ML20086C178

Forwards Semi-Annual Radiological Effluent Release Rept, for Period of Jul-Dec 1994

ML20086C178
Person / Time
Site:	Byron
Issue date:	02/24/1995
From:	Schwartz G COMMONWEALTH EDISON CO.
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20086C180	List: ML20086C178 ML20086C488
References
BYRON-95-0077, BYRON-95-77, NUDOCS 9507060317
Download: ML20086C178 (4)

Text

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FEB 2 81995 FILE:

2.12.1522 (1.10.0101)

Mr. J. B. Martin, Administrator Nuclear Regulatory Commission Region III 801 Warrenville Road Lisle, Illinois 60532-4351 SUBJECTS Semi-Annual Radiological Effluent Release Report i

Byron Station Units 1 and 2 Facility Operating' License Nos. NPF 37 and 66 NRC Docket Nos. 50'-454 and 50-455 Dear Mr. Mcrtin Enclosed.is the Semi-Annual Radiological Effluent Release Report for July through December, 1994, for Byron Nuclear Power Station. This report is required by Technical Specification 6.9.1.7.

Two copies of the report are provided for your use.

Two copies will be forwarded to the Document Control Desk and one copy to the Senior Resident inspector.

1 Sincerely, h

C.K. ta5wartz Station Manager Byron Nuclear Power Station GKS/DD/kh Enclosure cc Distribution List Attached C5GG3.

(363511/022495) 9507060317 950224

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SEMI-ANNUAL RADI,OLOGICAL EFFLUENT RELEASE REPORT DISTRIBUTION LIST Director of Nuclear Reactor Regulation - U.S. Nuclear Regulatory Commission Nuclear Regulatory Commission, Region III Illinois Department of Nuclear Safety, Office of Environmental Safety A.N.I.

U.S. Environmental Protection Agency Air and Radiation Division - Region V

'L Health Physicist Murray and Trettel, Inc.

Teledyne Brown Engineering Environmental Services' Midwest Laboratory 2.12.1522 Byron Station Central Files, File Number Health Physics Services Supervisor - Byron Nuclear Power Station a

Radiological Environmental Monitoring Program Coordinator NRC Senior Resident Inspector - Byron Nuclear Power Station i

B.P.I. Associates General Counsel i

Health Physics Services Supervisor - Braidwood Nuclear Power Station Mr. Lou DelGeorge Nuclear Licensing Operations ODCM Coordinator, EP - Environmental Emergency Prepa'4edness Director EP Files EPG-06-R09 i

s (363512/022495)

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BYRON NUCLEAR POWER SITATION EFFLUENT AND WASTE DISPOSAL REPORT JULY through DECEMBER 1994 Supplemental Information 1.

Regulatory Limits Fission and activation gases:

a.

Tech Spec Whole Body = 500 mrom/ year Skin = 3000 mrom/ year 10CFR50 Gasuna = 5 mrad / quarter; 10 mead / year Beta = 10 mrad / quarter; 20 mead / year see below) b.

Iodines (summed with particulate, Particulates witn half-lives > 8 days:

c.

Tech Spec organ = 1500 mram/ year 15 mram/ year 10CFR50 organ = 7.5 mrem / quarter; P

d.

Liquid effluents:

10CFR50 Whole Body = 1'.5 mrom/ quarter; 3 mram/ year i

10 mrom/ year organ = 5 mrom/ quarter; Total Effective Dose Equivalent e.

10CFR20 TEDE = 100 mrem / year Maximum Permissible Concentration 2.

10CFR20 Appendix B Table 2 Fission and Activation Gases:

a.

b.

Iodine 10CFR20 Appendix B Table 2 10CFR20 Appendix B Table 2 c.

Particulates:

10CFR20 Appendix B Table 2 d.

Liquid Effluents:

This item is not applicable. Release rates are Average Energy:

3.

calculated using an isotopic mix rather than average energy.

Measurements and Approximations of Total Radioactivity 4.

Prior to release, the isotopic content Fission and Activation Gases:

Released activity is calculated using volume of a.

is determined.

which is determined by the change in tank or containment

release, Additional methods of calculation utilize historical data pressure.

and assign an isotopic mix which is representative of normal vent stack isotopics, Particulate, Tritium and Iodine aampling media for the plant vent j

stacks are collected and isotopically analyzed daily for the plant b.

i vent stacks.

' i (3635EE/022495)

)

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BYRON NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL REPORT JULY through DECEMBF,R 1994 Supplemental Information (continued)

Batch releases are isotopically analyzed prior to c.

Liquids effluents: Total release activity is calculated using volume of Total tritium activity released is calculated from the release.

highest of a monthly circulating water blowdown composite activity or release.

a sum of the input composite activities.

Analysis results which are less than the lower lLmit of detection All are reported in units of C1/ml unless otherwise noted.

d.

(<LLD)

LLD values are listed in Attachment A.

5.

Batch Releases:

a.

Liquid:

Number of batch releases = 163 1.

17,211 minutes Total time period for batch releases =

2.

Maximum time period for a batch release = 308 minutes 3.

Average time period for a batch release = 105.6 minutes 4.

Minimum time period for a baten release = 1 minute into a Average stream flow during periods of release of effluent 5.

flowing stream = 4,442 cfs, based on information from the 6.

National Weather Service or Army Corps of Engineers for the Rock River.

b.

Gaseous Number of batch releases = 187 i

1.

Total time period for batch releases = 51,921 minutes 2.

Maximum time period for a batch release = 7,164 minutes 3.

Average time period for batch releases = 277.7 minutes 4.

Minimum time period for a batch release = 60 minutes 5.

6.

Abnormal Releases a.

Liquid - none b.

Gaseous - none s

s

% (36352E/022495)

.