ML20202F887

Forwards Corrected Pages 3.15-11 & 3/4 11-11 to Radiological Effluent Tech Specs Submitted on 860127,due to Typos

ML20202F887
Person / Time
Site:	Hatch
Issue date:	04/04/1986
From:	Gucwa L GEORGIA POWER CO.
To:	Muller D Office of Nuclear Reactor Regulation
References
0441C, 441C, SL-536, TAC-60728, TAC-60729, NUDOCS 8604140240
Download: ML20202F887 (3)

Text

_ _ _ _ _ _ _ _ _ . _ - _ _ _ - _

Georgia Power Company 333 Piedmont Avenue -I, Atlanta, Georgia 30308 Telephone 404 5264526 Maaling Address:

Fbst Office Box 4545 Atlanta. Georgia 30302 Georgialbwer L T. Gucws # "' M # "" *"C @

• Manager Nuclear Safety and Licensing

$(.536 0441C April 4,1986 Director of Nuclear Reactor Regulation Attention: Mr. D. Muller, Project Director BWR Project Directorate No. 2 Division of Boiling Water Reactor Licensing U. S. Nuclear Regulatory Comission Washington, D. C. 20555 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 CORRECTION TO RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS Gentlemen:

During a review of our submittal of proposed changes to the Radiological Effluent Technical Specifications dated January 27, 1986, typographical errors were identified. The corrected pages are enclosed. We apologize for any inconvenience this may have caused. If you have any questions, please contact this office.

Very Truly Yours, I

I cf %

L. T. Gucwa l MJB/lc Enclosure c: J. T. Beckham, Jr.

H. C. Nix, Jr.

Dr. J. N. Grace (NRC-Region II)

Senior Resident Inspector CO-NORMS weo4140240e6gj21 ADOCK PDR PDR P

Adel u 'lo m

c l-TABLE 4.15.2-1 (SHEET 2 0F 3)

RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Table Notations  ;

a. Lower Limit of Detection is defined in table notation

(a) of table 4.16.1-1, Specification 4.16.1.

l

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 Linit of Detection. Under l these circumstances, the Lower Limit of Detection may be inc.reased inversely proportional to the magnitude of the gamma yield (i.e.,1 x 10-4/I, where I = ohoton 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 i than 10 percent of the Maximum Permissible Concentration value specified in 10 CFR 20, Appendix B, Table II i (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 l 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 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 a 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 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 increased more than a factor of 3 and greater than 0.02u Ci/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 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.

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 1 3.15-11

i TABLE 4.11.2-1 (SHEET 2 0F 3)

RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Table Notations

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 i 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 r in this manner for a specific radionuclide, be greater than 10 percent of the Maximum Permissible Concentration i 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 I shutdown, startup, or a THERMAL POWER change exceeding 15 e 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. k

d. Sampling shall be performed weekly, and analyses shall I 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 -

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 a 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  ;

Detection may be increased by a factor of 10 The more frequent -

sampling and analysis requirement applies only if analysis shows -s 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. -

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 with Specification 3.11.2.1, 3.11.2.2, and 3.11.2.3

f. The principle gama 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. _

This list does not mean that only these nuclides are to a be detected and reported. Other measurable and Z identifiable peaks, together with the above nuclides,  :

shall also be identified and reported. Nuclides below HATCH - UNIT 2 3/4 11-11  :

_