2.0 (48/48)
K-12, Lecaptain Farm 2.5 (12/12) 2.0 (24/24) 0 (1.0-3.4) 1.5 mi WSW (1.6-3.4)
( 1.2-2.9) l GS 72 i j
K-40 50 1270 (48/48) i K-3, Siegmund Farm 1320(12/12)!
1280 (24/24) 0 (980-1700)
-l 6.0 mi N 1
(1150-1550)
(1110-1550)j i
Cs-137 10
<LLD l
l
<LLD
{
0 f
f Ba-140 10
<LLD
<LLD 0
(g/1)
K-steble 72 1.0 1.44 (48/48)
K-3, Siegmund Farm 1.50(12/12)'
1.46 (24/24)'
0 (1.11-1.93) 6.0 mi N (1.31-1.69)
(1.26-1.76);
g (g/1)
Ca 72 0.5 1.2 (48/48) i K-6. Novitsky Farm 1.3 (12/12) 1.2(24/24)!
0 (0.9-1.4) 6.7 mi WSW (1.0-1.7)
(1.0-1.7) i Well Water GA 40 2.9 3.9 (1/36)
K-lh, North Well j 3.9(1/12)
<LLD 0
(pC1/1)
Onsite, 0.12 mi NW l GB 40 0.5 2.9 (36/36)
K-lh, North Well l
3.7 (12/12) 2.2 (4/4) 0 (0.7-8.2)
Onsite, 0.1A mi NW (1.4-8.2)
(1.2-4.7)
H-3 4 '100
<tLD None 0
l K-40 40 0.10
! 1.6 (36/36)
K-lh, North Well 1.9 (12/12) 1.1 (4/4) 0 l
1 l
(flame)
! (0.9-2.4)
Onsite, 0.12 mi NW (1.3-2,4)
(0.9-1.5)
Sr-89 4 l 1.2
<LLD None 0
i i
Sr-90 4
0.6
<LLD None 0
i l
P
)
]
N
)
_/
Table 4.5 (continued)
Name of facility Ke aunee Nuclear Power Plant Indicator Location with Highest Control Sample Type and Locationg Annual Mean Locations Number of Type Number of Mean(F )
Mean(F)
Mean(F)
Non-routine (Units)
Analysesa LLDb RangeC Locationd Range Range Resultse Domestic Meat GA 4
0.03 0.17 (3/3)
K-25. Wotachek Farm 0.21 (1/1) 0.21 (1/1) 0 (chickens)
(0.13-0.20 2.~5 mi WSW (pC1/g wet)
GB 4
0.5 3.11 (3/3)
K-24. Fectum Fam 3.57 (1/1) 2.84 (1/1) 0 (2.95-3.57) 5.45 mi N Sr-89 4
O.006
<LLD
<LLD 3
0 i
I Sr-90 4
0.004
<LLD i
(LLD 0
i GS 4
Be-7 0.14 (LLD l
<LLD 0
t K-40 0.5 i
2.69 (3/3) l K-24, Fectum Fam j 3.40 (1/1) 2.93 (1/1) 0 l
(2.31-3.40) 5.45 mi N
^
l Nb-95 0.028
<LLD
<LLD I
O i
1 Zr-95 0.040
<LLD
<LLD 0
f Ru-103 0.022
<LLD
<LLD 0
I i
Ru-106 0.17
<LLD
<LLD 0
l I
j Cs-134 0.01F
<LLD
<LLD i
0 i
i
~
Cs-137 0.021 l
<tLD
<LLD 0
i Ce-141 l 0.034 (LLD
<LLD 0
i i
+
Ce-144 0.11
<LLD i
<LLD 0
I i
l 0.070 (4/4)
! K-27, Schlies Fam 0.070 (4/4) f Eggs GA 4
0.011 None 0
(pC1/g wet) j (0.049-0.107) l 1.5 mi NW (0.049-0.107)'
GB 4 ! 0.01 1.21 (4/4) l K-I7, Schlies Farm 1.21 (4/4)
None O
(0.87-1.40) l 1.5 mi NW l
(0.87-1.40) i Sr-89 4
0.005
<LLD I
None 0
l I
Sr-90 4
0.004
<LLD l
None 0
i GS 4
j j
Be-7 0.41
<LLD None O
K-40 0.01 1.28 (4/4)
K-27. Schlies Fam 1.28 (4/4)
None 0
(1.00-1.58)
,1.5 mi NW (1.00-1.58)
( ).
V,/~-
(f
(.
- r 44 Table 4.5 (Continued)
Name of facility Kewaunee Nuclear Power Plant
(,
~
Indicator Location with Highest t
- Contro',
1 Sample.
Type and Locationg Annual Mcan Lect.u ons Number of I Type Number of Mean(F)
MeantF )
.Fran(F)
Non-routine i (Units)
Analysesa
-LLDb RangeC Location -
Range Range' Results' d
' kg s Nb-95 0.067 (LLD
'None O
pCI/9 wet)
(cont d)
Zr-95 0.072 4LD None 0
I Ru-103 _
0.053
<LLD l
i None 0.
1 Ru-106 0.25 (LLD None 0
Cs-134 l
0.026
<LLD None
{
0
' Cs -144 0.16 ~
<LLD None 0
I f
t 1
i Vegetables i
GA 6'
0.02 0.20 (1/1)
! K-26, Bertler's Fruit 0.16 (5/5) 0.16 (5/5) 0' (pC1/g wet)
I Star.d 10.7 mi SSW (0.04-0.26).
(0.04-0.26)
(
GB 6i. 1.0 2.67 (1/11
! K-26, Bertler's Fruit:
2.26 (5/5) 2.26 (5/5) 0 i
~!
Stand, 10.7 mi SSW i (1.09-3.95)
(1.09-3.95)i Sr-89 6
0.004 l
<LLD -
<LLD 0
+
r I
[
Sr-90 6
0.001 0.004 (1/1)
K-26. Bertler's Fruit.
0.005 (5/5) 0.005 (5/5) ;
O Stand, 10.7 mi SSW (0.002-0.008)
(0.002-0.007)'
GS 6
I I
i Bc-706 0.12
<LLD
<LLD 0
1 K-26, Bertler's Fruit 2.08 (5/5) 2.08 (5/5) !
0 f
.63 (1/1)
K-40 0.75
-Stand, 10.7 mi SSW (0.88-3.54)'
(0.88-3.54)t l
Nb-95 0.018 !
<LLD f
<LLD-0 I
Ru-103 0.014
<LLD
<LLD 0
Ru-106 0.11
<LLD 1
<LLO O
<LLD 0
i Cs-137 0.013
<LLD Ce-141 0.024
<LLD
<LLD 0
Ce-144 0.077
<LLD
<LLD 0
. +
_ f~
N,l -
N.)
Table 4.5 (continued)
Name of facility Kewaunee Nuclear Power Plant Indicator Location with Highest Control Sample Type and Locationg Annual Mean Locations Number of Type Nunter of Mean(F)
Mean(F)
Mean(F) en-routine (Units)
Analysesa-LLDb RangeC Locationd Range Range Resultse iGrain - Dats GA j.
(pCi/g wet)
'1 0.1
' 0.2 (1/1)'
K-23, Kewaunee Site 0.2(1/1) i tune 0
~l l
0.5 mi ';
GB 1
0.1 6.1(1/1)
K-23, Kewaunee Site 6.1 (1/1).
None 0
0.5 mi W I
Sr-89 1
0.012
<LLD None 0
l t
Sr-90 1 ! 0.01 0.054 (1/1)
K-23, Kewaunee Site 0.054 (1/1) t;one 0
I 0.5 mi W g
j i
GS
~1 1
k
]
j None 0
l Be-7 0.50
! 0.79 (1/1) lK-23,KewauneeSite '0.79(1/1)
'l None 0
j j
0.5 mi W t
j K-40 0.1 l 3.54 (1/1) l K-23, Kewaunee Site l 3.54 (1/1)
None 0
}
t 0.5 mi W i
Nb-95 0.C14
<LLD I-None 0
i ro Zr-95 0.045
<LLD l
None 0
l w
Ru-133 0.019
<LLD f
None 0
Ru-106 0.011
<LLD l
None O
}
t Ce-141-0.036
<LLD j
None 0
Ce-144 0.075
<LLD None 0
I i
,Cattlefeed GA 6
0.24 O.40(2/4) lK-6,NovitskiFarm 0.49 (1/1) 0.49 (1/2) 0 l
j j (pC1/g wet) l (0.33-0.46) g l
l 6.7 mi WSW GB 6
0.2 I 8.06 (4/4)
(
K-4, Stangel Farm 13.67 1/1) 9.95 (2/2) 0 l
! (2.92-13.67) 3.0 mi N (7.83-12.07)
}
Sr-89 6
0.008 0.068 (3/4)
K-4 Stangel Farm 0.089(1/1) 0.036 (2/2) 0 (0.046-0.089) 3.0 mi N (0.026-0.046; f0.01
! 0.079 (4/4)
K-4. Stangel Farm 0.117 (1/1)
Sr-90 6
0.078(2/2))f 0
1 i
- (0.027-0.117) 3.0 mi N (0.059-0.097 j
i GS 6 !'
1 Be-7 i 0.37
<LLD
<LLD 0
4
- l.
,A
~'
j~,
N.Y I
Table 4.5 (continued)
Name of facility Kewaunee Nuclear Power Plant Indicator Location with Highest Control Sample ~
Type and Locationg Annual Mean Locations Number of _ ~
Type Nua6er of Mean(F)
Mean(F)
Mean(F)
(Units)
'Analystsa LLDb RangeC Locationd Range Range '
Non-routine,
e Resultte *I
- /
~{
'r Cattlefeed~
K-40 1.0 6.71 (4/4)
K-4. Stangel Fars 11.4 (1/1) -
7.72 (2/2) 0-1 r
(pCf/9w)et). I}
(2.46-11.40) 3.0 mi N (5.67-9.76)'
fcent d 8
Nb-95 0.073
<LLD
- J -
<LLD 0-
+
,f s
l _ Zr-95 0.086
<LLD
{
<LLD 0
1 l
.Ru-103 0.049
<LLD F
(LLD 0
f 4.
l j,'
f,
<tLD r
0-Ru-106 -
0.31 (LLD
'/
i l.
l Cs-134 i
'O.027'l
<LLD (LLD 0
i Cs-137 0.031 j
<LLD l
<LLD O
t
- Ce-141 0.088
<LLD l
<LLD 0
i l
j l
Ce-144 0.16
<LLD
<LLD 0
i ro cn 24,
0.2 l 0.6 (17/18)
K-1f, Meteorolo-0.8 (2/3) 0.5 (6/6) 0 Grass GA i
(pCf/g wet)
(0.2-1.3) gical Tower (0.4-1.3 )
(0.2-0.8) 3 l
0.12 mi S j
i GB 24 r 1.0 l 5.8 (18/18)
K-5, Paolham Farm 7.1-(3/3) 5.4 (6/6)
O j
l (2.1-8.7) 3.5 mi NNW (6.0-8.7 l
(2.8-7.1) 4 t
Sr-89 24 0.033 1 0.082 (1/18)
- K-lb, Middle Creek 0.082 (1/3)
<tLD 0
t Onsite, 0.12 mi N t
J l
I i
Sr-90 24 i 0.015 0.032 (12/18) t K-lb, Middle Creek 0.054 (3/3) 0.018 (3/6) l 0
l I (0.016-0.083)
Onsite, 0.12 mi N (0.016-0.020) i (0.035-0.083)i l
I GS 24 i
Be-7 0.59 1.50 (12/18)
K-1f, Meteoroto-2.40 (2/3) 0.72 (1/3) 0 (0.61 -3.95) gical Tower i (0.84-3.95) 0.12 mi 5 K-40 0.1 4.52 (18/18)
K-5, Pap 1 ham Farn 5.55 (3/3) 5.14 (6/6) 0 (1.66-6.97) 3.5 mi NNW (5.41-5.68)
(4.27-6.42)
Nb-95 0.10
<LLD
<LLD 0
l Zr-95 0.10
<LLD
<LLD 0
Ru-103 0.10 (LLD
<LLD 0
Ru-106 0.29
<LLD
<LLD 0
m 7
)-~
w]
_\\ )
Table 4.5
'(Continued)-
Name of facility
. Kewaunee Nuclear Power Plant
\\
l Indicator i
Location with Highest.
Control
. Nummer of !
f Annual Mean Locations Sample.
Type and Locationg-Type-Number of Mean(F) l Mean(F) l Mean(F) hun-routine!
(Units)
Analysesa LL@ -
RangeC'-
I Locationd Range i
Range Resultse t
<LLD 0
1 Grass Cs-137 0.03
<LLD (pC1/g dry) l
<LLD C
j (cont'd)
Ce-141 0.24 (LLD Ce-144 0.20
<LLD' j
<LLD 0
I' (pC1/g dry) (
(4.0-8.6) i 3.5 mi NNW I (7.9-8.6)
(4.3-7.2) l
. Soil I GA 14 4.0 6.4 (5/10)
! K-5, Pap 1 ham Farm
- 8.2(2/2) 5.8(3/4)-
0 r-
! GB 14 1.4 21.7(10/10)
K-3, Siegmund Fars 76.6 (2/2) 25.4 (4/4) 0
, (13.6-29.9) 6.0 mi N (22.9-30.3) 1 (18.7-30.3) t i
[
l Sr-89 14 ; 0.10 (LLD 0
<LLD t
14 0.02 0.11(10/10)
' K-12. Lecaptain Fara 0.24(2/2) 0.11(4/4) 0 8
Sr-90 i
(0.03-0.34)
~ 1.5 at WSW -
(0.14-0.34)
(0.06-0.15) i i
i GS 14 l
l l
m i
i I
<LLD 0
l N
Be-7 0.97
<tLD K -40 1.4 19.3 (10/10)
. K-5, Paplham Farm
- 24.2 (2/2) 18.9 (4/4),
O l
r (11.7-26.1) 3.5 mi NNW
- (23.5-25.0)
(15.3-22.8)l j
<LLD I
O Nb-95
.0.11
<LLD f
i
<LLD 0
i t
Zr-95 0.16
<LLD (LLD 0
Ru-103 0.11 (LLD
<LLD 0
I Ru-106 0.67
<LLD Cs-137 0.06 0.38 (8/10)
K-6, Novitsky Farm 0.69 (2/2) 0.52 (4/4) 0 l
(0.08-0.75)
, 6.7 mi WSW (0.43-0.95)
(0.28-0.95) l t
Ce-141 0.12 (LLO
<LLD 0
Ce-144 0.30 (LLD
<LLD 0
1 1
~
O uI
.J 4
Table 4.5 2(Continued)
~ Kewaunee Nuclear Power Plant fiame of facility
-l Indicator-Location with Highest controi Location Annual Mean l
Locations
' Muur of Sanple Type and-Type Mean(F)g (Units)..
Museer of Mean(F)
Mean(F)
Non-routine Analysesa LLDb-RangeC Locationd Range Range Resultse 1
Surface Water <
GAISS)
'72 i 0.6 1.0 (3/60)
K-14 Two Creeks Park 1.4 (1/12)
<tLD-0 l(pCI/1)
.l l
(0.7-1.4) 2.5 mi S 4
I GA(DS) 72 5.5
<LLD
<LLD ~
0 GA(TR) 72 '
6.0
<LLD
<tLD 0
GB(SS) 72 2.7
<LLD
<LLD 0
1 i
f GB(DS) 72 '
0.5 4.9 (60/60),
10.9 (12/12) 2.6 (12/12);
O i
K-la, North Creek, i
(1.2-27.2)
Onsite, 0.62 mi N (6.8-27.2)
(1.6-3.0) ;
i GB(TR) 72 1.0 5.1 (60/60) l K-la North Creek, 11.2 (12/12) !
2.6 (12/12).
0 3
(1. 6-28.2 )
Onsite, 0.62 mi N (6.8-28.2) l
- (1.6-3.0 )
+
t H-3 36. 220 980 (6/24)
K-Id, Condenser Dis-1350 (3/12) 280 (3/12) 0 l
1(270-3420) charge, Onsite (270-3420)
(270-290)
?
{
r 0.10 mi E l
ro 12 f 1.6 f
Sr-89
<LLO I
<LLD 0
4, l
t Sr-90 12 i 0.5 j 1.0 (7/8) l K-14, Two Creeks Park 1.1 (4/4) 0.7 (4/4) ;
O
!(0.6-1.4) 2.5 mi S I (0.6-1.4)
(0.5-0.7) !
t i
i K-40 72 0.5 3.4 (60/60)
K-la, North Creek 9.0 (12/12) 1.0 (12/12).
0 (flame) l (0.8-25.6)
Onsite, 0.62 mi N (4.7-25.6)
(0.8-1.3)
I Fish-Muscle GA 5
0.01 0.18 (3/5)
K-Id, Condenser Dis ! 0.18 (5/5) i None 0
I (pC1/g wet)
(0.08-0.26) charge. Onsite (0.08-0.26) j l
4 0.10 mi E f
t j
GB 5
1.0 2.80 (5/5)
K-Id, Condenser Dis-2.80 (5/5) l None 0
(1.48-3.82) charge, Onsite (1.48-3.82) 0.10 mi E i
1 l
Be-7 l
0.34
<1LD None 0
l K-40 l
1.0 3.02 (5/5)
K-1d, Condenser Dis-3.02 (5/5)
None 0
]
i (2.66-3.20) charge. Onsite (2.66-3.70) f 0.10 mi E 4
)
i i
Nb-95 0.077
<LLD None O
t f
3 Zr-95 0.067
<LLD None 0
r I;
b l
~
,m
,]
LA
)
Table 4.5
'(continued)
Name of factitty Kewaunee Nuclear Power Plant Indicator Location with Highest i
Control Sample Type and Locationg Annual Mean I
Locations Museer of Type Museer of Mean(F)
Mean(F)
Mean(F)
Non-routine (Units)
Analysesa LLDb RangeC Loca tiond Range Range Results' i
None 0
Fish-Muscle Ru-103 0.070 1 4LD (pC1/9w)et) l None-O (Cont d Ru-106 0.17 4LD g
g l
Cs-137 0.02 0.14 (4/5)-
K-id, Condenser Dis : 0.14 (4/5)
I O
None j
(0.07-0.20) charge Onsite (0.07-0.20)
I
[
0.10 mi E
{
Ce-141 I
0.13 l
<LLD None 0
^
I 1
O Ce-144 l
0.10 4LD None None 0
Fish-Bones GA 5
1.22 i
<tLD
. (pC1/g wet).
l G8 5
1.15 i1.75(3/5)
K-1d, Condenser Dis-1.75 (3/5)
None
.l 0
(1.41-1.94) charge. Onsite (1.41-1.94) i 1
5 0.10 mi E N
l None 0
e Sr-89 5l 0.44
<LLD 1
t i
Sr-90 5'
O.01 0.30 (5/5)
! K-Id. Condenser Dis ! 0.30 (5/5)
None 0
l
!(0.21-0.42)
, l charge, Onsite (0.21-0.42)
- 0.10 mi E j
l l
4! K-le, South Creek 1.6 (2/2) i 0.8 (2/2) 0 I
I Periphyton GA 12 0.2 0.7 (10/10)
(slime)
(0.3-1.8)
! Onsite, 0.12 mi S (1.3-1.8)
(0.4-1.2 )
i (pC1/g wet)
GB 12 0.50 I 2.4 (10/10)
K-9 Rostok Water 4.9 (2/2) 4.9 (2/2) 0 l
l (1.1-4.7) i Intake,11.5 mi NME (4.0-5.8)
(4.0-5.8) 12l
<LLD I
O i
Sr-89 0.11
<LLD i
Sr-90 12 '
O.010 0.046 (10/10)
K-le South Creek, 0.096 (2/2) 0.021 (2/2) 0 (0.066-0.125) l.
(0.019-0.023).
f (0.009-0.125)
Onsite, 0.12 mi S
- I l
GS 12 l
i Be-7
- 0. 92 1.20 (1/10)
K-le, South Creek, 1.20 (1/2)
<tLD 0
Onsite, 0.12 mi S K-40 0.50 2.44 (10/10)
K-9, Rostok Water 3.08 (2/2) 3.08 (2/21 0
(1.57-3.75)
Intake,11.5 mi NNE : (2.10-4.05)
(2.10-4.05) l
f5.
f'}I b_i7)
G Talile 4.5 (Continued)
Name of facility Kewaunee huelear Power Plant t
Indicator Location with Highest Controi
. Sample Type and Locationg Annual Mean Locations-I Numer of Type Number of Mean(F)
Mean(F )
Mean(F)
. Non-routine (Units)
Analysesa LLDb RangeC Locationd Range Range i
Results'
?
'Periphyton Mn-54
- 0.047 GLD
' <LLD 0
.1(511me) 1 (pC1/g wet)
Co-58 0.081 0.24(1/10)
K-Id, Condenser Dis-0.24 (1/2)
(LLD 0
(Cont'd) charge. Onsite l
0.10 mi E Co-60
, 0.047 0.17 (1/10)
K-Id,-Condenser Dis-0.17(1/2)
<tLD 0
l charge. Onsite O.10 mi E 9
i Nb-95 0.16
<LLD RLD 0
'Zr-95
! 0.15 i
' LLD g
j
<tLD O
I s.
Ru-103 0.15
<LLD
<LLD 0
l j
g l
{
Ru-106 0.44 GLD (LLD O
j I Cs-134 0.042 j
<LLD
<tLD O
Cs-137 0.048
<LLD~
j
<LLD 0
w o
I Ce-141 0.26
<LLD
<LLD O
f 6
i i
Ce-144 0.31
<LLD i
<tLD 0
a i
- K-1d, Condenser Dis-7.4 (1/4)
Bottom GA 20 4.2 6.2(2/16) 4
<tLD 0
Sediments (4.9-7.4) i charge. Onsite (pC1/g dry) 0.10 mi E i
I l
1 GB 20 1.4 6.5(16/16) 1 K-1c, Condenser Dis-6.8 (4/4)
? 6.1 (4/4) 0 i
- (3.7-10.2) i charge, Onsite (4.3-8.0)
!(3.5-7.9) 0.10 mi N t
l I
1i Sr-89 20 0.030 ;
<tLD
<LLD 0
l
<LLD 0
Sr-90 20 0.021
<LLD l
l 20 IK-1c,CondenserDisj Gs j
K-40 1.4 l5.9(16/16)
- 8.0 (4/4) 5.9 (4/4) 0
!(3.0-10.0) charge, Onsite j(5.7-10.0)
- (4.1-8.4) 0.10 mi N Co-58 0.04 0.18 (2/16)
K-1c, Condenser Dis-0.18 (2/4)
<LLD 0
(0.10-0.25) charge, Onsite (0.10-0.25) 1 t
0.10 mi N I
f
.(
)
I i
i l-G
- Q' m
-Table 4.5
-(continued)
Naune of facility Kewaunee Nuclear Power Plant Indicator Location with Highest Control Sample Type and Locationg Annual Mean Locations Number of i
Type Nunter of i
Mean(F) i Mean(F)
Mean(F)
Non-routine
-(Units)
Analysesa j
ttob RangeC Locationd i
Range Range Resultse l0.06 0.08'(7/16)
K-Id. Condenser Dis-0.08 (2/4)
<tLD 0
Bottom.
Co-60 Sediments (0.06-0.11) charge Onsite (0.06-0.11)
(pCi/g dry),
0.10 mi E -
(Con't)~
i.
Cs-134 0.05 0.11(1/4)
K-lj, Condenser Dis-
-0.11-(1/4)
(LLD 0
charge. Onsite 0.10 mi 5 Cs-137 0.04
'O.16 (12/16)
K-14. Two Creeks 0.27(3/4)
<LLD 0
(0.04-0.40)
Park, 2.5 mi S (0.04-0.40) b GA = gross alpha, G8 = gross beta, GS = gamma spectroscopy, SS = suspended solids DS = dissolved solids, TR = total residue.
LLD = nominal lower limit of detection based on 3 sigma counting error for background sample.
g Mean based upon detectable measurements only.. Fraction of detectable measurements at specified locations is indicated in i
parentheses (F).
d' Locations are specified by station code (Tabh 4.1), distance (miles) and direction relative to reactor site.
Nonroutine results are those which exceed te times the control station value. If no control station value is available.
the result is considered nonroutine if it exceeds ten times the pre-operational value for the location.
t i
k 4
I
o I
k.
/
5.0 REFERENCES
Arnold,.J. R. and H. A. Al-Salih.
1955.
Beryllium-7 produced by cosmic rays.
Science 121: 451-453.
Eisenbud, M.
1963.
Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275, and 276.
Gold, S., H. W. Barkhau, S. Shlein, and B. Kahn, 1964. Mnsurement of Naturally Occurring Radionuclides in Air, in the Natural kadiation Environment, University of Chicago Press, Chicago, Illinois, 369-382.
Hazleton Environmental Sciences,19/9.
Annual Report.
Radiological Monitoring Program for the-Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, Final Report - Part II, Data Tabulations and Analysis, January - December 1978.
V 1980.
Annual Report.
Radiological Monitoring Program for the Kewaunee Nuclear Power Plant, KE.Jnee, Wisconsin, Final Report Part II, Data Tabulations and Analysis, January - December 1979.
1981.
Annual Report.
Radiological Monitoring Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, Final Report Part II, Data Tabulations and Analysis, January - December 1980.
1982.
Annual Report.
Radiological Monitoring Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, Final Report Part II, Data Tabulations and Analysis, January - December 1981.
1983.
Annual Report.
Radiological Monitoring Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, Final Report Part II, Data Tabulations and Analysis, January - December 1982.
Industrial BIO-TEST Laboratories, Inc. 1974.
Annual Report. Pre-operational Radiological Monitoring Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin. January - Decer her 1973.
1975.
Semi-annual Report.
Radiological Monitoring Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin.
January -
June 1975.
es NALC0 Environmental Sciences.
1977.
Annual Report.
Radiological Monitoring
(~j Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, January - December 1976.
32
.A4 1978.
Annual' Report.
Radiological Monitoring Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, Final Report - Part II, Data Tabulations and Analysis, January - December 1977.
National Center for Radiological Health.
1968.
Section 1.
Milk surveillance.
Radiological Health Data Rep., December 9:730-746.
National Council on Radiation Protection and Measurements.
1975. Natural Radiation Background in the United States. NCRP Report No. 45.
Solon, L. R., W. M. Lowder, A. Shambron, and H. Blatz.
1960.
Investigations of Natural Environmental Radiation. Science. 131: 903-906.
Teledyne Isotopes Midwest Laboratory.
1984.
Annual Report.
Radiological Monitoring Prcgram for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, Final Report, Part II, Data Tabulations and Analysis, January - December 1983.
Wilson, D. W., G. M. Ward, and J. E. Johnson, 1969.
In Environmental Contamina-tion by Cadioactive Materials, International Atomic Energy Agency, p.
125.
rs r
U 33
4 i
I l
l i
i 5
i, Appendix A Crosscheck Program Results J
<0 I
I l
9 A-1
b,a Apoendix A Crosscheck Program Results Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of its quality control program in December 1971.
These programs are operated by agencies which supply environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories.
The purpose of such a program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems.
Participant laboratories measure the concentrations of specified radionuclides
- and report them to the issuing agency.
Several months later, the agency reports the known values to the participant laboratories and specifies control limits.
Results consistently higher or lower than the known values or outside the control-limits indicate a need to check the instruments or procedures used.
o The results in Table A-1 were obtained through participation in the environ-(j -
mental sample crosscheck program for milk and water samples during the period 1980 through 1983.
This program has been conducted by the U. S. Environmental Protection Agency Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, - Las Vegas, Nevada.
The results in Table A-2 were obtainad for thermoluminescent dosimeters (TLD's) during the period 1976, 1977, 1979, 1980, and 1981 through parti-cipation in the Second, Third, Fourth, and Fifth International Intercomparison of Environmental Dosimeters under the sponsorships listed in Table A-2.
V A-2
,o Appendix A Crosscheck Program Results Teledyne Isotopes Midwest Laboratory (formerly Hszleton Environmental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of its quality control program in December 1971.
These programs are operated by agencies which supply environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories.
The purpose of such a program is to provide an independent check on the laboratory'.s analyt.ical pro.cedures and to alert it to any possible problems.
Participant laboratories measure the concentrations of specified radionuclides and report them to the issuing agency.
Several months later, the agency
- reports the known values to the participant laboratories and specifies control limits.
Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.
The results in Table A-1 were obtained through participation in the environ-fmQ mental sample crosscheck program for milk and water samples during the period 1980 through.1983.
This program has been conducted by the U. S. Environmental Protection Agency Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, Las Vegas, Nevada.
The results in Table A-2 were obtained for thermoluminescent dosimeters (TLD's) during the period 1976, 1977, 1979, 1980, and 1981 through parti-cipation in the Second, Third, Fourth, and Fifth International Intercomparison of Environmental Dosimeters under the sponsorships listed in Table A-2.
- g v
A-2
f L)
Table A-1.
U.S. Environmental Protection Agency's crosscheck program, com-parison of EPA and Teledyne Isotopes Midwest Laboratory results for milk and water samples,1980 through 1983a, Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis igac i 30, n=1d STW-206 Water Jan. 1980 Gross Alpha 19.0i2.0 30.0i8.0 Gross Beta 48.012.0 45.0i5.0 STW.208 Water Jan. 1980 Sr-89 6.111.2 10.0i0.5 Sr-90 23.9 1.1 25.5tl.5 STW-209 Water Feb. 1980 Cr-51 112 14 101i5.0 Co-60 12.7 2.3 11i5.0 Zn-65 29.7 2.3 2515.0 Ru-106 71.7 1.5 5115 Cs-134 12.012.0 10i5.0 Cs-137 30.0 2.7 30 5.0 STW-210 Water Feb.-1980 H-3 1800il20 1750i340
,.s N -)
(
STW-211 Water March 1980 Ra-226 15.7 0.2 16.012.4 Ra-228 3.510.3 2.6 0.4 STM-217 Milk May 1980 Sr-89 4.4 2.69 Si5 Sr-90 10.0il.0 12 1.5
'. STW-221 Water June 1980 Ra-226 2.0 0.0 1.710.8 Ra-228 1.610.1 1.710.8 STW-223 Water
^ July 1980 Gross Alpha 31 3.0 38i5.0 Gross Beta 44i4 3515.0 STW-224 Water July 1980
.Cs-137 33.9i0.4 35 5.0 8a-140
<12 0
K 1350 60 1550178 I-131
<5.0 0
-STW-225
-Water Aug. 1980 H-3 1280 50 1210t329 STW-226-Water Sept. 1980 Sr-89 22 1.2 24 8.6 Sr-90 12 0.6 1512.6 STW-228 Water Sept. 1980 Gross Alpha
. nae 32.0 8.0 Gross Beta 22.5 0.0 21.0i5.0
/~'T-
'STW-235 Water Dec. 1980 H-3 2420 30 22401604
\\_)
A-3
L g
Table A-l'.
'(continued)
...n Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code-Type Collected Analysis ikc i30, n=1d STW-237 Water
'Jan. 1981 Sr-89 13.0il.0 16i8.7 Sr-90 24.010.6 34t2.9 STM-239
- Milk Jan. 1981 Sr-89
<210 0
Sr-90 15.7 2.6 20i3.0 I-131 30.9i4.8 26110.0 Cs-137 46.9i2.9 43t9.0 Ba-140
<21 0
~
K-40 1330153 1550 134
- STW-240 Water Jan. 1981 Gross alpha 7.3i2.0 9i5.0 Gross beta 41.0i3.1 44i5.0
^
' STW-243 Water Mar. 1981 Ra-226 3.Si0.06
?.ai0.5 Ra-228 6.5i2.3
' 311.1 STW-245 Water Apr._1981 H-3 3210i115 2710t355 V
STW-249
- Water
. Mr_y 1981 Sr-89 51 3.6 3618.7 Sr-90 22.7i0.6 22i2.6
- STW-251 Water.
May 1981 Gross alpha 24.0i5.3 21t5.2 Gross beta 16.lil.9 14t5.0 STW-252 Water Jun. 1981-H-3 2140195 19501596 STW-255 Water Jul. 1981 Gross alpha 20 1.5 22i9.5 Gross beta 13.0t2.0 15i8.7 STW 59 Water Sep.~1981 Sr-89 16.1 1.0 2$15 Sr-90 10.3i0.9 11tl.5 STW-265 Water Oct. 1981 Gross alpha 71.2 19.1 80i20 Gross beta 123.3116.6 11115.6 Sr-89 14.9i2.0 2115 Sr-90 13.lil.7 14.4tl.5 Ra-226 13.0i2.0 12.711.9 STW-269 ~
Water-Dec. 1981 H-3 2516 181 27001355 w
{t A-4 y
4 1
-v-c, y
-,,,--,,-,,,----,,.-.-.e1..--.y, v.-
.w,
,- - -. - - - -, ~.
-o.-
,yr-,,,-
--,,--y,,%_,,=~3~,c.-
V Table A-1.
(continued)
Concentration in DCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis 18ac 30, n=1d STW-270 Water Jan. 1982 Sr-89 24.3 2.0 21.0i5.0 Sr-90 9.4i0.5 12.Dil.5 STW-27,3 Water Jan. 1982 I-131 8.610.6 8.4tl.5 STW-275 Water Feb. 1982
'H-3 1580 147 1820i342 i
STW-276 Water Feb. 1982 Cr-51
<61 0
Co-60 26.013.7 20i5 Zn-55
<13 15 5 Ru-106
<46 20 5 Cs-134 26.8 0.7 22 5 Cs-137 29.7 1.4 2315 STW-277 Water Mar. 1982 Ra-226 11.9 1.9 11.611.7
\\_)
STW-278 Water Mar. 1982 Gross alpha 15.6 1.9 19 5 Gross beta 19.2 0.4 19 5 STW-280 Water Apr. 1982 h-3 2690 80 2860 360 STW-281 Water Apr. 1982-Gross alpha 75 7.9 85 21 Gross beta 114.1 5.9 10615.3
~
Sr-89 17.4 1.8 24 5 Sr-90 10.510.6 12 1.5 Ra-226 11.412.0 10.9 1.5 Co-60
<4.6 0
STW-284 Water May 1982
~ Gross alpha
'31.516.5 27.5t7 Gross beta 25.9i3.4 29i5 STW-285 Water June 1982 H-3 197011408 18301340 STW-286 Water June 1982 Ra-226 12.611.5 13.4 3.5 Ra-228 11.1 2.5 8.712.3 STW-287 Water June 1982 1-131 6.510.3 4.410.7 STW-290 Water Aug. 1982 H-3 3210i140 28901619 STW-291 Water Aug. 1982 1-131 94.6 2.5 87t15 (v}.
A-5
- (~3 V
' Table A-1.
(continued)
Concentration in aC1/lb Lab Sample Date TIML Result EPA lesult Code Type Collected Analysis 20c 30, n=1d STW-292 Water Sept 1982 Sr-89 22.713.8 24.5 8.7 Sr-90 10.9 0.3 14.512.6
-STW-296
. Water Oct. 1982 Co-60 20.0 1.0 2018.7 Zn-65 32.315.1 2418.7 Cs-134 15.3 1.5 19.~018.7 Cs-137 21.0 1.7 20.0 8.7 STW-297 Water Oct. 1982 H-3 2470 20 25601612 STW-298 Water Oct.1982 Gross alpha 32 30 55 24 Gross beta 81.7 6.1 81 8.7 Sr-89
<2 0
Sr-90 14.1 0.9 17.2 2.6 Cs-134
<2 1.8 8.7 Cs-137 22.7 0.6 20 8.7
/~')
Ra-226 13.6 0.3 12.5 3.2
(_ /
Ra-228 3.9 1.0 3.6 0.9 STW-301 Water Nov. 1982 Gross alpha 12.0 1.0 19.018.7 Gross beta 34.0 2.7 24.0 8.7 STW-302 Water Dec. 1982 I-131 40.0 0.0 37.0110 STW-303 Water Dec. 1982 H-3 1940120 19901345 STW-304 Water Dec. 1982 Ra-226 11.7 0.6 11.0 1.7 Ra-228
<3 0
STW-306 Water Jan. 1983 Sr-89 20.0 8.7 29.2 5 Sr-90 21.7 8.4 17.211.5 STW-307 Water Jan. 1983 Gross alpha 29.0 4.09 29.0 13 Gross beta 29.3 0.6 31.0 8.7 STM-309-Milk Feb. 1983 Sr-89 3512.0 37 8.7 Sr-90 13.7 0.6 18 2.6 I-131 55.7 3.2 55 10.4 Cs-137 29 1.0 2618.7 Ba-140
<27 0
d,n,
~
(continued)
Table A-1.
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis i20c i3o, n=1d STW-310 Water Feb. 1983 H-3 2470i80 2560i612 STW-311 Water March 1983 Ra-225 11.911.3 12.7i3.3 Ra-228
<2.7 0
STW-312 Water March 1983 Gross alpha 31.614.59 31t13.4 Gross beta 27.0i2.0 2818.7 STW-313 Water April 1983 H-3 3240i80 3330i627
-STW-316 Water May 1983 Gross alpha 94t7 64i19.9 Gross beta 13315 149i12.4 Sr-89 1911 2418.7 Sr-90 1211 1312.6 Ra-226 7.9i0.4 8.512.25 Co-60 30i2 30i8.7 Cs-134 27i2 33i8.7 g3q )
Cs-137 29t1 27 8.7 STW-317 Water May 1983 Sr-89 59.712.1 57i8.7 Sr-90 33.711.5 38i3.3 STW-318f Water May 1983 Gross alpha 12.8tl.5 11i8.7 Gross beta 49.4i3.9 57f8.7 STM-320 Milk June 1983 Sr-89 2010 25i8.7 Sr-90 10i1 1612.6 I-131 3011 30110.4 Cs-137 52 2 47 8.7 K
1553i57 14861129 STW-321 Water June 1983 H-3 1470189 15291583 STW-322 Water June 1983 Ra-226 4.3i0.2 4.811.24 Ra-228
<2.5 0
STW-323 Water July 1983 Gross alpha 3f1 7i8.7 Gross beta 2110 22i8.7 STW-324
. Water August 1983 I-131 13.310.6 14110.4
- (~~\\
%,Y A-7
(
Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis i33 c 13o, n=1d STAF-326 Air August 1983 Gross beta 42i2 3618.7 filter Sr-90 14t2 1012.6 Cs-137 19t1 1518.7 STW-328 Water Sept. 1983 Gross alpha 2.310.6 518.7 Gross beta 10.7tl.2 918.7 STW-329 Water Sept. 1983 Ra-226 3.010.2 3.110.81 Ra-228 3.210.7 2.010.52 STW-331 Water Oct. 1983 H-3 1303132 12101570 a Results obtained by Teledyne Isotopes Midwest Laboratory as a participant in the environmental sample crosscheck program operated by the Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring
~')
'(d and Support Laboratory, U.S. Environmental Protection Agency, (EPA), Las Vegas, Nevada, b All results are in pCi/1, except for elemental potassium (K) data which are in mg/1.
c Unless otherwise indicated..the TIML results given as the mean 12a standard deviations for three determinations.
- d USEPA results are presented as the known values i control limits of 3a for n=1.
e NA = Not analyzed.
f Analyzed but not reported to the EPA.
9 Results after calculations corrected (error in calculations when reported to EPA).
/ %.
s.,,
A-8 w
,e--
,----r--y.-
-y.
7--
>----,-t
~
~
g o
O i
F Table A-2.. Crosscheck program r'esults, thermoluminescent dosimeters (TLDs).
L Teledyne Average 12 d Lab' TLD 12 a Value.
participants)
Result Known (all Code Type
-Measurement l
l-
>2nd International Intercomparisonb
.115-2b CaF2:Mn Gamma-Field' 17.011.9 17.lc-16.417.7 Bulb Gamma-i.ab 20.814.1 21.3c 18.817.6 3rd International Intercomparisone 115-38 CaF :Mn Gamma-Field 30.713.2 34.9i4.8f 31.513.0 2
Bulb f
}
Gamma-Cab 89.616.4 91.7tl4.6 -
86.2124.0 4th International Intercomparison9
}
CaF :Mn Gama-Field 14.111.1 14.lil.4f 16.09.0 115-49 2
Bulb l
Gamma-Lab (Low) 9.3rl.3 12.212.4f 12.017.6 l
Gamma-Lab (High) 40.411.4 45.819.2f 43.9113.2 i
Sth International Intercomparisonh 115-5Ah CaF :Mn Gamma-Field 31.411.8 30.016.01 30.2il4.6 Cufb Gamma-Lab' 77.415.8 75.?i7.6i 75.8t,40.4 at beginning Gama-Lab 96.615.8 88.418.81 90.7131.2 l
at the end i
i l
Table A-2.
(Cont'inued) mR d
Teledyne Average i 20 Lab TLD Result Known (all Code Type Measurement 12aa Value participants) 115-5Bh LiF-100 Gama-Field 30.314.8-30.016i 30.2114.6 Chips Gamma-Lab 81.117.4 75.217.61 75.8140.4 at beginning Gamma-Lab 85.4111.7 88.418.8i 90.7i131.2 at the end alab result given is the mean 12o standard deviations of three determinations.
bSecond International Intercomparison of Environmental Dosimeters conducted in April of 1976 by the Health 4
and Safety Laboratory (GASL), New York, New York, and the School of Public Health of the University of Texas, Houston, Texas.
o cValue determined by sponsor of the intercomparison using continuously operated pressurized ion chamber.
dMean ik standard deviations of results obtained by all laboratories participating in the program.
eThird International Intercomparison of Environmental Dosimeters conducted in summer of 1977 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas, Houston, Texas.
f Value ik standard deviations as determined by sponsor of the intercomparison using continuously operated pressurized ion chamber.
9 Fourth International Intercomparison of Environmental Dosimeters conducted in summer of 1979 by the School of Public Health of the University of Texas, Houston, Texas.
hFifth International Intercomparison of Environmental Dosimeter conducted in fall of 1980 at Idaho Falls, Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas and Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy.
4 I
Value determined by sponsor of the intercomparison using continuously operated pressurized ion chamber.
9
~.
-.. _. _.. - - -.=
I t
O t
i i
[
l Appendix 8 Data Reporting Conventions t
il l
(
l B-1 l
l r
7 eaf-e-.gw py--,7->g,ww+gg-y-ep.e---,e---,
3 p-3iv p
_my--,y----pr+.myw%-um-m e w ww vew w w egen-wwe_
1 (n
-(
-Data Reporting Conventions
- 1. 0'.
All activities are decay corrected to collection time.
~2.0.
Single Measurements
.Each single measurement is reported as follows:
xis where x = value of the measurement; s = 20 counting uncertainty (corresponding to the 95% confidence level).
In cases where the activity is found to be below the lower limit of detection L it is reported as
<L where L = is the lower limit of detection based on 3a uncertainty for a background sample.
3.0.
Duplicate Analyses
')
3.1.
Individual results: x1 i s1 x2 i s2 Reported result:
xis where x = -(1/2) (x1 + x2) s=(1/2){fs2+s2 3.2.
Individual results:
<L1
<L2 Reported result:
<L where L = lower of L1 and L2 3.3.
Individual results:
xis
<L Reported result:
x i s if x < L;
<L otherwise
.(~)
\\._,/ -
B-2
-mp-m
- - - - g
,e g
er re-
-67 g
g g
--we er =-
--m---
,%gyw g -
gy-'y
,,e--,-s
%wmwm-g eieer-a---
4 w
-m
<3
,V 4.0.
Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviations of a set of n numbers x1, x2, Xn are defined as follows:
x = hI x
E (x-x )2 3,
n-1 4.2 Values below the' highest lower limit of detection are not included in the average.
4.3 If all of the-values in the averaging group are less than the highest LLC, the highest LLD is reported.
TN 4.4 If all but one_of the values are less than the highest LLD, the b
single value x and associated two sigma error is reported.
4.5. In rounding off, the following rules are followed:
4.5.1. If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged.
As an example,11.443 is rounded off to 11.44.
4.5.2 If the figure following those to be retained is g: eater than 5, the figure is dropped, and the last retained figure is raised by 1.
As an example,11.446 is rounded off to 11.45.
4.5.3. If the figure following those to be retained is 5, and_if there are no figures other than zeros beyond the five, the figure 5 is dropped, and the last-place figure retained is increased by one if it is an odd number or it is kept unchanged if an even number.
As an example, 11.435 is rounded off to 11.44, while 11.425 is rounded off to 11.42.
m
'\\
B-3 1
O l
TL,h Appendix C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas P
4 O
C-1
)
>AS C. W. Giesler Vice President - Nuclear Power js Enc.
cc - Mr. Robert Ncison, US NRC Mr. S. A. Varga, US NRC Mr. J. G. Keppler, US NRC Region III (2)
.s/M
'#