ML20205H654
| ML20205H654 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/08/1986 |
| From: | Wenkhous J DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20205H612 | List: |
| References | |
| PROC-860708, NUDOCS 8704010125 | |
| Download: ML20205H654 (16) | |
Text
,t DUQUESNE LIGHT COM?ASY Nuclsar Sarvicts Unit Review and Aopreval Sheet UNIT 1 - OFFSITE DOSE CALCULATION MANUAL ISSUE 1 Admin.
Rev.
Pgs.
Tech. Rev.
OSC Approv.
Eff.
No.
Issd.
Sign.
Date Review Date Sign. Date Date 0 M ' M " O'00f Rev. 1 111 1-17,18,19 E45 - // NM ~ f f- /7 2-12,13, ga s-/jum - te-C o 7
W R$-/>M 'U W 2-27 2-37 and OVPS-MsC'Y~fY 2-51 9A P MP I % y&/"N
())flo.
- Iofn/a y
Rev. 2 1-4.1-5 ERS-SFL-85-031 1-6,1-16 ERS-ATL-86-008 2-2,2-2a BVPS-RSC-5-86 BV-OSC-25-86 2-3,2-4 May 1, 1986 6/12/84 2-7,2-17
. ).
b b
2-19,2-65
/ J.W. Wenkhous and 2-82 May 2, 1986 q,
g
(
't s
1.1.1.3 The maximum acceptable radioactivity concentr: tion in WCL/m1 cf radionuclide "i" in the liquid effluent prior to dilution (CL) was deter-k mined by:
C
=S C
(g,g.4) g g c 1.1.1.4 The calculated monitor count rate in acpu above background attributed to the radionuclides, C.R., was determined by:
C.R. = [ C E i (1.1-5) i Detection ef ficiency of the monitor for radionuclide "1" E
=
g (cpe/pci/ml) from Table 1.1-1 or if not listed in Table 1.1-1 from Reference 4.
1.1.1.5 The monitor high-high alarm setpoint above background (neps) should be set at the C.R. value. Since only one tank can be released at a time, adjustment of this valus is not necessary to compensate for release from more than one source.
3 1.1.2 Setpoint Determination Based on Analysis Prior to Release j
The following method applies to liquid releases when determining the set-point for the maximum acceptable discharge flow rate prior to dilution and
(
the associated high-high alarm setpoint based on this flow rate for the Li-quid Waste Effluent Monito'r (LW-104) and the Liquid Waste Contamination Hon-itor (LW-116) during all operational conditions.
The monitor alarm setpoint is set slightly above (a factor of 1.25) the rate that results from the concentration of gamma emitting radionu-count clides in order'to avoid spurious alarms. To compensate for this increase in the monitor alarm setpoint, the allowable discharge flow sate is reduced by the same factor.
When the discharge flow rate is limited by the radwaste discharge punp rate capacity or by administrative selection rather than the allowable flow rate determined from activity concentration, the alarm set point will be propor-tionally adjusted based upon the excess dilution factor provided.
1.1.2.1 The maximum acceptable discharge flow rate (f), prior to dilution (in gpm) is determined by:
1-4
/
1ssue 1
(
Revision 2
- .s
( -
f=
(1.1-6)
F C i 1.25 [
MPCi Dilution water flow rate (gpm)
F
=
(16,000 + 9,000 R) - P.E.
=
Number of turbine plant river water pumps in T
=
operation Number of reactor plant river water pumps in R
=
operation 10,000 (gpa) from plume evaporation rate when P.E.
=
the plant is operating Radioactivity concentration of radionuclide "i" C
=
in the liquid effluent prior to dilution (pCL/ml) from analysis of the liquid effluent td be're-leased.*
A factor to prevent spurious alarms caused by de-1.25
=
viations in the mixture of radionuclides which affect the monitor response.
The liquid effluent radioactivity concentration HPC
=
limit for radionuclide "i" (pCi/ml) from Table 1.1-1 or if not listed in Table 1.1-1 from Ref-('
erence 3.
1.1.2.2 The calculated monitor count rate (in nepm) above background attrib-uted to the radionuclides (CR) is determined by:
1.25 [C E (1.1-7)
C.R.
=
g g i
The detection efficiency of the monitor for radion2-E
=
clide "i" (cpm /pci/ml) from Table 1.1-1 or if not listed in Table 1.1-1 from Reference 4.
A factor to prevent spurious alarms caused by devia-1.25
=
tions in the mixture of radionuclides which affect the monitor response.
- If the radioactivity of a radionuclide is below the LLD value specified in Table 4.11-1 of the BVPS Technical Specifications, the radionuclide should not be included as a source term in this setpoint calculation.
[
1-5 Issue 1 Revision 2
e 1.1.2.3 The liquid ef fluent monitor high-high alarm setpoint above back-ground (neps) should be set at the,C.R. value adjusted by any excess dilu-tion factor provided as defined in the tollowing equation:
f C.R.
HHSP
=
f' Monitor hig'a-high alarm setpoint above background HMSP
=
calculated monitor count rate (in ncpe) fron 1.1-7 C.R.
=
f Maximum acceptable discharge flow rate prior to dilution determined by equation 1.1-6 Actual maximum discharge flow rate to be maintained f'
=
for the discharge. The reduced value of f' may be due to pump limitations or administrative selection.
.+
1 4
9
\\
s
(
1-6 Issue 1 Revision 2' i
I
)
I I
1.3.2 Projection of Doses (Liquids)
(
Doses due to liquid releases shall be projected at least once per 31 days in accordance with BYTS 4.11.1.3.1 and this section. The Liquid Radweste Treatment System shall be used to reduce the radioactive materials in each liquid waste batch prior to its discharge in accordance with BVTS 3.11.1.3 when the projected doses due to liquid effluent releases from the site averaged over 31 days would exceed 0.06 mrem to the total body or 0.2 mrem Doses used in the projection are obtained according to eqiia-to any organ.
The 31-day dose projection shall be performed according to the tion 1.3-1.
following equations:
When including pre-release data A+B 31 + C (g,3,7)
D 3g When not including pre-release data A
31 + C
=
D (1.3-8) 31
,T, Where:
D31 = Projected 31 day dose, arem Cumulative dose for quarter, mrem A
=
Projected dose from this release, mrem B
=
Current days into quarter T
=
Value which may be used tc anticipate C
=
plant trends, mrem
(
1-16 Issue 1 Revision 2
2.1.1 Setpoint Determination Based on a Conservative Mix for Ventilation Vent and Containment Building Vent Releases (Ground and Mixed Mode Releases)
The calculated monitor count rate above background (C.R.), in acpa, the moni-tor high-high alarm setpoint above background (RHSP), and the monitor high alarm setpoint above background (HSP) for each vent and operational condition should be as follows:
PRIMARY MONITOR C.R.
HHSP HSP Continuous Release Via VS-101B 1.63E3 1.30E3 1.63E2 The Ventilation Vent Batch Release of Contain-VS-101B 6.87E2 5.50E2 6.87El ment Purge Via the Venti-Lation Vent Continuous Release Via The VS-1078 3.98E4 3.18E4 3.98E3 Containment Building Vent Batch Release of Contain-VS-107B 1.28E5 1.02E5 1.28E4 ment PURCE Via the Con-tainment Building Vent When the primary monitor is O.O.S. and technical specifications can be met for the respective alternate monitor, the following setpoints may be utilized:
ALTERNATE MONITOR C.R.
HHSP HSP Continuous Release Via VS-109 3.49E4 2.79E4 3.49E3 The Ventilation Vent CHANNEL 5 Batch Release of Contain-VS-109 1.46E4 1.117E4 1.46E3 ment Purge Via the Venti-CHANNEL 5 lation Vent Continuous Release Via The VS-110 2.04E4 1.63E4 2.04E3 Containment Building Vent CHANNEL 5 Batch Release of Contain-VS-110 6.80E4 5.44E4 6.80E3 ment Purge Via the Con-CHANNEL 5 tainment Building Vent l
2-2 Issue 1 Revision 2 y,
(.
The setpoints were determined using the following conditions and informa-tion:
Source terms given in Table 2.1-1.
These source terms are those The source developed in the FSAR for maximum expected releases.
term mix (relative activity) is conservative in that shorter half life nuclides with lower maximum permissible concentrations are present in greater proportion than is realistic due to decay times selected.
Discharge flow rate of 62,000 cfm for the Ventilation Vent (Contin-uous)
(Batch Discharge flow rate of 92,000 cfm for the Ventilation Vent release of containment purge).
Discharge flow rate of 49,300 cfm for the Containment Building Vent (Both continuous and batch release of containment purge).
Information listed under References - Gaseous Effluent Monitor Set-points.
The calculation method given in Sections 2.1.1.1 through 2.1.1.7 was was used to derive the monitor setpoints for the following operational
~
conditions:
Continuous release via the Ventilation Vent.
Continuous release via the Containment Building Vent.
Batch release of containment purge via the Ventilation Vent.
Batch release of containment purge via the Containment Building Vent.
2.1.1.1 The " mix" (noble gas radionuclides and composition) of the gaseous effluent was determined as follows:
The gaseous source terms that are representative of the " mix" of a.
the gaseous effluent were selected. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent.
Caseous source terms can be obtained from Table 2.1-1.
2-2a Issue 1 Revision 2
(
b.
The fraction of the total radioactivity in the gaseous effluent
(
comprised of noble gas radionuclide "i" (S ) for each individual noble gas radionuclide in the gaseous effluent was determined by:
i (2.1-1)
S
=
[
^i i
The total radioactivity or radioactivity concentration of A
=
noble gas radionuclide "i" in the gaseous effluent from Table 2.1-1.
2.1.1.2 The maximum acceptable total release rate in pCi/sec of all noble gas radionuclides in the gaseous effluent (ky) based upon the whole body exposure limit was calculated by:
500 (2.1-2) r (X/Q) [ K S g g i
Where y/ for each case is given below:
(
(X/q),
The highest calculated annual average relative concen-
=
tration of effluents released via the Ventilation Vent for any area at or beyond the unrestricted area boundary for all sectors (sec/m ) from Table 2.2-7 and Table A-3 of Appendix A.
5.3 E-5 sec/m for continuous releases.
=
3 (X/q)v 8.5 E-5 sec/m for batch release of containment
=
purge.
(X/q),
The highest calculated annual average relative concen-
=
tration of effluents released via the Containment Build-ing Vent for any area at or beyond the unrestricted area boundary for all sectors (sec/m ) from Table 2.2-9 and Table A-4 of Appendix A.
1.3 E-5 sec/m for continuous releases
=
\\
Issue 1 Revision 2
3.7 E-S sec/m for batch release of containment purge (X/q),
=
The total whole body dose factor due to gamma emmissions. -
K
=
g 3
from noble gas radionuclide "i" (arem/ year /pci/m ) from Table 2.2-11.
2.1.1.3 he was also determined based upon the skin exposure limit by:
d 3000 (2.1-3)
(X/q) { (L + 1.1M ) S t
g g
g i
The skin dose factor due to beta emissions from noble L
=
I 3
gas radionuclide "i" (mrem / year /pci/m ) from' Table 2.2-11.
The air dose factor due to gamma emissions from noble gas M
=
3 radionuclide "i" (mrad / year /pci/m ) from Table 2.2-11.
The ratio of the tissue to air absorption coefficients 1.1
=
over the energy range of the photon of interest, (mrem / mrad).
2.1.1.4 The maximum acceptable re' lease rate in UCi/sec of noble gas radionu-clide "i" in the gaseous effluent (h)foreachindividualnoblegasradio-nuclide in the gaseous effluent was determined by:
~
S Q (2.1-4)
Q g
t t (NOTE: Use the lowerofthehvaluesobtainedinSection2.1.1.2and 2.1.1.3) 2.1.1.5 The maximum acceptable radioactivity concentration pCi/ml of noble gas radionuclide "i" in the gaseous effluent (C ) for each individual noble g
gas radionuclide in the gaseous effluent was determined by:
2.12 E-3 Q I (2.1-5)
C(
=
y 2-4 Issue 1 Revision 2
(
I
{
The maximum acceptable effluent flow rate at the point F
=
of release (cfa) 62,000 cfm (Ventilation Vent)
~
=
49,300 cfm (Containment Building Vent)
=
Unit conversion factor (60sec/ min x 3.53 E-5 ft /ml).
2.12E-3
=
2.1.1.6 The calculated monitor count rate in ncpm above background attributed to the noble gas radionuclide (C.R.) was determined by:
[C E (2.1-6)
C.R.
=
i E. =. The detection ef ficiency of the monitor for noble g
gas radionuclide "i" (cpm /pci/cc) from Table 2.1-2.
2.1.1.7 The monitor alarm setpoints above background were determined as follows:
The monitor high-high alarm HHSP setpoint above background (in nepm) a.
was determined by:
HHSP = 0.80 C.R.
(2.1-7) b.
The monitor high alarm setpoint HSP above background (in ncpm) was determined by:
HSP = 0.10 C.R.
(2.1-8)
NOTE: The values 0.8 for the HHSP and 0.1 for the HSP are fractions of the total radioactivity concentration that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded due to simultaneous releases from several release points.
2-5 Issue 1 Revision 2
(
\\
2.1.2 Setpoint Determination Based on a Conservative Mix for Process (n
Vent Releases (Elevated Releases)
The calculated monitor count rate above backgound (i R.), the monitor high-high alarm setpoint above background (HHSP), and the monitor high alarm setpoint above background (HSP) for each operational condition are as follows:
PRIMARY MONITOR C.R.
HHSP HSP Continuous Release CW-108B 2.29E7 1.83E7 2.29E6 Batch Release of Pri-CW-108B 2.57E6 2.06E6 2.57ES mary Systems Degas Batch Release of CW-108B 3.33E6 2.66E6 3.33E5 Cas When the primary monitor is out of service and technical specifications can be met for the respective alternate monitor, the following setpoints
('
may be utilized:
ALTERNATE MONITOR C.R.
HHSP HSP Continuous Release CW-109 1.72E7 1.38E7 1.72E6 CHANNEL 5 Batch Re, lease of Pri-CW-109 8.28E7 6.62E7 8.28E6 mary Systems Degas CRANNEL 5 Batch Release of CW-109 8.23E7 6.58E7 8.23E6 Waste Gas CHANNEL 5 The setpoints were determined using a conservative mix from the FSAR and discharge flow rate of 1200 cfm for the Process Vent.
Issue 1 Revision 2
{
2-6
The calculational method below was used to derive the monitor setpoints for the following operational conditions:
Continuous release via the Process Vent Batch release of primary systems degas via the Process Vent Batch release of waste gas via the Process Vent.
'2.1.2.1 The " mix" (noble gases and composition) of the gaseous effluent was determined as follows:
The gaseous source terms that are representative of the a.
" mix" of the gaseous effluent were evaluated. Caseous source terms are the radioactivity of the noble gases radionuclides in the effluent. The gaseous source terms can be obtained from Table 2.1-1.
b.
The fraction of the total radioactivity in the gaseous effluent comprised by noble gas radionuclide "i" (S )
for each individual noble gas radionuclide in the gaseous effluent was calculated by:
A i
S' (2.1-9)
=
(
I A
t i.
i A
The total radioactivity or radioactivity con-
=
g centration of noble gas radionuclide "i" in the gaseous e.ffluent from Table 2.1-1, 2.1.2.2 The maximum acceptable total release rate (in DCi/sec) of all noble gas radionuclides in the gaseous effluent (6)baseduponthewhole body exposure limit was determined by:
500 (2.1-10) y
=
t
[
V.
S.
1 L
i The constant for noble gas radionuclide "i" account-V
=
ing for the gamma radiation from the elevated finite plume (area / year /pci/sec) from Table 2.1-3.
Issue 1 Revision 2
(
2-7
O n
I TABLE 2.1-2 MONITOR DETECTOR EFFICIENCIES EFFICIENCY IN CPM /pci/ce, CORRECTED (1.)
a RADIONUCLIDE VENTILATION VENT CAS PROCESS VENT.CAS CONTAINMENT-BUILDING VENT VS-101B VS-109 CHS CW-108B CW-109 CH5 VS-107B VS-110 CH5 Kr $3m Kr 85m 9.80 E7 2.39 E7 9.00.E7 2.43 E7 5.16 E7 2.57 E7 Kr 85 3.88 ES 2.47 E7 3.56 ES 2.51 E7 5.04 E7 2.67 17 Kr 87 7.38 E7 2.95 E7 6.78 E7 3.00 E7 9.60 E7 3.19 E7 Kr 88 1.14 E8 2.11 E7 1.05 E8 2.14 E7 5.16 E7 2.28 E7 Kr 89 1.39 E8 2.93 E7 1.28 E8 2.98 E7 9.59 E7 3.16 E7 y
Kr 90 1.34 E8 3.05 E7 1.23 E8 3.10 E7 9.87 E7 3.29 E7 Xe 131m 2.25 E6 1.56 E7 2.07 E6 1.59 E7
- 2.94 E7 1.68 E7 Xe 133m 1.26 Ef 1.94 E7 1.16 E7 1.97 E7 4.17 E7 2.09 E7 s
Xe 133 1.01 E7 1.24 E7 9.24 E6 1.26 E7 2.28 E7 1.33 E7-Xe 135m 7.15 E7 5.70 E6 6.58 E7 5,80 E6 1.51 E7 6.15 E6 Xe 135 1.12 E8 2.91 E7 1.03 EC 2.96 E7 6.42 E7 3.14 E7 Xe 137 3.16 E7 2.96 E7 2.91 E7 3.01 E7 1.05 E8 3.19 E7 Xe 138 1.15 E8 2.66 E7 1.06 E8 2.70 E7 7.35 E7 2.87 E7 Ar 41 7.17 E7 3.00 E7 6.59 E7 3.05 E7 7.19 E7 3.23 E7
( 1.) Table 2.1-2 Part A list detector ef ficiencies f or the respective Victoreen monitors corrected for the reduced pressures observed and documented during operation. Also listed are the SPING Channel 5 efficiencies corrected for detector unique installation Issue 1 factors.
(pressure corrections are not required for the SPING monitors) See references Revision 2 for additional information, i
l
I
(
BEAVER VALLEY ODCM REFERENCES Gaseous Effluent Monitor Setpoints (1) " Beaver Valley Power Station, Appendix I Analysis - Docket No. 50-334 and 50-412", Table 2.1.3.
(2) " Beaver Valley Power Station, FSAR", Table 11A-5.
(3) " Beaver Valley Power Station, FSAR", Table 11.5-5.
(4) "Duquesne Light Co., Beaver Valley Nuclear Plant, Specification No. BVPS 41.4, Table V Nuclide Data, S/30/74", Table 1 and Figure 1, Table 3, and Figure 2.
(5) Caseous Effluent Monitor Efficiency Data; Calculation Package ERS-SFL-85-031.
(6) ODCM Alarm Setpoint Revisions for Gaseous Monitors; Calculation Package ERS-ATL-86-008.
1 2-19 Issue 1 Revision 2 i !
l
(
~e s s Tha qu:rterly limito givsa cbova rapresamt cee-half tha canual daoign cb-jective of Section II. B.1 of Appendix I of 10 CFR-50.
If any of the limits of Expressions 2.3-17 through 2.3-20 are exceeded a special report pursuant
(
to Section IV.A of Appendix I of 10 CFR 50 must be filed with the NRC.
In addition, BVTS 3.1.2.4 requires that the gaseous radweste system must be used to reduce radioactive materials in that waste when projected doses aver-aged over 31 days exceed any of the following:
D 5
0.2 mrad 7
Dg 5 0.4 mrad 2.3.1.2 Projection of Doses (Noble Cas)
^
least once Doses due to gaseous releases from the site shall be projected at (See also Sec-per 31 days in accordance with BVTS 4.11.2.4 and this section.
tion 2.3.2.2 Projection of Doses). The Caseous Radwaste Treatment System and the Ventilation Ex5aust Treatment System shall be used to reduce radioactive materials in gaseous vaste prior to their discharge in accordance with BVTS 3.11.2.4 when the projected gaseous ef fluent air dose due to gaseous effluent releases from the site averaged over 31 days would exceed 0.2 mead for gamma radfation and 0.4 erad for beta radiation.
(See also Section 2.3.2.2 Projec-
{
tion of Doses for additional specifications). The doses used in the 31-day dose projection will be calculated using Expressions 2.3-5 through 2.3-10 as appropriate. The 31-day dose projection shall be performed according to the following equations:
When including pre-release data A
B 31 + c (2.3-20a)
D
=
3 When not including pre-release data 31 + C (2.3-20b)
D
=
3l T_
Where:
Projected 31 day dose, mrem D
=
Cumulative dose for quarter, mrem A
=
Projected dose from this release, mrem B
=
Current days into quarter T
=
Value which may be used to anticipate
=
(
plant trends, mrem Issue I Revision 2 2-65
'g' 's FJr tha cciandar yacra (2.3-39)
D 5 15 meen to any organ Where:
'~
from radioiodines and the dose to any organ D
=
particulates, area.
The quarterly Itaits given above represent one-half the annual design objec-tive of Section IIC of Appendix I of 10 CFR 50.
If any of the limits of Expressions 2.3-38 and 2.3-39 are exceeded, a special report pursuant to Section IV A of Appendix I of 10 CFR 50 must be filed with the NRC.
2.3.2.2 Projection of Doses (Iodines and Particulates)
Doses due to gas.cous releases from the site shall' be projected'at least once (See also per 31 days in accordance with BVTS 4.11.2.4 and this section.
Section 2.3.1.2 Projection of Doses). The appropriate portions of the Ven-tilation Exhaust Treatment System shall be used to reduce radioactive mater-fals in gaseous waste prior to their discharge in accordance with BVTS 3.11.2.4 when the projected doses due to gaseous effluent release from the (See also site averaged over 31 days would exceed 0.3 mrem to any organ.
'Section 2.3.1.2 Projection of Doses for additional specifications).
Doses resulting from the gaseous effluent release of radiciodines and particulates
('
will be calculated for use in the 31-day dose pro'jection using Expressions 2.3-32, 2.3-34, and 2.3-36 as appropriate. The 31-day dose projection shall
/
be performed according to the following equations:
When including pre-release data t
Y s
(2.3-40)
A+B 31 + C
=
D31 T
When not including pre-release data l
(2.3-41) d 31 + C D
=
37 T
Where:
D31 Projected 31 day dose, mrem
=
Cumulative dose for quarter, aren A
=
Projected dose for this release, arem B
=
Current days into quarter T
=
Value which may be used to anticipate C
=
f.
plant trends, urem Issue I Revision 2 2-82
. _ _ _ _ _ _ _ _