ML19308A750
| ML19308A750 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/04/1976 |
| From: | DUKE POWER CO. |
| To: | |
| References | |
| NUDOCS 7912110712 | |
| Download: ML19308A750 (40) | |
Text
_
h DUKE P3WER COiVPANY OCONEE NUCLEAR STATION PROPOSED TECHNICAL SPECIFICATIONS FOR COMPLIANCE WITH 10 CFR 50 APPENDIX l JUNE 4, 1976 THE ATTACHED FILES ARE OFFICIAL RECORDS OF THE OFFICE OF REGULATION. THEY HAVE BEEN CHARGED TO YOU FOR A LIMITED TIME PERIOD ANS MUST BE RETURNED TO THE CENTRAL RECORDS STATION 008. ANY PAGE(S)
REMOVED FOR REPRODUCTION MUST BE RETURNED 7 JS/JHEIR Og,lg[NgORDER.
E DEADLINE RETURN DATE N
76 N 2
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SDV MARY JINKS, CHIEF CENTRAL RECORDS STATION 7912110]/N
DUKE POWER COMPANY OCONEE NUCLEAR STATION PROPOSED TECHNICAL SPECIFICATIONS FOR COMPLlANCE WITH
- 10 CFR 50 APPENDIX I JUME 4, 1976 0
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2.4 RADI0 ACTIVE EFFLUENTS L.
- 3. :
Introduction a'
Objective: To define the limits and conditions for the controlled 5
yg release of radioactive =aterials in liquid and gaseous effluents I
1 to the environs to ensure that these releases are as low as is reasonably achievable in conformance with 10 CFR Parts 50.34a and 50.36a, and.to ensure that these releases result in concentrations of radioactive materials in liquid and gaseous effluents released to unrestricted areas are within the limits specified in 10 CFR i
Part 20.
i To ensure that the releases of radioactive material above backe ground to unrestricted areas are as low as is reasonably achievable, the following design objectives as defined in Appendix I to 10 CFR Part 50.36a apply:
A.
The annual total quantity of all radioactive material above The site background that may be released from cach light. :ter :::1:d r.uc1::: pm::r rereter to unrestricted areas should not result in an annual dose or dose commitment from liquid effluents for l
any individual in an unrestricted area from all pathways of T
exposure in excess of 7 millirems to the total body or h,
30 te millirems to any organ.
1
. i t'
e i
B.
The annual total quantity of all radioactive material above k
d[
Th
+
background that may be released from c;e S.re
- .11 L:,;;. c;;1;d
.c4
.R,.i nu:':;r pc;;;r r;;; tor to the atmosphere should not result in yk an annual air dose from gaseous effluents at any location (f
near ground level which could be occupied by individuals in u
1w 30 unrestricted areas in excess of 19 millirads for ga=na radia-Go I
tion or 29 millirads for beta radiation, or that this quantity should not result in an annual external dose from gaseous effluents to any individual in unrestricted areas in excess i
65 45 of -E millirens to the total body or t5 millirens to the skin.
C.
The annual total quantity o'f all radioactive iodine and radioactive material in particulate form above background that Th may be released from caca.e w+c 1;gh;, ;... 1.2 c.ucica; p;.;m.
ren ter in-:fflu;nts to the atmosphere should not result in an annual dose or dose commitment from such radioactive iodine and radioactive material in particulate forn for any individual in an unrestricted area from all pathways of exposure in 45 excess of F5 millirems to any organ.
r Definitiene :
h Te 2rrure "aifer ity of interpretation, the f;;;; wing i
definition: cr:
- d ir Sc: tier 2. ' cf thc;; Tccha.
1 Specificaciuns.
t sub:;.1;;s I
i - refers to indi'fidual ::dienuclids, j - "-f rr te time paried for ;;;ccu,.1 mou3
1 l
\\,
,l
- refers to time period for liquid releases.
/,C v - refers to all releases per site. These are non-el vated
~i
..4, eases as defined in Regulatory Guide 1.111.
fp r
s - ref s to all stack releases per site. Thes are elevated W
releas s as defined in Regulatory Guide 1.11.
ik 8 - refers t beta emission of a radionuc1' e.
l 1
Y - refers to g a emission of a radion clide.
T - refers to the oral body or an or n.
0 - refers to direct'on sector.
T}- direction sectors for the I
sites are defined -
the si een 22-degree sectors of a circle with the apex tt e center of the building complex.
The northsector shall that sector with true north as a centerline.
Notations Ki the total b dy dese factor due to gamma emissions for
=
3 each ide tified radionuclide, in rem /yr per pCi/m (from able B-1 of Regulatory Guide 1.109).
L th skin dose factor due to beta emis 'ons for each
=
i dentified radionuclide, in miem/yr per Ci/m (from Table B-1 of Regulatory Guide 1.109).
the air dose factor due to ga=ma emissions f each t =
3 identified radionuclide, in mrad /yr per pCi/m from Table B-1 of Regulatory Guide 1.109).
N
= the air dose factor due to beta emissions for each g
identified radionuclide, in crad/yr per pCi/m3(
H om g
i ble B-1 of Regulator'/ Guide 1.109).
hr e
P
= the, roduct of the largest inhalation dose actor for g
any or n of an infant for each identifi radionuclide in Table 4 of Regulatory Guide 1.109 and the infant 3
inhalation e of 1900 m /yr, in em/yr per pCi/m.
The infant age \\
group and pathway are the most restric-tive.
R
= the dose factor for each id ntified radionuclide into gg sector 9, in mre:n/yr pc
'Ci/m3 from Table 2.4-6.
For
/
sectors with real pat ays ithin 5 miles from the center of the build' g comple.
the values of R have gg been determined sed on these r 1 pathways.
For sectors with no real thways within 5 mile from the center of the buildin complex, the R has been determined assuming g
that all athways exist at the 5-mile dis ance.
D
=
et a aa OS se in sector 0 hom ga ous ehenu n
for the total time period I At., in mrad.
j=1 3
l.
D
= the total gamma air dose in sector 0 for gaseous e fluents I
l OY n
[
for the total time period E At., in nrad.
J j=1 k.
C-C 5-3 D
= the maximum dose from gaseous effluents to the total I
e y
body or an organ of an individual in sector 0 for t e N
n tal time period I at), in mrem.
j=1 h
D
= the umulative dose to the total body or an rgan T r
A from t liquid effluents for the total t'.e period m
l E at n cres.
g, 1=1 th at = the length o the I time period oper which C and g
gg
/
F are averaged or all liquid r esses, in hours.
g i
at) = the length of the ~
time pe.od over which (x/Q);g and Q.. are averaged for a I gaseous releases, in hours For batch rele s, no time period at,.
shall be more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; r ontinuous releases no time period at shall b more tha 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
a e
= the total number of time perio during which liquid m
effluent rele es occur.
s a
= the total
-ber of time period dur g which gaseous effluent release occurs into sector 8.
Qg = the a erage release rate of radionuclide in gaseous ef# uent during time period at. from all s ek or all J
ent release points at the site, in uCi/sec.
Q
= the average release rate of nuclide i i gaseous effluent 1
from all stack or all vent release points at the s te during time periods of I hour for noble gases and 1 w ek for all other radionuclides, in uCi/sec.
\\
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6-I l
~
g = the concentratien of radio'._12de i in liquid effluen l
passing the effluent radiation monitor during time tC N
eriod At from c."y liquid release, in uCi/ml.
W g
}
Ah = th adult ingestion dose factor to the total b y or any 32n t for each identified radionuclide in mres/pCi
]
(from T le A-3 in Regulatory Guide 1.109, listing 169
'A radionucli' des).
F
= the near fiel average dilution facto of C during g
ig any liqui ' if1 nt release.
Defir d as the ratio of the maxit.:n liquid aste finw pa sing the effluent radiation monitor du relea e to the product of the average measured liquid as 6
flow from the site discharge stureture to unrestricted ceiving waters and any appli-cable factor for the mi ing e ect of the discharge structure.
B
= the bioaccumulatio factor in fish or each identified y
radionuclide, i pCi/kgm per pCi/litar (from Table A-8 in Regulatory uide 1.109).
(X/Q)jes = the average atmospheric dispersion factor f the time period a. in secter 0, from all stack release J
oints at 3
the si e, in sec/m.
When 4t. is greater than 1 J
- our, the verage shall be based on observations of wind s eed 3
atmospheric stability taken at least every hour I
during at).
=kL3 es/
"h"#*
~
(
( ~
\\
2 Lg, = 2.0 exp(-h /2r,)/o,r i
s g
The values of L are provided in Table 2.4-5 fo g
y the site boundary and food pathways.
\\
o, = th vertical standard deviation of the plu= for
[.
the a,,plicable atmospheric stability c1 P
\\
(Pasquill Ha Catego.
determined at least hourly, or the dis-ik i
tance r
'-ing the timer period at g
r = the distanc from the center of t#e building complex g
to the recept & fa each secto- 0, in meters, provided in Table 2.4-5.
h = the height of the tack a ve grade, in meters.
3 U = the average wind speh etermined at least hourly,
\\
during time period a. 'n sector 9, at a height of J
10 meters for vent.eleas s and at the upper measure-ment level for s ack releas s, in m/sec.
k = the recircul ion factor accou. ting for spatial and e
temporal y riations in air flow.
For non-continuous release, its value is unity.
For ontinuous relea e its value is determined usin the methodology de ribed in Regulatory Guide 1.111.
(X/Q);gy = the av rage atmospheric dispersion factor for t
(
time per' d at. in sector 0, from all vent release poin s at J
3 e site, in sec/m.
When at. is greater than 1 hou, the L
J average sha.11 be based on observations of wind speed a. d atmospheric stability taken at least every hour during at).
kLg 3y/6 where,
=
I
i i
b
(
av = 2.0/r 42 + h 2 4
0 z v
i-@
- g The values od Lev are Provided in Table 2.4-5 fo the ite boundary and food pathways.
e,r,E e
g de ined above.
N
(
h = the o erage height of all on site buildin s, with y
the li tation that h
[2~e,,inm ers.
y The noble gases to e considered are:
Ar-41 Kr-88 Xe-133 Kr-83m Er-89 Xe-135m Kr-85m L 90 Xe-135 Kr-85 Xe. Im Xe-137 Kr-87 Xe-13 Xe-138 The radioiodines, radioact' e mas rials in particulate form and radionuclides o er than n ble gases to be considered are:
H-3 Zn-65 Cs-134 C-14 Sr-89 Cs-136 Cr-51 Sr-90 r
Cs-137 1,
bh-54 Zr-95 a-140 Fe-59 Sb-124 Ce 141 Co-58 I-131 Othe nuclides Co-60 I-133 with alf-life greate tha 8 dais.
b A copiplete list of 169 radionuclides that could be identi ied i
liquid releases is given in Table A-3 of Regulatory Guide 1.109
C}.
2.4.1 LittlTiru; Lor 4Dillotl5 FOR OPLRAllON Sycc i f ica t ions for Liquid U,-.tc Effluents The annual average concentratien of radioactive materials (exc ludi ng a.
noble gases) in any unrestricted arca, as a resul t of liquid relcases from the site, shall not exceed the values in Column 2 of Table ll of Appendix B to 10CFR20.
For noble gases, the annual average l
concentration shall net exceed 4 x 10-5 uCi/mi.
b.
The maximum concentration of radioactive materials (excluding noble i
gases) in any unrestricted area, as c result of liquid releases from the site, shall not excccd 35 times the va h'es in Column 2 of Table 11 of Appendix 8 te 10CTR20.
For noble gases, the maximum cencentr ation shall not exceed 1.4 x 10-3 pCi/ml.
C -br During release of radioactive material in liquid effluents, the effluent radiation control monitor shall be set to alarm and to initiate the automatic closure /isolatien of each radioactive waste discharge to this monitored effluent line prior to exceeding the limits specified in 2.4.1.b-above.
J
-e, The operability of each automatic isolation system in speci-C fication 2.4.1.6, above, shall be functionally tested quarterly.
e "b.
The design objective annual dose from radioactive materials in liquid effluents to unrestricted areas from weede the site is 3 radi:22 ize
~2 te producin; re :::: :
e-mrem 30 to the total body and te mrem to any organ.
The licensee shall maintain a quarterly cumulative record of calculated dose contributions due to the release of radioactive materials in liquid effluents.
T5: d::: ::ntribution: f r the m
tet21 time peri:d
[itg F n11 ':
2212:12:2d for all radio -
i=1 A
nuclid:: :l tified ir Ep::ificati:n 2.'.2, 2nd : running sum of these total body and any organ doses shall be recorded after each batch release and at least monthly for all con-
(
( tinuous releases using the equations in de# Q b de 1.101(Nenh,) ;
169 m
M7(-
0 O.
2.'
. 10
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1.
2 Y
it-Cu, ? _ _
[,,
g to i g;;;
6 4
4 g
r.4
-her: th: :=: cre lefir.21 ir 2.4.
h
- f. e.
The maxi:: rum quantity of radioactivity contained in any c'
?, ;
liquid radwaste tank that can be discharged directly to the environs without the cor,tinuous autocatic control pro-e visions of Specification 2.4.1.b, shall not exceed a quantity which, if evaluated as a batch release, results in calculated b or 2.4. n e doses exceeding Specifications 2.4.1.6 at any time.
3 96 The equipment installed in the liquid radioactive waste system shall be maintained and shall be operated to process radioactive liquid wastes prior to their discharge when P
the projected cumulative release could result in a calculated dose exceeding one-fourth Specification 2.4.1.e in any C
calendar quarter.
h t.
If the actual release of radioactive caterials in liquid effluents results in a calculated dose exceedir.; one-half Specification 2.4.1.31n any ca1endar quarter, the ticensee shall:
(1) make an investigation to identify the causes for such
- releases, (2) define and initiate a program of action to reduce such C
releases to Specification 2.4.1.e, and 5-(3) report these actions to the NRC in accordance with Specification (0. 0. U.
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L h.
An unplanned or uncontrolled offsite release of radioactive caterials in liquid effluents resulting in a calculated sr a
dose exceeding one-sixth Specification 2.4.1.I$ in a single
'$W event, requires notification.
The notification shall be L
in accordance with Specification C.v.2).
I h
A 2.4.2 LIMITING CONDITIONS FOR OPERATION Specifications for Licuid Waste Sancling and Monitoring Sampling and analysis of liquid radioactive waste shall be a.
performed in accordance with Table 2.4-1.
b.
Prior to taking sa:ples fro a tank from which batch liquid waste releases are to be =ade, at least two tank volumes shall be recirculated to assure that any transferable solids are sampled.
If :du:::, cr: used, :h t= : r'-
ccI r ::
cpplic: te th: entrair.:2 flu;l.
Prict to a batch liquid waste release, the sample taken c.
in Specification 2.4.2.b shall be analyzed for nuclide identification and concentration in accordance with Table 2.4-1 and recorded to demonstrate compliance with r
Specification 2.4.1.
d.
Plant records shall be maintained of the radioactive concen-i tration and volume before dilution of all liquid radioactive waste intended for discharge and the average dilution flow and length of time over which each discharge occurred.
I Sample analysis results and other reports shall be subm' ed e,
(
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in accordance with Specification (0.v.1}. Estimates of the sampling and analytical errors associated with each reported value shall be included.
H The radioactivity in liquid wastes shall be continuously
- .a e.
conitored during release.
Table 2.t-3 indicates the y
location and minimum requirements for continuous monitoring
- a.
instrumentation for liquid waste effluent systems.
(1)
If the effluent radiation centrol monitor on a batch release line is inoperable for a period not to exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, two independent samples shall be taken and analy:ed in accordance with Specification 2.4.2.c and
~
two plant personnel shall independently check valving i
prior to the release.
If the conitoring or controlling instrumentation on a batch release line is inoperable for a period exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the effluent from this release line shall be terminated.
(2)
If the effluent radiation =onitor on a continuous release line raquiring automatic isolation control in Table 2.4-3 is inoperable, the effluent from this y
release line shall be terminated.
(3)
If the effluent radiation moniter on a release line not requiring automatic isolation control in Table 2.4-3 is inoperable, grab samples shall be taken, analy:ed for w
bela.
emedine Ted 'va 7
gross activity 3at f sensitivity of 10 uCi/ml and 3
}
(- (
recorded each eight hours.
If this monitoring instrumen-i tation is inoperable for more than seven days, the effluent lar C%
from this release line shall be terminated.
}
(4)
If the flow rate indicators are inoperable, estimates n:
?4 of the flow based on operating conditions shall be made j
3 and recorded whenever there is flow and each four hours
!au i
thereafter.
If the flow rate indicators are inoperable for more than seven days, the effluent from the release line shall be terminated.
f, All liquid effluent radiation monitors shall be calibrated at least annually by means of a known liquid radioactive source i
and checked at least monthly by means of a known solid radio-active source.
i The gamma spectrum for the know i liquid source shall contain the principal gamma emitter peak; representative of those to bo monitored at the set point alarm level by the effluent radiation monitor. The known solid source ch:11 have an av:::g gam:0 encr;7 ithir ;25'; cf th: averag ;;mma :ncrgy cf th: ::dienuclid:: '.::
- b; pr::ent in the liquid ;t;;;;, ac,d shall have a check position for reproducible calibration of the r
monitor. The known solid source and the sources used to calibrate the known liquid source shall be certified to standards l
of the National Bureau of Standards.
The relationships between f
the known liquid source, the known solid source, and the effluent radiation monitor readings shall be established. Each effluent L
radiation monitor shall have a monthly functional check, and
(, (
shall have an instrument check either prior to making a release or daily for continuous release effluent radiation h
=onitors.
!a
.u Bases:
The release of radioactive materials in liquid effluents ti
~
to unrestricted areas shall not exceed the concentration limits specified in 10 CFR Part 20 n..,
.im. and should be as low as is reasonably achievable in accordance with the requirements of 10 CFR Part 50.34a and 50.36a. These specifications provide reasonable assurance that the resulting average annual dose or dose co=mitment from liquid effluents from e2crTbc 6.y.
rau : nti;; ec.;t e prd:ing racer for any individual in an unrestricted area from 9
all pathways of exposure will not exceed -3 mre.% to the total body 3o or M mrem to any organ. At the same time, these specifications i
permit the flexibility of operation, compatible with considera-tions of health and safety, to assure that the public is provided a dependable source of power even under unusual operating conditions which may temporarily result in releases higher than such numerical guides for design objectives but still within levels that assure that the average population exposure is equivalent to small fractions of doses from natural background radiation.
r i
4, mal Averap Specification 2.4.1.a requires the licensee to limit the concentra-f g
tion of radioactive materials in liquid waste effluents released I
from the site to levels specified in 10 CFR Part 20.106.
I This speci-p fication provides assurance that no member of the general public will
-- s ST -
be exposed :
an; time-to liquid containing radioactive materials in excess of limits considered permissible under the Commission's Regulations.
Specification 2.4.lb limits the quantity of radioactive material released in liquid effluents from the site such that the dose to an individual in any unrestricted area would not exceed 2 mrem whole body or its equivalent in any one hour, consistent 20.105.
with 10CFR Part I
Consistent with the requirements of 10 CFR Part 50, Appendix A, c
General Design Criteria 60 and 64, specificatiens 2.4.1.b.and 2 4.1.he-require operation of suitable equipment to control and monitor the i
t releases of radioactive materials in liquid wastes during any period that these releases are taking place, j
Specification 2.4.1.k-establishes the annual quantity of radio-l 4L active materials in liquid waste effluents from e :e s.lc P radic::tiv:
pr:ducin; re :ter to unrestricted areas, in accordance with Appendix I to 10 CFR Part 50 dose design objectives and calcula-tional procedures based on models and data such that the actual i
exposure of an individual through liquid pathways is unlikely to be substantially underestimated.
p Specification 2.4.1.e establishes an upper limit to the quantity of radioactive material that is allowed to be released without e
the automatic control provisions of Specification 2.4.1.4.
The intent of this specification is to perdit operational flexi-bility when releases will not result in doses exceeding the design objectives of Appendix I to 10 CFR Part 50cr iht dose honds ok t o crg to.ios 9
Specification 2.4.1.4 requires the licensee to maintain and operate the equipment installed in the liquid radwaste treatment systems to sm-w wagae
,.., : w..
- . ;aar,w.are
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reduce the release of radioactive caterials in liquid effluents to as low as is reasonably achievable, consistent with th e require-L ments of 10 CFR Part 50.36a.
Normal use and =aintenance of installedi%
equipment in the liquid radwaste treatment system provides g
['
reasonable assurance that the quanticy released will not e::cced 1
-)
i the design objective.
In order to keep releases of radioactive o
caterials as low as is reasonably achievable, the specification requires operation of equipment whenever the projected cumulat discharge rate could result in doses exceeding one-quarter of the design objectives in Section II.A of Appendix I to 10 CFR P art 50 during any calendar quar:er, The reporting requirements of Specification 2.41 b t
..t are in accordance with Section IV.A of Appendix I to 10 CFR Part 50 and Specifi cation
%)of these Technical Specifications.
t'.
Specification 2.4.1.it provides for reporting spillage or r l e ease events which, while below the limits of 10 CFR Part 20, could result in exposures higher than the design objectives The sampling and monitoring requirements given under Specifi ca-tion 2.4.2 provide assurance that radioactive caterials i n liquid wastes are properly controlled and monitored in confor=
U ance with the requirements of General Design Criteria 60 and 64
}
H TLse requirements provide the data for the licensee and the Commission 4
L to evaluate the plant's perfomance relative to radi
\\
oactive liquid
1
(
17 -
1 1
wastes released to the environment. Reports on the quantities of radioactive materials released in liquid waste effluents are ir t
r4 furnished to the Commission according to Section(5-+:4)of these
[.?
es Technical Specifications.
On the basis of such reports and any y
additional information the Commission may obtain from the licensee or others, the Co=missien may from time to time require the 3
- n, licensee to take such action as the Commission deems appropriate.
1 i
9 I
L
O le -
'i 2.4.3
-LililllNG CONDITIONS FOR OPERATICN l
i Specification for 1
{
Gasecus 'Jaste Effluents The annual average concent ra t ion of radioac t iv a.
unrestricted area, as a result of e r'aterials in any the site, gasecus effluent reicases frcm 8 to 10CFR20.shall not exceed the values in Co 3
Appendix 11 of b.
The max imum concentra t ion of radioac t ive riot restricted area, erials in any un-shall not as a resul t of gaseous releases f rom exceed 35 times the values in Column the site, Appendix B to ICCFR20.
I of Table !! of e
O 1
1 4
I m,
- ===P-**
4
. (
C.-b.
During the release of gaseous wastes from the primary system I
waste gas holdup system, the effluent monitor shall be opera-H ting and set to alarm and to initiate the automatic closure 8 lj-of the waste gas discharge valve prior to exceeding the
[I:
limits specified in 2.4.3.b (1) abt,ve.
c.
During purging of the containment building, the effluent monitor shall be operating i
1 and set to alar = and to initiate the automatic closure of the containment purge release valve prior to exceeding the li=its b
specified in 2.4.3.c..(1) above, cl.er The operability of each automatic isolation valve in Speci-C fication 2.4.3.+ above, shall be functionally tested quarterly.
e.&
The design objective annual air dose from radioactive noble gases l
in gaseous effluents to unrestricted areas in each diEection sector from cach r:dicactive ::::: producing ::cctor 2t the site is 3o mrad for gamma radiation and Go mrad for beta radiation. The licensee shall maintain a quarterly cumulative record of calculated dose contributions to each of the 16 sectors due to the release of radioactive materials in all gaseous effluents. The :::::: 2:p ad=t d:;; :=tributi=s n
fer the total time period [ lt. 23.:11 i: ul ;1;t d f:
- 11 J
j=1
.;hi; ;;;;; id=tifi;d in C,; nifi uti;.; 2. ' '. ;, b =d c, a nd I
A i
a running sum of these doses per sector shall be recorded after l
each batch release and at least weekly for all continuous releases using the equationsf n R9lahr1 Gode. l.lo't @gck M1 i
20 -
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l 15 n
n s.,
e se r,.
r.
us,
~8Y
^^~
y 'i.'1"'j
- j av 'ijv
'^'
- j es *ij s
' ^ '
,ir J=
eg end-
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.n 15 Nh~'
n n
- 9,n
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r..
e,.in, n
e., ins n
~ed
{ 'i
' 'j "jev ~ 1) v
" j e s 'ij s-t;j<
j=1 sher: ::.: t e r--
tre definee i-2.t.
Lj L
$ em The design objective annual dose or dese commitment from radio-iodines, radioactive material in particulate form and radio-nuclides other than noble gases in gaseous effluents to unre-stricted areas in each direction sector from c :h ::di::: tic:
'a;;t.
- f. __;...; :; :: r :: the site is kmremtothetotal
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body or any organ. The licensee shall maintain a quarterly cumulative record of calculated dose contributions to each of i
the 16 sectors due to the release of radioactive materials in all gaseous effluents.
T:: :::::
3;;;nd:c.: d:: ; :: c :..'_ f..e.s n
.en. _. +%-
e_, ~_ _, 9_
- e. :. ~.,,-n. 4_, A T _.. _.
,9.,..s
~.t
- e. n...,.s
.a j=1 r:Aici:dinet, relic ctice
- teri:1 ir particulat: fe rr and radienuclide:
ther than.chl: ;;;;; :d-;ntified in Sp :ifi-A
- ti:n:
2.'.'.2, b 2nd :, and a running sum of these doses per si tor shall be recorded after each batch release and at least weekly for all continuous releases using the equation, 5
i in Reptslery G.,Je i.lo1 (t1 ARCH,197(.)
,5 n
1 r,
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6 e.
ins n
- r.. un n
"at
^^"
"is.'1
~ ~j ['^' " j ev 'ij v
'^' j 9s '1]S 1=1
'=
~
i where the terms are defined in 2.4.E.
b"
- g. f.
The maximum activity to be contained in one waste gas storage tank shall not exceed 3,8 Ato curies (considered as Xe-133).
l 1
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h+
All equi =ent installed in the s2seous radioactive waste P
system shall be maintained. The licensee shall operate
!r t.g equipment installed to reduce the radioactive materials W
in gasecus wastes prior to their discharge when the projected cu=ulative doses could exceed ene-fourth 3
Specification 2.4.3.hinanycalendarquarter,orcould C
exceed one-fourth Specification 2.4.3.e in any calendar quarter.
i i.-ir.
If the actual release of radioactive materials in gaseous effluents results in a calculated dose exceeding one-half Specifications 2.4.3.+6 or -e. above, in any calendar quarter, 4
the licensee shall:
(1) make an investigation to identify the causes for such release rates, (2) define and initiate a program of action to reduce such e
releases to Specification 2.4.3.+ and 2.4.3.Ee, and (3) report these actions to the NRC in accordance with Specification @.0.2) d in An unplanned or uncontrolled release of radioactive materials in gaseous effluents resulting in a calculated dose excessing e
l of one-sixth Specifications 2.4.3.4 or +s above, in a single j
event requires notification. This notification shall be in accordancewithSpecification(Grer2)
K j, Potentially-explosive gas mixtures of hydrogen and oxygen contained in waste processing system components shall be continuously monitored for gas concentration during power
( (
operation. All gas monitors shall have daily sensor checks, monthly functional checks, and quarterly calibra-7 tion.
+p (1) For systems designed to withstand a hydrogen explosion, b
g the gas monitor shall alarm, both locally and in the c
y control room, at a set point of 4*. by volume of hydro-
- ](
gen or oxygen.
If the gas monitor or alarm is inoperable, gas samples shall be taken and analyzed each 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during power operation, and either the instrument should be made operable within two weeks or the licensee shall notify the NRC in accordance with Specification (0. s.2._(Tr) 30-Day Report.
(2) For systems not designed to withstand a hydrogen explosion, the automatic control features to pre-vent potentially-explosive gas mixtures in the system components shall be initiated by either of two independent gas monitors and both shall alarm, locally and in the control room, at the set points of 2% and 45 by volume of hydrogen and/or oxygen, At least one continuously controlling gas monitor r
with alarms shall be in operation whenever the gaseous I
q waste processing system is operating.
1 l
L 4
(
- 23
(
2.4.4 LIMIIING CONDITIONS FOR OPERATION Specifications for Gaseous 'daste Samuling and Monitaring 4
Sampling and analysis of radioactive material in gaseous a.
- .,3
'9 Id effluent, including radioactive materials in particulate foms and radiciodines shall be performed in accordance
- r; with Table 2.4-2.
m iA b.
Noble gas releases to the environment, except from the j
turbine building ventilation exhaust, shall be contin-uously monitored for gross radioactivity and flow according to Table 2.4-4 tihenever these radiation monitors are in-operable, grab samples shall be taken and.inaly:ed daily for gross radioactivity. _ieteorological monitoring instrumen-tationshouldbeoperatedasspecifiedin(~.2.)Ifthese monitors, devices or instruments are inoperable for more than seven days, these releases shall be te minated.
During any planned batch release of radioactive materials in c.
effluent, the gross activity monitor, the iodine collee-tion device, the particulate collection device, and the metecrologicalmonitoringinstrumentationspecifiedin(M) shall be operating.
f.
d.
Plant records shall be maintained and reports of the sampling and analyses results shall be submitted in accor-I dance with Spec.#i ation(h4-1-)
Estimates of the sampling g
and analytical errors associated with each reported value should be included.
I
(
24 -
All gaseous effluent radiation monitors shall be calibrated e.
at least annually by means of a known noble gas radioactive
!P3 source and checked at least weekly by means of a known solid m
radioactive source.
The gamma or beta spectrum for the r;
known noble gas source shall contain at least one of the a
62 principal gamma or beta emitter peaks known to be present 3
16 in the gas stream to be monitored by the effluent radia-tion monitor. The known solid source F01: hav: ar. tvera;;
g'--
er bet 2 :nerrf :ithir
- ': cf th: ;;;r:;: ;; :; cr bet enerm' ^ # *'a
'idae - ~ - ' ' k a
--aca-*
i-
- 'a
~'s strent, --Ashallhaveacheckpositionforreproducibke calibration of the monitor.
The known solid source and the sources used to calibrate the known noble gas source and monitors used for analysis in Specification 2.4.4.a shall be certified to standards of the National Bureau of Standards.
The relationships between che known noble gas source, the known solid source, and the effluent radiation monitor readings shall be established.
Each effluent radiation monitor shall have a monthly func-tional check, and shall have an instrument check or a r
solid source check either prior to making a release or d
t daily for continuous release effluent radiation monitors.
i I
b
i i
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Bases:
The release of radioactive materials in gaseous waste I
effluents to unrestricted areas shall not result in concentration that exceed limits specified in 10 CFR Part 20 et r; time and should be as low as is reasonably achievable in accordance with
{
the requirements of 10 CFR Part 50.34a and 50.36a.
r These speci-i.}
fications provide reasonable assurance that the resulting annual air dose due to ga.ma radiation will not exceed W mrad and that 3o the resulting annual air dose due to beta radiation will not Go exceed M mrad from the gaseous waste effluents from ed ::dic -
nti c:
xt:
- d :in; ::xt n -
the site.
These specifications also provide reasonable assurance that no individual in an unrestricted area will receive an annual dose to the total body greater than @: arem or an annual dose to the skin greater than
%S M mrem from these gaseous effluents, and that the annual dose to an.y organ of an individual from radioiodines and radioactive ma'erial in particulate form will not exceed b mrem from cach ;;dio-t cetic;.:::t pr:ducin; ::xt= ct the site.
At the same time, these specifications permit the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided with a dependable source
~
of power even under unusual operating conditions which may tem-porarily result in releases higher than such numerical guides for design objecti,ves but still within levels that assure that the L
average population exposure is equivalent to small fractions of doses from natural background radiation.
i 26 -
1 1
1 w s.ac4; e Ndrree8Ali" Specification 2.4.3.a limits the release of gaseous waste effluents to the environs so that the Specification 2.4.3.b limits the quantity of radioactive material released in gaseous effluents from the site such that the dose to an individual in any unrestricted area would not exceed 2 mrem whole body or its equivalent in any one hour, consistent with 10CFR Part 20.105.
ugf ul.ou.C l
Tre The equations ut hzel in,these Technical Specifications are provided in Regulatory Guides 1.109 and 1.111.
Since many reactors do not have provisions for instantaneous radionuclide identification at all batch and continuous release points for radioactive materials in gaseous effluents, and since the collection process required to obtain adequate sensitivity for the identification of particulates and radio-iodine is a function of time, these Technical Specifications permit the accumulation of atmospheric dispersion, factors over time periods consistent with those utilized in the collection of effluent data. For batch releases, the average X/Q corres-ponding to release rate-h-during each time period 44.
not J
greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> shall be determined after each batch for each sector from the average wind speed and atmospheric stability
( {
class (Pasquill Category) measured during each time period 64,.
J For continuous releases, the average X/Q shall be determined i,
m for each time period a:- not greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
This
{#
J 7.4 average X/Q is derived from the X/Q values calculated hourly 3
or more frequently, and is based on hourly or more frequent
_!j observations of wind speed and atmospheric stability class 2
gg (Pasquill Category), and is equal to the sum of the individual x/Q determinations divided by the total number of determina-i tions during eeenh time period e4..
These sector-dependent doses ewc 3
are cumulated and recorded to show compliance with the require-ments of 10 CFR Part 20 and design objectives of Appendix I to 10 CFR Part 50.
The licensee may employ a computeri:ed system to measure, determine, cumulate, and record the sector doses to show compliance with the Commissions Regulations.
Th'e release rate Specifications for radioicdine, radioactive material in particulate form and radionuclides other than noble gases are dependent on existing radionuclide pa'thways to man.
The pathways which were examined for these Specifications are
- 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consump-tion by man, 3) deposition onto grassy areas where milch animals h
and meat producing animals gra:e with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. Methods for estimating doses :: th th :id via these pathways are described in Regulatory Guide 1.109.
l
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{ Specifi:: tier 2.* '.1:C limit: th: : 1;;;; ::: :f reli:icdinen, radi:::t i'.
- crial ir p2rti:u12!
form rn! rrlianuclife: ether e
tS' ncbie ;2 c to -k1 I.%
the errerpendin; t'"reid >:re r2te Ej 2be"e b2ck;rrund 1-infect 11 the irhal:ti r p2t' 1; i:
[s ler th:2 II*n tre '; r 15^ :itz b:r.itr;, ir ::rpli1nze 9A a
m w44p :32
,e in cro o,r-on__
[d L
Consistent with the requirements of 10 CFR Part 50, Appendix A, Design Criteria 60 and 64 Specifications 2.4.3.4 and 2.4. 3.d C
e-require that suitable equipment to conitor and control the radioactivo gas-eous releases are operating during any period these releases are taking place.
Specification 2.4.3.e e-establishes the design objectives for radioactive noble gases in waste effluents from each radioactive waste producing reactor to unrestricted areas.
Specification c
2.4.3.e-establishes the design objective for radiciodines, radioactive materials in particulate form and nuclides other than ne s.\\ c noble gases in releases from ecch u. nit to unrestricted areas.
These Specifications are in accordance with Appendix I to 10 CFR Part 50 dose design objectives and calculational procedures I
g based on models and data such that the annual exposure of an l<
i individual through gaseous and airborne pathways is unlikely l
to be substantially underestimated.
L..
t
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4 I
Specification 2.4.3.%- limits the maximu= quantity of radioactive gas that can be contained in a waste gas storage tank.
The calcu-Wr lation of this quantity sh-dA assu=esinstantaneous ground release, lQ Qq a X/Q based on 5 percent ceteorology, an average gross ene.
ly pema rgy of F4 3
c.cws Ortt Mev per disintegration (considering Xe-133 to be the princi-
+4 n
pal emitter) and exposure occurring at the minimum site boundary
(
radius using a seci-infinite cloud model.
The calculated quantity vill li=it the offsite dose above background to 0.5 rem or less,
[
consistent with Co:21ssion guidelines, h
Specification 2.4.3.s requires that t'he licensee maintain and operate the equipmen* 'nstalled in the vent, purge, exhaust, off-gas and ventilation systems to reduce the release of radioactive materials in gaseous waste effluents to as low as is reasonably achievable, consistent with the requirements of 10 CFR Part 50,.34a and 50.36a.
Normal use and maintenance of installed equipment in the gaseous waste system provides reasonable assurance that the quantity released will not exceed the design objectives.
In order to keep releases of radioactive materials as low as is reasonably achievable, the specification requires operation of equipment whenever the projected cumulative discharge i
rate will exceed one-fourth the dose design objectives of Appendix l
I to 10 CFR Part 50 during any calendar quarter.
The reporting reqairenents of Specification 2.4.3.h are in L
b accordance with Section IV.A of Appendix I to 10 CFR Part 50 and Specification h.. )of these Technical Specifications.
(
i
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l a
Specification 2.4.3.i-provides for reporting release event s which, while below the limits of 10 CFR Part 20, could result in ex 4
posures higher than the design objectives.
]
h g
Specification 2.4.3.f provides for maintaining instrumentation 9'e.j on systems handling potentially-explosive gas mixtures of y
The sampling and menitoring requirements given under Specificatio 2.4.4 provide assurance that radioactive materials released in gaseous effluents are properly controlled and monitored in conformance with the requirements of General Design Criteria 60 a 64 These requirements provide the data for the licensee and the Commission to evaluate the plant's performance relative to radioactive materials released in gaseous effluents.Reports on the quantities of radioactive materials released in g aseous effluents are furnished to the Commission according to Section M)of these Technical Specifications.
On the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Commission may from time to ti me require the licenses to take such action as the Commission deem s
I appropriate.
Specification 2.4.4.b excludes monitoring the turbine building s
ventilation exhaust for PWR reactors since this release is expected to be a negligible release point.
( (
l 2.4.5 LDfITING CONDITIONS FOR OPERATION Specifications for Solid Waste Handling and Discosal rM Tne total curie quantity and principal radionuclide co=po-
!sj a.
sition shall be deterrined by ceasurement or estimates for 3
v...
4 all radioactive solid waste shipped offsite.
b.
Reports of the radioactive solid waste shipments, volumes,
- L principal radionuclides, and total curie quantity, shall be i
submitted in accordance with Section @ W )
Bases:
The require =ents for solid radioactive waste handling and disposal given under Specification 2.4.5 provide assurance that solid radioactive caterials stored at the plant and shipped off-site are packaged in confor:2nce with 10 CFR Part 20, 10 CFR Part 71, and 49 CFR Parts 170-173.
(-
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1 TABLE 2.4-1 1
RADICACTIVE LICulo WASTE SAMPLING AND ANALYSIS tD" i33 iM Li id hra Samph.ng and Analysis Detectable
?;
Frequency Typs of Activity Analysis Concentrations 7
( Ci/mila A.
Monitor Tank Batch Releases Each Batch Principal Gamma Emittars l 5 x 10-7b in W
One Batch / Month Dissolved Gases
- 10-5 1
2.,.
. t; 7__;_
,,p
. g_ a Monthly Composite:
Gross c 10-7 l
m____.
l
,,.a g,
.r,g:,
% i, % _ %,ur. w I m + m.
in-6
)
_. -. m e. q.._.,
l y,;,,,.;-,e %,e
- m c
- , e-7b w
i
._ m
.s r
C C c..,.. _ _.
C..
- d ' - *
'. : A o,
u.
,. n..._,
W 4W C....
j
-40 2 C=:/ C2-,.:.
O.- J . Oc 0 3 Cm
^-?
a The detectability limits for activity analysis are based on the technical feasibility and on the potential sig the environment of the quantities released. For scme nuclides, lower detection limits may be readily achievable an when nuclides are measured below the stated limits, they should also be reported.
b For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near th sensitivity limits when other nuclides are present in the sample in much greater concentrations. Under these circ *tm.
stances. it will be more appropriate to calculate the concentrations of such radionuclides using measured ratios with those radionuclides which are routinely identified and measured.
c A composite sample is one P - "" *he ;u:- ^ c' "i d ::- :':2 I: ; ::;:* ^- ' *: - ---"; c' ";_ M....
J.._.. c r2 !.i which the method of sampling employed result:in a specimen which is representative of the liquids
- r released.
d,q
_, _,, a., m s,,.. - m.
.._:c.
--n_.
_._..u_,,_r..:_&.,
q. t.--_--
--, e _: c -.:_ _ e g,
(
v.
..... m.
-g...
I r,
T L.,......._..
,c' *'- - --,-
- * * - -d-~'-~'~"^'^'"*'-';"a
[
- "a -'
- i ' "^"id^"'"-"
- '- - 'd 5
": ::d H ; :;:
^t : t: : :: : ;' ";
"Yes 1
c ' : c ' "- '- - " - - - '. ; :g" : ~ : ', _ ^ ^., 9 ' : ; ' : _ : ' -
o__-
_t-a j s_ _.u7___._tt. _ : yj ? - g _ f.. _. '.
- _ _-. y 3 - g
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gu e'-
Y TABLE 2.4-2
- d RADIOACTIVE GASEOUS WASTE SAMPLING AfJO ANALYSIS h
Gaseous Source Sampling and Analysis t
Frequency Ty e of Activity Analysis Detectable Concentrations luci/ml)*
A.
Waste Gas Cecay Tank Each rank Batch rleieases Principal Gamma Emitters 104b
~4 f
10-6 A
H-3 B.
Containment Purge Each Purgs8 Batch Releases Principal Gamma Emitters 10 4 H-3 10-6 C.
Condanser Air Ejector Monthly (Gas Sampiele Principal Gamma Emit en l 10-4b 1
Continuous Releases H-3 10-6 0.
Other Environmental Monthly (Gas Samples)*
Principal Gamma Emitters 10-4b Continuous Releases H-3 10-6 Weemly (Charcoal Samp!er*
l-131 10-12 Monthly (Charcoal Samole)*-
I 133.1-135 10-10 Weekly (ParticulatesP Principal Gamma Emitters (Ba-La-140,1-131 O thers) 10-11 Monthly Composits*
(Particulates)
Gross a 10-11 Quarterly Compositd*
Sr 39, Sr-90 10-11 (Particulates)
The above detectability limits for activity analysis are based on technical feasibility and on the potential significance in the environment of the quantities released. For some nuclides. lower detection limits may be readily achievable, and when nuclides are measured below the stated limits, they should also be reported.
b For certain mixtures of gamma emitters,it may not be possible to measure radionuclides at levels near their sensitiv-ity limits when other nuclides are present in the sample at much higher levels. Under these circumstances, it will be more appropriate to calculate the levels of such radionuclides using observed ratios with those radionuclides which are measurable, c
Analyses shall also be performed following each refueling, startup, or similar operational occurrence which could alter the mixture of radionuclides, d
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TABLE 2.4-5 VALUES OF Lgv AND Lgs,IN METERS-2 FOR PRES 3URIZED WATER REACTORS ent Sits Boundary Lgy. m-2 Food Pathway Lgy, m.2 [
Distance Pascuill Category Distance Pasquilt Category [
g re A
B C
D E
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g, rg A
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i TABLE 2,4 G DOSE FACTOR ft,);,IrJ mrem /yr PER pCi/m3 FOR PRESSunt2ED WATER REACTORS Sector,0 N
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5.6.2 NONR0fJrINE REPORTS c.
Nonroutine Radioactive Effluent Recorts Im M
(1) Liquid Radioactive Wastes Report.
If the cumulative dose W
Q due to releases of radioactive =aterials in liquid effluents f,
S e
exceeds one-half Specification 2.4.1.d-during any calendar bj it quarter, the licensee shall =ake an investigation to identify lk the causes of such releases and define and initiate a program of action to reduce the releases to correspc d with the dose design objective levels of Appendix I to 10 CFR Part 50.
A written report of these actions ~ shall be submitted to the NRC within 30 days from the end of the quarter during which the release occurred.
(2) Gaseous Radioactive Wastes Report.
Should the conditions (a) or (b) listed below exist, the licensee shall make an investigation to identify the causes of the releases and define and initiate a program of action to reduce the releases i
to correspond with the dose design objective levels of l
Appendix I to 10 CFR Part 50.
A written report of these actions shall be subnitted to the NRC within 30 days from r
the end of the quarter during which the releases occurred j
{
(a)
If the cumulative dose due to releases of noble gases during any calendar quarter exceeds one-half Specification 2.4.3.h.
j b*
1 l
33 -
e (b)
If the cu=ulative dose due to releases of all radio-I
\\
e iodines, radioactive caterials in particulate fom T
m.<
and nuclides other than noble gases discharged during N
R any calendar quarter exceeds one-half Specification g
c 2.4.3.4.
'y H;;
(3) Unplanned or Uncontrolled Release Report. Any unplanned or uncontrolled offsite release of radioactive materials that results in exceeding one-sixth of the annual dose design objectives for radioactive =aterials in liquid or gaseous effluents requires notification. This notification cust be made by a written report within 30 days to the NRC.
The report shall describe the event, identify the causes of the unplanned or uncontrolled release and report actions taken to prevent recurrence.
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