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Effluent & Waste Disposal Semiannual Rept for Jan-June 1989
	ML20246K273
Person / Time
Site:	Byron
Issue date:	06/30/1989
From:	Pleniewicz R; COMMONWEALTH EDISON CO.
To:	;
References
	BYRON-89-0805, BYRON-89-805, NUDOCS 8909050422
	Download: ML20246K273 (18)
	v • d • e

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.. -, N Commonr::lth Edison p

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)~-) - 4450 North German Church Road Bynon NucinrSt tion 4

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1989 LTR BYRON 89-0805 FILE:

2.12.1522-U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

SUBJECT:

Byron Station Operating Report, NRC Dockets Unit 1 Docket Number STN 50-454

. Unit 2 Docket Number F.TN 50-455 TO WHOM IT MAY CONCERN Enclosed is the Radioactive Effluent Report for January through June, 1989, for Byron Nuclear Power Station.

A copy of this report will be furnished to the NRC Resident Inspector.

Sincerely, N

R. Pleniewicz r

Station Manager Byron Nuclear Power Station RP/SB/jr Enclosure cc: Distribution List 8909050422 890630

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PDR ADOCK 05000454 R

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Distribution List Page 2 August 24, 1989 l

NRC Resident Inspector i

Illinois Department of Nuclear Safety l

ANI B.P.I.-

I American Electric, Power Service ~ Corp.

i U. S. Environmental Protection Agency - Region III

)

Illinois Environmental Protection Agency - Division of Watar Pollution Control Illinois Power Company i

Murray & Trettel, Inc.

Teledyne. Isotopes Midwest Laboratory Radiochemistry Services Group - Tech Center l

Emergency Planning - G.O.

l P.W.R. Operations - G.O.

Health Physics Services Supervisor - Braidwood Station Manager - Byron Health Physics Services Supervisor - Byron j

i Regulatory Assurance - Byron i

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_-_-____-_________________________s

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'95 LBYR'ON NUCLEAR' POWER STATION

. EFFLUENT'AND WASTE DISPOSAL SEMIANNUAL REPORT-1JANUARYLTO. JUNE 1989-

, Supplemental Information-1,

+

'1.

Regulatory Limits

Fiss'ionf and activation gases:

r4 a.

10CFR20 Whole Body'= I500 mrem / year "N.

Skin

= 3000 neem / year l10CFR50;,. Gamma =.:5' mrad / quarter; 10 mrad / year s

Beta, = 10 mrad / quarter; 20 mrad / year b.

I,odines (sunmed with particulate, see below) c.

Particulate.with. half-lives *> 8 days:

10CFR20 Organ'= 1500 mrem / year y.

.3 10CFR50 Organ = 7.5 mrem / quarter;

.15' mrem / year

d.. Liquid effluents:-

10CFR50 ' Whole Body = 1.5 mrem / quarter; 3 mrem / year Organ.

= 5 mrem / quarter; 10 mrem / year

2. 'Maxicum Permissible Concentration

a. -Fiscion and' Activation Gases:

10CFR20 Appendix E Table II b.

Iodine: 10CFR20 Appendix'B Table II c.

Particulateds.10CFR20 Appendix B Table II d.

Liquid-EfC Snts:

10CFR20 Appendix B Table II

't i

3.

Average Energy: This. item is not applicable. Release rates are calculated using an isotopic mix rather than average energy.

4.

Measurements and Approximations of Total Radioactivity a.

Fission and Activation Gases: Prior to release, the isotopic content is determined. Released activity is calculated using volume of release, which is determined.by the change in tank or containment pressure.

'b.

Iodine sampling media for the plant vent stacks is collected and isotopically analyzed daily for the plant vent stacks.

c.-

Particulate same methodology as iodine, d.

Liquids effluents: Batch releases are isotopically analyzed prior to release. Total release activity is calculated using volume of release.

4 t

U v

i 5.

Batch Releases:

a.

Liquid:

1.

Number of batch. releases = 144 p

-2.

Totcl time period for batch releases = 14,000 minutes 3.

Maximum time period for a batch release = 229 minutes 4.-

Average time period for batch releases = 97. minutes 5.

Minimum time period for a batch release = 61 minutes 6.

Average stream flow during periods of release of

. effluent into a flowing stream = 4171 cfs, based on information from the National Weather Service or Army j..

Corps of Engineers for the Rock River.

b.

Gaseous:

1.

Number of batch releases = 162 2.

Total' time period for batch releases = 27,300 minutes 3.

Faximum time period for a batch release = 1573 minutes 4.

Average time period for batch releases = 168.5 minutes 5.

Minimum time period for a batch release = 47 minutes 6.

Abnormal releases:

a.

Liquid -- none b.

Gaseous -- none a

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BYRON NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY TO JUNE 1989 c

ADDENDUM A.' The'following is the breakdown for the continuous releases for gaseous effluents:

1st quarter Xe-133. 19.8 Curies Xe-135 0.077 Curies-TOTAL = 19.88 Curies 2nd quarter:

No continuous releases

' B.-

The following data is the' estimated compositionfof' Byron's solid waste streams:

c 1.

Dry Active Waste (DAW) 2.

Primary Resin 3.

Radwaste Resin-C-14 7.7%

Mn-54 1.54%

Mn-54 2.7%

'Mn-54 4.0$

co-58 60.9%

Co-58 30.6%

Fe-55 46.6%

co-60 4.3%

Co-60 6.8%

co-58 12.2%

Cs-134 8.7%

Cs-134

'17.8%.

Co-60' 12.0%

Cs-137 7.5%

Cs-137 24.3%-

.Ce-134 3.3%

H-3 0.6%

H 9.0%

Cs-137

.5.8%

C-14 1.2%

C-14 0.45%

Ni-63 8.4%

Fe-55 14.3%

Fe-55 6.8%

Ni-63 0.9%

Tc-99 0.05%

Sr-90 0.02%

I-129 0.1%

Tc-99 0.03%

Pu-239 0.01%

I-129 0.001%

Pu-238 0.01%

Pu-239 0.001%

Am-241 0.04%

Pu-238 0.001%

Cm-244 0.04%

Am-241 0.001%

Ni-63 1.3%

CM-244 0.001%

Pu-241 0.005%

l

I e.

y/o e.

C.

Per Technical Specifications.3.3.3.9 and 3.3.3.10, the following

.is a summary of effluent monitoring instrumentation inoperable for'a period of time greater than specified in the Technical Speci-

~

fication:

El.

Unit 1 Reactor Containment Fan Cooler Essential Service Water Outlet Monitor was inoperable for greater than 30

]

h days. The extended period of inoperability was due to a l

L faulty sample pump.

l D.

During this period, there were no major changes to the liquid, gaseous,.

or solid radwaste treatment systems. There were no major changes'to the Process Control Program (PCP). Byron Station continues to utilize

{

'the services of Westinghouse-Hittman for dewatering and solidification services.

i f

]

E.

Error Analysis The following is an estimate of the' errors associated with effluent mor.itoring and analysis. The estimate is calculated using the square j

root of the sum or the squares methodology.

j 1.

Gaseous Effluents 1 to 3.5%

j Sampling error

=

10%

l Calibration error

=

5%

Counting Statistics error

=

1.5%

Vent Stack flowrates error

=

i 11 - 12%

Total error

=

2.

' Liquid Effluents 1%

j Sampling error

=

10%

i Calibration error

=

1%

Sample volume error

=

2%

Discharged volume error

=

10%

Total error

=

I F.

Meteorological and environmental impact information is reported in the Station Annual Radiological Environmental Operating Report as required by Technical Specification 6.9.1.6.

I I

I i

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ML20246K273

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