ML19316A059
| ML19316A059 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/07/1976 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19316A057 | List: |
| References | |
| NUDOCS 7911210629 | |
| Download: ML19316A059 (22) | |
Text
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FORWARD The attached draf t model technical specifications are still under internal NRC review.
This review may result in further changes :o these specifications.
Such changes may affect:
1.
Implementation of 10 CFR 50.36a and Appendix I with respect to usage of radwaste equipment, 2.
Implementation of 10 CFR 20 wi:h respec: to gaseous releases, 3.
Parameters used to derive R including deposition f actor g
and controlling pathway determination, 4
Sa=pling and analysis of effluents, 5.
Revision of specific wording to assure the enforceability of certain provisions, 6.
Further definition of terms including batch and continuous releases, and 7.
Revision of equations in see: ion 2.4.3. a. (1) and 2.4.3.d to include call stacks.
The equations now in 'these sections only apply to vent releases (less than 50 meters).
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1 791121062f
DRAFT MODEL TECHNICAL SPECIFICATIONS FOR PRESSURIZED WATER REACTORS Docket Nu=ber(s) 2.4 RADI0 ACTIVE EFFLLTITS Introduction Objective:
To define the limits and conditions for the controlled release of radioactive materials in liquid and gaseous effluents to the environs to ensure that these releases are as low as is reasonably achievable in confor=ance with 10 CFR Parts 50.34a and 50.36a, and to ensure"that these releases result in concentrations of radioactive materials in liquid :nd gaseous effluents released to unrestricted areas are within the lisits specified in 10 CFR Part 20.
To ensure that the releases of radioactive saterial above back-ground to unrestricted areas are as Icw as is reasonably achievable, l
the following design objectives as defined in. Appendix I to 10 CFR
~
Part 50.36a apply:
A.
The annual total quantity of all radicactive material above background that may be released from each light-water-cooled nuclear power reactor to unrestricted areas should not result in an annual dose or dose commitment from liquid effluents for any individual in an unrestricted area from all pathways of exposure in excess of 3 milliress to the total body er 10 sillirens to any organ.
1 1 - refers to time period for lia,uid releases.
. v - refers to all releases per site.
These are non elevated releases as defined in Regulatory Guide 1.111.
s - refers to all stack releases per site. These are elevated releases as defined in Regulatory Guide 1.111.
S - refers to beta emission of a radionuclide.
y - refers to gamma emission of a radionuclide.
T-refers to the total body or an organ.
9 - refers to direction sector.
The direction sectors for the
-ites are defined as the sixteen 22-h degree sectors of a circle with the apex at the center of the building complex.
The nordisector shall be that sector with true north as a centerline.
Notations
= the total body dose factor due to ga=ma emissions for Ki 3
each identified radionuclide, in mrem /yr per pCi/m (from Table B-1 of Regulatory Guide 1.109).
= the skin dose factor due to beta emissions for each Li
.i dentified radionuclide, in arem/yr per pCi/m (from Table 5-1 of Regulatory Guide 1.109).
emissiens for each Mi
= the air dose factor due to go-a identified radionuclide, in mrad /yr per pCi/m3 (from Table B-1 of Regulatory Guide 1.109).
D
= the maximum dose from gaseous effluents to the total g
body or an organ of an individual in sector 9 for the n
total time period I at., in mrem.
3 j=1 D
= the cumulative dose to the Octal body or an organ -
T from the liquid effluents for the total time period m
g, in mrem.
I at L=1
.h at = the length cf the a time period over which C.L and L
L F are averaged for all liquid releases, in hours.
g
= the length of the j 'h time period over which (x/Q)33 t
atj s
and Q.. are averaged for all gaseous releases, in
~
13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.
For batch releases, no time period at. shall J
be more than I hour; for continuous releases no time period at. shall be more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
]
= the total number of time period during which liquid i
m effluent releases occur.
= the total number of time period during which gaseous n
effluent release occurs into sector 9.
Q ). = the average release rate of radionuclide i in gaseous 4-effluent during time period at. from all stack or all J
vent release points at the site, in uCi/sec.
Q
= the average release rate of nuclide i in gaseous effluent i
from all stack or all vent release points at the site during time periods of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for noble gases and I week for all other radionuclides, in uCi/sec.
s
.. 2 2
L, = 2.0 exp (-h,/ 20,) /c,r g
g The valuer of L, are provided in Table 2.4-5 for g
the site boundary and food pathways.
= the vertical standard deviation of the plume for e
s the applicable a:=ospheric stability class (Pasquill Category) determined at least hourly, for the dis-during the timer period at).
tance rg r = the distance from the center of the building ce= plex g
to the receptor for each sector 9, in meters, provided in Table 2.4-5.
h = the height of the stack above grade, in =eters, s
6 = the average wind speed deter =ined at least hourly, during time period at) in sector 9, at a height of 10 meters for vent releases and at the upper =easure-ment level for stack releases, in s/sec.
k = the recirculation fact: ac::un:ing for spatial and g
te= poral variations in air flew.
For non-c:ntinuous releases, its value is uni:y. For continuous release its value is determined using the methedclogy described in Regula:Ory Guide 1.111.
(x/Q)39y the average atmospheric dispersion factor for the ti=e
=
period at. in sec:c 9, from all vent release points a:
J the site, in sec/=. When at. is grea:er than I hour, the J
average shall be based on observati:ns of wind speed and a:=ospheric stability taken 2: least every hcur during it).
kLg gy/G where,
=
i
. 2.4.1 LIM *T;NG CONDITIONS FOR OPERATION Specifications for Licuid Waste Effluents 2.
The concen: ration of radioactive =a:erials released in liquid effluents to unrestricted areas fres all reactors at the site shall not exceed the values specified in 10 CFR Part 20.106.
b.
During release of radicactive =aterial in liquid effluents, the effluen: radiation control =eni:cr shall be set to alarm and to initiate the au::=a:i: closure / isolation of each radicactive waste discharge to this seni:cred effluen: line prior to exceeding the limits specified in 2.4.1.2 above.
c.
The operability of each aut::ati: isclation syste= in speci-fication 2.4.1.5, above, shall be functi:nally tested quarterly.
d.
The design obj ective annual dose fr:= radicactive =aterials in liquid effluen s to unrestricted areas from each radioactive waste producing reactor at the site is 3 mre=
to the total body and 10 = rem to any organ.
The licensee shall =aintain a cuarterly cumulative recc -
of calcula:ed dose contributions due to the release of radioactive materials in liquid effluents.
The dose contributions for the m
total time period I at shall he calculated for all radio-1 1=1 nuclid,es d'*a-434*>
- n Specification 2.2.2, and a running su= of these total bcdy and any organ d:ses shall be rec rded after each ba::h release and 2: 1els: =cn:hly for all con-1
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h.
An unplan materials dose exces event, req in accordar 2.4.2 LIMITING CON t
Soecifications f4 a.
Sampling and perfor=ed in b.
Prior to takit waste releasee shallberecire$
are sampled.
N applies to the (
3 Prior to c.
a ba:ck in Specification.
identifica:icn as 2.4-1 and recor Specification 2.J.
d.
Plant records s tration and volume waste intended fo and length of time 6 Sample analysis resu
. recorded each eight hours.
If this sonitoring instrumen-tation is inoperable for more than seven days, the effluent from this release line shall be terminated.
(4)
If the flow rate indicators arc inoperable, estimates of the flow based on operating conditions shall be made and recorded whenever there is flow and each four hours 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 and checked at least =onthly by means of a known solid radio-active source. The ga:ma spectrum for the known liquid source shall contain the principal ga=ma emitter peaks representative of those to be monitored at the set point alarm level by the effluent radiation =enitor.
The known solid source shall have an average gs=ma energy within +25% of the average gamma energy of the radionuclides known to be present in the liquid stream, and shall have a check position for reproducible calibration of the monitor.
The known solid source and the sources used to calibrate the known liquid source shall be certified to standards of the National Bureau of Standards.
The relationships between the known liquid source, the kh)wn solid source, and the effluent radiation =enitor readings shall be established.
Each effluent radiation =onitor shall have a montnly functional check, and
'l i
. i be exposed at any time to liquid containing radioactive materials in excess of limits considered permissible under the Cc= mission's Regulations.
Consistent with the require =ents of 10 CFR Par: 50, Appendix A, General Design Criteria 60 and 64, Specifications 2.4.1.b and 2.4.1.c require operation of suitable equip =en: :o con:rol and =enitor :he 1
releases of radioactive materials in liquid wastes during any period tha: these releases are taking place.
Specification 2.4.1.d establishes the annual quantity of radio-active materials in liquid waste effluents from each radioactive waste producing reactor 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 tha: the actual i
exposure of an individual through liquid pathways is unlikely to be substantially underestimated.
Specifica:icn 2.4.1.e establishes an upper li=i: to :he quanti:7 of radioactive asterial that is allcwed to be released without the autc=atic control provisions of Specifica icn 2.4.1.5.
The intent of this specification is : per=i: cperational flexi-bility when releases will not result in deses exceeding the design objectives of Appendix I to 10 CFR Par: 50.
Specification 2.4.1.f requires the licensee to maintain and opera:e the equipment installed in :he liquid radwaste reatment syste=s to
4 wastes released to the environment.
Reports on the quantities of radioactive materials released in liquid waste effluents are furnished to the Commission according to Section 5.6.1 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 time require the licens4 to take such action as the Commission deems appropriate.
+
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19 b.
During the release of gaseous wastes from the primary, system waste gas holdup system, the effluen: =enitor shall be opera-ting and set to alar = and to initia:e the automatic closure of the waste gas discharge valve prior to exceeding the limits specified in 2.4.3.a. (1) above.
During purging of the containment building, the effluent nonitor shall be operating and set to alar = and to initiate the automatic closure of the containment purge release valve prior to exceeding the limits specified in 2.4.3.a. (1) above.
c.
The operability of each au:c=atic isolation valve in Speci-fication 2.4.3.b above, shall be fune:icnally tested quarterly.
d.
The design objective annual air dose from radioactive noble gases in gaseous effluents to unrestricted areas in each direction sector from each radioactive waste producing reactor at the site is srad for ga==a radiatica and
- ad for beta radiation.
The licensee shall naintain a quarterly cu=ulative record of calculated dose contributions to each of the 16 sectors due to the release of radioactive r.aterials in all gaseous effluents.
The sector dependen: dose contributions n
for the total time pericd [ 1. shall be calculated for all 3
j=1 ncble gases identified in Specifications 2.2.4.2, b and c, and a running sum of these deses per sector shall be recorded after each batch release and a: leas: weekly for all continuous releases using the equaticns, i
_ 21 -
g.
All equipment installed in the gaseous radioactive waste system shall be maintained.
The licensee shall operate equipment installed to reduce the radioactive materials in gaseous wastes prior to their discharge when the projected cumulative doses could exceed one-fourth Specification 2.4.3.d in any calendar quarter, or could exceed one-fourth Specification 2.4.3.e in any calendar quarter.
I h.
If the actual release of radioactive =aterials in gaseous effluents results in a calculated dose exceedin}'one-half Specifications 2.4.3.d or e above, in any calendar quarrer, 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 releases to Specification 2.4.3.d and 2.4.3.e, and (3) report these actions to the NRC in accordance with Specification 5.6.2.
i.
An unplanned or uncontrolled release of radioactive =aterials in gaseous effluents resulting in a calculated dose excessing of one-sixth Specifications 2.4.3.d or e above, in a single i
event requires notification.
This notifica:icn shall be in accordance with Specifica icn 5.6.2.
j.
Potentially-explosive gas mixtures of hydrogen and oxygen contained in waste processing system components shall be continuously =enitored for gas concentration during power
2.4.4 LIMITING CONDITIONS FOR OPERATICN Specifications for Gaseous Waste Sa= cling and Monitoring a.
Sa=pling and analysis of radioactive =aterial in gaseous affluent, including radicactive materials in particulate forms and radiciodines shall be perfor=ed in accordance with Tabi s 2.4-2.
b.
Noble gas releases to the environ =ent, except from the turbine building ventilation exhaust, shall be contin-uously =enitored for gross radioactivity and flew according to Table 2.4-4.
Whenever these radiation =enitors are in-operable, grab sa=ples shall be taken and analy:ed daily for gross radioactivity.
Meteorological =cnitoring instrumen-tation shculd kg operated as specified in 3.2.
If these l
=enitors, devices or instruments are inoperable for = ore than seven days, these releases shall be terminated.
c.
During any planned batch release of radioactive =aterials in effluent, the gross activity =cnitor, the iodine collec-tion device, the particulate collectica device, and the
=etecrological conitoring instru=entation specified in 3.2 shall be operating.
d.
Plant records shall be maintained and repor s of the sa=pling and analyses results shall be sub=i::ed in accor-dance with Spec 'i ation 5.6.1.
Esti=a:es of the sa=pling and analytical er:crs associated with each reported value should be included.
Bases:
The release of radioactive =aterials in gaseous waste effluents to unrestricted areas shall not result in concentrations that exceed li=its specified in 10 CFR Part 20 a any time and should be as low as is reasonably achievable in accordance with the require =ents of 10 CFR Part 50.34a and 50.36a.
These speci-fications provide reasonable assurance that the resulting annual air dose due to ga==a radiation will not exceed 10 mrad and that the resulting annual air dose due to beta radiation will not exceed 20 = rad frem the gaseous waste effluents frem each radio-active waste producing reactor at 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 5 = rem or an annual dose to the skin greater than 15 srem from these gasecus effluents, and that the annual dose to any organ of an individual from radioicdines and radioactive material in particulate form will no: exceed 15 = rem from each radio-active waste producing reactor at the site.
A: the sa=e ti=e, these specifica: ions permi: the flexibility of operation, ce=patible 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 =ay tes-porarily result in releases higher than such numerical guides for design objectives but still within levels that assure tha: the average population exposure is equivalent :s small fractions of doses from natural background radiation.
class (pasquill Category) measured during each time period a:).
For continuous releases, the average X/Q shall be determined for each time period at. not greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
This 3
average X/Q is derived from the x/Q values calculated hourly or more frequently, and is based on hourly or more frecuen:
observations of wind speed and at=ospheric stability class (Pasquill Category), and is equal to the su= of the individual x/Q deter =inations divided by the total nu=ber of determina-tions during ecah ti=e peried at..
Thes.e sector-dependen: doses J
are cumulated and recorded to show c =pliance with the require-
=ents of 10 CFR Part 20 and design objectives of Appendix I to 10 CFR Part 50.
The licensee =av. e=r.loy a c:=puteri:ed system to measure, determine, cu=tlate, and record the sector doses to show compliance with the Cc==issions Regula:icns.
The release rate Specificati:ns for radioicdine, radicactive material in particulate for= and radienuclides other than noble gases are dependent on existing radienuclide pa:hways :o =an.
The pathways which were exa=ined for these Specificati:ns are
- 1) individual inhalation of airborne radionuclides, 2) deposition of radienuclides onto green leafy vege:a:icn with subsecuen: consu=p-tien by =an, 3) deposition en:o rassy areas where cilch ani=als s
and = eat producing ani=als gr2:e with consu=ption of the milk and sea: by =an, and 4) depcsi:icn en the grcund with subsec.uen:
exposure of an.
Methods f:: esti=ating doses :: the :hyroid via these pathways are described in Regula:: y Guide 1.10c.
6 4
29 -
o Specifica icn 2.4.3.f limits the maximu= quantity of radioactive gas that can be contained in a waste gas storage tank.
The calcu-lation of this quantity shculd assume instantaneous ground release, a X/Q based on 5 percent =eteorcicgy, an average gross energy of 0.19 Mev per disintegration (censidering Xe-133 to be the princi-pal emitter) and exposure occurring at the nini=u= site boundary radius using a semi-infinite cicud medel.
The calculated quantity
)
will lisi: the offsite dose above background to 0.5 rem or less, consistent with Cc==ission guidelines.
Specification 2.4.3.g requires tha: the licensee maintain and operate the ec,uipment installed in the vent, purge, exhaust, off-gas and ventilatien systems to reduce the release of radioactive materials in gaseous waste effluents to as icw as is reasonably achievable, consisten: with the requirements of 10 CFR Par:
50.34a and 50.3ea.
Ner=al use and =aintenance of installed equipment in the gasecus waste system prevides reasonable as:urance :ha: the quantity released will ne: exceed the design objectives.
In crder to keep releases of radicactive caterials as icw as i< reascnably achievable, the specifica:icn recuires operation of ecui;=ent whenever the projected cumulative discharge
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2.4.S LIMITING CONDITICNS FOR CPERATICN Scecificatiens for Solid Naste Handling and Disposal The total curie quantity Ir.d principal radienuclide co=po-a.
sition shall be determined by =easurement or esti=ates for all radioactive solid waste shipped offsite, b.
Reports of the radicactive solid waste ship =ents, velu=es, principal radienuclides, and Octal curie c.uantity, shall be submitted in acccrdance with Secti:n 5.6.1.
Bases:
The require =ents fer solid radioactive waste handling and disposal given under Specifica:icn 2.4.5 prcvide assurance that solid radioactive naterials s:cred a: the plant and shipped off-site are packaged in confer:ance with 10 CFR Part 20, 10 CFR Part 71, and 49 CFR Parts 170-173.
.. i i
TABLE 2 4-1 RADICACTIVE LICUID WASTE SAMPLING AND ANALYSIS Detectable Sernpi ng and Analysis Type of Activity Analysis Concentrations Liquid Source Frequency (uci/mi)*
l Principal Gamma Emitters f 5 x 10-7b A.
Monitor Tank Batch Releases Each Batch d
One Batch / Month l Dissolved Gases
- l 10-5 Weekly Ccmposited l
Ba-La-140,1-131 l
10-8 l
10-5 H-3 Monthly Composite 8 Gross c l
10-7 l
Sr-89, St-90 l
5 x 10-4 c
Cuarterly Composate B.
Primary Coolant l Tech. Spec. - Accendix Ad l Radioicdines f
10-4 C.
Steam Generater B!cwdewn Principal Gamma Emitters l 5 x 10-7b f
Weekly Sa-La-140,1-131 l
10-a l Cissolved Gases
- l 10-5 One SampleeMonth l
10-5 H -3 f
Mony Composite l
10-7 Gross c Quarterly Comoosite!
Sr-89, Sr-90 5 x 10-a a The detectability limits for activity analysis are based on the tecnnical 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 snould also be reported.
b For certain mixtures of pmma emitters,it may not be possible to measure radionuclides in cencentrations near their sensitivity limits when other nuclides are present in the sample in much graater concentrat: ens. Under these circum-stances,it will be mere accropriate to calculate the cencentrations of such racionuctides using measured ratics with those radienuclides wnich are reutinely identified and measured.
A composite sample is one in wnich the quantity of ficuid sampled is proportional to the cuantity of liquid waste C
oisc'iarged and in wnien the methcd of sampling empioyed results in a specimen whicn is recresentative of the fiquids reftasad.
Th.t power level and cleanuo cr purification flow rate at 'he sample time shall also be rescried. Scecification 5.6.1.
d For dissolved nocie gases in water, assume a MPC of 4 x 10-5 aci/ml of water.
' To be representative of the average quantities and concentrations of radicactive materials in liquid effluents. samoies should be collected in precortion to the rate of flew of the effluent stream. Prior to analyses, att samcles taken for the composite should be ther0ughly mixed in order for the composite sample to be representative of the average affluent release.
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3 1 yE
.#. u 1
= s a m U
= " ] m -
=*
N O
.3 ih J
- 5 dj3 31 4 :}
5m$
=2
- =. = -
- -3
=
a u
=
- a "O
3 1 3.*5 5
E ^.?.2
-=
-=
-4a E
u
=
- i 3s2 s
c =. =. = 2 - (~4 3 3 5
=
- =
5
=
2 2-S m:
.1 s -
1
= 3T g
=
l 3
=2
...j
,==
=
3
- 4
=
1
=
=
=.
=
r
.= -
3 =.==
yu E 2 u >
=
a=-
=
. =
e
< =-
qi d 2 =,.=
3 x-
a
- - ~ = -
g =
w
=
W d : = = -
5
$ d
[.
- um
- h -
x 4
.=
u
- =
9 O
[ l ~W M 3 D J'b v3k/&lqL
TABLE 2.4-5 VALUES OF Lgy AND Lgs,IN METERS.2 FOR PRESSURIZED WATER REACTORS l
Site Boundary L y, m 2 l
Food Patnway Lgy, m.2 l
Vent 9
l Pascuill Category l Distance Pascuill Category Distance S.c:ce lG 8
rg A
B C
O E
F G
rg A
B C
D E
F 1.
N I
l l
l l
l l
l l
l l
l l
l l
- 2. NN E i i
i l
l 1
l l
l l
l l
l 1
I i
- 3. NE I
I i
i I
i l
I i
l I
i i
i l
I 4.
ENE I I
(
l 1
i l
i I
i l
i i
i i
I 5.
E l
l l
1 l
l 1
l l
t I
i l
l I
I 6.
ESE
.l l
l l
l l
l t
l l
l l
l l
l
- 7. SE I
i 1
1 4
1 1
1 I
I I
I I
I I
S.
SSE I
l l
I i
1 1
1 1
I i
l i
l I
9.
S l
l l
l l
I l
l l
l l
l l
l I
i
- 10. SSW l i
i i
i i
i i
i l
I i
i i
1
- 11. SW l
I i
i i
l I
i i
i t
i I
I I
i
- 12. WSW l l
l 1
l l
l 1
l l
i i
i i
l I
i
- 13. W l
I i
I i
i i
i l
l i
I i
l i
I 14 WNW l 1
l l
1 l
l l
l l
l l
1 i
l l
- 15. NW i
l I
i l
i l
1 l
l 1
4 I
l l
- 16. NNW 4 I
I I
I I
i l
1 l
l l
l l
1 1
1 l
Site acundary Lys, m 2 l
Feed Pathway L s, m.2 9
Stack i
Cistance Piscuill Category l Distance l Pasquilt Category 3
rg A
B C
D E
F G
rg A
B C
D E
F G
1.
N l
l l
l l
1 l
l
\\
l l
l l
l l
- 2. NNE I I
I i
i I
I I
I I
l 6
I I
l l
3.
NE I
I I
i i
i l
i i
l i
I I
I l
l 4 ENE I i
i i
i l
i l
I I
i I
I i
i I
j 5.
E I
I I
I I
I I
I I
l i
I I
i i
1 6.
ESE 6
i i
i i
l i
i i
i l
i i
1 I
i 7.
SE i
1 I
i l
i i
I i
t i
i i
l i
1 3.
SS E I
i i
l I
I I
I I
i I
i i
i I
9.
S I
i i
1 4
i i
l i
i l
i i
l I
i
- 10. SS'A 1
l l
l 1
I I
I i
l i
i i
l i
I l
- 11. SW l
I I
I I
I I
i i
I I
I I
I l
- 12. WSW i i
l l
l l
l l
l l
l l
l 1
I i
- 13. W l
l l
l l
l l
l l
l l
l 1
I l
- 14. WNW l I
l l
l 1
I i
i l
1 i
I I
i
- 15. NW l
i i
i I
i i
t i
i i
?
I I
i i
l16. NNW l l
l l
l l
{
l l
l l
l l
j l
l l
l hy=
h=
s
^
?
s 32 -
5.6.2 NCNR0 TRINE REPCRTS c.
Nonroutine Radioactive Effluen: Recorts (1) Liquid Radioactive Wastes Report.
If the cunulative dose due to releases of radioactive na erials in liquid effluents exceeds one-half Specification 2.4.1.d during any calendar quarter, the licensee shall :. : an investigation to identify the causes of such releases and define and initiate a program of action to reduce the releases to correspond with the dose design objective levels of Appendix I to 10 CFR Par: 50.
A wri::en report of these actions shall be subni :ed to the
.iRC w;..4.4.~..O da-ts.:..-.4. =...* a. ~..'~. =. u.. = ~. '".;.n a-h.'..h s
the release occurred.
(2) Gaseous Radioactive Nastes Report.
Should the conditicas (a) or (b) listed below exist, the licensee shall nake an investigation to iden-ify the causes of the releases and define and initiate a program of action to reduce the releases to correspond with the dose design Objective levels of A r.endix I to 10 CFR Par: 50. A written rec.or of these actions shall be subnitted to the NRC within 50 days from
.g. e a
. a.
..b.e ua-.*.
'"-i..
w'..i.-'..5e...?ea es oc-"..a.d.
.3 (a)
If the cunulative dose due o releases of noble gases during any ca.,en,ar quarter exceeds one..na., : apec::::atica d..,.>..
l 1
l
- 3o s - a (b)
If the cu=ulative dose due to releases of all radio-iodines, radicactive na erials in particulate f0:s and nuclides other than noble gases discharged du-ing any calendar quarter exceeds one-half Specification 2.4.3.e.
(3) Unplanned or Uncontrolled Release Report.
Any unplanned or uncontrolled offsite release of radicactive naterials that results in exceeding one-sixth of -he annual dose design objectives for radicactive na:erials in licuid :: gaseous effluents requires no:ifi:sti:n.
This notifica:icn =ust be nade by a written report within 30 days Oc the.NRC.
The report shall describe the event, identify the causes of the unplanned er u. con:rclied release and reper: a:-i:ns :aken
- prevent recu ren:e.
j b@
m l
l l
l l
l l
l r
i
?
- -.