ML20238D865
| ML20238D865 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 02/28/1985 |
| From: | Law R, Peterson J, Sundberg L PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20237L734 | List: |
| References | |
| NUDOCS 8709110454 | |
| Download: ML20238D865 (128) | |
Text
,,. . . , _..
~'~ ~ ~
l pf : 3.; ,
. .y ,
S y Enclosure 1
. r-Docket Wos. 50-277 i.
50-278 l-
+
L .
, .j i
1 PEACH BOTTOM III-HYDROGEN' WATER CHEMISTRY MINI' TEST' FINAL' REPORT-s.
y R. J. LAW ,
L. L. SUNDBERG J. P. PETERSON R. B. DAVIS FEBRUARY 1985
- l Compiled By:
(k .]
// f/dib
,M. Siegler #
Reviewed and W
Approved By:
R.-L. Cowan, Manager Plant Chemical and Radiation Technology Approved By:
g --)p M . .
E. Kiss, Manager l Plant Technology i
m i
.i 1
7 8709110454 870824 PDR ADOCK 05000277 G PM 2_=_ _ _ _ _ _ _ _ _ _ _ _ -_; .
- __ a
L:
1 l
1 h.
DISCLAIMER OF RESPONSIBILITY
\ This document was prepared by or for me General ElecVic Company. Neither me General Elecmc Company not any of me contabutors to this document:
A. Makes ersy warranty or representation, express or implied, wlm respect to the accuracy, completeness, or usetutness of the informe00n containedin mas docu-ment, or that the use of any informe00n discbsed on thrs document may not ininnge pnvetely owned rights; or l B. Assumes any responsibihty for habikty or damage of any kmd wtuch may result l trom me use of anyinforme00n disclosed in ttus document.
l l
i
)
l i
l 1
l I
__ ---__-_J
L e.,
a
[.f;).,
l 's ACKNOWLEDGEMENTS h) >
- The assistance , of the management and personnel of. the philadelphia Electric Company. and the Peach Bottom Nuclear Power . Station 'is gratefully. acknowledged. Particular thanks are due to Drew Odell, Steve Conrad, Harry McFadden, Harry Watson, and Bob Scholz..
1 h
n Thanks also go to the combined and educated efforts of the.
following General Electric personnel who contributed to the timely completion of the test: R. L. Armstrong, A. E. Conti, R. B. Davis, R. J. Law, W. B. Nelson, J. P. Peterson, D. N.
(.
l Rodgers, M. Siegler and L. L. Sundberg.
k l
I
__-_a_.. _ - _ _ - _ _ _ ._ _ _ _ . i
/: - R f- 11
-l ABSTRACT -i l
8'-
1 A Hydrogen Water Chemistry . pre-implementation test was successfully completed at the Peach Bottom-3 Nuclear Power Di Station during December 1984. The test results provide plant !
specific HWC implementation information, such as:
Offgas system general performance response Shielding performance / requirements
[)
Reactor recirculation water Dissolved oxygen concentration as a function ..
l
.I of injected hydrogen J Electrochemical potential'as a function of l q
recirculation water dissolved oxygen content l 4 Hydrogen / oxygen injection points and flow rates The basis for permanent tech / spec licensing changes-using measured plant parameters 3
Safety analysis and requirements j j
h i 1
1 4
Mb' L l l )
l l
l L !
b TABLE OF CONTENTS PAGE
- 1.
SUMMARY
1-1 1.1 Operations 1-1 3: 1-2
- 1.2 .Results
- 2. . TEST DESCRIPTION 2-1
- 3. CHEMISTRY RESULTS 3-1 3.1 Feedwater Chemistry 3-3 3.2 Reactor Water Chemistry 3-6 3.3 Main Steam Chemistry. 3-10 4-1
- 4. ELECTROCHEMI' CAL POTENTIAL MEASUREMENTS Introduction' 4-1 4.1 4.2 Experimental 4-6 4.3 Results 4-8 4.4. Discussion 4-9 l 4.5' References 4-11 5-1
- 5. RADIATION SURVEYS 5-1 uS.1 Results 5.1.1 Steam Line Monitors 5-2 5.1.2 Interior Measurements 5-2 y' .
5.1.3 -Plant Exterior Within Protected Area 5-2 5.1.4 Plant Exterior Outside Protected Area 5-15 5-16 5.2 Discussion 5-25 5.3 Conclusions 6-1
- 6. HYDROGEN DISTRIBUTION STUDIES A-1 APPENDIX A B-2 APPENDIX B N
h I
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _J
LIST OF TABLES TABLE NO. PAGE 2-1 Identification of Hydrogen Injection Test Sequence. 2-2 L
y L 4-1 Electrochemical Potentials and Water Chemistry' 4-4 B- 5 .1.1,. Average Main Steam,Line Monitors and Ratios to Zero Hydrogen Addition 5-3 5.1.2.1 Interior Plant Dose Rate Measurement Locations 5-12/5-13 5.1.2.2 Interior Dose Rate Measurements (PECO)' 5-14 5.1.3.1 Exterior Radiation Survey Points 5-18 5.1.3.2 Exterior'to Plant Inside Protected' Area Dose Rate Measurements 5-20/5-21
? 5.1.4.1 Exterior to Plant Outside Protected Area Dose j Rate Measurements 5-22/5-23 5.2.1 Exterior to Plant Dose Rates Group by Direction 5-26 6-1 Distribution Test Results 6-3 3
?
L LIST OF FIGURES I' . FIGURE NO.
PAGE I
1-1 Peach Bottom 3: Feedwater Hydrogen Requirements ,
as a Function of Power 1-4 2 3-1 Peach Bottom III Mini Test (F/W 0xygen Concentration) 3-4 j December 18-20, 1984 3-2 Peach Bottom III Minf Test (F/W Conductivity) 3-5 December 18-20, 1984 3-3 Peach Bottom III Mini Test (Recirc 0xygen Concentration) 3-7 December' 18-20, 1984 L 3-9 3-4 Peach Bottom III Mini Test (Recirc Conductivity)
December 18-20, 1984
) 3-5 Peach. Bottom III Mini Test (Recirc Hydrogen Concentration) 3-11 3-6 Peach Bottom III Mini Test (Steam Oxygen Concentration) 3-12 3-7 Peach Bottom III Mini Test (Steam Hydrogen Concentration) 3-14 4-1 ECPs From Dresden-2 and Lab CERTs 4-3 4-2 ECPs From Ringhals-1 CERTs 4-5 4-3 Reference and Metal Electrodes 4-7 4-4 ECPs at Two Operating BWRs 4-10 5.1.2.1A Reactor Building Elevation 135 Feet 5-4 B Turbine Building Elevation 135 Feet 5-5 C Turbine Building Elevation 116 Feet S-6 D Turbine Building Elevation 165 Feet 5-7 5-8 E Turbine Building Elevation 220 Feet F New Administration Building 4th Floor 5-9 G New Administration Building 3rd Floor 5-10 H New Administration Building Roof 5-11 5.1.3.1 Dose Rate Measurement Locations Inside the Protected 3 Area 5-19 5.1.4.1 Environmental Dose Rate Measurement Locations 5-24 5.2.1 Steam Line Monitors - Peach Bottom-3 5-27 L _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
e' a
'l '
(- s
^
LIST OF FIGURES ,(
FIGURE NO. PAGE 5.2.2 Gross and Net Dose Rate With Power 5-28 t' 5-29 ji. 5.2.3 Turbine Dose Rates.- Peach Bottom-3 t
5.2.4 Turbine Roof Dose Rates - Peach Bottom-3 4 5-30 0
5.2.5 Dose Rate Relative to Distance Rom Turbine -
Peach Bottom-3 Mini HWC Test 5-31 g; Exterior Environmental Dose Rates (East) 5-32 5.2.6 l 5.2.7 ExteriorEnvironmentalDoseRates(Nort![nst) .5-33 5.2.8 Exterior Environmental Dose Rates (North) 5-34
' 5-35
)~ 5.2.9 Background Environmental Dose Rates <
.(
5-36
~
5.2.10 Calculated Relative Dose At Distance ,r 6.1 Peach Bottom-3 Feedwater System 6-2
-i 6.2 Top View Sketch of Reactor Pressure Vesse.fNozzles 6-5
/ ,
Y , in
'f e ,
e
)
y l
.5 >
s
\ /
- i
/>
L .
J t
.p ..
,. p.
- y
' tv _ , y Nk; **
n
, W i
- l. ,,
.p y.~ j i
- 1.
SUMMARY
n- '
V .c ,,
si
') I
]
r-? .- ' { y, t
.'. ' h_l .,tf e J "+ 1.1 OPERATIONS 3,
7 i . g> M,f J, .
s iu . . ,.
liydrogen was ,in$td.ed into the three Peach Bottom-3 feedw(ater p' '" - w
- 1. y '.
g 1
pumps. Vahdikinjectionrateswere,usedinordertosuppress ,
the reactor recirculation water dissolved oxygen concentrations, m,
and to reduce the ciectrochemical potential (ECP) to levels that -
x ,;
wouldeliminat{Jbtergranularstresscorrosioncracking(ICSCC).
3
- 2. The testing Itas conducted at 90% and 100% power levels.
'3. Oxygen was Wyected into the offgas system to recombine with the 1 3-( excess hydrogen.
- 6. ,,
P ,,
4.' Uater chemistry measurements were made on feedwater, reactor recirculation water and main steam sample streams.f 1
- 5. Transition metal ion concentrations (Cu " and Zn") were
/ measured in'the reactor recirculation water during the various
' hydrogen addition test sequences.
3 i
- 6. Electrochemical potential (ECP) measurements were performed in
' l recirculation water.
s 1
/
-7. Walk around radiation surveys were made inside the Reactor and Turbine buildings and at variovo external locations.
s ik ,
f.
- 8. A special, test was performed to determine the effects of ;
3- .g l
' feedwater hydrogen distribution variations.
y4s >
A )
\
l
\ ,
s ,
l 3
1 1-1 s :t n' - : !
't i bi bl s i
, 'N i
_ .-___.l.m_._c k-_ _ -
f .
1.2 RESULTS
- 1. The WC recirculation piping protection specification for Peach Bottom Unit 3 is $15 ppb dissolved oxygen and a conductivity of This c- 3 30 us/cm, with a target conductivity of 10.2 pS/cm.
condition was obtained with 57 SCFM of hydrogen (STP-25'C, 760 mm L
.Hg) injected into the feedwater at 100% power.
- 2. A feedwater hydrogen concentration versus power level correlation lO to maintain 10 ppb, 15 ppb, or 20 ppb dissolved oxygen in the recirculation water was developed specifically for Peach Bottom-3. The required feedwater hydrogen concentration varies logarithmically from 1.28 ppm at 100% power to w .10 ppm at 20%
lO power as shown in Figure 1-1.
- 3. Unequal distribution of hydrogen can occur in the reactor vessel unless proper hydrogen injection flow controls / logic are utilized.
- 4. At the hydrogen injection rates required to protect the recirculation piping the general radiation level increased to lQ-approximately three times the background level without hydrogen inj ection. This is attributed to the increased formation of more volatile nitrogen species in the WC reducing environment.
- 5. No problems were encountered with the injection of oxygen into the offgas system.
- 6. The recirculation water conductivity decreased,
-est egn=s==
%.04 pS/cm, from its baseline value to the value at the r imum hydrogen injection rate.
J 1-2 1
~
, n i ..
2 '!
l U.. , .,
P
-> 7. The feeddat O conductivity increaced %0.0) pS/cm from its baseline value to the value at the maximum hydrogen injection s
, l s1 . 3
- 8. The normal feedwater dial.c1ved oxygen was 410 ppb. This g -i decreased to <2 ppb with ircreasing hydrogen injection. Oxyg,en
.o E addition into the feedw. ster abould be considered with at without
. .HUC t'o maintain 2515 ppb, as per SIL 136-Supplement 3.
j y 9. Hydrogen addition caused a decrease in the reactor recirculation
' wateT di m Aved copper concentrations.
- 10. Entdnsive? electrochemical and CERT t,tudios at the Dresden-2 BWR have demonstrated that ICSCC in sensitized 304SS is eliminated by j 3 ~
i HWC~oparation when the, electrochemical potential of stainless i sine:L is below a threshold vaine of -0.230 V(SHE). At,Jeach l
/
Bottem this value was achieved, with margin, sten the (se6 water H E ition reduced the recirculation, water disselved oxygen 2
concentration to 15 ppb at both cho 90% and 100% power levels. ; l
\
l
- 11. W H W licensing process hss been int.tiated and the p1tht ~ )
apecific data base for permanent Tec5.:utcal specification changes 3
has been established. l
- 12. Tha plant and utility staff members have acquired considerable j
~
HWC experJence and technology.
l l
t J
l
(
1-3
. .r
% . pg - FICURE 1-1 1
PEACH BOTTOM 3 FEEDWATER HYDROGEN REQUIREMENTS i AS A FUNCTION OF POWER ;
a o' o -
.j A ,1 ff ff
_ . _ . . . . . . _ _ _ .. . . . ~ . .
-- / = nlogC + A __ .
__4_ Recirculation n A C . . . ._ . . . . .
ol 73.2 84.1: t 3
2.0 10 ppb 02=C1 . .
._ f e-..-.. 15 ppb 02 =. C2 73.8 91.6 . .. . . . . .
(..___._ - 2 0 ppb 02=C3 75.4 100 .L. .. __._. __... .
1
.__..a.__ .. . _ _ , - _ _ - __ _
..__..._w. __- . ___ . ./.
m._._____ ._.._. _ . . _ _ _ . . . _ _ _ . . . ..
). .,
, . ._a
~
, , ,'l y'1.0
/ / /
- a. - / / r
/ !
. / / -/
), g -
1 /- /
/ /' / '
!: i 0.7 .m 3 .< . . . f. y #. ; y w ;
.._.. = . . - -- . ;=. : / / =.=f . . . .. ;
f _z-ig.
- =-
u _-.
.=.-. =_ .:. .
f f. _
h"o,5 -
y;r . -- -
/ /. / - M-% -
A: : _ ..: ,
...._ Ji- f : / / ;.: :_:::i .2 . . , _j
~
= ~
gg
= .?..i.=. . . .
. = b.5.. .:= %
-.=. =. -
. .. - AI c 0.4 ., ..... . . . - _ . . .
. . . . . .x...
'g ._._ .
._ . . . .._ s
-t
/-S _ .. _
. _s y p _ __ __..._
)o
, . 9, 3 ;__ _ _- __ _ .-_. ..=... ~ -
y f... g. v
_.~...__.
D .p a w
. . . /...
x .
---2---
ds..__.. .
0.2
___.-/
- f. ._ _ f . . . . . . .
. . ~ _.
.._.j..
- r. . .
)
l .
l
. - .....L_ . . . . .
,ggg ._
'20 30 40 50 60 70 80 90 100 POWER, %
1-4 i
- - - _ _ _ _ _ _ _______z___.
1 I
1 1
- 2. TEST DESCRIPTION The EWC Mini Test was conducted in accordance with PECO Peach Bottom Site Procedures; Receiving inspection Procedure PB10-17-84, MAT 1599, Part j
2, Special 755 HWC Test Plan and GE TP&P 519.1153 (Rev. 1), 50P 519.1117. f The hydrogen additions were performed over a three-day period during the second and third shifts to conform with as low as reasonably acceptable 3
(ALARA) guidelines at 90% and 100% power. Sufficient hydrogen was injected into the three feedwater pump inlets to suppress the reactor recirculation water dissolved oxygen concentrations to below that required for a protec-tive electrochemical potential. Stoichiometric quantities of oxygen were p
injected into the offgas system to recombine with the injected hydrogen to )
minimize the effects on offgas system performance. Table 2-1 identifies the test sequences and the actual hydrogen addition rates.
Most of the testing was performed with equal distribution of the 1 hydrogen into the three feedwater pumps. A special test sequence was {
conducted to verify the effects on dissolved oxygen in both recirculation l loops with unequal hydrogen distribution into the two feedwater trains.
3 i Three sequences were added to inject 100% of the hydrogen flow separately l into each feedwater pump (7A. 7B, and 7C). The results of these tests (
l indicate that a sufficient problem exists to warrant additional flow i
- controls and/or monitors to insure that the oxygen levels are sufficiently f suppressed in both recirculation loops. I I
Water chemistry monitoring equipment was installed on four streams to f p measure dissolved oxygen, dissolved hydrogen, conductivity and pH. A summary of these measurements and results are contained in Section 3. A l
spread sheet of the data is included in Appendix A. J i
)
l i
2-1 i
TABLE 2-1 Identification of Hydrogen Injection Test Sequences INJECTION RATE DATE TIME OF HYDROGEN
- POWER h: SEQUENCE (SCFM) (%)
Baseline 12/17 2321 0 90 la 12/18 0301 6.8 90
, Ib 0335 14.4 90 le ~0410 21.0 90 2a 0544 28.0 90 0 90
) Baseline 2013 2b 2258 37.6 90 2c 2346 48.6 90 3a 12/19 0120 55.6- 90 3b 0143 65.2 90 3c 0212 71.0 90-Baseline 2009 0 100 4C 2230 71.2 100 1 2310 80 100 SA .
2335 88 100 5B 12/20 0002 96 100 SC 0130 109 100 SD 0230 56 100 6A 7A 0320 45.4 Valve A 100 7B 0350 44.4 Valve B 100 7C 0420 45.0 Valve C 100 3.
- 1/3 into each pump, except for Sequences 7A, B, C.
2-2
1 1
On-line transition metal analyses were performed on these same streams at the non HWC baseline conditions and exclusively on the reactor recircu-lation water during periods of hydrogen addition. .These results are presented in Appendix B.
.) <
An autoclave was' installed on loop A reactor recirculation water for ECP measurements at various hold periods. These results are' discussed'in <
Section 4.
h j
5 2-3
t L
b
- 3. CHEMISTRY RESULTS This section summarizes the chemistry findings for the Peach Bottom-3 hydrogen addition minitest conducted during December 18-20, 1984. The sample points und instrumentation used in the test are shown below:
)
Hydrogen Sample Point Conductivity Oxygen pH "A" Feedwater- X X X "B" Feedwater X X X
)- Recire Water X X X X Main Steam X X "A" Jet Pump Loop X "B" Jet Pump Loop X The first four-sample points were tee connections downstream of the
)
temperature conditioning trim coolers'in the sample hood located at the 165-foot elevation of the reactor building. All four ifnes passed through a Forma temperature conditioning bath to the sensor panels, and effluents drained to the sample hood. The jet pump sample lines were located at the instrument racks at the 135-foot elevation of the reactor building. The sample lines were routed to countercurrent tube-in-tube closed cooling water heat exchangers, followed by constant temperature baths for condi-3 tioning to 25'C.
The following chemistry instrumentation was used for the test:
Oxygen Meter: Orbisphere Model 2606 l 0xygen Probe: Orbisphere Model 2110 i j
Hydrogen Meter: Orbisphere Model 2630 Hydrogen Probe: Orbisphere Model 2230 3 Conductivity Meter: Leeds and Northrup Model 7076-1 Conductivity Cell: Leeds and Northrup Model 4973 (0.01 cell constant) pH Meter: Leeds and Northrup Model 7076-3 pH Sensor: Leeds and Northrup Model 7773 ;
Temperature Meter: YSI Model 4320 Temperature Probe: YS1 Model 44018 i
3-1 1 i
l
l Gas calibrations were performed on a ' daily basis by saturating a volume of water, temperature conditioned to 25'C, with primary standard gas mixtures, and continuously recirculating the fluid through the sensor chambers. The temperature, the barometric pressure, the water vapor pressure at temperature, the system back pressure, and the gas composition p were all logged for each instrument calibration. The gas solubility coefficient at temperature completes the information package for the J i
calibration input. The conductivity meters were calibrated on site with a pr cision decade resistance box and digital voltmeter. The pH meter and )
sensor was calibrated on site with NBS traceable reference buffers, With
)
the exception of the jet pump oxygen signals and the recirculation water pH signal, instrument output was continuously monitored on strip chart record- ;
ers. f b
l' Several corrections have been made to the official data sheets that were produced at the site during the various test sequences. The refined data package with most of the key test data is shown in Appendix A. All conductivity measurements have been temperature corrected to 25'C. In most cases, the corrections to the reactor water conductivities are negligible.
Most feedwater corrections were about 10% downward due to measurements at 26*C. Steam oxygen concentrations during the testing at 100% power (day 3) have been increased by 2% due to a calibration correction. Several rec-
) "B" feedwater conciliations have been made in the data for the "A" and trains after post-test review of the strip chart recordings. In many cases, the "A" and "B" data were switched on the original log sheets.
Additional data points during testing at 100% power were obtained from the strip chart recordings. These were not official test sequences per the test plan and procedures. They are dessgnated as Sequences 41-45, and were obtained during periods of constant hydrogen injection flow rates.
?
)
3-2
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ --- i
t.
3.1 FEEDWATER CHEMISTRY l-Baseline dissolved oxygen concentrations in Peach Bottom-3 feedwater were on the order of 10 ppb. Earlier plant measurements had indicated substantially higher concentrations. The baseline concentrations are lower than the recommended operating limit of 2525 ppb (SIL 136 - Supplement 3).
7 '
The concentration of feedwater oxygen was reduced to less than 2 ppb at the maximum hydrogen addition rate of 2.45 ppm (Figure 3-1). The reduction in feedwater oxygen was not a step change associated with incremental hydrogen addition rates, but rather a smooth gradual process over the entire testing
}
interval.- The decrease in feedwater oxygen concentration is the result of a lower equilibrium oxygen concentration in the main condenser,'since the main steam contains less oxygen when hydrogen is added. It is not the result of hydrogen-oxygen recombination in the feedwater train. The
] j oxygen concentrations returned to their baseline values in an equally gradual fashion when hydrogen addition was stopped. The concern over low concentrations of feedwater dissolved oxygen arises from the general ,
corrosion of the carbon steel feedvater piping, and the release of soluble iron and transport to the reactor. Soluble iron can form a very tenacious fuel deposit, and can cause degraded heat transfer, and perhaps fuel failure.
3 Figure 3-2 shows the feedwater conductivity as a function of feedwater hydrogen concentration. A small, but significant inenase in conductivity 1 is observed as the hydrogen concentration increases. If the conductivity )
{
- - increase is solely attributed to the ferrous ion, then the feedwater j soluble iron concentration increased by about 4 ppb from the baseline I j
condition to the period of the maximum hydrogen addition rate. Like oxygen, the conductivity changed in a gradual fashion over the testing interval, f
- g. and returned to baseline values in a gradual fashion when the hydrogen
{
addition system was turned off.
l l
l 3-3 i
J
d 45 4 -
2 N
5 _
m h
) _ _
0
_b m _
t 2 p s p vT a
a e NS (
n r i o e i w n4 8 b t
a o i
c 6 rP M9 3 4 t 1
~54 1 n%
e0 -
u1 1 0
a c0 n1 1
2 o -
m8 1
'3 C n
o 4
3 c 2 o r C2 e g
t t
e 1 o
b 4 r o m 4 d B e ;
H y
c
^
6 _
e 2 r h D 8 er -
c m s t e 0 a w a N o w o t_
e Z de P P e%
F0 1 9 a
- 4 4 t \ g 0 O h
a v
o n 4 N ;c u
N '
i 0
n 0 0 0 0 0 0 0 0 0 0 0, 0 0 O '
0 2 1 0 9 8 7 6 5 4 3 2 l 0 1 1 1 Do3 c 0 COO e O j,e
,Il ll
(a-- 4 -
/
2
/ c -
u
- S
) .
0 m t -
b p S 2 s p e _o
(
uiT e 3 S nr oe i
n4 8 / b c 6 iw t
a r o M9 1 5 -
4 1 tP n
, e 54 e%
i 0 c0 ml l 2 n0
- 3J C o1 m8 1 2 no o r
" e g
5 3
/
1 t e t o b e4 r o
m 4 d -
B e H
y c
e h
c D
3 8
0 r
e t r ae a - ww e ' 0 3 4
do P eP e
2 F%
. 2 3
1 db.- 0 4
0 4
0 9
E 1 R c 14 O W
M 3- -
1 v
i r 3 0
l 1 0
6 4 2 0 8 6 4 2 0 8 6 4 2 0 8 6 4 7 7 7 7 6 6 6 6 6 5 5 5 5 5 4 4 4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 O O 0 0 O O O 0 O 0 0 0 0
^ E D \ $ v y_. 3 $ o s_2. o 3 ] e b-l !l)
4 At the first demonstration: test of hydrogen addition at:the Dresden-2
~
- reactor, a. gradual . decrease in . feedwater oxygen from 55 to 25 ppb was observed as the feedwater hydrogen concentration was increased in stepwise increments. . ' However, no feedwater conductivity changes were observed..
Apparently, the 25 ppb dissolved. oxygen measured at the highest hydrogen p
. addition rate was sufficient to protect the carbon steel feedwater piping-from general corrosion. At peach Bottom-3, this is not the case. If.
condenser air inleakage remains unchanged, the utility should also consider
- feedwater oxygen addition-if a hydrogen water chemistry flowsheet is to be y permanently adopted. At full power, an oxygen addition rate of %.07 SCFM to the'feedwater would be sufficient to maintain feedwater oxygen concen-trations above 25 ppb during hydrogen addition. A careful engineering evaluation of the actual point of oxygen injection will be required.
) A year of full power operation, with an increase of 4 ppb soluble iron in'the feedwater, will result in the input of an additional 475 pounds of iron to the core. About 70% of this input will deposit on fuel surfaces.
3.2 REACTOR WATER CHEMISTRY At peach Bottom Unit 3, hydrogen addition changed the reactor recircu-
'lation water oxygen concentration in a predictable fashion, as depicted in y
Figure 3-3 with a logarithmic y-axis. At full power, the addition of 2.45 ppm of hydrogen to the feedwater reduced the primary coolant dissolved oxygen concentration from 196 to 4 ppb. The test data show, that a full-e power feedwater hydrogen concentration of 1.28 ppm is required to maintain the recirculation water dissolved oxygen concentration at 15 ppb. For plant operation at less than full power, the feedwater hydrogen addition '
rate is accordingly less. The power dependence of the baseline reactor y recirculation oxygen concentration was also predictable, i.e. 182 ppb at 90% power, 196 ppb at 100% power, although both values' are somewhat lower than those measured at other BWR's.
I t
l 3-6
j4
. 3 4 .
i 2 ._
C - -
t b Q 5 '
0 2
)
m p _
s p h
(
e a T 5 g n re _
mi 3 o i
n4 8 c \
hb n 3 6 i
t a
rP w
o -
M9 1 A ' 1 t
n% -
m1 1
0
\ e0 c0 1
2 t o n1 3
m8 1 a
Kc h 2 C
n o
7 o r 6' 2 e 3 g
t t
e 1 o
b B
o m e
4 4 \ s d r
y c H h D e \ 8 r
er
- c \ \
0 t e a w a x Na wo e h de P P
\
$ g
\
2 e%
F0 h
D1 9 w\
3
\ 4 3
E R \y 1' 1
0 0 -
U G
I F
t s
c
\s\
\
1 0
B L 0 0 8 6 0 ' 0 0 2 5 6 O 5 4 3 0 5 2 0 ' 5 4 3 2 1 2 1 1 1 go.s 5 5' ce c $ ces O 2 e%
ll llw
l A feedwater pump hydrogen distribution test was conducted at 100% a i
power. For this test, a fixed quantity of hydrogen was injected 4 individually inco each of the three feedwater pumps at separate time ,
periods. The intent of this distribution test was to determine the level of protection in both recirculation loops (as measured free the oxygen g
concentration in the jet pump sample lines) as a function of the pump into which the hydrogen was injected. Though the results of this test are (
extremely clouded by insufficient jet pump sample line conditioning, the coolant oxygen concentration as measured from the conditioned normal f recirculation sample line showed substantial differences depending on the y
pump into which hydrogen was injected. These data are discussed in Section 3.6. The jet pump results demonstrate the need for balanced injection among the three pumps, and the need for ample line conditioning for the measurement of dissolved gases.
)
At Dresden 2, hy,drogen addition caused a real, and repeatable increase Jc in reactor recirculation water conductivity and pH. Mass balance data indicated that the increase in conductivity could be ascribed to the increase in coolant pH. There is still no satisfactory explanation for this phenomena. At Peach Bottom-3, the conductivity decreased with increas-ing feedwater hydrogen addition rates (Figure 3-4). This conductivity change wag also a smooth, gradual process, and did not occur as a step y
change with hydrogen flow rate increases. An overseas licensee plant also reported the vessel conductivity decrease _with increasing feedwater hydro-gen addition, and attributed the conductivity decrease to the reduction of
- y. the soluble chge ion to insoluble , chromium oxid__e. The licensee had corrosion product data to support this argument. The concentrations of soluble copper and zinc, as measured by the liquid ion chromatograph, decreased as feedwater hydrogen increased. The on-line transition metal liquid ion chromatography results are ' included as Appendix B.
9 1
3-8
i 4, N
~
, 4
^
o -
E .
+ >
L l W o. i i
v O' e-H fIJ c.sg
.9 %
- *o
.C- 00 O 8c.
ye "
[] .,
em f 8@
O _
~~
d N m, c
u O j
{ O 1 EO o '
O u 9 5 e e en
+-
+ e o A 4 s.
O g CD e f I 1
o ,
s.
C a e' O o e. +c oy i'
o O Ro
@ e, j a.
a om Eo G
e 4, A
o O g $ [
E f o E 1 g
9 i
o
@ 4 N o O O 4 N o O O 4 N o '
N N N N "
. 9 9 9 9 9 o o o o o o o o o o o o o o (i.uo/sn) A;!^!;onpuoo o;!oeg ,
The " coolant pH did indeed decrease as more hydrogen was added to the feedwater, from a nominal baseline value of 7.35, to 7.28 at the highest hydrogen addition rate. This decrease in pH would correspond to a conduct-ivity decrease of only 0.006 pS/cm if the assumed impurities are sodium and chloride ions. The overall conductivity decrease observed during the test
]? at 100% power was 0.043 US/cm, which further supports the theory that some soluble transition metal' ions were reduced to the insoluble metal oxide form.
31 The concentration of reactor recirculation water hydrogen is shown in Figure 3-5. Entirely predictable by mass balance equations, the hydrogen concentration in the recirculation water is essentially a linear function of the feedwater hydrogen concentration, and is nearly independent of 4 J power. The maximum concentration of hydrogen observed in the recirculation !
i water was about 360 ppb. This concentration is far below the operating regime-of a pressurized. water reactor. For operation at 100% power, the
~
feedwater hydrogen concentration (1.28 ppm) required to give a recirculation loop oxygen concentration of 15 ppb will result in a recirculation hydrogen concentration of about 200 ppb.
3.3 MAIN STEAM CHEMISTRY
) -
The concentration of dissolved oxygen in condensed main steam is shown in Figure 3-6. Like the test at Dresden 2 the main steam oxygen concentration was reduced with increasing hydrogen addition. At full power, the concen-tration was reduced from 17.5 ppm (baseline condition) to 3.2 ppm with the addition of 2.45 ppm hydrogen to the feedwater. The baseline value at 100%
power was higher than its 90% counterpart. The decrease in steam oxygen concentration provides additional evidence that radiolytic oxygen suppress-U" ion has occurred l
3-10 L _ _ _ _ _ _ _ _ _ . _ . _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _____
>l!l ;
3 )
.o 4 8a 2 u
Y s
, 0
)
m o t b 2 p s 5
(
p e
T 0 a nr i 3 5 i oe ,
n4 8 w I
t i 6 a r o M9 1 1 tP n
e%
/y 1
0 c0 -
1 1
2 n0 n o1 _
- C m8 1 2 no 1 -
o e 1 g
r '
1 g -
t t
e o 3
b r o m - d B e ' y c
e 3
2 H
h r D 8 e c / 0 t r ae n a ww P
e af '34 2 do eP e
c F%
5 1 0 3
- 4 9 o.
0 E
R U
b#
1 1 0 G
I F
0 f4 1
o gE
- 0 i
O 0 0 0 0 0 0 0 O O 0 5 0 5 0 5 0 S 4 3 3 2 2 1 1 nod.0 o; . l OO ! o 11 85e* '
ll' ,
a
_o 4 2
N N
(
t 3 M 0
2
)
m p
s (
p o o e n r T
i S 3 o e E
i w n4 k
t 8 6 a rPo i
, ~
- M9 1 5_ N s 1 t
n%
4 e0 O
k 1
0 c0 1
2 N u n1 o
1
- )o C m8 1 c
kA 2 n e
o 2 1
o r " 1 g 3 t e o t b 4 r o m 4 m d
y B e H c
e r h
c D
h 8 0
er t e a w O
a w o P
e b de P e%
F0 6
3 E
R 2
(
K b
I 4
0 9
O O_ _
Nx U l G 3 I
F .
1 Q
N e'
\
h 0 _
" " O _
0g 6 43 2 1 O _
09 87s5 4 32 1 21 1 1 i1 1 1 1 nEiv c2 c $ cbNo he M -
The concentration of dissolved hydrogen in condensed main steam is shown in Figure 3-7. For.both tests at 90 and 100% power, the hydrogen concentration reached a minimum value at about 0.4 ppm feedwater hydrogen, and then increased somewhat linearly with further hydrogen addition. The shapes of these curves were also predicted by previous mass balances. At y the highest hydrogen addition rate, the concentration of hydrogen.in the main steam increased to only 30% above the concentration with no hydrogen addition. At the 100% power operating point, to achieve 15 ppb dissolved oxygen-in the re:irculation water, the concentration of steam hydrogen will be only 5% greater than that for operation with no hydrogen addition. This i
reduces concerns about generalized steam leaks, and attendant flammability thresholds within steam driven systems, particularly the offgas treatment i system. l D
i I
3 3
3-13
j ) ' !
d 4 _
5a 2 s
e s' )
u r
0 m t 1 2 p s p
(
T e 5# o ' -' nr i S " i oe _
n4 t ao w .
i M9 8
1 "
M b 5
6 1
r tP n
5 e%
1 0
4 c0 .
1 1
2 F n0
- - C o1 J
m8 1
- - 2 no e 4 o r '
1 g 1
t t
e o 3 .
b -* r _
o m
- d _
B e H y _
c e r h
c D M 8 0
e t r ae n a ww e 3 4
do eP P e F%
0 4 9 D 7
3 O
E ' O R
U A G '
I F
0 A
- l i, I 0
4 2 0 8 4 2 0 8 6 4 2 0 0 0 0 0 0 2 2 2 1 1 1 1
^EnO o eEoU Cept?I Eo[
l
)
4.- ELECTROCHEMICAL. POTENTIAL MEASUREMENTS l
i
4.1 INTRODUCTION
g In recent years, stress corrosion cracking tests using the constant j extension rate technique (CERT) in conjunction with electrochemical poten- l t
tial (ECP) measurements have been performed in operating BWRs. These 1 studies have demonstrated that reducing the dissolved oxygen and conduct-ivity levels sufficiently will eliminate intergranular stress corrosion 9 j cracking (IGSCC) in sensitized austenitic stainless steel and other BWR structural materials. The electrochemical potentials of stainless steel and platinum electrodes in water from the recirculation system decrease substantially when the dissolved oxygen is reduced by hydrogen injection 7
into the feedwater. Extensive stress corrosion and electrochemical testing at Dresden-2(I' ) demonstrate that IGSCC is eliminated in HWC conditions when the electrochemical potential of stainless steel decreases below some threshold value defined as the protection potential. ,
I Electrochemistry measurements were performed in a small pressure l vessel (1 liter autoclave) supplied with high temperature, high pressure reactor recirculation water. The purpose of these measurements was to 7
verify the mitigation of IGSCC by HWC. The measurements were performed during the three nights of hydrogen injection and during four days of normal baseline operation. A substantial decrease in the electrochemical potential of T-304 stainless steel and platinum was observed during hydrogen injection periods.
From ECP and CERT results of previous in-reactor and laboratory studies, the threshold potential below which no IGSCC will occur is -0.230 p
V(SHE). This potential fe defined as the protection potential for IGSCC for austenitic stainless steel. At the HWC recirculation water conditions of 15 ppb dissolved Oy , <0.2 US/cm conductivity, the 304SS potential in 4-1
Peach' Bottom-3 was below the protection potential by 0.095-0.12 volts.
Therefore, at these conditions, no IGSCC of sensitized austenitic stainless steel could occur.
l:
As the techniques of ECp measurement in high temperature /high pressure environments have evolved, the configuration of the reference electrode p'
used by GE and other organizations has varied. In order to compare'ECP
'results from different studies, the corrosion potentials can be re-evaluated using platinum as the reference electrode. In HWC, platinum can serve as a hydrogen reference electrode and its potential can be calculated with the j Nernst equation
- as long_as the dissolved hydrogen and the high temperature pH are'known. Once the potential of the platinum reference electrode is known, it can also 'be- used to standardize the high temperature Ag/AgC1 l electrode. Using this method of standardization, a voltage bias was found in the original Dresden-2 data. The bias was the result of a specific However, electrode construction detail which has since been corrected.
when the original data were re-analyzed versus the platinum / hydrogen electrode, the protection potential was found to be -0.230 V(SHE), rather i
than the reported -0.325 V(SHE). i The average electrochemical potential of stainless steel during CERTs II' ) , as calculated with the hydrogen conducted at Dresden-2 in 1982-84 reference electrode is shown in Figure 4-1. IGSCC testing at Ringhals-1 "
In both cases, the yielded similar results, as shown in Figure 4-2.
protection potential below which no IGSCC occurred was -0.230 V(SHE),
v including one CERT at Dresden-2 where pre-existing IGSCC cracks did not propagate in HWC. In environments that result in corrosion potentials above the protection potential, IGSCC of increasing severity was observed with increasing potentials.
RT (E=E,- _
nF in H))
H 2,,
i 4-2
FIGURE 4-1 ECPs FROM D-2 & LAB CERTs< ')
304SS ECP vs MGSCC p-90 - '
PROTECTION .
a ,
80 - POTENTIAL 195/<.10 D -
70 - o' 270/.29 60 - NOIGSCC /
8 /
/ ,
8 50. -
/ a R '
40 - j 65/.60 XEY D Welded 30 - 40/.37
/ D Dresden 2 20 - <20/<.20 21/.30 m VNC Lab 7
6 Te Ms Welded o , =
[ , ,
ppb 02[ S/cm
- 0.4 - 0.2 0 0.2 ECP - V(SHE) 2 i
4-3 l
1
- n .
o 96 44
) i 33 22 55 E t t 55 H aP S l .
00 00
( u - - - -
V c -
l'
- a l'
C" S 86 64 7' 9 44 a tS 44 33 - -
s4 -
i t n0 00 00 - -
n r3 - - - -
e e -
t N o 1 9 77 P 04 e 55 09 1 0 l d t 55 54 00 a oP 00 00
} c r 00
- i t - - - - - -
( . m c Y e e R h l T c E S o 1 r lS
- 94 44 49 CS 76 22 44 M t 33 00 E c g4 44 H e A0 00 C l /3 00 00 E g - - - - - -
, R A E
T A
W . . -
C 81 80 58 D
- H 23 23 33 N 5 p A
2 - 77 77 77 4
_._ S 4 L
A I .
T )
N y b E t
(
T i O e v)
P 74 00 1 3 t i m 67 77 1 0 o L t c 22 n c/ 1 1 1 1 A . . t C uS .
o I
d U o M r n( f E e o H t C y C a b O W R d T n e C o t E i d o L t en n E ave-l l g) 02 30 21 s uoob 99 1 1 a 1 csrp 61 rsd p 33 1 1
- t 4 ii y( p cDH e .
E e . c 4 L R x -
B e 4 A
T % . e d 0% r e 00 u vn) l eb 1 1 1 9 g ogp . . 5%i F syp 35 56 68 ex( 1 1 97 rr i O 1 1 een D
wwi oo ppd e
t t t nnt rd een aao lll tal ve) 30 1 1 PPP ga 56 66 )
woop 41 22 b
. (
d sr p )))
esd( 22 1 1 00 ab c eiy ( ( (
FDH
.1 i
, FIGURE 4-2 j
1 F ECPs FROM RINGHALS 1 CERTs o )
304SS ECP vs AWRAGE do/dt E-6 D PROTECTION POTENTIAL o
R 23/.15 __
/*13 g D
'No IGSC3 10/.13 ' 4/,18 3 1 p ,
gE6 - - / 927,2 y g
a 10/.10 e / !
y< o/
4/.13 l XEY 3 ppb 02 / uS/cm
- ./.12 ,
.E-7 * *
-0.4 ~ f,;
_ 0.2 ECP - V(SHE)
?-
4-5
'4.2 EXPERIMENTAL-The~ECP test vessel installed at Peach Bottom-3 consisted of a 1 liter f I
316SS pressure vessel piped to receive water from the same line as that supplying the recirculation water sample station located at the 165-ft G reactor building elevation. The pressure vessel contained cover ,
penetrations for the ECP ' electrodes and a thermowell for accurate temperature monitoring. The facility included a flow Venturi with a differential pressure transmitter installed in the system outlet piping.
?
The basic ECP data acquisition package consisted of two Ag/AgC1/0.01M KC1 reference electrodes, and metal sensor electrodes of 304SS and Pt as shown in Figure 4-3. The high temperature Ag/AgC1 electrode was slightly
[] different in design than that used.at Dresden-2. The 304SS working elec-trode was unfilmed at installation, but was allowed to' grow an oxide film at reactor water conditions for over,5 days prior to ECP measurements at 100% power.
In order to increase understanding of electrode performance, the following electrodes were also installed in the test vessel:
3' -(1) Ag/AgC1 reference electrode of the same design as used at Dresden-2 and in previous laboratory studies; (2) a 304SS electrode with a very thick oxide film produced by long exposure to high temperature air saturated water (8 ppm 02 ); and (3) an electrode of unfilmed A533-Grade B pressure vessel steel.
hS .
f l
4-6
. _ _ _ _ _ _ _ _ _ ~
/ t- >
j 'y i
FIGURE 4-3 \
REFERENCE AND METAL ELECTRODES r
9 swmiNK TF E 80""" -
TusiNG **" O .
D C A1 W kcl M,
f s s___ 1 -- 1 f
\ .
Q
) EdC PLula As w b (wo) TFE COATED FUSED @ STAINLES$ STEf L MOD stLVERSILVER CHLORIDE / , gLgg,gg ELECTRODE AS8EMBLY '
gggyLAyon b
l WR ? ?. //,
.m , / M
\'% ~
PACKING Lowgm fTA:udSS ETs1L.
TPESEAL TusiNG UPPER CON Ax FITTING a-TFE SEAL i
i ME.T AL. TIPP(0 ELECTADDE i I
l t
Pb '
4-7
m 7
- O ,
(1 of
}" $ klx .
.g 1 V
Tp- - >S
.w f'
. M t,. each H 2 injection level, potentials between each metal electrode bi and the Ag/AgC1 electrode were measured and recorded. The ECP instruments-
- Q* d. t WC[ , tion'inAluded a'prerechIifier mounted near the pressure vessel, an automatic
' / ,,
switching' circuit,'a strip chart recorder, and a digital voltmeter.. All measured potentials were converted to potentials on the standard hydrogen scale '(SHE) using the Ag/AgC1 reference electrode. (,
3 4
=
At very high hydrogen concentrations, the potential of the platinum
.y "
electrode can be calculste,d from the Nernst equation -
a t' 3 h '
s (H 2 RT
~ 1" s
F.H2
"' l oC nF HT o ('
The par;ial pressure of hydrogen is estimated from the dissolved hydrogen g '
concentration using the solubility relationship at $20'F (Pg = (H2 )/6440, ,
d g
where (H2 ) is expressed in ppb). With the high temperature pH taken as neutral- (i.e., pH-5.65 at 520'F), the pot.tntdal of the platinum electrode 5-
-n is j
a
.')
E H
= 1.985x10" (T'K)(5.65+11og PH) 4 '
2 2
\
'g, Once the platinum potential, with respect to SHE, has been calculated, the 3 corrosion potential of the stainless steel can be determined from the l potential difference between platinum and stainless steel.
The 25'C cond.uctivity and pH, and the dissolved oxygen and dissolved g
hydrogen inforuction for the reactor recirculation water associated with each ECP measurement were obtained from the recirculation water sample station data.
) 4.3 RESULTS ECP measurements were made during all phases of the H2 injection test at both peer levels. Electrochemical potentials of lightly filmed 304SS l
l 4-8 1:
l
l j
and platinum measured during the final night of Ha injection are shown in !
Table 4-1. At the NWC conditions of 15 ppb Os in the recirculation water l at 100% power, the potential of the stainless steel was 0.095-0.120V below the protection potential, which indicates complete protection from IGSCC. l At extremely high He injection rates giving 3-5 ppb 02 in the recirculation j
I water, the potential dropped an additional 0.1-0.2 volts. The lower the D
potential, the greater the margin against IGSCC. f i
E.:seline ECP measurements in recirculation water with 4200 ppb diss-j olved oxygen produced potentials 40.200 volts above che protection
) l potential. Potentials above the protection potential indicate an environ- i ment that can facilitate ICSCC. All 304SS potentials were more negative at f
90% power than at 100% power for a given recirculation water oxygen concen- :
) tration. !
i On the second and third nights of H2 injecti n, at recirculate n water i dissolved hydrogen levels above 190 ppb, the calculated potentials using l
the platinum / hydrogen reference were in very good agreement with those Thus, a high measured by the new GE design Ag/AgC1 reference electrode.
temperature ECP calibration was achieved.
) 4.4 DISCUSSION Figure 4-4 shows the lightly filmed 304SS potentials of Table 4-1, Also included is the average plotted as a function of dissolved oxygen.
dissolved Os and ECP value of each Dresden-2 CERT'and the data envelope
?
first developed from laboratory tests.(5,0 The Peach Bottom-3 measure-ments at baseline conditions (4200 ppb 20 ) are essentially equivalent to the measurements at Dresden-2. How4ver, at the 15 ppb 02 level the Peach Bottom-3 potentials are nearly 0.100 volts lower than the Dresden-2 values.
} Peach Factors that might contribute to the lower measured potentials at Bottom-3 include different water chemistries, the extremely low recircu-lation water conductivities, and/or the oxide film thickness effects.
4-9
7- ~. 77; ' '
n
}l: QR,XfyW ;=r. 1
-).
.:( , , T c ' ' * [;l
- . e ,
I-
.c y. >
4 ..
- iF -
,j[ ,
]
Q
.l ]:tfi4. ? ;% %l y ' i [, V ,
+ 1 e.,!,' ,
TIGURE 4-41
~ .,' .>1
/
', _ o m.' q _
.? f
~
.' h ' E 1 y ; / ,] ' 1
~ c 4!'. ,. ,.
'; ) :(
.;t , c , .
[
'I % 1 s
,/ ,
E,
'( 1 ) p/ -
.l l\. , y ?
v
.I
- _ 4
- o'^
h' >
t . EC PsA AT '2 tG P'ER ATiN - a 1 G BW R s-(*) ,
(;
c
~
O,2 s+9 '
7 LOG O2 vs 304$$ ECP i ,
\
8, < s &>
- . r
' ; ., 's i j
d, ., s t j' .x l( i, .,
s'
~; ':. '
s a O.% - y g;, o.
, D' .
y )
.v
/ />
- l r O'
, 6, , +
T
, i a.:,i ! j li
'O n' g :. , '
. < ' g- - o,1 - ,-
w ,s ',), i ;
- 0.2 - f PROThCTION I ,
. ' a. POTENTIAL +3,+ r
. y _ o,3 - (- t Em NO10500 7
,. .y .
\? - 0. 4 ~ ' > s L ; i ggy 1,
y-e D- / , , , e/
a . o '
d c- ')
1 ,
i.h0.5- Pooch .' Bot'o, m 3
+ Dresdsn 2 (82-84)
- t
- 0.6 , , ~,
0 10 100 / 1000-
. m
- t DISSOLVED OXYOEN - PT?B , ,
.('~
f n (a) Date Envelope from laboratory Measurement s Ref. (5),(6) s
'L
' l, ,
I
- i
-}.
I
- .I
! l:
'i
) 4 -l f) q- e' 71
'1 4 /,
? .) .'t :
't .\
t- 'l
7~
% .e lJ9: s Specifying a particular corrosion potential for a given dissolved
- y 4
< crygen' concentration is difficult because of the effects of~ oxide film formation. In early tests at Dresden-2 , it was found that when an initially unfilm 304SS electrode was exposed'to high temperature water, the corrosion potential increased with time. This potential increase is g Thought to continue until passivation occurs and film growth is slowed. At Dresden 2, the potential measured from an "unfilmed" 304SS electrode
- int.reased to within 0-,030 volts of a filmed 304SS electrode within 3 days.
At Peach Bottom-3, measurements =r 100% power on the third night were made
[\ after the 304SS electrode had been in the reactor water for over 5 days.
g 't This, coupled with the nearly equivalent potentials observed at both plants in baseline water chemistry, indicate that the initially unfilmed electrode had sufficient oxide growth for proper potential measurements. Although' the final potentials on the 304SS electrode indicate that adequate pro-3 tectiot.sgninst IGSCC was achieved in HWC, it is possible that with time and furEher film growth, the margin against IGSCC would still exist, but would be less.
p
4.5 REFERENCES
- 1. M. E. Indig J. E. Weber, Corrosion, Vol. 41, No. 1, p. 19 (1985).
2i Unpublished data to be presented at the Second International Symposium on Environmental Degradation of Mater.als t in Nuclear Power Systems - Water Reactors, Monterey, California, September 1985.
3.. L. Ljungberg, " SCC Testing in BWR Environment," EPRI Project RP1930-4, Progress Report, May 1984.
7 .
- 4. R. S. Greeley, W. T. Smith, R. W. Stoughton, M. H. Lietzke, J.
Phys. Chem., Vol. 64, p. 652 (1960).
t
\. 5. .M. E. Indig, R. L. Cowan, " Electrochemical Measurements in Eoiling Water Reactors; Relationship to Water Chemistry and
][ Stress Corrosion," 2nd Int. Conf. Water Chem. of Nuclear Reactors, British Nuclear Energy Soc., Paper 15, Bournemouth,
'j; England, 1980.
- 6. M. E. Indig. A. R. mci 1ree, Corrosion, Vol. 35, No. 7, p. 288 (1979).
'r.
4-11 a
- 5. RADIATION SURVEYS The primary source of radioactivity in the steam from a BWR is 7.6 sec j I
N-16 from the 0-16 ' (n,p) reaction. The N-16 is formed in the liquid phase f;
g within the reactor we and then partitioned between the reactor water and steam during the phase separation. With standard BWR water chemistry, the I
bulk of the N-16 formed is quickly converted to relatively non-volatile
~
~
I anionic species, primarily N0n or N0s . Only a small amount of the N-16 j goes into the steam. As the oxidizing potential of the coolant is reduced by hydrogen, the proportion of the N-16 converted to more volatile species, such as NH,, Ng, or NO2 , markedly increases and the fraction released to.-
the steam rises commensurately. One of the objectives of the mini test was to evaluate this partitioning effect and the resulting dose rate changes in 3
the plant and in the surrounding environs. These data should help to answer questions on changes in local and overall ALARA, shielding.
requirements, and boundary dose rates.
5.1 RESULTS The radiation measurements were made in four different distinct y location sets and with three different instrument types. The location sets were determined on the basis of geography and expected radiation level.
The procedures used for the measurements were documented in SP-755, Hydrogen Water Chemistry Test Plan, Peach Bottom-3, Philadelphia Electric
& Coupany, Section'7 and Appendix C.
The four location sets were:
- 1. Steam Line Monitors a, b, c, d B .ne X-area 3-
- 2. Interior to the plant, admini;tration and vendor buildings (including roofs)
- 3. Exterior to plant within the protected area
- 4. Exterior to the plant outside the protected area.
5-1
)
5.1.1 Steam Line Monitors The normal steam line monitors are located in the X-area and have a continuous readout in the control room. The' dose rates measured by these )
ion chambers were recorded at each of the hold points in the test sequence.
The data collected are shown in Table 5.1.1, along with the reference
)
q
- p sequence number'and feedwater hydrogen concentration. f 5.1.2 Interior Measurements The plant measurements were taken in normally occupied areas, potential maintenance areas, and in areas needeo to estimate the source term of the turbine end surrounding area for environmental dose calculations. The dose rates were measured with two types of instruments, a'C.P. (air ion chamber) 9 and G.M. tube type.
Both contact and field readings were made. The procedure used was HP0/C01, " Radiation Dose Aate Survey Techniques," Philadelphia Electric 0'opany. A list of the survey points is shown in Table 5.1.2.1. The actual locations are shown on the layout drawings (Figure 5.1.2.1, A-H).
The same' instruments were used throughout the measurement sequence for the g same locations. Table 5.1.2.2 shows the dose rate measured by the PECO personnel under the direction of Fred Crosse. The single dose rate measurement point on the administration building roof was expanded to measure any local hot spots due to non-uniform skyshine. The vendor y building survey point was expanded to two, one on each end to show the gradient through the building, and to allow area specific dose rates to be calculated for the building.
4 5.1.3 Plant Exterior Within Protected Area The plant exterior dose rate measurements were made using a Reuter-Stokes High Pressure Ion Chamber (HPIC). It was calibrated by a well characterized Co-60 source and was checked for reproduction of the original 54 3
_____________.__.______w
4 TABLE.5.1.1 AVERAGE MAIN STEAM LINE MONITORS AND RATIOS TO ZERO HYDROGEN ADDITION
$3 ' Feedwater 90% Power 100% Power Hydrogen _ Average- Average Sequence No. (ppm) MSLM Ratio MSLM Ratio Base .00 999.25 1.00 1A .20 975.25 0.98 C) 1B .35 1015.00 1.02
'1C .52 1067.5 1.07 2A .70 1937.5 1.94 Base .00 1033.333 1.03 I 2B .94 2562.5 2.56 2C 1.22 2925 2.93 3A 1.40 3150 3.15 3B 1.64 3375 3.38 30- .1.78 3500 3.50 Base .00 1115 1.00 4C 1.68 3725 3.34 SC 2.16 4125 3.70 6A 1.26 3125 2.80 (3 7A 1.04- 2327.5 2.09 O
c.
1 5-3 I
i
. _ _ _ - _ _ _________ - _ A
s 8
we g G ,Q g o o - I f, @
- 8 a.. J "- ~
s ;I
.. v - ... i .. . ., ,. .
m u :- .
- 2
- , Y I L *Ia m
WI f I
l ,
.g
-. p. l ,
t l- n aty :
3 -. .j . .; ;f r * ! ,
f --
' I' . jf, ,,
jf. , 'i .;' N(.,-
,s' g
% , s r r.W v. g
- . I 6 '
', i '.. !
[,' f 3 dr _
5
h } , f-'
d: i._l d,, [ 1 F
i i
I i e
. k g
u u5 < -
,u ,
3 @' i *.. . w Q- ' ;.ib. i.,
. ,j. Q l ,j
- -g...w .- % j ..
,3
,v . L .) p!
e p:,! s
.. -s o c
- *, v' .s. :
' 's
' ')
f' 'y'N lli . g , j,! ,9 F , .Oa O -
I,j,l 'r A ,
r , dy.f.,,/ r i ,
g o ,',-
e bq.%
$. J; ;' l 1
O E 1 I\
' 4 Hit ,1 n.
i i . t'o' s.
d .~.. -.>D
- - 6 a
I *
- i. .f. *
~
- .a t.mam wm n'
g 'i : , ., 1 3" J T J.L I "!s 3 E . ~
e ,! r. :
~ .l '-
jk-~ -
J{\\ lj ' ' .,, i' *g' .l .' t~
e$l7(.5- -"Q'l"<Ter
' #IC ae3 ,
t- ,
a '
ly(
i 'n--
f
-[ g
,?,5 b..;
[W ' I
,3 >&.n l $
J .
C Dm c .u c' ,
I di b
Jr
' .g*. -
i JwdS )'i =l <>
(
-. - flc, l . n,
$L.'l2if.WM=gg,,, ,ygyjsl f l < i i
. .'. s. ...I f
. , y }&
f p,- l% t.
Me w
3 ,
y. it ( "'
i n
.n. g .
< .-i z ew I
+- e .::
f:i.".f . A a .
e e 8
"3
['g ,/ .:!.IDI s'!-l lv' i qh._- - 1 4
w-ln J 3 '
4 g
_j g-, ;g " .
- s' .j. .
~ T .. j_ ,,u f S gg
"{
/ k m g~. l l6_ Qg
. . LYJ]_i,;' , 7# ..y. g2'8 v . . ... 1 , , , -]
i_ q.- [, , 5
,>[ > ', p g , + , h,:,,, ,
J )'(
,g_, - - -
- 7 .- . . . . . . . . . g. .- - . --- - .
^
- l ('.!
9 : !.
!?)
.l q
5-4
Fe +, h !l e o E p 4! o n
,; - .. .. ; .; . . . M,- ... ..
o .m .
~
9 - ,
- qy-- ,c._
~ n r -. . g. ...As y[~~ Q , y. ,.
1y .
q4
'w; a- Pr"._ . d
.7--Tf;
, - g- v., ,ea S .. .r,. .
a u 47 ..
i I,
- _ _ . . _x IL : -1;.j !i.: .h.yth_.vp
% med_.y 4
h i
V e- v ._ * '
mg g g ; ll j ..
l Si j l
hkRADhYND ki
~
IF 2,5 p /.! J@ I
h#jfj ifh'f i8
.l g glifi.,,
"H i f 5 wd l
.i .U :v _.
(c.3 @~
..c. . . . . _ . . ~_ % .),,_e ,
B gw O
./
= .. , .-
0 }:
- il l ,
- . '
ll . - . z
,F .
l$.
i =
-4,n-;l It z '
")
j .ji:.j \
rg ; E e -Q] .'
<- f. - . . .,j.g.
l E*-
g$
' Q.p-4
. .i j\ r
\ ,
" 1 . ;
's. l ,
y .. __ __
i' I - g[ .
_a-r.= n -x W.. J ~*
~:' e riad """"
a l- ;
}- +f l. w:a I - - .
m.
r-f J ;
s s
\
it.. WIE ==a * --
I- -
6
! $ 3 t i, l i
,I
- \ M -
.@, ' l ---
!.L c:
g l j -
~
't e f j{ .
e --
0 -B -i itw Y4 -
WS
)
-F " ,W y 3.,,
~ ' ~ ~
d,
" .'p< ![] : - '
g .-
p )-- - 7._.2 e -
t.
N.. r. " 2
. ..g. e. .r. 3 , t se gE:* .._. - .
t g .
- e. g I flN'J .a**= : '
O ,,
. ,, ., , , , g gy - --- -
W l- I- :u ;;;;;_, -
r^
- ~~
--+-*- Jb. .
M N "
3-. j; 3_~~[-l-p :.; - k; &
) . . - ,
3 k
g .nf 3f ' '
p 1 m N p.:
/
. m ./ _g;,_,
1 1
.a I s.,/ 3ll l 3 .
- e. ...
g .: *, a, o
g
.(, ..
i ar:3.. -. .
( i '--p-Py* .
-i 3 .__ ., s
,l(* I - - --H4+= +=.
].h e -.
t
. , , ri it pgAj L g =
g
, alil< : l
' - - ll 81.. ? , .f .
f; @ ,j
- ~ ~y+"'h$6 '; I : : 6 E..: d, .. _.:d;'hl ='r.* i!, i
, .. s
[.I
'~
i . .
} . , ,
- m. .
m.. . , . .
t 8' -
' - .; j! . . . i ; .
-[mj *O sa gj
. ' =". tr;,
,..3 ln q., ,
p j ! v i ,[
' I '
=
i .4 _ i
,o,
. g ., !
na, ux e v X- . .
-,.. 7hntwf
. <../
@ i.
SP :
{
1 l
1 5-5 l
1 j
f G
?' sn . @
q p
%j O e
I - 4 . gryJEe-'m . ..upl m
or,a, nm Mw. .. n M 1 L.. . .-
g' g
8t., i a* ',' C ij Wn . - .) v (
o g,i!t 4lh"i
" @)
C f'.
N .q
's,* F. ;.
L ff p r; 1 -
- "%, . i 4.F- L f. . U"}
f Ni F h.if *'$~ ' ' , h9 E ! q fg h.k.k1),b ,, '
f; h b 3-{
[. :
\ c' Nh 'd.--- : --@
s .s , ,
te ..u. 4 5
lg5, 6 # i 'l "I . ... 0 \
s l_.)
i , i o . o. ,a *i j l ,t t:- i f s s .
ilI' 3
-- 8 3 1: g i e **!,
% if l
- E U si . '"~f(J)gi.g 8 -----8t 3
')-- j 1
t j
i 3 ,, , , ,
t ,-
- i' . . .[q * !
- q- ++ - . ;. ..
3 i
t,' . ".?
- w,,
!, IIS ,t m e- l *
-j 1 w
? 3 l .
e g , . .
{~.-
l {, l s -
. . g,. 6 l '
L '
h E r p.m. v.j
- at I . . .
I P* hOh1I I I
)_ .
'm [j 0: . ,
i th 8
['- *
]
i 'I '
- , .-j I U~ "'-
h F a,nkyly(!
3 h'
5, ~.
p "~ l y i - q m *-- 4 .--". m ..
sj M il [ E[p.4(.. i
~,3 "" "
lil L' 3
. o
,irg g n
lp:-
J Y.,.;( .
) a u.i ,
mps.
.- n -.
e m
6 -.
ml .- -
'ir ~ A- s L h N-\*
f l;.P*---
g
.- lj 1
h *r E'-.:X!g . )7,,. , --' h f' ru,, O r- x.~ %.. %_,_ .
Il 7 6
e o>
' ~'
- -a1 !b F 1,! .\ 1
.?%.. a .
, , . .. E- -- ri. -mi c , , N g ,
! ); :
.j(_ I,p. . 8] _, ' , -u I 's _ _ , , *g, /
~M g i I *-i .
e k- .I a:: A
~ e ,<-
4.1,d-.- .
x fg. t. ...-g. - .S. .
,; .a,- .I g o sc
(.j;.g , -'f .'_,,a,
--. P:j: -c ti -
l (( , F-~ .* N .., L i Sw r
4 g ,
J pN&. . 6=':1
,Q , t'.'gr j
r' :
r
-1.
f- fl'.N h.
wz
- is 3
6
- H i - - - -
-4 1 P. i ly}-! -
ah -
M h
I.Q[T.' 7'
- '~ '
k,i[ ', '. 3 ,
-- L J
)
g_._ _.* ,.. y. 3 I l' I
.it'/ 8 Y, - b ex- E. .j,[M., g g,),jla.1N --Hr _,.h_--m I r lis0-- M, ;@I .
. . ,=n. ,_,~h;,;
6-
'I 7 r"t -- ~
~,
6
- . [. ilii!.hM. g SI. 1 I r', r . A Q)~.4,, N L 3 ,
g[I(-r ,3 y-s*_
ma
[p_b k I !!
e a .
3 3
i jh.,D up -
N ] ~~~"~' ; ,f e
44 m .
_ r 4..-.
' L8( ..
t.s
.. b. 1 3
1 I p!i(--M. '
7'. f
~
E 4 II :
2 li
- p. a% m h AM M.:- ', $. M. F MYnh & ',..~l,p.
y
$'ig f 11 Il '
dp 7 ] ': I dpib$f
] b__. -] k g M M [ hj; . e 5-6
e- e Ei
-:.F 6i 9 S, ,c.. J . . Ee ., - - 7 . ;.. .. _, J-t, e ..
[- ,
. . . . . t ---t g ...r n.,_.
llq --
g._
di,F:s w\
y m i
- - m -
4 N'y ' / :
- , 2.cr 22Mf! '
i
_ _ l 10 k f
^i' Cr_.] h 8 41:g '
i i
!. v aa
-L.
i g ml e
, %.p- .: ,,
y/
m_= .v a L p: 1
. . . === t o3 i.
,$ ;g-
- !i .
4a -
l, ,
[C>e.a_
c a-i ,
T i,
- f. _p llj, '
j ' ntr.
I Iq
} . .
l
{
i-[
$ .%y ; < ~
@4E_. . _ , _ . . _ _ ._ _ _ _ _ . , -
= 3 j g m i ,
t -
., . ; i e ,
i-l Ti I ~ , ,' el *7 3
- - =. h$li-e t
l ! .
4
, L 7._.L gl '_q. l .
l
- _3 d .. -
I "~dunc t E s,k -
.o
- a x- i i ,
1 ---
, ,3W 7,
[ -4 .Q I g , . -
w ,
l" n .
\8 b 8 %/ i l
') l th
!)-
i Eme! l [.L !
d4 @l .,
ex ,
l@j 60 r jfq , _ k 7, ,
- a. . . - 3 w j ,,,,
, g ?> ,,j g 6
Li # 1! T i
- [.Ji.$. ym e 1
i i [g . l irJ
-e i ... . .
4 r .._, , J._ i l g5 J ' h_'g 6f ,i ' m_ 4
=:bal. ,i. .i ,;_
i i _.i
@J g
.;l
- L .._,
w
,'3 b
it .T %- .: _ .i i a 6 8 If _ l h I k y
, , e e . l l s
i Ie
!! <* g, m m II, f
u;g' . mm_ __ _ _Oa .1
;;;;;,,, i _ , , _ _
g f ,l[ h_ h' 6 ' d
~~~7(O
'd _Lhlj _F e N, d [,
.i i
p i i li g;
)
~"
A' 4 ff22
. n l1 .h
,0 ,* i -
i 8 i 0 .i
. g . _ ,4. -
o ja i . ; i;; g-i
, i l s %.t lH I T ~
l g tl g
. , _ _ .i~' i ) i 5-7
8-5 e LSTHCES a , ... r e . u ..
- m. .=.;:eno
. .....iw . . . . .
. .. e . e . . , . . %A
..r .: . *.5
. :?.4 ::, * / ., ..A
.g .. a , .. . . y,x . , . . s,, . A
,,,, g . . . . ,,......,g
- ... -..m.. -.,g '022 .VELE GNIDLIUB ENIBRUT
' ' E .1 2 1 5 ERUGIF
-,g,,.4 . f. 3_ * " ' ' . ",.".e'. i. ' . . ' . ' . . ' ' . ' '
.
- h',! J-{ !i./'I' 'eh
,.p '* . . 3 '.E',',.;** 6, .m .' ' . ." . i.' . . it
- . .... w. n.
,w . .e e .iv-
.t
-( . . .
...........q . . . .
- ..L 1.... :. 6 I.L. .
aL 7 I h . C f
.,;0':l ;'
I
$ 0 '
l O @ l . . . _ . . l g: I
,t . __ . . - - -, .
s __....w _ .v_ x ...i u m, s
. w 1 E8 l" 3
~( (i',* hs.
G-t-\ .
/ 's. - . 4 c ,.
- 1. - -- h.s'u.
_s . ..i. -
.( m.. . '....;;.nm...%.
r )
.. n .. . w '
D. .... e
. s L, _
g
. . s , s , ;. .N . G, . ..
- d. O y. 4 g.
s T/ l ,\ . .- - 6. . . _ . e L ' ; G " AN v / %y [3 ,liiiiiq
- 71
~
'Cg .s a , ,'
lri- ',
~.,
[
- - . .3
)4 -
9
. ,\
.g
- l. . 3,
*.ne.e. .a* \,
, ,.O ,. .,1
...-...--s.........
i
....s. n ni
. I ,.,
,.a. 4
@ O -@- @ 6 6 @ l' O
1 [.. t 4
.' an ee n g i dE2 ;
i et {
> .t O
I M dU d - at ) x "c 3~ e
~e g% Yb b5 d3
@ e s, ms xa B.
c5 E M b
=
s 3' E 4 4 M ? 5-9
l . liI1i1 0 8 f o O 3 5 6 5 7 . e
- v g P e a S R P S
e*0 t N t 6 E s Q . M toE0 L - g g e-t % - c U gLto t i et 1 r E . e % s Q m ti mN w o A T . 1 E CF d
"r
" . d "Fo .
- 1. 3r
- 2. G N
3 1. 5D I g L 7 EI RU UB
. . G .
I 3 T 2 FN C m , I m C M P D M A P H W E
.i N -
~
3 ;gi
~ =
g g C g a t g I _
- i '
Q -
,g
1
- /
0 8 f o O 7 5 6 5 : 7 . eg
- v .
P e a S R P
\
H
.f 1 o o
B 2. R A
- 1. G
@ S 5I EL N
D RI UU GB I F . N I M D A N E N
) -
Y:: l 1 lflL
?: . , F.
-). . .
TABLE 5.1.2.1 It!TERIOR PLANT DO$E RATE ttEASUREtlEtti LOCATION 5 andastJan surwy Puants: Ansctor M1 dang
- 3. Cut auard PC7V Acces Door fWhr
- 2. Cartidor under Pape Twmel (Omtact ~'
- 3. Qarridor thder Pa6e Twwel (taeld)
Turbine M1 ding
- 4. Ptaiheter atr. Mrsa. (Uhdar steam knes)
S. 3k 6 4A N Ft.r. (Ccmtact) .
- 6. 3A 6 4A FW Btr. (Field)
'[ 7. 3B 6 48 N k.r. (Omtset)
- 9. 38 4 4B N Ntr, (Faeld)
- 9. 3C 4 4C N Ntr. 40mtact
- 10. ' 3C a 4C N trtt. tneid)
- 11. 9t>1sture asp. Ares (Field) 13, su>isturs Steen step Mwes (corttact)
- 13. $t.in Steam Stop Walve Plat.fass tFaeld)
- 14. Condenser Area (Fleld)
.l 1$. 'A' Omdenaar (Centact)
- u. hebtne ces meld)
- 17. Turbire Deck (raeld) *
- 18. Turtune Deck (field)
- 19. Turtene Dod (Faeld) 20, furtene Deck traeMi
- 21. Turt4ns (Qmtact) 22 Turtune (omtact)
- 23. hrbine (CentactI
- 34. Turture (Qmtact) i
- 25. hrbine (Qmtact)
- 26. Turtune (Cantact) 27 Inlet Pipe to Civ
- 20. hrtene Dock 41 Biological 8tueld (Faeldi 29 Turtune teck (V5 81o19m1 Sueld (Field) l
- 30. Pistform for Crane
- 31. art 6 FTTT Qerdanster trae.ld;
~~
- 33. Qu11er Ares (held)
M. Turtane M1 dang kof 34 Turbine M1 dant kuf .-
- 35. hrbine M1dhng Reef 36 Wrbine kiMang ket i 37 hrbine M1 dang W
- 38. hrtene M1 dang kof
},. hadde Arese
- 30. Dew Adnan. M1 ding oth Flaer 40 tw Aiban. M1 dang 4th ficar
- u. im man. M14ang 4th rieor 42 Issw Admin. M1 dang 3rd F1 cur
- 41. msw Adran. M1 dang 3rd TJoor de lhw AnnLn. M1 dang 3rd riour
~ 45. new Admin. M1 dane 4xf 44 terder M1 ding (South teh111
, Add 1tiemal Pointss 47 165 e1. hasetor 3:P erug tentar sa:rdtming stations
- 40. 165 el. Turtene Midang mArapan Injection Station _
49 157.e1. Aectabaner Ce) Sun in3 ret. fan Statter. Sd. 135 al. Arcare, sagte prvutors (A) i (B) 1 1 5-12
4 TABLE 5.1.2.1(Cont.) ADDIT *CNAL FOINTS ADDED TO ORIGINAL SET. 15A MECHANICAL VACUMN FUMP 15B "B" STEAM JET AIR EJECTOR 15C "B" STEAM PACKING EXHAUSTER 15D WALL ELEV. IC5' SOUTH OF TURBINE LUBE DIL CONDITIONER TURBINE BUILDING ELEV. 116'
"-M lEt ] + .a a I i i y n-f' g * *
+ "si __ M, ,,FbJLJ 'sl "'. -
*" 4' g .
c.
,T &' ~
l(e. Gt , 6 pp' ** 7.v/)w
~f t,
.'3 A f~ = =x > .c N :t a..n. . -v;y
-. . . nu? nn= A.
< m by
'l'". O , C ,,..
. g:::[:\
.. lll g"" s rac. H g,M p
i Es'r . _ . _ . e
.N:' ; E.A. g -,- L ,e q y gg,_g
' W-e
.rs. n
, l.~1.-m'EIt sf M I b- y- ::"
Ky a , e g; 'n ' l
* ===
M 7.
.i
- f ,jf A, i iM.
, s O .o.al d, j.lQ ! i - . . . <
W~ . :m. . -
%E__ m :i-{' *g _
== J imi .* a a .e. aus .i gE 3 ac O .l a=*=" E Es.
.., O=
n (9k: t". i.n.$;5%)
't-
'41mm-'
'g'I t i
. j
~
b L 4 Y 9 7'.'-i 9- SI L-in:n--
-["l
.- s. ..
G
.p(l j.ylf 5 1 0 n: !
.hY/p , D ,
i --a
.3 .,-
L . ,. u, . ly j l' , +: 2,_.g;.. el
, . . _:.. e,.J+,
~
s
= A~ . ]
r TURBINE BUILDING ELEV. 105'
.... ,4 g i
T] *""" g . ., 7 "") '- '*.= .- -
.,.. g. v -o - -- -
g.""' A C '" . . ~ jI~--- g**N t; = = '--- r% l! f ....
,"*.l4FEEEE*T W--h e m" s 1,/T ,
n a...~II N@i% l 'Q pd lg /' k.) I} {=== ===<= == . i ' EC - l _ l i .u EE +_=, ist 4..
;T;:;.,d .e R-:,1. +. 8r l.%..,.
,, , . .... , ... . . . . .. N .. , ,
"" *.*=
.i.
SM......e G l- L s,, . G l-A L , s - - - m.r. q p - 7s - u( T$t m 250 =io .
- mp
...sf.g a B::- , .
l
\ i i
.- ~. : .
aL b. -
.. s y
4MQ._-- t _L 0
~
, j.; NOY, _
.:y* r --
r . b}. '
.h I p g
~y 7 E!--I .
. 2 J 5-13 J
l i (
)
. y nascose a p " .usse=ss-
. a.
E MEdEEE8 E 8838-- 82 m -s e - - g
- .- ~
i y , sesszee a-- -
- i. ,
messeeg EEdEEEE CS8EESE t c - - E n
- r. r. s a m.sssgsg "% ense==e
- s. -
- s g=es s :r c888888 a-s =E8 :.
- :2 i e K.E !((F E i: = 0".:0000
. =
- gesssyg = ces~~e~ = sessass
=dK& d j E d i = l: m l
0 : E e EEdEEEE i: a 004""0*
=
i= A 28e2288
=
o i : cescess w y :
-enesgggs: -
5 x cesce== s u s ss
. a.
m
- ~~.-~~~ w. ~~.....
E S . E E , E, --s- -- as a s= - O r
=
= - - - -
- m - m se w = = g-
.w x:
88 -8 SSd**::
= 2
= ~
-AmdEEE8 s_. =
=
EE mz.E ==- s
=> : : ~~ =c-m : : =. a g, e
W E. ER< . E E E E. . i
~
EE.<!EEE .E n N : . : .
- w s : :
N. r- sess egessg sssse=t
- a e
~ .
I. s-= ~- s-- , = - sess.ss us w 4 = m. R .: w a I $. , E5!EEEg E E= E E =.!-- ! E ! *k E7.s 98=l9.c'.9 ae EA EJ e o - a n ss
--.sn .sss.- :
w : : :
= = nns~nn- :
gasgE~ nee :
- =
=cznacn
- - - w--- :
~~
w sessses
= :
E nss--n- E aseEssa E aussens
- I. - w- - :
~- -w -- : a- essssse n :
g
= =
g i $. ER=!!!ER -- - i: g 88 .!a8: E i: ; ...... c 888.99.{
* = =
= masssag ceasezs g= s-- g; sessses O' t nngc = i e ~ ~ .; - e i: ; enqns c
. Eg. :
, - n.~sses : ssssgs: : nnn.ner n sssss- : ~- s- ~ : -
sessses E .E : = w r :
- E i, E E .< f E E S E
.:.l, 9999299 .
y en : a waaxEh ! E3
- - - . -- - i. .,
00=!0000 5 5.s. - 9999992 ... .
- : :I W n.. e n. n n. e .. ..
SEss3EN E&EEEEE - W- W W = W W W W 235CCCC 3 C. 3 : n a ===ecce E w me lll 3 a se
.======= . a .aunaxam . m E. zwznxma L_ - _ _ ___ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ -
L calibration of 20 mV/pR/h. Two instruments were used, a semi portable unit i with a digital voltmeter / continuous recorder, and a portable one with a digital LED readout and a Rustrak point recorder. The semi portable Anstrument was installed in the training library on the third floor of the new administration building and rc7ained there throughout the test. The (p; measurement points and the measurements were taken following the philosophy
'in ANS1/ANS-6.6.1-1979, " Calculation and Measurement of Direct and Scattered ' Camma Radiation from LWR Nuclear Power Plants." The . main requirements being that two lines of measurement should be established at
<g -90*~to each other and in an area unaffected by offgas stack plume. Both of these lines should extend for a reasonable distance and be unobstructed by shielding between the point and the source (i.e., Turbine). Table 5.1.3.1 lists the location of the measurements. Further maps of the site are shown () on Figure 5.1.3.1 and the precise location in terms of other site structures. The selected points were marked with International Orange spray paint in a location vnich would not wear off, and thus would allow reproducing the exact locatien. The data collected consisted of between 15-25 individual readings af ter equilibration of the electrometer. These were averaged and a etandard deviatiec of the precision calculated. Table 5.1.3.2 shows the dose rate in terms of UR/h measured at each location. Limited data sets were taken at sequence hold points which did not allow (3 for a complete set (<4 hrs). 5.1.4 Plant Exterior Outside Protected Area e The exterior measurement location methods and the measurements tech-niques of 5.1.3 were duplicated. The list of locations is shown in Table 5.1.3.1 with the precise locations shown on the map in Figure 5.1.4.1. The dose rates measured at each test sequence are tabulated in Table 5.1.4.1. A 5-15
l h l 5.2 Discussion The steam line measurements, as recorded by the steamline monitors, have been plotted in Figure 5.2.1. They follow a curve shape observed in the Dresden-2' test except for twc fundamental differences. The short ' f6 - initial period where increased hydrogen did not affect the dose rate on the
. steam lines extends to 0.5 ppm hydrogen in the feedwater, while the Dresden-2 steam lines were affected earlier (i.e., 0.3' ppm). The second observed difference was the lower ratio change between baseline (zero
. C) hydrogen addition) and the maximum feedwater addition of approximately 2.45 ppm. For the Dresden-2 test, the general ratio was between 5 to 6, with a l maximum ratio nt the generator of 9. At Peach Bottom the ratio was <3 at the HWC operating specification. O The measurement of the effect of power level on the environmental dose rate is shown in Figure 5.2.2 and has been plotted in two ways, with and without. the zero power background dose rate. In previous studies at Duane Arnold and Cooper the dose rate varied linearly between 60% and 200% power. In the present study at Peach Bottom, the equation for the change in dose rate with power is () ' Fractional Factor = [9.21+0.328(P-62)]/21.6 where P = Percent of full power f Dose Rate @ 100% Power = Dose Rate @ X% Power /FRACT FACTOR
' To convert the environmental dose rate measured at 90% power to 100%
power, the' factor should be 1/0.852 or 1.172. The interior dose rate measurements taken by PECO personnel showed the G3 same factor of 3 to 4 during sequence 3e as the steam line monitors. The turbine dose rates are shown on Figure 5.2.3 and the turbine building roof dose rates are shown on Figure 5.2.4. The turbine dose rates follow the steam line monitor data but show some scatter at the higher hydrogen 5-16
injection rates. The roof data show almost a linear increase with hydrogen injection rate. In a recent Swedish HWC test, a difference in the dose rate ratio with hydrogen was seen between the steam lines at the reactor (5X) and at the turbine (8X). Figure 5.2.5 shows the increases at various measurement points. A variability is readily seen but no definite trend g relating the X-area to turbine can be seen. The environmental dose rates outside the plant have been plotted in Figures 5.2.6, 5.2.7, and 5.2.8 for the direct lines of measurement points for the northern, northeastern and the eastern directions. These figures j. represent the net dose rate increase due to 1.78 ppm hydrogen injection in the feedwater at 90% power. The data in the northern direction yielded negative values at 2500 to 3500 ft distances. A measurement of the dose j rate at a location which should have only terrestrial and cosmic radiation was also made. The point was located at the Ball field / playground 2.6 miles north of the site and resulted in 7.1 WR/h reading. The individual measurements are shown on Figure 5.2.9. It is apparent that these data are randomly distributed around the average value. The serial' survey conducted by EGG in August 1969 over the site and surrounding environs estimated the background in the area of the site to be 6-8 UR/h, which is consistent with the measured values and consistent with the values measured at zero hydrogen injection at the outer boundary points. 3 Gamma rays passing through air are attenuated by both absorption and scattering and are also decreased by the inverse square law. The exposure - rate at a point in a homogeneous medium is represented by the equation E= E,B(px)e X 2 where E, = source term at unit distance, UR/h B = (ux) = buildup factor = 1+k(Ux) for (vx) <1
~
for N-16(v=0.00325 ;k=0.46) e = attenuation of the direct radiation xe distance from source in meters l l i l 5-17 l
);
TABLE 5.1.3.1 Exterior Radiation Survey Points 5equence i_ _ .._... Ti s e .... .. . . . Description DOSE R C InsideProtectedArea: uR/hr
.9' 1 Between Fence & Trailers-North .......
2 Between Fence & Trailers-N:rth . .. 3 Corner Of Fence Behind ECT-North . 4 Edge Rd Of Inline W/ 1,2,3-North ..._. 5 Edge of Rd Ctr Vendor Bldg . .. 6 New fuel Storage Beside ECT-NNW 7 Ctr of Trk-E of Wall Torus Water ik iO B W Edge Rd Between Torus &Cond Tks-NWW 9 W Edge Rd Ctr of Radmaste Bldg -WWS . 10 W Edge Rd w/ Switchgear Bldg-SW ...
!! Ctr Trks-N Edge of Rd- SSW ..
12 S Edge Rd-Ctr Diese! 6en Bldg SSW .. 13 Rd Intersection-Near Carptr Shop-SSE
.O -
14 W Near Fence Ctr New Ad Bldg W .. 15 W Edge Rd Between New Ad6 Turbine S!dg-E _ _ . . 16 W Edge Rd Between New Adn Turbine Bldg-E _ _ _ . . f 17 10 ft W-Exit Doors Guar'J House . 18 30 ft W-Esit Doors Guard House ._ Dutside Protected Area: A 5 Edge Parking Lot-E of 114 .; I B SE Corner Parking Lot-E of 114kA ._. . C NE Corner of Parking-N of Sandblast-NEllB . . . _ _
' D Ctr Parking -Between llD & C-NE ... ._.
E Corner of Baseball Backstop-NNNE $ F Cons.PL-East Fence Post-Naterside-NNNE 6 Cons.PL-Fence Post-Under 500kv Line-NNNE ... .. H Cons.PL-Corner Fence Post-NNNE .. I Boat Landing Ctr Parking Lot NNNE _ J Road Interse: tion Off-site-N _ K Top of Hill Parking-Outside Fente-NW . L Top Hill Under 220kr Line-W2250/,N1600 M Top Hill E of Stack-W1750/N1200 N PUB N200/W1700 SSW .. O Info Ctr S200/W1000 S . .. P River Side-SE Corner of Discharge Pool ._ O River Side- NE Corner of Discharge Pool 5-18
E H T E D I S l l I S . N 1 O , I 3 T A 1 C O .', l 5 L .' E T ,N R U l l E T
\
G I I E F R U s S A s' E ,' \ g 1 1
~ J ,
E T '
.\
A O R
'/
E S ,
/
0 ' 0 E
, C s N ,
E p F 6 I A
,' E w 7 #_
E_ 4u
-- g
- 3 s
DT O g% g 1 H P l
+
#@9
~
., ~f,~
j '
" 1 2 3
/ 1 1 1 g,
. \
i
,[ / -
/
[ / t
f
- 1 1
1
)
a i
-W 3 "O
- - .- > ~ -. .n M.. O.M -_ .e
( W 'MS NM NM *E NN I - m .N C .= .~ - _, .__ -- A$ E- , . . mm. no 4
- m n $$
v $$ a. Y S' h $$ m , h h & NO E8 M
- e- ~
$Y
- a. -
h @
. . neem-
@M
.M .
M g
- m n w
% && - e d
wh N N MW MM . pg N e
>- N N .M
- N .N h w-N eN
$Y
= ,Y $ & $O &$ *
- 9
~ n. $ R ~
M M g - -ON . N-un # 9
~~ g e Ww eh
-mR e cW nn . . . 4 INo W
= 2 *
-H N j G mm p e
- mE w ==
N =
* * =N mm SNw ee== w e m
W
~
as
- -44 *s A
m' a N. Ad dsian J4 m-J4 44 44 6 *
= E is O
44 44 Ea 44 O -W m ~ ~~ -- .~ . . -~ .~..
- w N MM e M r, W p p e .-
e h $ ew$ m $ W E = == a= ss == zE sEss == w ge es ge
- sa as sega as .
N >
- W e we me M W em
** me e Eem
-e
-e a n E-o %
m% en m r, f$ h$ d& dd A$a$ A$ N W W
- i a m C. 2 C. S. M. E. E. 3 02 M m m e - e- w. -m we 2 3 0. R. F. O.
4 w C w E ~ U C
.-%M 7
-e we I
~l .
3N. R4. *3
- mm S
g ga is is
~.
ga .~ %. di gaga as5i
- m. M. -
rJ d - - a d
~
R= == 2 22 :32 23:2 RE a ms aa aa
- ce as
- las assa as
- ~ -
g 3 w
. .- *- -=
~. 3 .. ca-~
~ m. m.
me
- e. n. m. m. w. e. =. w. w n. >
E.
- go go .. ~a ~ e e no c . R..
$Y
-m u.
Y - =. =. R--
-n.
w ~--e .R e E Y Y Y m Y w E g .
- a* ERM 34 ==* 22 CCCE E2 g.s w
A Ea4 gm Egi g ~ W a. s
~ =
as siis
- e da E = 7
- 12% 2: Ise RC .TR E88 ~: 8:
524 w-d m - =ss gm E as asas se -
. N. . g H
E ge s 2
- se 4, $as sags as OM N
- 3-m .
l . $ h e SEh w h Ias 2 t ggo *~s
~a da YJaad a dae e a
= -
E~ e g C EE=E 2 - e E =
%=*E* [E a_
m- ~-
~ E
_es
- su-e s Ee*
5 E 4 E 4 W W P - MM - -,=~ gO ~ *- -. ~. - w' b =
= A
- AEE CEE ggs . I"E E* E I
.E .Eln.dEnd
. -.- ((ai .si
... i
- w.B u-w
1
.I l,
O l l
'O 253 5 3g 3 m 3 .q . eqq qs
~
- c. ~.
n4=3
- 3
- g. 4 -
=== m- R= n _
~~
~ y. $d A d$ 5 j W
E
" *ES E CR R .; .
-gg 5 ~~ A Y J jAa A a n ~
~
O y a g .e - =~ s n~ ~ w = ~ s m~-tm
-. - .~~ - e
~~
w g :g4 J: A s :9 - 2
* * ~.
$ n g
I
=
2- =
= ~
M i: ~
~
J g : E. E: g. c c
- O
- E:
g N o w -~~ ~ cn - n N u c:
- e
- < m " * *: -- ": * . R. 2 s ..' ;t. m. ; e
~= aw a =- ~
.s
- a .. g. g. 2. n- g.2. ,.
~.-~. . _2. =.
g . . +
- u~
- m. ~
a . . g u E
". N 5 g ? E- .
= g 5 . . 1 g g u u-c g a =
a I . C EE
- n. <
A e s c - E a a s,, .= - ag a
- c. - : .
.~ .
e .: - o
= g R -
~
r n E
, . ~
= . . .
E & E u. E E. i : E - R $ eg s.a a ~ g
= -
"" mg e a: D .!ge e :s 5 a n e .- e gg I*e s Ea Aa
- 5:
. ~
w as
. .a E s a 83 - an
=
- h EJJ .
~
2 Es =e 3 3 g . R*E e =a W
= :
- 2 3 r a E EEE E E l g
.a i
l l l l l l
c_ G 9 3 1 4 3 9 6 _ 2 4 l 7 6 8 0 3 4 4 _ I. _ 2 0 1 1 3 0 1 1 _ P2 1 9 4 7 2 4 _ 54 8 9 0 _ 6 0 2 6 1 4 _ 8 0 1 9 0 1 _ O9 1 _ 5 4 _ B 0 N0 3 e _ 2 2 0 0 _ 1 S _ T _ l i 1 8 l 3 2 4 3 5 l _ 2 3 1 E _ 6 0 4 l l _ 3 0 1 5 E _ R _ U _ O S _ E8 8 2 2 55 4 3 4 A _ 8 0 1 E _ 1 9 0 1 1 _ E _ K 0 5 _ T _ 8 2 9 9 9 A _ 5 0 2 1 0 R _ 6 0 1 - E _ S _ O O _ J 6 5 1 4 55 4 D _ 6 4 9 _ B 0 A _ 7 0 0 E _ R _ A _ I 0 7 5 1 4 0 6 2 2 2 2 D _ 1 - 6 0 E _ 6 0 0 5 _ T _ C _ - E _ I 5 0 T _ D3 4 1 4 3 O _ L 83 9 R _ l 7 0 l 6 0 0 P _. l E _. H6 9 D _ 6 3 0 8 2 2 6 0 1 1 _ 71 0 6 4 0 5 _ 9 0 f 0 1 T 0 1 4 T _ U _ O 1 G _ G 2 6 1 7 7 _ 3 4 4 2 5 T i_ 1 03 1 3 1 1 6 7 0 8 8 2 2 1 4 6 : 6 2 2 7 2 2 9 f _ 4 B 0 ) 9 0 1 0 : 3 4 2
- 0 9 0 0 E. A _ 5 1 f0 1 -
& 2 5 0 01 0 I l L _ ! : 0 2 0 B P _ D 4 1 : 1 A _ I F 1 6 055 4 6 7 5 4
4 5 T Q _ 6 3 2 1 7 3 0 8 2 0 5 8 1
- 1 1
?
0 D1 8 5 5: 8 6 1 T _ 4 1 0 5 9 0 1 9 0 1 3 T 8 1 1 3 0 2 2 _ : 0 2 01 0 1 8 0 0 1 2 21 0 T* R _ 4 1 4 4 1 1 1 O _ 4 8 2 4 8 I _ 8 E1 4 4 8 4 1
/
? 6
/
R _ / 5 4 5 3 l 7 8 6 0 2 3 / 9 3 1 94 2 8 1 4 0 2 7 1 E _ 7 8 - 3 2 3 1 8 4 4 - 1 2 1
. 1 1 0 1 2 0 8 9 6 T 1 3 0 1 1 5 6 f X ._ /
2 1 1 2
/ 1 1
/1 2
1 1 5 0
/ 1 2
1 l 8 0
/ 1 1
E _ 1 1 1 I 1 2 l _ I 1 I _ D7 4 R 6 1 5 R 92 1 R R 92 E 1 E 95 E 6 8 2 R 8 1 5 _ 0 0 W 6 2 O2 0 W O 4 1 3 O W 9 4 8 E W 3 2 9 E 3 3 W 53 4 2 } 1 P 1 1 1 P 91 0 1 O 1 0 O { _ P1 1 P 4 0 2 _ 1 P2 2 1 1 1
, 9 2 4 1 6 0
_ C3 0 0 D 9 2 2 3 0 3 4 8 I _ 7 2 87 2 1 9 9 2 2 9- 80 6 0 7 0 4 - 1 3 0 N - 2 2 4 9 66 6 - 63 _ E 2 0 - 8 0 - T 0 N 9 _ S N 1 1 E1 0 - 2 0 N - O N 1 1 E 4 0 I _ R E E G 1 0 N1 S 1 S S E D _ D U O R S R Y R R D 0 D H B 2 6 D 6 9 1 D I R T _ 52 Y 0 Y H 5 8 8 U 4 0 4 G H 6 2 H 1 3 2 T l l 4 1 6 _ R E f 0 M 9 0 1 M M F 2 0 1 H 18 0 2 2 1 M F 4 0 83 5 1 _ Z F T C 1 S M1 C1 _ C C F 5 S S C _ R 6 S 2 _ E A 4 0 1 6 5 3 8 W 6 3 2 0 4 0 2 8 6 4 6 1 7 0 1 1 7 4 6 O 4 2 7 4 7 1 7 6 1 _ P 6 0 . 7 0 1 . 1 6 8 _ 1 1 . 1 . 4 0 1 . 6 0 1
. 0 0
. . 2 2 . 3 I
_ 0 C A . _ 9 1 2 0 0 2 3 0 _ EN . E . E . 4 _ N O E V C E Y 2 E E V E . E . l I G E N G E 1 12 C E Y 2 C E V E . N G 2 2 l T A o 1 T u 1 N G E EE G VE D. i 0 1 E A E A 1 N G E I E A R D. UR U R E A l0 10 E A I t n o f I D. U
- t. l 0 U R D. E S C E D Q E D t 1 Q E p / U R l U t n D. O E
S AV sti tm4 Q E D l l
. A U V I E V I a8 U E D l / miD l I B L A S S A S r1 E V A 6 E V I 7 S A IS R 3 S A S R 5 A 4 i vI A S A S R 7
?
lc
3 M' a4 3= a4 I I I w .. m W
=
t
. E w
l
- 0. .' : , e i
=>
m .-; u 2 I w-H 5
-O w w
.g .
< ==
n Y dd
.a -
m e o u o w i w - . M. c. ,n v v N o
- w
. w
- e. o c > >
- c. : 9 e oo m w -
o w -
.J D n m O- e s - r .o. .o .o n .
lh #d
- r S g $d
- !~ n
-- m E
a K. R.
;;;. M. = .
a O
** g.
no - o - r , e + - e om e .e e m i e o 2
~ 3 " :
- m. -
*=4 c:
pg g *"* y - - H em N e
>C ** M o.e w Sm W Nd W 44
- g m
= on
. C
- =
a n= m W ed E
=
f =I b
.., W nm =5 WE 99 :s b!
tu c* . .e 1 E : ? l g7 -a et, cWEwd
=3: WE
$d a ws ~ '
Wm*"4 $*52Wo* g 5 4_ =
- e
. == .$. W e c =- w m .n. cme n
g ' T_ .\> o, N y \
, n u
s ri
\ - ,
K _ , s q o r S o N ' O ~ s' %' x I o T E O A f C ,\ f O ; L T , x . , n 'j/o N E .
-N D
o A M ^ -
- N,*
E R U L
=L- *.
i M &, S '
.l
~
^
o A . E M / - - I ju E 1 T / e
- t. A . "
4 1 R .s a f i 3 E R U G E S O t c e t o m s _.
,g 1 k
~
I F D s n - L .e o t A u o d u T o. N . E M O R I V - N _ E .
w l- f A This equation-can be used in a preliminary' evaluation of the net data p (without terrestrial and cosmic).-The north, northeast,'and eastern data are plotted.in Figure 5.2.10, along with estimates of the dose rates using
.the above equation. It,was neceu ry.to adjust the E values in order to visually fit the curve ' to the measured points. The source term by
( direction is in the ratio of 3:0.9:2 for north; northeast: east. These differences show the effects of shielding rnd scattering in the l i. three directions. It was observed that the easterly direction is shielded O' by the administration building for directly transmitted gamma rays, and the north and, northee?terly direction have a direct line of sight to the turbine and should contain more of the directly transmitted gamma ray term. g Since the background dose rates measured at the ball field north of the
!O x'
'l' site are larger than the dose measured at point 1, the value measured at point I without hydrogen injection was used as the background value for the t
other measurements'. 4 With this estimated background, net values for all other points on the three main measurement lines were calculated. Using linear regression techniques and equation of the form of 1, 3 L'.
.)
'A In(dose) = A+B/in(distance) gv Q pr it is possible to get a reasonable fit to the data for each of the three directional npsurement lines. .By using these equations extrapolated to
,[r 4 the boundary distance, the yearly total due to Unit 3 with hydrogen injection at the operating specifications and 100% power can be estimated. The values were 5-6 mR/yr at 3300 ft north, 12 mR/yr at 1050 ft northeast (river edge), and 27'zR/yr 1050 ft east (river edge).
)
a
5.3 CONCLUSION
S e. With the data set of environmental and plant dose rates measured, it is possible to calculate the effects of HWC on the ALARA and boundary dose I rates at Peach Bottom-3. k Ll 3-25
' 3
-1.
. k. _ _ ______m___ _____________. _ _ _ _ _ _ _ _ _
T N A C E N A i 7 7 3 2 4 1 1 1 0 0 0 0 0 0 3 4 231 4 6 1 1 1 1 R E R S 1 O 8 R U 2 7 5 5 G 5 6 0 5 8 0 1 25 546 74 60 1 24 65 851 2 6 9 3 8 5 3 2 14 0 498 6 3 0 3 1 Y T E 1 N ll E S 57 26 12 6929 4 f 1 0 0 0- 0 0 6 6 O T M O B - - - 8 6 1 3 3 2 1 2 R N E I Z D 2 P H 7 4 S U l M 6 3 84 09 535 75 75 4 3 8 0 1 7 445 18 34 1 54 6 8 8 31 1 6 5 6 N A F 6 0 317 76 38 9 4 3 3 5 I C 1 0 8 8 5 6 3 4 3 0 M 2 5 8 6 1 0 5 4 2 H 4 2 N 71 E O S R 8 O R l E 2 0 27 29 2 45 20 5 1 2 8 724 62 2 1 8 3 3 9 6 8 8 1 1 5 3 7 4 8 1 1 4 8 2 O I 0 Y N 9 4 5 6 9 5 3 1 3 0 1 1 86 4 1 6 1 7 1 3 H O 0 N M U F O l C R E 1 9 4 72 75 96 0 9 31 30 081 48 29 6 57 6 4 4 5 0 0 5 1 i S 6 C 8 6 5 2 6 7 5 5 3 0 1 C K N 3 4 5 3 4 0 A 9 9 4 9 0 1 3 3 7 0 1 1 1 3 6 9 I 7 A T 1 1 1 2 2 3 3 1 T F 9 S C O D I B E E R S M I 23 4 6 EF 6 H1 J ) 8 7 D C 56 4 4 8 I T U D 1 1 1 1 1 O S L D L P S A T N T I l I Y L H A T o B P N l I S f N A P l i C E 0 t 3 H H 0 E R U R T T i P. l E O R s O A G l S M N N E F F 1 O 8 7 1 0 5 9 6 0 8 7 S E O C S 7 6 R 8 9 4 0 5 1 9 6 3 2 16 31 99 42 23 43 20 09 44 T D 0 a. 0 5 8 4 1 2 9 9 9 9 4 9 9 6 7 7 7 6 2 A l 1 O l R 4 3 2 6 2 1 1 1 0 0 0 0 6 5 1 1 7 0 3 f 1 1 1 R A 1 E R 7 Z E E S 1 9 7 5 6 0 9 3 0 8 41985 2 C 6 6 5 4 2 7 9 1 3 0 67267553 6 4 4 5 0 0 5 1 O- . fN 3 4 5 3 4 0 919 14 920 2 3 31 3 3 7 0 1 1 3 6 0 A - 1 1 1 1 D.. 5 1 0 2 T l N E 5 t A. _ 6 0 T 6 . N 1 I 23 4 6 E F 6 H1 J ) D 1 1 L 8 7 0 C56 4 1 A 1 1 8 L. P . R 6 Y I O E P D 5 i l E . N I L O. O B T R A E Z T R . D. I S U N R- I M T E. S T N A E X. E S E H H O T T T R R R S O O O A T N N E N 2 7 5 5 1 2 5 6 4 6 1 4 6 8
- M F T E 6 05 8 0 5 4 7 0 2 5 5 2 9 41 69 3 6
8 1 5 6 3 2 1 3 C E S 7 66 22 9 9 4 1 1 0 0- 0- 80 6 11 0 4 8 6 33 3 0 2 S N O521
. D 2 1
N T 2 A H 49 8 8 3 7 1 1 8 2 % 5 1 8 5 8 9 4 2 2 7 4 E M 5 0 3 7 8 8 7 6 2 6 8 0 53 6 9 4 9 7 8 S F 2 6 4 2 4 5 0 A E P C 7 32 8 4 5 1 1 1 9 9 6 7 6 59 4 7 12 1 4 6 4 2 1 2 0 0 9 6 1 2 C 7 N
. I 2 1 3 8 6 9 6 2 6 5 6 5 2 7 7 3 4 2 4 2
. 3 55 4 7 2 3 0 6 1
T E 5 0 1 2 5 1 9 8 9 6 81 73482590 7 7 2 4 3 6 9 3 2 4 6 5 M 2 1 1 1 1 1 1 1 1 1 2 1 1 H F O 0
. S E1 T
O C 8 9 6 57 4 52 6 7 90 9 3 01 38 0 4 9 5 6 4 4 5 0 0 5 1 1 8 2 6 7 2 6 7 5 5 3 L N 3 4 5 3 4 0 41 1 9 4 1 0 A 1 3 3 7 9 1 1 3 6 9 P T 1 2 2 3 3 1 1
. S
_ L I _ . A B N O ! 23 4 6 E F 6H I J 1 _ l 9 8 7 1 D t5 6 4 A 8 1 1 1 1 i C H T L T - E T N I R R l I _ I D O o _ N P g l .. : '. .' ! ! ! ! ! ! ! ! ! : ! 1 I ! :
! ! : ! I !
- 0
- _. 10 M ,
3 O ~ T ,!l T - O B / p 0 O T S 6 H Tr. s. C I Y
.y 'a-1a
'w O A T R / '-
U - E S I [ . P ME 0 1
,I 6
- HC 4
1 2 S R R TA B .. f-' / , l' 5 0 / E R OW ,
/
U G P N s
.~
~
i
/ ? i
/
7 I F : Z = / 0 O G NO - ' /
/ 4 ORYD /
/
MH 'g
/r
/
? ,!
I -
- N I
EM -
/
X I t~ s'
!!s b 1
/
$ 0 2
g - O I
- ,. x 7-q M
A
' u E
T 1 44 :: 0 S 2 4 8 6 4 2 3 ,- 6 , 2-3 3 3 3 g 2 a' a. 2 8 6 a 4, 2 1 A 1 1 1 1 O Wg$,*2 O C$a m!s3>7wN 9-C -
,- E '.f
/
-W
/
t O +y o% ,0 o C - P ' 8
;3 ETS
/ O T ET I
C
./ D ,
W WR ,0 I _ 6 EN I
,T M 2
A 3 2 R MO 5 T E R T ,0 U G E OB 4 c I F S H O CA D EP , T E .
,0 2
N
,y S
S - - - - -
- 0 O 5 4
0 4 5 3 0 3 5 2 0 2 0 1 5 0 R G m $ = @ 5i 8 5>4= eO C hs%Q$= H3oA H< M NyA l
O T - , T o O B T 0 S , 6 E HT o C YR A TS E M I P EH o - C S RE , 0 3 E TA 4 2 TW 5 E R A NE U G I R GO , F R D E YH 0 S I O N I , 0 2 DM 7 E N p, I B 8 R U - - - - - - - - - - - - - - 0 T 4 8 6 4 2 3 8 6 4 2 2 8 6 4 2 1 3 3 3 3 2 2 2 2 1 1 1 1
$ Z oH O g0 n gioA
B 9 H CTS 6 AET '
, 8 4
E PRTY o S I SME EHC T R O 4 2 AET , 8 5 E RAW 2 R U N G I F EEG SOR ODY DH I e N FI M , 2 1 O O e R ~ E X I U B - 0 R 4 8 3 6 3 4 3 2 3 3 8 2 6 2 4 2 2 2 2 8 1 6 1 4 2 1 U 1 1 T
$ Z OP O g S g
U T
,, M O y R
FTS o E 6 T E C
, 8 4
CW XH I o AN I 5 TM 2 S 3-I 5 M E R U D OT G T I F O O B T HC 1 A i 2
, E E P V
~ I T n A L E R o E - - - - - - -
- O S 5 5 4 5 3 5 2 5 1 O 4 3 2 1 D
n% o oH m Z %o gE<% MH$ MroA n
S i E O T 0 A 2 R O E 4 2 S O T D S E O T 2 L CW AH 2 6 T N I
)
5 E X M I 6. R U G E 3 1a I - F MM O O TT h T O RO 2.( I B 1 V HC _ N AE q E P 8 0 R - r O - I ' Q R ' 4 0 E (' \ T a ,D X E 0 0 0 0 0 0 0 0 0 , 0 5 0 5 0 5 0 5 4 3 3 2 2 1 1
$!8 ]e4a gb h*
S E o T 8 A 2 R O E 4 2 S O T D SE T o 2 L C W AH T NI
)
NIM 6 . 7 2 E3 - 1 5 E MMO R U G OTT 9 I F RO IB 2 1 VHC % NAE n EP \ 8. n 0 R \ O I 9 R l0 \ \) k 4 0 E T X E 0 0 0 0 0
- 0 0 0 0 0 9 8 7 6
- 4 3 2 1
$3o
- M O 2MNgm (5 I
S E T ~ 3 A - R E 6. 2 S O . DSET T 2 . 2 LCN AH TIN 0 ) 8 NIM 8 . 2 5 E3 1 E R U MMO-G I OT y F RT IB O 4.( 1 V'HC NAE EP % 1 _ R O I R
\g 6 0
D E ,\ T 0 1:
,\'\
X E 2 0 0 0 0 0 0 0 0 0 0 7 6 5 4 3 2 1 1 aC le *;n M o xag8$ ,$5 e s
O a , E o S
- 0 ,4 o O -
a-2 D T ~0 , S ~ o LE T -
,0 o AC O 2 TNH 0 0
NIN - o EI M -
,6 0
o M 3 0 1 O-M o k - k IO T
- 0 T -
,2 O 0 bH 1
B O bC A o E a P - e D a -
- ,8 X o -
U o - O -
- a o R - 0
,4 o
G , K - 0 C 0 4 A - - - - - - - - - - - - - - - - - - 0 B 8 98 76 5 4 3 2 77 7777 777 1 7 9 8 76 5 4 321 6 6 6 6 6 6 6 66 6 u# d$$d2 yy m oA
T = S ,8 I 2 D
~o ,
T * =, 4 A T 2 S
~
E G E T , S CN OH a =
,2 D I N
I , )d C M 0 1 n 2 E 3- i 6. s 5 V M 1u
~
E I O
, c o R h U
G T T T A I F D E ,2 L H 1 E C A v a x " R E i O P 8 D Y +,0 E x + T 6 A 6 0 D A ,4 L E Y' D % X + 0 U + + x , C _ L A 2 0 8 6 4 2 0 8 0 C 6 4 2 0 2 2 1 1 1 1 1 I hm.dB<tu r r c$Q oMB d
i
.)
l
- 6. HYDROGEN DISTRIBUTION STUDIES
!~ 1 Unequal distribution of hydrogen- in the reactor can occur unless
- rf proper ' hydrogen injection flow - controls / logic are utilized. For peach-
-Bottom, this is.due to the immediate separation of the feedwater streams after the hydrogen injection into the feedwater pumps (Figure 6-1). -There is some cross-tie piping between the two feedwater trains, but no common 5 . piping where the two streams converge and could mix prior to entering the reactor. i l
Without .a hydrogen injection flow distribution system, the gas will f () . follow the path of least-resistance. Minor pressure differences between the pump inlets will cause the majority, if not all, of the hydrogen to
-flow into the lowest pressure location. Unequal distribution can also occur if the operator wants to keep a pump in service but does not want to inject hydrogen into it or if a pump is taken out of service.
A sequence of tests were performed at peach Bottom to study hydrogen flow distribution effects. The tests were performed during test sequences (3 7a, 7b, and 7c. During this sequence, 100% of the hydrogen flow was injected individually into each of the three feedwater pumps (Table 6-1). In sequence 7a, 45.4 SCFM of hydrogen were injected into valve A, with g7 valves B and C isolated from the hydrogen supply. The measured recircu-lation water dissolved oxygen was 58.0 ppb, and the measured main steam dissolved oxygen'was 11.7 ppm. G) . In sequence 7b, 44.4 SCFM of hydrogen were injected into valve B, with valves A and C isolated from the hydrogen supply. The recirculation water dissolved oxygen decreased to 22.5 ppb and the main steam dissolved oxygen decreased to 9.5 ppm. 6-1
li l l FIGURE 6.1 Peach Bottom - 3 Feedwater System MAIN STEAM D A FAIN STEAM O. C
. .l B A G . RA N -' '
g7 v/ 3
;Q O O V _)L /L U RECIRCULATION RECIRCULATION LOOP A LOOP B REACTOR PRESSURE VESSEL O
i t-FEEDWATER PUMPS ; H H 2 2 2 i 6-2 1 1
I J f T4BLE 6-1
' DISTRIBUTION TEST RESULTS O
TEST SEQUENCE NUMBER 7a 7b '7c
;- g HYDROGEN INJECTION FLOW RATE VALVE A. SCFM 45.4 0 0
' VALVE B,-SCFM 0 44.0 0 VALVE C, SCFM O .0 45.0-O? ,
REACTOR RECIRCULATION WATER (LOOP A) 02 , ppb 58 22.5 61.6-
- MAIN STEAM 02 e ppm 11.7- 9.5 7.75 (LINE D):
L.
;l d'
6-3 l \ l
. _ _ _ - ._____________O
g l, In sequence 7c, 45 SCFM of hydrogen were injected into valve C, with-valves A and B isolated from the hydrogen supply.- The recirculation water dissolved oxygen increased to 61.6 ppb (similar to that obtained in seq-uence 7a), while the main steam dissolved oxygen decreased to 7.75 ppm.
@i With an equal ' distribution of 15 uSCFM hydrogen into each of three pumps, the measured recirculation water dissolved oxygen was about 22 ppb and the main steam dissolved oxygen was about 9 ppm. These values are similar to the results obtained in sequence 7b. This'is what would be (7 expected if the ifquid flow from pump B splits equally into trains A and B.
The specific reactor vessel configuration and internal design details s cha be used to explain the s'equences of high-normal-high recirculation (C) water dissolved oxygen concentrations and the high-normal-low main steam dissolved oxygen concentrations. A sketch of the top view of the vessel coolant nozzles at peach Bottom-3 is shown in Figure 6-2. Train A feedwater enters the vessel in quadrants I and II. Train B feedwater enters the vessel in quadrants III and IV. .The A recirculation water is drawn from quadrants I and IV and returns back to quadrants III and IV. Thus, some of the water from the C) right side of the vessel is brought over to the left side. The B recircu-lation water is drawn from quadrants II and III and returns to quadrants I and II. Now some water from the left side is brought over to the right side. Each main steam line is representative of the particular quadrant to i 1 7 which it is attached, If all of the hydrogen is introduced through one feedwater train, the majority of this excess hydrogen tends to stay on the side of the vessel it Ce enters. There is little or no radial flow mixing within the vessel due to the flow straightening configuration of the jet pump piping, fuel channels, steam separators and dryers. 6-4
-________a
i . O' REACTOR RECIRCULATION WATER SAMPLE CLEAN UP RECIRCULATION LOOP A OUT A'- ,c ,n \ / is. N
\ g / g
/ E y /s A A g
- # '~ g I
/ , s lO.liAINSTE/Ji f
' N g
s ' \
)
SAMPLE N N y / l f
/
s / \ < g itAIN / \ 1%IN ,
/ g STEAM \ gSTEAM D / g j
O i IV I l H 'E ! C ! FEED TEED ___ L a B 4 ____q 4 UATER r M - IATER B k- 1 A
\ I B l I
C
\ III i II / MAIN 1%IN- g \ / STEA
STENi g c \ f /
\ -
' \
i / - 's % /
/ \ /
Y \ /
\ '% - ,.*- C
/
\ ' ,
T
\ \ .l
/
s
./ g s / /
c ~/s y \p ' RECIRCULATION LOOP B OUT l O LEFT 180*' RIGilT 1 l FIGUPI 6.2 Top View Sketch of Reactor Pressure Vessel Nozzles 6-5
The proportion of the excess hydrogen that is transported to the other side of the vessel and the overall system effects can be explained by using sequence 7a as an example. The total core flow is 100 M1b/hr with a total external recirculation flow of 33.6 M1b/hr. Each quadrant has 25 M1b/hr of core flow with 8.4 M1b/hr of recirculation driving flow. The hydrogenated
. () - feedwater from feedwater train A mixes with the core exit liquid above the downcomer in quadrants I and II. Tvc thirds of this liquid is forced through the jet pumps into the core, significantly reducing the oxygen concentration in the right half of the vessel. Of the total 16.8 M1b/hr of o- downcomer flow on the right side of the vessel, 8.4 M1b/hr enters recircu-lation loop A and 8.4 M1b/hr enters recirculation loop B. Thus, 8.4 M1b/hr t
of this liquid from quadrant II is returned to the right side along with 8.4 M1b/hr from quadrant III, while 8.4 M1b/hr from quadrant I and 8.4 (J M1b/hr from quadrant IV are mixed in recirculation loop A and transported to the lef t side of the vessel. Thus, some oxygen suppression is accomplished on the left side of the vessel in quadrants III and IV, due to the mixing of lower oxygen and excess hydrogen water from quadrant I with the liquid from quadrant IV in recirculation loop A. Since the recirculation loops draw equally from both sides of the vessel, i.e., loop A from quadrants I and IV, and loop B from quadrants II O and III, and since the hydrogen and oxygen concentrations are always the same in quadrants I and II and in quadrants III and IV (but concentrations in quadrants I and II are not necessarily the same as those in quadrants III and IV) regardless of how the hydrogen is distributed, the concen-trations of dissolved oxygen will always be the same in both recirculation loops. If oxygen suppression were linearly proportional to excess hydrogen in lCL the recirculation loops, no differences in oxygen concentrations would have been measured in sequences 7a, 7b, or 7c. But the relationship is I 6-6
nonlinear. By shif ting ths injected hydrogen to one side of the vessel, the suppressed ~ oxygen concentration decreases from the normal 20 ppb on the injection side towards zero, while the other side increases from 20 ppb towards 200 ppb. Due to this nonlinearity the average values in both recirculation loops increase. O The main steam line oxygen measurements made on the D line from
-quadrant.IV reinforce this analysis. Without hydrogen addition the steam contains approximately 17 ppm oxygen. With all of the hydrogen entering on t) the right side of the vessel, the quadrant IV steam oxygen content is reduced to 11.7 ppm, indicating some suppression. This value decreased to the near expected 9.5 ppm with equal hydrogen distribution (for valve B injection) and decreased further to 7.75 ppu oxygen when all of the hydro-c) gen was injected on the left side of the vessel (feedwater train B).
i If this unequal distribution had not been measured during this pre-implementation phase and the injection techniques currently in use at other reactors were used at Peach Bottom, the required oxygen suppression concen-tration could have been attained, but with probably 3 to 4 times the hydrogen required for equal distribution hydrogen flow. Since there are l already significant differences between plants that have injected hydrogen, ( Peach Bottom might have been written off as having a new set of conditions. The entire cost of the mini test is roughly equivalent to operating Peach Bottom for one cycle at about two times the equal distribution hydrogen injection rate. s '. O 1 1 6-7
I .o I APPENDIX A O PEACH BOTTOM-3 HYDROGEN ADDITION MINI TEST DATA PACKAGE G P 1 A-1
l a E G R K C 3 9 12
- 1 262006760.0 0 15.2571110170007739024.00007300 000050507 O_ _
C R 22 10 9021233317.3576.250025 3333 0 7 479 291392227 1 11
. 66 . 2509921 1
P 9 00?2975455000070505 R 0 13 7 4 00 T R 3 21
- 4 042977072.35 9020211156255.330025 291392226 6.3 2 5 3 1 65 0 9 0 6.2 63333 0 67 0 1000073.470 1
2 _ O 10 1 11 . . 0 - T 1 9 000040 L-S 1 R 000090502 10 0 9 00 E Y 3 T R 21
- 2 15200565650.240900%610 9 8 2 1 15 2913911 2 0 0 0 51 3.2733.230016
. 66 . 3 5.0 0 2004591 2332 0 0 7 3.4 7 7 20 I O 10 11 . . 0 N
I M C 0 16 042972226.19 411 7 0029509730.00559300 3.5 3 3 9.5 5 0 0004.1052271 000014501 N E 2 23 12
- 4 9820266602.2 . . 330017 291391114 1 11 12332 7 0
462 2 I 9 T I 0 0 2 0 10
- 5 052905656300030442393.50000300 0 4 3442.55 4 00001 6506 0 22 12 9020222279.1 291391113 0 00 099.3400106 6 0 12222 4.1 4 2 0 9 3 2.7 467 1 )T
.)
7 0 TN 4 N E 0 00 7 n S (M E G S R 13 4 0 3 2 5 5 0 0 0 0.000.00%. 5 1733.00001300700096500 061 e I ( . 9920100000000.0 g -
- 1 5 1 51 g 1 9 2.7 460 O B 20 29139 R
O ::: 12 0 08 0 1 6 1 0811 11 0 2 yx nign Y
- l ::::::::: 1 : :::::::: 1 : : : : l :::: : o id H da R
0 1 4 124953430.9100223399412.50001 7 1372.559066.11 801 1 00002050227 05 t n ae er I I I 2 - 4 25 10 9020299906.1 29139 2 0 00 4 7 7.4 5 0. 8. 1 9 2122102.74.46091 0 2 1 c.r e rsre egew r _ - T I C 0 10 1 6 9 4 0 2 0 0 0 0. 10 5.0 0609595595.50952305 1 4166697 00001 950760 pnwo i op - M L I 24 10 1 9920277715.1055.560010 201 39 2 0 00 55 1 680882.7 3111 1 0 46971111 ba yd p eot o M drt O I 0 e d T T Y 0 15 614030004524023533340.0240230500006750035 6 . 5 3552.5566635 6111 t rde O R B D 1 23 10 3 9020244443733.670012 29139 1 0 00 1 208902.71 0 46001 234 ceen et no raoi H rcit C R R 0 1 1 093713230.69454101 6102.55 6 . 6667330600.502223100059900760 6 o cero tr E P 1 23 1 0 0 9920222261322.700013 20139 . 0 00 1 9 9 9 0 1 1 0 90
- 2. 7 46957 164 ti po ocor rop nerp -
E 7 ,rp S R 1 1 09371000000.007166771006232511105023050029 6 . 0 001 03 ; B 23 1 2 2 9920200000000.900016 20139 0 80 1 55
. . 1 2
0 1 9 0 0 9 82. 7933.461 11 239 21 11 e f ;T t oTN a HM
- : ::::::::: l 1 S RRR 0 : l ::: : l :::::: :: rnN MM RRRRH FF o 3 T HHHMMMM M CC HHHHC wi39 I T ///FFFFMFMMDB//MMDO///// GG OO ot92 N H sssCCCCPCPPPPSSPPPPRRRRS EE PP l a23 U M%MMMSSSSPSPPPPUUPPPPMMMMU DD%PP f z3 7 i 0 nl 0 (h
4 ei gb r h r.. _ yah/ea yx xt/sl t _ ) 2 ossHba eo M iade t 2.5. l l W) WWW* T0 O& OOO( ) LLL
- R" O R O" T
TT00 22 i cwd40vb 2a E L( )" FFFW( " " " " 22 TEE t e31 aa C F O " H0 ELLTT c n N W "( 222L2 . . . . R O" D LTTEE dnddt o E U mO HHHFH SSSS" " MM N NUUJJ eeeeoi f LW RRRR RR22 " OHI DD mrmmNt Q ) . . ueuu s 5 E + EFOPwP2H T LM MHFWEEEEODTTEN E H 0 R"" O"" " C O" C. P . R" 0" 40 S ( SCFUe U RR R PPPL .L2222OO O NNSSCC" RPMMMMPPMMt CCOOE"* APRA sf ss) e sess Q u 2 EE v2 T S TM EENIWI CP" E
" " TL RCFHH00CCHNI IRRRRI 1 I CCLLLLCCCCCO0 I OO0PP ) ) )
OO(D *) t - E RI P1 OT 99RE 9RBCDR2RBBEEuRRfE5S5SEE EEE O9 - P T PPMRC" " " TC0FFFFFFMMPPMMMMPPPRRLL ( ( ( ll jl!l 1 1(lll 1l 1G
H 0 K C 7 0 20 5 734600404.144.642607045 3 000001 0005 00 62 500 2033004040.2 9 4.2 2 0650 1 9.12 1 A 23 391 30 4 4 2 1 201
. 7 21 P 1 0 1 1 00 . . 8 -
R T A R 0 20 2 734604004.375.031 3 0505230320.000073777.1005641 6.6 5 6 00000 50553 02 D 7 23 10 2833050050.2 391 304 1 4 1 1 00.12001 1 0 . . 1 1 52222 8 4721 1 21 T S E T R 0 20 056007670.6 00 00 00 321 7 1 24.00007 47134 9 003.156450100000 50021 03 . I N 6 22 1
- 3 0
2934200062.2 391 301 115 1 1 1 1
. 2 020 5
1 2333 8-
. 21 I
M 0 N D S 20 056003430.5354 7 0 2 2 36600 2 941 6 70 62 060 O I I 21 1 0 3 2934266694.5 391 303330 1 12 2 2 1 5 023
. 33 1 8
7 1 33 21 T I I I 0 5061 0020053521000041 50521 D C 22 0 1 00007307 30000.60 0. 9 2 4 5. 6 52632.3552001 D Y S - 0 2934222261 R R D 28 1 0 391 303339 1 2 009.1 4 21 1 0024 3444 7 47954 1 1 N - 8 E G O 0 5 9 1 5 3 406253430.0 9 20342999094 00 7 0 0 3 6 261 00 5620.26 0 60 73 1 052 263 R 23 301 302220 4 1 025 7 21 D 1 2 1 1 1 1 8 Y H - R S 9 1 0 406257670.0 9 00 0 5 9 1 09007 6 .1 7.2 7 6 90 73 597 l l I 23 1 2 1 2034233300.4 301 1 302228 1 1 0 6 1 1 5 025 1 8 7 253 21 T I M C 4 9 1 0
- 3 40625707226.5560761 9
203423331 0 002671 31 1500000350029 55 3 4.2920100000304 L 22 12 301 302227 6. 3544.1 20026 1 1 1 1 1 3443 61 8 7 47951 1 1 M - - O T 5 9 15 406256660.2607 9 4 6 0 2 1 50 609 6 4 9 035 T 0 0 d r4 e 22 1
- 1 2
2034222275.2 301 1 302226 1 1 3 1 2 026 5 0 1 1 0 1 42 21 r H o C R c4 9 1 0 406250909.7014 9 . 0 9 0 2 1 6075 9040
% 000 P
E R e4 21 1 2 5 2034265670.2 301 301 1 1 4 1 1 1 9 0 3 5 01 0 1 9 1 1 8 1 76 21 m o 9 48625070392 9 0 1 5030 9- 005 r3 9 _ F4 1 4 21 3 2034299996.10 301 30 2 5 9 6 2 6 675.10 34 5 01 0 9 1 1 221 60 s 1 2 1 1 0 0 1 8 e l u a4 2 9 1
- 2 5 9406253430.9513 .
0 0 0 0 00030 6707 4 0 000 V 21 2 2034277724.1 301 30 2 0 4 0 0 5 01 2 5 7 2 176 243 m 1 1 1 1 8 _ h1 e 9 1 0 9 0 6 2 4 5 2 3 2 7.0 66 6 6 0 0 03050 6704 0 0 0 _ C4 1 20342444229 2 5 2 2 1 21 301 30 1 0 01 4 0 2
- 1 2 1 1 0 0 1 1 1 8 -
E 9 70001 5000501 S R 19
- 0 4062 9 5 0 0 0 0. 00.0045569410073000720.00001 2
.55 B 20 1 2 2034200000000.1 301 30 1 1 0 001 1
1 0017 1
%91102302.73.4 1
1 O 26471 19 11
- l : ::::: :::: l : 1 l ::::L:: l : :::: ::: 1 l S RRR HM RRRRM - FF T HHHMMMM M CC HHHHC I T ///FFFFMFMMBB//MMDB///// GG OB N
U W sssCCCCPCPPPPSSPPPPRRRRS M%HMMSSSSPSPPPPUUPPPPMMMMU EE DD%PP PP - E W) O& L( ) FFFW( NWWe OOO( ) LLL
)
RBRB" T T0 TT00 2 22 i 22 TEE t C F ~ O " " H0 . ELLTT N W( 222L2 . . . .RO D LTTEE d E NO HHHFH SSSS " MM N HUUJJ U Q ) RLW 2H RRRR" RR22" " " " OHI DD - 40 5 E S
+
( EFOPPmHFWNMNPEEEE..EEH0ROCDCP T SCFUUU L M O OOTT HHSSCC" " " " CCOOO
. . . R B" 2
T EE RR R E PPPL .L2222OO RCFHH00CCHNI RRNMNMRPMMM" I RRRRI OOOPP A V2 S TM EEN1CR WI TL I I CCLLLLCCCCCOO I
)
E - R1 E T RI OT OOREOR" B" TC0FFFFFFMNRRMMMMRRPPRLL PPHRC" " " C" OA2HHHHWHRREESSSSEEEEEOO * ( - l}
l l l i. APPENDIX B i O PEACH BOTTOM III TRANSITION METAL ION ANALYSIS O J. L. Simpson A. E. Conti O ! i 8 B-1 l l l
l: p l Introduction
'An automated on-line, semi-continuous transition metal ion analyzer was placed in operation at Peach Bottom III. This program was requested by PECO to ascertain baseline metal ion concentration prior to the hydrogen water
'i4 - mini test (HWC) and determine the effects of hydrogen water chemistry _on transition metal ion concentrations. The prime objective of this supplementary program funded by PECO was to determine the effects of HWC on the copper and zine concentration in the recirculation water. 'O Summary Baseline data were obtained during the four day period prior to the HWC for transition metal ion concentrations in final feedwater A&B, main steam, and O recirculation water. Final feedwater measurements indicate transient conditions exist for copper ion concentration. Main steam measurement gave surprisingly high results. Substantial decreases in copper ion concentrations in the recirculation water (10 ppb) were measured during j l each of the three hydrogen addition periods. Experimental An aut mated n-line, semi-c ntinu us transiti n metal i n analyzer was used O at Peach Bottom III. The instrument is capable of twenty-four hour operation, accommodating six individual sample sources with a two-hour cycle I time, and includes a real time data collection and reduction. A list of
% measurable ions and their sensitivities are listed in Table 1. These sensitivities are based on the injection or concentration of a 30 milliliter sample in the instrument. Thirty milliliter samples were used for all sample sources, except recirculation water. Because of the high levels of j g copper and zine in the recirculation water, the sample size was reduced to 2-3 milliliters, therefore, the sensitivities for the ions listed in Table 1 l are affected accordingly. Neither Fe * , Fe " , nor Pb " were detected during the program. Fe" takes approximately 20-25 minutes to be eluted i from the separator column (compared to Co" , the peak prior to Fe" , which takes 8-9 minutes) and therefore was not sought in every sample.
B-1
- _______-________________a
a. It was decided by the PECO Chemistry' staff,that the instrument would be dedicated to's single sample line the recirculation water, during the hydrogen water addition' tests. 3-t, Table'B-1 Ion Measurement Sensitivity
-Ion Part per-Trillion O; Fe+++ 100 m Cu** 10
-Ni+# 20 Pb 1000 O- zn++ 10-Co** 10 Fe** 50 The on-line transition metal instrumentation arrived on site on 12/3/84.
- The equipment was set up and operational on 12/5/84. Final feedwater A and standards were analyzed from 12/5/84 to 12/7/84. The results of the k standard measurements are listed below, Table 2. The system was shut down from 12/7/84-to 12/10/84. Airborne contamination prevented operation on 12/11/84'and 12/13/84. The system was operational 12/14/84 to 12/20/84.
The sample lines available on 12/14/84 were: e
- Final Feedwater A Final Feedwater B Q' Recirculation Water Main Steam B-2 h
i l... l _ _ _ _ _ . _ _ _ _ . _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
y I Final Feedwater Final' fee'd water.A & B were on-line from 12/14/84 thru 12/17/84. These lines were shut off during the hydrogen water addition test to dedicate the g analyzer to the recirculation water. During the 12/14/84 to 12/17/84 period, cobalt and i zine concentrations in FFWA and zine in.FFWB (cobalt concentrations were at trace. levels) remained fairly consistent. Copper
- from.both feedwater lines was-sporadic, the concentrations varying between 3L 0.1 to 0.9. ppb.
Main Steam )
. Copper, cobalt,; nickel, and zine (except for initial levels) concentrations remained reasonably steady throughout the analysis period. The source of these impurities is not. understood. It was assumed prior to this test that
'this sample would not produce measurable concentration for the metal-impurities because.the carryover would be extremely low. The cobalt and nickel (not detected in feedwater) concentrations are higher than those l detected in t,he final feedwater.
31 incirculation Water The three additions of hydrogen 12/18/84, 12/19/84, and 12/20/84 resulted in 7 decreases in the measured concentrations of copper. Zinc levels remained essentially the same through this period. (The graph final figure indicates a possible decrease in zinc, however, significant changes were not observed.)' Cobalt and nickel were not generally detected. An occasional cobalt spike was detected at approximately the 0.2 ppb level. The detection ) sensitivity is directly related to the sample size. For FFW and main steam 20-25 m1 sample were used. For the recirculation water, because of the higher concentrations of copper and zinc, only 2 m1 sample were injected into the analyzer, i B-3
l. Table B-2 Standard Data Peak Area Cu Ni Zn Co 10 Nanograms 310K 40K 278K 162K 311 40 278 161 3 312 42 278 160 lm# 312 41 277 165 308 40 275 166 305 49 273 163 305 40 276 164 j 307 42 272 162 306 39 274 161 305 40 274 165 307 40 274 165 g 305 9 3_9 276 166' E 308 41 275 163 20 Nanograms 629 83 541 319 623 81 539 316 598 83 533 307 572 80, 539 312 i 605 82 538 313 O 4 35 Nanograms 983 158 783 593 979 151 785 591 987 144 790 598 ) 986 155 787 592 f 978 153 791 599 968 156 781 597 952 156 775 593 q 3 971 156 781 601 l 967 154 780 602 961 151 785 600 956 152 785 604 l 937 148 769 591 ] 5 969 153 783 596 B-4
- i r
.J.__..._ . - . _ - _ . . . . . _ . . i p
MAIN -STEAM i I
- 300 PARTS PER TRILLION ,
i
. 1 i '~
- 200
) j .._ _ _ . _ . . _ . _ . _ , ,
.N.
( i.
- '! - - 100 J ! i
! i
_L . ._ . ._ __.- - 0 _. __; . . . . _ . _ j . _ _.. ..q _ _ . _..J . . _ .. _ j . _ ..__ . .
..__.]..-_..._._il l
! } i, !.
i i , , i NICKEL ! , i 3 1 I ae ' )I, __ . . . .
--__..-.._I.___._-..___.--_._.._.__... - 1 .
i , z, ! ' q . [' i l l
..----.e..--._--...-..-... !
i g)
; i ,
l, ,
. . - . , . - - . +
- - _- i- ---
- _ . - . . . ~ - - _ . . . . _
g ;
! [
l : - . 3 ' ~ ~ ~ ' '
- [
t t- COBALT ~~~ , ; I ' 3[ .
}
3 m . _.._.200 - 4 4 7 I ~'
~
i j . ,
- j. . .
l_...-_.__..._-__ 100 ..a J , _. _- . . .
. j ;
-.i. i ! , .4 ' '
-i ! t. f__
f . 1 ! !
-i { i 1 -- - l _ !_ --
..__.._:.-..._-_:_-_.-._.._.___.-...-._._..L ..
9 t 3 l 3 l l l l. l 1200 2400 1200 2400 2400 1200 2400 l I 12-16-84 :12-17-84: 12-15-84 I. 1
.*es._ .=
..6..ea.
.,-.e-o.ee<- e..e.'...m.e
o
'f i
.')i ii s 'N Ie- _',~ ._
g 'I ,_ i
~ . -(, . . . _
I , i
- 500
' PARTS PER TRILLION t_ ..
i :'
- 400 a) l
. - . J . .. c - 300
(+ _ _ _ . _ _ _ _ . . _ . . _ . . - _ _ - g : ; l ) r-- i
+
. ZINC
. . . . _ _ _ _ _ _ _ _ . _ _ _ _ _ , ' ~
- 200 4 .
t i i t i: l l
, - -- 100 j
)> j
. i, i l l
= i _
, i i; '
' i
)
.j _ _ .l .
j_ __. - _._
.._.i ___
- _ .. . - 0 ._ _ .;
, i l,
; , t i 1.b k.
T, Hr , [ . i t . _ . , . . . .... - .
.~l !
g . . j ! ! ! I, i,
. ,3 -
7 , i , i ,
- i L _ _._.t_ 300
) f. A i l l I - ! ,
? ! ! '
e A' / \+ 1
'. i 5
' U i l '
i i [ I
- l ,
i
'. l l
I j 6
, e
_ + __ q, 1. _ 200
' , . .l < ,
t !- i f [ l i
! i
.1 ..1
-j. -
- i. _I i- _- : l-l 7
- i. .---- -- - 10 0 - -
, . . . .3 ,
4 '
, _ _C.OPPER . _ . . _ _ - _ _ _ .
- 0 i , 1 l l l l l l '! '_ l 2400 1200 2:00 1200 2400 ' 42b0 >
2400 . 1 12-15-84 12-16-84 12-17-88 x l
. - - _ _ _ - _-_-_.--~_---_-_.-______-_-_._-__--.--___.a
i l
/
f l: L .
- t
..;_ . 4 . .c . 16_ -._. . ..l. TINAL FEEDWATER !'B" ' '
a .4 - 4 . 1: -_ .. - . . g9n { .
+ i 1
,. i ., . . . . - ... _ _ . . .- - ;..-
- 7. ,
i f.. , i .
~T 100
..i.
~
4 - _- ~ _ ._ _ _ _ . _ _ _ . _ _ . _ _ . . . _ , _ . . _ . . _ _ . . . . _o 1 { , ZINC
;- j-( '-
I 1._ _J j i . ; _._______.p.. i 1- ' ' l 1, ;- 7 i . Bi , i i st ,
, . _1
.; , j I
1
,' 700-":
,- t : . i #
, a
* ' 75 l _ ~
J y,L __. . a J t
. 4 i
I' 4 i 1 e 600 $ -
"f .
c .. I i l
' t . l, ' sa:
L,i
, i w
, ..,_.._a
;. . i. i. . ,.
, ~
i g L' 't
- ' s ,t ,.
e
, 500~5 3 '
i a-I t. L, .
, , _ . _ _ _ . I '
,,_.._.__._.J
!ui ;
i , x y i. 1
* ' "J 1 ;
l j
' : 400 ;~.'
- [-
I ' '
-! l, -- d COPPER ! !
)- :' 1, -
-g
. . I L - _ . . . . _ ,.M.-
1 i
. i j
w o s . l 4 i , . , 300 o8 n -
;; . ~ r . .:. -
i I 1
.j j
.f- ,
} g j
- j
.- . .; _ j j L.- 1 . , . . .
.l._
--4} 1..
i , . _ .. a . .
.-200 ,
.c , .
.i...
i
. l.. . . l. , t
-l. - ; .. . _ _j.
t
-!. j t-
- . 1:; ;
4 '
' = -- - - - - 100 -
. . -/ -- -
-s 4 4 e i ...
- 0~~
i
.I I 2400 I
1200 I 2400 I R. ..
- 1200 ; 2400 I
2400 1200 -
'12-15-84 . 12-16-84 12-17-84
. t L_.. _. . . . _ . _ . . . .
l _____:______- _- - . ~_
_ , , - ;;y v ..y; ' .,,.
. q ,.
'j 47 T - ,,i /'
-i a o . .: . -
t- , ; ,
.,i 8.. ,g y d 3 , .c .,
- a. T 'i# - - - - - ~
ff
; .[e,s/q *~- ;t
[ 3" . + =. ; i . d; _ irk _.4 " ' E3ALJEEDWATER .. - A-u .. . - . . h
*,./'. _~
{ 4 j PARTS;PER iTRILLIOY, . , ' _ + 1 p' t, .L .- .-
- 3
[ :/ - p I
-i - ;.
,.._ _ _ _ y ..- - 7 --200;
_;_ f . _. .
.): -.at;- .j..
;, s I
r g- g,
----- 4
- COB /.LT - -
D ^> ' g. - ,
?y ;
i
-.1oor 0
.i : , ;. . i
,. ...-, _ o._ 5
,f, <
q) ' f i 9 ,,
! q O.
--g -+ 3- 7 -
D, , {,U l-
.q ; t
, je ., l. -. , .
. . , ~ . . +
e . . . . ..
..C~, ,p :
,,;o '-
i 7 , ,
- s. ,: ! ., , -
}.
.) .'h f; ; , . = . -
! 1 F ,
)a '
) -j)t n g-
) ,., -.-. y
},. -_..a - . . . -
..i ef 1 , : , ;
,[ 1 1, l
.. i i t- . I j! 1 1 ,
2 t
, l. g '
_a. _._ M O ,
.i.
. r. ,
e, 1 I 4,l
,1 p
1 t N00 h- _, L. Z INC--- q
, ,1 4, e
1 .
. k..-
I l . ,4 ,1 . u 2 I.
..-..-} 4
' p. . h ,... , e i l l
g f <
} . . . }. 4 < ,
$ , o 89 0 ,' k
- 4) I
_ . .[_ ~ __s
+.,. 2
)f t ,
f g' a .
. . 4 1
. /
4 7.
. / . . . - -3 00 l
,/
h >
.l'.i -.
.e 7 ,
J..'_a..t / .4 1 T ,- 1.-
. i
. ,r q. r . ,a f c ,.
, 'El' L
- f- f..'
t,
--i i.
'f
,/
-w c
.a 4 -
i - i
, ,._ - , ' . _ ' ./.-- .00
( f i. j - '. j a ]' dl ! f 1l ' . ., -..'i-_.. _f. .l 1. !. 3 T ....
, 3 ,. . c (s
_.1 2 , i_ . , . . .
.t.
., o- .,. .,..i.. .;
{00 1 _. , .. ._ L . . _ _. x 3
, 3 r-
.. p _..
. . . x. . . , . .
a - J vo _.
-y..
. .i .,,,*^
t,
, 3 ., ,
._. t . ~..- . .,.
.. .,. i , ,. . ; ,
-- .- .- ~ .. ~ . - .-.-
y -...~p- ,. ,6 . . _ ~ .
.', h' ;
__s
, >J
-...-.p.....,.7+,9..-...--- , t- I
+
------.. wt -- --. .-. :,
,-.--o
&. I a ,-
,s i
' ?j e < ,
f f g f. p, . . . ._ s
'?400 1200~
2420 1200 2400 : :-1200 --.,.I2400 {,_
,/ - -
4 j i . . 12-15-84 , . _ 12-16-84 , , _ . i.12-17-a4
- p. .
e'
/ f-
? ,.
. - - . --..w........_-..-. . . _ . .
f
4 l'
. . . i_, _ .
.. !. 4 r '
. ! I
't* ~
'" a . . ;.L., _ !.
_ . - . . . ,, 3 ... ;_ 4 i . y 1000 4' 7' FINAL FEEDWATER -A-- q.1 -
- 1. !; ._.. _
PARTS PER TRILLION '.. ; ~ .
- A a Vf . 3: ;. ._ , . . _ _ _ _ - .-_ _ _ _ _ _ . . - _ . . - . . . - - - -- -
900
! :1:.
2
~
8 ' g - i%,i i_ . . . _ . . . _ _ _ _ . _ _ . _ . . . _ _ _ _ . . _ . _ _ _ _ . - 800 s .
.w.+.,. ), . g enas= e**e ~=+-q=*ah N- -- ****===*=*-~~'~m*e-'* ~ ~**"*'-*-- * "C"** ' - ' ' " * * ' * - * - * ' - -
1 -j ; - ,
? l' i .- I .[ ,
yg pu - _ I
- 700 -j i e ;
. 1, - 1 i.
+- ,
.'}.
8 i e
,s.
600-rrJPPE.R 4 ;
-. l l . 4 e, . :1 4 , .
; i____.~._..._..<
e . . 6 1 '. ! i J
-! n t j ,
J. t'.L i. . l 4 o ;
-J, 500 q v- .
I. i . n.-. t s3 -
. g: . . <
, e i-i U . c
- 4. '
I
-400-h' i ,.
l
'{ .
_. ' 3 Ll.- t 4 - l f ~h i i
, f. I A
I
'/
t 300.. ).<
' s.
I s
- i. [ ! '. I l
. ( ,. ' . .
't j '
j l U y . [' 1 l
} 'l I
; i .t y:
' j , 200 1 ,
.i. i 4-
' l , !
! j _
* *1 _3 _ . . . ~
-,, - - . .. , I 1 v .. , . , 4 .
. .. - - 4 >9. ; y - ;, ,_
~!
.4
.100 .
i i
.3 7 ,
- s. .
. .- r -;1 A " -
I-
.. 4 f
_4 .
. _ . . _ . ._. . . . . . _ _i.._._.______.___.- -
0~ k. f _ .l. ,. .l.. .d ._ . _ l _ - _ . .!_ i. 2400 1200 2400 1200 2400 1. . il200 2400 12-15-84 12-16-84 !T12217-84 1
.m._ --
._ . . . ~ ~ . , . . _ _ . .
3 g
'f. .I I
.l f f f' !
'l. j j. If nih H i' :l .] ! I: 1 i . . i ; il:
4 I: !-
.nm m me -
! i .I
- mum-
! L l- l ! i l- 1 i i' !: ! i 3
l, , I ,, ., ,, , :l - f -l o I_. 'i; ,,f I.,f:i 'i
; i- 4 L :i 1 ;. t -!
tu q p i- a i i
- .. .t
-"l
\ .
j
- ) r i I i e
0 f i . pappt ud6captg % i h !
* ~
..=t.:. ,- j - N +. 1
. .I N 4
- h. , , .
4 ;. .a : = + ./ s - .: ; -
;- , _g g y aeaoc us= n sinnaq #
uoneny% _ p.p. : . EEg. _[- i-ig n-..t,4 t-bit ;w ,0
--. l --
2, , I y-
- i g ,, - . .
/ - *
- i. :l .j- -[ T p - ! j
( ! 'l g 1~
! ! 1 1 !E ! E i ) i ,8 (_
.O i L I :l I
~D4, i ! k
- IhEI U h EW m , , 'O L'
i # iuy~-4 _.4
,j. .1'
. 'K .
i j /
; , E .
. ! .37 j.. . . . . 1 i
1 I .I. ..
- t. t .
/ _ g_
l l l I ~~l h' -l-~ l ! fI '
-*h N 11 4 4
- i .i !. .! ic 1 i a e : .. =
.1 ). /e" I I y :l' } l' $ '! ! !
3 o h - g :_ 4 .._-}.- Ej}p =f .:_. .: l _. .. } i fi
-jE l """'~8
., = .
l L t h 4- i. !. . T (.
. +
Q , l
- J' ._ .l ~i l ' ~ .I l
; ~k !
2
. - j- .
c .y +- =rir i j/ !. r .i
~
1
. r S .= # =e T .ij i: .i. i e i l-f 4r = =E .E -
.if y[-) I i !
i i .. = f as = s : ._ [ - - =gl =i ; .
,g~
!.=- p _::l:c i 4. <-pl.:s. .. . : p.. 4
.q . .I i !. . .
' h y l. i !
< 4...
= --. e x .l. I' i 4_
= ===: _
. .a
.q - J. ::.. ;p .5 -11: (j [ l, l r = ' - e ~
l , _. . fi i ! o -
,- L-< -
/ L -i .
. e :i L i i:: -i ! I
~
~}
l ! I
! - j
- - i
' ' l f
l l j .
! l l ! ! 1 f ! : !
l l l l .
. 4 mri er. ;;r- - .......................4,.....~ . . = =
.. 1
' a sie =
PIPING ISOMETRIC SKETCH SHEET o SWETc4 W, SM-39775-PI CATALYTIC. INC. g op q
, K
' PHILADELPHIA. PA. k FECO da "- PBAPS UU1T3142. -HWC SYSTEM-HYORo4Gh) DGTGCTION %Ro up.S - urt '/20t7 A TITLE MAIN FtoW con 7ect STAT)oN ,, c ot
- eo -
0 _$ a 2 I
- g. m -
P N i 1 QL \ J hh
+\
\ 4\ (tj
\-n k
e oo i 0 N c4
-g\;
'\
D m g $s \
. ~_s ~ .
N
/ 'k 7 Q~ ~
!Qf 8 v D
I
~, \ Q ! -l'\-
\ Q
, x =
dm 21 tk \W\ M Q. \aQ
\ %,4 h V
'\
b N 4 '\ b 4
~
\\
- 2. z m Ch bW t %-
l 2<5 ! k-J Enclosure 1 Vk
~Z.
Docket Nos. 50-777 50-278 _o
SK 39T75-?l PFCO PBAP5 UNITS I a2. - HWC 6ys7EM ftYDeC4E1J D ( T E C 1'l o N' 6t+Roups - MA M Ftoct; CON T710 L 6T&TlotJ % . 2 o F 4., Nc7res :
- f. dug 7tT/ l Rep utgs D psp UtJtT [2 TOTAL)
- 2. hjo .6cTTOM Ctd Si+Roub a 3 fl16 1=OLLO W IM Q R GG v1 P-CD So THkT SH RO u D t 1hY B E lNSTALL6D AF'rER PlPluf AM3 SOFFOR.T5 AR.E IN PLACE:
&< 6N VNIT 2, No SACM PAHELQUHALL SG $UPPU Gp.
N M T u i $ f 3 D cr d @_" d M " d T fs d dC9 M 4 e u o vs A s e ,
- b. FIGLD To cur Stars la roe or SHROUD So TH&T~
fop. MAY SLIDG INTe PLACE PAST PJ PGS.,
- d. FAbRL CATOR TO PRCVIDG 3" WlOc STR n PS ~~
To coven sto15 STR.IPS To SG SCRG%to To
.SHf2ovD Gy Fi(Lp AND Ceut k.ED.
- 0. BhCk cF si+RovD cd VMI T 2 To Fn f FLVS H To uJALL.
F t CL.O To CA vu k , - ea 96kL 791ETRATions w>TH DOCT TAPC IN FJELD. aW$$ n#?N?$eWsW?og,PgS 34 ELD OM FRoMT too ry ev 5 MATEA.I ALS CF CONSTA.y-CT IcN : H cT- Di FPED QALV,4W^&ED dARBc4 STEEL (gi+ssy Mc7At #.le M54 oR. ttEA VIER.) 6, REFrggw cc 15 o METRI C UNITZ. M- 3o57 sg. Io VM(T 3 H' 3059 SH. N Mo l+oLO Si+oP FABat CATiOM VM Ts L SH P-g uD DJ M e~MsgcuS NRE FIGLb ct+Gce6b Fon FR.cyDog PR.oM trJ TGn FL=TreM ce.S ,, V. SONT cp SM2.0VD To 66 hPP NGD u)) TH H13C M VISt& tLITf SIGN STA Tl M Q " H1 D R o QcN LGPcx DETec Tio M st+ R0 vb . kere poo R.s closed-UP mb T& Pep To REpvcc DR&PT. " L ETTERs SRih t se ipu is vM l' Mt 49
- 9. LIFTIMG Lv43 REcusR ED cu rop OF GHRouD.
i
8"'a "" PIPING ISOMETRIC SKETCH SHEET CATALYTIC. INC. SK ~39773*- P) g gp y PHILADELPHIA. PA. PECO PBA P.S UNITS I 4 2 - NWC SYS 73?M so, no. 3 9 7 75~ NYDROGGW DETEC77W SHA0&'bS- onre )/24/77 isrue BRANcn now costrAoi Srsnod ,, con
, s g D Rr $ ky 4 =en 2g 44 . 2 h g. . k'
% . g#
s %'E . o 2a m it a 30
% bk
- Sh MT be E m
"q 7 *s p% s @ Mi z s 'e*zc e er T
\ w 2w N
* 'S* c 3r" (o"/WA\ 4 # \ A G
\M -t ok
% Xr\\r Es
% v .\x \ 0 A-i v.
n a 2 U \k
=\ a h,k-
[d ~' i
=.
s
,i
- . } d L M \
iI p T 7 1\x\ L \ [7 \ l h I
/ >
\
\
/ 7
)- l j L - -- -- -------- - E
P6Co PShPS UNITS I 42 - Hsuc S)um k Y.D R O 4 % D G~ Th~ O 70 N 94hecu DS - 6Id-3'1773~~PI 8P.6tJCH Fi-oLO couTP-oc 6 7"'ATlou S t h I.} o p 9 Mo71r'<: It & Vr+wYt7y . 9 RAG Vt44D PGR VH I T (4 TorkL)
- 2. NO SofroM oeJ G44Rou.D
- 2. TI+G Foccowt uQ P 6GulR.E"b .So TrF&T~ 3&h20 UD MAY 66 IN5 ntt.cgp AF ruR PIP 1M4 AND SuPPott.r3 h-P-c 1N Pt. Ace ;
A. YGLD wit.c cur SCor5 Iw SopeS cF SitRouD AS SHow tJ. ;se Avp Scipe MRo up oven sra-Tierv
,L PA-sa.: cA rca. To F'r2 ovioc 3" W/D6 STR.s PS TO Covce SLOTS s STA ifs Sl&A-M., B,E $CR.dWces Sucy As LsFT-oFF Hi144es.
$s CONSTF2 uCTIOM MA75R)&c.S(Of;* d 07- DIPPG GALVA kil2%
CAAsoM Siz. S Hcc71 s e~rs e j @ r.is c, e s. thmviev ) (a . REY-Gnwncc lso v.<cTzt cs : PvMP 24 M-30 s 7 SM. Il R/nf 3A M-3057 sH (, 28 3.3 7 2c. p p 3c p 78
- 7. Kocp suoe Fesa.:cerim uM,,e s+aavD pum cust ous ARC T1CLD CHCCKED FO R Fi2 E@cM F9otA tween'.FER-en c65.
O FR.o a T of: sugavD To GE A. W e wfru tw4H visi sturf fl4N 5TRT1 tv6 " /tYD2.C 4e:N LEAE. PF TE cT10 0 SH12o vD, KE*GP c.LoskD- VP ' AM.D 7 hP'@ To REpu ce' DPAFT. " LET7kP-5 51h41 L pg 1-1 :N1is v m i I+ n C,11, E_ _ -- - - - - - - - - - - - - - - - - - _ - _ - _ - - - _ -
- h. ,
9 , i ' 1 PIPING ISOM ETRIC SKET.CH SHEET.-
.. CATALYTIC. INC.
$X-3427f-?)
pp q PHILADELPHIA A. PA. PEC0 PB+PS UNITS /M - HWG S)'5Wh1, aos no. 39 ~19 f Hy.pz o sca DETc e n oa SHeo vb s - om 12./r,Je& ritu l#JE CTioM ' Pol u T VALVE star;6( n doi) D e e
+ ::zi U
k'b O at W
% w
. kW /
g / py-4. j x'
, /
\- 9
'f 6.. y m ' ~
p e
\p-x L<-
i 's
\ s \
ne \ - h O 4 n e. D 9*agt s-
\",r t LR a%( t,1
~S
)
"s f 1
up
'th.d s
4 cw , 1
Lt l i M Ei E a L w "a T'.kI oP 9r u eY 5 5l o Mg' l l
/DT 5 Rt . oL " s U A l&
S 4 sI L c CR OTT E 7 vR 'A ~
/
S 3M (L N V 3 oD x J vH Y' 1 n~
- P HS E-V M q D 2 1
F t L s
"7 O -
MA L6 4 t EI 2 P 2oV A 8/ AF L ' & i I T f U TSC T S I EM i MTo UEP d E N D S D MU i P k
.X d
E - O AMo cPf P bel A R P4T OC
, - ORE 5 C DJ
( P) P E YN phi - 4 A ';d E d
' E g
\
%i D
u o R H S r '
,. y .
It1 O R 0 @ N D6TG'CTlcd SurrouDS ~ SK-39775'-PI L IM 5FCTio w Pold 7' VALvc STkT1 o V SH. '7 CF 9 P6co PbhPS VNIT3 (4 L - Hv)C SYSTm p kl0T66: p la QVAN $ REqutRe!) PER ud IT. (G ToTbL) l . 2. NO BOTTOM ' oM SH RO UD. 3, Tits I=oLL ou.) t J4 ' R E~QusMD So TH&T SHRo VD MAY ; bE ' IMSTht-CED AFTER. PlP1Nq $ SUPPOR-TS ARE 34 PLA CE l G.. YsGLb 0)scu evT Sto rs ja su pe5 Asic roe v7 SHROUD' W AS S+fc v 3 d A d b INSTAu SHRoub OVER VA1 VE .S-TA-Tlo M - E~A-ST S s DC crF'
$H12ovD mvSrSC R G MOVCh6u6 To Do Tlfts.
A P'A-s Ri cATo e. ro Peevips 3 ' A+>.D 5" o og
. STP. s P.S To co uG% .5LO TS.
sHsh,L ss SCAeiGP ro sHnou$l$$)STR.tPS cnuLVGD< C< ~ SCA PENETRATION 5. to1TH DUCT TAFE"
&i 5VPPt Y 2.G'MOVEAAC6 A CcG% Ph+d G~L N6LD oM,fR.cM T h)sTH Quicx-cP6hlis/G DEVICE'S SucH AS L iFr- 0FF HIMS ES .
K Mk-TERIIH G OF CoMSTY2 uCT1CH : dot- OL PPED Gr+t VAWIEeg) CAR.804 SrcrL-(5Harscrat *Ey M 14.)
- 6. RGFiQil,Gh)C4~ l @ H G~TM.t C5-Pum.P SA n-3057
,It Pumt 3A b1-3057 .sn. G
& ll B ~7
- c. ? 10 d v + f 71 touD S%P F#se cAmov un rnu srpaovD i p(hEWStou S AA6 RELD SNCWED YvP- R2-eGbo y FR OM ivT9 FGEcuCsG .
L l 9, FR OM T O F SWROUD TO SE A FI~' X 6D VO L TH dl4H V\SiStu TY } SIG M 6T'ATI M$i "HYDROdiFM LEAK D1ETEC.TioM SH4tou.b, I KEEP ci-pSCD- VP AND TAPGD To REDvCE DR A'PT." L6TTun.5 6HAth 66 H lNIM VH I" HI 4 l+ <
% TOTA L (.0 c:4;+r o F A s%wecy 5fe es LEs s THr%t 5'o L.9S.
*/ J,
".. TI C it T-P R
I MM U RD_ Y aL AT ., uE STTAN G P E n>. i.=CTA EAY D PS RIT BS E G
! W O=
A T A L n".e r t t t t F . Pu eO C. t Mo N I D P i.=
- a. e CW sE. E
^
nn E PH TM "4 p 3 ,4 *MG i. [I :,.i *aM t
) -
T.MI ui' (4 = g T l. _ EJ U m* . .
._ ac I/
JG t ' g Du =* .
. o W . =* , *, ,, , C .
M -. l
- n L i.
i, E , F. T S _ I5 - r1 V.
".l.
L ' ,n A o G 'J" u.
=4- ' i f
l __ K E. .
,'IN H .m 2 T :.
TA M .
'8L ,
H i.
'/ P .
7 1 0 2-D
>t o
C n. i TI RC R EMA H T W S u S G F. ' M . MS A t o . E AO P YE R H1) a E T. . O U EH R S . T H T )5 REE _ EE 5D AR u H T) RE T. u S T .\ Po EH x oO M- PT iRY ' o Mo FC(B l4Ea Ey T (B
.I'
[o
}
I .1 i I l I I i k
' I 1/ EI M L ._
L D oAlE HI uH )S -l L' DN t ' E A G LLA (S C E CTP NI P k ,REM L A A rec .F xDU S P_ AB P TA E F SW 4' LO O N4 CT T U HK P 2dEc 3LoTY E u T'
. 0 W (Lu(
1
f , , e m c.TO ST e u v t SM M ME NHSED I U- S G A T E. e m awAi W c PE n BY T Eu-S GT a PS O Yw RuM 8 D l A
'/
)
4 ( 4 .
~
3 , 4
'A G L
P E s% Eo m
=s
=
e m{ C.. E. PH D Y W HM o T.T MI T
' g EM f
/
k s DU =
=
O I N
=
E_ooo?" em"$ u e . * - L b.= E "5 = r e E m T e S b e. a M ns L a. A G .g- e KE HT .M . TA 8 L '
'/ P
.T )S D U T O u GER R M IMHT A H SO S E T.
E NY F H EE O E (B SD 8 S P 2 Y C - NS T F CS E) GA No O U 'o RD ' E DA 81~R YE , HH .l:J '8 i
'-(
l J
, N
, tI t
G o. N I D I H AI L i L . EK T E.D ME C~ A WCu O N P. P GLM) I A L
* (x5 R FO AE
/4dEEC E BP 4nH A A i
I ; L O b xL4 L . CTT P SP F u ,R 4 ., u E DHP i'U 2uSY ! 3 STAT 01 W( !
1 OVERSIZE DOCUMENT , PAGE PULLED l SEE APERTURE CARDS
-NUMBER OF OVERSIZE PAGES FILMED' ON APERTURE. CARDS- 4
{ I APERTURE CARD /HARD COPY AVAILABLE FROM RECORD SERVICES BRANCH,TIDC - FTS 492-8989 i e
, Enclosure 2 Docket Nos. 50-277 50-278 Question (USNRC):
Provide additional information on situations when dose at the Main Steam Line Radiation Monitors (MSLRM's) is between 3x background and the proposed setpoint of 15x background. Answer (PECo): In the unlikely event of an incident causing fuel damage, the speed and magnitude of the fission product release generally is directly related to the time sequence and overall severity of the - damage. The MSLRMs operate in the presence of the normally high v level of N-16 steam activity, which is on the order of 100 CI/sec Cat rated power) for large BWRs. Cladding defects, expected to release less than a curie of noble gases per second per fuel rod, are normally not large enough to trigger an MSLRM response. Although the MSLRM is capable of detecting large releases of radioactivity, the radiation detectors which provide the greatest sensitivity are the Steam det Air Ejectors (SJAE) retreatment monitors. l The time increment to detection and alarm for the SJAE offgas retreatment monitor is about 2 minutes. The SJAE offgas protreatment monitor is designed to incorporate a holdup period that allows for decay of N-16 and other short half-life fission products and activation products. Consequently, the SJAE offgas retreatment monitors are not unduly sensitive to operational events, such as condensate bed switching and the associated increase in N-16, which result in increases of short Ilved activity. With expected fuel performance, a change associated with a noble gas release rate in the range of 1 to 10 Cl/sec would be promptly alarmed. Calculations (ref. A) for a system similar to Peech Bottom shovrthat the MSLRMS are capable of detecting failures of approximately 10 fuel rods with the current 3x rated full power background. The differerice ' H tween the 3x and 15x setpoint corresponds to 10 to 50 fuel rods. These tallures correspond to an approximately 10 to 50 Ct/sec release rato. which would promptly be alarmed by the SJAE offgas retreatment monitor. In addition, the main stack radiation monitors downstream of an augmented ' offgas system will provide alarms when their setpoints are reached. The station technical specifications ensure that offsite doses in excess of the established release ilmits are not exceeded. Ref. A: Docket No. 50-387, "Susquehanna Steam Electric Station Additional Information For MSL High Radiation Setpoint Technical Specification Change, ER 100450, File 841-8" l l CMC /cmv/08138701 l
( .. - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - -
- --(-
'6~ '4 Enclosure 3 Docket Nos. 50-277 50-278 MECHANICAL ENGINEERING DIVISION N2-1. 2301 Market Street MEMORANDtN
SUBJECT:
Peach Bottom Atomic Power Station
. Hydrogen Water Chemistry System, Mod 1549C.
System Conformance Review Against BWROG Guidelines
REFERENCE:
- 1) Bolling Water Reactor Owner's Group, "Guldelines for Permanent BWR Hydrogen Water Chemistry Installations",
1987 Revision (BWROG Guidelines)
- 2) Letter, J; W. Gallagher, PECo, to W. R. Butler,.USNRC, dated May 27, 1987
- 3) Letter, E. J. Bradley,.PECo to H. R. Denton, USNRC, ,
dated February 12, 1987 ATTACit1ENTS: 1) Safety Evaluation for Hydrogen Water Chemistry, Mod 1549C, Rev. 1, with Attachments !
- 2) BWROG Guidelines Review for Hydrogen Water Chemistry
'A Hydrogen Water Chemistry (HWC) system 1s presently being Installed at Peach Bottom. In order to provide guidelines for such a system, the Bolling Water Reactor Owner's Group (BWROG) has developed "Guldelines for Permanent BWR Hydrogen Water Chemistry Installations" ,
.(Ref.'1). This memorandtm documents the.'conformance of the Peach j Bottom HWC design to the BWROG Guidelines. l The Peach Bottom HWC system will Inject hydrogen gas into the ;
suction of the three feedwater pumps for reactor dissolved oxygen control, and will inject oxygen upstream of the offgas preheater to provide a stoichiometric mixture of hydrogen and oxygen for the reconbi ner. Oxygen will also be injected into the condensate ptmp suction line to control feedwater pipe corrosion. The system is controlled either automatically or manually from the main control room. A complete description of the system and its safety features is included in Attachment 1. An evaluation was perfonned on the design of i our injection systems againtc the BWROG Guldelines and is contained in , Attachment 2. Ourzreview concluded that the design of the PBAPS HWC ; System is in conformance with these Guidelines. Additionally, we have been involved in the preparation of the next revision of the BWROG Guldelines and have modified the design of our system such that we expect to be in conplete compliance with the revised Guidelines when they are published. Certain aspects of the HWC program for Peach Bottom were not included in the original review of the system design (Ref. 2). We have reviewed these areas agalnst the appilcable sections of the BWROG Guldelines and the results are sunmarlzed below. I
- 1) Hydrogen / Oxygen Storage Systems-(BWROG Guidelines Section 3 and 4):
Cryogenic'11guld hydrogen and oxygen storage systems will be used at Peach Bottom for gas supply. The siting, design, installation and operation of these systems is in accordance with the Guidelines. Our evaluation of the storage systems is contained in Reference 2.
- 2) Radiation' Assessment Program (BWROG Guidelines Section 6.1.3)
An ALARA review addressing the various aspects of the radiation increase caused by HWC operation has been performed. No major dose impact is expected due to the operation of the first unit (Unit 2) on HWC. Additional evaluations will be performed during the start-up and initial operation of the system. The HWC mini-test in December 1984 established that the expected main steam line dose rate increase at full power HWC operation at Peach Bottom will be approx 1mately three times (3x) normal full power background without HWC. Additionally, dose measurements were taken both in plant, outside plant on-site, and off-site during the test. These measurements confirmed the three times dose rate increase to the station vicinity and also showed no effect to the off-site dose. Since the mini-test, TLD's have been placed at approximately 60 locations throughout the plant site during all stages of plant operation to provide baseline data to help quantify the effect of HWC following system operatlon. Following startup of the HWC system, additional dose nonitoring will be performed. Actual personnel exposure records shall be monitored and checked for any changes due to HWC operation. Also, TLD's will be placed in the same locations used to record basellne dose rate measurements so a direct ccmparison of done rates with and without HWC can be performed. Following the conclusion of these evaluations, a decision will be made on whether any action, such as administrative controls or shleiding, is required. The in-plant dose rates effect will be minimized through the use of administrative controls. All areas which will see a significant dose rate increase during HWC operation will be identified. Entries to these areas will be controlled administratively. Entries to these areas over the last few years are being evaluated for exposure and duration. Guidelines will be developed to identify entries for which the hydrogen injection ficwrate should be reduced or turned off. All significant entries to these locations during power operation will be evaluated prior to making the entry. L
,;. l
]
-i No significant changes to offsite dose rates due to HWC i: operation are expected. . The PBAPS environmental dose monitoring program places .TLD's surrounding the plant site i and are read on a regular basis. These wlil be monitored during HWC operation and'any dose Increases off-site will be identified. i Finally, the potential impact of the Increased'N-16 background. i dose effects on Health Physics monitoring equipment is under l review. Possible resolutions are increased shleiding or i relocation of the Instrumentation once the HWC' system is placed in service. I
- 3) Water Chemistry Control Program (BWROG Guidelines Section 6.1.4) o Presently, a Policy Statement and implementing Corporate Procedure 1 has been drafted and is under review which defines the Philadelphia j Electric Company conmitment to the BWROG Guldelines for Nonnal Water Chemistry and/or Hydrogen Water Chemistry. Our program is designed to comply completely with the BWROG Chemistry Guidelines. We expect to have the Policy Statement and Implementing Corporate Procedure l by the end of 1987. l l
Special monitoring programs to be perfonned during HWC start-up and j operation include use of a Crack Arrest Verification (CAV) system, ; a Constant Extension Rate Test (CERT), in addition to dissolved gas ! rronitors and an Ion Chromatograph. These parameters will be used l during start-up to optimize the operation of the injection j system. l l
- 4) Fuel Surveillance (BWROG Guidelines 6.1.5) ;
A Fuel Surveillance Program shall be performed at Peach Bottom to observe any impact on the fuel due to Hydrogen Water Chemistry. .I Four (4) fuel bundles containing pre-characterized Zircaloy j fuel components will be Inserted at the beginning of the l first cycle under HWC. Pre-characterized fuel undergoes a special documentation process which traces materials and verifles physical characteristics prior to placing the fuel ! In service. These pre-characterized fuel bundles shall be inspected I l following each of the first three cycles under HWC for unexpected corrosion or deposits which could be related to Hydrogen Water Chemistry.
- 5) Radiation Monitoring (BWROG Guidelines Section 8) l Due to the increased radiation levels of the main steam during HWC, the effect on various radiation nonitoring equipment has been addressed for Peach Bottom. The environmental qualification of safety related equipment was ,
reviewed and is not affected by the Increased radiation levels. The setpoint change which is required for the Main Steam Line Radiation Monitors was addressed in Reference 3. J1 2 87 A L
[ h. MECHANICAL ENGINEERING DIVISION N2-1 2301 Market Street SAFETY EVALUATION FOR HYDROGEN WATER CHEMISTRY MOD 1549, REV. 1 l PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 f, 3 FILE: GOVT 1-1 (NRC) RES 17-8-1 (HWC) ATTACHMENTS:1) " Criteria for Prevention and Detection of Hydrogen Leaks", Stearns Catalytic Corp., January 1987
- 2) " Permanent Hydrogen Water Chemistry Safety Analysis", General Electric Ccmpany, January 1987
REFERENCES:
- 1) Bolling Water Reactor Owners Group, "Guldelines for Permanent Bolling Water Reactor Hydrogen Water Chemistry Installations"
- 2) " Safety Evaluation for Liquid Hydrogen and Liquid Oxygen Storage Systems", December 3, 1986
- 3) " Peach Bottom 3 Hydrogen Water Chemistry Mint-Test Final Report", February 1985
SUBJECT:
This Safety Evaluation reviews the Installation and operation of the Hydrogen Water Chemistry system at Peach Bottom Atomic Power Station (PBAPS). The Hydrogen Water Chemistry system will prevent Intergranular Stress Corrosion Cracking of reactor piping and components. This Safety Evaluation does not address the storage of hydrogen or oxygen onsito, which is discussed in a separate safety evaluation. CONCLUSION: This modification does not involve safety related equipment. An unreviewed safety question is not involved. A change to the PBAPS Technical Speelfications is not required. A license amendment is not required, and therefore prior NRC approval is not required. ThIs edification maintains the capability to safely shutdown the plant in the event of a fire. A significant hazards consideration is not required. DISCUSSION: Hydrogen Water Chemistry (HWC) operation involves the injection of i i hydrogen gas into the reactor feedwater to eliminate the oxidizing ! chemistry conditions which promote Intergranular Stress Corrosion f Cracking (IGSCC). The HWC mini-test (reference 3) Indicated that at full ! power a hydrogen flow of approximately 60 scfm is required to drop the reactor dissolved oxygen to IGSCC mitigating levels of approximately 15 ppb. 1 >
I The injection of hydrogen into the . reactor coolant reduces the oxygen concentration by' suppressing / reversing the oxygen forming l radiolysis of water. High dissolved oxygen levels are a significant contributor to IGSCC, so the injection of hydrogen ' reduces the potential for IGSCC. ' Laboratory studies, HWC tests at numerous stations, and ope' rating history at Dresden-2, have shown that the potential for IGSCC can be eliminated if HWC is properly implemented. During normal operation a stoichiometric ratto (2:1) of hydrogen to oxygen is present in the main steam which, with the addition of air Inleakage, results in sufficient oxygen to react with the available i hydrogen at the offgas recombiner. Due to the reduction in dissolved oxygen l In the reactor water under HWC operation, less oxygen is available to be stripped away with the main steam. In addition, nore hydrogen is carried over to the steam due to the hydrogen addit lon. These two facts combined result in a potentially explosive hydrogen rich mixture ; downstream of the recombiner. .In order to prevent this problem, j oxygen gas will be injected upstream of the recombiner so that sufficient i oxygen will be present at all times to react with the available hydrogen. The injection of hydrogen results in an increase in the N-16 l activity of main steam due to a redistribution of the nitrogen in the water and steam. The Increase in the N-16 steam concentration occurs because of the chemical change that occurs in the core with hydrogen addition. The N-16 Isotope is formed by a (n,p) reaction W!th the reactor water while operating with normal water chemistry conditions, l the majority of'the N-16 forms nitrate (NO z ), which is relatively l non-volatile. The more reducing core chemTstry of HWC result in a l greater fraction of the nitrogen forming volatile compounds (anmonia, nitrous oxide), which are swept into the steam phase. The ifdC mint-test (reference 3) showed that under HWC operation at Peach Bottom the increase l- In main steam activity should be approximately three times (3x) the present normal full power background. The MSLRM setpoint is being adjusted by a separate modification and the new setpo!nt will accommodate HWC operation. The reduction of available oxygen in the condenser results in less oxygen in the condensate /feedwater. Extremely low dissolved oxygen levels in the feedwater cause general corrosion and thereby increase the Iron input to the vessel. This modification wi11 include a condensate oxygen injection system to keep dissolved oxygen levels at the recommended levels (20-60 ppb). System Description , General: l l The system is designed in accordance with the guidance provided in the BWROG "Guldelines for Permanent BWR Hydrogen Water Chemistry < Installations" (Reference 1). i
Hydrogen Injection: Hydrogen gas will be supplied to the station f' rom the storra- site l approximately 1700' west of the Unit 3 Reactor Building. '.i.e pennanent hydrogen facility is addressed in reference 2. The hydrogen supply system consists of a cryogenic liquid hydrogen storage tank, cryogenic punps, anblent vaporizers, high pressure gaseous storage tubes, and associated controls. The system also incorporates provisions for temporary hydrogen delivery via trucks. The gas is delivered at high pressure (approximately 1000 psig) to the station. The hydrogen piping is stainless steel, Schedule 160. The hydrogen pipeline feeds similar injection control systems for Unit 2 and 3 and also feeds the existing generator cooling hydrogen supply system. The supply line to the existing hydrogen storage tubes for generator cooling ties into the systens fl11 line and does not affect the systens operation. This supply line will permit filling these existing hydrogen storage tubes from the new hydrogen storage facility. The hydrogen injection flow rate is proportional to feedwater flow and a final adjustnent is nede based on reactor water dissolved oxygen concentration. The feedwater flow signal is electrically J lsolated fran the present feedwater flow control system. Redundant i flow control trains are provided for reliability and nelntenance. Following the control station the flow is split and injected evenly into the suction piping of the three reactor feed pumps. The systen control logic is designed to inject the hydrogen so that the hydrogen is fed into the reactor vessel synetrically such that the oxygen concentration will be suppressed in all parts of the vessel. Check valves are included on all injection lines to prevent back feed to the hydrogen injection system from the feedwater system. Although the maximum hydrogen flow rate to be injected into the suction of one reactor feed pump will be approximately 60 scfm, the injection of hydrogen at a flowrate of 100 scfm into a single feed pump suction line at all operating conditions has been evaluated and will not adversely inpact feed pump I operation or naterials. This flowrate is greater than the excess flow check valve setpoint (approximately 90 scfnD or the high hydrogen flow trip setpoint (approximately 75 scfm), so system transients will not result in an adverse impact on the plant. The injection of hydrogen is tripped on the following inputs: a) SCRAM b) High area hydrogen concentration / area temperature c) Low offgas excess oxygen concentration l d) High injection hydrogen flowrate e) Less than 20% power f) Low hydrogen injection pressure g) Operator request l L
~
L _4_ [ Additionally, the high area hydrogen concentration and low hydrogen t
. injection pressure signals isolate hydrogen flow to the station by closing an outside. Isolation valve. The existing hydrogen storage tubes for the main generators will be isolated from the HWC system ~except during tube filling operations.
l- Oxygen Injectlon:' l 0xygen gas will be supplied to the station from the storage site appror.imately 800'. north of the Unit 3 Reactor Building. The permanent oxygen facility is addressed in reference 2. The-oxygen supply system consists of a cryogenic tank, an ambient air ' vaporizer and associated controls. The system also incorporates provisions for temporary oxygen supplies by truck. The gas is to the injection point on g ,p/W deliveredatapproximately100psighepiping. the offgas system preheater dfsefef A check valve is included on the injection line to prevent backfeed to the oxygen i injection system from the offgas system. I The oxygen flow is proportional to hydrogen injection flow (ratio is approximately 2:1) and a final adjustment is made based on offgas excess oxygen. Redundant flow control trains are provided for reliability and maintenance. Following a trip of the hydrogen injection system the flow of oxygen wl11 be held constant for a period of time (approximately 10 minutes) WM ch is sufficient to permit the hydrogen and oxygen carryover to return to a stoichiometric ratio. Oxygen is also injected into the suction piping of the "B" condensate pump for feedwater pipe corrosion control. The oxygen injection to the feedwater is very low flow (approximately .1 standard cubic feet per minute) and will be manually set. The exygen flow will be automatically isolated from the station on low condenser vacuun. Instrumentation: The hydrogen and oxygen flow controllers will be Installed on the existing feedwater panel (C06A). All controller inputs, which include reactor water dissolved oxygen concentration, offgas excess oxygen, hydrogen flowrate, and oxygen flowrate are Indicated on the panel except for feedwater flow, which Irr indicated on panel COSA.
~
The manual system trip push button and Indicating Ilghts for all hydrogen isolation valves are also located on the feedwater panel. The remainder of the system controls Chand switches, Indicating lights, annunciators, progranTnable controller, etc.) are located on new panels 20C810 and 30C810 located in the main control room at the present location of the 00C512 panel. The scram signal used to trip the non-safety related hydrogen injection system is electrically isolated from the safety related reactor protection. Annunciators will be provided on the main control room annunciator panel to alert the operators of system " trip" or " trouble". The new panel will be provided with annunciators / alarms for specific system upsets. The modifications to panel CO6A, and the design of panels 20C810, 30C810, and 00C512, have incorporated hunan factors considerations.
Additional station chemistry nonItorIng equipment Is also beIng added to support this modification. Instrumentation will be added to measure the reactor water dissolved oxygen concentration and the offgas excess oxygen percentage, both of which are inputs to the injection controllers. In addition, nonitors will be added to measure the hydrogen concentration, or high temperature, in areas where leakage could occur so the injection system can be isolated and vented in such an event. Electrical: Power to the system components inside the plant via System Control panels 20C810 and 30C810 will be supplied from 120 VAC instrurent power panel 00YO6 which is fed from MCC 00829. The additional process load is fused at 20 amps per panel, 4.8 KVA max. total. A separate line, fused at 20 amps, is connected to each system control panel for internal lighting and convenience receptacles. Since panel 00YO6 and its feed have a capacity of 30 KVA and only approximately 16 KVA are presently connected, the additional load is acceptable. Power to the existing hydrogen storage area will be supplied by a separate feed from the 4 KV line near the North Substation. This is a power grid line and is not safeguard power. A new pad-nounted 150 KVA transformer will be installed to supply the estimated 50 KVA load. The additional bus loading at panel 20C06A is estimated at 350 watts which is not significant. Hydrogen Injection System Safety-Hydrogen gas Is combust 1ble with a lower 1imit of f1anmabi11ty of 4% and a lower explosive limit of 17%. The injection system has been designed, as detailed in Attachment 1, to safely handle the hydrogen injection gas considering the possible occurrence of abnormal process upsets or accidents. The major safety features of the system include:
- 1. Area Hydrogen Concentration / Temperature Monitors
- 2. Vent /Porge System with External Flame Arresters
- 3. Low Pressure H 2 !" 1#ti "
- 4. Piping Quality
- 5. Excess Flow Check Valves '
- 6. Hydrogen Isolation Spool Pieces for Maintenance Use
- 7. Zero-Leakage Bellows Seal H v"IV**
2 The area hydrogen concentration rronitors are located in hydrogen collection shrouds. All portions of the injection line which contain valves, instruments, spool pieces, etc. which create an increased possibility for hydrogen leakage will be monitored. All Instruments I within the shrouds are of explosion proof design. As detailed in reference 1, area hydrogen nonitors are ineffective in large, open i spaces, so the system design calls for enclosing areas with possible leakage points to permit hydrogen detection. When significant hydrogen is detected, an alarm is annmelated in the main control room and the injection l system is automatically shut off. Additionally, a isolation valve l
7 AO-7640, external to the building, is also closed, Isolating the hydrogen from the plant; any hydrogen within the plant can then be vented through i flame arrestors outside. Temperature tronttors are also included in the l shrouds to isolate the system in the event of an Ignited hydrogen leak. In such an event, hydrogen would not be detected, so the Increase in l j temperature caused by the hydrogen flame will shutdown the system. A vent / purge connection is provided which permits the hydrogen piping to be vented. The vent lines are located Immediately upstream of the Isolation valve from the feedwater piping which permits the entire system from the gas supply to the injection' tap to be purged. The hydrogen is vented through a flame arrester which prevents the released hydrogen from igniting. The hydrogen piping is stainless steel, schedule 160, with socket weld fittings. All welds will undergo a last pass liquid penetrant examination prior to service. The hydrogen piping system will be hellun pressure tested following installation and soap-bubble tested for any leakage. The injection system valves are zero-leakage, sparkless bellows seal valves with a backup packing. Excess flow check valves have been provided to shut off hydrogen flow in the event of a large scale piping system rupture. A single 2 ccmron excess flow check valve is provided Immediately downstream of the supply system and additional excess flow check valves are included after the hydrogen supply line tees to the individual unit control stations. The excess flow check valves will preclude the buildup of a flamnable, or explosive, concentration of hydrogen in the turbine building due to a pipeline rupture. Hydrogen supply piping will not be routed in safety related structures or areas housing safety related equipment. In addition, the hydrogen supply will be Isolated from the plant by closing AO-7640, the external isolation valve, on low hydrogen pressure, which would occur in the event of the rapid hydrogen release and system depressurization following a hydrogen pipeline break. As a means to completely isolate the feedwater piping from the hydrogen supply spool pieces have been included which can be removed when the hydrogen system is to be out of service for an extended period i of time. A more detailed review of the safety aspects concerning hydrogen gas usage is provided in Attachment 1. Effects of Hydrogen Water Chemistry Operation on the Plant: Operation under HWC has been analyzed by the General Electric Company (see Attachment 2) for possible impact on the plant. The ) reference analysis addressed the changes in the station operation due primarily to the change in reactor chemistry, which includes:
- 1. Fuels Impact
- 2. Offgas impact
- 3. Sunp Hydrogen Concentration
b - u
+
- 4. Torus Airspace Hydrogen Concentration
- 5. Condensate /Feedwater Materials L .6. Reactor /RecIrc Materials L 7. Main Steam Line/ Turbine Operation
)
Based on this analysis, we have concluded that there are no unreviewed l safety questions associated with HWC operation in terms of the changes l to plant chemistry and 'Its effect on the plant. As mentioned in the GE analysis, a fuel surveillance program will be implemented at Peach L Bottom. Four (4) precharacterized fuel bundles will be in service throughout the next cycle and will'be inspected to identify any l changes due to the HWC operation. 4 ALARA As previously described, the main steam line activity will change due to an increase In the N-16 concentration. A preliminary radiological evaluation based on a conservative 4X increase (the mint-test results indicated a 3X increase) using sky shine and direct dose computer nodels indicates that an increase to the site dose rate will be released under HWC operation. The increased dose wl11 be to workers (primarily non-radiation workers) in the administration building and the other support structures, but not to workers in the plant. Hydrogen injection can be turned off for as much as eight hours before the IGSCC mitigating benefits are lost. This will permit work to be performed in areas, such as near the turbine, where excessive dose rates could be experienced when HWC is in operation. The dose increases of concern will not result in any workers exceeding any Federal /NRC exposure guidelines including 10CFR20. The offsite dose rate, as measured during the HWC mini-test (reference 3), will remain a small fraction of the 40CFR190 limits. Therefore, shielding is not necessary, and will not be installed on Unit 2 for the HWC system startup. Dresden-2, which has operated with HWC for two cycles, did not see an increase to the total site exposure from HWC operation. Additionally, the location of the Unit 2 turbine results in significantly less dose to the station than Unit 3 strictly because of relative location to high occupancy locations. An estimate of the possible dose increases due to Unit 2 HWC operation are expected to be less than 30-40 manrem. There are no cost effective shleiding options for Unit 2 considering dose rates in this range. A final radiological assessment is in progress which shall better define the expected dose increases at Peach Bottom and track dose rate infonnation following system start up. The results of this evaluation will specify any shielding required to meet long-term ALARA goals; HWC is not a significant ALARA concern over the short term.
+ ~
- 8'-
General: This modification nelntains the capability of the station to shut down-in the event of a' fire. .In: addition to the fire concerns. associated.with hydrogen, which has been addressed, the oxygen injection line also poses a concern. Oxygen supports ccnbustion so an increase in the oxygen concentration will increase the likelihood of Ignition and the rate of combustion. To prevent such a possibility, an excess flow check' valve is included on the oxygen injection line to shut off oxygen flow in the event of a rupture of the injection.line. This will prevent the development of oxygen concentrations that' would pose _a.significant combustibility concern. Additionally, the exygen
;lnjection line does not run through any areas housing safety related equi pnent .
Environmentally qualified equipnent in the area of the main stean line tunnel has been evaluated for the increased radiation dose due-to the change in N-16 activity and the increased dose is acceptable.. All hydrogen and oxygen piping will be identified following Installation for personnel safety during maintenance and operation. These modifications to plant systems are in accordance with the appilcable portions of 10CFR20, 30, 50, 100, 40CFR190, Reg. Guide 1.23 as required by I.E._ Circular 80-18. Changes to UFSAR Sections 9, 10, and 11 will be nede to add a description of this system. 10CFR50.59 Chances, Tests; and Experiments:
- 1. The installation and operation of a HWC system at PBAPS does not involve an unreviewed safety question.
A. This modification does not involve a significant increase in the probability of occurrence or consequences of an accident or malfunction of equipment important to safety previously evaluated.in the safety analysis report. This modification adds new equipnent which does not interface with existing station safety-related equipment. The design of the systen is such that even considering system nelftnction, no adverse impact on existing station equipment will result. B. This modification does not create the possibility of an accident or malfunction of a different type than any previously evaluated In the safety analysis report. In addition to neeting all industrial and regulatory standards, the HWC system as designed provides an additional margin of safety by: 1) reducing the likelihood of an accident by equipnent quality and safety features such as- zero leakage valves, and 2) minimizing the results of any postulated accidents by system design features such as excess flow check valves and flow Isolation. I I 1 l l
yn llll .1
-.9.- g'
.{! . {
e s. The remainder of the system (Instruments,~ controls, etc.) Is designed and installed in accordance with Ind.:stry standards *and ~ l
'do .not create-the possibility for any.unevalutted accidents.or l
. .)
mal functions. g L' : / j
. , , :4 C. This modification does not reduce the margi'n of safety as J '
. defined In the basis for any Technical. Specification. No S sections of the Technical-Specifications are affected by the' 'i
- Installation or operation'of HWC.
i
- 2. AchangetotheTechnicalSpecifications.lsnotrkquiredwiththis. ,G modification; no' sections'of the Technical Specifications are
' involved.
10CFR50.92 SIGNIFICANT HAZARDS DETERMINATION: 'Sl A 1Icense amendment!Is not' required for this modification;-
.therefore, a Significant. Hazards' Determination.Is not ap licab le.
3-- g, t ,,
' o%.p 3
k ys s. t k
r.. . s s. . 10 - O Prepared by: > u J73 Date: k, Y. ,[87 f-7 Reviewed by: O \ Date: 3/4/P7 f 4 I
-. f /l- wJ Date: 3 'i ]
PPSS (Section Head) , g,
,/ ^
v',/ /
/ de(C#
u /s. v-/ Date: 2 c 3 '87 B.L. $(BM N e f/ on-Lead Divislod R' viewer A - Date: 3'Y'WY Non-Lead %ivisionInd@ndentReviewer 4 b $$Ll.
& Date: 5fY ].
Non-Lead 0lvision , 3 i' < ~b Date: NE'S.(Section Head) CMC /cmv/0301870t+ ( .. , . Copy to: MEsf M BAPS C. M. Cooney" D. A. Anders ' ~; R. E. Simpson DAC (NG-8)
't s
s
% ['
\
l
- - - - - - - _ . _ _ _ _ _ _ _ _j
l 2870000452 l
, . ~
/ FIRE PROTECTION REVIEW CHECKLIST, REV. - C _.
responsible Eng. Clac s (n>v, Station PBAPS~ unie # 2+R MOD 0 l5'!il I. Mod
Description:
h <., c/rc rch Mafe bftnf/3 f/4 U J O
- 1. New penetrations.through rated fire barriers are being created. Existing penetrations require removal or modification (not including cable penetrations). (See Architectural Fire Barrier Dwg.)
No 6 Yes Description, location
- 2. New equipment represents an increase in the co.mbustible loading to the site. Items to.be cons.idered are
~
' lubricants, fuels,' combustible gases,~ bulk gas storage, ,
insulation, plastics, etc. No Yes / ( List quantity, natore, and location of combustibles llNew u s fiM/ int _ 5> Sbra v si& W' uecJ 50s, t3 QueIv" n2/M -.W x %L tL i.L.. . _ , A tw e.,1 + x, o.v /n u,a taq~ b
,1 M, 0 c' G FK M du.Ti2 L~,s < - r&re~ k. ndad / tvja_c 1 Ai-c.-
cospis c sscoo k x.
- 3. Relocation or addition of any safety related equipment / component / cabling.
No 2(_ Yes Description
- 4. Relocation or addition of any safety related equipment / components / cabling identified as safe shutdown in the FPER and circuit and raceway schedules.
No Yes Description EXHIBIT 3.3-VI , 4/86 (Page 1 of N 6
J - ffb ?P'0000452
- 5. Will the modification interfere with the effectiveness of .
,' (exis this; fire detection. and, suppression 'equivaent; such as require modification to_ sprinkler piping, o; block a sprinkler hesd or ' fire detector? Is there a apression or (
detection eqQipment within ose
' installed for this modification)n? footWill of newaccessequipmentto detecti.on; suppr,ession; fire dampers'be. compromised?
i , No /' Yes ! 1 Description _ [ / ii' , Prepared by: s A6L P).4,_ Date M/J//fd ' Revi,evdd by: Edg Date l[5- 87, I i> Any items marked Yes must be referred to the Buildings , l Facilities Branch for completion of Section II. f II. Requirereents/ resolutions of items 1, 2, 3, or 7, narked t ; Yes. A "T .~2- . '
% dkc Mtw re-fm*bo_%Ed$ced hM hSd.4o N P4 f- 'l Th. Ace W-wuW* ae444- tmsWEg% O dw M o.tW.4 ' MWL h%fw hw rh OM9evAm@Aexw _ M
%Einw was e (boxed i ed4 y 4t<<. tb%jh im A p , , CWg4 Prepared by: ,6 A Date ""y ~f 8I g.'F. Branch)
( Revie.wed b"4 N h he~ Date iR I 6Y I [ Tf F. Branch) Requirements / resolutions of item 4 merked Yes. >
,z '
Prepared by: , Date (E.E. Div.P Revikwedby: Date _ v (E.E. Div ) , ,, Approved by: ,j / Date ', (Sufv
.' 'Eng . 1(FB) _, .i / i x ;
ces E-I-C Ir}bustrial MPE EPE
, Station ^ Superintendent
.DAC-(coctype = 197)
~
tleA (Bvi %W. . (Page 2 of %
~
EXHIDT.T 3'.3-VI 4/86 , 3 {
, )
8 { t - - - - - - - - - - - - - - - - - - -
'y. s f7.,l .
4, 28'0000452
- ,1
'.,. c >
~
a
% f} !
sa m u. .
.asy. a., ,gp.- gre e. . e- see."8 s %e.t* e.**,.* P4 * * ' *
._, i _ _. . . . . .
do. , ) , waMs.(,ys e a4.7 5 - l>* . nard u J E L h e_ x
.. reaw w . FW4.-
, . . + ~ ... . . . . ... - .-. . .- ..* . . <e. . . .
w*..=*. ..w.es. .
.ep . .ee....e w . . s,e e . g 9..
a ..
-vea.p..t- ies.o . . . w ee . - e.
.. .- . . . - . . .+ . . . - . .
..e@ m
.ee.s . p..e =
m e- -= ese -.,.4 ep.- ..m ..p..m..w.e..k e m. m -
. e per w,se b e . .
e epp- e p. , Me .seg.v,p.- 4 - e g . pe m. p $ $ wge wp . essa b d p.p p. .p p.$ 1 w# .. . . - -.. .
.... war .. --. ,
- ... .6 e- ., +.-
.:.~ . :
b ',
. . , .... ... . . _ . _ . _ _ . - ~ . ..
4, . . . . . L
... i -. . . _ . . . . .
. .. . -. ..ae. -. .
esse-.ai *- a+ . hee .e-l k. l
....-~., .._. . . - . - . . -. . .. ... - -. . . . . - . . . - - ,
l
.j +
it + 6 f
/
.'.-+...$fE.[,-.-..........
4 I' \ k I
- i. %./ ,r ..- . . -
g ' ' l [ k' ? F' 'V t
.==e.o.- .e4 . . **
. ep .coe _
.er-- - . -. w esaer -
. ,(
g._........,.. , 1 3 s
+ .. . . , ,. t' ~ . .- %.. . . . -. . . . . . - ... . .., .. ..
l I L -- _ _ _ _ - _ - _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _
, M . *bU
'~-
~
- Industrist'SectIon -
FPRC Evaluation. R70000452 Mod 154H Station 9c>Ae5 Resp FB Eng c._ sr., Date s \ b th'?
~
Items Checked'Yes: 1.1. (1)' If PBAPS, require seals to be installed per , Spec M-610. (2) .lf LGS, require seals to be Installed per Spec M-629 - 1.2. (1) Will Increased loading impact on a ccrrbustible free zone @"~.
- IO .. PBN)S - 1.' FPP Sections B.6
- 2. FPP Sections 5.3.e's -
- 3. FPP Figures 5.3'.f's" -
b) LGS - FPER Sections 5.4.e's c) If Item I.2.1.a & b include any items marked yes, l Inform the responsible engineer that this is not { acceptable without additional analysis by Electrical Engineering or fireproofing the hazard, d) Calculate quantity of combustibles to be added in units PBAPS or the i consistent FPER forwith those given LGS.~IIM N vin3\FPP be for, d d ~m Pi#e I O'A O -" !EL.n. * .e4 be-- e ch W_ % Cd w b Jh.M6 ] h QJ4A'. unala r f.e N &veu m ~"S W /lti N oi M 0 kbe- rkt.bW a cha ' d l' ' -I j s i (2) Will increased combustibles be added to an area containing safety related equipment / cab!es which 1 is not protected by automatic detection? If yes, add detection, request an exemption prior'to , approval of work or relocate combustibles. Nb M M eM SeEn M.1 A l~2 : cA-c4JcholL teae A-U \
g."~%' i l > . 797_90004-57
* ~..
. . . . ;i p
..- 2. _
j l (3) . Will l Increased ccrrbustibles cause combustible . ~. - L- loading to be in excess of a requested exemption , l; for PBAPS - refer to'FPP Sections 5.3.f's ' p If.yes, determine 'lf increased loading defeats the' Intent of l the exemption request. I f no, inform the NRC in accordance ; i
.with estabilshed mechanism. If,yes,-request an exemption !
- prior .to start of work. s (4) Will the loading be added to an area in which there is unprotected structural steel?
a) Refer to PLC Structural Steel Stnmary . Calc tb. Yes Go to 1.2.4.b . - No \
.Go to I.2.5 g !
b) Determine if increa~se-Is treater or equal to 10% of the . , oriolnal fixed loading the calc is based on
- 1. If no, go to I.2.4.d
- 2. If yes, go to Structural Steel calc and reperform analysis. After completing analysis, go to I.2.4.c c) Did the increased loading cause steel to fall?
- 1. If no, go to 1.2.4.d
- 2. If yes, determine corrective action and Inform responsible engineer to go to 1.2.4.d d) Update analysis: If loading is greater than 10%, add an additional 10% or the total amount of increased loading which causes the steel to fall, which ever is less. If loading is less than 10%, update the safety factor (original 10%) so that the next calculation will'be based on the original 10% less any subsequent mods which have added combustible material to the area.
ppeM _ 7 ~ 9
. . . P 01)00452 - -
- 5. Does increased loading r'epresent an unevaluated hazard 'to safety related eculpment?
a) No, go to I.2.6 O b) Yes, go to I.2.5.c c) Determine if there is any adverse impact and any additional fire protection enhancements required.
- 6. After satisfactorily resolving items I.2.1 through I.2.5 on this evaluation form and items I.3 and I.5 on the FPRC, forward this evaluation and the FPRC to the responsible Facilities Branch engineer for the FPP for PBAPS or the FPER for LGS to revise the app 11 cable sections of the respective reports as required by this evaluation.
- 7. Sections of FPP or FPER reviewed. . . . ~
Secb> S.3 No i 6.\ /7 $ r *
. g
- 8. Conments. '
N M_ 6 Ct "" w w S td-th M wa W A ahk W %drb FPER . A<; mcJL.w M L hjML MJ\' W =s +4.4 Wiled % Oto % &c S W W.be ND I VM: _.
' \ '
WA\i *.n. *. ?TO t 9 epe/4 seci-iM
/ l.hbdAbw per IJF9N sokp E%.c L+-f 5e$hm 3.1 (See
/a .n w >o3 .aw w sc 44- M e=< -
vea % s,f% ]g Cn4e'm: '*-
/3.m Cau %s1sw g.u m s . m wh W-"4 -
cc. m % (scw ww Aac wi 55 w EpPCae b"*'6* *C ' sp % aA. 2 % , k Vau h\dh % 4- $ erHo^ 4.3
/% % h p% bdow */o 6 6e sh e_my CQ.Yh:$a ;, "$c
~~ + e -
se
- 4. ps.d svem s A 9 4 tsaf 4 mus swa sa p .94 to preAqA-eM
/ 5 :
7' d.swy.b~d %M u)LLlede. % s:d*()6 MM81%g p *- y h J e- ( d " P T A y .Q. $ f. H s
/at 3? % yms mAM O=DM s.2-cW4)
"*" CALCULATION SHEET .7
- NAME PR70000452 PHILADELPHIA ELECTRIC CD.
1.OCATION DATEi U SHEET NO. N
.susJECT N S. - ~^ O k JOB /CA NO.
y bb 5 ?#9.c-. sect-hu
,.a)umLa a p h a 2 4 P , q q , d s, u j
8.a) awv,~\ u o 46yux99 c m.h tuks, z i j z 2-94 e , t.z.3 z.o w' <a.M.4 g spb sb Jb 'w ome4 +. s,A 9. s .c . P.f,g sb+dE. k {cheld o-> 0)e- Q v.c.'a 4 %d wbo a pk+-a k u p chw, t. 6 g%.(goaM 69 am. y o u (o. h 6 b b \c V.dce,-h ,19 93 5.33 b a. p u a .a
'dt.L-6.h couanc.sg g.ee) PhIo rt-3% d b, cevad _
SW h P!# " (*3M . 7 %(ent Pme pan gkAp% e tu spa uswA w gn~ ' p .de u< w__ . . *-A_ (O d.k\ k k>fA cApim e pr mfi ast.1 oce e34 s 3 &J'Aeuav.ca ~ts c ccende ca e4Lh-b EPR oc_ e.a.p<+ t%.b ea3 s&t we-6 -sg -Lo
~5.hVth 5 3.40 Q 3.\ 7k.^~-7 3 c4 Tb 1*?P M be- Mo veD to ed61- tt o MMlx.
9J~~es 0 Ddw W Liaa 9 od.y Lo:s Qc e% us, b .04uao's 4 w)c g - @i.h s h.llelk oo. ca2 4 ss 3 ,4 s%& 2%e ,, %Aw%~
% nw 9
.s.. %
t- e p -t-m ,3+ reha t'{ w. 3 6 w%gu sf*ss e L.wum
- c. d 3 W
- 3) E bb- % .W 64q\ t[co}% Lp'& thydqw 9
3
%$e_ g *~
@ h a c.Adu<. y GAtgDesp CAkAt Mbl i 3
- b. D
- w a O
, 5)S/n 3A }w+4 +.c 1 M b N, S<=.vv.=> C' kd Hc.y 3 lMDO$ 3 G5%Aa.Av- h/L' - l
&ub,o4WMao%
eWc- erre os -1 MaAf[1 M%LaJa,dn.122.lse,cou.o
+ og ,
,}}