ML20024J334

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Proposed Tech Spec Removing one-hour Requirement for Completing Noble Gas & Tritium Sampling & Analysis
ML20024J334
Person / Time
Site: River Bend Entergy icon.png
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 l h RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM E

Minimum Lower Limit of mme @f $ Sampling Analysis Type of Detection (LLD)*

3, Gaseous Release Type Frequency Frequency . Activity Analysis ,

(pCf/ml) hC

~

$ 'A . Main Plant /^ ~ fr1ncipalGayaEmitter[ 1x10 4 jb ;-

no -4 Exhaust Duct Grab Sa/ mple M .

/  ! H-3

- s 1x10 s 3 2

d b 80 8. Fuel Building M Principal Gamma Emitters 1x10 4 jgg Ventilation Grab Sample M

"$ Exhaust Duct H-3 1x10 s C. Radwaste Building M Principal Gamma Emitters b 1x10 4 m Ventilation Grab Sample M y Exha'ust Duct

> y D. All Release Types Continuous

  • WI I-131 1x102 m as listed in A, 8, Charcoal .

C above. Sample I-133 1x10 1*

. Continuous

  • W Principal Gamma Emitters D 1x10 11 Particulate (I-131, Others)

Sample Continuous

  • M Gross Alpha 1x10 11

. Composite .

Particulate Sample Continuous

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.

c- Sampling and anplysis shall/also be perf , withiryone hour foll wing 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 1-131 concentration i;Vthe primary , coolant has,n t increased re than a j

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. l 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. 1 l

i RECEIVED l SEP 101993 i

SDC RIVER BEND - UNIT 1 3/4 11-10 Amendment No. 68