ML19319E034
| ML19319E034 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 05/06/1976 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19319E033 | List: |
| References | |
| NUDOCS 8003310501 | |
| Download: ML19319E034 (39) | |
Text
- _ - _.
ll.-
n '.
e O
FORWARD The attached draft model technical epecifications are still under internal NRC review.
This review may result in further changes to these specifications. -Such changes may aff9et:
1.
' Implementation of 10 CFR 50.36a and Appendix I with respect to usage of radwaste equipment, 2.
Implementation of 10 CFR 20 with respect to gaseous releases, 3.
Parameters used to derive R including deposition factor g
and controlling pathway determination, 4
Sampling 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 i
7.
Revision of equations in section 2.4.3.a.(1) an] 2.4.3.d to include call s tacks.
The equations now in these sections only apply t9 cent releases (less than 50 meters).
8 00831050.y
m p) i DRAFT h0 DEL TECHNICAL SPECIFICATIONS FOR PRESSURIZED NATER REACTORS Docket Number (s) 2.4 RADIOACTIVE EFFLUENTS 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 conformance witIt 10 CFR Parts 50.34a and i
50.36a, and to ensure that these releases result in concentrations of radioactive materials in liquid and gasect.s effluents released l
to unrestricted areas are within the limits specified in 10 CFR Part 20.
To ensure that the releases of radioictive material above back-ground to unrestricted areas are as low as is reasonably achievable, j
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 b xground 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 millirems to the total body or 10 millirems to any organ.
gs B.
The annual total quantity of all radioactive material above background that may be released from each light-water-cooled nuclear power reactor to the atmosphere should not result in an annual air dose from gaseous effluents at any location near ground level which could be occupied by individuals in unrestricted areas in excess of 10 millirads for gamma radia-tion or 20 millirads for beta radiation, cr that this quantity should not result in an annual external dose from gaseous effluents to any individual in unrestricted areas in excess t
of 5 millirems to the total body or 15 millirens to the skin.
1 1
C.
The annual total quantity of all radioactive iodine and radioactive material in particulate form above background that may be released from e'ach light-water-cooled nuclear power reactor in effluents to the atmosphere should not result in an annual dose or dose commitment from such radioactive iodine and radioactive material in particulate form for any individual in an unrestricted area from all pathways of exposure in excess of 15 millirems to any organ.
Definitic,s :
To assure uniformity of interpretation, the following definitions are used in Section 2.4 of these Technical Specifications.
Subscrints.- -...
i - refers to individual radionuclide, j - refers to time period for gaseous releases.
i
.r 9
y-w-
w w
y--
w->
ew
.A mi
- 3 C
/
.)
1 - refers to time period for liquid 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 aie 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.
e - refers to direction sector. The direction sectors for the sites are defined'as the sixteen 2215 degree sectors of a circle with. the apex at the center of the building complex.
The northsector shall be that sector with true north as a centerline.
Notations Ki = the total body dose factor due to gnen emissions for 3
each identified radionuclide, in mrem /yr per pCi/m (from Table B-1 of Regulatory Guide 1.109).
Li = the skin dose factor due to beta emissions for each identified radionuclide, in mrem /yr per pCi/m* (from Table B-1 of Regulatory Guide 1.109).
Mi
= the air dose factor due,to gamma emissions for each identified radionuclide, in mrad /yr per pCi/m3 (from Table B-1 of Regulatory Guide 1.109).
i 1
q 4
0 N
= the air dose factor due to beta emissions for each g
identified radionuclide, in mrad /yr per pCi/m (from Table B-1 of Regulatory Guide 1.109).
P
= the product of the largest inhalation dose factor for 1
any organ of an infant for each identified radionuclide in Table C-4 of Regulatory Guide 1.109 and the infant 3
inhalation rate of 1900 m /yr, in mrem /yr per pCi/m.
The infant age group and pathways are the most restric-tive.
R6i = the dose factor for each identified radionuclide into sector 6, in mrem /yr per pCi/m from Table 2.4-6.
For sectors with real pathways within 5 miles from the center of the building complex, the values of R have gg been determined based on these real pathways.
For sectors with no real pathways within 5 miles from the center of the building complex, the R has been detemed assdng, gg that all pathways exist at the 5-mile distance.
D
= the total beta air dose in sector 8 from gaseous effluents gg n
for the total time period I At., in mrad.
)=1
)
D
= the total gamma air dose in sector e for gaseous effluents OY n
for the total time period I at., in mrad.
3 j=1
t
).
-S-r.)
r D
= the maximum dose from gaseous effluents to the total er body or an organ of an individual in sector e for the n
total time period I at., in mrem.
3 j=1 D
= the cumulative dose to the total body or an organ :
from the liquid effluents for the total time period m
E at, in mrem.
g 1=1 0
at = the length of the 1 time period over which C and g
yg F are averaged for all liquid releases, in hours.
g th At) = the length of the j time period over which (X/Q)3e and Q are averaged for all gaseous releases, in g
hours.
For batch releases, no time period at. shall J
be more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; for continuous releases no time peri d 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 />.
J m
= the total number of time period during which liquid
-effluent releases occur.
~
n
= the total number of time period during which gaseous effluent release occurs into sector 6.
= the average release rate of radionuclide i in gaseous 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:
t 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.
O - 8 t,.
(
Cyg = the concentration of radionuclide i in liquid effluent passing the effluent radiation monitor during time period at from any liquid release, in uC1/ml.
g A
= the adult ingestion dose factor to the total body or g
any organ r for each identified radionuclide, in mrem /pCi (from Table A-3 in Regulatory Guide 1.109, listing 169 radionuclides).
F
= the near field average dilution factor of C during g
gg any liquid effluent release.
Defined as the ratio of the maximum liquid waste flow passing the effluent radiation monitor during release to the product of the average measured liquid waste flow from the site discharge stureture to unrestricted receiving waters and any appli-cable factor for the mixing effect of the discharge structure.
B
= the bioaccumulation factor in fish for each identified g
radionuclide, in pCi/kgm per pCi/ liter (from Table A-8 in Regulatory Guide 1.109).
(X/Q)jes = the average atmospheric dispersion factor for the time period at. in sector 9, from all stack release points at J
the site, in sec/m.
When at) is greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the average shall be based on observations of wind speed and atmospheric stability taken at least every hour during at).
=kL /G where g 33 1
A
' q
.i 2
2 L, = 2.0 exp (-h,/2a,) /e,r0 g
The values of L, are provided in Table 2.4-5 for g
the site boundary and food pathways.
a.
= the vertical standard deviation of the plume for s
the applicable atmospheric 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 complex e
to the receptor for each sector e, in meters, provide in Table 2.4-5.
h = the height of the stack above grade,
'n meters.
s E = the average wind speed deter =ined at least hourly, during time period at. in sector e, at a height of J
10 meters for vent releases and at the upper measure-ment level for stack releases, in m/sec.
k
= the recirculation factor accounting for spctial and e
temporal variations in air flow.
For non-continuous-releases, its value is unity.
For continuous I
release its value is determined using the methodology -
described in Regulatory Guide 1.111.
CX/Q)jev = the average atmospheric dispersion factor for the time period at. in sector 0, from all vent release points at J
the site, in sec/m.
When at. is greater than i hour, the J
average shall be based on observat'icns of wind speed and atmospheric stability taken at least every hour during at).
=kLg gy/G where, w-,-m
~
{
<];.
+h2 L
= 2.0/r0 "z gy The values of L are provided in Table 2.4-5 for the gy site boundary and food pathways.
o,,
r, u are g
defined above.
h = the average height of all on site buildings, with y
the limitation that h < 7 o,, in meters.
y The noble gases to be considered are:
Ar-41 Kr-88 Xe-133 Kr-83m Kr-89 Xe-135m Kr-85m Kr-90 Xe-133 Kr-85 Xe-131m Xe--137 Kr-87 Xe-133m Xe-138 The radiciodines, radioactive materials in particulate i
form and radionuclides other than noble gases to be considered are:
1 H-3 Zn-65 Cs-134 C-14 Sr-89 Cs-136 j
Cr-51 Sr-90 Cs-137 Mn-54 Zr-95 Ba-140 Fe-59 Sb-124 Ce-141 Co-58 I-131 Other nuclides !
Co-60 I-133 with half-life greater than 8 dafs.
A complete list of 169 radionuclides that could be identified in liquid releases is given in Table A-3 of Regulatory Guide 1.109
,g, f'\\
j 2.4.1 LIMITING CONDIT~ONS FOR OPERATION Soecifications for Licuid Waste Effluents a.
The concentration of radioactive materials released in liquid ef9uents to unrestricted areas from all reactors at the site shall not axceed the values specified in 10 CFR Part 20.106.
b.
During release of radioactive material in liquid effluents, the effluent radiation control monitor shall be set to alarm and to initiate the automatic closure / isolation of each radioactive waste discharge to this monitored. effluent line prior to exceeding the limits specified in 2.4.1.a above.
The operability of each automatic isolation system in speci-c.
fication 2. 4.1.b, above, shall be functionally tested quarterly.
d.
The design objective annual dose from radioactive materials in liquid effluents to unrestricted areas from each radioactive waste producing reactor at the site is 3 mrem to the total body and 10 mres to any organ.
The licensee shall maintain a quarter 1 csulative record of calculated dose contributions due to the release of radioactive materials in liquid effluents.
The dose contributions for the m
total time period
[at shall be calculated for all radio-1.= 1 nuclid,es identified in Specification 2.4.2, and a rt:nning sum of these total body and any organ doses. shall be recorded -
after each batch release and at least conthly for all con-
7 tinuous releases using the equation, 169 m
6 O = 2.4 x'10 A B
[ At C F
r gg g g gy g 2.
1=1 where the terms are defined in 2.4.
The maximum quantity of radioactivity contained in any e.
-liquid radwaste tank that'can be discharged directly to the environs without the continuous automatic control pro-visions of Specification 2.4.1.b, shall not exceed a quantity which, if evaluated as a batch release, results in calculated doses exceeding Specification 2.4.1.d at any time.
f.
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 the projected cumulative release could result in a calculated dose exceeding one-fourth Specification 2.4.1.d in any calendar quarter.
i g.
If the actual release of radioactive caterials in liquid effluents results in a calculated dose exceeding one-half Specification 2.4.1.d in any calendar quarter, the licensee shall:
(1) make an investigation to identify the causes for such
- releases, l
l (2) define and initiate a program of action to reduce such t
releases to Specification 2.4.1.d, and (3) report these actions to the NRC in accordance with Specification S.6.2.
l
p, r h.
An unplanned or uncontrolled offsite release of radioactive materials in liquid effluents resulting in a calculated dose exceeding one-sixth Specification 2.4.1.d in a single event, requires notification.
The notification shall be in accordance with Specification 5.6.2.
2.4.2 LIMITING CONDITIONS FOR OPERATION Specifications for Liouid Waste Samuling and Monitoring a.
Sampling and analysis of liquid radioactive waste shall be performed in accordance with Table 2.4-1.
b.
Prior to taking samp1'es from a tank from which batch liquid waste releases are to be made, at least two tank volumes shall be recirculated to assure that any transfe able solids are sampled.
If eductors are used, the two tank volumes applies to the entrained fluid.
Prior to a batch liquid waste release, the sa=ple taken c.
in Specification 2.4.2.b shall be analy::ed for nuclide identification and concentration in accordance with Table 2.4-1 and recorded to demonstrate compliance with Specification 2.4.1.
d.
Plant records shall be maintained of the radioactive concen-tration and volume before dilution of all liquid radioactive waste intended for fischarge and the average dilutten ficw - -
and length of time over which each discharge occurred.
Sa=ple analysis results and other reports shall be submitted
e s.
(,
)
La accordance with Specification 5.6.1.
Estimates of the sampling and analytical errors associated with each reported value shall be included.
The radioactivity in liquid wastes shall be continuously e.
monitored during' release.
Table 2.4-3 indicates the location and min 4== requirements for continuous monitoring instrumentation for liquid waste effluent systems.
(1)
If the effluent radiation control monitor on a batch i
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 sa=ples shall be taken and analyzed in accordance with Specification 2.4.2.c and two plant personnel shall independently check valving prior to the release.' If the monitoring 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 monitor on a continuous
.._ ease line requiring automatic isolation control in Table 2.4-3 is inoperable, the effluent from this release line shall be terminated.
(3)
If the effluent radiation monitor on a release line not requiring automatic isolation control in Table 2.4-3 is 1
s inoperable, grab samples shall be taken, analy:ed for-gross activity at a sensitivity of 10' uCi/mi and i
- t',
recorded each eight hours.
If this monitoring instrumen-tation is inoperable for more than seven days, the effluent from this release line shall be terminated.
(4)
If the flow rate indicators are 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 radicactive source and checked at least monthly by means of a known solid radio-active-source.
The gamma spectrum for the known liquid source shall contain the principal gamma emitter peaks representative of those to be monitored at the set point alarm level by the effluent radiation monitor.
The known solid source shall have an average gamma energy within +25% of the average gam =a energy 1
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 known solid source, and the effluent rav stion monitor readings shall be established.
Each effluent radiation monitor shall have a monthly functional check, and
!,T J
shall have an instrument check either prior to making a release or daily for continuous release effluent radiation monitors..
Bases:
The release of radioactive materials in liquid effluents to unrestricted areas shall not exceed the concentration limits s'pecified in 10 CFR Part 20 at any time 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 commitment from liquid effluents from each radiosr.tive waste producing reactor for any individual in an unrestricted area from all pathways of exposure will not exceed 3 mrem to the total body or 10 mrem to any organ.
At the same time, these specifications 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.
Specification 2.4.1.a requires the licensee to limit the concentra-tion of radioactive materials in liquid waste effluents released from the site to levels specified in 10 CFR Part 20.106.
This speci-fication provides assurance that no member of the general public will
^ ' '
r~
i
/
be exposed at any time to liquid containing radioactive materials in excess of limits considered permissible under the Commission's Regulations.
Consistent with the requirements of 10 CFR Part 50, Appendix A, General Design Criteria 60 and 64, Specifications 2.4.1.b and 2.4.1.c require ~ operation of suitable equipment to control and monitor the releases of radioactive materials in liquid wastes during any period that 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 that the actual exposure of an individual throrgh liquid pathways is unlikely-to be substantially underestir-ated.
Specification 2.4.1.e establishes an upper limit to the quantity of radioactive material that is allowed to be released without the automatic control provisions of Specification 2.4.1.b.
The intent cf this specification is to per=it operational flexi-bility when releases will not result in doses exceeding the design objectives of Appendix I to 10 CFR Part 30.
Specification 2.4.1.f requires the licensee to maintain and operate the equipment installed in the liquid radwaste trest =ent systems to 1
r) a
.. )
reduce the release of radioactive materials in liquid effluents toaslowasisreasonabiyachievable,consistentwiththerequire-ments of 10 CFR Part 50.36a.
Normal use and maintenance of installed equipment in the liquid radwaste treatment system pro ' %s reasonable assurance that the quantity released will not exceed the design objective. -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 rate could result in doses exceeding one-quarter of the design objectives in Section II.A of Appendix I to 10 CFR Part 50 during any calendar quarter.
The reporting requirements of Specification 2.4.1.g are in accordance with Section IV.A of Appendix L to 10 CFR Part S0 and Specification S.6.2 of these Technical Specifications.
Specification 2.4.1.h provides for reporting spillage or release 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 Specifica-tion 2.4.2 provide assurance that radioactive materials in liquid wastes are properly controlled and monitored in confor=ance with the requirements of General Design Criteria 60 and 64 These requirements provide the data for the licensee and the Co= mission to evaluate the plant's performance relative to radioactive liquid
17 _
/
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 licensee to take such action as the Commission deems appropriate.
l l
.i
/
T,
[.
s 2.k.3 LIMITING CONDITIONS FOR OPERATION Specificatiens for Gaseous Waste Effluents The concentration of radioactive materials in gaseous a.
effluents to unrestricted areas from all reacNrs at the site shall not exceed the values specified in 10 CFR Part 20.106.
(1)
The release rate limit at any time of noble gases from the site shall be such that 15 8
[K (yfQ)gy Q (X/Q3 SQ < 5.0 x 10
+
g y
0s i
and 15
[ (Li+l1M) h
+ ('d )es is, < 3.0 x 10' i
gy iy i
where the terms are defined in Section 2.4, (2)
The release rase limit at any time of all radiciodines and radioactive =aterials in particulate form and radio-nuclides other than noble gases released to the environs as part of the gaseous wastes from the site shall be such that 19
[P (X M iv + (X M)33 h
< 1.5 x 10 9 i
ev is.
1 where the terms are defined.in Section 2.d.
.-., _ =. -...
.=
[
- 19.-
b.
During the release of gaseous wastes from the pri=ary system waste gas holdup system, the effluent =onitor shall be opera-ting and set to alarm and to initiate the automatic closure 4-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 monitor shall be operating, and set to alarm 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.
The operability of each automatic isolation valve in Speci-c.
fication 2.4.3.b above, shall be functionally tested quarterly.
d.
The design objective annual air dose from radioactive noble gases :
l in gaseous effluents to unrattricted areas in each direction 7
sector from each radioactive waste producing reactor at the site is mrad for ga-a radiation and 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 sector dependent dose contributions n
forthetotaltimeperiod[at. shall be calculated for all J
j=1 noble gases identified in Specifications 2,2.4.a, b and c, and a running sum of these doses per sector shall be recorded after
^
each batch release and at least weekly for all centinuous~
releases using the equations,
?
e g-pq,
%e
+
.~..:. +;
..... -. =.. '..
.. = -.. - :
- 1.
l 3
i '
.t.
I i
15 n
D
= 110
[My[at)
(X/Q)fev Sijv * (X/9)jes ijs S
ey 1
4 31 ad 4
15 n
D
= 110
[Ni [ at OS j
(x/Q)j ev Q..
+ (x/Q)jes t].
Q 13v s
)
i j=1 where the terms are defined in 2.4.
e.
The design objective annual dose or dose 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 each radioactive waste producing reactor at the site is 15 mrem to the total
- ~ ~
body or any organ.
The licensee shall maintain a quarterly cumulative record of calculated dose centributions to each of the 16 sectors due to the release of radioactive materials in.
4 all gaseous effluents.
The sector dependent dose contributions n
for t.te total time period [ at. shall be calculated for all J
1 radiciodines, radioactive]=aterial in particulate form and c
radionuclides other than noble gases identified in Specifi-cations 2.4.4.a, b and c, and a running sum of these doses per sector shall be recorded after each batch release and at least weekly. for all continuous releases using the equation, 19 n
2 D
= 110 [R
[
at GT 19 j
(X/Q)j ev Q - ].
(X/Q)j 9s Q 1v ijs
.1=1 j=1 where the terms are defined in 2.4.E.
j f.
The maxi =u= activity to be contained.in one waste gas storage l
mank shall not exceed curies (considered as Xe-133).
i-l.
l
J
~.. )
I i
{
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.
h.
If the actual release of radioactive materials in gaseous effluents results in a calculated dose exceeding one-half Specifications 2.4.3.d or e above, in any calendar quarter, 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 S.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 event requires notification.
This notification shall be in accordance with Specification 5.6.2.
j.
Potentially-explosive gas mixtures of hydrogen and oxygen contained in waste processing system components shall be continuously monitored for gas concentration during power
l',.
l
.) ~
operation. All gas monitors shall have daily sensor
~1 checks, monthly functional checks, and quarterly calibra-tion.
t (1) For systems designed to withstand 'a hydrogen explosion,
'the gas monitor shall alarm, both locally and in the control room, at a set point of 4% by volume of hydro-gen or oxygen.
If the gas monitor or alarm is inuperable, 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 5.6.2.a(2), 30-Day Report.
(2) For systems not designed to withstand a hydrogen d
explosion, the automatic control features to pre-1 vent potentially-explosive gas mixtures in the
~
l 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 4% by volume of hydrogen and/or oxygen.
At least one continuously controlling gas monitor with alarms shall be in operation whenever the gaseous waste processing system is operating.
~
.) I s
2.4.4 LDfITING CONDITIONS FOR OPERATION Soecifications for Gaseous Waste Sa= cling and Monitoring a.
Sampling and analysis of radioactive material in gaseous j
effluent, including radioactive materials in particulate forms and radiciodines shall be perfor=ed in accordance with Table 2.4-2.
b.
Noble gas relear-s to the envircnment, except from the curbine building 5_ntilation exhaust, shall be contin-c uously monitored for gross radioactivity and flow according to Table 2.4-4.
Whenever these :adiation =onitors are in-operable, grab sa=ples shall be taken and analy:ed daily for gross radioactivity. Meteorological monitoring instru=en-tation should be opertted as specified in 3.2.
If these monitors, devices or instruments are inoperable for more than seven days, these releases shall be ter=inated.
c.
During any planned batch rtlease of radf oactive materials in effluent, the gross activity =onitor, the iodine collec-tion device, the particulate collection device, and the meteorological monitoring instru=entation specified in 3.2 shall'be operating.
i d.
Plant records shall be maintained and reports of the i
sampling and analyses results shall be submitted in accor-dance with Spec.fi.:atien 5.6.1.
Estimates of.the sampling and analytical errors associated with each reported value should be included.
~
1
-~
\\
1
)
e.
All gaseous effluent radiation monitors shall be calibrated 3
at least annually by means of a known noble gas radioactive source and checked at least weekly by means of a known solid 1-radioactive source. The gamma or beta spectrum for the known noble gas source shall contain at least one of the principal gamma or beta emitter peaks known to be present in the gas stream to be monitored by the effluent radia-tion monitor. The known solid source shall have an average gamma or beta energy within 25% of the average gamma or beta energy of the nuclides known to be present in the gas 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 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 the 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 i
solid source check either prior to making a release or daily for continuous release effluent radiation monitors.
I
-e w
' ' =
w 25 -
r' I
Bases:
The release of radioactive materials in gaseous waste i
effluents to unrestricted areas shall not result in concentrations l
that exceed limits specified in 10 CF? Part 20 at any time and
~
should be as low as is reasonably achievable in accordance with the requirements of 10' CFR Part 50.34a and 50.36a. These speci-fications provide reasonable assurance that the resulting annual air dose due to gamma radiation will not exceed 10 mrad and that the resulting annual air dose due to beta radiation will not exceed 20 mrad from the gaseous waste effluents from 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 mrem or an annual dose to the skin greater than 15 mrem from these gaseous effluents, and that the annual dose to any organ of an individual from radioicdines and radioactive material in particulate form will not exceed 15 mrem from each radio-active waste producing reactor at 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-pararily result in releases higher than such numerical guides for design objecti,ves but still within levels that assure that the 1
average population exposure is ecuivalent to small fractions of doses irca natural background radiation.
4 W
-y my m
e.rm y
-w v
. :... - i
.~
^ #
l Specification 2.4.3.a(1) limit.1 the release rate of gaseous waste effluents to the environs so that the corresponding ga=ma and l
beta dose rates above background to an individual in an unrestricted area are at all times less than that corresponding to 500 mrem /yr to the total body or 3000 mrem /yr to the skin, in compliance with the limits of 10 CFR Part 20.
i For Specification 2.4.3.a(1), ga=ma and beta dose factors for the individual radionuclides are provided in Table B-1 of Regulatory Guide 1.109.
The equations provided in these Technical Specifications are developed from the methodology 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 utili::ed in the collection of effluent data.
For batch releases, the average x/Q corres-ponding to release rate Q during each time period.it.
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 r....
-.m
.. ++---
--vg
.... =..
.u r
-.-.m-
=
1 m,.
f-.
e class (Pasquill Category) aeasured during each time period at).
j For continuous releases, the average yfQ sha;.1 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 average X/Q is derived from the X/Q values calculated h'ourly 4
or more frequently, and is based on hourly or more frequent
' observations of wind speed and atmospheric stability class (Pasquill Category)', and is equal to the s of the individual X/q determinations divided by the total number of determina-tions during ecah time period at).
These sector-dependent doses are cumulated and recorded to show compliance with the require-ments of 10 CFR Part 20 and design objectives of Appendix I t
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.
The release rate Specifications for radiciodine, radioactive material in particulate form and radionuclides other than noble gases are dependent on existing radionuclide pathways to man.
The pathways which were examined for these Specifications are
- 1) individual inhalation of airborne radionuclides, 2) deposition i
of radionuclides onto green leafy vegetation with subsequent consump-tion by man, 3) deposition onto grassy areas where milch animals 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 to he thyroid via these pathways are described in. Regulatory Guide 1.109, 4,
e,
'n..
4
= ~
~~
~ 28 -
r Specification 2.4.3.a(2) limits the release rat. of radiciodines, radioactive material in particulate form and radionuclides other than noble gases so that the corresponding thyroid dose rate above background to an infant via the inhalation pathway is less than 1500 mrem /yr at the site boundary, in compliance
' with the limits of 10 CFR Part 20.
Consistent with the requirements of 10 CFR Part 50, Appendix A, Design Criteria 60 and 64 Specifications 2.4.3.b and 2.4.3.c require that suitable, equipment to monitor and control the rad!' active gas-eous : releases are operating during any period these releases are taking place.
Specification 2.4.3.d establishes the design objectives for radioactive noble gases in waste effluents from each radioactive waste producing reactor to unrestricted areas.
Specification 2.4.3.e establishes the design objective for radiciodines, radioactive msterials in particulate form and nuclides other than noble gases in releases from each unit to unrestricted areas.
These Specifications are in accordance with Appendix I to 10 CFR Part 50 dose design objectives and calculational procedures based on models and data such that the annual exposure of an individual through gaseous and airborne pathways is unlikely to be substantially underestimated.
w-t y
,9
e-
-M-
?
~
b I
Specification 2.4.3.f limits the maximum quantity of radioactive gas that can be contained in a waste gas storage tank.
The calcu-lation of this quantity should assu=e instantaneous ground release, a X/Q based on 5 percent meteorology, an average gross energy of
. 0.19 Mev per disintegration (considering Xe-133 to be the princi-pal' emitter) and exposure occurring at the min 4-m site boundary j
radius using a semi-infinite cloud codel. The calculated quantity will limit the offsite dose above background to 0.5 rem or less, consistent with Commission guidelines.
Specification 2.4.3.g requires that the licensee maintain and operate the equipment installed in the vent, purge, exhaust, off-gas and ventilation systems to reduce the release of radioactive materials in gaseous wastt. effluents to as low as is reasonably achievable, consistent with the requirements of 10 CFR Part 50.34a and 50.36a.
Normal use and =aintenance 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 caterials as low as is reasonably achievable, the specification requires i
operation of equipment whenever the projected cu=ulative disenarge
\\
rate will exceed one-fourth the dose design objectives of Appendix I to 10 CFR Part 50 during any calendar quarter.
i The reporting req:.tirements of Specification 2.4.3.h are in accordance with Section IV.A of Appendix I to 10 CFR Part 50 and Specification 5.6.2 of these Technical Specifications, e
i e es v
{.
e 30 t
~
Specification 2.4.3.1 provides for reporting release events which,'
w while below the limits of 10 CFR Part 20, could result in exposures higher than the design objectives.
Specification 2.4.3.j provides for maintaining instrumentation on systems handling potentially-explosive gas mixtures of hydrogen and oxygen.
i
!j The sampling and monitering requirements given under Specification 2.4.4 provide assurance that rac'ioactive materials released in gaseous effluents are properly controlled and monitored in conformance with the requirements of General Design Criteria 60 and 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 gaseous effluents are furnished to the Commission ac ording 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 =ay from time to time require the licensee to take such action as the Commission deems appropriate.
Specification 2.4.4.b excludes monitoring the turbine building ventilation exhaust for PWR reactors since this release is expected te be a negligible release point.
en...
w
-- m r,
31 r
)
2.4.5 LIMITING CONDITIONS FOR OPERATION t
Specifications for Solid Waste Handling and Discosal The total curie quantity and principal radionuclide compo-a.
sition shall be determined by measurement or estimates for all radioactive solid wasta shipped offsit'e.
b.
Reports of the radioactive solid waste shipments, volumes, principal radionuclides, and total curie quantity, shall be submitted in accordance with Section 5.6.1.
Bases:
The requirements for solid radioactive waste handling and disposal given under Specification 2.4.5 provide assurance that solid radioactive materials stored at the plant and shipped off-site are packaged in confor:ance with 10 CFR Part 20,10 CFR Part 71, and 49 CFR Parts 170-178.
~y
a
- 2...
a
}
l TABLE 2.4,1 RADICACT!VE LIQUID WASTE SAMPLING AND ANALYSIS Detectable Liquid Source Sampling and Analysis Type of Activity Analysis Concentrations (uCi/ml)
A.
Monitor Tank Batch Releases Each Batch Principal Gamme Emitters 5 x 10-7h One Batch / Month Olssolved Gases
- 10-5 Weekly Composites Ba-La-140,1-131 10-8 H-3 10-8 Monthly Composite
- Quarterly Composite
- St-89, St-90 5 x 10-4 i
B.
Primary Coolent Tx:h. Spec. - Appendix Ad Radiciodines 10-8 C.
Steam Generator Slowdown Principal Gamma Emitters 5 x 10-7b Weeklyf Sa-La-140,1-131 10-8 One Sample / Month Dissolved Gases
- 10-5 H-3 10-5 Monthly Compositef Gross a 10-7 Quarterly Composit-Sr-89, St-90 5 x 10-a a The detectability limits for activity ana.ysis are based on the technical feasibility and on the potential significance in 1
the environment of the quanuties released. For some nuclides, lower detection limits may be readily achievable, and l
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 their sensitivity limits when other nuclides are present in the sample in much greater concentrations. Under these circum-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.
j c A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
d The power level and cleanup cr purification flow rate at the sample time shall also be reported. Specification 5.6.1.
e For dissolved noble gases in water, assume a MPC of 4 x 10 5 gCi/mi of water.
I To be representative of the average quantities and concentrations of radioactive materials in liquid effluents, samples should be collected in proportion to the rate of flow of the affluent stream. Prior to analyses, all samples taken for the composite should be thoroughly mixed in order for the composita sample to be representative of the average effluent release.
e 4
[
._..u x
...e r
TABLE 2.4-2 RAOlOACTIVE GASECUS WASTE SAMPt.ING AND ANAL YSIS Gaseous Source SamM W Analyns Prequency Type of Activity Analysis mble Concanmens (gCUmi)8 -
A.
Weste Gas Decay Tank Each Tank Principal Gamma Emitters 10-ah 8 etch Roleseos H-3 10-8 8.
Containment Purge Each Purge 8 Principal Gamma Emitters 10-8 Batch Reiseses H-3 10-6 C.
Condenser Air Ejector Monthly (Gas Sample)*
Principal Gamma Emitters 10-dh Continuous Releases H-3 10-8 0.
Other Environmental Monthly (Gas Samples)*
Principal Gamma Emitters 10-4b Continuous Releases H-3 10-6 Weekly (Charcoal Sample)*
l-131 1C-12 l
10-10 Monthly (Charcoal Sample)*
l-133,1-135 Weekly (Particulates)d
- Principal Gamma Emitters (Ba-La-140,1-131, O thers) 1 0-11 Monthly Composited (Particulates)
Gross a 1 0-11 Quarterly Composited Sr-39, Sr-90 10-11 (Particuiares)
- a The above detectability limits for activity analysis are based on technical feasibility and on the potential sigt.ificanca in the environment of the quantities released. For some nuclides, lower detection limats may be readily achievable, and when nuclides are measured below the stated limits, they should also be reported.
b Por 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.
e Analyses shall also be performed following each refueling, startup. or similar operational occurrertce which could alter the mixture of radionuclides.
d To be representative of the average quantitles and concentrations of radioactive materials in particulate form released in gaseous affluents, samples should be collected in proportion to the rate of flow of the effluent stream.
l Analyses shall also be performed daily for a week following each refueling, startup or similar operational occurrence which could lead to significant increase or decrease in radiciodine releases.
l
.._.a.
2 y
nnm D
0 <1 V<JL
.r V
n D.
.g
.a.
S
'O 1
Z 3
.= l u.
4 g
3 83 4
~
i L
J oi j2 I
"g "I' n
.g d
>=
I
.a
==
s
=
o
$ k
- h E
a 4
=4 3 2 8
lS
=
~$
4 5*5
'[
3 2
2 s
2
==
4, 3 =j u.
a xx x
x g
s3 t
u
}.
a 3
8 gy w
h 9
=. *P 1
+-
2_
..- e.=
3
.J
=
.g 4 l t
=u a et 9
xx xxxxxx x
3 83 a
w=
E g
d j =s-
=
=
n s$
.5 1
i o
c
.$,k.
g u
g.
=
o w$
I
=
-5 1
4 zB i
- E
=
g =.S 8 3
=
.= 3
==
g3 xx 3
3 5
=
w e n-a.=
e
=
w al w
o
-g
?
4 wz s-So 3 i
>2 e
o
. _ - o 5,.
8 2y 3
W o
=
o 3
. -
.g o
- E 2
l RW E
C I
3 >*
2 e
~*
=*
c 3
=
.3 2
u 3
v g
==
s hah
=
4 og 5
X X o
2:
2 3C 1-3
=
m u
3$
d>
$2 g
=
n W
=3 1 k ";8 j3 3
32
=
=
4g E
=
WQ sc y
>w =-
g
=
a
- o..g g
w u$
.= 8 23
=
=E
.=
k"W 2
3 a
j!
E.$
E=
0 E
m
=
H =E C
E e
xxxx X
3 j.
5 3E 3
f.
gQ 35 :S
- y
=y g
g 0
W*
=
35 "3
43 o-1
-s:
22 3 O E
82 si S
~
3 w
zg
.E "= 2 > - -
w
=
c
=
=. 4
.,: 2,,.
,c I
$w s2 i
O$
X X
'3==
1 d <" m$
3j 3
E Z
d
-w
=
=m
- i
.a o
=
a 2
3
=a a
- 4 ms
= s s
e
=
.
Ub 83 8i
.3 C=
=
2 f_f j
X xX x x
o a
==
ss h
.% =
5 =
&o 5-N 3-g E.
23 3
=
8
,y 38 5
~5 L $ A 9
- g
=
U aO3 3 4
4 2
=
a 2
3 3
SE2
> 5.
=
~
-g T
=
3
=
'$.3 3 1 I
$35 3~
.2 $.
]
S 4.=
cs
. = =,.
"3 E
o e-2 3
.=
2 o
j
- e. 3
-. w=
53 5'-
g 2u0 2
3 E=
=2.:.
.= 3
=
.
. 3
es
,. o
,. = -
J y
j $ b 6"
M 3
g 3C=
=
S "y a d
g
.x
.s.= = -
4_ =v U :=
s = s =.
u a.3 o
a
~
=
~ =
=.
e a
=
I
>3
>s
- 3. = S
= I =_ w,. -
=. _ -
o3 4
=
=
sH u=
.m 2 *i =g. L = c=2 s rG
=
a.
8 -
)
1 o ~i a
E
=
= i
- 2. -
22 -
i
=
2
=
w
=
is m
.
=
=
o d 3 &= 3 33yo
- g; 33 sE B
a35 33
=
d j= a
=7
=g 3
e C
- 2 E %
3 3 1 $3 3;g3 52
="
4>
q=
=
? E
-3
= e
=
5 2
sv 2
gE>
M 5
E'8
=U
.a J 3 g g =5
.s. =
-g
=
=_-
o=
2 **
1 a
S
.=
=.
i 3 j2 i 22 E d 2
?=
933 i S$
si d 2,:y E _ i r i5 e as 15 e e25 5 as E
2 o
cae cssac4 x
l.
.=
p
-.+7
.w g.---
.t TABLE 2A4 y
PflESSURIZED WATER REACTOR GASEOUS WASTE SYSTEM LOCATION OF PROCESS AND EFFLUENT MONITOlls AND SAMPLERS REOUlHED BY TEctlNICAL SPECIFICATIONS
~-
?
i flelease Point Continuous Monitosing insismnentation Continuous Grah P=A=aw Monitor Sampler' Sample Plant Process Stream or Fielease Point Activity Radiasimi Auto pulmi to Hm he Stah har m b.
Activity Recoeder Alarm isolation Valve is.dicator i
Particulate t
9 Waste Gas Stosage Tank Heleases X
X X
X X
X X
X
/
4 i
Corulenser Air itemoval System" X
X X
X X
X X
a Vent llemler System X
X X
X X
X X
~
Unikling Ventilation Systems Ileaceor Containment ilmkling (Whenever Thereis Flowl X
X X
X X
X X
X Auxiliary finiklinu" X
X X
X X
X X
Fncillatullins & Seoraue Buildmu or Asca" X
X X
X X
X X
a II.ulwaste Buikling or Asca X
X X
X X
X X
Sec.un Generains hinwdown (c =>)
Tank Vent os Cmulenser Vuith X
X X
X X
X Timhine Glaeul Seal Canutenser X
X X
X X
X Waste Evaposator Canulcaser Vent' X
X X
X X
X r
o fd >_EJ "X-Hequised e
i 18 any or all of tho gwocess streams or luaikling ventilation systems ase routed to a single selease point. the need for a continuous monitor at alie indivkkial dis-p i
chasuo point to the main exhaust skict is eliminated. One continnous monitor at the final sclease point is sullicient.
[
h in some PWits the steam Generalor blowstown tank went is souted to alie main sushine comienser, amt the need for a continuous enonitor at this release point is climinati;d.
8 For PWHs in which the waste evaporator cosulenser is vented directly to the atmosphese.
9 t.
3 4
4
~-
..u.
l
-'7
)
.l TABLE 2.4-6 j
VALUES OF Lgy AND Lgs,IN METERS.2 FOR PRESSURIZED WATER REACTORS l
Vent Site Soundary Lgy, m.2 Food Pathway Lgy, m 2 j
Distance Pesquill Category Distance Pasquill Category g
re A
B C
D E
F G
rg A
B C
D E
F G
- 1. N l
- 2. NNE l
l
- 3. NE 4.
ENE
- 5. E l
l S.
ESE l
l i
i
- 7. SE I
i
- 8. SSE l
l
- 9. S
- 10. SSW I
i
- 11. SW
-1 1
l i
- 12. WSW l
l l
I 1
l 1
- 13. W I.
l l
l 1
I i
1 14 WNW l
l l
l l
l l
l l
- 15. NW l
l l
1
-i i
l l
i
- 16. NNW l
l l
1 l
L l
l l
l l
Stack Site Boundary L s, m 2 Food Pathway Lgs, m.2 d
l Distance Pasquill Category Distance pasquill Category 3
0 rg A
B C
D E
F G
rg A
B C
D E
F G
- 1. N l
l l'
l l
l i
- 2. NNE i
j
'l 1.
I 1
l
- 3. NE I
l l
l 4 ENE l
i l
i i
5.
E 1
I 1
l l
- 6. ESE h
I l
i l
i l
i
- 7. SE I
i i
l l
l
- 8. SSE I
l l
1 l
1 l
_ 9.
S i
l l
i i
i 1
l i
- 10. SSW
.I l
l 1
l i
i l
i
- 11. SW l
l I
I i
l i
i i
l i
- 12. WSW i
l i
i e
1 i
i l
l l
- 13. W l
1
'I l
l l
l l
l l
- 14. WNW i
j i
l l
l l
15.- NW l
l I
i i
i i
i
- 16. NNW j
l l
l l
l l
l l
l l
D"*%
hv =
hs
- Cs c;
_k D '@~T
~
A R_2_i a
+
s
-e
..,-,.-,----,-,,-,,,.a
1
.... t.. _
I
.t J
h i
t TABLE 2.4-6 DOSE FACTOR 8 s,IN nwom/yr PEll pCi/m3 0
FOR I
PRESSURIZED WATER REACTORS Sector,0 N
NNE NE ENE E
WNW NW NNW i
l' Diseanco, r0 t
N..
- R.ulionuclide 11 3 t
C-14 Cr 51 t
Mn 54 Fe-59 Co-Su Co GO 2n GS Sr-119 Q.6&
Zr-US Sh 124 i
3 l131 i
I133 Cs 134 Cs 136 Cs-137 4
11a 140 f
Co 141
- 1
\\
i
\\
t-J
1-
~
32 -
k 5.6.2 NONROUTINE REPORTS c.
Nonroutine Radioactive Effluent Reports (1) I.iquid Radioactive Wastes Report.
If the cu:.ulative dose due to releases of radioactive materials in liquid effluents exceeds one-half Specification 2.4.1.d during any calendar
~
quarter, the licensee shall =ake an investigation to identify the causes of such releases and define and initiate a program of action to reduce the releases to ee respond 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) l'isted 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 to correspond with the dose design objective levels of Appendix I to 10 CFR Part 50.
A written report of these actions shall be subnitted to the NRC within 30 days from the end of the quarter during which the releases occurred.
(a)
If the cu=ulative dose due to releases of noble gases during any calendar quarter exceeds one-half Specification 2.4.3.d.
m '
-n--
y y
w
.r. ::^. L.
.~
~
.~ a= 4 7
- i. '
_ 33 j
(b)
If the' cumulative dose due to releases of all radio-iodines, radioactive materials in particulate form and nuclides other than noble gases discharged during any calendar quarter exceeds one-half Specification 2.4.3.e.
~
(3) Unplanned or Uncontrolled Release Report. Any unplanned or uncontrolled offsite release of radioactive materials that i
i results in exceeding one-sixth of the annual dose design objectives for radioactive materials in licuid or gaseous effluents requires notification. This notification must 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, 1
l 1
I