ML20151R782

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Proposed Tech Specs,Allowing 24 H Before Estimating Radioactive Gaseous Effluent Pathway Flowrates When Less than Min Channels Operable & Eliminating Tritium Level Checks During Startup & Power Level Changes
ML20151R782
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 01/27/1986
From:
GEORGIA POWER CO.
To:
Shared Package
ML20151R778 List:
References
TAC-60728, TAC-60729, NUDOCS 8602060233
Download: ML20151R782 (7)
v • d • e


Text

r-TABLE 3.14.2-1 (SHEET 3 0F 4)

RAn cacti = cann003 nrrL=:T non:Toninc IncTnU=NTATron Table Notations

+ Monitor must be capable of responding to a Lower Limit of Detection of 1 x 10-4 pCi/ml.

  • During releases via this pathway.

ACTION 104 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABIE requirement, effluent releases via this pathway may continue, provided the flowrate is estimated at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

If the number of channels ORERABLE remains less than required by the Minimum Channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report.

ACTION 105 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided grab samples are taken daily and analyzed daily for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With the number of main stack monitoring system channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, without delay suspend drywell purge.

If the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report.

ACTION 106 - With the number of channels OPERABLE less than required by the minimum Channels OPERABLE requirement, operation of the main condenser offgas treatment system may continue provided:

(a) Gas samples are collected once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within the ensuing 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or (b) Using a temporary hydrogen analyzer installed in the offgas system line downstream of the recombiner, hydrogen concentration readings are taken and logged every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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TABLE 4.15.2-1 (SHEET 2 0F 3)

RADI0 ACTIVE GASE0US WASTE SAMPLING AND ANALYSIS PROGRAM Table Netations

a. -Lower Limit of Detection is defined in table notation (a) of table 4.16.1-1, Specification 4.16.1.
b. For certain radionuclides with low-gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radionuclides in concentrations near the Lower Limit of Detection. Under these circumstances, the Lower Limit of Detection may be increased inversely proportional to the magnitude of the gamma yield (i.e., 1 x 10-4/I, where I = photon abundance expressed as a decimal fraction), but in no case shall the Lower Limit of Detection, as calculated in this manner for a specific radionuclide, be greater than 10 percent of the Maximum Permissible Concentration value specified in 10 CFR 20, Appendix B, Table II (column 1).
c. Analyses shall also be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following  !

shutdown, startup, or a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a 1-hour period if analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has increased more than a factor of 3 and greater than 0.02 uCi/g.

d. Sampling shall be performed weekly, 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 af ter removal from sampler). Sampling shall also be performed once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15-percent RATED THERMAL POWER in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and analyses 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 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 Lower Limits of l Detection may be increased by a factor of 10. The more frequent sampling and analysis requirement applies only if analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3 and greater than 0.02 uCi/g.

f e. The ratio of the sample flowrate to the sampled stream l flowrate shall be known for the time period covered by each dose or dose rate calculation made in accordance l

with Specification 3.15.2.1, 3.15.2.2, and 3.15.2.3.

f. The principle gamma emitters for which the Lower Limit of Detection specification will apply are exclusively
the following radionuclides: Kr-87, Kr-88, Xe-133, XE-133m, Xe-135. and Xe-138 for gaseous emissions; and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134,

' Cs-137, Ce-141, and Ce-144 for particulate emissions.

l This list does not mean that only these nuclides are to be detected and reported. Oth6r measurable and identifiable peaks, together with the above nuclides, shall also be identified and reported. Nuclides below HATCH - UNIT 1 3.15-11

Georgia Powerkn ATTACHMENT 5 NRC DOCKET 50-366 OPERATING LICFNSES NPF-5 EDWIN 1. HATCH NUCLEAR PLANT UNIT 2 REQUEST TO REVISE RADI0 ACTIVE EFFLUENT TECHNICAL SPECIFICATIONS The proposed change to Technical Specifications (Appendix A to Operating License NPF-5) would be incorporated as follows:

Remove Page Insert Page 3/4 3-60h 3/4 3-60h 3/4 11-10 3/4 11-10 3/4 11-11 3/4 11-11 l

l 700775 k

i TABLE 3.3.6.10-1 (SHEET 2 0F 3)

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Table Notations .

+ Monitor must be capable of responding to a Lower Limit of Detection of 1 x 10-4 pCi/ml.

  • During releases via this pathway.

ACTION 104 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement effluent releases via this pathway may continue, provided the flowrate is estimated at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l If the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report.

ACTION 105 - With the number of channels OPERABL4 less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided grab sampics are taken daily and analyzed daily for gross activity. With the number of Main Stack Mcnitoring System channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, without delay suspend drywell purge.

If the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requirnment for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report.

ACTION 106 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of the main condenser offgas treatment system may continue provided: (a) gas samples are collected once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within the ensuing 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or (b) using a temporary hydrogen analyzer installed in the offgas system line downstream of the recombiner, hydrogen concentration readings are taken and logged every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

If the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report.

HATCH - UNIT 2 3/4 3-60h

5 000498/15/85 j

  • 1 0

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TABLE 4.11.2-1 (SHEET 1 OF 3) 5 El RADIOACT IVE CASEOUS kASTE SAMPLING AND ANALYSIS

  • PROGRAM "I

Lowe r L im i t bJ of Sampling Analysis Type or Detection'*8 Gaseous Release Tvoe F reana ncv F reatsency Activity Analysis (sci /ml)

A. Envi ronmente l M M Principa l Gamma Emi tters(' 8 1 x 10-*'"88*8 l Release Poinds G rab Sample

1. Main Stack H-3 1 x 10-*
2. Reactor Building Vent B. All Release Continuous 8 *8 Wi88 l-131 1 x 10-'8 Types (as listed Cha rcoa l 1-133 1 x 10-

in A above) Sample bi Continuous 8 '8 W'8 i

Principal Gamma Emitter;1'8 1 x 10-

Pa rt icu l a te (1-131, Others)

- Sample w

1 Continuous 8 '8 M

  • Gross Alpha 1 x 10-

o Composite Pa rt icu l a te Sampic Continuous 8 *8 Q Sr-89, Sr-90 1 x 10 '8 Composite -

Pa rt icu la te  !

e Sample

TABLE 4.11.2-1 (SHEET 2 0F 3)

RADI0 ACTIVE GASE0US WASTE SAMPLING AND ANALYSIS PROGRAM Table Notations

a. Lower Limit of Detection is defined in table notation (a) of table 4.16.1-1, Specificatior. 4.16.1.
b. For certain radionuclides with low-gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radionuclides in concentrations near the Lower Limit of Detection. Under these circumstances, the Lower Limit of Detection may be increased inversely proportional to the magnitude of the gamma yield (i.e., 1 x 10-4/I, where I = photon abundance expressed as a decimal fraction), but in no case shall the Lower Limit of Detection, as calculated in this manner for a specific radionuclide, be greater than 10 percent of the Maximum Permissible Concentration value specified in 10 CFR 20, Appendix B, Table II (column 1).

I

c. Analyses shall also be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a 1-hour period if analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has increased more than a factor of 3 and greater than 0.02 pCi/g.
d. Sampling shall be performed weekly, 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 perforaed once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15-percent l

RATED THERMAL POWER in I hour and analyses 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 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 Lower' Limits of Detection may be increased by a factor of 10. The more frequent sampling and analysis requirement applies only if analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3 and greater than 0.02 pCi/g.

e. The ratio of the sample flowrate to the sampled stream flowrate shall be known for the time period covered by
each dose or dose rate calculation made in accordance j

with Specification 3.15.2.1, 3.15.2.2, and 3.15.2.3.

f. The principle gamma emitters for which the Lower Limit of Detection specification will apply are exclusively l

the following radionuclides: Kr-87, Kr-88, Xe-133, XE-133m, Xe-135 and Xe-138 for gaseous emissions; and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions.

This list does not mean that only these nuclides are to be detected and reported. Other measurable and identifiable peaks, together with the above nuclides, shall also be identified and reported. Nuclides below HATCH - UNIT 2 3/4 11-11

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