ML20062D533
| ML20062D533 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 11/20/1978 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7811240183 | |
| Download: ML20062D533 (22) | |
Text
1 e
e BALTIMORE GAS AN D ELECTRIC COMPANY GAS AND ELECTRIC BUILDING BALTI M O R E, M A RYLAN D 212 03
. November 20, 1978 Aar.eum C. Lumov4LL..Jm VeCE Pet 10&ssf bea t s
Office of Nucleu Reactor Regulation U. S. Nuclear Regulatory Co==ission
'Jashington, D. C.
20555
[
t Attn:
Mr. Robert W. Reid, Chief T'
Operating Reactors Branch #h Division of Ouerating Reactors
~
Subject:
Calvert Cliffs Uuclear Power Plant Unit No. 1 & 2, Decket No'. 50-317/& 50-318 Control Roon Dose
/
s
Reference:
NRC letter dated 10/10/73 from R. W. Reid to A. E. Lundvall, Jr., same subject.
Gentlemen:
The referenced letter requested that vc provide additional i
information relative to our analysis of the potential radioactive dose to i
control room operators following a loss-of-coolant accident. Our original analysis was submitted in a letter dated h/10/78 and was in response to your request dated 10/17/77 Attached are 1) a copy of the enclosure to your 10/10/78 letter stating the additional information required and 2) a c;py of our responses.
If you need further information or vish to discuss the information give.,
please contact us.
Very tr tly yoters,-
/. /
/
q
'. - (L ec - J. A. Biddison, Ecquire I
G. F. "rowbridge, Esquire ht. E. L. Conner, Jr. - NRC Mr. J. 'i. 3rothers - 3echtel P
f*W
'81124a 8 2 p
t
+-s
f
. Attachment (1)
ENCLOSUkE RE, QUEST FOR ADDITIONAL INFORMATION RADIATION DOSE TO CONTROL ROOM OPERATORS FOLLOWING POSTULATED LOCA CALVERT CLIFFS UNITS NOS. 1 AND 2 1.
Describe the equipment and procedures which have been incorporated into the control room ventilation system design which will assure isolation of the control room from contaminated outside air in the presence of a single failure.
2.
An independent calculation of the atmospheric dispersion factors for the control room intakes indicates a few differences which need to be clarified. Therefore, provide the analysis for the calcula-tion of the containment cross-sectional area and for the detennina-tion of the building wake effect (K value).
Provide a list of the wind sectors used, annual frequencies of winds in those sectors and the wind velocities used in the calculation of the control room X/Q's, Discuss any differences between the model used in your analysis and the current NRC model as presented in the Standard Review Plan.
Indicate the conservatisms that are available in your assumptions.
(Note that at present single sector consideration is not acceptable for diffuse sources such as the containment).
3.
Describe all methods by which the control room intakes can be isolated during or follwine a postulated LOCA.
4.
We understand from a telephone conversation of September 27, 1977, that the ventilation system design duct leakage is about 300-400 cfm. Your submittal used a 19 cfm control room inleakage rate.
Clarify the apparent discrepancy between these two numbers. Also identify tests and/or procedures which would be used to verify that the maximum control room inleakage under control room isolation conditions would not exceed the 19 cfm used in your analysis.
,e
Attachment'(2)
RESPONSES TO NRC REQUEST FOR ADDITIONAL INFORMATION ON CONTROL ROOM DOSE
- 1) The control room ventilation atmosphere is continuously monitored for gaseous activity. Whenever a high radiation signal is initiated, the fresh air intake dampers close, the exhaust damper closes, the post LOCI filter fan units start, their discharge dampers open, and the toilet and kitchen exhaust fan stops. Simultaneously, the condition is alarmed-in the control room. An alarm response procedure serves as a checklist to aid the operator in verifying that the ventilation system has aligned itself for the 100 percent recirculation mode.
To ensure that failure of the radiation monitor does not render the system inoperative, the monitor is checked for proper operation once per 2h hours. Additionally, Emergency Operating Procedures require that the ventilation system be manually placed in the recirculation mode following a LOCI until portable air sacmles are taken to confirm that the control' room atmosphere is not contaminated.
- 2) See attached sheets.
- 3) The control room air intake dampers may be isolated by:
a.
A handsvitch located in the control room; b.
initiation of a high radiation signal from the control room ventil-ation radiation monitor RI-5350; l
Manually bleeding control air from the damper actuators.
c.
f h) Control room ventilation system duct leakage is leakage out of_ the entire system ducting when pressurized.
(300-h00 CFM). Control room in leakage is that leakage into the control from oucside (19 CFM).
Leakage out of the ducting is into many areas other than the control room.
Hence, no correlatien can be made between the inleakage and the out-leakage.
Neither the FSAR nor the Technical Specifications require any testing to measure the leakage into the control room. Further, the control room was not designed to facilitate any such testing. We believe testing would be a major burden with no commensurate increase in overall i
safety.
t
RESPONSE TO QUESTION 2 I' ~
l CONIROL ROOM I/q DUE TO A POSTULATED LOCA i;
i i
.j I.
MODEL USED The relative concentration, X/q, is approximated by I/q
= Ke x f
'(Halitsky, 1963) j Ag (Murphy, 1974) 5j where ij.
Ke non-dimensional concentration coefficient 5
i The Ke values will be deduced from Halitsky's (1963) j wind tunnel tests on EBR-II reactor.
1i A
Reference building area which is the side projected
{
area of the isolated reactor building.
5 4
Reference wind speed which is equivalent to the tunnel u
E mean velocity at an elevation of 20 inches above the tunnel floor (0.77 D above the dome of the full scale reactor building).
f Wind direction frequency adjustment factor.
)
CALCULATIONS h
a)
Reference cross-sectional ares 1.12 D 2 A
=
where D is the diameter of the dome i
1.12 x (140) 2 ft2 A
=
2 i
2039 m
=
i 5
b)
Reference mean vind velocity 5
j Equivalent level for mean wind H = h + 0.77 D i
l i
where h is the height of the containment ij H
148.5' + 0.77 x 140'
=
I E
256.3' = 78.1 m
=
i!
4 h
Control Room I/q Page 2 of 9 2
l Based on three years of onsite data, 10/74 - 9/77, the wind speed frequency distribution independent of stability and direction is:
Percentile Class Wind Speed @ 10 m I
(mph) 5 1.6 i
10 2.2 20 2.9 40 4.1 Wind speed at 78.1 meter level is approximated by:
r 78.1 )p U
U
=
78.1 10 10 Where p
0.5 for stable conditions
=
Time After Corresponding Wind Wind Speed
}
Accident Speed Percentile At 78.1 m l
(m/sec,)
0-8 hrs 5
2.0 8-24 hrs 10 2.75 1-4 days 20 3.62
{
4-30 days 40 5.12 c)
Kc values determination Ii For uniformly leakage containment, the Ke value is obtained by averaging the Ke values for bottom up wind, mid-ht. up wind, I
top, mid-ht. down wind, bottom down wind, bottom left side, bo ttom right side, mid-ht. left side and mid-ht. right side releases.
(All Ke values are extracted from Halitsky's vind tunnel test results).
i s
4
.2 j
1
..., < - ~ -, -
w
a i
Control' Room X/q i
Page 3 of 9 e
I e
{
(Plant Directions) max. Kc I
Plant Direction N
NW W
j Release Location Site Wind W
WW W
i 1.
bottom up wind 15 15 4
i i
2.
mid-ht. up wind 0.4 1.6 3.5 ^
ij 3.
top 0
2.4 3.5 ii 4.
mid-ht. down wind 0.9 2.9 5
i i
S.
bottom down wind 0
0 0
3 6.
bottom side, left 0
0 4
2 7.
bottom side, right 0.6 0
0 8.
mid-ht. side, left 3.5 3.5 4
3 9.
mid-ht. side, right' O.5 2.8 4
Average 2.32 3.13 2.67 I
For release location covered by other building, Ke value sets equal to O for there is no cintaminant released from that part
~
of the reactor to the atmosphere.
(See figures 1, 2a and 2b for plant plan view and elevations).
d)
Wind direction frequency reduction factor
\\
Wind Direction Wind Direction Freq. (7.)
WSW 6.79 5i W
5.75 WW 6.89 W
8.65 (Independent of wind speed & stability)
+
l
7,
=
R aj Control Room X/q Page 4 of 9 3
=
?
tj From onsite met. data provided by Dames & Moore 2
i Time after Wind Direction
.{.
Accident Reduction Factor (Murphy,1974) 0-8 hrs 1
Ej 8-24 hrs
.0.80
=
i.:3 1-4 days 0.60
_i j
4-30 days 0.21 Use three wind sectors (vind sector of concern and two adjacent i_
sectors).
+
4 i
I 2
.5 l
f
II.
MODELS COMPARISON NRC APPROAC11 APPLICAlfr APPROACH X
Model Xf A
)
/
" (,,, p h + K+2 Kc x f
=
E
-A A
Projected area of containment building Reference building area (side projected area of the isolated reactor b1dg.)
3 Halitsky's EBR - II wind tunnel K
K
=
( S/D ) 1.4 tests Kc isopleths Wind speed at an elevation of 10 meters Reference wind speed equivalent U
to the tunnel mean velocity at an elevation of 20" above the tunnel floor (0.77 D above the done of the full scale reactor b1dg.)
Corresponding Wind Wind Direction Speed Percentile Factor 0-8 hrs 5
1 9
cr 8-24 hre 10 0.75 + F/4.
sM g.
1-4 days 20 0.50 + F/2 Same as NRC approach jw (For wind direction factor -
o 4-30 days 40 F
determination, the wind sectors on used are the sector of concern pg plus i.wo adjacent sectors)
OS s
i j
Control Room f X
q Page 6 of 9 b
=
j III. DISCUSSIONS
.5 i
The wind tunnel data (Halitsky's 1963) were reported as isopleths of j
the non-dimensional concentration coefficient Kc, defined by 5
i I
Ke
=
f i
4 4
?
4 where 3
}
Kc Concentration coefficient at any corresponding dimensionless
=
location X/t, y/t, z/
reference area A
=
i reference wind mean velocity V
=
reference length L
=
Ke field is independent with respect to length, velocity and source-strength scales. The mechanism of contaminant diffusion is the oddy motion of the carrier fluid. Concentration fields should be similar and Ke field should be identical in dynamically similar flow fields having similar source arrangements. Furthermore, the Kc field for a given building configuration, source configuration, and wind direction is considered to be invariant.
Accordingly, Kc values determined by wind tunnel tests with a model structure should be the same as those would be obtained with a geometrically similar building in the full scale atmosphere in the same wind direction, with a similar leak.
Specific quantities had been used in the calculation of the Halitsky's wind tunnel test Kc values. Therefore, representative equivalents for the Calvert Cliffs Nuclear Station configuration must be used in order to derive valid full scale concentrations.
The prototype of the EBR - II reactor shall be consisted of a hemisphere on a vertical cylinder of diameter D, overall height H (1.225 D) and 2
reference area A (1.12D ).
The mean velocity varied with height.
The reference velocity u was the tunnel mean velocity at an elevation of 20 inches (anemometer elevation) above the tunnel floor (18.9 m or 0.77 D above the top of the dome of die full scale reactor building).
e e
l
l Control Room I/q i
Page 7 of 9 5
l
[
Conservatism as outlined in the following has been applied in i
j using the model.
ij 1.
In selecting the Ke values from Fig. 8 - 14 of Halitsky's i
vind tunnel study (1963) slightly higher value than the I
corresponding value for specific receptor (air intake)
]
location has been picked.
(See attached Fig. 8 - 14 with g
the corresponding control room air intake location marked).
2.
Aerodynamic (mechanical) turbulence is caused by the introduction of obstacles into the flow. Buildings, trees,
.{
grass, rocks, etc. all produce changes in the velocity and 5
pressure fields. The Calvert Cliffs reactor building is 1
in conjunction with buildings, such as auxiliary building, 2
9 turbine building, control building, radwaste building, etc..
Therefore, the turbulence wake of buildings 'is created by the entire pwer plant complex. Using the cross-sectional i
area of the reactor building alone for dilution in the model
.(
~
is underestimating the intensity of mechanical turbulence available for diffusion..
3.
Atmospheric turbulence results from vertical and horizontal temperature gradients. In NRC model, the atmospheric dis-persion factor, X/q, is estimated by 1
W Q GQ /'=
and the model, used in Calvert Cliffs control room X/
)
estimation has neglected diffusion caused by atmosph ric t
turbulence.
l f
4.
NRC model applies to single leaks at high elevations (where l
separation between the source and receptor is greater than
~
307. of containment height) or to many simultaneous leaks at the containment surface (uniformly leakage over containment).
In both cases, no differentiation in'K values due to difference E
in release location and relative locations of the release and l
5 receptor pairs is given. For low-level leaks, the NRC model l
l
[
may be unconservative as illustrated below.
I I/q 1
Equ. (1)
=
l l
(* % %
- b)a l
/q I
=
Ke Equ. (2)
[
~
j i
e l
Control Room I/q Pese 8 of 9 i
i i
Sec Equ. (1)
Equ. "(2) by assuming both models' prediction
=
in agreement.
[
Ke
=
1
(< r ry y + g) u.
Av i
Kc 1
A V
=
i 1+
a u-f 1rr r (Kt2)
"t %-
yg
?
5 where K is defined as K 3
=
(f) 1.4 140' for S 72' and D
=
=
7.6 K
=
Simplified by assuming V
=
u 2039 m2 and A
=
a
=
Stability values of Equivalent Kc at Intake A
7.2 t
B 8.1 C
8.7 D
9.3 E
9.4 F
9.5 i
b I
Control Room I/N Page 9 of 9 l
?
U 5
By comparing the equivalent Kc values with the Ke values extracted j
from the Halitsky's wind tunnel experimental data for Calvert Cliffs air intake location, low-level release experimental Ke values have values higher than 9.5.
On the other hand, for high-level releases, g
the equivalent Kc values are higher than the experimental data, i
Therefore, it will be appropriate and reasonable to use the applicant i
model together with Ke values from the EBR - II model tests to j
estimate the control room I/q values for the Calvert Cliffs nuclear
~
station.
j
?
j The model and approach used in t'his calculation are theoretically E
sound and experimentally confirmed. It also contains the basic data from which the NRC evolved its interim position.
=
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