ML20012C082
| ML20012C082 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 02/13/1990 |
| From: | Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| Shared Package | |
| ML20012C080 | List: |
| References | |
| NUDOCS 9003200051 | |
| Download: ML20012C082 (57) | |
Text
q 3..
r, s
- '1 MEETING
SUMMARY
-Licensee:
Gulf States Utilities i
Facility:
River Bend Station.
License No.:
NPF-47 Docket No.:
50-458 i
Subject:
=
RADIATION SOURCE TERM PRESENTATION On January 26,-1990, representatives of Gulf States Utilities met with Region IV personnel in Arlington, Texas, to discuss the radiation levels that exist at the River Bend facility and the source term associated with these
' radiation levels; The' attendance list.is attached to this Summary.
The
. meeting was held at the request of Gulf States Utilities.
D i
The-licensee outlined the history of -the Radiation Source Term Task Force -
activities along with. planned work for 1990. The licensee's presentation also included a discussion of-radiation levels that exist at various locations within-the plant, identification of the radionuclides involved, and-the origin of the radioactive materials.
TheTaskForce51anstoissueareportbylate
- February 1990 which will contain recommendations concerning actions to prevent any: additional buildup of radiation levels and to reduce those levels that presently exist.
W
))b'W)l<
l Blaine Murra9 Dhte '
i Attachment
. Attendance List j
L
-P
{
+
-ATTENDANCE LIST Attendance at the Gulf States Utilities - NRC Meeting on January 26, 1990, at the NRC Region'IV office, j
Gulf States Utilities
'l J. C. Deddens,' Senior'Vice President River Bend Nuclear J, E. Booker, Manager, River Bend Oversight L. A. England,. Director, Nuclear Licensing T. F. Plunkett, Plant Manager P. 0.- Graham, Executive Assistant E., ML Cargill, Director, Radio 1_ogical Programs C. U Fantacci,: Radiological Engineer Supervisor NRC' L: A. Yandell, Deputy Director, Division of Radiation Safety and Safeguards (DRSS)
S. A Collins, Director, Division of Reactor Projects (DRP)
J. P. Jaudon, Deputy Director, Division of. Reactor Safety (DRS) l B..Murray, Chief, Facilities Radiological Protection Section, DRSS
~G. L. -Constable, Chief, Project Section C, DRP I. Barnes, Chief, Materials and Quality Programs.Section,.DRS R. E.-Baer, Radiation' Specialist, DRSS
% B. Jones, Resident Inspector, River Bend Station
. R.-V. Azua, Project Engineer,-DRP' 1'
t l
I l
1 e
a
r L
t RIVER BBND STATION
?
'h i
'i l-
' RADIATION SOURCE TERM PRESENTATION L.
L JANUARY 26,-1990.
1 l '
f f
l rh.
i NRC CONCERNS WE INTEND TO ADDRESS i
RIVER BEND SOURCE TERM IS VERY HIGH COMPARED TO OTHER PLANTS.
l '
THE SOURCE TERM IS A MANAGEMENT ISSUE AND RADIATION PROTECTION 1:
DOES NOT APPEAR TO BE PUSHING A RESOLUTION.
l-1 1.
- . DEVELOPING A PLAN OF ACTION APPEARS TO BE MOVING SLOWLY.
THE RADIATION SOURCE TERM TASK FORCE APPEARS TO HAVE BEEN PLACED ON THE "BACK BURNER."
1
F'
\\
i
]
. I 1-t I
AGENDA I. HISTORY II. RADIATION SOURCE TERM TASK FORCE A. Management Direction B.
Participants C. Objectives D. Tasks E. Task Force Findings III. TA8K FORCE CONCLUSIONS l-1:
IV. TASK FORCE RECOMMENDATIONS V. WRAP-UP i.
I-I:
l.
e 2
v
CHRONOLOGICAL LIST March 1989
- RF-2 start - higher dose rates encountered.
April 1989
- Director-Radiological Programs informs Plant j
Manager of higher dose rates.
Senior management notified, other plants called-for l
comparisons.
June 1989
- RF-2 complete.
June.14, 1989
- Radiological programs completes cost benefit for zinc injection.
June 26, 1989
- Radiological Programs initiated MR for consideration by Work Scop _e for sinc injection.
L July 5, _1989
- Radiological Programs cost benefit analysis for control rod pin / roller replacement.
L
-July 18, 1989
- Work Scope review MR for sinc injection.
f July 24, 1989
- Plant Manager asks INPO - for evaluation and advice on source term.
August 1, 1989
- Senior Vice President's Performance Monitoring Quarterly Review Meeting.
Discussed' dose, i
curves, source term, chemical cleaning, sinc l
injection, shielding and training.
August l',
1989
- Assignment of employees to source term task force.
August 30, 1989
- Source Term Task Force Meeting.
Sept. 14, 1989
- Source term concern presented to Nuclear Safety Advisory Committee.
l ~
Sept. 25, 1989
- Task force concludes Co-60 responsible for dose
(
1.
rates.
Sept. 25, 1989
- ALARA Committee updated on task force activities.
sept. 27, 1989
- Task force updates senior management personnel.
Sept. 29, 1989
- Comprehensive telephone survey. of BWR dose rates.
I' Oct. 15, 1989
- Chairmanship of task force changed.
3
s CHRONOLOGICAL LIST (continued)
Oct. 19, 1989
- Maintenance reviewed valve cleanliness and concluded that procedures should be modified.
Oct. 23, 1989
- Source Term Task Force Meeting.
Nov. 7, 1989
- Source Term Task Force Meeting.
Nov.
8, 1989
- Task force updates senior managssent personnel.
Nov. 10, 1989
- Engineering study on system materials and quantitative data for radwaste radionuclides.
Nov. 13, 1989
- Radiological Programs Report - Stellite Vilve Summary'.
Dec.
4,
- 1989,
- Radiological Programs Repor;t - River Bend Dose Rates Versus 6 Other BWRs.
Dec.
5, 1989
- Task force updates senior management personnel.
Dec. 12, 1989
- ALARA Committee updated on task force activities.
Jan.
4, 1990
- Source Term Task Force Meeting.
Jan.
5, 1990
- Chemistry report on elemental and radionuclide concentration in feedwater, condensate and reactor coolant system.
Jan. 26, 1990
- Source Term presentation to the NRC.
l l.
Mid-Feb. 1990
- Issue Radiation Source Term Task Force Report.
Mid-Cycle Outage
- Obtain survey data to track source term.
May 15, 1990
- Develop actiorr plan to address task force recommendations.
-By RF-3
- Implement action plan to the level it can be implemented.
l i
1 4
4 INPO COMMENTS
[
Recommendation Take actions to identify the sources of increased radiation-levels in the drywell, reactor
- building, and auxiliary building.
Develop plans to reduce the effects of these sources on plant radiation. levels.
Response
A task force has been established to-investigate the.
radiation source
-term
. associated with man-rem expenditure at the plant.
Task force recommendations will be presented to management two months after the completion of the mid-cycle outage in 1990.
- However, any interim measures or recommendations identified by-the task force will be implementedz prior to.the mid-cycle outage, if feasible.. Implementation of the recommendations will be.prioritized~
and scheduled by the Work Scope Committee.-
.I I'
5
-6.-
E
' i :..
s SENIOR VICE PRESIDENT DIRECTION TO THE TASK FORCE s
i l
WEY Is RIVER BEND DIFFERENT7
't WHAT ARE WE DOING THAT WE CAN DO BETTER?
s
/
h l
l I
6
. - - ~.
ee i
3-RADIATION SOURCE TERM TASK FORCE Task Force Composition Chemistry Radiation Safety Engineering Maintenance Operations Cost Systems Projects Oversight-l' L
l l
m
..a 1
1 i
TASK FORCE OBJECTIVES b
1)
Verify the identity and approximate contribution of radionuclides hat account for the majority of personnel radiation dose.
2)
Report current radiation field levels, present comparisons to other plants and provide projections of future radiation field levels.
1 3)
Use plant construction, operation and maintenance records to provide'a best estimate of the equipment, materials, operating actions and maintenance activities contributing to the formation of the radiation fields that result in absorbed dose to personnel.
4)
Make full use of industry experience data available from INPO,
- EPRI, General Electric, other plants and other industry information sources to evaluate River Bend's current and projected radiation exposures in relation to industry standards.
5)
Provide several radiation dose control
- options, with l-recommendations and evaluations, to management.
l l
l l-8 l e
e-
.4-1 TA8K FORCE ACTIVITIES r
1)' Determine actual dose rates and radionuclides at selected plant equipment locations.
2)
Provide. quantitative data for radwaste radionuclides, particularly Reactor Water Clean Up and Condensate demineralizer resins.
3)
Provide quantitative data on metals present in reactor water.
In particular, data on iron, nickel, sinc, chromium and cobalt is needed.
Reactor startup and power operation data will be provided to the extent available.
4)
Assemble materials data on reactor recirculation, Reactor Water Clean Up, feedwater, condensate, main steam and heater drain systems.
5)
Provide current plant dose rates, dose rate trends and comparisons to other plants.
Why are we different?
6)
Contact EPRI and INPO for current information on dose rates, radionuclides causing the dose rates and zinc treatment information.
7)
Obtain data on zinc levels present in other plants.
8)
Complete listing of locations and tasks producing exposures at River Bend.
9)
Review EPRI document, " Cobalt Contamination Resulting From s
Valve Maintenance," evaluate against our procedures, and l
recommend improvements.
l~
9
?.
k:
-t.
'_ s '.
.e a
i 4
I 1)
DETERMINE ACTUAL DOSE RATES AMD RADIONUCLIDES AT SELECTED PLANT EQUIPMENT LOCATION 8 l
10
FIXED & LOOSE DEPOSITS WCS SAMPLE FW SPARGER SIEAR 1 Activity 5 Activity 5 Activity 5 Activity Radiolsotope 9 Rx $hutdown When Sampled 9 Rx Shutdown When Sampled Cr-51 43.7 12.8 34.2 8.6 Mn-54 7.7 12.9 12.5 17.9 Co 58 12.4 11.8 7.3 5.9 Fe-59 4.3 2.7 4.6 2.5 Co-60 26.2 50.8 36.1 60 1 Zn-65 4.8 7.6 1.9 2.5 Nb-95 0.4 0.4 0.4 0.3 Sn-113 0.6 0.6 l
Sb-124 0.5 0.4 2.6 1.8 RELATIVE 00$ERATES 9
9 Radioisotope Rx Shutdown Sampling Cr-51 1
0.025 Mn-54 5.1 4.3 Co-58 9.7 4.6 Fe-59 4.1 1.3 Co-60 52.1 50.7 n
In-65 2.1
1.7 Motes
- 1) Point source configuration used for comparison 2)
Figures are relative to Cr-51 9 Rx shutdown in WCS sample 11
t-i
=
i LOCATION SYSTEM RF-1*
RF-2*
Drywell Reactor Recire Risers 80 300 Drywell Reactor Recirc Pump Suction 200 500 Drywell Reactor Recirc Pump Disch 110 225 Drywell RWCU Ring Header 110 850 Aux Bldg RWCU Pump 250 400 Aux Bldg RHR Heat Exchanger 70 110
- mrem /hr general area 18" readings I
i 12
l
~h I
N
?gsq; u
x\\@
s
^
^4
.,n u "' g j
p>,\\!
s i
a i
s/
8 9@
x q
9 e
li t
~,.
=
. tv v,,ip;..
';# s.i 1
i d
in O t
i-
^
///
0 0 3 @
\\\\ @A G
A A
f le, l'
m-I
/
II
-. Mk m
- 19-I
{';
q n
s',A s
- 2 o0 00 N
'O D@
V e
i
---,,n...,,
,,..w-_,.,,,-,,---r-,,-,--gner v
,e--
v
- - -g
l RHCU RING HEADER.
\\
AND
)
VA LVES 1
1986 1987 min 1989 CONTACTDOSERATES F
5i zws (000 4m >
t
\\gda/
,co 8ee toe <:
?l Q i
=
t 00 l
=
~
na e
. <a
!*jlc,
)
. iue uoo ft 1991 ig' JA
(/9 9 m ]
70' DRYWELL 14
R WCU RING HEADER no VA LVES 99 c
18'DOSERA TES
...p..
t
%)I h
'd) s.-
L 8
a 50) b T
IU *
/
A g<sq A.
(,9...)
70' DRYWELL 5
o L
,a ma""*
,,,,. - * " * ' " ~ ' '
.s**
AUXILIARY BUILDING L
R86 RhR PVMP ROOMS A,B,C 1967 sw
/969 COVTACTDOSEAATf3
~
5
\\
gs yLee!
\\
m ln,e. g(
5>/E 7Y A
i
\\ /co Q". s to j\\yh) i i
8" 1
s I
z n e a
+
/
M
,~.
/L
)
t A-
{
vr i
~-
w J
a_
Mp,
%_G t
W-
-s M
.g,
- -q
'""T y E/
c
[
j!.T,
[,
'T' x_
=
m s
A 7
oI t
i 3
l g
(
'M L l
~
p m 3
1 g
4 C ?"*
~
~I
- 1.
1
)y 1
aE %, s a>
.x q
-r rp j
%h
'O
,y x
\\jl O f W
-')t
,a Q
~
\\
t G
..v i
,...A i ',. '- \\
a-e-
w te.-w%we-'e--w
- - ~ ~
,a+
~
- ' ' - ~
AUXILIARY BUILDING i
??oG RhR PVMP ROOMS AAC
\\
/9 8 7,u m 1969 i
i 18 "ldSEA.4 TES
)
r f
'4 t?o
=(,a.1.([
f y y(p~,
(4) i rag
=m ~ 4
~
A ti.
gQ
~~'W M
'Y 3,f '
-v a i
4 br or A)
/80
< go, h
(M
- go+%
4, J.
.r e
.w.
l.;.,..
"-i C.
l g &:-
g sj
.rg@, NM (1,)
m,
}-
E-r i
,Q ir x
'^
q de V. [ p 1
/2 i
i L
i i
-q
> 'A j
E 3-
.3 m
c l
ONGOING ALARA ACTIVITIES TO ADDRESS DOSE RATE 1
i Hydrolazina, Reactor Vessel Nozzles /,gg-lji, Dose Rate Reduction i
/
400-700 mR/hr - 200-500 mR/hr Reactor Sparger Repair /_50% Reduction
/ 1.7 R/hr- ~8 F mR/hr l
Flushina System Pinina RHR/LPCS Flush - Factor of 8 Reductions Snubber Reduction RF-1 50 Man-Rem Saving 6,000 Man-Rem Over 'c:'fe of the Plant J
Live Load Packina 126 Valves Converted Since RF-1 RWCU Pumo Seal Modifications Development of a More Reliable Seal 18 t
Ys.
i l
4 t
i 2)
PROVIDE QUANTITATIVE DATA FOR RADWASTE RADIONUCLIDES, PARTICULARLY REACTOR WATER CLEAN UP AND CONDENSATE DENINERALIBER RESINS t
19
l j
?
SPENT RESIN WASTE PERCENT OF ACTIVITY Significant 1st Malf ist Ralf Radioisotopes 1988 1989 Co-60 44.1 30.3 w
Mn-54 25.5 18.9 i
Cr-51 3.6 13.8 Co-58 4.5 5.5 Zn-65 4.4 2.5 Fe-59 0.6 0.3 Ni-63 1.0 0.8
'Fe-55 10.7 27.0 CONFIRMS COBALT-60 IS OUR PRIMARY SOURCE l
20 m
1 l
5 3)
PROVIDE QUANTITATIVE DATA ON METALS PRESENT IN REACTOR WATER.
IN PARTICULAR, DATA ON IRON, NICREL, EINC, CHROMIUM, AND COBALT IE NEEDED.
l REACTOR STARTUP AND POWER OPERATION DATA WILL BE PROVIDED TO TEE EETENT AVAILABLE.
l 21 IG
1 l
Reactor Coolant System Metals Concentrations Reactor Coolant Systen metals concentrations are meas made using a grab sample collected over a several hour period. The metals which are routinely measured are Nickel, Iron, Chromium, Zinc, Copper, and i
Aluminua. The resul'ta of these samples are summarized below.
1988 Average value, in micrograms / liter, for Month Al Co Cu Cr Fe Ni 2n Juns 1.28 NM 4.01 0.63 4.17 0.85 2.86 July 0.94 NM 3.80 0.50 5.03 1.65 1.98 Aug.
1.29 NM 6.06 3.94 50.5 1.77 3.62 3ep.
1.12 NM 3.65 3.89 27.2 0.99 2.71 Oct.
0.58 NM 5.43 1.19 28.8 1.23 2.31 Nov.
0.45 NM 1.43 0.27 1.27 0.68 1.89 Dec.
1,81 NM 2.44 2.15 3.96 2.08 2.81 1388 Ave.
1.07 NM 3.83 1.80 17.3 1.32 2.60 1
1989 Average value, in micrograms / liter, for H: nth Al Co Cu Cr Fe Ni Zn Jan.
1.55 NM 1.90 1.49 6.41 1.87 1.69 Fob.
1.67 NM 3.64 0.98 19.4 1.14 7.96 Har.
0.68 NM 2.09 0.58 1.41 1.60 2.09 Apr.
NOT SAMPLED THIS MON'IN DUE TO REFUELING OUTAGE (RF-2)
May NOT SAMPLED THIS MONTH DUE TO REFUELING OUTAGE (RF-2)
June 740 NM B.54 3.27 431 3.65 20.8 July 4.85 NM 4.70 4.96 227 3.25 4.22 Aug.
3.05 NM 3.39 2.83 5.02 0.68 2.71 le ~jt Sap.
3.12 1.06 2.65 8.97 87.2 2.22 4.99 i
Oct.
2.62 0.90 3.03 1.96 5.30 1.99 2.40 1389 Ave.
2.51 0.98 3.74 3.13 97.8 2.05 5.86 (3.05)
(50.2)
(1.82)
(3.73)
NOTES: 1)
NM - Not Measured 2)
Values obtained immediately after RF-2 significantly affected the 1989 averages.
3)
June 1989 value for Aluminum not used in calculations of average.
4)
Values in brackets indicate 1989 averages without the influence of the June 1989 values.
- Task Force initiated sampling for Co-60 l
22
. -- -.=-
1 J
Metals Introduction Rate Data Review Summary 1.
Effluent from the Main Turbine Condenser Hotwell Assuming an average flowate of 20,000 gallons per minute through the Main Turbine Condenser, and using the average metals values reported above, the following estimates were generated.
Average total metals concentration..........
0.019 milligrams / liter Introduction rate of metal............
4.6 pounds per operating day On the average, the constituents are:
Iron..
3.10 pounds (68%)
Copper..
0.80 pounds (17%)
Zinc..
0.60 pounds (14%)
Cobalt... 0.03 pounds
(<
1%)
Nickel 0.03 pounds
(<
1%)
Aluminum... 0.02 pounds
(<
1%)
Chromium... 0.02 pounds
(<
1%)
2.
Effluent from the Condensate System Domineralizers Assuming an average flowate of 20,000 gallons per minute through the Condensate System Domineralizers, and using the average metals values l
reported above, the following estimates were generated.
Average total metals concentration.........
0.0014 milligrams / liter Introduction rate of metal...........
0.34 pounds per operating day On the average, the constituents are:
Iror... 0.222 pounds (65%)
Copper.. 0.033 pounds (10%)
l Zine.. 0.020 pounds ( 6%)
Nickel.. 0.020 pounds ( 6%)
Aluminum.. 0.016 pounds ( 5%)
Cobalt.. 0.014 pounds ( 4%)
l l
Chromium.. 0.013 pounds ( 4%)
l l
On the average, removal efficiencies'are:
Copper..(96%)Af l
Zinc...(96%)
Iron...(93%)
Cobalt....(50%)
Chromium...(35%)
Nickel...(35%)
Aluminum... (10%)
- High removal of copper is contributing to our fuel integrity.
~.
23 L
Metals Introduction Rate Data Review Summary 3.
Feedwater System (including pumped forward heater drains)
Assuming an average flowate of 25,000 gallons per minute through the Feedwater System, and using the average metals values reported above, the following estimates were generated.
Average total metals concentration..........
0.0015 milligrams / liter Introduction rate rf metal............
0.44 pounds per operating day On the average, the constituents are:
Iron..
0.297 pounds (67%)
Nickel..
0.052 pounds (11%)
Copper... 0.026 pounds ( 6%)
Cinc..
0.020 pounds ( 5%)
Aluminum..
0.019 pounds ( 4%)
Chromium... 0.018 pounds ( 4%)
Cobalt... 0.012 pounds (-3%)
4.
Reactor Coolint System Assuming a volume of 80,000 gallons for the reactor vessel and associated piping, and the average metals concentrations reported
- above, l'
the following estimates were generated:
Hith two WCS demineralizers in service, at steady state reactor power, approximately 0.020 milligrams / liter total metals exists in the Reacter Colant System. This equates to approximately 0.013 pounds of metal suspended in the water, at any given time during reactor operation.
Assuming a flowrate of 125 gallons per minute for a WCS System domineralizer, and with two demineralizers in service, the following estimates were generated:
Approximate weight of metals removed.. 0.099 pounds per day The constituents of these metals are Iron.. 0.060 pounds per day Nickel.. 0.005 pounds per day Copper.. 0.010 pounds per day i
Zinc.. 0.009 pounds per day Aluminum.. 0.005 pounds per day Chromium.. 0.007 pounds per day Cobalt.. 0.003 pounds per day 24
.._m e
d l
i t
I f
4)
ASSEMBLE MATERIALS DATA ON REACTOR i
l-RECIRCULATION, REACTOR WATER CLEAN UP, FEEDWATER CONDENSATE, MAIN STEAM AND HEATER DRAINS.
I l
25
i.
e i
SYSTEN MATERIALS h
L Reactor Recirc.
Stainless Steel - 316K Stainless Steel - 304L f
Stainless Steel - 316L RWCU Carbon Steel - 106B Condensate Carbon Steel - 106B condensate Domins carbon Steel - 106B Saran or Poly Lined Steel Stainless Steel - 304 j
Main Steam Carbon Steel - 106B Carbon Steel - A155/A333 Stainless Steel - 304 i
Stainless Steel - 316 Heater Drains Carbon Steel - 106B Stainless Steel - 304 1 1/4 Chrome, 1/2 Moly Steel r
i Main Condenser 70/30 Copper / Nickel (tuDes)
Admiralty Brass Muntz Metal l
Tanks Aluminum (CST, Makeup Water) l l
26
l I
1 r
tI' i
l l
l l
l nattarat coneestrian - wesent Practnr l
consrITUtwrj canson
- svarattss ; staantess stettats ; monimatry
- monsmativ : aontmativ
- numrz nerat mese i
. stett toesjstatt3o4 : srett 316 :
6
- emess 443 : omass 444 : seass 44s ; e-171 asas : 209-ses4 Ca**oM 0.3 0.co o.oo j
.4 j
j j
se j
31 i
~ i j
CMacnIUM j
20 j
o.2 j
2.06 2.0 2.0 j
MANG8Mrst j
j j
1 g
j j
MICKEL 10.5 34 s
sItzcow g
g 1,5 j
j j
j o.1 j
.o Inow
- so.s4 66.42 65.92 s
o.4 MGLyectMUM 3,3 cosett 52.1 j COPPER 73 73 73 63 o.s van j
a.2 1.2 s.2 l
j j
j 25.7 j
25.7 j
2s.7 rruc
.i 37 j
o.2s AmstwIc
,, 3 j
marrnomy o.3
.e j
j j
j j
o.1 j
j MAGNtsIUM j
3
+
TIraNIUM 0.2 runssitw 3,3 ALUMINUM 94.6 27
-, -, ~,. -.,.
- s
s.
stilin paa O tuftit tas teetttml st LLitt-4 mfi sm (mnet-I sJ frsten 8; sten lutrittin 0,1 i,tl 1
1.5 1
1.5 3
4 I
t 18 11 Il 18 Il it 24 20 Irata 3
fetal til 1: tecirrelattu li 141 N
1 6
1 181 let endensata
(
111 1
43 14 3
1
)
t in t
tsg it?
Puisiter
$1 It 33 g
3 tt 151 lit leater Feeduler let til 156 3
113 g
(; g } t It 14 g Ig ( ggg titracties8taan lettertroiss let taissteaa til 13 43 14 11 g ( $4 3 gg ( til ill 11 fator Claunt lil 1( l 4 5 l 11 i 6illters lit l 10 fit LLL intill (<1811) ~ 1 l 28
p~ p. p e e t I l i r I t CONTROL ROD COBALT DATA GE ORIG. PROPOSED EQUIP. GE CR'S t Mass of Pin, Roller, and Button Material 233 g 233 g i + Weight Percent of Cobalt in Material 44-49 % 0.01 % Mass of Cobalt in Rod Wear Components 103.67 g HO.23 g r l l. Man-Rem per_ Outage from Co-60 r - Per Rod 0.6 0.001 - From 24 Rods 15 0.03 i i - From 145 Rods 89 0.2 i l 29 i )
s, ISOTOPE MEAMS OF. PRODUCTION MATERIALS Cr 51 Cr 50(n,g) Stainless Steel Mn 51 Stellite Mn 54 Fe 56(d,g) Carbon Steel Cr 53(d,n) Stainless Steel Cr 54(p,n) Stellite Co 57 Ni 58(g,p) Carbon Steel Fe 56(d,n) Stainless Steel Fe 56(p,g) Stellite Mn 55(d,2n) Ni 57(b+) Co 58 Mn 55(a,n) Carbon Steel Stainless Steel Stellite Fe 59 Fe 58(n,g) Carbon Steel-Stainless Steel Stellite Co 60 Co 59(n,g) Stellite Zn 65 Zn 64(n,g) Valve packing i Condenser tubes Tanks l Nb 95 descendant Kr SH5 Fission product i descendant Rb 95 Sb 124 Sb 123(n,g) Co, denser tubes o Startup source 30 i 5
l j I l l 5) PROVIDE CURRENT PIANT DOSE RATES, DOSE RATE TREND 8, AND CONPARISON TO OTHER PLANTS. WHY ARE WE DIFFERENT7 31 t
Fuerr VARIM U s tunnell PIPING PIPES
- gem i
ZINC
- TYPE (IMO.
4 N:S 77088
- Flec : 14CS
- %CS
- (I)BRLT :
smrzon
- Psa m o m cmeo! oemn mc INJBCrI N I OEMINS l 10 NCS 11EMIN l INW6 lPOMRIAI jpWWIAI,j MRCrION!
Onggt
- not water with I
- Preig. ;
3-44 IInitanted itating At nollow !Lo d 0 I Tef.t
- (Tryirq t IPins &
Fhr Filter Prior 2 nope cree
- lInvels No I t'r l At Startty itW p Bed l L6 J
! iso l SS I SS lbliers) lTo Deep Beds
- Possibly
- Anticipate
! 4 proximately : clinton No l ror w-3 :
- Post w-3
- osep med l
n ! No ! SS316 ; cs ! No
- Not neire
- M yrostin..
Jy : l w ttee ! crand <kir : iso iso seo omteswIatas
- Deep and n
- Yes
- SS304 : <sv
- Initimesd !
- yes, ey virtue ;
- h i-
.;. Installed,;
- Initiated ; taming At Alt
- or Iong Startup!
- close To Systne
- Deep and
- Apprusiimately :
- (Pins s nard sw erials l Perry l Time No I
too l Start I + '- It ! Yes ! SS304 ! Cs inollers) ! Pbr Valws I
- W.ely :
! w ttee : River send l No No No l Under Study j Deep Bed j It ! Yes l SS316 l CS IInitated I
- ent i
Yes,since:
- muered nesin:
- Project DRet l
No l No IMid 1987 ! Uruhr Study I(Sgtnsus) I 1 - 24 l ro l SS304 l SS304 l Initiated I ,E
- Ini. Accel;
= l
- Pen /blier:
Sh'-P=hanne ! No No l No No
- Deep and I - 3e
- sao l SS304 ; (s
- change i
- Pens and
- 1984 6 1995 NCS &
! Electro l l
- nollers
- NCs Pipe Iteplace-jrolishedand j
l ' No, Passivation
- Apr= =mtely :
Only, NCS I sent in Dryue11 ,lookingAt!Doiriqteell l w" l 10% l 18 0 i SS316 1 SS316 Ivalves Sch! Good OneunLFur Cooper ,Passivated No NOTE: TELEPHONE SURVEY RESULTS 32
l ? e GRAND GULF RIVER BEND I i
- 1. Condenser tubes are stainless
- 1. Most of the condenser tubes steel material.
Tube sheets are Admiralty metal and water boxes are carbon (71 Cu-28Zn-1Sn). The steel material. impingement tubes are 70-30Cu-Ni tubes. The tube Hotwell has a 1.5 minute sheets are Muntz metal effective detention. (60Cu-40Zn). The condenser shell is carbon steel material. Hotwell has a 5-minute effective detention. l l 2. Condensate System has two
- 2. Condensate system has eight operating and one standby operating and two standby precoat filters used during deep bed demineralizers, startup.
There-are six operating and two standby deep bed demineralizers.
- 3. Liquid radwaste system has
- 3. Radwaste has no precaat a 300 gpm precoat type type filter.
Attempt to
- filter, recycle all water.
All floor drain effluent is discharged to the environment. L 4. Reactor Water Clean Up has
- 4. Reactor Water Clean Up has a precoat filter rated a precoat filter rated about 1 1/2% feedwater about 1% feedwater flow, flow.
- 5. WCS Ring Header routed
- 5. WCS Ring Header routed I
along bioshield (i.e., along drywell (i.e., inside drywell radius). outside drywell radius). 1 33
} F i e = TURBINE STOP AND CONTROL VALVE SURVEY RESULTS k WEAT FREOURNCY IS IT PERFORMED? PLANT NAME STOP YALVE CONTROL VALVE i Browns Ferry Monthly 2 Brunswick Weekly Monthly Cooper Monthly Dresden Weekly Monthly Duane Arnold Monthly Peachbottom Weekly Weekly Oyster Creek Weekly Quad Cities Weekly Monthly f Vermont Yankee Monthly Grand Gulf Bi-weekly LaSalle Monthly Limerick Weekly Monthly l River Bend Weekly susquehanna Weekly Chinsan Monthly Monthly Kuosheng Monthly Monthly 34
l l I i L ( 6) ^ CONTACT EPRI AND INPO FOR CURRENT t INFORMATION ON DOSE RATES, RADIONUCLIDES I CAUSING THE DOSE RATES AND RINC I TREATMENT INFORMATION i 1 P I I 7) OBTAIN DATA ON BINC LEVELS i PRESENT IN OTHER PLANTS F 'l 35 ,-a..., .r.. ..n.
RADIONUCLIDE COMPARISON
SUMMARY
l .EPRI STUDY INDICATE 8 RBS AVERAGE DO8E RATES ABOVE THE NORMAL I i i R88 DOSE RATES TWICE THOSE AT NATURAL EINC OR THOSE INJECTING EINC i EPRI REPORTS Co-60 RESPONSIBLE FOR 90% OF DO8E RATE 8 I t EPRI STUDY OF HOPE CREEK AND HILLSTONE 1 SHOWS SAME RADIONUCLIDES WITH Co-60 PRIMARY CONCERN DUE TO IT8 THO GAMMA 8 AND 5.2 YEAR HALFLIFE EINC -65 WILL INCREASE BASED ON HOPE CREEK DATA f l t t i 9 i l 1 36
400 3 N.e Mont r C A n; ::naa m. upp.r u :ent - n -n. m C e N e e ::r./.s 4 mp. u E ane mont. - sone A a non-mn. moni. - o,.a m v 300 i oczip pi nt. _ fe,2fe, .s O A =* i a A u.ne a. xxL 1 g xm i o t o 200 es m r s w 4 i O i CD e - m, s.w a tan sea. o e' A,.e.no i , o, ,, 2 i a i 4,gg .,, a'"'m"*.u e a.u.s i , y_ _, i ru, e _,.2 e - p,2.,. * =_ _, y a s a.m a ,,ma. 4 4 c, a 2
- '4 % T enee e A n.e.n 2 mm.
A 5 a i Vt Ye.de a Mete 2 ,,.a y,,,,,gg, u, i na mu n a o, i i i i i 1 \\ 0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 i i i Operating Time (EFPY) I i I f l 37 l
,A r.h-w Gt PEDF E90GutY 2tIP Hope Creek New Plant Nine Mile Point 2 Millstone 1 s NATURAL ZINC Limarick 1 New Plant WPPS 2 New Plant Hatch 2 Replacement Pipe Peach Bottam 2 Replacement Pipe Vermont Yankee Replacment Pipe NON-ZINC (IORMAL) Grand Gulf New Plant River Bend New Plant Susquehanna 1 New Plant Susquehanna 2 New Plant Cooper Replacanent Pipe (Pmoxidized) Monticello Naplacanent Pipe Nine Mile Point 1 Replacement Pipe Dresden 2 Decontaminated Pipe Dresden 3 Decontaminated Pipe Pilgrim Decontamirated Pipe Quad Cities 2 Decontaminated Pipe i-l l 38 l i .a
h e 9 o n n i A 5 5 ?g t m n bl l l 5 C = e.
- =
e a3 v CQ y r/) l b b 00 1 e nw + } o
- g 8
e. CO a ua G e 8 w 4 n O I f I e o e o e o a A A a (urobs/ Ton)- dnpITng og-og 4 e
== 9
- l.. c.,
4 ' I t SOURCE TERM XNDUSTRY TRENDS l Remove the Radioactivity -c-Prevent the Introduction of Co Into Systems [ Replace Co With other Materials Displace Co-60 (2n). 40 = .4 g
V .:6' l l RIVER BEND'S ACTIVITIES t Remove the Radioactivity Hydrolt'ing Reactor Vessel Nozzles Reactor Sparger System Flushing RHR/LPCS Pipe Flush Prevent Introduction of Co Into Systems Maintenance Valve Repair Procedures Improved chemistry During Startup-Reolace Co With Other Materials 1 25 Control Rod-Pins & Rollers for RF-3 Feed Reg Valve Internals l l DisDlace the Co-60 1 Task Force Established 41 e i<-,... m .a
V, i e l t i SINC INJECTION CONSIDERATIONS. (WHY ARE WE' PROCEEDING CAUTIOUELY?) 3 POSSIBLE NEGATIVE EFFECTS ON FUEL INTEGRITY -1 i l
- . CONTROLLING Zn-65 EXCURSIONS DURING TRANSIENTS
.I FEEDWATER IRON CONCENTRATION EFFECTS 1 FEEDWATER COPPER' CONCENTRATION EFFECTS SS316 EXPERIENCE RIVER BEND'S ABILITY TO EFFECTIVELY REMOVE Co-60 s 42 t
-....--n.. . - ~. - e ) 1 i e f t. I 8). COMPLETE LISTING OF LOCATIONS AND TASK 8 i i PRODUCING EXPOSURES AT R1VER BEND 1 l ( s t 43
F: RF-2 MAN-REK DRYWELL Man-Rem JOB DESCRIPTION Elev. Source Expended
- Inservice Weld Inspection Norsle Inside the Bioshield ALL ruel 57.9 Shielding Installation and Removal 83'-127' WCS,RCS 39.9 Plant Painting ALL RCS,WCS 27,9
.i Inservice Weld Inspection WCS,RCS Outside the bioshield ALL RRR 21.9 WCS,RCS RP Surveillance ALL RER 29.9 LPCI,HPCS, Core Spray Valve Repair 125-136' RHR 17.1
- Recirc pump, valve & inst.
WCS HDR Maintenance 83'-95' RCS 15.6 Safety Relief Valves & LPCS,RCS Accumulators 123' HPCS 14.3 j WCS,RCS Limitorque Switch Bypass ALL RHR 13.9 Main Steam laolation Valve r HPSC,FW Repair and Inspection 136' WCS,RCS 12.0 i 4 WCS,RCS Inservice Snubber 7nspection ALL RER 11.9 WCS,RCS I Install Live-Load Packing ALL RER 6.2 L WCS,RCS LLRT/IST/ILRT Inspection ALL RER 6.9 WOE,RCS Operations Valve Lineup All RRR 5.9 WCS,RCS Inspection & Surveillance ALL RRR 4.5 Replace Loose Parts Monitor WCS,RCS Cable ( In/Out Bioshield) 83'-141' RER 4.2
- ~
Temporary shielding reduced Man-Rem e=pe~" her e, {ar RF-2.
- Flushing \\Hydolasing reduced 4an na
. ar " 'i ure. t r RF-2. Man-Rem Expended (Pocket Dosim to: Da t. h.
- )
44 ma m
- m
I RF-2 MAN-REN f-STEAM TUNNEL JOB DESCRIPTION Man-Rem Elev. Source Expended j Limitorque Switch Bypass 114-123' WCS,RHR 12.9
- WCS,HSIV,RCIC Valve Repair 114' WCS,RHR 7.5 t
Reinsulate WCS piping 114' WCS 6.9 Move conduit (HPt 85-5963) 114' WCS 6.5 h RP Surveillance ALL WCS,RHR 5.8 LLRT/IST/ILRT Inspection ALL WCS,RHR 5.9 I e Install Live-Load Packing 114' WCS,RHR 4.2
- Shielding Installation and Removal 114' WCS,RHR 3.9 Operations Valve Lineup All WCS,RHR 3.9 i
Inspection & Surveilance ALL WCS,RHR 2.7 Inservice Weld Inspection ALL WCS,RHR 2.S Inservice Snubber Inspection ALL WCS,RHR 9.6 -Temporary shielding reduced Man-Rem expenditure.
- Flushing \\Hydolasing reduced Man-Rem expenditure.
Man-Rem Expended (Pocket Dosimeter Data from RWP's) 45
__.. _ ~.. _ [. l toeperin e of Refuell a estage High tapesure Jobe (Nejorestages) 300 M $ttlP110N-E-1 E W-2Est Resarks Ree-tee Raa-tes Mae-tes 1)!acrease dose rate : 2.5. ReacterAssembly/Disasseebir, $huffia. sed lespecties 1 14 11
- 2) Stone separator belts (2.0 Rat-Ree).
3)t unter level est salatalud at flasse duties sees asistenance activity (1.5 Man-Ree) 1)!acrease done rates a 2.5. l' Rafe$teseisolatletValve Repair and leapecties 6 12 6 2)$tV's renoval laterference. 3)Pover, equipeest, and shortsee. Operstles-Surveillance,
- 1) Increase dose rates 2.5.
Routies and Valve Lineup 10 12 e/a i s Notlaoriginalscopeofworkfor1989
- Shieldlag installaties saved apprealaately 700 Naa-tee for F-2 47
. ~.. _. -. ' ik 9)' REVIEW T4PRI DOCUMENT, " COBALT CONTAHINATION RESULTING FROM VALVE MAINTRMAR'CB," EVALUATE AGAIW8T OUR PROCEDURES AND RECOMMEND IMPROVEMENTS. WEAT CAN WE DO BETTER7 1 4-48
i e EPRI VALVE MkINTENANCE r conc 19sions
- . cobalt input due to valve seat maintenance can range from 10 to 30 grams per year in PWRs and - from 30 to 90 grams per year in BWRs.
This represents 10-30 percent of the estimated input rates from wear and corrosion mechanisms. Grinding of valve seats is the preferred method to restore damaged seat faces because it can be done quickly and in place. Options to reduce the. amount of grinding include replacing the seat (when possible), replacing the valve, or repairing the valve out of line. Substantial portions of the grinding debris can migrate into the valve runs and piping, where it may be impossible to remove. These problems l can be minimized. Post-maintenance cleaning techniques are not necessarily adequate. Vacuuming, followed by wiping, was determined to be a more efficient means of cleaning. Maintenance procedures are lacking in the areas of valve seat grinding l-techniques, preventive measures, postwork cleaning, and inspection. Procedures should be improved to reflect the inartance of limiting cobalt input. The valves that require frequent' repairs are those that undergo regular and rigorous testing, such as MSIVs, feedwater check, and containment isolation valves. Some valve designs promote excessive erosion or wear of the seating surfaces. Improved valve design will help alleviate this problem. Cobalt-based alloys have been indiscriminately specified for use as hard-facing material in valves, regardless of the service encountered. 49
i 1A .i i s i l' 1 1 REVIEW OF RIV:CE BEND NAINTENANCE PROCEDURES l i 'j l: _23 PROCEDURES IDENTIFIED WHICH MAY CAUSE COBALT INTRUSION. l l.. l< 1 l WE HAVE RECOGNIZED THAT THE PROCEDURES CAN BE IMPROVED IN THE l AREA OF CLEANLINESS CONTROL. 4 l REVIEW IS ONGOING AND WILL INCLUDE ALARA GROUP. NEED TO ENHANCE TRAINING OF MAINTENANCE PERSONNEL ON COBALT 1 l. l' REDUCTION. i i l 50 .s.
- ent e ENGINEERING REVIEW RIVER BEND STATION - UNIT 1 j GULF STATES UTILITIES COMPANY MR NO.
- 1. REVIEW CHECKLISTS ALARA %o YES N/A IV. CONTROL OF AIRBORNE CONT AMINANTS AND GASEOUS RADIATION SOURCES
- 16. Use of air pressure gradients and flow from crea of low potential cirborne contominonts to creos of higher potential contamination.
- 17. Ventilation and goseous treatment systems designed f or ease of maintenance and located to prevent exposure from odjacent equipment.
- 18. Use of portoble ventilation systems for the control of locolizec cirborne contamination.
- 19. Utilization of wet transfer or storage for highly contaminated components.
V. CRUD CONTROL
- 20. Use of low nickel and low cobolt bearing materials (limits the procxtion of CO-58 and CO-60).
- 21. Use of Chemistry controls in reactor systems.
- 22. Use of decontomination, fluring, filtration and purification on reactor systems.
- 23. Minimize crud traps by providing for tominor flow and smooth internal piping surf aces. Avoid stagnant vertical legs, locate connections above pipe centerlines.
- 24. Use of recirculation ond/or flushing lines to albw for chemical or physical removal of radiocctive materiol.
I V]. FJDI ATION MONITORING SYSTEMS
- 25. Reccout capability at the main control creo.
- 26. Placement of detectors for optimum coverage of crecs.
- 27. Circuitry which indicates component f ailure.
- 28. Local clorm and readout.
- 29. Clear and unambiguous readout.
- 30. Ranges adequate to ensure reedout of the highest and lowest anticipated reading.
- 31. Copobility to permanently record oil readouts.
VII. RES1N AND SLUDGE COLLECTION AND TRE ATMENT SYSTEM
- 32. Accumulation of radioactive materials in components con be r educed by the use of:
A. Short runs of piping. B. Large diameter pipe. C. Reduced number of pipe fittings. D. Avoiding dead legs and low points. E. Sloping horizontal runs to toke, odvantage of gravity flow. F. Use of large radius bends in piping. l r Z 1 ENolNEERjNo R(vlEW t
V 4 i e. ,e'-. TASK FORCE' CONCLUSIONS 7 FISSION PRODUCTS ARE NOT A MAJOR NO FAILED FUEL TO DATE CONTRIBU10R TO RADIATION SOURCE TERM COBALT-60 IS THE PRIMARY ISOTOPE BWR-6 PLANTS ARE " HOTTER"-PLANTS-l RIVER 7 BEND'S SOURCE TERM - COMPARES - FAVORABLY WITH'THE OTHER BWR-6'S MAJORITY OF MAN-REM EXPENDED IS ASSOCIATED WITH WORK ON THE l REACTOR COOLANT SYSTEM, RHR, AND REACTOR WATER CLEAN UP SYSTEMS-
- ~ LARGE INCREASES 1N ELEMENTAL AND RADIOACTIVE CORROSION PRODUCTS ARE EXPERIENCED DURING PLANT START-UP FROM REFUELING.
MAINTENANCE PROCEDURES ARE IN PLACE FOR COBALT INTRUSION. IMPROVEMENTS IN THE PROCEDURES AND TRAINING ARE NEEDED. LOW COBALT REMOVAL EFFICIENCY IN THE CONDENSATE AND RADWASTE l ' SYSTEMS l-l MAIN: STEAM" ISOLATION VALVES ARE EXPERIENCING EXCESSIVE WEAR. AGGRESSIVE ALARA TECHNIQUES HAVE BEEN EFFECTIVE IN MINIMIZING EXPOSURE 52
[ J RECCMMENDATIONS Maximize long cycle cleanup of condensate /feedwater prior to startup for more effective metal removal. Ensure cobalt removal concepts are fully incorporated into our maintenance procedures and maintenance personnel are sensitized to cleanliness methods when working on components containing cobalt. Evaluate the Grand Gulf slow shutdown method. Sensitize design engineers to the incorporation of components - with reduced cobalt. Continue to implement effective methods of shielding and flushing. Continue to remove " dead leg" hot spots through design changes. Evaluate cost / benefit of modifying WCS ring header. Continue to evaluate industry experjence with zinc injection and chemical decontamination. Evalucte the addition of filters for the hotwell, Radwaste Stream and CST. Evaluate methods / cost / benefits of reducing MSIV wear. 53
{ ~~ ~ o' l b-J -WRAP-UP _j .I f -1 WHEN COMPARED TO OTHER BWR'S, RIVER BEND HAS HIGH RADIATION LEVELS IN THE DRYWELL, BUT WE ARE NOT'AN OUTLIER. ALL BWR/6'S ARE HOITER PLANTS THAN EARLY BWR'S. -316 SS PLANTS (RBS)'ARE HOTTER THAN 304 SS PLANTS. i l' WE WILL CONTINUE OUR EFFORTS TO REDUCE THE SOURCE TERM. 1 I f' EVEN WITH OUR HIGHER SOURCE TERM, WE HAVE HAD LOWER EXPOSURE, WHICH IS A TESTIMONIAL TO OUR EXCELLENT ALARA PROGRAM. 54 ..}}