ML20024J334
| ML20024J334 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 10/04/1994 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20024J333 | List: |
| References | |
| NUDOCS 9410140025 | |
| Download: ML20024J334 (2) | |
Text
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l TABLE 4.11.2.1.2-1 h
RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM l
E Minimum Lower Limit of mme $
Sampling Analysis Type of Detection (LLD)*
@f3, Gaseous Release Type Frequency Frequency Activity Analysis (pCf/ml)
Grab Sa/
/ ^
~ fr1ncipalGayaEmitter[
'A.
Main Plant C
h
~
1x10 4 jb ;-
mple M
no
-4 Exhaust Duct 3
/
H-3 1x10 s s
2 d
b 80 8.
Fuel Building M
Principal Gamma Emitters 1x10 4 jgg Ventilation Grab Sample M
Exhaust Duct H-3 1x10 s b
C.
Radwaste Building M
Principal Gamma Emitters 1x10 4 Ventilation Grab Sample M
my Exha'ust Duct I
y D.
All Release Types Continuous
- W I-131 1x102 as listed in A, 8, Charcoal 1x10 1*
m C above.
Sample I-133 D
Continuous
- W Principal Gamma Emitters 1x10 11 Particulate (I-131, Others)
Sample Continuous
- M Gross Alpha 1x10 11 Composite Particulate Sample Continuous
- Q SR-89, SR-90 1x10 11 Composite Particulate Sample Continuous
- Noble Gas Nob'le Gases 1x10 8 Monitor Gross Beta or Gamma s
BBLE 4.11.2.1.2-1 (Continued)
TABLE NOTATION b-The principal gamma emitters for which the'LLD specification applies exclusivily are~the following radionuclides:
Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59,.
l Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Co-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides l
are to be considered. Other gamma peaks that are identifiable, together-with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to Specification l
6.9.1.8.
Sampling and anplysis shall/also be perf
, withiryone hour foll wing c-shutdown, startup, or a TSERMAL POWER ange excee thg 15 percent f EUU RATEDTHERMgPOWER,unJ(ss(1)analyssshowst the DOSE E U VALENT
' F [74C///#66 j
1-131 concentration i;Vthe primary, coolant has,n t increased re than a 3
factor of/3 and (2)f4he condenseyoffgas nobja gas activity nitor shows that offgas activity has not increased by more than a factor of 3.
d-Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
e-The ratio of the sample flow rate to the sampled stream flow rate shall
~'
be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.
f-Samples shall be changed at least once per 7 days, and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing or after removal from sampler.
Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for the main i
plant exhaust for at least 7 days following each shutdown, startup or j
THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one l
hour, and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When l
samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the condenser offgas noble gas monitor shows that offgas activity has not increased more than a factor of 3.
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RECEIVED SEP 101993 l
i SDC RIVER BEND - UNIT 1 3/4 11-10 Amendment No. 68