Text

Correction to Radioactive Effluent Release Report
	ML041320541
Person / Time
Site:	Zion File:ZionSolutions icon.png
Issue date:	05/04/2004
From:	Daniels A; Exelon Generation Co
To:	; Document Control Desk, NRC/FSME
References
	+kBR1SISP20051207, -RFPFR
	Download: ML041320541 (90)
	v • d • e

May 4, 2004 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Zion Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. DRP-39 and DPR-48 NRC Docket Nos. 50-295 and 50-304

Reference:

Letter from Artice Daniels Jr. (Exelon Generation Company, LLC) to U. S.

NRC, "Radioactive Effluent Release Report for 2003 and Offsite Dose Calculation Manual for 2003," dated March 16, 2004

Subject:

Corrections to Radioactive Effluent Release Report In the referenced letter, Zion Nuclear Power Station submitted the Radioactive Effluent Release Report for 2003. Subsequently, errors were identified in the report. Following identification of the error, Zion Nuclear Power Station conducted a review of all of the gaseous and liquid effluent spreadsheets. Additional errors were identified. The attachment to this letter provides a corrected report.

If you have any questions concerning this letter, please contact Mr. Ron Schuster at 847-746-2084 at extension 2700.

Resp ctfully, Artice Daniels Jr.

Decommissioning Plant Manager Zion Nuclear Power Station Attachment cc:

Regional Administrator-NRC Region IlIl

bcc:

NRC Project Manager - NRR - Zion Nuclear Power Station Decommissioning Branch Chief - NRC Region Ill Manager of Energy Practice - Winston & Strawn (w/o enclosures)

Office of Nuclear Safety - IEMA Decommissioning Plant Manager - Zion Nuclear Power Station (w/o enclosures)

Director, Licensing - West (w/o enclosures)

Manager, Licensing - Braidwood, Byron, and LaSalle Stations Document Control Desk Licensing (Hard Copy)

ZION NUCLEAR POWER STATION 2003 RADIOACTIVE EFFLUENT RELEASE REPORT UNIT 1 & 2 (DOCKET Numbers 50-295 & 50-304)

EXECUTIVE

SUMMARY

A review of 2003 effluent data versus previous years' data showed there were no abnormally high amounts of radioactivity released during 2003. In 2003, there was no radioactive iodine released. The release of noble gas and particulates continued to trend downward. This trend can be attributed to the shutdown of both units. Unit I discharge vent was mechanically closed.

Airborne Yearly Dose Limit per Reactor Unit Dose to Maximally Exposed Receptor (Adult) from Unit 1 Dose to Maximally Exposed Receptor (Adult) from Unit 2 Gamma Air 10 mrad 0 mrad 0 mrad Beta Air 20 mrad 0 mrad 0 mrad Total Body 5 mrem 7.53e-5mrem 1.74e-4 mrem Skin 15 mrem 0 mrem 0 mrem Organ 15 mrem 8.55e-5 mrem 1.97e-4 mrem

Aquatic doses were low because both units are no longer operational. Aquatic doses for Unit 1 were higher than the doses for Unit 2 because there are no discharges of radioactive effluents performed using the Unit 2 Discharge Canal.

Aquatic Yearly Dose Limit per Reactor Unit Dose to Maximally Exposed Receptor (Teenage) from Unit I 2.48e-2 mrem I 3.93e-2 mrem I Dose to Maximally Exposed Receptor from Unit 2 Total Body Organ 1

f3 mrem I1 0 mrem 0 mrem 0 mrem I1 The doses to the public, from all Zion Station effluent paths during 2003, were extremely low and far below all regulatory limits.

To the Zion Nuclear Power Station, Units I and 2, 2003 Radioactive Effluent Release Report.

The following identifies those actions committed to by Exelon Nuclear in this document. Any other actions discussed in this submittal represent intended or planned actions by Exelon Nuclear. They are described to the NRC for the NRC's information, and are not Regulatory Commitmnents.

eommitnent:

Nond

ZION STATION Unit 1 10CFR20 Compliance Assessment

1.

10CFR 20.1301 (a) (1) Compliance Total Effective Dose Equivalent, 10 CFR 20.1301 (a) (1) limit

% of the limit mrem/year mrem/vr 6.29e-2 100 0.06

2.

Compliance Summary IOCFR20 PSt Qtr.

2nd Qtr.

3rd Qtr.

TEDE 0

l.Ole-4 4.14e-2 4th Qtr 2.12e-2

% of Limit 0.06%

ZION STATION Unit 2 10CFR20 Compliance Assessment 1.

10CFR 20.1301 (a) (1) Compliance Total Effective Dose Equivalent, 10 CFR 20.1301 (a) (1) limit

% of the limit mrvem hTP~2?

' V,--A 7__11 yo JV-s mrem/vr 100 0.00034

2.

Compliance Summary 10CFR20 1st Qtr.

2nd Qtr.

3rd Qtr.

TEDE 0

9.2e-5 1.9e-4 4th Qtr 5.41e-5

% of Limit 0.00034%

I RETDAS v3.6.3

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VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2

=== I&P DOSE LIMIT ANALYSIS Q

Quartr -

Limit Qtr 1 -

Admin. Any Organ Qtr 1 -

Admin. Total Body Age Group Dose Organ (mrem) 0.00E+00 0.00E+00 UARTER 1 Limit (mrem)

1. OOE+C

1. OOE+C Max % of Limit

)1 0.OOE+00

)1 0.OOE+00 Qtr 1 -

T.Spc. Any Organ Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compas Critical Pathway:

Major Contributors ( 0% or greater to total)

Nuclide Percentage 0.OOE+00 1.OOE+01 O.OOE+00 s Point: NA Qtr 1 -

T.Spc. Total Body Receptor: 5 Composite Crit. Receptor Distance:

0.00 (meters)

Critical Pathway:

Major Contributors ( 0% or greater to Nuclide Percentage 0.OOE+00 1.00E+01 0.OOE+00 IP Compass Point: NA total)

Date/Time: 02/25/2004 07:47 retdas Page - 6

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VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2

=== NG DOSE LIMIT ANALYSIS Quartr -

Limit Qtr 1 -

Admin.

Gamma Qtr 1 -

Admin. Beta

=========== QUARTER 1 =-

Dose Limit (mrad)

(mrad)

E-_-----

0.00E+00 1.00E+01 0.00E+00 1.00E+01 Max % of Limit

0. 00E+00

0. 00E+00 Qtr 1 -

T.Spc. Gamma 0.OOE+00 1.00E+01 0.OOE+00 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Nuclide Percentage Qtr 1 -

T.Spc. Beta 0.00E+00 1.00E+01 0.00E+00 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Nuclide Percentage Date/Time: 02/25/2004 07:47 retdas Page - 7

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VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2

=== I&P DOSE LIMIT ANALYSIS

=

Quartr -

Limit Qtr 2 -

Admin. Any Organ Qtr 2 -

Admin. Total Body Age Group ADULT CHILD Organ GILLI TBODY Dose (mrem) 1.08E-04 9.50E-05 UARTER 2 Limit (mrem) 5.63E+0 5.25E+0 Max % of Limit 0 1.92E-03 0 1.81E-03 Qtr 2 -

T.Spc. Any Organ ADULT GILLI 1.08E-04 7.50E+00 1.44E-03 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors ( 0% or greater to total)

Nuclide Percentage CO-60 1.OOE+02 Qtr 2 -

T.Spc. Total Body CHILD TBODY 9.50E-05 7.50E+00 1.27E-03 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors ( 0% or greater to total)

Nuclide Percentage CO-60 1.OOE+02 Date/Time: 02/25/2004 07:47 retdas Page - 8

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VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2

=== NG DOSE LIMIT ANALYSIS

===================

Quartr -

Limit Qt_2---__A______mi_______________Gamma___________

Qtr 2 -

Admin. Gamma Qtr 2 - Admin. Beta-Dose (mrad) 0.00E+C

0. OOE+C QUARTER 2 =-

Limit (mrad) 0

)0 7.50E+00

)0 7.50E+00 Max % of Limit 0.OOE+00 0.OOE+00 Qtr 2 -

T.Spc. Gamma 0.OOE+00 7.50E+00 0.OOE+00 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Nuclide Percentage Qtr 2 -

T.Spc. Beta 0.00E+00 7.50E+00 0.00E+00 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Nuclide Percentage Date/Time: 02/25/2004 07:47 retdas Page - 9

, RETDAS v3.6.3

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VSSI 4OCFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2

=== I&P DOSE LIMIT ANALYSIS Quartr -

Limit Qtr 3 -

Admin. Any Organ Qtr 3 -

Admin. Total Body

==================

Age Group ADULT CHILD Organ GILLI TBODY Dose (mrem)

1. llE-04

9. 82E-05 UARTER 3 Limit (mrem) 5.63E+0 5.25E+0 Max % of Limit 0 1.98E-03 0 1.87E-03 Qtr 3 -

T.Spc. Any Organ ADULT GILLI 1.111 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors (

0% or greater to total)

Nuclide Percentage CO-60 1.OOE+02 E-04 7.50E+00 1.49E-03 E-05 7.50E+00 1.31E-03 Qtr 3 -

T.Spc. Total Body CHILD TBODY 9.82]

Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors ( 0% or greater to total)

Nuclide Percentage CO-60 1.OOE+02 Date/Time: 02/25/2004 07:47 retdas Page - 10

, RETDAS v3.6.3

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VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2

=== NG DOSE LIMIT ANALYSIS

===================

Quartr -

Limit Qt_3---_____d______i______.______Gamma___________

Qtr 3 -

Admin. Gamma Qtr 3 - Admin. Beta-Dose (mrad)

0. OOE+C

0. 00E+0 QUARTER 3 =

Limit (mrad)

_0 ----

E---

)0 7.50E+00 10 7.50E+00 Max % of Limit

0. OOE+00

0. OOE+00 Qtr 3 -

T.Spc. Gamma 0.00E+00 7.50E+00 0.OOE+00 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Nuclide Percentage Qtr 3 -

T.Spc. Beta 0.00E+00 7.50E+00 0.OOE+00 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Nuclide Percentage Date/Time: 02/25/2004 07:47 retdas Page -

11

RETDAS v3.6.3

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VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2

=== I&P DOSE LIMIT ANALYSIS

==================

Quartr -

Limit Qtr 4 -

Admin. Any Organ Qtr 4 -

Admin. Total Body Age Group ADULT CHILD Organ GILLI TBODY Dose (mrem) 6.32E-05 5.57E-05 UARTER 4 Limit (mrem) 5.63E+C 5.25E+C Max % of Limit

)0 1.12E-03 0 1.06E-03 Qtr 4 -

T.Spc. Any Organ ADULT GILLI 6.32E-05 7.50E+00 8.43E-04 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors ( 0% or greater to total)

Nuclide Percentage CO-60 1.OOE+02 Qtr 4 -

T.Spc. Total Body CHILD TBODY 5.57E-05 7.50E+00 7.43E-04 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors (

0% or greater to total)

Nuclide Percentage CO-60 1.OOE+02 Date/Time: 02/25/2004 07:47 retdas Page - 12

. RETDAS v3.6.3

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VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2

=== NG DOSE LIMIT ANALYSIS Quartr -

Limit Qt__--__________min______________Gamma___________

Qtr 4 -

Admin. Gamma Qtr 4 - Admin. Beta Dose (mrad) 0.OOE+00

0. OOE+00 DARTER 4 =

Limit (mrad) 7.50E+00 7.50E+00 Max % of Limit 0.0 OE+00 0.OOE+00 Qtr 4 -

T.Spc. Gamma 0.00E+00 7.50E+00 0.OOE+00 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Nuclide Percentage Qtr 4 -

T.Spc. Beta 0.OOE+00 7.50E+00 0.OOE+00 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Nuclide Percentage Date/Time: 02/25/2004 07:47 retdas Page - 13

RETDAS v3.6.3

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VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2

=== I&P DOSE LIMIT ANALYSIS

==================

Annual -

Limit 2003 Admin. Any Organ 2003 Admin. Total Body Age Group Organ ADULT GILLI CHILD TBODY-Dose (mrem)

2. 82E-C 2.4 9E-C ANNUAL 2003 Limit (mrem)

)4 1.13E+01

)4 1.05E+01 Max % of Limit 2.51E-03 2.37E-03 2003 T.Spc. Any Organ ADULT GILLI 2.82E-04 1.50E+01 1.88E-03 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors (

0% or greater to total)

Nuclide Percentage CO-60 1.OOE+02 2003 T.Spc. Total Body CHILD TBODY 2.49E-04 1.50E+01 1.66E-03 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors ( 0% or greater to total)

Nuclide Percentage CO-60 1.OOE+02 Date/Time: 02/25/2004 07:47 retdas Page -

14

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VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2

=== NG DOSE LIMIT ANALYSIS

===================

Annual -

Limit 2003-____A______m_____n._________Gamma___________

2003 Admin. Gamma 2003

- Admin. Beta Dose (mrad) 0.OOE+C

0. OOE+C ANNUAL 2003 Limit (mrad)

- - - -E - - -

)0 1.50E+01

)0 1.50E+01 Max % of Limit 0.OOE+00

0. OOE+00 2003 T.Spc. Gamma 0.OOE+00 1.50E+01 0.OOE+00 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Nuclide Percentage 2003 T.Spc. Beta 0.OOE+00 1.50E+01 0.OOE+00 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Nuclide Percentage Date/Time: 02/25/2004 07:47 retdas Page -

15

RETDAS v3.6.3

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VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT

______________LIQUID___DOSE___

SUMMARY

LIQUID DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2 Liquid Receptor

=== PERIOD DOSE BY ORGAN AND AGE GROUP (mrem)

QUARTER 1 =

Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB

=== SITE DOSE LIMIT ANALYSIS Quartr -

Limit Qtr 1 -

Admin. Any Organ Qtr 1 -

Admin. Total Body

=================

Q Age Group Dose Organ (mrem) 0.00E+00 TBODY 0.0OE+00 UARTER 1 Limit (mrem)

0. 00E+C

1. 13E+C Max % of Limit

)0 0.0OE+00

'0 0.00E+00 ADULT Qtr 1 -

T.Spc. Any Organ Critical Pathway:

Major Contributors ( 0% or greater to total)

Nuclide Percentage 0.00E+00 3.75E+00 0.00E+00 0.OOE+00 1.50E+00 0.00E+00 Qtr 1 -

T.Spc. Total Body ADULT TBODY Critical Pathway: Potable Water (PWtr)

Major Contributors (

0% or greater to total)

Nuclide Percentage

RETDAS v3.6.3

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VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2 Liquid Receptor

=== PERIOD DOSE BY ORGAN AND AGE GROUP (mrem)

QUARTER 2-Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB

=== SITE DOSE LIMIT ANALYSIS

=================

Q1 Quartr -

Limit Qtr 2 -

Admin. Any Organ Qtr 2 -

Admin. Total Body Age Group Dose Organ (mrem) 0.00E+00 TBODY 0.0OE+00 JARTER 2 Limit (mrem) 5.00E+C 1.13E+C Max % of Limit

)0 0.00E+00

)0 0.00E+00 ADULT Qtr 2 -

T.Spc. Any Organ Critical Pathway:

Major Contributors ( 0% or greater to total)

Nuclide Percentage 0.00E+00 3.75E+00 0.00E+00 0.00E+00 1.50E+00 0.00E+00 Qtr 2 -

T.Spc. Total Body ADULT TBODY Critical Pathway: Potable Water (PWtr)

Major Contributors ( 0% or greater to total)

Nuclide Percentage

RETDAS v3.6.3

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VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2 Liquid Receptor

=== PERIOD DOSE BY ORGAN AND AGE GROUP (mrem)

QUARTER 3 -

Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 1.82E-02 2.50E-02 1.83E-07 8.48E-03 2.82E-03 5.91E-04 0.OOE+00 1.64E-02 TEEN 1.94E-02 2.60E-02 1.34E-07 8.84E-03 3.44E-03 4.44E-04 0.OOE+00 9.11E-03 CHILD 2.45E-02 2.36E-02 1.84E-07 7.67E-03 2.76E-03 1.74E-04 0.OOE+00 3.51E-03 INFANT 2.59E-05 3.09E-05 1.26E-07 8.30E-06 3.44E-06 8.10E-07 0.OOE+00 2.88E-06

=== SITE DOSE LIMIT ANALYSIS

===========

Age Quartr -

Limit Group Qtr 3 -

Admin. Any Organ TEEN Qtr 3 -

Admin. Total Body ADULT

======= QUARTER 3 Dose Limit (mrem)

(mrem)

Organ LIVER TBODY Max % of Limit

)0 6.94E-01

)0 1.46E+00

2. 60E-02

1. 64E-02

3. 75E+(

1. 13E+(

Qtr 3 -

T.Spc. Any Organ TEEN LIVER Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 5.16E-04 CO-60 2.20E-02 CS-134 1.41E+00 CS-137 9.86E+01 2.60E-02 5.OOE+00 5.20E-01 1.64E-02 1.50E+00 l.lOE+00 Qtr 3 -

T.Spc. Total Body ADULT TBODY Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 l.1lE-03 CO-60 7.70E-02 CS-134 1.80E+00 CS-137 9.81E+01

RETDAS v3.6.3

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VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT

_____________LIQUID____DOSE___

SUMMARY

LIQUID DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2 Liquid Receptor

=== PERIOD DOSE BY ORGAN AND AGE GROUP (mrem)

QUARTER 4

Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 9.31E-03 1.28E-02 7.93E-08 4.34E-03 1.44E-03 3.02E-04 0.OOE+00 8.41E-03 TEEN 9.97E-03 1.33E-02 5.83E-08 4.53E-03 1.76E-03 2.27E-04 0.OOE+00 4.66E-03 CHILD 1.26E-02 1.21E-02 7.98E-08 3.93E-03 1.41E-03 8.88E-05 0.OOE+00 1.80E-03 INFANT 1.33E-05 1.58E-05 5.45E-08 4.25E-06 1.75E-06 4.01E-07 0.OOE+00 1.46E-06

=== SITE DOSE LIMIT ANALYSIS Quartr -

Limit Qtr 4 -

Admin. Any Organ Qtr 4 -

Admin. Total Body

=================

Age Group TEEN ADULT Organ LIVER TBODY Dose (mrem)

1. 33E-02

8. 41E-03 UARTER 4 Limit (mrem) 3.75E+(

1.13E+(

Max % of Limit

)O 3.55E-01

)0 7.48E-01 Qtr 4 -

T.Spc. Any Organ TEEN LIVER Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 4.37E-04 CO-60 2.17E-02 CS-134 1.07E+00 CS-137 9.89E+01 Qtr 4 -

T.Spc. Total Body ADULT TBODY Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors (

0% or greater to total)

Nuclide Percentage H-3 9.42E-04 CO-60 7.58E-02 CS-134 1.37E+00 CS-137 9.86E+01 1.33E-02 5.OOE+00 2.67E-01 8.41E-03 1.50E+00 5.61E-01

RETDAS v3.6.3

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VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT

______________LIQUID___DOSE___

SUMMARY

LIQUID DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2 Liquid Receptor

=== PERIOD DOSE BY ORGAN AND AGE GROUP (mrem)

ANNUAL 2003=========

Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 2.75E-02 3.78E-02 2.62E-07 1.28E-02 4.26E-03 8.93E-04 0.OOE+00 2.49E-02 TEEN 2.94E-02 3.93E-02 1.92E-07 1.34E-02 5.20E-03 6.71E-04 0.OOE+00 1.38E-02 CHILD 3.70E-02 3.56E-02 2.64E-07 1.16E-02 4.17E-03 2.63E-04 0.OOE+00 5.31E-03 INFANT 3.92E-05 4.67E-05 1.80E-07 1.25E-05 5.19E-06 1.21E-06 0.OOE+00 4.34E-06

=== SITE DOSE LIMIT ANALYSIS Annual -

Limit 2003 Admin. Any Organ 2003 Admin. Total Body

=================

Age Group TEEN ADULT Organ LIVER TBODY Dose (mrem)

3. 93E-02

2. 49E-02

,NNUAL 2003 Limit (mrem) 7.50E+00 2.25E+00 Max % of Limit 5.25E-01

1. 10E+00 2003 T.Spc. Any Organ TEEN LIVER Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 4.89E-04 CO-60 2.19E-02 CS-134 1.29E+00 CS-137 9.87E+01 3.93E-02 1.OOE+01 3.93E-01 2.49E-02 3.OOE+00 8.28E-01 2003 T.Spc. Total Body ADULT TBODY Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 1.05E-03 CO-60 7.66E-02 CS-134 1.65E+00 CS-137 9.83E+01

RETDAS v3.6.3

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VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2

=== I&P DOSE LIMIT ANALYSIS

============

Quartr -

Limit Age Group Organ

====== QUARTER 1

Dose Limit Max % of (mrem)

(mrem)

Limit

____E ___

E ---

0.00E+00 1.OOE+01 0.00E+00 0.00E+00 1.00E+01 0.00E+00 0.00E+00 1.00E+01 0.00E+00.

Qtr 1 -

Admin. Any Organ Qtr 1 Admin. Total Body Qtr 1 -

T.Spc. Any Organ Receptor:

0 Distance:

(meters)

Compas Critical Pathway:

Major Contributors

( 0% or greater to total)

Nuclide Percentage s Point:

Qtr 1 -

T.Spc. Total Body Receptor: 0 Distance:

(meters)

Compas Critical Pathway:

Major Contributors ( 0% or greater to total)

Nuclide Percentage 0.OOE+00 1.OOE+01 0.OOE+00

s Point:

RETDAS v3.6.3

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VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2

=== NG DOSE LIMIT ANALYSIS Quartr -

Limit Qtr 1 -

Admin.

Gamma Qtr 1 Admin. Beta

========= QUARTER 1

Dose Limit (mrad)

(mrad)

_ _ _ _E + _ _

0.00E+00 1.00E+01 0.00E+00 1.00E+01 Max % of Limit

0. 00E+00

0. 00E+00 Qtr 1 -

T.Spc. Gamma Receptor: 0 Distance:

(meters)

Nuclide Percentage 0.00E+00 1.00E+01 0.00E+00 Compass Point:

Qtr 1 -

T.Spc. Beta Receptor: 0 Distance:

(meters)

Nuclide Percentage 0.00E+00 1.OOE+01 0.OOE+00 Compass Point:

RETDAS v3.6.3

<ZIO>

VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2

=== I&P DOSE LIMIT ANALYSIS

============

Quartr -

Limit Qtr 2 Admin. Any Organ Qtr 2 -

Admin. Total Body Age Group Organ

====== QUARTER 2

Dose Limit (mrem)

(mrem) 1.08E-04 5.63E+00 9.50E-05 5.25E+00 Max % of Limit

1. 92E-03

1. 81E-03 ADULT GILLI CHILD TBODY Qtr 2 -

T.Spc. Any Organ ADULT GILLI 1.08E-04 7.50E+00 1.44E-03 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors ( 0% or greater to total)

Nuclide Percentage CO-60 1.00E+02 Qtr 2 -

T.Spc. Total Body CHILD TBODY 9.50E-05 7.50E+00 1.27E-03 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors (

0% or greater to total)

Nuclide Percentage CO-60 1.OOE+02

RETDAS v3.6.3

<ZIO>

VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2

=== NG DOSE LIMIT ANALYSIS

===================

Quartr -

Limit Qtr 2 -

Admin. Gamma Qtr 2 -

Admin. Beta Dose (mrad)

0. 00E+0

0. OOE+G QUARTER 2 =

Limit (mrad) 0 7.50E+00

)0 7.50E+00 Max % of Limit

0. OOE+00

0. OOE+00 Qtr 2 Receptor:

Distance:

Nuclide T.Spc. Gamma 0.001

5 Composite Crit. Receptor -

IP 0.00 (meters)

Compass Point: NA Percentage E+00 7.50E+00 0.OOE+00 -

Qtr 2 -

T.Spc. Beta 0.OOE+00 7.50E+00 0.OOE+00 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Nuclide Percentage

RETDAS v3.6.3

<ZIO>

VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2

=== I&P DOSE LIMIT ANALYSIS

==================

Quartr -

Limit Qtr 3 -

Admin. Any Organ Qtr 3 -

Admin. Total Body Age Group ADULT CHILD Organ GILLI TBODY Dose (mrem)

1. 1lE-04 9.82E-05 UARTER 3 Limit (mrem) 5.63E+C 5.25E+C Max % of Limit 10 1.98E-03

'0 1.87E-03 Qtr 3 -

T.Spc. Any Organ ADULT GILLI l.l1E-04 7.50E+00 1.49E-03 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors ( 0% or greater to total)

Nuclide Percentage CO-60 1.00E+02 Qtr 3 -

T.Spc. Total Body CHILD TBODY 9.82E-05 7.50E+00 1.31E-03 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors ( 0% or greater to total)

Nuclide Percentage CO-60 1.00E+02

RETDAS v3.6.3

<ZIO>

VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2

== NG DOSE LIMIT ANALYSIS

Quartr -

Limit Qt_3---_______________n._________Gamma___________

Qtr 3 -

Admin. Gamma Qtr 3 Admin. Beta

=========== QUARTER 3 =-

Dose Limit (mrad)

(mrad)

____E ___

E+ --

0.OOE+00 7.50E+00 0.00E+00 7.50E+00 Max % of Limit

0. 00E+00

0. 00E+00 Qtr 3 -

T.Spc. Gamma 0.00E+00 7.50E+00 0.00E+00 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Nuclide Percentage Qtr 3 -

T.Spc. Beta 0.00E+00 7.50E+00 0.00E+00 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Nuclide Percentage

RETDAS v3.6.3

<ZIO>

VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2

=== I&P DOSE LIMIT ANALYSIS

==================

Quartr -

Limit Qtr 4 -

Admin. Any Organ Qtr 4 -

Admin. Total Body Age Group ADULT CHILD Organ GILLI TBODY Dose (mrem) 6.32E-05

5. 57E-05 UARTER 4 Limit (mrem) 5.63E+C 5.25E+C Max % of Limit

)0 1.12E-03

'0 1.06E-03 Qtr 4 -

T.Spc. Any Organ ADULT GILLI 6.32E-05 7.50E+00 8.43E-04 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors ( 0% or greater to total)

Nuclide Percentage CO-60 1.00E+02 Qtr 4 -

T.Spc. Total Body CHILD TBODY 5.57E-05 7.50E+00 7.43E-04 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors ( 0% or greater to total)

Nuclide Percentage CO-60 1.OOE+02

RETDAS v3.6.3

<ZIO>

VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2

=== NG DOSE LIMIT ANALYSIS

===================

Quartr -

Limit Qtr 4 Admin. Gamma Qtr 4 -

Admin. Beta Dose (mrad)

0. OOE+0

0. OOE+0 QUARTER 4 =

Limit (mrad)

-0 7.50E+00 0 7.50E+00 Max % of Limit

0. OOE+00

0. 0OE+00 Qtr 4 -

Receptor:

Distance:

Nuclide T.Spc. Gamma 0.001

5 Composite Crit. Receptor -

IP 0.00 (meters)

Compass Point: NA Percentage E+00 7.50E+00 0.OOE+00 Qtr 4 -

T.Spc. Beta 0.OOE+00 7.50E+00 0.OOE+00 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Nuclide Percentage

RETDAS v3.6.3

<ZIO>

VSSI 4OCFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2

=== I&P DOSE LIMIT ANALYSIS

============

Annual -

Limit 2003 Admin. Any Organ 2003 Admin. Total Body Age Group ADULT CHILD

======= ANNUAL 2003 Dose Limit (mrem)

(mrem)

Organ GILLI TBODY Max % of Limit 2.51E-03

2. 37E-03

2. 82E-04 2.4 9E-04

1. 13E+01

1. 05E+01 2003 T.Spc. Any Organ ADULT GILLI 2.82E-04 1.50E+01 1.88E-03 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors (

0% or greater to total)

Nuclide Percentage CO-60 1.OOE+02 2003 T.Spc. Total Body CHILD TBODY 2.49E-04 1.50E+01 1.66E-03 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors (

0% or greater to total)

Nuclide Percentage CO-60 1.OOE+02

RETDAS v3.6.3

<ZIO>

VSSI 4OCFR190 URANIUM FUEL CYCLE DOSE REPORT

_____________GASEOUS____DOSE__

SUMMARY

GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range -

From: 1 To: 2

=== NG DOSE LIMIT ANALYSIS

===================

Annual -

Limit 2003 Admin. Gamma 2003 Admin. Beta Dose (mrad)

0. OOE+(

ANNUAL 2003 Limit (mrad)

)0 1.50E+01

)0 1.50E+01 Max % of Limit

0. OOE+00

0. OOE+00 2003 T.Spc. Gamma 0.OOE+00 1.50E+01 0.OOE+00 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Nuclide Percentage 2003 T.Spc. Beta 0.OOE+00 1.50E+01 0.OOE+00 Receptor: 5 Composite Crit. Receptor -

IP Distance:

0.00 (meters)

Compass Point: NA Nuclide Percentage

RETDAS v3.6.3

<ZIO>

VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT Report for: 2003 Unit Range -

From: 1 To: 2

=== MAXIMUM DOSE ANALYSIS

====================

ANNUAL 2003=========

Dose Type Any Organ Liquid Receptor:

0 Gaseous Receptor: 5 Distance:

0.00 Age Dose Group Organ (mrei TEEN LIVER 3.72:

Liquid Receptor Composite Crit. Receptor -

IP (meters)

Compass Point: NA

.M)

'E+00 Liquid Dose:

Critical Pathway:

Major Contributors Nuclide H-3 CO-60 CS-134 CS-137 Gaseous Dose:

Critical Pathway:

Major Contributors Nuclide CO-60 3.93E-02

% of Total: 1.06E+00 Fresh Water Fish -

Sport (FFSP) 0% or greater to total)

Percentage 4.89E-04 2.19E-02 1.29E+00 9.87E+01 2.38E-04

% of Total: 6.40E-03 Ground Plane Deposition (GPD) 0% or greater to total)

Percentage 1.00E+02

=== MAXIMUM DOSE ANALYSIS

====================

ANNUAL 2003=========

Dose Type Total Body Liquid Receptor:

0 Gaseous Receptor: 5 Distance:

0.00 Age Dose Group Organ (mrei ADULT TBODY 2.35.

Liquid Receptor Composite Crit. Receptor -

IP (meters)

Compass Point: NA EM) bE+00 Liquid Dose:

Critical Pathway:

Major Contributors Nuclide H-3 CO-60 CS-134 CS-137 2.49E-02

% of Total: 1.06E+00 Fresh Water Fish -

Sport (FFSP)

( 0% or greater to total)

Percentage 1.05E-03 7.66E-02 1.65E+00 9.83E+01

RETDAS v3.6.3

<ZIO>

VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT Gaseous Dose:

Critical Pathway:

Major Contributors Nuclide CO-60 2.40E-04

% of Total: 1.02E-02 Ground Plane Deposition (GPD)

( 0% or greater to total)

Percentage 1.00E+02

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 DOSE TO PUBLIC UNIT 1 (Docket Number 50-295)

INFANT RECEPTOR Maximum Quarterly Dose (mrad, mrem)

I IQtrly Ob 1st Qtr I2nd Qtr I 3rd Qtr I 4th Qtr I A. Airborne Gamma Air 5.0 mrad O.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Beta Air 10.0 mrad 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Total Body 2.5 mrem O.O0E+00 4.53E-05 0.OOE+00 2.65E-05 Skin 7.5 mrem 0.00E+00 O.OOE+00 0.OOE+00 O.OOE+00 Organ 7.5 mrem O.O0E+00 4.68E-05 0.OOE+00 2.75E-05 Critical Organ I_

Lung Lung B. Aquatic Total Bodr 1.5 mrem l.OOE+00 I.00E+00 2.88E-06 1.46E-06 Internal Organ 15.0 mremr 0.00E+00 0.OOE+00 3._09E-05 1.58E-05 Critical Organ I

l Liver _

Liver Yearly Maximum

% of Limit Annual Yearly Dose Dose 10CFR50 (mrad, Limit Appendix I mrem) 10.0 mrad 0.00E+00 0.00%

20.0 mrad 0.OOE+00 0.00%

5.0 mrem 7.18E-05 0.00%

15.0 mremr 0.OOE+00 0.00%

15.0 mrem 7.43E-05 0.00%

Lung 3.0 mrem 4.34E-06 I 0.00%

110.O mreml 4.67E-05 I 0.00%

Liver I

Total body doses to individuals and populations in unrestricted areas from direct radiation from Zion Station are judged to be negligible in comparison with 10CFR20 annual limit of 100 mrem TEDE and 40CFR190 annual limits of 25 mrem DDE whole body, 75 mrem CDE thyroid, and 25 mrem CDE other organs.

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 DOSE TO PUBLIC UNIT 1 (Docket Number 50-295)

CHILD RECEPTOR I

Maximum Quarterly Dose (mrad, mrem) l Qtrly Obj 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr A. Airborne Gamma Air 5.0 mrad 0.00E+00 l.OOE+0 0.00E+00 -0.00E400 Beta Air 10.0 mrad 0.00E+00 0.OOE+00 0.002+00 0.00E+00 Total Body 2.5 mrem 0.00E+00 4.75E-05 0.00E+00 2.79E-05 Skin 7.5 mrem 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Organ 7.5 mrem 0.OOE+00 4.99E-05 0.OOE+00 2.93E-05 Critical Organ Gi-Lli Gi-Lli B. Aquatic Total Body 1.5 mrem 0.f E00 0.00E+00 3.51E-03 1.80E-03 Internal Organ 5.0 mrem 0.00E+00 0.O0E+00 2.45E-02 1.26E-02 Critical Organ bone bone I Yearly Maximum

% of Limit Annual Yearly Dose Dose IOCFR50 (mrad, Limit Appendix I mrem) 10.0 mrad 0.00E+00 0.00%/

20.0 mrad 0.OOE+00 0.00%

5.0 mrem 7.54E-05 0.00%

15.0 mrem 0.OOE+00 0.00%

15.0 mrem 7.92E-05 0.00%

Gi-Lli 13.0 mrem 5.31E-03 0.18%

10.0rmrem 3.71E-02 0.37%

bone Total body doses to individuals and populations in unrestricted areas from direct radiation from Zion Station are judged to be negligible in comparison with 10CFR20 annual limit of 100 mrem TEDE and 40CFR190 annual limits of 25 mrem DDE whole body, 75 mrem CDE thyroid, and 25 mrem CDE other organs.

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 DOSE TO PUBLIC UNIT 1 (Docket Number 50-295)

TEENAGE RECEPTOR Maximum Quarterly Dose (mrad mrem)

Qtrly Obj I 1 st Qtr 2nd Qtr I 3rd Qtr 4th Qtr A. Airborne Gamma Air 5.0 mrad 0.OOE+00 0.OOE+00 0.OOE+00 O.00E+00 Beta Air 10.0 mrad 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Total Body 2.5 mreml 0.OOE+00 4.62E-05 0.OOE+O0 2.71E-05 Skin 7.5 mrem O.OOE+00 0.00E+O O.OOE+00 O.OOE+0O Organ 7.5 mrem 0.00E+00 5.30E-05 0.OOE+00 3.11E-05 Critical Organ Gi-Lli Gi-Lli B. Aquatic Total BodY 1.5 mrem O. OOE+00 0.0OE+00 9.IIE-03 l 4.66E-03 l Internal Organ 5 0 mrem 0.00E+00 0.OOE+00 2.60E-02 1.33E-02 Critical Organ liver liver2I Yearly Maximum

% of Limit Annual Yearly Dose Dose 10CFR50 (mrad, Limit Appendix I mrem) 10.0 mrad 0.OOE+00 0.00%

20.0 mrad 0.OOE+00 0.00%

5.0 mrem 7.33E-05 0.00%

15.0 mrem 0.00E+00 0.00%

15.0 mrem 8.41 E-05 0.00%

Gi-Lli 3.0 mrem 1.38E-02 l 0.46%

110.0rremr 3.93E-02 j 0.39%

liver Total body doses to individuals and populations in unrestricted areas from direct radiation from Zion Station are judged to be negligible in comparison with 10CFR20 annual limit of 100 mrem TEDE and 40CFR190 annual limits of 25 mrem DDE whole body, 75 mrem CDE thyroid, and 25 mrem CDE other organs.

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 DOSE TO PUBLIC UNIT 1 (Docket Number 50-295)

ADULT RECEPTOR I

Maximum Quarterly Dose (mrad, mrem) l Qtrly Ob 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr A. Airborne Gamma Air 5.0 mrad 0.OOE+00 0.OOE+00 0.OOE+00; 0.OOE+00l Beta Air 10.0 mrad O.00E+00 0.OOE+00 0.O0E+00 o.OOE+00 Total Body 2.5 mrem 0.00E+00 4.95E-05 0.OOE+00 2.69E-05 Skin 7.5 mrem 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Organ 7.5 mrem 0.00E+00 5.39E-05 0.OOE+00 3.16E-05 Critical Organ Gi-Lli Gi-Lli B. Aquatic Total Body 1.5 mrem 0.00E+00 0.OOE+00 I 1.64E-02 8.41E-03 I Internal Organ 5.0 mrem 0.OOE+00 0.OOE+00 2.50E-02 J1.28E-02 Critical Organ liver liver Yearly Maximum

%of Limit Annual Yearly Dose Dose 10CFR50 (mrad, Limit Appendix I mrem) 10.0 mrad 0.OOE+00 0.00%

20.0 mrad 0.OOE+00 0.00%

5.0 mrem 7.64E-05 0.00%

15.0 mrem O.00E+00 0.00%

15.0 mrem 8.55E-05 0.00%

Gi-Lli 3.0 mrem 2.48E-02 0.83%

110.0mreml 3.78E-02 0.38%

I liver Total body doses to individuals and populations in unrestricted areas from direct radiation from Zion Station are judged to be negligible in comparison with 10CFR20 annual limit of 100 mrem TEDE and 40CFR190 annual limits of 25 mrem DDE whole body, 75 mrem CDE thyroid, and 25 mrem CDE other organs.

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 DOSE TO PUBLIC UNIT 2 (Docket Number 50-304)

INFANT RECEPTOR Maximum Quarterly Dose (mrad, mrem l Qtrly Obj I 1st Qtr I 2nd Qtr I 3rd Qtr 4th Qtr A. Airborne Gamma Air 5.0 mrad 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Beta Air 10.0 mrad O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Total Body 2.5 mrem O.OOE+00 4.52E-05 9.35E-05 2.66E-05 Skin 7.5 mrem O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Organ 7.5 mrem 0.OOE+00 4.68E-05 9.68E-05 2.75E-05 Critical Organ Na Lung Lung Lung B. Aquatic Total Body 1.5 mrem 0.OOE+00 [0.OOE+00 O.OOE+00 0.OOE+00 Internal Organ 5.0 mrem 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Critical Organ N/A l

N/A N/A N/A Yearly Maximum

% of Limit Annual Yearly Dose Dose IOCFR50 (mrad, Limit Appendix I mrem) 10.0 mrad O.00E+00 0.00%

20.0 mrad 0.OOE+00 0.00%

5.0 mrem 1.65E-04 0.00%

15.0 mrem 0.00E+00 0.00%

15.0 mrem 1.71 E-04 0.00%

Lung 3.0mrem 0.0E+00I 0.00°/

10.0Lmrem I0.OOE+00 I 0.00%

I NIA Total body doses to individuals and populations in unrestricted areas from direct radiation from Zion Station are judged to be negligible in comparison with 10CFR20 annual limit of 100 mrem TEDE and 40CFRI90 annual limits of 25 mrem DDE whole body, 75 mrem CDE thyroid, and 25 mrem CDE other organs.

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 DOSE TO PUBLIC UNIT 2 (Docket Number 50-304)

CHILD RECEPTOR Maximum Quarterly Dose (mrad, mrem) 1 I Qtrly Obj I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I A. Airborne Gamma Air 5.0 mrad 0.OOE+00 j.OOE+00 0.OOE+00 0.OOE+00 Beta Air 10.0 mrad 0.OOE+00 0.OOE+00 0.00E+00 0:OOE+00 Total Body 2.5 mrem 0.OOE+00 4.75E-05 9.82E-05 2.78E-05 Skin 7.5 mrem 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Organ 7.5 mrem 0.OOE+00 4.99E-05 1.03E-04 2.93E-05 Critical Organ NA GI-Li GI-Li GI-Li B. Aquatic Total Body 1.5 mrem 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 Internal Organ 5.0 mrem 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Critical Organ N/A N/A N/A N/A Yearly Maximum

% of Limit Annual Yearly Dose Dose 10CFR50 (mrad, Limit Appendix I mrem) 10.0 mrad 0.OOE+00 0.00%

20.0 mrad 0.OOE+00 0.00%

5.0 mrem 1.74E-04 0.00%

15.0 mrem 0.OOE+00 0.00%

15.0 mrem 1.82E-04 0.00%

GI-LIi 3.0 mrem 0.00E+00 0.00%

l110.0Omrem 0.00E+00 0.00%

l NIA I

Total body doses to individuals and populations in unrestricted areas from direct radiation from Zion Station are judged to be negligible in comparison with IOCFR20 annual limit of 100 mrem TEDE and 40CFRI90 annual limits of 25 mrem DDE whole body, 75 mrem CDE thyroid, and 25 mrem CDE other organs.

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 DOSE TO PUBLIC UNIT 2 (Docket Number 50-304)

TEENAGE RECEPTOR I

Maximum Quarterly Dose (mrad, mrem I Qtrly Obj i 1 st Qtr I 2nd Qtr i 3rd Qtr 4th Qtr A. Airborne Gamma Air 5.0 mrad 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Beta Air 10.0 mrad 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 Total Body 2.5 mrem 0.OOE+00 4.62E-05 9.55E-05 2.71 E-05 Skin 7.5 mrem 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Organ 7.5 mrem 0.OOE+00 5.30E-05 1.1 OE-04 3.11 E-05 Critical Organ Na GI-Li GI-Li GI-Lli B. Aquatic Total Body 1.5 mrem 0.OOE+00 l0.OOE+00 0.OOE+00l 0.00E+00 Internal Organ 5.0 mreml 0.OOE+00 0.OOE+00 0.OOE+00 l 0.OOE+00 Critical Organ N/A N/A N/A j

N/A Yearly Maximum

% of Limit Annual Yearly Dose Dose 10CFR50 (mrad, Limit Appendix I mrem) 10.0 mrad 0.00E+00 0.00%

20.0 mrad 0.OOE+00 0.00%

5.0 mrem 1.69E-04 0.00%

15.0 mrem 0.OOE+00 0.00%

15.0 mrem 1.94E-04 0.00%

GI-Lli 3.0 mreml 0.00 E+00 I 0.00%

110.0 mrem 0.00 E+00 I 0.00%

I N/A Total body doses to individuals and populations in unrestricted areas from direct radiation from Zion Station are judged to be negligible in comparison with 1 OCFR20 annual limit of 100 mrem TEDE and 40CFR1 90 annual limits of 25 mrem DDE whole body, 75 mrem CDE thyroid, and 25 mrem CDE other organs.

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 DOSE TO PUBLIC UNIT 2 (Docket Number 50-304)

ADULT RECEPTOR Maximum Quarterly Dose (mrad, mrem) j Qtrly Obj 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr A. Airborne Gamma Air 5.0 mrad 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 Beta Air 10.0 mrad 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 Total Body 2.5 mrem 0.OOE+00 4.59E-05 9.48E-05 2.69E-05 Skin 7.5 mrem 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Organ 7.5 mrem 0.OOE+00 5.40E-05 1.11E-04 3.16E-05 Critical Organ Na GI-Li GI-li GI-Lli B. Aquatic Total Body 1.5 mrem 0.OOE+00 [0.OOE+00 0.OOE+00 l 0.OOE+00 Internal Organ 5.0 mrem 0.OOE+00 [.OOE+00 0.OOE+00 0.OOE+00 Critical Organ N/A N/A N/A N/A Yearly Maximum

% of Limit Annual Yearly Dose Dose 10CFR50 (mrad, Limit Appendix I mrem) 10.0 mrad 0.00E+00 0.00%

20.0 mrad 0.00E+00 0.00%

5.0 mrem 1.68E-04 0.00%

15.0 mrem 0.OOE+00 0.00%

15.0 mrem 1.97E-04 0.00%

GI-Li!

l3.0mrem l 0.OOE+00 I

0.00%

110.0mreml 0.OOE+00 I 0.00%

I N/A Total body doses to individuals and populations in unrestricted areas from direct radiation from Zion Station are judged to be negligible in comparison with 10CFR20 annual limit of 100 mrem TEDE and 40CFR190 annual limits of 25 mrem DDE whole body, 75 mrem CDE thyroid, and 25 mrem CDE other organs.

VSSI RETDAS v3.6.3 cZIO>

LIQUID ANNUAL DOSE

SUMMARY

REPORT

(PERIOD BASIS) --------

Report for:

2003 Release ID:

1 All Liquid Release Types Liquid Receptor

=== PERIOD DOSE BY ORGAN AND AGE GROUP (mrem)

QUARTER 1 Bone Liver Thyroid Kidney Lung GI-Lli Skin TB SITE DOSE LIMIT ANALYSIS Age Dose Limit Max % of Period -

Limit Group Organ (mrem)

(mrem)

Limit Qtr 1 Admin. Any Organ 0.OOE+00 3.75E+00 0.OOE+00 Qtr 1 -

Admin. Total Body ADULT TBODY 0.00E+00 1.13E+00 0.OOE+00 Qtr 1 -

T.Spec Any Organ 0.00E+00 1.50E+00 0.OOE+00 Critical Pathway: Potable Water (PWtr)

Major Contributors (

0% or greater to total)

Nuclide Percentage Qtr 1 -

T.Spec Total Body ADULT TBODY Critical Pathway: Potable Water (PWtr)

Major Contributors

(

0% or greater to total)

Nuclide Percentage 0.00E+00 1.50E+00 0.00E+00

RETDAS v3.6.3

<ZIO>

VSSI LIQUID ANNUAL DOSE

SUMMARY

REPORT

(PERIOD BASIS) --------

Report for:

2003 Release ID:

1 All Liquid Release Types Liquid Receptor

=== PERIOD DOSE BY ORGAN AND AGE GROUP (mrem)

QUARTER 2 Bone Liver Thyroid Kidney Lung GI-Lli Skin TB SITE DOSE LIMIT ANALYSIS

=

-==

Age Dose Limit Max % of Period -

Limit Group Organ (mrem)

(mrem)

Limit Qtr 2

- Admin. Any Organ 0.OOE+00 1.13E+00 0.OOE+00 Qtr 2

- Admin. Total Body ADULT TBODY 0.OOE+00 1.13E+00 0.OOE+00 Qtr 2 T.Spec Any Organ 0.OOE+00 1.50E+00 0.OOE+00 Critical Pathway: Potable Water (PWtr)

Major Contributors ( 0% or greater to total)

Nuclide Percentage Qtr 2 T.Spec Total Body ADULT TBODY Critical Pathway: Potable Water (PWtr)

Major Contributors ( 0% or greater to total)

Nuclide Percentage 0.OOE+00 1.50E+00 0.OOE+00

RETDAS v3.6.3 cZIO>

VSSI LIQUID ANNUAL DOSE

SUMMARY

REPORT

(PERIOD BASIS) --------

Report for:

2003 Release ID:

1 All Liquid Release Types Liquid Receptor PERIOD DOSE BY ORGAN AND AGE GROUP (mrem)==

QUARTER 3==

Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT 1.82E-02 2.50E-02 1.83E-07 8.48E-03 2.82E-03 5.91E-04 0.OOE+00 1.64E-02 TEEN 1.94E-02 2.60E-02 1.34E-07 8.84E-03 3.44E-03 4.44E-04 0.OOE+00 9.11E-03 CHILD 2.45E-02 2.36E-02 1.84E-07 7.67E-03 2.76E-03 1.74E-04 0.OOE+00 3.SlE-03 INFANT 2.59E-05 3.09E-05 1.26E-07 8.30E-06 3.44E-06 8.10E-07 0.OOE+00 2.88E-06

=== SITE DOSE LIMIT ANALYSIS =-

Age Dose Limit Max W of Period -

Limit Group Organ (mrem)

(mrem)

Limit Qtr 3 Admin. Any Organ TEEN LIVER 2.60E-02 Qtr 3 Admin. Total Body ADULT TBODY 1.64E-02 Qtr 3 T.Spec Any Organ TEEN LIVER 2.60E-02 Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 S.16E-04 CO-60 2.20E-02 CS-134 1.41E+00 CS-137 9.86E+01

3. 75E+00

1. 13E+00

5. OOE+00 6.94E-01 1.46E+00 5.20E-01 Qtr 3 -

T.Spec Total Body ADULT TBODY Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 1.11E-03 CO-60 7.70E-02 CS-134 1.80E+00 CS-137 9.81E+01 1.64E-02 1.50E+00 1.10E+00

RETDAS v3.6.3

<ZIO>

VSSI LIQUID ANNUAL DOSE

SUMMARY

REPORT

(PERIOD BASIS) --------

Report for:

2003 Release ID:

1 All Liquid Release Types Liquid Receptor PERIOD DOSE BY ORGAN AND AGE GROUP (mrem)

QUARTER 4 Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT 9.31E-03 1.28E-02 7.93E-08 4.34E-03 1.44E-03 3.02E-04 0.OOE+00 8.41E-03 TEEN 9.97E-03 1.33E-02 5.83E-08 4.53E-03 1.76E-03 2.27E-04 O.OOE+00 4.66E-03 CHILD 1.26E-02 1.21E-02 7.98E-08 3.93E-03 1.41E-03 B.88E-05 0.OOE+00 1.80E-03 INFANT 1.33E-05 1.58E-05 5.45E-08 4.25E-06 1.75E-06 4.01E-07 0.OOE+00 1.46E-06 SITE DOSE LIMIT ANALYSIS Age Dose Limit Max % of Period - Limit Group Organ (mrem)

(mrem)

Limit Qtr 4 -

Admin. Any Organ TEEN LIVER 1.33E-02 Qtr 4 -

Admin. Total Body ADULT TBODY 8.41E-03 Qtr 4 -

T.Spec Any Organ TEEN LIVER 1.33E-02 Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 4.37E-04 CO-60 2.17E-02 CS-134 1.07E+00 CS-137 9.89E+01

3. 75E+00

1. 13E+00

5. OOE+00 3.55E-01 7.48E-01 2.67E-01 Qtr 4 T.Spec Total Body ADULT TBODY Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors

(

0% or greater to total)

Nuclide Percentage H-3 9.42E-04 CO-60 7.58E-02 CS-134 1.37E+00 CS-137 9.86E+01 8.41E-03 1.50E+00 5.61E-01

RETDAS v3.6.3

<ZIO>

VSSI LIQUID ANNUAL DOSE

SUMMARY

REPORT

(PERIOD BASIS) --------

Report for:

2003 Release ID:

1 All Liquid Release Types Liquid Receptor PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) =

ANNUAL 2003========

Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT 2.75E-02 3.78E-02 2.62E-07 1.28E-02 4.26E-03 8.93E-04 0.00E+00 2.49E-02 TEEN 2.94E-02 3.93E-02 1.92E-07 1.34E-02 5.20E-03 6.71E-04 0.00E+00 1.38E-02 CHILD 3.70E-02 3.56E-02 2.64E-07 1.16E-02 4.17E-03 2.63E-04 0.00E+00 5.31E-03 INFANT 3.92E-05 4.67E-05 1.80E-07 1.25E-05 5.19E-06 1.21E-06 0.00E+00 4.34E-06 SITE DOSE LIMIT ANALYSIS===-

Age Dose Limit Max % of Period - Limit Group Organ (mrem)

(mrem)

Limit 2003

- Admin. Any Organ TEEN LIVER 3.93E-02 7.50E+00 5.25E-01 2003

- Admin. Total Body ADULT TBODY 2.49E-02 2.25E+00 1.10E+00 2003 T.Spec Any Organ TEEN LIVER 3.93E-02 1.00E+01 3.93E-01 Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors (

0% or greater to total)

Nuclide Percentage H-3 C0-60 CS-134 CS-137 4.89E-04 2.19E-02 1.29E+00

9. 87E+01 2003 T.Spec Total Body ADULT TBODY Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors (

0% or greater to total)

Nuclide Percentage H-3 1.05E-03 CO-60 7.66E-02 CS-134 1.65E+00 CS-137 9.83E+01 2.49E-02 3.OOE+00 8.28E-01

RETDAS v3.6.3

<ZIO>

VSSI GASEOUS ANNUAL DOSE

SUMMARY

REPORT

--(Composite Critical Receptor)---

Release ID: 1 All Gas Releases Coefficient Type: Historical I&P DOSE LIMIT ANALYSIS QUARTER 1 Age Dose Limit Max % of Period-Limit Group Organ (mrem)

(mrem)

Limit Q1 Admin. Any Organ 0.OOE+00 5.63E+0O 0.OOE+00 Ql Admin. Total Body 0.OOE+00 5.25E+00 0.OOE+00 Q1 T.Spec Any Organ 0.OOE+00 7.50E+00 0.OOE+00 Receptor: 0 Distance: 0.OOE+00 (meters)

Compass Point:

Critical Pathway:

Major Contributors ( 0% or greater to total)

Nuclide Percentage Q1 T.Spec Total Body Receptor: 0 Distance: 0.OOE+00 (meters)

Compas Critical Pathway:

Major Contributors ( 0% or greater to total)

Nuclide Percentage 0.OOE+00 7.50E+00 O.OOE+00 s Point:

RETDAS v3.6.3 ZZIO>

VSSI GASEOUS ANNUAL DOSE

SUMMARY

REPORT

---(Composite Critical Receptor)---

Release ID: 1 All Gas Releases Coefficient Type: Historical

2

NG DOSE LIMIT ANALYSIS===============================-QUARTER 1 Dose Limit

% of Period-Limit (mrad)

(mrad)

Limit Q1 Admin. Gamma 0.OOE+00 3.75E+00 0.OOE+00 Q1 Admin. Beta 0.OOE+00 7.50E+00 0.OOE+00 Q1

- T.Spec Gamma 0.OOE+00 5.00E+00 0.00E+00 Receptor: 0 Major Contributors (

0% or greater to total)

Nuclide Percentage Q1 T.Spec Beta Receptor:

0 Major Contributors ( 0% or greater to total)

Nuclide Percentage 0.OOE+00 1.OOE+01 O.OOE+00

RETDAS v3.6.3 cZIO>

VSSI GASEOUS ANNUAL DOSE

SUMMARY

REPORT

--(Composite Critical Receptor)---

Release ID: 1 All Gas Releases Coefficient Type: Historical I&P DOSE LIMIT ANALYSIS QUARTER 2 Age Dose Limit Max % of Period-Limit Group Organ (mrem)

(mrem)

Limit Q2

- Admin. Any Organ ADULT GILLI 1.08E-04 5.63E+00 1.92E-03 Q2

- Admin. Total Body CHILD 9.50E-05 5.25E+00 1.81E-03 Q2

- T.Spec Any Organ ADULT GILLI 1.08E-04 7.50E+00 1.44E-03 Receptor: 5 Composite Crit. Receptor -

IP Distance: 0.00E+00 (meters)

Compass Point:NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors (

0% or greater to total)

Nuclide Percentage CO-60 1.OOE+02 Q2 T.Spec Total Body CHILD 9.50E-05 7.50E+00 1.27E-03 Receptor: 5 Composite Crit. Receptor -

IP Distance: 0.OOE+00 (meters)

Compass Point:NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors (

0% or greater to total)

Nuclide Percentage CO-60 1.OOE+02

RETDAS v3.6.3 CZIO>

VSS I GASEOUS ANNUAL DOSE

SUMMARY

REPORT

-- (Composite Critical Receptor)---

Release ID: 1 All Gas Releases Coefficient Type: Historical NG DOSE LIMIT ANALYSIS QUARTER 2 Dose Limit

% of Period-Limit (mrad)

(mrad)

Limit Q2

- Admin.

Gamma O.OOE+00 3.75E+00 0.OOE+00 Q2 Admin. Beta 0.OOE+00 7.50E+00 0.OOE+00 Q2 T.Spec Gamma O.OOE+00 5.00E+00 0.OOE+00 Receptor: 5 Composite Crit. Receptor -

IP Major Contributors ( 0% or greater to total)

Nuclide Percentage Q2 T.Spec Beta Receptor: 5 Composite Crit. Receptor -

IP Major Contributors ( 0% or greater to total)

Nuclide Percentage 0.OOE+00 1.OOE+01 0.OOE+00

RETDAS v3.6.3

<ZIO>

VSSI GASEOUS ANNUAL DOSE

SUMMARY

REPORT

--(Composite Critical Receptor)---

Release ID: 1 All Gas Releases Coefficient Type: Historical I&P DOSE LIMIT ANALYSIS QUARTER 3 Age Dose Limit Max V of Period-Limit Group Organ (mrem)

(mrem)

Limit Q3 Admin. Any Organ ADULT GILLI l.llE-04 5.63E+00 1.98E-03 Q3 Admin. Total Body CHILD 9.82E-05 5.25E+00 1.87E-03 Q3 T.Spec Any Organ ADULT GILLI l.llE-04 7.50E+00 1.49E-03 Receptor: 5 Composite Crit. Receptor -

IP Distance: O.OOE+00 (meters)

Compass Point:NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors ( 0% or greater to total)

Nuclide Percentage C-________

CO-60

1. OOE+02 Q3 T.Spec Total Body CHILD 9.82E-05 7.50E+00 1.31E-03 Receptor: 5 Composite Crit. Receptor -

IP Distance: 0.OOE+00 (meters)

Compass Point:NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors ( 0t or greater to total)

Nuclide Percentage CO-60 1.OOE+02

RETDAS v3.6.3 RZIO>

VSSI GASEOUS ANNUAL DOSE

SUMMARY

REPORT

--(Composite Critical Receptor)---

Release ID: 1 All Gas Releases Coefficient Type: Historical NG DOSE LIMIT ANALYSIS QUARTER 3 Dose Limit t of Period-Limit (mrad)

(mrad)

Limit Q3

- Admin.

Gamma O.OOE+00 3.75E+00 O.OOE+00 Q3 Admin. Beta O.OOE+00 7.50E+00 O.OOE+00 Q3 T.Spec Gamma 0.00E+00 5.OOE+00 0.00E+00 Receptor: 5 Composite Crit. Receptor -

IP Major Contributors (

0% or greater to total)

Nuclide Percentage Q3 T.Spec Beta Receptor: 5 Composite Crit. Receptor -

IP Major Contributors ( 0% or greater to total)

Nuclide Percentage 0.OOE+00 1.00E+01 0.OOE+00

RETDAS v3.6.3

<ZIO>

VSSI GASEOUS ANNUAL DOSE

SUMMARY

REPORT

-- (Composite Critical Receptor) ---

Release ID: 1 All Gas Releases Coefficient Type: Historical

=== I&P DOSE LIMIT ANALYSIS QUARTER 4 Age Dose Limit Max % of Period-Limit Group Organ (mrem)

(mrem)

Limit Q4 Admin. Any Organ ADULT GILLI 6.32E-05 Q4

- Admin. Total Body CHILD 5.57E-05 Q4

- T.Spec Any Organ ADULT GILLI 6.32E-05 Receptor: 5 Composite Crit. Receptor -

IP Distance: 0.00E+00 (meters)

Compass Point:NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors (

0% or greater to total)

Nuclide Percentage

5. 63E+00 5.25E+00

7. 50E+00 1.12E-03 1.06E-03 8.43E-04 CO-60

1. OOE+02 Q4 T.Spec Total Body CHILD 5.57E-05 7.50E+00 7.43E-04 Receptor: 5 Composite Crit. Receptor -

IP Distance: 0.OOE+00 (meters)

Compass Point:NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors ( 0% or greater to total)

Nuclide Percentage CO-60 1.00E+02

RETDAS v3.6.3 RZIO>

VSSI GASEOUS ANNUAL DOSE

SUMMARY

REPORT

--(Composite Critical Receptor)---

Release ID: 1 All Gas Releases Coefficient Type: Historical NG DOSE LIMIT ANALYSIS QUARTER 4 Dose Limit

% of Period-Limit (mrad)

(mrad)

Limit Q4 Admin. Gamma O.OOE+00 3.75E+00 O.OOE+00 Q4 Admin. Beta O.OOE+00 7.50E+00 O.OOE+00 Q4 T.Spec Gamma O.OOE+00 5.OOE+00 O.OOE+00 Receptor: 5 Composite Crit. Receptor -

IP Major Contributors ( 0 or greater to total)

Nuclide Percentage Q4 T.Spec Beta Receptor: 5 Composite Crit. Receptor -

IP Major Contributors ( 0% or greater to total)

Nuclide Percentage O.OOE+00 1.OOE+01 0.OOE+00

RETDAS v3.6.3

<ZIO>

VSSI GASEOUS ANNUAL DOSE

SUMMARY

REPORT

--(Composite Critical Receptor)---

Release ID: 1 All Gas Releases Coefficient Type: Historical I&P DOSE LIMIT ANALYSIS ANNUAL 2003=========

Age Dose Limit Max % of Period-Limit Group Organ (mrem)

(mrem)

Limit 2003 -

Admin. Any Organ ADULT GILLI 2.82E-04 1.13E+01 2.51E-03 2003 -

Admin. Total Body CHILD 2.49E-04 1.05E+01 2.37E-03 2003 -

T.Spec Any Organ ADULT GILLI 2.82E-04 1.50E+01 1.88E-03 Receptor: 5 Composite Crit. Receptor -

IP Distance: 0.OOE+00 (meters)

Compass Point:NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors ( 0t or greater to total)

Nuclide Percentage CO-60 1.OOE+02 2003 -

T.Spec Total Body CHILD 2.49E-04 1.50E+01 1.66E-03 Receptor: 5 Composite Crit. Receptor -

IP Distance: 0.OOE+00 (meters)

Compass Point:NA Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors ( 0% or greater to total)

Nuclide Percentage CO-60 1.00E+02

RETDAS v3.6.3 (ZIO>

VSSI GASEOUS ANNUAL DOSE

SUMMARY

REPORT

---(Composite Critical Receptor) ---

Release ID: 1 All Gas Releases Coefficient Type: Historical NG DOSE LIMIT ANALYSIS ANNUAL 2003=========

Dose Limit

% of Period-Limit (mrad)

(mrad)

Limit

__003_

Admin.

-Gamma-

-OE__________---

2003 - Admin. Gamma 0.OOE+00 7.50E+0l 0.OOE+00 2003 - Admin. Beta 0.00E+00 1.50E+01 0.00E+00 2003 -

T.Spec Gamma 0.OOE+00 1.OOE+01 0.OOE+00 Receptor: 5 Composite Crit. Receptor -

IP Major Contributors ( 0% or greater to total)

Nuclide Percentage 2003 -

T.Spec Beta Receptor: 5 Composite Crit. Receptor -

IP Major Contributors (

0% or greater to total)

Nuclide Percentage 0.00E+00 2.00E+01 0.OOE+00

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 UNIT 1 (Docket Number 50-295)

GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION

1. Regulatory Limits See "Unit 1 & 2 GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION"

2.

Maximum Permissible Concentrations See "Unit 1 & 2 GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION"

3. Average Energy See "Unit 1 & 2 GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION"

4. Measurements and Approximations of Total Radioactivity See "Unit 1 & 2 GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION"

5.

Batch Releases 1st Qtr 2nd Qtr 3rd Qtr

a. Total Number of Batch 0

0 0

Releases

b. Total Time Period for Batch O.oOE+00 0.OOE+00 0.OOE+00 Releases (minutes)

c.

Maximum Time Period for a O.OOE+00 0.OOE+00 O.OOE+00 Batch Release (minutes)

d. Average Time Period for a O.ooE+00 0.OOE+00 0.OOE+00 Batch Release (minutes)

e. Minimum Time Period for a O.OOE+00 O.OOE+00 O.OOE+00 Batch Release (minutes)

6. Abnormal Releases

a. Number of Releases 0

0 0

b. Total Activity Released (Ci) 0.OOE+00 0.OOE+00 0.00E+00 4th Qtr 0

0.00E+00 0.00E+00 0.00E+00 0.00E+00 2003 0

O.OOE+00 O.OOE+OO O.OOE+O0 O.OOE+00 0

0 0.00E+00 0.OOE+00

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 UNIT 2 (Docket Number 50-304)

GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION

1. Regulatory Limits See "Unit 1 & 2 GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION"

2. Maximum Permissible Concentrations See "Unit I & 2 GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION"

3. Average Energy See "Unit 1 & 2 GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION"

4. Measurements and Approximations of Total Radioactivity See "Unit 1 & 2 GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION"

5. Batch Releases 1st Qtr 2nd Qtr 3rd Qtr

a. Total Number of Batch 0

0 0

Releases

b. Total Time Period for Batch 0.OOE+00 0.OOE+00 0.OOE+00 Releases (minutes)

c. Maximum Time Period for a 0.OOE+00 0.OOE+00 0.OOE+00 Batch Release (minutes)

d. Average Time Period for a 0.OOE+00 0.OOE+00 0.OOE+00 Batch Release (minutes)

e. Minimum Time Period for a 0.OOE+00 0.OOE+00 0.OOE+00 Batch Release (minutes)

6.

Abnormal Releases

a. Number of Releases 0

0 0

b. Total Activity Released (Ci) 0.OOE+00 0.OOE+00 0.OOE+00 4th Qtr 0

0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 2003 0

0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0

O.OOE+00 0

0.OOE+00

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 UNIT 1 & 2 (Docket Numbers 50-295 & 50-304)

GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION

1. Regulatory Limits The calculated annual total quantity of all radioactive material above background released from each unit at Zion Station to the atmosphere is limited by off-site dose restrictions stated in the station technical specifications, Off-site Dose Calculation Manual (ODCM), and 10CFR50 Appendix 1. The off-site dose limits per reactor unit are listed below.

Quarterly Yearly (mrem)

(mrem)

Gamma Air Beta Air Total Body Skin Organ 5

10 2.5 7.5 7.5 10 20 5

15 15

2. Maximum Permissible Concentrations Zion Station gaseous effluent release-rate limits were not calculated using maximum permissible concentra-tions of activity. Gaseous effluent activity release rates are limited by off-site dose-rate restrictions stated in station technical specifications and the ODCM. The release-rate limits were determined by using the ODCM computer code to calculate release rates which would produce a specified instantaneous dose rate at the site boundary. The off-site dose-rate limits are listed below.

Noble Gases Noble Gases 1-131, 1-133, H-3, and particulates with half-lives greater than 8 days 500 mrem/year Total Body 3000 mremlyear Skin 1500 mrem/year Organ

3. Average Energy There were no measurable noble gas releases during 2003. Due to permanent cessation of operation and radioactive decay, the only gas available for release is Kr-85 present in spent fuel rods.

Isotope Kr-85 Percent of Effluent 100 Average Gamma Energy per Decay of the Mixture (keV)

Average Beta Energy per Decay of the Mixture (keV) 5.0 269.0

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 UNIT 1 & 2 (Docket Numbers 50-295 & 50-304)

GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION

4. Measurements and Approximations of Total Radioactivity

a. Fission and Activation Gases Gamma Spectroscopy

b. lodines Gamma Spectroscopy

c.

Particulates Gamma Spectroscopy, Liquid Scintillation Gas Flow Proportional Counting

d. Tritium Liquid Scintillation Composite sample analyses for gross alpha, Sr-89, and Sr-90 are performed by off-site vendor.

5. Batch Releases

a. Total Number of Batch Releases

b. Total Time Period for Batch Releases (minutes)

c.

Maximum Time Period for a Batch Release (minutes)

d. Average Time Period for a Batch Release (minutes)

e. Minimum Time Period for a Batch Release (minutes) 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr 2003 0

0 0

0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.OOE+00 O.OOE+00

6. Abnormal Releases

a. Number of Releases

b. Total Activity Released (Ci) 0 0

0 0

0 0.OOE+00 0.OOE+0O 0.OOE+00 0.OOE+00 0.00E+00

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 GASEOUS EFFLUENTS - ALL RELEASES ARE AT GROUND LEVEL UNIT 1 (Docket Number 50-295)

SUMMATION OF ALL RELEASES I Units I Jan I

Feb I

Mar I istQtr IApr IMay IJun I2nd Qtr IJul IAug ISep I3rd Qtr IOct INov IDec I4th Qtr I Total

-I A. Fission and Activation Gases

1. Total Release Activity Ci

<LLD

<CLD

<LLD

'<LLD 0.002+00

12. Average Release Rate uCi/sec

<LLD

<CLLD

<LLD

-9LLD 0.002+00 B. Iodine

1. Total 1-1 31 Activity Ci

<LLD

<LLD cLLD

<LLD

<LLD cLLD 0.002+00 J2. Average Release Rate uCllsee

.CLDLD LLD LD <CLLD

<LLD

<LLD CILD <LLD <

LLD

<LLD

<LLD <

LLD I

1D LLD I0.002+00 C. Particulates (halt-lives > 8 days)

Ii. Total Release Activity4 I

Ci I<LLD I<LLD I<LLD I<LLD I<LLD I1.02E-06 I

<LD 1

I.0212-06 I<LLD I<LLD I41--1

< LLD I<LLD I5.93E-07 I <LLD I 5.93E-07 1 1.61 E-06

12. Average Release Rate IuCi/sec:

<LLD I<LLD I<LLD I

<LLD I<LLD 3.81E-07

<LLD 1.30E-07 I<LLD I<LLD I<LLD I<LLD

<LLD 2.29E-07 I LD I7.46E-08 15.11 E-09

13. Gross Alpha Activiyt Ci I

I

LLD, I

4<LD I

LLD I

LLD D. Tritium

1. Total Release Activity Ci I<LLD

<LLD

<LLD 0.OOE+O0

12. Average Release Rate uCi/sec I<LLD

<LLD

<LLD 0.OOE+00 E. Sum of Iodine, Particulate (half-lives > 8 days),

and Tritlum Releases.

1. Total Release Activity Ci 0.002+00 1,.00E+00 0.00E+00 0.00E+00 0.002+00 1.02E-06 0.OOE+00 1.02E-06 0.002+00 0.OOE+00 0.002+00 0.002+00 0.002+00 5.932-07 0.002+00 5.93E-07 161-0 t Gross Alpha, Sr-89, and Sr-SO Activities are quantified by quarterly composite analyses. The difference between the quarterly Particulates total and the Sum of the totals of the three corresponding months equals the total quarterly activities of Sr-89 and Sr-SO. The cells for monthly activity values of Gross Alpha on this page and Sr-89 and Sr-9O on the Batch and Continuous Mode data sheets are blank because monthly values are not applicable.

Lower limit of detection (LLD) values are presented in the Gaseous Effluents LLD Values for Gaseous Releases section. The abbreviation '<LLD" indicates the activity concentration of the radionuclide for each Individual sample analyzed during the applicable period was less than the LLD value for that nuclide. If the abbreviation '<LLD" is listed for a group of radionuclides, the activity concentration of each radionuclide for each sample during the period was less than the LLD value for the respective radionuclide.

Percent of technical specification limit information is presented In the Gaseous Effluents Supplemental Information and Dose to Public sections of this report.

The abbreviation "No Rel" indicates that no batch releases were performed during the applicable period.

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 GASEOUS EFFLUENTS - ALL RELEASES ARE AT GROUND LEVEL UNIT 1 (Docket Number 50-295)

BATCH MODE Units Jan I

Feb I

Mar 1st Qtr Apr I

MaY I

Jun I 2nd Qtr I Jul Aug Sep 3rd Qtr Oct Nov I

Dec I 4th Qtr Total A. Fission and Activation Gases Ar-41 Cl No Re!

No Re!

No Rel No Re[

No Rel No Rel No Re!

No Rel No Re!

No Re!

No Rel No Rel No Re!

No Rel No Rel No Rel

<LLD Kr-85 Ci No Rel No Rel No Rel No Re!

No Rel No Rel No Rel No Re!

No Rel No Rel No Rel No Rel No Rel No Re!

No Rel No Re!

<LLD Kr-85m C!

No Re!

No Rel No Rel No Re!

No Rel No Re!

No Rel No Rel No Rel No Rel No Rel No Rel No Re!

No Rel No Re!

cLLD Kr-87 Ci No Rel No Rel No Re!

No Re!

No Rel No Re!

No Rel No Rel No Rel No Rel No Rel No Re!

No Rel No Re!

No Rel cLLD Kr-88 Cl No Re!

No Rel No Re!

No Rel No Rel No Re!

No Re!

No Rel No Rel No Re!

No Re!

No Rel No Rel cLLD Xe-131 Ci No Re!

No Re!

No Rel No Rel No Rel No Re!

No Rel No Re!

No Rel No Rel No Re!

No Rel No Rel

<LLD Xe-131m C!

No Re No Re!

No Re!

No Rel No Rel No Rel No Rel No R No Re!

No Re!

cLLD Xe-133 Ci No Rel No Re!

No Rel No Rel No No!

No No NR No N

No No Re!

No Re!

No Rei cLLD Xe-133m Ci No Rel No Rel No Rel No Rel No Rel No Rel No Re!

No Re!

No Rel No Re!

No Rel No Rel No Rel No Rel No Rel cLLD Xe-1353 Ci No Rel No Rei No Rel No Rel No Re!

No Rel No Rel No Rel No Re!

No Re!

No Rel No Re!

No Rel No Rel No Rel No Rel

<LLD Xe-135m Ci No Rel No Re No Re No Re No R!

N Re!

No R!

No R No Re!

No Re!

lNoe!

No Re!

No R!

N LLD Xe-138 Ci No Rel No Re!

No Rel No Rel No Rel No Rel No Re!

No Re!

No Rel No Rel No Rei No Rel

<LLD B. lodines Br-82 Ci No Rel No Rel No Rel No Re!

No Re!

No Rel No Rel [

No Rel No Re! l No Rel No Rel No Rel No Rel No Rel l No Rel No Rel

<LLD 1-131 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel l No Rel No Rel No Re!

No Rel No Rel No Rel No Re!

<LLD 1-132 C!

No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Re!

No Rel J No Re!

No Rel No Rel No Rel No Re!

<LLD 1-133 C!

No Re!

No Rel No Rel No Re!

No Re!

No Rel No Rel No Rel No Re!

No Re!

No Rel No Rel No Rel No Rel No Rel

<LLD 1-134 C!

No Re!

No Rel No Rei No Re!

No Rel No Re!

No Rel No Rel No Rel No Re!

No Rel NoRel!

No Rel No Re!l LLD 1-135 Ci No Rel No Re!

No Rel No Rel No Rel No Re!

No Rel No Rel No Re!

No Rel No Re!

No Rel No Rel No Reol LLD C. Particulates Na-24 C!

No Re!

No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Re!

No Rel No Rel No Rel No Re!

No Rel No Rel No Rel No Rel Cr Ci No Rel No Re!

No Re!

No Rel No Re!

No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel Mn-54I C!

No Rel No Re!

No Rel No Rel No Rel No Rel No ReI No Rel No Re!

No Re!

No Rel No Rei Co Ci No Rel No Rel No Re!

No Rel No Rel No Re!

No Rel No Rel No Rel No Re!

No Re!

No Rel Co-58*

Cl No Re!

No Re!

No Rel No Rel No Rel No Re!

No Re!

No Rel No Rel No Re!

No Re!

No Rel No Rel No Rel Co-60*

C!

No Rel No Re!

No Rel No Rel No Rel No Rel No Rel No Rel No Re!

No Rel No Rel No Rel No Rel No Rel No Rel Zn-65s Ci No Rel No Rel No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Rel No Rel No Rel No Rel No Re!

No Rel Se-75' Cl I No Re!

No ReI No Re!

No Rel No Rel I No Rel No Re! I No Rel No Rel I No Rel No Rel No ReI No Rel I No Rel No Rel No Rel No Rel Rb-88 Ci No ReI No Re!

No Rel No Re!

No Rel No Rel No Rel No Rel No Rel No Rel No Re!

No Rel No Rel No Rel No Rel No Rel No Rel Sr-89*

C!

No Re!ol No Re!ol No Re!_

No Re!

Sr-901 C!

I___ No Re!

No Re!ol__

No Re!

No Re!_

zr CI No Re!

No Rel No Rel No Rel No Rel No Re!

No Re!

No Rel No Rel No Rel No Rel No Rei No Rel No Rel No Rel No Rei No Rel Nb-959 C!

No Re!

No Rel No Rel No Re!

No Re!

No Rel No Rel No Re!

No Rel No Re!

No Rel No Rel No Re!

No ReI No ReI No Re!

No Rel Mo-99 Ci No Rel No Re!

No Re!

No Rel No Rel No Rel No Rel No Re!

No Re!

No Rel No Rel No Rel No Rel No Rel No Rel No Rel Tc-99m Ci No Rel No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Rel I No Re!

No Re!

No Rel No Rel No Rel No Rel No Rel No Rel No Re!

Ru-103m Ci No Re!

No Rel No Rel No Rel No Re!

No Re!

No Rel No Rel No Re!

No Rel No Rel No Rel No Rel No Rel No Re!

No Re!

No Rel Ag-1 10m Cl No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Re!

No Rel No Rel No Re!

No Re!

No Rel Cs-134I C!

No ReI No Rel I No Rel No Rel No Rel No Rel No Rel No Rel No Rei No Rel No ReI No ReI No Rel No Rel No Rel No Rel No Re!

Cs-1367 Ci No Rel No Rel No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Rel No Rel No Re!

No Rel No Rel No Rel No Rel No Re!

Cs-137T Ci No Rel No Re!

No Rel No Rel No Rel No Re!

No Re!

No Rel No Rel No Re!

No Rel No Re!

No Rel No Rel No Rel No Rel No Re!

Cs-138 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Re!

No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Re!

No Re!

No Rel Ba-140*

Cl No Rel No ReI No Re!

No Rel No Rel No Rel N

e No Re!

No Re!

No Rie La-140 Cl No Re!

No Rel No Rel No ReI No Rel No Re!

No Re!

No Rel No Rel I No Rel No Rel No Rel I No Re!

No Rel No Rel No Rel No Rel Ce-1441 C!

No Re!

NoRe No Re!

No Re!

o R!

N Re!

No Re!

oR!

N e

oR!

N R!

N e oR!

N e

Pr-144 Ci No Rel No Re!

-No Rel No Re N Re!

No Re!

N R o Re!

No No!

No R Re!

No Re!

No Rle W-187 Ci No Rel No Re!

No Rel INo e!

No Re! I No Re!

No Re!

No Re! I No Re!

I No Re! I No Rel I No Re! I No Rel l

No Re!

0. Tritium

1. Total Release Activity Ci I No Re!

No Re! I No Rel I No Re!

No Re! I No Re!

I No Rel I No Re!

I No Rel I No Rel I No Rel I No Re!

I No Rel I No Rel I No Rel No Rel No Rel Particulate isotope with half-life greater than 8 days.

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 GASEOUS EFFLUENTS -ALL RELEASES ARE AT GROUND LEVEL UNIT 1 (Docket Number 50-295)

CONTINUOUS MODE I Units I Jan I

Feb I

Mar I 1stQtr I Aar I

May I

Jun I 2nd Qtr I Jul I

Aua I

Sen I 3rd Qtr I Oct I

Nov I

Dec I 4th Qtr I Total I

A. Fission and ActIvatIon Gases Ar-41 Cl

<LLD

<LLD CLLD

<LLD CLD

<LLD

<LLD Kr-85 Ci

<LLD

<LLD CLLD

<LLD Kr-85m Ci

<LLD

<LLD CLLD

<LLD

<LLD CLLD

<LLD

<LLD CLLD

<LLD Kr-87 Ci

<LLD

<LLD CLLD

<LLD

<LLD Kr-88 Ci

<LLD

<LLD CLLD

<LLD

<LLD CLLD

<LLD Xe-131 Ci

<LLD

<LLD Xe-131m Ci

<LLD

<LLD CLLD

<LLD

<LLD CLLD Xe133 Ci

<LLD

<LD CLLD CLLD CLLD

<LLD

<LLD CLLD

<LLD

<LLD CLLD

<LLD CLLD CLLD

<LLD

<LLD Xe-133m Ci

<LLD

<LLD CLLD

_LLD LDWLD <LLD

<LLD

<LD L

LDLD

<LLD

<LLD Xe-135 Ci

<LLD

<LLD CLLD

<LLD

<LD

<LLD CLLD QLLD Xe-135m Ci

<LLD

<LLD DLLD <LLD

<LLD

<LLD Xe-138 Ci

<LLD

<LLD CLLD

<LLD

<LLD <

LLD C LLD

<LLD

<LLD dLD CLLD

<LLD B. lodines Br-82 Ci

<LLD

<LLD CLLD

<LLD l

LLD

<LLD l LLD

<LLD

<LLD 1-131 Ci

<LLD

<LLD CLLD

<LLD

<LLD T

LLD

<LLD

<LLD 1-132 Ci

<LLD

<LLD l

LD

<LLD l

LLD

<LLD 1-133 Ci

<LLD

<CLLD

<LLD

<LLD T LD

<LLD CLLD

<LLD 1-134 Ci

<LLD

<LLD l

LLD

<LLD l LLD

<LLD

<LLD 1-135 Ci

<LLD

<LLD l

LLD

<LLD

<LLD C. Particulates Na-24 Ci

<LLD

<LLD CLLD

<LLD

<LD lCLD I

LLD

<LLD Cr Ci

<LLD

<LD

<LLD

<LD LLD

<LLD

<LD LD l

LLD lILD l LLD

<LLD

<LLD Mn-54 CI

<LLD

<ILLD

<LLD

<LD

<LLD

<LD

<ILD

<LLD

<ILLD

<LLD

<LLD LLD

<ILLD I

LLD ILLD Co-57l Ci

<LLD

<LLD CLLD CLLD Co-58 Cl

<LD

<LID

<LLD

<1

<L LD 1

CLD

<LD <LLD l

LL LLD

<LLD

<LLD lLLD

<LLD

<LW Co Ci

<LLD

<LLD 1.02E-06

<LLD 1.02E46l

<LLD

<lLD

<LLD

<LLD 5.93E-07

<LLD 5.93E407 1.61EE-06 Zn Ci

<LLD

<LID

<LLD

<LLD Se Ci

<LLD

<LLD I

LLD LLW

<LLD T LLD

<LLD LLD

<LLD

<LLD D LLD LD

<LLD

<LID ILLD

<LLD Rb-88 CI

<LLD

<LD

<LLD

<LLD ILLD

<LLD l CLD

<LLD Sr-891 CI T

<LLD

<LLD CLLD

<LLD Sr-90l Ci l

<LLD

<LLD CLLD

<LLD Zr-95l CI

<LLD

<LLD I <LLD l

LID l LLD l LLD lLLD lLLD

<LLD

<LLD CLLD LLLD

<LLD lLD <LLD

<LID Nb-95l Cl

<LLD

<LLD l

LLD

<LLD

<LLD CLLD

<LLD MO-99 CI

<LLD

<LD

<LLD

<LLD LLD

<LLD

<LLD Tc-99m Ci

<LLD

<LLD l

CLLD I <LLD

<LLD I

<LLD

<LLD I

<LLD

<LLD Ru-103I CI

<LLD

<LLD I <LLD

<LLD

<ICLLD

<LLD I

LLD

<LLD

<LLD A -110m CI

<LLD

<LLD I

LD

<LLD ILLD

<LLD Cs-134 Ci

<LLD

<ILLD

<LLD

<ILLD

<LLD

<ILLD

<LLD

<ILLD

<ILLD Cs-136 CI

<LLD

<LD

<LLD

<LD

<LLD

<LLD TLLD

<LLD

<LLD Cs-137-Ci

<LLD

<LLD ILLD

<LLD

<LLD CS-138 Ci

<LLD

<ILLD

<LLD

<LLD I<LLD

<LLD

<LLD Ba-140 C;

<LLD

<ILD

<LLD

<rLD

<LLD

<LLD I LLD

<ILLD

<LLD

<LLD La-140 CI

<LLD

<D <

I LLD

<LLD,

<LLD

<LD I

LLD

<LD CLLD

<LLD Ce-144I C!

I LLD

<LLD

<LLD l

LLD D

<LLD LD LLD

,LLD

<LLD

<LLD I

LLD ILD

<LLD ID l CLD I LLD Pr-144I C

LLD LLD

<LL l

LLD LL D LLLD LLL D

<LLD

<LL D

<LD lLLD l

LLD l

LID W-187 Ci

<LLD

<LLD I <LLD

<LLD

<LLD I

LLD

<LLD

<LLD D.

Trltum

1. Total Release Activity Ci

<LLD

<LLD I

<LLD

<LLD I <LLD

<LLD

<LLD ICLLD

<LLD

<ILLD I Particulate isotope with half-life greater than 8 days.

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 GASEOUS EFFLUENTS - ALL RELEASES ARE AT GROUND LEVEL UNIT 2 (Docket Number 50-304)

SUMMATION OF ALL RELEASES Units I Jan IFeb I

Mar I1lst Otrt Apr IMay Jun I2nd Qtr I Jul Aug Sep 3rd Ott Oct INov IDec I 4th Otr I Total A. Fission and Activation Gases

1. Total Release Activit C I

<LID I<LID I<LLD I<LID I<LLD0

<LID I<LLD I<LLD I<LLD

<LID I<LID I<LLD

<LLD I<LID I<LLD I<LLD I

.OOE+00

12. Average Release Rate IuCI/sec I<-LLD I<LID I<LD I<LLD

<LLD

<LID

<LLD

<LID I<LLD

<LLD

<LID I<LID

<LLD

<LLD 0.008+00 B. Iodine 1I. Total 1-1 31 Activity Cl

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LLD 0.00E+00

12. Average Release Rate uCi/sec

<LLD

<cLLD

<LLD

<LID

<LLD

<LLD 0.00E+00 C. Particulates (half-lives > 8 days)

Ii. Total Release Activity~l I

Ci I <LLD I <LLD I <LLD I<LLD I<LID I1.02E-06 I<LLD I1.02E-08

<LLD I2.09E-06 I<LID I2.09E-06 I<LLD I5.93E-07 I<LLD 5.93E-07 I3.70E-06

12. Average Release Rate IuCl/sec I<LID I<LID

<LID I<LLD I<LID I3.81E-07 I<LLD I1.30E-08 I<LLD I7.80E-07

<LLD 2.63E-07

<LID 2.29E-07 I<LLD I7.46E-09 I1.117E-08

13. Gross Alpha Activiyt ClI

<LLD I<LLD I<LLD I<LID I

<LLD D. Tritium

1. Total Release Activity Ci I<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LLD 0.00E+00

12. Average Release Rate uCilsec I<LLD

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD 0.00E+00 E. Sum of Iodine, Particulate (half-lives > 8 days),

and Tritium Releases.

1. Total Release Activity Ci I0.OOE+00 I.OOE+00 0.OOE+00 0.00E+00 0.00E+00 1.02E-06 0.OOE+00 1.02E-08 O.OOE+00 2.09E-06 O.00E+00 2.09E-06 0.OOE+00 5.93E-07 0.OOE+00 5.93E.07 3.70E86-06 Gross Alpha, Sr-89, and Sr-9O Activities are quantified by quarterly composite analyses. The difference between the quarterly Particulates total and the sum of the totals of the three corresponding months equals the total quarterly activities of Sr-89 and Sr-9O. The cells for monthly activity values of Gross Alpha on this page and Sr-89 and Sr-SO on the Batch and Continuous Mode data sheets are blank because monthly values are not applicable.

Lower limit of detection (LLD) values are presented in the Gaseous Effluents LLD Values for Gaseous Releases section. The abbreviation "<LLD" indicates the activity concentration of the radionuclide for each individual sample analyzed during the applicable period was less than the LLD value for that nuclide. If the abbreviation `<LID" is listed for a group of radionuclides, the activity concentration of each radionuclide for each sample during the period was less than the LLD value for the respective radionuclide.

Percent of technical specification limit information is presented in the Gaseous Effluents Supplemental Information and Dose to Public sections of this report.

The abbreviation "No Ret" indicates that no batch releases were performed during the applicable period.

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 GASEOUS EFFLUENTS - ALL RELEASES ARE AT GROUND LEVEL UNIT 2 (Docket Number 50-304)

BATCH MODE Units Jan IFeb Mar I 1stQtr Apr I

May I

Jun I 2ndQtr I

Jul I

Aug Sep 3rdQtr Oct Nov I

Dec 4th Qtr Total A. Fission and ActIvation Gases Ar-41 Ci No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel

<LLD Kr-85 Ci No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret

<LLD Kr-85m Cl No Ret No Rei No Ret No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret cLLD Kr-87 Ci No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret No Rel No Ret No Ret No Rel No Ret No Ret No Ret No Rel

<LLD Kr-88 Cl No Ret No Rel No Ret No Rel No Ret No Rei No Ret No Rel No Ret No Rel No Ret No Rel No Ret No Ret No Ret No Ret

<LLD Xe-131 Cl No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret No Rel No Ret No Ret No Rel cLLD Xe-131m Ci No Rei No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel No Ret No Ret No Rel

<LLD Xe-133 Ci No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rei No Rel No Ret No Ret No Rel

<LLD Xe-133m Ci No Ret No Rei No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel cLLD Xe-135 Cl No R No Rel No Ret No Ret No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel

<LLD Xe-135m Ci No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel

<LLD Xe-138 Ci No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Rei No Ret No Ret No Rel No Ret No Ret No Ret No Rel cLLD B. lodines Br-82 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Ret No Rel No Rel No Rol No Rel No Rea No Rel No Rei

<LLD 1-131 Ci No Ret No Ret No Ret No Rel No Ret No Ret No Ret l No Ret No Ret No Rel No Ret No Rel No Rei No Ret No Rei No Rel l

cLLD 1-132 Cl No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret l No Ret No Rel No Rel No Rel No Ret No Rel No Reol LLD 1-133 Ci No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Reol LLD 1-134 Ci No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel No Ret No Ret No ReI No ReI No ReI No ReI No ReI No Ret

<LLD 1-135 Ci No Rel No Rei No Re e

No Re e

No R Rl No Rel No Ree No Rel No Rel No Re R

No Rel No Rel No Rat No Rel NoRet NoRel cLLD C. Particulates Na-24 lC No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rei cLLD Cr-51*

Ct No Ret

'No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret

<LLD Mn-54 Ctl No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rei

<'LLD Co-57l Cl No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel

<LLD Co-58 Cil No Rel No Ret No Ret No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret cLLD Co-60l Ci No Ret No Ret No Ret No Rel No Ret No ReI No ReI No ReI No ReI No ReI No ReI No Rel No Ret No Ret No Ret No Ret

<cLLD Zn-65l Cl No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret l

LLD Se-75*

Cl I No Ret No Ret No Ret I No Ret No Ret I No Ret No Ret I No Ret No Ret I No Ret No Ret No Rei I No Ret No Ret I No Ret No Ret I

<LLD Rb-88 lC No Rei No Ret No Ret No Ret No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret

<LLD Sr-89l Ci l

No Rel No Rel No Rel No Rel

<LLD Sr-9oI Ci I

I I

I No ReI No Rel No ReI No Rel

<LLD Zr-95l Ci No Ret No Rei No Ret No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel l

LLD Nb-95l Cl No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel

<LLD Mo-99 Ci No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel

<LLD Tc-99m Ci No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret No Ret No Ret I No Ret No ReI No ReI No ReI No Ret No Ret I

LLD Ru-103I Ct No Ret No Ret I No Ret No Ret I No ReI No Ret No Ret No Ret No Ret No Ret No Ret No Rel I No Ret No Ret I No Ret No Rel cLLD A9-110m' Cl No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Retl LLD Cs-134l Cl No Ret No Ret No Ret No Rel No Ret No Rel No Ret No Rel No Ret No Rel No Ret No Rel No Ret No Ret No Ret No Rel

<LLD Cs-136l Ci No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel

<LLD Cs-137*

Ct No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel No ReI No ReI No ReI No Rel No Ret No Ret No Ret No Ret cLLD Cs-138 Cl No Ret No Relt No Ret No Ret No Ret No Rei No Ret No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel

<LLD Ba-140' I

Ci No Ret No Ret No ReI No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret I

LLD La-140 Ci No Ret INo Ret No Ret No Ret No Ret I No Ret No Ret I No Ret No Ret No Ret I No Ret No Ret No Ret No Ret No Ret l No Ret l

cLLD Ce-144 Ct No Ret No Ret No Rel No Ret No Ret No Retl

_No Ret No Ret I No Ret No Ret l No Ret No Ret No Ret No ReI No Ret No Ret

<LLD Pr-144 Cl No Ret No Ret No No No R No Re ReRet No R Not NR No Ret No Ret No Ret No Ret No Ret No Ret l

LLD W-187 Cl No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret l

dLLD D. Tritium

1. Total Release Activity Cl No Ret No Ret No Ret No Rel No Rel No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret

<LLD

Particulate isotope with half-life greater than 8 days.

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 GASEOUS EFFLUENTS - ALL RELEASES ARE AT GROUND LEVEL UNIT 2 (Docket Number 50-304)

CONTINUOUS MODE I Units Jan Feb Mar 1st Qtr Apr May I

Jun I 2nd Otr Jul Aug Sep 3rd Otr Oct Nov Dec 4th Qtr Total A. Fission and ActIvatIon Gases Ar-41 Ci

<LLD

<LD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID cLLD Kr-85 Ci

<LLD cLLD

<LLD

<LID

<LLD

<LLD Kr-85m Ci

<LLD

<ILD

<LLD

<LLD Kr-87 Cl L

<LLD

<LD LLD

<LLD

<LiD

<LLD

<LLD Kr-88 Ci

<LLD cLLD

<LID

<LLD

<LLD Xe-131 Cl

<LLD

<LLD Xe-131m Cl

<LLD

<LLD Xe-133 I

Ci

<LLD

<ILLD

<LLD

<LLD 4LD

<LLD

<LLD Xe-133m Ci

<LLD

<LD

<LLD

<LLD Xe-135 CI cLLD

<LLD

<LLD cLLD

<LLD

<LID

<LLD cLLD LLD

<LLD

<LLD cLLD cLLD

<LLD

<LLD cLLD cLLD Xe-135m Ci

<LLD

<LLD LID

<LID L

LLD

<LLD

<LID

<LLD

<LLD Xe-138 Ci

<LLD

<LLD L

LLD

<LLD B. lodines Br-82 Ci

<LLD

< LLD

<LLD

<LLD 1-131 Cl

<LLD

<LID

<LLD

<LLD l

<LLD

<LLD 1-132 Ci

<LLD

<LLD 1

<LLD

<LLD 1-133 Ci

<LLD

<LLD l

<LLD

<LLD l

<LLD

<LLD l

<LLD

<LLD 1-134 Ci

<LLD

<LID

<LLD

<LLD I

<LLD

< cLLD

<LLD

<LLD I

<LLD

<ILLD

<LLD 1-135 Ci

<LLD

< <LLD

<LLD

<LLD C. Particulates Na-24 Ci

<LLD

<LID

<LLD

<LLD Cr Ci

<LLD

<LID

<LLD

<LLD,

<LLD

<LLD Mn-54' Ci

<LLD

-,LLD

<LID

<LLD

<LD

<LLD

<LLD Co-57l Cl

<LLD

<LD

<LLD

<LLD Co-58 Ci

<LLD

<LID

<LLD

<LD

<LLD

<LLD Co Ci

<LLD

<LLD 1.02E-06

<LLD 1.02E406

<LLD 2.09E-06

<LLD 5.93E-07

<LLD 5.93E-07 3.70E406 Zn Ci

<LLD

<ILD

<LLD

<LLD Se-75' Ci

<LLD

<LID

<LLD

<LLD Rb-88 Ci

<LLD

<LID

<LLD

<LLD Sr-89' Ci

<LLD

<LLD I

I I

<LID II I

LLD

<LLD Sr-90 Cl

__ci I

<LLD

<LLD i

<LLD

<LLD Zr_95' Ci

<LLD

<jLD

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LLD Nb-65I Ci

<LLD r LLD

<LLD

<LLD Mo-99 Ci

<LLD cLLD

<LLD

<LID

<LLD

<LLD Tc-99ml Ci

<LLD

<LID

<LLD

<LID

<LLD

<LID cLLD

<LLD Ru-103' Ci

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LLD Ag-110m*

Ci

<LLD

<LiD

<LLD

<LLD l <LLD

<LLD I <LLD

<LLD

<LLD Cs-134' Cl

<LLD

<LID

<LiD

<LLD

<LILD

<LLD

<LD Cs-136 Cl

<LLD

<LID

<LLD

<LID

<LLD

<LLD Cs-137 Ci

<LLD iLLD

<LLD

<LID

<LLD

<LID

<LLD

<LLD cLLD

<LLD Cs-138 Ci

<LLD j LiD

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LLD Ba-140 Cl

<LLD

<LID

<LLD

<LLD La-140 Cl

<LLD lcLLD

<LLD

<LID

<LLD

<LLD Ce-144' Ci

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LLD I

LD Pr-144 Ci i

LID i<LLD

<LID i

LID

<LID i<LD i<LD i

LD D DLDLID LIDD LD

<LID

<LD LD LLD D

W-187 Cl

<LLD i<LLD l<LLD I LOD

<LLD

<LLD l LLD

<L D

<LLD I <LLD

<LLD

<LID

<LLD

<LLD D. Tritium

1. Total Release Activity Ci

<LLD l<LLD

<LLD I

<LLD

<LID

<LLD

<LD

<LLD

<LLD LD

' Particulate Isotope with half-life greater than 8 days.

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 GASEOUS EFFLUENTS - ALL RELEASES ARE AT GROUND LEVEL UNIT 1 & 2 (Docket Numbers 50-295 & 50-304)

SUMMATION OF ALL RELEASES Units Jan Feb Mar 1st Qtr Apr may Jun 2nd Otr Jul Aug Sep 3rd Qtr Oct Nov Dec 4th Qtr Total A. Fission and Activation Gases

1. Total Release Activity Cl

<LLD

<LLD O.OOE2+00

12. Average Release Rate uCi/sec

<LLD

<LLD O.OOE+00 S. Iodine

1. Total 1-1 31 Activity Ci

<LLD

<LLD O.OOE+00

12. Average Release Rate uCilsec I<LLD I<LLD I<LLD I

LLD I<LLD I<LLD I<LLD I LLD I 4LD I<LLD I

LLD

<LLD I<LLD

-cLLD IO.OOE+00 C. Particulates (half-life > 8 days)

I1. Total Release Activftyt I

Ci I<LLD I <LLD I<LLD I

-cLLD I <LLD 12.02E-061

<LLD I 2.02E-06 I <LLD I2.09E-06 I LLD I2.09E-06 I <LLD I1.19E-06 I <LLD I1.19E-06 I 5.30E-06

12. Aversge Release Rate IuCI/sec I<LLD I<LLD I<LLD I

LLD I<LLD 17.54E-071

<LLD 2.57E-08 I<LLD 7.80E.07 I<LLD I2.63E.07 I<LLD I4.59E-07 I<LLD I1.50E.08 I1.68E.08

13. Gross Alpha Activity Ci

<LLD

<LLD D. Tritium

1. Total Release Activity Ci

<LLD

-cLLD

<LLD

<LLD O.OOE2+00

12. Average Release Rate IuCi/sec I<LLD I<LLD I<LLD I

LLD I<LLD I<LLD I<LLD I

LLD I<LLD I 4LD I<LLD I

cLLD I <LD I<LLD I<LLD I LLD IO.OOE+00 E. Sum of Iodine, Particulate (half-lives > 8 days),

and Tritium Releases.

1I. Total Release Activity Cl 0.00E+00 I0.OO1E+00 I.00E+00 IO.OOE+00OI0.OOE+00 I2.02E-061 0.OOE+00 I Z02E.06 I0.00E+00 I2.09E-06 I0.00E+00 I2.09E-06I 0.00E+00 I1.19E-06 I0.00E+00 I1.191E.06

.3E0

Gross Alpha, Sr-89, and Sr-90 Activities are quantified by quarterly composite analyses. The difference between the quarterly Particulates total and the sum of the totals of the three corresponding months equals the total quarterly activities of Sr-89 and Sr-90. The cells for monthly activity values of Gross Alpha on this page and Sr-89 and Sr-90 on the Batch and Continuous Mode data sheets are blank because monthly values are not applicable.

Lower limit of detection (LLD) values are presented In the Gaseous Effluents LLD Values for Gaseous Releases section. The abbreviation "<LLD" indicates the activity concentration of the radionuclide for each Individual sample analyzed during the applicable period was less than the LLD value for that nuclide. If the abbreviation "<LLD" is listed for a group of radionuclides, the activity concentration of each radionuclide for each sample during the period was less than the LLD value for the respective radionuclide.

Percent of technical specification limit information is presented in the Gaseous Effluents Supplemental Information and Dose to Public sections of this report, The abbreviation "No Ref" indicates that no batch releases were performed during the applicable period.

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 GASEOUS EFFLUENTS - ALL RELEASES ARE AT GROUND LEVEL UNIT 1 & 2 (Docket Numbers 50-295 & 50-304)

BATCH MODE Units Jan I

Feb Mar l

stQtr I

Apr I

May Jun I 2nd Qtr I Jul I

Aug Sep 3rd Qtr Oct Nov Dec 4th Qtr Total A. Fission and Activation Gases Ar-41 Ci No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Rel No Re!

No Re!

No Rel No Rel Kr-85 Ci No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Rel No Rel Kr-85m C!

No Re!

No Rel No Re!

No Re!

No Rel No Rel Kr-87 C!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Rel Kr-88 Ci No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel Xe-131 Ci No Re!

No Re!

No Rel No Rei No Re!

No Re!

Xe-131m C!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rei No Re!

No Re!

No Rel No Rel Xe-1 33 Ci No Re!

No Re!

No Rel No Re!

No Re!

No Rei No Rel No Re!

No Re!

No Rel No Rel Xe-133m Ci No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Rel Xe-135 Ci No Re!

No Re!

No No!

No NooiR No Re !

No Re N

No Rel No Re!

No Re!

No Rle Xe-135m C!

No Re!

No No!RoR!

N R o

No Re!

No R N

e Xe-138 C!

No Re!

No Rel No Re!

No Re!

N No Re!

No Re!

No Rie No Re!

No Re!

No Rel B. lodines Br-82 Cl No Re e

No R Re No R Re No Rai No R Re No Re e

No Ree No Rol No R Re No Re[

No Rel No RRi No Re!

No Rel No Rel NoRl NoReol 1-131 Ci No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rei No Re!

No Re!

1-132 Ci No ReI No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel I No ReI No ReI No ReI No Rel No Rel No ReI 1-133 Ci No Re!

No Rei No Re!

No Re!

No R!

l No Re R

No Rel No Rel No Rel NoRl NoRe!i 1___135 C!

No Re!

No Rei No Rei No Re!

No Re!

No Rol No Re!

No Re!

-No Rol No Rai No Re!

C. Particulates Na-24 C!

No Re!

No Rei No Re!

No Rel No Re!iNo Re!

No Re!

No Rei No Re!

No Re!

No Rel No Re!

Cr-51*

Ci No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel Mn-54*

C!

No Re!

No Rel No Re!

No Rel No Rel Co-57*

Ci No Re!

No Re!

No Rel No Rel No Re!

No Re!

No Rei No Re!

No Re!

No Rel No Re!

Co-58I Ci No ReI No ReI No ReI No Rel No ReI No ReI No ReI No Rel No ReI No Re!

No ReI No ReI No ReI No ReI No ReI No Rei No ReI Co-60*

C!

No Rei No Rei No Rel No Rel No Rei No Rei No Re!

No Rel No Rei No Rei No Rei No Rel No Rei No Rei No Rel No Rel No Rel Zn-65i Cl No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Rel Se-75l C!

I No Re!

No Re!

No Rel No Re!

No Re!

-No Re!

No Rel No Rel Rb-88 C!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel No ReI Sr-89I Ci I

_I _

II No Rel No ReI No Rel No Rel No ReI Sr-90i Ci i

_i _

ii No Rel No Rel i_

iii No Rel No Re!

No Rel zr-95j Ci No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

Nb-95' Ci No Re!

No Rel No Re!

No Re!

Mo-99 Ci No Rei No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

Tc-99m Ci No Re! I No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Rel No Re!

Ru-103j Cl No Rei No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Rei Ag-110ml Cl No Re!

No Re!

No Rel No Re!

No Rei No Re!

No Re!

No Rel No Rel No Re!

No Re!

No Rel No Re!

No Re!

Cs-134l Ci No Re!

No Re!l No Re!

No Re!

No Rel No Rel Cs-136l Ci No Re!

No Re!

No Rel No Re!

No Re!

No Rei No Re!

No Re!

No Rel No Rel Cs-137I Ci No ReI No ReI No ReI No Rel No ReI No ReI No ReI No Rel No ReI No ReI No ReI No ReI No ReI No ReI No Rel No Rel No ReI Cs-138 C!

No Rei No Rei No Rei No Rel No Rei No Re!

No Re!

No Rei No Rei No Re!

No Rei No Rel No Rei No Re!

No Rei No Rei No Re!

Ba-140-I C!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel I

No Re!

La-140 C!

I No Rei No Re!

No Rei No Rei No Re!

No Re!

No Rel No Rei No Re!

No Re!

Ce-144 Ci l No Re!

No Re No Re No Re!

No Re!

No Re No Re!

No Re!

No Re N Re!

No Re!

No Rel No Rel No Re!

Pr-144 C

No Re!

No ReI No Re!

No Re No Re No Re No Re No Re No Re No Re No Re No Re No Re!

W-187 C!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

D. Tritium

1. Total Release ActivitV C!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Rel Particulate Isotope with half-life greater than 8 days.

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 GASEOUS EFFLUENTS - ALL RELEASES ARE AT GROUND LEVEL UNIT 1 & 2 (Docket Numbers 50-295 & 50-304)

CONTINUOUS MODE Units I Jan Feb Mar l

st Qtr Apr May Jun 2nd Qtr Jul I

Aug Sep 3rd Qtrl Oct Nov Dec 4th Qtr Total A. Fission and ActIvatIon Gases Ar-41 Ci

<LLD

<LLD cLLD Kr-85 Cl

<LLD

<LD

<LLD

<LLD Kr-85m Cl

<LLD

<LLD cLLD

<LLD

<LLD Kr-87 Cl

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-131 Cl

<LID cLLD

<LLD

<LID LLD LLD

<LLD

<LID cLLD LLD

<LLD

<LLD cLID

<LLD Xe-131m Cl

<LLD

<LLD cLID Xe-133 Ci

<LLD

<LID

<LLD I <

LDLD

<LLD

<LcLLD cLLD

-LLD cLLD

<LID LLD

<LLD

<LLD Xe-133m Ci

<LLD

<LL

<LLD cLLD

<LLD

<LLD cLLD

<LD

<LLD

<LLD Xe-1 35 Cl

<LLD

<LLD cLLD

<LLD LID LLD cLLD I<LD

<LLD

<LID cLLD

<LLD

<LLD cLLD Xe-135m Cl

<LLD

<LLD Lo cLLD I

<LLD

<LLD LI IL LLD

<LLD cLID Xe-138 Ci

<LLD

<ILD

<LLD

<LLD B. lodines Br-82 Cl

<LLD

<LLD 1-131 Ci

<LLD

<cLLD

<LLD 1-132 Ci

<LLD

<LLD -

<LLD

<LD

<LLD

<LLD 1-133 Cl

<LLD

<LLD LLD cLD

<LLD

<LLD LLLD

<LID

<LLD LLD LD

<LLD

<LLD cLLD I-134 Cl

<LLD

<LID

<LLD

<LID

<LLD

<LID I

LLD

<LLD 1-135 Cl

<LLD

<LLD jLLD

<LLD

<LLD C. Particulates Na-24 Ci

<LLD

<LLD Cr Ci

<LLD

<LLD Mn-54 Ci

<LLD

<cLLD

<LLD

<LLD lcLLD

<LLD

<LLD l

LLD l

<LLD

<lLD Co Cl1

<LLD

<LLD cLLD

<LLD

<LLDl

<LLD

<LLD l

cLLD

<LLD Co-58r Ci

<LLD

<LD

<LLD

<LLD Co-60j Ci

<LLD lLLD

<LLD

<LID

<LLD 2.02E-06

<LLD 2.02E-46

<LLD 2.09E-06

<LLD 2.09E406

<LLD 1.19E-06

<LLD 1.19E-46 6.30E406 Zn-65 Cl

<LLD

<LID

<LLD

<LLD Se Cl I

<LLD

<LID

<LLD

<LID

<LLD

<LLD I

<LLD

<LID

<LLD

<LLD Rb-88 Ci I

<LLD

<LLD LD

<LLD

<LID

<LLD

<LD

<LLD ILID

<LLD I

LID Sr-89 Ci

<LLD

<LLD Sr-90l C

<LLD j___l_

LLID

<LLD lI i

<LLD

<LLD Zr-95 C

<LLD

<LID

<LLD

<LID

<LLD

<LID

<cLID

<LLD

<LID

<LLD

<LID Nb-95 C

r LLD

<LLD

<LID LLD

<LLD

<LLD lLID

<LLD r LID

<LID

<LLD

<LLD Mo-99

<C

<LLD

<cLLD

<LD

<LID

<LLD

<LLD cLLD

<LLD

<LID

<LLD

<LLD Tc-99m Ci

<LLD

<LID

<LLD

<ILLD

<LLD I LLD

<LLD

<LID

<LLD

<LLD Ru-103-Ci

<LLD I <LLD

<LLD

<LLD AI-13-m Ci

<LLD

<LLID

<LD

<LLD

<LID

<LLD

<LLD Cs-1347 Ci

<LLD

<LID cLLD

<LLD

<LID

<LLD

<LLD Cs-1368 Ci

<LLD

<LLD l LLD

<LLD

<LLD CsA-137 Ci

<LLD

<LID

<LLD

<LLD lLID

<LLD

<LLD Cs-I 38 Ci

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<:LID Ba-140*

Cl

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD I

<LLD La-140 Ci

<LLD

<LLD I <LLD I

<LLD 1<'LLD

<LLD

< LID

<LLD Ce-144I Ci I LD I LLD

<LID

<LLD

<LLD cLID

<LLD

<LID

<LLD ILLD

<LLD

<LLD Pr-144 Cl lLD j LLD

<LLD

<LD

<LLD

<LID

<LLD

<LLD LO

<LLD

<LLD W-187 Cl

<LLD

<LID

<LLD

< LLD

<LLD

<LLD I

<LL L<LLI

<LLD

<LLD I

<LLD

<LLD D. Tritium

1. Total Release Activity Ci

<LLD

<LLD I

<LLD

<LLD I <LLD

<LLD

<LID

<LLD

<LLD r'LD I

<LLD

Particulate isotope with half-lie greater than 8 days.

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 UNIT 1 (Docket Number 50-295)

GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION

1. Regulatory Limits See "Unit 1 & 2 GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION"

2.

Maximum Permissible Concentrations See "Unit 1 & 2 GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION"

3. Average Energy See "Unit 1 & 2 GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION"

4.

Measurements and Approximations of Total Radioactivity See "Unit 1 & 2 GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION"

5. Batch Releases 1st Qtr 2nd Qtr 3rd Qtr

a. Total Number of Batch 0

0 Releases

b. Total Time Period for Batch 0.OOE+00 O.OOE+00 0.00E+00 Releases (minutes)

c. Maximum Time Period for a O.OOE+O0 0.00E+00 0.00E+00 Batch Release (minutes)

d. Average Time Period for a 0.00E+00 0.00E+00 0.00E+00 Batch Release (minutes)

e. Minimum Time Period for a 0.OOE+00 0.00E+00 0.OOE+00 Batch Release (minutes)

6.

Abnormal Releases

a. Number of Releases 0

0 0

b. Total Activity Released (Ci) 0.00E+00 0.00E+00 0.00E+00 4th Qtr 0

0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 2003 0

0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0

0 0.00E+00 0.OOE+00

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 UNIT 2 (Docket Number 50-304)

GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION

1. Regulatory Limits See "Unit 1 & 2 GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION"

2.

Maximum Permissible Concentrations See "Unit 1 & 2 GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION"

3. Average Energy See "Unit 1 & 2 GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION"

4.

Measurements and Approximations of Total Radioactivity See "Unit 1 & 2 GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION"

5. Batch Releases 1st Qtr 2nd Qtr 3rd Qtr

a. Total Number of Batch 0

0 Releases

b. Total Time Period for Batch 0.OOE+00 0.OOE+00 0.OOE+00 Releases (minutes)

c. Maximum Time Period for a 0.OOE+00 0.OOE+00 0.OOE+00 Batch Release (minutes)

d. Average Time Period for a 0.OOE+00 0.OOE+00 0.OOE+00 Batch Release (minutes)

e. Minimum Time Period for a 0.OOE+00 0.OOE+00 0.00E+00 Batch Release (minutes)

6.

Abnormal Releases

a. Number of Releases 0

0 0

b. Total Activity Released (Ci) 0.OOE+00 0.OOE+00 0.OOE+00 4th Qtr 0

0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 2003 0

0.OOE+00 0.OOE+00 a.ooE+00 0.OOE+00 0

0

0. OOE+00 O.OOE+00

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 UNIT 1 & 2 (Docket Numbers 50-295 & 50-304)

GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION

1. Regulatory Limits The calculated annual total quantity of all radioactive material above background released from each unit at Zion Station to the atmosphere is limited by off-site dose restrictions stated in the station technical specifications, Off-site Dose Calculation Manual (ODCM), and 10CFR50 Appendix 1. The off-site dose limits per reactor unit are listed below.

Quarterly Yearly (mrem)

(mrem)

Gamma Air Beta Air Total Body Skin Organ 5

10 2.5 7.5 7.5 10 20 5

15 15

2.

Maximum Permissible Concentrations Zion Station gaseous effluent release-rate limits were not calculated using maximum permissible concentra-tions of activity. Gaseous effluent activity release rates are limited by off-site dose-rate restrictions stated in station technical specifications and the ODCM. The release-rate limits were determined by using the ODCM computer code to calculate release rates which would produce a specified instantaneous dose rate at the site boundary. The off-site dose-rate limits are listed below.

Noble Gases Noble Gases 1-131, 1-133, H-3, and particulates with half-lives greater than 8 days 500 mrem/year Total Body 3000 mrem/year Skin 1500 mrem/year Organ

3. Average Energy There were no measurable noble gas releases during 2003. Due to permanent cessation of operation and radioactive decay, the only gas available for release is Kr-85 present in spent fuel rods.

Isotope Kr-85 Percent of Effluent 100 Average Gamma Energy per Decay of the Mixture (keV)

Average Beta Energy per Decay of the Mixture (keV) 5.0 269.0

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 UNIT 1 & 2 (Docket Numbers 50-295 & 50-304)

GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION

4.

Measurements and Approximations of Total Radioactivity

a. Fission and Activation Gases Gamma Spectroscopy

b. lodines Gamma Spectroscopy

c.

Particulates Gamma Spectroscopy, Liquid Scintillation Gas Flow Proportional Counting

d. Tritium Liquid Scintillation Composite sample analyses for gross alpha, Sr-89, and Sr-90 are performed by off-site vendor.

5. Batch Releases

a. Total Number of Batch Releases

b. Total Time Period for Batch Releases (minutes)

c. Maximum Time Period for a Batch Release (minutes)

d. Average Time Period for a Batch Release (minutes)

e. Minimum Time Period for a Batch Release (minutes) 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr 2003 0

0 0

0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00

6. Abnormal Releases

a. Number of Releases

b. Total Activity Released (Ci) 0 0.OOE+00 0

0 0

0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 UNIT 1 & 2 (Docket Numbers 50-295 & 50-304)

GASEOUS EFFLUENTS LOWER LIMIT OF DETECTION (LLD) VALUES FOR GASEOUS RELEASES Isotope LLD (uCi/ml)

Alpha 1.00E-11 H-3 1.00E-06 Kr-85 1.OOE-06 Mn-54 1OOE-1 1 Co-58 1.OOE-1 1 Co-60 1.OOE-11 Zn-65 1.OOE-1 1 Sr-89

1. OE-11 Sr-90 1.OOE-11 Mo-99 1.OOE-11 Cs-134 1.OOE-11 Cs-137 1.00E-11 Ce-141 1.OOE-11 Ce-144 1.00E-11

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 LIQUID RELEASES UNIT 1 (Docket Numbers 50-295)

CONTINUOUS MODE IUnits IJan IFeb IMar 1sktr Ar May

_ Jun I2nd Qtr Jul Aug Sep 3rd Qtr Oct Nov Dec I4th Qtr Tot.l A. Fission and Activation Products Na-24 Ci

<LLD

<LLD No Rel

<LLD

<LID

<LID No Rol

<LID

<LLD

<LID

<LLD

'LID

<LLD

-<IL LLD _111

<LLD Cr-51 Cl

<LLD

<LLD "LLD No Rell

<LLD

<LLD No Rel

<ILD

'LLD

<LLD

<LID

<LLD

-<LLD

'LLD

<LLD

<LLD Mn-54 Ci

<LLD

-,LLD

<LLD No Rel

<LLD

<LID

<LID No Rol

<LLD

'LLD

<LLD

<LID

<LLD

<LLD Co-57 Ci

<LID

<LLD

<LID No Rel

<LID

'LLD

'LLD No Rel

<LLD

'LLD

<LLD

<LLD cLLD

<LLD Fe-55 Cl LLD

-,LLD LID

____<1L0

<LID Fe-S9 Cl

<LLD

<LLD eLLD No Rel

'LID

<LLD

'ILD No Rol

'ILD

'LID

<LLD

<LLD Co-58 Ci

<LLD

'LID

<LLD No Rel

<LLD

'LLD No Rel eLLD

'ILD

<LLD

<LLD cLLD

<LLD CG-60 Ci

<LLD

<LID

<LID No Rol

<LLD

<LLD INo Rel

<LLD

<LLD I <LD

<LLD I

LLD

<LLD

<LLD Zn.65 CI

<LID

<LID No Rel

<LLD

'LID

<LID No Rel

<LLD

<ILD

<LLD

<LID

<LLD

<LLD Sr-85 Ci

<LLD

'LLD

<LLD No Rol

<LLD

'LID No Rel

-LID

'LID

<LLD

.<LLD

<LID

<LLD

<LLD Rb-88 CI

<LLD

<LLD No Rel

<LLD

<LID No Rel

'LLD

'LID

<LLD

'LD

<LLD

<LLD Sr-89 Cl

<LLD

<LID,

<cLLD LLD

<LLD Sr-9D CI

<LLD

<LID

____<LLD LLD

<LLD Sr-92 CI

<LLD

<LID

<LLD No Rol

'LID

'LLD

<LLD No Rel

<LID

'LID

<LLD

<LD cLLD

<LLD Nb-95 Cl

'LLD

<LLD

'LLD No Rol

<LLD

'LID No Rol

-<LID

' LLD

'LD

<LLID

'LID

'LID <LL D

<LLDILD

<LD Zr-95 Cl

<LLD I

LLD

<LLD No Rol

<LLD I'LID

-qLID INo Rel

<LLD

'LLD

<LLD I

LLD

'LLD

<LLD

<LLD Zr-97 Cl

<LLD I<LLD

<LLD No Rel

<LLD

'LLD No Rol

<LID

'LD

<LLD

'LLD

<LLD

<LLD MO-99 Cl

<LLD

<LLD INo Rol

<LLD

<LID No Rel

<LID gLID

<LLD

'LID

'LD

<LLD

<LLD Tc-99m CI

<LID

<LLD

'LLD No Rol

'LID

'LD

<LD No Rel

<LID

'LD

<LD

'LD

<LLD

'LLD eLLD

<LLD Ru-103 Cl

<LLD

<LLD No Rol

<LID

'LD

'LD No Rel

<LID

'LID

<LLD

'LID

<LLD

<LLD Ag-110m Cl

'LID

'LLD

<LID

-No Rol

<LLD

-qLID No Rel

<LID

<LLD

<LLD Sn-113 CI

<LLD

<LLD No Rel

<LLD,

<LLD

<LID No Rol

<LID

'LID I

LLD

<LID

'LD

'LLD

<LID

<LLD

<LLD Sn-1 17m Cl

<LUD

<LLD

<LLD No Rel

'LID

'LLD

'LD No Rol

<LLD

'LID I'LLD

<LLD

<LID

'LD

<LLD

<LLD Sb-122 Ci

<LLD

<LID

'LLD No Rel

<LID

'LD

'LD No Rel

<LID

'LID

<LLD

' LLD

<LLD

<LLD Sb-1124 Cl

<LLD

<LID No Rol

<LLD

'LID

'LID No Rel

<LD

'LD

'LLD

<LLD

<LID

'LD

<LLD

<LLD Sb-125 Ci

'LID

<LLD

<LLD No Rel

'LID

<LID No Rel

<LLD

'LD

<LID

<LLD

'LD

<LLD

<LLD Sb-126 CI

'LD

<LLD No Rel

<LLD-

<LLD

'LID No Rel

<LID

'LID

<LLD

-~LLD

<LLD

<LLD Te-123m Cl

<LLD

<LLD No Rol

<LLD

'LLD

'LID No Rel

<LID

'LLD

<LLD

<LID

'LLD

<LLD 41.1.D

<LLD Te-132 Ci

<LLD

<LLD No Rel

'LID

<LID

<LID No Rel

<LLD

'LID eLLD

<LLD Cs-1 34 Ci

'LID

<LLD

<LLD No Rol

<LID

'LLD

'LID No Rel

'LID

'LD

<LID

<LLD

'LLD

<LLD

'LID

<cLID

<LLD Cs-137 Cl

<LLD

<LLD No Rol

<LLD

'LLD No Rel

<LLD

'LID

'LLD

<LLD

'LID

<LLD

<LLD Cs-138 CI

<LLD

<LLD No Rol

<LLD

'LLD No Rel

<LID

'LD

-- LLD

<LLD

<LID

<LLD

<LID

<LLD

<LLD Ba-140 Cl I

LLD

<LLD

<LLD No Rel

<LLD

'LLD No Rel

<-LLD

'LID

<LID

<LLD

<LID

--- LLD

<LID dLLD I_<LLD La-140 CI

'LID

<LLD

<LLD No Rol

<LLD

<LD

'LD No Rel

<LLD

'LD

<LLD

<LLD I

<LLD Ce-141 Ci

'LLD

LD

<LLD No Rol

'LID

<LID

<LID No Rel

' LD

'LD

<LID

<LLD

<LID

<lLID

<LLD jCe-144 iCI1

'LL D

<LD LID No Rol

<LLD

'LLD No Rel

<LID

'LD

<LLD

'LID

<LLD

~-14C I

'LLD I

LID

<LLD I

No Rol

<LLD

'LID No Rol

<LID

'LD

<LLD

<LID

<LLD

a. lodines 1-131 Cl

'LID I<LLD

<LLD INo Rol I'LID I'LID

<LLD No Rel

'LID

'LID I <LLD I

<LLD I'LLD I'LID I

LLD I

<LLD I

LLD 1-132 Ci

<LLD

'LID

<LLD No Rel 4LID

<LLD

'LID No Rel

<LID

'LD

< LLD

<LLD

'LID

<LLD j LID

<LLD 1-1133 Cl

<LLD

'ID<'LLD No Rel

'LD

'fLD

'LD No Rel

<-LLD

'LID J LD

LID LD

<LLD

<LLD j LID

<LLD 1-134 1

Cl

'LID

'LLD

<LLD INo Rol LIDi

'LD

-LID No Ie

<LLD

'LD

< LLD j LID

'LID

.41.LID

<LLD 1-135 1

Ci

'LLD I

LID

<LLD No Rel

<LLD

'LID

'LLD jNo Rel j<LD

'LD J LD [<LLD

'LID

'LLD

'LD 41-1-1D

<LLD C. Tritium

[It. Total Release Activity J

CI

< LLD

<LLD

< LLD [No Rol

'LLD

<LLD j LID (No Rel, [

LID

'LID

< LLD I

<LLD

< LID r LLD

< LLD I<LID

<I D. Dissolved and Entrained Gases Ar-41 Ci

<LID

<LLD

<LID No Rel

< LLD

<LLD

< LLD

-No Rel

<LLD

'LD

<LLD

<LID

'LID

<LLD

<LID

<LLD

[K_____________5 CI

<LLD

<LD

<LLD

-No Rol

< LID

<LLD

-No Rel

<LLD

'LID

<LLD

'LID

<LLD

<LID

<LLD Xe-131rnm Ci

<LLD

'LID

<LLD No Rel

<LLD

<LLD No Rel

<LLD

'LID

<LLD

<LID D

<LL

<I LID

<LLD

<110 Xe-133m CI

<LLD

'LID

< LLD No Rel

'LLD

<LLD

'LID

-No Rel

<LLD

<LD

<LLD

'LLD

<LLD

[Xe-135r Cl

<LLD

'LLD

<LID No Rol

'LID

'LLD

< LLD No Rel

'LID

'LD

<LLD

<LID

<LD

'LD

<LLD

<LID

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 LIQUID RELEASES UNIT 1 (Docket Numbers 50-295)

BATCH MODE I Units I Jan I

Feb l

Mar I1st Qtr Apr I

May I

Jun 2nd Qtr Jul Aug I

Sep I

3rd Qtr Oct I

Nov I

Dec I 4th Qtr Total A. Fission and Activation Products Na-24 Ci

<ILD No Rel

<LLD No Rel

<LLD

<LLD No Rel

<LLD

<LLD Cr-51 CI

<LLD No Rel

<LLD No Ref

<LLD

<LID

<LLD No Rei

<LLD

<LLD lcLLD LID

<LLD

<LLD Mn-54 Ci

LLD No Rel

<LLD No Rel

<LLD

<LLD No Rel

<LLD

<LID cLLD

<LLD Co-57 Ci cLLD No Rel

<LLD No Rel

<LLD

<LID

<LLD No Rel

<LID

<LLD

<LID

<LLD cLLD

<LLD Fe-55 Ci

<LID

<LLD

<LLD Fe-59 Ci

<LLD No Rel

<LID No Rel

<LLD

<LID

<LLD No Rel

<LLD

<LID

<LLD

<LID

<LLD cLLD

<LLD Co-58 Ci

<LLD No Ref

<LLD No Rel

<LLD

<LLD No Rel

<LLD

<LLD cLLD cLLD Co-SO Ci

<LID No Rel

<LLD No Rel

<LID I<LD

<LLD No Rel

<LID 1.09E-05 7.OOE-06 1.79E-45 8.78E-06

<LID

<LLD 8.78E-06 2.67E-05 Zn-65 Ci

<LLD No Rel

<LID No Rel

<LLD

<LLD.

No Rel

<LLD

<LID c<LD

<LLD

<LID

<LLD

<LLD Sr-85 Ci

<LID No Ref

<LLD No Rel

<LID

<LLD

<LLD No Rel

<LD

<LLD

_LID

<LLD

<LLD cLLD Rb-88 Ci

<LID No Rel

<LID

<LLD

<LLD No Rel

<LLD

<LID

<LLD

<LLD Sr-89 Cl No Rel No Rel

<LLD

<LLD Sr-9o Ci

<LLD

<LLD L_

cLD

<LLD Sr-92 Ci

<LLD

<LID

<LID No Ref

<LLD

<LID No Rel

<LLD

<LLD Nb-95 Ci

<LLD

<LLD No Rel

<LID I<LD

<LD No Ref

<LID

<LLD

<LID

<LLD

<LLD Zr-95 Ci

<LID I<LD

<LLD No Ref

<LLD

<LID

<LLD No Rel

<LLD

<LLD I<LD

<LLD

<LID

<LLD cLLD

<LLD Zr-97 Cl

<LD

<LLD

<LLD No Rel

<LD

<LLD

<LLD No Ref

<LD

<LLD

<LLD Mo-99 Cf

<LID

<LLD

<LLD No Rel

<LID

<LLD No Rel

<LLD

<LID

<LD

<LLD

<LD

<LID cLLD

<LLD Tc-99m Ci

<LLD

<LD

<LD No Rel

<LLD

<LLD No Rel

<LD

<LLD

<LD

<LLD

<LID

<LLD

<LD

<LLD cLLD Ru-io3 Ci

<LLD

<LID

<LID No Ref

<LID

<LLD No Refl

<LD

<LID

<LLD

<LID

<LLD

<LLD Ag-110m Ci

<LID

<LID No Rel

<LID

<LLD No Rel

<LLD

<LID

<LLD

<LID

<LD cLLD

<LLD Sn-1i3 CI

<LLD

<LD

<LLD No Rel

<LLD

<LD No Rel

<LLD

<LD

<LLD

<LD

<LLD

<LID

<LLD

<LLD Sn-117m Cl

<LLD

<LLD No Rel

<LID

<LLD

<LLD No Rel

<LID

<LLD

<LID

<LD

<LLD

<LLD Sb122 Ci

<LID

<LID No Rel

<LLD

<LID

<LID No Rel

<LLD

<LID

<LLD

<LID

<LID cLLD

<LLD Sb-124 Ci

<LLD

<LDD

<LLD No Rel

<LLD

<LLD No Rel

<LID

<LLD

<LLD cLLD

<LID

<LLD

<LID

<LLD

<LLD Sb-125 Cl

<LID

<LLD

<LLD No Ref

<LLD

<LID

<LLD No Rel

<LID 1.60E-06 8.80E-07 2.48E-06 6.20E-07

<LID

<LID 6.20E-07 3.10E06 Sb-126 Ci

<LID

<LLD

<LID No Rel

<LLD

<LLD No Rel

<LD

<LLD

<LID

<LLD

<LD

<LLD

<LLD Te-123m Ci

<LLD

<LD

<LLD No Rel

<LLD

<LD

<LLD No Rel

<LID

<LD

<LLD

<LID

<LLD

<LLD Te-132 Ci

<LLD

<LID

<LID No Rel

<LLD

<LLD No Rel

<LLD

<LD

<LLD

<LLD Cs-134 Ci LD

<LD

<LLD No Ref

<LLD

<LLD No Rel cLLD 2.50E-07 1.70E-07 4.20E-47 1.60E-07

<LLD

<LLD 1.60E-07 5.80E-07 Cs-137 Ci

<LLD

<LLD No Rel

<LID

<LLD No Ref

<LLD 2.16E-05 1.69E-05 3.85E.05 1.92E-05

<LLD

<LD 1,92E.05 5.77E-05 Cs-138 Ci

<LLD

<LID No Rel

<LLD

<LLD No Rel

<LID

<LD

<LLD

<LID

<LLD

<LLD Ba-140 Ci

<LD

<LLD

<LD No Ref

<LID

<LD

<LLD No Rel

<LLD

<LID

<LLD

<LID

<LLD cLLD

<LLD La-140 Ci

<LLD

<LLD No Rel

<LLD

<LID

<LLD No Rel

<LLD

<LD

<LLD

<LID

<LLD

<LD cLLD

<LLD Ce-141 Ci

<LID

<LLD No Rel

<LLD

<LLD No Rel

<LLD

<LID

<LLD

<LID

<LLD

<LID cLLD

<LLD Ce-144 Ci

<LLD

<LLD No Rel

<LID

<LLD

<LLD No Rel

<LLD

<LID

<LLD

<LID

<LLD

<LLD P-144 Ci

<LID

<LLD No Rel

<LLD

<LD

<LLD No Ref

<LID

<LLD

<LID

<LLD

<LID

<LLD cLLD

<LLD B. lodines I-131 Ci

<LLD

<LD

<LID No Rel

<LLD

<LID

<LLD No Ref

<LD

<LLD

<LID

<LLD

<LID

<LLD

<LLD 1-132 Cl

<LLD

<LID

<LLD No Rel

<LLD

<LID

<LLD No Rel

<LLD

<LID

<LLD

<LID

<LLD l

LLD 1-133 Ci

<LD

<LLD

<LLD No Ref

<LLD

<LID

<LID No Rel lLID

<LID

<LLD

<LID

<LID lLID cLID

<LID 1-134 Ci

<LD

<LLD No Rel

<LLD

<LLD No Rel l dLD

<LID

<LLD

<LID I

LID

<LID

<LLD C. Tritium

i. Total Release Activity Ci

<LD l <LID LLD No Rel l <LD l <LID

< <LLD No Rel

<LLD 34.47E-04 1.ISE-04 5.65E.04 12.35E-04

<LLD

-LLD 2.35E-04 8,OOE-04 D. Dissolved and Entrained Gases Ar-41 Ci

<LLD

<LLD No Rel

<LLD

<LLD l

<LLD No Rel lLLD lLLD

<LID

<LLD

< LLD

<LID 3 <LD

<LLD LLD I

Kr-85 Ci

<LLD

<LLD No Rel

<LLD

<LLD No Ref lLID l

LID lLID l

LID l <LID lLID l

LID l

LID Xe-131m

<C l

LLD

<LLD l

<LID No Rel

<LLD

< LLD No Ref lLID

<LID lLID l

LID l

LID lLID l

LID

<LID J pL Xe-133 Ci

<LLD

<LID

< <LLD No Ref

<LID

<LID No Ref lLID lLLD lLID l LID l dLD

<LID J <LID I

LID I

cL j

Xe-133m Ci

<LID

<LLD

<LLD lNo Ref lLID lLID l

cLLD No Ref lLID l

cLID l

LD LID

<LID l

LLD l

cL l

Xe-135 lCi l

LD

<LID lLID No Ref TLLD lLID lLLD No Ref lLID lLID lLID l

LID

<LID lLID lLID l

LLD l

LLD

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 LIQUID RELEASES UNIT 2 (Docket Numbers 50-304)

SUMMATION OF ALL RELEASES Units I Jan I

Feb I

Mar 1st Qtr Apr May Jun 2nd Qtr Jul Aug Sep 3rd Qtr Oct Nov Dec 4th Qtr Total A. Fission and Activation Products (not Incl. tritlum, gases, alpha)

I1. Total Activity Released § I

Ci

<LLD

<LLD l

<LLD

-LD l

<LLD l <ILD l

<LLD l

<LLD l <LLD

<LLD

<LLD 0.00E+00

2. Average Conc. Released uC/ml

< LLD

<LLD

<LID

<LLD

<LD

<LLD

<LD

<LLD

<LD cLLD

<LLD

<LLD O.OOE+OO

3. % of Value (9E-7 uCi/mI)

<LLD

<ILD

<LLD

<LLD 0.OOE+OO B. Tritium

1. Total Activity Released Ci l

<LLD

< <LLD l

<LLD

<LLD LLD

<LLD cLLD

<LLD

< <LLD l<LD

<LLD

<LLD cLLD cLLD l

O.OOE+00

2. Average Conc. Released uClimI

<LLD I

<LLD

<LD

<LLD

<LLD I<LLD

<LD

<LLD

<LLD I

<LLD

<LLD O.OOE+00

3. % of Value (1E-3 uCiml)

<LLD I <LD

<LLD

<LLD I

<LLD

<LLD O.OOE+00 C. Dissolved and Entrained Gases

1. Total Activity Released Ci

<LLD I

<LLD

<LLD I

<LLD

< <LLD I <LLD l

<LLD

< <LLD

<LLD l

<LLD

< cLLD

< cLLD l

<LLD l

O.OOE+00

2. Average Conc. Released uC/ml I

<LLD I <LLD I

<LLD I

LLD I <LLD I <LLD I

LD I

LD LLD I

<LLD I

<LD LLD I

<LLD i

LLD

<ILLD O.OOE+00

3. % of Value (7E-5 uCQml)

I

<LLD I

<LLD

<LLD I

<LLD cLLD I

<LLD LLD I

<LLD

<LLD I

LLD

<LD LLD L

<LLD

<LD I

<LLD

<LLD I

<LLD 0.00+00 D. Gross Alpha I1. Total Activity Released l

Ci l

<LD l

<LLD

<LLD l

<LLD

< LLD l <LLD l

<LLD l

<LLD

< cLLD

< <LLD

< LLD

< <LLD cLLD

<LLD

< cLLD

2. Average Conc. Released I uCi/ml

<LLD

<LD

<LLD

<TLD

<LLD

<ILD

<LLD

13. % of Value (2E-9 uCi/m)

I

<LD CLLD I

<LLD

<LLD E. Volume of Releases

1. Volume of Waste Releasedj liters I QOOE+00 I O.OOE+O0 I 0.00E+00 0.ODE+00 I 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 I O.OOE+00 O.00E+00 I O.OOE+00 I O.OOE+00 O.OOE+00 O.OOE+00 j2. Volume of Ditution Water+

liters j4.46E+10 I 2.18E+10 I 2.75E+09 6.92E+10 j3.49E+09 3.29E+09 3.17E+09 9.95E+09 j3.28E+09 3.29E+091 3.17E+09 I 9.74E+09 j3.29E+09 3.17E+09 3.29E+09j 9.75E+09 I 9.86E+10

§ Fe-55, Sr-89, and Sr-90 Activities are quantified by quarterly composite analyses. Therefore, the difference between the Fission and Activation Products total quarterly activity and the sum of the total activities of the three corresponding months equals the total quarterly activities of Fe-55, Sr-89, and Sr-90.

The cells for monthly activity values of Fe-55, Sr-89, and Sr-90 on the Batch and Continuous Mode data sheets are blank because monthly values are not applicable.

t These data include only information for batch releases from Lake Discharge Tanks.

Lower limit of detection (LLD) values are presented in the Liquid Effluents LLD Values for Liquid Releases section. The abbreviation "<LLD" indicates the activity concentration of the radionuclide for each individual sample analyzed during the applicable period was less than the LLD value for that nuclide. If the abbreviation "<LLD' Is listed for a group of radionuclides, the activity concentration of each radionuclide for each sample during the period was less than the LLD value for the respective radionuclide.

The abbreviation "No Rel" indicates that no releases were performed during the applicable period.

"% of Value" means percent of concentration values in Appendix B. Table 2, Column 2 to 10CFR20. The % of Value for Fission and Activation Products and Dissolved and Entrained Gases provides a comparison of the total concentration of the group to the lowest Isotopic concentration value of the particular group. The concentration of Fission and Activation Products and Dissolved and Entrained Gases are compared to the concentration limits for Cs-134 (9E-7 uCi/mI) and Ar-41 (7E-S uCl/mI), respectively. Concentration limits for Dissolved and Entrained Gases are listed in ODCM Table 12.3-1.

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 LIQUID RELEASES UNIT 2 (Docket Numbers 50-304)

BATCH MODE I Units Jan I

Feb Mar 1st Qtr Apr I

May Jun 2nd Qtr Jul I

Aug I

Sep I

3rd Qtr Oct I

Nov I

Dec 4th Qtr Total A. Fission and Activation Products Na-24 CI No Rel No Re!

No Rel No Rel No Re!

No Rel No Re!

No Re!

No Rel No Rel No Re!

No Rel No Re!

No Re!

<LLD Cr-51 Ci No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

<LLD Mn-54 Ci No Re!

No Rei No Re!

No Re!

No Rel cLLD Co-57 Ci No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Rel No Rel No Rel No Rel No Re!

No Rel No Re!

<LLD Fe-55 Cl No Re!

No Rel No Rel No Rel

'LLD Fe-59 C!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Rel

<LLD Co-58 Ci No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Rel No Re!

No Re!

<LLD Co-60 Ci No Re!

No Re!

No Rel No Re!

No Rel No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

<LLD Zn-65 C!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

cLLD Sr-85 Ci No Rel No Re!

No Re!

No Rel No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Rel

<LLD Rb-88 Ci No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel cLLD Sr-89 Ci No Rel No Re!

No Rel No Rel

<LLD Sr-90 Ci No Rel No Rel No Rel No Rel cLLD Sr-92 C!

No Re!

No Rei No Re!

No Re!

No Rel No Re!

No Re!

No Rel cLLD Nb-95 Cl No Re!

No Re!

No Rei No Rel No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

<LLD Zr-95 Ci No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rei No Re!

No Re!

No Rel

<LLD Zr-97 C!

No Re!

No Rel No Re!

No Re!

No Rei No Re!

No Re!

No Rel No Re!

No Rei No Re!

No Re!

No Rel cLLD Mo-99 Cl No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Rel No Rel No Re!

No Re!

No Rel No Rel

<LLD Tc-99m Ci No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

<LLD Ru-103 C!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Rel cLLD Ag-110m C!

No Rel No Rel No Rel No Rel No Rel No Rel No Re!

No Rel No Re!

No Rel No Rel No Rel No Rel No Rel No Rel No Rel

<LLD Sn-113 Ci No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

<LLD Sn-1 17m C!

No Re!

No Rel No Re!

No Re!

No Rei No Re!

No Re!

No Rel cLLD Sb-122 Ci No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rei No Re!

No Rel

<LLD Sb-124 C!

No Re!

<LLD Sb-125 C!

No Re!

No Rei No Rel No Re!

No Rel No Re!

No Re!

No Rel No Rel No Re!

No Rel cLLD Sb-126 Ci No Re!

No Re!

No Rel No Re!

No Re!

No Rei No Re!

<LLD Te-123m Ci No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Rel No Rel cLLD Te-132 Ci No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

<LLD Cs-134 Ci No Re!

No Rel No Rel No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Rel No Re!

cLLD Cs-137 Cl No Rel No Re!

No Re!

No Rei No Rel No Re!

No Re!

No Rel No Re!

No Rei No Re!

No Re!

<LLD Cs-138 Ci No Re!

No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

<LLD Ba-140 Ci No Re!

No Rel No Re!

No Re!

cLLD La-140 C!

No Rel No Re!

No Re!

No Rel No R No Re No Re!

No Re!

cLD Ce-141 Ci No Re!

No Rel No Rel No R!

No Re No Re!

No Re!

cLLD Ce-144 Cl No Rel No Re!

No Re!

cLLD Pr-144 C

No Re!

No Rel No Re!

No Re!

cLLD B. lodines 1-131 Ci No Re!

I No Re!

No Re!

No Rel No Rel No Re!

No Re!

l No Re!

No Re!

-No Re!

No Rel No Re!

l No Re!

<LLD 1-132 iCl No Re! I No Re!

No Re!

No Rel No Re!

No Re No Re!

No Re!

lNoRe!

NoRel No Re!

l No Rei

<LLD 1-133 t

Ci No Re I No Re!

No Re!

NoRell No Re!

No Re!

NoReli NoRel No Re!

No Rel No Rel NoReli

<LLD jl-134 lCi N. Rel lNo Rel l No Rel No Rai No Rel No Reli No Reli No Rol lNo Rel lNo Rel No Rel No Rol No Rel lNo Reli No Rel No Rel

< LL lI-135 lCl No Rel I No Rel No Rel No Reli No Rel No Reli No Rel No Rel No Rel No Rel lNo Reli No Rol No Rel No Rel lNo Rel lNo Rol l

LL C. Tritium

1. Total Release Activity l

Ci l No Re!

No Re!

NoRel l No Re!

No Re!

No Rel No Re!

No Rel No Re No Re I

No Rel [

<LLD D. Dissolved and Entrained Gases Ar-41 3 Cl No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Re!

<LLD lKr-85 lCi lNo Reli No Rel No Reli No Reli No Reli No Rel No Rel lNo Rol lNo RelI No RelI No Rel No Rol lNo Rel No Rel No Rel No Rol l

LLD lXe-131mrl Ci lNo Reli No Reli No Rel No Reli No Reli No Reli No Reli No Reli No Rel No Reli No Reli No Rel No Reli No Rel lNo Rel No Rel

< LLD Xe-133 Ci lNo Rel No Rel NoRe!

NoRRe No ReR No ReR No ReR No ReR No ReR No Rel No ReR No ReR No Rel R

No Rel No Re No Rel

<LLD Xe-133m l

Cl l No Re!

No Rel No Re!

No Re!

No Rel No Re!

No Rel No Rel No Re!

No Rel No Re!

No Re!

No Rel l No Re!

<LLD Xe-135 J Ci No Re!

No Re!

No Rel No Re! l No Rel No Re!

No Re!

l No Re!

<LLD

ZION NUCLEAR POWER SIAIION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 LIQUID RELEASES UNIT 2 (Docket Numbers 50-304)

CONTINUOUS MODE I Unhs I Jan I

Feb I

Mar I

1st Qtr Apr May Jun 2nd Qtr Jul Aug I

Sep I

3rd Qtr Oct I

Nov I

Dec I 4th Qtr Total A. Fission and Activation Products Na-24 Ci No Ret No Ret No Ret No Rel No Ret No Rei No Ret No Re!

No Ret No Rel No Ret No Rel No Ret No Ret No Ret No Re!

<LLD Cr-51 Ci No Rel No Ret No Ret No Rel No Ret No Rei No Ret No Rel No Ret No Ret No Rel No Rel No Rel No Ret No Ret No Rel

<LLD Mn-54 Ci No Ret No Ret No Rei No Rei No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel cLLD Co-57 Ci No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel

<LLD Fe-55 Ci No Rel No Rei No Re!

No Rei

<LLD Fe-59 Ci No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel

<LLD Co-58 Ci No Ret No Ret No Rel No Re!

No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel

<LLD Co-60 Ci No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Ret

<LLD Zn-65 Ci No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Re!

<LLD Sr-85 Ci No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Re!

<LLD Rb-88 Ci No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel

<LLD Sr-89 Cl No Re!

No Re!

No Rel

<LLD Sr-90 Ci No Re!

No Re!

No Ret

<LLD Sr-92 Ci No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Re!

No Ret No Ret No Rei No Ret

<LLD Nb-95 Cl No Ret No Ret No Ret No Re!

No Ret No Ret No Rel No Re!

No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Rel

<LLD Zr-95 Ci No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Ret

<LLD Zr-97 Ci No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Re!

<LLD Mo-99 CI No Ret No Rel No Rel No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Rel

<LLD Tc-99m Ci No Ret No Ret No Ret No Rel No Ret No Rei No Ret No Re!

No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel

<LLD Ru-103 Ci No Ret No Ret No Ret No Rel No Ret No Rei No Re!

No Rel No Ret No Ret No Ret No Ret No Ret No Rei No Ret No Re!

<LLD Ag-110m CI No Ret No Ret No Rel No Re!

No Ret No Ret No Rei No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel

<LLD Sn-1 13 Ci No Ret No Ret No Ret No Re!

No Ret No Ret No Rel No Re!

No Ret No Ret No Ret No Re!

No Ret No Rei No Rei No Rel

<LLD Sn-117m Ci No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Re!

No Rei No Ret No Ret No Re!

No Ret No Ret No Ret No Rel

<LLD Sb-122 Ci No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret

<LLD Sb-124 Ci No Ret No Re!

No Ret No Re!

No Rei No Rei No Ret No Rel No Ret No Re!

No Ret No Re!

No Ret No Ret No Ret No Re!

<LLD Sb-125 CI No Rel No Ret No Rei No Rel No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Re!

No Rei No Rei No Ret No Rel

<LLD Sb-126 Ci No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Re!

No Rei No Ret No Ret No Rel No Ret No Ret No Ret No Re!

<LLD Te-123m Ci No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel

<LLD Te-132 Cl No Ret No Ret No Rei No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret

<LLD Cs-134 Ci No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret

<LLD Cs-137 Ci No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Rel No Ret No Ret No Rei No Rel No Ret No Ret No Ret No Rei

<LLD Cs-138 CI No Ret No Ret No Ret No Rel No Ret No Ret No Rei No Re!

No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Ret

<LLD Ba-140 Ci No Rei No Ret No R No No Re No Ret No Ret No Re!

No Rei No Ret No Ret No Rel No Ret No Ret No Ret No Rel

<LLD La-140 Ci No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Re!

No Ret No Rei No Rei No Rei No Ret No Ret No Rei No Re!

<LLD Ce-141 Ci No Ret No Rei No Ret No Rel No Rei No Ret No Ret No Re!

No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel

<LLD Ce-144 Ci No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Re No Ret No Ret No Ret No No!

No Ret No Re!

<LLD Pr-144 Ci No Ret No Ret No Ret No Rei No Ret No Ret No Ret No R No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret

<LLD B. lodines jl-131 I

Ci l No Ret No Ret No Ret l

No Rel No No Re!

No Ret No Ret N R N

No Ret No Roel

<LLD l1-132 l

Ci No Ret No Ret No Ret l

No Re!

l No Ret No Ret No Ret No Re!

NolRi No Ret l No Ret No Rel No Ret No Rei No Ret No Re!

<LLD

_1-133 l

Ci No Ret No Ret j No Ret J No Re!

l NoRei NoRRel No Ret No Re!

No Ret No Ret NoRet NoRel*

No Ret No Ret No Ret j No Re!

<LLD 1_-134 Ci No Ret No Rei l No Ret l No Rel l No Ret No Ret No Ret No Re!

No Relt No Rel l No Rel No Re!

No Ret No Rei No Ret No Re!

<LLD 1-135 _

Ci No Rel No Ret No Ret No Re!

No Ret No Ret No Rei No Ret No Ret No Ret No Ret No Re!

No Ret

_No Ret No Ret No Re!

<LLD C. Tritium

1. Total Release Activity l

Ci No Rel No Rel No Rel No Re!

No Rel No Rel No Rel No Re!

No Rel No Rel No Ret No Re!

No Rel No Rel No Rel No Rel l

LLD D. Dissolved and Entrained Gases Ar-41 l

Ci NoReti NoRe]

NoRel NoRelt NoReti NoReli NoReli NoReol NoReail NoRelt NoRelt NoRe!i No Rel NoRelt No Ret No Re!

<LLD Kr-85 j

Ci No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Re!

<LLD Xe-131m l

Ci No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel

<LLD Xe-133 J

Ci No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Re!

No Ret No Ret No Ret No Rel No Ret No Ret No Ret l No Rel

<LLD Xe-133m Ci No Ret No Ret No Ret No Rei No Ret No Ret l No Ret No Re!

No Ret No Ret No Ret No Re!

No Rei No Ret No Ret No Rel

<LLD Xe-135 Ci No Ret No Ret No Rei No Rel No Ret No Ret No Ret No Rel No Ret No Rei No Rei No Rel No Ret No Ret No Ret No Ret

<LLD

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 LIQUID RELEASES UNIT 1 & 2 (Docket Numbers 50-295 & 50-304)

SUMMATION OF ALL RELEASES Units I Jan IFeb IMar 1 st Qtr Apr May Jun 2nd Qtr Jul IAug Sep 3rd Qtr I

Oct INov Dec 4th Qtr Total A. Fission and Activation Products (not mncl. tritium, gases, alpha)

Ii. Total Activity Released § I

Ci I <LLD I <LLD i <ULD

-<LLD I<LLD I<LLD I<LLD

~LD I<LLD I 3.43E-05 I 2.50E-05 I 5.93E.05 I 2.88E-05 I <LLD I<LLD I2.88E-05 I8.80E.05

12. Average Conc. Released uCi/mlI

<LLD I<LLD I<LLD I

<LLD I<LLD I<LLD I<LLD I

LLD I<LLD I9.81E-12 I6.95E-12 I5.49E.12 I7.74E-12 I<LLD

<LLD 2.61E-12 8.51 E-13

13. % of Value (9E-7 uCi/mI)

<LLD

<LLD I

LLD

<LLD

<LLD i.09E-03 I7.72E-04 6.10E-04 8.61 E-04 I<LLD

<LLD 2.90OE-04 9.46E.05 B. Tritium II. Total Activity Released ICi I<LLD I<LLD I<LLD I

<LLD I<LLD I<LLD I<LLD

< LLD I<LLD I4.47E-04 I1.18E-04 5.65E.04 I2.35E-04

'LLD I<LLD I2.35E-04 I8.OOE-04

12. Average Cone. Released uCI~ml I<LLD I<LLD

<LLD I

LLD I<LLD I<LLD I -LLD I

4LL

<LLD 1.28E-10 3.29E-11 I5.23E-11 I6.33E-Ii

<LD

<LLD 2.13E-11 7.74E-1 2

13. % of Value (IE-3 uCi~ml)

<LLD

.cLLb

<LD

<CLLD

<LLD

<LLD 1.28E-05 3.29E-06 5.23E-06 6.33E-06

<LLD

<LLD 2.13E-06 7.74E-07 C. Dissolved and Entrained Gases Ii. Total Activity Released Ci I

CLD

<LLD I 4D

<LLD

<1-1

<LLD

< LLD

<LLD

<LLD CLD

<LLD

<LLD I

.OOE+00

12. Average Conc. Released uCilmlI

<LLD I <LLDI

<LLD

<LLD I

LLD

<LLD

<LLD I <LLD I <LLD I <LLD I

1-1 LLD ICL <LLD

<LLD

<LLD O.ODE+00

13. % of Value (7E-5 uClmIm

<LLD

<LLD I<LLD I<LLD

<LLD

<LLD O.OOE+00Q D. Gross Alpha Ii. Total Activity Released ICi I<LLD I<LLD

< LLD I

'LLD I<LLD I<LLD

< LLD I LLD I <LD I<LLD I <LLD

< LLD I<LLD I<LLD

<LLD I LLD

< LLD

12. Average Conc. Released uCl/mI

<LLD

<LLID

<LLD

<LLD I

LLD I<LLD I<LLD I <LLD I<LLD I

LLD

<LLD

13. % of Value (2E-9 uCVmI)

<LLD

<11-1-1

<LLD

-cLLD

<LLD

<LLD I<LLD I

LLD I<LLD I

LD I<LLD I<LL

'LLD E. Volume of Releases

1. Volume of Waste Releasedl liters I0.OOE+00 I0.0ED

.OOE+00 I

0.00E+00 I

O.OOE+0O0.OO IO 0.00E+00 I0.00E+00I O.OOE+00 10.OOE+0012.41E+0511.24E+051 3.65E+05 11.29E+0510.OOE+0010.OOE+001 1.29E+05 4.4E0

12. Volume of Dilution Water

~ I Iters 14.51E+11012.19E+1013.71E+091 7.07E+10 13.59E+09 13.71E+0913.58E+09 I1.OSE+1O 13.70E+0913.50E40913.59E+091 1.08E+10 13.71E+0913.59E+0913.71E+091 I.IOE+10 I1.03E+11

§ Fe-55, Sr-89, and Sr-90 Activities are quantified by quarterly composite analyses. Therefore, the diffierence between the Fission and Activation Products total quarterly activity and the sum of the total activities of the three corresponding months equals the total quarterly activities of Fe-55. Sr-89, and Sr-90.

The cells for monthly activity values of Fe-55, Sr-89, and Sr-90 on the Batch and Continuous Mode data sheets are blank because monthly values are not applicable.

t These data Include only Information for batch releases from Lake Discharge Tanks.

Lower limit of detection (LLD) values are presented In the Liquid Effluents LLD Values for Liquid Releases section. The abbreviation "<LLD" indicates the activity concentration of the radionuclide for each individual sample analyzed during the applicable period was less than the LLD value for that nuclide. tIfthe abbreviation "<LLD" is listed for a group of radionuclides, the activity concentration of each radionuclide for each sample during the period was less than the LLD value for the respective radionuclide.

The abbreviation "No Rl" indicates that no releases were performed during the applicable period.

`% of Value" means percent of concentration values in Appendix B, Table 2, Column 2 to 1 OCFR20. The % of Value for Fission and Activation Products and Dissolved and Entrained Gases provides a comparison of the total concentration of the group to the lowest Isotopic concentration value of the particular group. The concentration of Fission and Activation Products and Dissolved and Entrained Gases are compared to the concentration limits for Cs-134 (9E-7 uCi/ml) and Ar-41 (7E-5 uCI/mI). respectively. Concentration limits for Dissolved and Entrained Gases are listed in ODCM Table 12.3-1.

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 LIQUID RELEASES UNIT 1 & 2 (Docket Numbers 50-295 & 5D-304)

BATCH MODE IUnIts Jan Feb Mar 1st Qtr IApr May Jun 2nd Qtr IJul IAug Sep 3rd Qtr IOct INov Dec I4th Qtr I

Total A. Fission and Activation Products Na-24 Cl

<LLD

<LID

<LLD

<LID

<ILD I<LID

<LLD I<LID

<LLD

<LID Cr-51 Ci

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD Mn-64 CI

<LID

<LLD

<LLD Co-57 Cl

<LD

<LLD

<LD

<LLD

-<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LLD Fe-55 CI

<LLD

____<LLD

<LLD

____<LLD

<LLD Fe-59 CI

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LLD Co-58 CL

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID Zo-65 CI

<ID

<L

<LDD

<LL<IDD

<L<LD

<LLD

<LLD-

-1.09E-05 7.OOE-06 1.79E.05 I8.78E-06

<LLD

<LLD 8.78E-O6 2.67E.05 Sr-85 C

LD LD

<LD

<LID-

<LLD

<LID

<LLD.

<LLD

<LID I<LLD

<LLD

<LLD SR-88 Cl

<LLDD

<LL

<LLD

<LIDL I

<I LD

<LLD

<LID I<LLD

<LID

<LLD

<LLD RbS I

<I LD

<LID

<11D

<LID

<LLD

<LID I<LLD

<LLD

<LID

<LLD

<LLD Sr-89 CI

<LLD

____<LLD

<LLD

<LLD Sr-190 CI-

<LLD

<LLD Sr-92 CI

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LLD Nb-95 CI

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LLD Zr-95 Cl

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LLD I<LID

<LLD

<LLD Zr-97 CI

<LID

<LLD I<LID

<LLD

<LID

<LLD

<LLD I<LLD

<LLD

<LDLD Mo-99 C-<I LD

<I LD

<I IL LD

<I LD

<LLD

<LLD Tc9mCl

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LLD Tc-19m CI

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LLD I<LLD

<LLD

<LLD Au-11Dm Cl

<LID

<LLD

-,LLD

<LID

<LLD

<LID

<LID I<LID

<LLD

<LID

<LLD

<LLD Ag-110m CI

<LID

<LLD

<LID

<LLD

<LID-

<LID I<LLD

<LLD

<LLD Sn-113m CI

<LLD

<LID

<LLD

<LID

<LLD

<4LLD

<LID

<LLD

<LLD Sn-117m Cl

<LID

<LLD

<LID

-<LLD

<LID

<LLD I<LLD

<LID

<LLD

<LID

<LLD

<LLD SbJ-1122 CI

<LLD

<LLD I<LLD

<LLD

<LID

<LLD

<LID

<LLD

<LLD Sb-124 Cl

<LID

<LLD

<LID

<110

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LID Sb-123m CI

<LLD I<LID

<LLD

<LID

<LLDD

<LL

<LD <LD 16E0 8<LID

<LID 6<LID0

<LLD

<LLD 6<LID0 3.LID0 T-3Cl

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LDLD Te-123m CI

<I LI LD

<L<LDD

<LL<IDD

<LLDI 2SE07170-74.0.0

<LELD<I LI

.6E0

<LLD-0 C-3CI LD

<LD LD

<LLD

<LLI

<LDI

<LD <

LLII-LLDID 21E0

<LLD9-

<LLD-0

<LLD

<LLD-0 5.LLD0 Te-132 CI

<LLD

<LID-

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LLD Ca-134 Cl

<LID

<LLD

<LID

<LLDD

<LL 2<LID0

<LID.0 4<LID0

<LID-0

<LID

<LLD I<LID01-0 5<LID0 Cs-137 CI

<LID

<LLD

<LID

<LLD

<LID

<LLD I<LLDD

<LL 2<LID0 LID6E0 3<LID0 1<LID0

<LID

<LID I<LID-0 5<LID0 Cs-138 el

<LLD

<LLD I<LLD

<LID I<LLD

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LLD Be-10 Cl-

<LID

<LLD

<LID --

<LID

<LLD

<LLD La-140 CI

<LID

<LLD

<LID

<LLD

<:LLD

<LID

<LLD

<LID

<LLD

<LLD Ce-14 Cl

<LID

<LLD

<LID

<LLD

<LD LD

<ID LD

<IDLD Ce-14 CI

<LLD

<LLDD

<LL

<LI

<LD LD

<LD

<LLD

<LID

<LLD

-<LLD

<LLD

<LLD I-l

<I LD

<LLD

<LLD ILI<L LI LLD

<LID

<LLD

<LLD Pr-14 Cl

<LID

<LLD

<LID

<LLD

<LLD I<LD IDD

<LLD

<LID

<LLD

<LLD 1C3 l

<LID

-<LLD

<LLD

<LID LID

<LLD

<LID

<LLD

<LLD 1.13 Toa eeaeAhl

<LID 3<LID

<LID ]

<LID

<LIDL

<ID(<ID<LLLID]<LD<LLD7-D 1.8-D 5.5E04[._E.4

<LD-<I

.5.4~8OE0 A-1C

<LD LD

<LD LI

<LD-<D

<LD

<LLD

<I LDD

<LLDLI JILID

<I LI LD

<I 1~-85C1LD

<ID

<I LD

<LD

<I4 LI LD

<I

<LID

<LLD LID

<LI

<LID

<LLD j

<LLD Xe11 l

<LID

<LI

<LID

<LID-

<LID

<LLD

<LID

<LLD

<LID

<LI

<LID

<LD f LD L~-3 i

<I LD

<LID

<LLD

<LID

<LLD

<LID -F<LID

<LID j<LID

<LI j<LID

<LLD j

<I Xe-41 33 l

<LLD

-<LID

<LLD_

<LLD

<LLD J<LLD

<LID J<LLD

<LID j

<LLD LXe-135 Ci

<LID

<LLD

<LID

<LLD

-<LID

<LLD

<LLD j<LD ~<LLD

<LLD j

<LLD

<LID

<LLD j

<LLD

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 LIQUID RELEASES UNIT I & 2 (Docket Numbers 50-295 & 50-304)

CONTINUOUS MODE IUnits IJan IFeb IMar I1sat Qtr IApr may Jun 2nd Qtr IJul IAui Sep 3rd Qtr Oct INov Dec 4th Qtr Total A. Fission and Activation Products Na-24 Ci

<ILD

<LLD

-<LLD

<LID

<LLD

<LLD 4ILD

<LLD

<LLD-

<LLD

<LID

<LLD

<LLD Cr-51 Ci

<LLD

<LID

<LLD

<LID-

<LLD

<LID

<LLD

--<LLD

<LLD Mn-54 CI

<LID

.CLLD

<LLD

<LID

<LLD

<ILD

<LLD

<LLD Co-57 Ci

<LLD

<LID

<LLD

<LID

<-LLD

<LLD

<LID

<LLD

<LLD Fe-55 Ci

<LLD

<LID Fe-59 CI

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<ILD

<LLD

<ILD

<LLD

<LLD Co-58 Ci

<LID

<LLD

<LID

-cLID

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LLD Co-60 Ci

<LLD

<LLD I<LLD

<LLD

<LID

<LLD I<LLD cILD

<LID

<LLD

<LLD Zn-65 Cl

<LLD

<LLD Sr-85 Ci

<LLD

<LLD cLLD

<LID

<LLD

'LLD I<LLD

<LLD I<LLD

<LLD

<LLD Rb-88 CI

<LID

<LLD

<LID

<LLD

<LID

<LLD-

<LLD

<LID

-<LLD

<LID I<LLD

<LLD

<LLD Sr-89 CI

<LLD

____<LID

<LLD

<LID

<LLD Sr-9O Ci

<LLD

<LLD Sr-92 Ci L <LI D

<LLD

<LI D

<ILD

<LI D

<LLD

<ILD

<LLD

<LLD LLD <LLD

<LLD

<LLD LL LID Nb-95 CI

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD Zr-95 CI

<LLD

<LLD.

<LID I<LLD

<LLD I<LID

<LLD

<LID_

<LLD

<LLD Zr-97 Ci

<LID

<I LD

<LID

<LLD

<LID

<LLD

<LLD Mo-99 CI

<LLD

<LID

<LI LD <LI D

<LLD

<LD <LID I<LLD

<LID

<LLD

<LID Tc-99m Ci

<LID

<LLD

-<LID

<LID

<LLD

<LID

<ILD

<LLD

<LID

<LLD

<LID

<LLD Ru-103 CI

<LLD

<LID

<ILD

<LID

<LLD

<LID

<LLD

<LID

<SLID

<LLD

<LID Ag-110m Cl

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LLD LLD

<LL

<LLD

<LID Sn-1 13 Ci

<LID

-<LLD

<LID

<LLD

<LID

<LLD

<LID

<LD <LLD

<LID

<LL D

<LLD<

<LID

<LLD Sn-117m Ci I<LID

<LID

<LLD

<LID

<LLD

<ILD I<LLD

<LID

<LLD

<LID

<LI

<LID

<LLD

<LLD Sb-122 Ci

<LID

<LID I<LID

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD Sb-124 Ci

<LID

<LLD

<LLD I<LLD 4LID I<LID

<LID

-<LLD

<LID

<LLD I<LID

<LD I<LD

<LD

<LID

<LID Sb-125 CI

<LID

<LID I<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID Sb-126 Ci

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD Te-123m Cl

<LID

<LLD

<LID

-<LID

<LID

<LLD

<LID

<LLD

<LLD Te-132 Ci

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LLD Cs-134 CI

<LID

<LLD

<LID

<110

<LID

<LLD

<LID

<LID Cs-137 Ci

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LLD Cs-138 Ci

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LID Ba-140 Ci

<LID

<LD

<LID

<D

<LID I<LID

<LID

<LID I<LD I<LLD I<LID

<LID

<LD

<LID

<LID La-140 CI

<LID

<LLD

<I LD

<LD

<I LD

<LD

<I LI

<LD-LD-LD-ID

<ID

<I

_e11C LD

<I

<[LID

<LIDD

<LL

<LD

<LLD

<LID

<LIL~D

<LID LD

<I LD

<I Ce-141 Ci

<LLD

<LID

< LI

<I

<LID

<LLD

<LD

<LD LD

<ID LD

<IDLD Pe-44 CI

<LID

<LLD

<LI

<LLD I<LLD

<LID

<LLD

<LID

<LD LI

<ID LD

<LD LD

<IDLD I-_44i Cl

<LID

<LLD

<LI

<LID

<LID ID-LI

<LD

<I

<ID LD

<IDLD 1-1I Ci

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LLD 1-13 Ci

<LID

<LLD

<LID

-<LID

<LID

<LbD

<LID

<LLD

<LID

<LLD 1-13 Ci

<LID

-<LD j<LD

<LLD

<LID

<LLD

<LID

<110

<LID

<LLD

<LLD 115Ci

<LLD

-<LID

<LID cLLD

-<LID

<LID

-<LID

<LLD

<LID

<LLD

<LID

<LLD I<LID

<LID I<LLD

<LLD C. Tritium

1. Total Release Activity ClF[ <LID ]<LID

<LID [<LID f<LD j<LID ]<LID [<LLD

<LID

(<LID

<LLD

<LLD [<LID ]<LLD

(<LLD J

<LLD D. Dissolved and Entrained Gases Ar-41 Ci

<LID

<LID J<LID

<LLD

<LID

<LD

<LID

<LLD

<LID

<LLD

<LID Kr-85 Ci

<LLD

<LID

-<LID

<LLD

<LID

<ILD

-<LID

<LLD

<LID

<LLD

<LLD Xe-131m Cl

<LID

<~LID j<LID

<LLD

-LLD

<LLD

-<LID

<LLD

<LID

-<LID

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LLD Xe-133 Ci

<LID

<LLD

<LID

-<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID Xe-133m Cl

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID Xe-135 Ci

<LID

<LLD

<LID

<LLD

<LID-

<LID

-<LLD

<LLD

<LID

<LLD

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 LIQUID RELEASES UNIT 1 (Docket Numbers 50-295)

SUMMATION OF ALL RELEASES IUnits I Jan IFeb I

Mar I st Qtr Apr May Jun 2nd Qtr Jul IAug Sep 3rd Qtr I Oct INov Dec 4ht oa A. Fission and Activation Products (not mnci.

tritium, gases, alpha) ii. Total Activity Released § I

Ci I <LLD I <LLD I<LLD I<LLD I<LLD I<LLD I<LLD I<LLD I<LLD I 3.43E-05 I 2.50E-05 I 5.93E-05 I 2.88E-05 I <LLD I<LLD I2.88E.05 I8.80E-05

12. Average Conc. Released uCI/mI

<ILD I<LLD

<LLD I<LLD I<LID I<LLD I <LLD I<LLD I<LLD I1.62E-10 I8.34E-10 I8.93E.11 16.81 E-1 11

<LLD I<LLD 16.81 E-1 I 1.39E-12

13. % of Value (9E-7 uC/mI)

<LLD

<LLD I<LLD

<LID I<LLD 1.BOE-02 9.26E-02 I9.92E-03, 7.57E-03 I<LID

<LID 7.57E-03 1.SSE-04 B. Tritium

1. Total Activity Released I

Ci I<LLD I<LLD I<LID I<LLD I<LLD I<LLD I<LLD I<LID I<LLD I4.74E-04 I1.18E-04 I.65E-04 I2.35E-04 I<LLD I<LLD I2.35E-04 I8.00E-04

12. Avera a Conc. Released uCI/mlI

<LLD

<LLD I<LLD

<LLD I<LLD I<LLD I<LID

<LID I<LLD 2.23E-09 3.95E-09 I8.51E.10 I5.57E-10

<LID

<LLD 2.78E-1O0 1.27E-11 3.%o au E3uim LD ID

<LLD

<ILD

<LID

<LLD

<LID I<LID 2.23E-04 3.95E-04 8.51 E-05 5.57E-05

<LLD

<LLD 2.78E-05 12E0 C. Dissolved and Entrained Gases Ii. Total Activity Released ICl I<LLD I<LLD I<LLD I<LID I<LLD I<LLD I<LLD I<LLD I<LLD I<LLD I<LLD I<LLD I<LLD I<LLD I<LLD I

<LLD I O.OOE+00

12. Average Conc. Released uC/I Im <LID I<LID

<LID I<LID I<LLD I<LD I<LLD I<LID I<LID I<LID I<LID I<LID I<LID I<LLD I<LLD I<LID IO.OOE+00

13. % of Value (7E-5 uCIrnmi

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LLD

<LID

<LID O.OOE+0O D. Gross Alpha Ii. Total Activity Released Ci

<LID I <LID I <LID

<LLD

<LID I <LLD I

<LLD

<LID

<LLD I <LID

<LLD

<LID I <LID

<LLD

<LID I

<LID

12. Avera e Conc. Released IuCl/mII

<LID

<LID I<LID I LID I<LID I<LID I<LID I<LID I<LID

<LID I<LID

<LID I<LID I<LID I<LLD I<LID

<LID

13. % of Value (2E-9 uC1/mI)

% I<LID

<LID I<LLD I<LID I<LD I<LLD I<LD I<LLD I<LID

<LID I<LID

<LID I<LID I<LLD I<LID I<-LID

<cLD E. Volume of Releases

1. Volume of Waste ReleasedS liters I.OOE+00 I0.OOE+00 I0.OOE+00 IO.OOE+00OI.OOE+00 IO.OOE+00 I.OOE+00 O.OOE+00 10.OOE+0012.41E+0511.24E+051 3.65E+05 I1.29E405 I0.IJOE+00 I0.CE+00 I1.29E+05 I4.94E+05 j2.Volume of Dilution Water Iliters 14.14E+10 1186E+1014.22E+081 6.04E+10 14.08E+0814.22E+08 I4.08E+08 I1.24E+09 14.22E+0812.12E+08 12.98E+07 I6.64E+08 14.22E+08 I4.OOE-08 14.22E+081 8.44E+08 I6.32E+10

§ Fe-55, Sr-89. and Sr-90 Activities are quantified by quarterly composite analyses. Therefore, the difference between the Fission and Activation Products total quarterly activity and the sum of the total activities of the three corresponding months equals the total quarterly activities of Fe-55, Sr-89, and Sr-g0.

The cells for monthly activity values of Fe-55, Sr-89, and Sr-90 on the Batch and Continuous Mode data sheets are blank because monthly values are not applicable.

t These data include only Information for batch releases from Lake Discharge Tanks.

Lower limit of detection (LLD) values are presented in the Liquid Effluents LLD Values for Liquid Releases section. The abbreviation "<LLD" indicates the activity concentration of the radlonuclide for each Individual sample analyzed during the applicable period was less than the LLD value for that nuclide. If the abbreviation '<LLD' is listed for a group of radionuclides, the activity concentration of each radionuclide for each sample during the period was less than the LLD value for the respectIve radionucide.

The abbreviation "No Rel" Indicates that no releases were performed during the applicable period.

'% of Value" means percent of concentration values in Appendix B, Table 2, Column 2 to 10CFR20. The % of Value for Fission and Activation Products and Dissolved and Entrained Gases provides a comparison of the total concentration of the group to the lowest Isotopic concentration value of the particular group. The concentration of Fission and Activation Products and Dissolved and Entrained Gases are compared to the concentration limits for Cs-134 (9E-7 uCl/mi) and Ar-41 (7E-5 uCI/mi), respectively. Concentration limits for Dissolved and Entrained Gases are listed In ODCM Table 12.3-1.

419 81..,,M @ A6.%~LfI~

%JIVW L.

4I' A In, 1

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 LIQUID RELEASES UNIT 1 (Docket Numbers 50-295)

BATCH MODE I Unts I Jan I

Feb I

Mar I

1st Qtr Apr I

May I

Jun I 2nd Qtr Jul I

Aug Sep I 3rd Qtr Oct I

Nov Dec I 4th Qtr Total A. Fission and Activation Products Na-24 Ci

<LLD No Rei

<LLD No Rel

<LLD

<LLD No Rel

<LLD

<LLD Cr-51 CI

-LLD No Rel

<LLD No Rel

<LLD

<LLD No Rel

<LID

<LD

<LLD

<LD

<LLD

<LLD Mn-54 Ci

<LID No Rel

<LLD

<LLD No Rel

<LLD

<LD

<LID

<LLD

<LID

<LLD

<LLD Co-57 Ci

<LD No Rel

<LLD No Rel

<LLD

<LLD No Rel

<LID

<LLD

<LD

<LLD

<LID

<LLD

<LLD Fe-55 Ci

<LID

<LLD cLLD

<LLD

.LLD

<LLD Fe-59 CI

<LID No Rel

<LLD No Rol

<LD

<LLD

<LLD No Rol

<LLD

<LD

<LLD LLD

<LID

<LD

<LLD

<LLD Co-58 Ci

<LLD No Rel

<LID No Rol

<LD

<LID

<LID No Rel

<LLD

<LID

<LD

<LLD

<LD

<LLD

<LLD Co-60 Ci

<LLD No Rei

<LLD No Rel

<LID

<LLD

<LID No Rel

<LLD 1.09E-05 7.00E-06 1.79E405 8.78E-06

<LLD

<LID 8.78E-06 2.67E-05 Zn-65 Ci

<LD No Rel

<LID No Rel

<LD

<LLD

<LLD No Rel

<LLD

<LD

<LLD

<LD

<LLD

<LLD Sr-85 Cl

<LID No Rel

<LLD No Rel

<LLD

<LID

<LLD No Rel

<LLD

<LID

<LD

<LLD

<LD

<LLD

<LLD Rb88 Ci

<LID No Rel

<LLD No Rol

<LLD

<LID

<LLD No Rol

<LD

<LLD

<LLD Sr-89 Ci No RcL No Rol

<LLD

< <LLD

<LLD Sr-90 CL

<LLD

<LLDD

< LLD

<LLD Sr-92 Ci

<LD

<LLD

<LID No Rl

<LLD

<LID

<LLD No Rel

<LLD

<LD

<LLD

<LD

<LLD

<LD

<LLD

<LLD Nb-95 Ci

<LLD

<LLD No Rel

<LLD

<LID

<LLD No Rel

<LID

<LD

<LLD

<LD

<LLD

<LLD Zr-95 Ci

<LID

<LLD

<LLD No Rel

<LLD

<LLD No Rel

<LLD

<LID

<LLD

<LID

<LD

<LLD

<LLD Zr-97 Ci

<LD

<LLD

<LLD No Rel

<LD

<LID

<LLD No Rel

<LID

<LLD

<LID

<LLD

<LLD Mo-99 Ci

<LD

<LID

<LLD No Rel

<LLD

<LD

<LLD No Rel LID

<LD

<LLD

<LD

<LLD

<LLD Tc-991 Ci

<LLD

<LLD No Rel

<LLD

<LD No Rel

<LLD ULID

<LLD

<LID

<LD

<LLD

<LLD Ru-1 03 Ci

<LD

<LLD No Rel

<LLD

<LD

<LLD No Rl

<LLD

<LD

<LLD

<LID

<LLD

<LLD cLLD

<LLD AS-113m Ci

<LID

<LD dLD No Rel

<LLD

<LD No Rel

<LLD

<LID

<LD

<LLD

<LLD Sn-1 13 CI

<LLD

<LLD No Ret

<LID

<LLD No Rol

<LID

<LLD I<LLD

<LID

<LLD

<LID

<LID Sn-1 17m Ci

<LLD

<LLD No Rei

<LID

<LLD

<LID No Rel

<LLD

<LID

<LLD

<LID cLLD

<LLD Sb-i122 Ci cLLD

<LD

<LLD No Rel

<LLD

<LD No Rel

<LLD

<LD

<LLD

<LLD Sb-1i24 Ci

<LID

<LLD

<LLD No Rel

<LLD

<LID

<LLD No Rel

<LLD

<LD

<LLD

<LID

<LLD

<LLD Sb-125 Ci

<LLD

<LLD No Rel

<LD

<LID No Rel

<LLD 1.60E-06 8.80E-07 2.48E48 6.20E-07

<LLD

<LLD 6.20E47 3.1OE-06 Sb-126 Cl

<LID

<LLD

<LLD No Rol

<LD

<LLD No Rel

<LLD

<LID

<LLD

<LD

<LID

<LLD

<LLD Te-123m Ci

<LLD

<LID No Rel

<LLD

<LD No Rel

<LLD

<LD

<LLD

<LD

<LLD

<LLD Te-132 Ci cLLD

<LLD

<LLD No Rel

<LLD

<LLD No Rel

<LID

<LD

<LLD

<LID

<LLD

<LLD Cs-134 Ci

<LID

<LLD

<LLD No Rel

<LID

<LID No Rel

<LLD 2.50E.07 1.70E-07 4.20E-07 1.60E-07

<LLD

<LLD 1.60E-07 5.80E-07 Cs-137 Ci

<LD

<LLD No Rel

<LLD

<LD No Rel

<LLD 2.16E-05 1.69E-05 3.85E.05 1.92E-05

<LLD

<LID 1.92E-05 5.77E-05 Cs-138 CI

<LID

<LLD

<LD No Rel

<LLD

<LLD No Rel

<LID

<LD

<LLD

<LD

<LID

<LLD

<LLD Ba-140 Ci

<LLD

<LD

<LLD No Rel

<LID

<LLD

<LLD No Rel

<LID

<LLD

<LD

<LID

<LLD

<LLD La-140 Ci

<LD

<LID

<LID No Rol

<LD LLD

<LID No Rel

<LD

<LLD

<LD

<LLD

<LLD Ce-141 Ci

<LID

<LLD

<LD No Rel

<LID

<LD

<LLD No Rel

<LID

<LLD

<LD

<LID

<LD

<LLD

<LLD Ce-144 Ci

<LID

<LLD

<LLD No Rel

<LLD

<LID No Rel

<LD

<LLD

<LD

<LLD

<LID

<LLD

<LLD Pr-14 Ci LID

<LD

<LID No Rl

<LD

<LD No Re

<LD

<LLD

<LD

<LLD

<LID

<LLD

<LLD B. lodines 1-131 Ci

<LID

<LD d<LD No Rel

<LLD

<LID

<LLD No Rel

<LLD

<LLD lLID

<LLD

<LID

<LLD

<LD I

<LLD lT

<LLD 1-132 CI

<LLD

<LD

<LLD No Rel

<LD

<LLD

<LID No Rel

<LID

<LID l

LD l

LID l

LID

<LID cLLD l

LLD i-133 Ci

<LD

<LID

<LD No Rel

<LLD l

LID

<LID I No Rel lLLD lLID l

LID cLID

<LID

<LID ID I

LLD

<LID 1-134 Ci

<LLD

<LID

<LID No Rel

<LID lLID lLID No Rel l

LID l

LID

<LID l

LID l

LID lLID

<LID l

LID 1-135 CI

<LD

<LLD No Rel a L D

<LID

<LLD No Rel lLID l

LID

<LID cLLD cLID

<LID

<LID l

LID cLLD C. Tritium

1. Total Release Actlvily Ci

<LID

<LID i

<LID No Rel l

<LD l

<LID

<LLD

[

No Rel

<LID I 4.47E-04 11.18E-04 5.65E-04 ]2.35E-04 [

<LID l

<LID l 2.35E404 8.00E44 D. DIssolved and Entrained Gases lAr-41 l

Ci

<LID

<LID No Rel

<LLD

<LID No Rel

<LID

<LLD

<LLD l

<LLD

<LLD Kr-85 Ci

<LD

-No Rei

<LD

<LID

<LLD No Rel

<LLD

<LID

<LLD

<LID

<LLD

<LLD Xe-131mr Ci

<LID

<LLD

<LID No Rel

<Ll D

<LLD

<Ll D No Ret

<LLD

<LLD l

LLD

<LLD

<LLD Xe-133 Ci

<LID

<LLD

<LID l

No Rel

<LLD

<LID

<LD No Rel

<LID

<LLD

<LLD l

<LLD

<LLD Xe-133m CI

<LID

<LID No Rel

<LID

<LID No Rel

<LLD

<LID

<LLD

<LID

<LLD

_Xe-135 I

Ci

<LID

<LLD -

<LLD No Rel

<LLD

<LbD

<LD No Rel

<LLD

<LD

<LLD

<LID

<LLD cLLD

<LLD

IV MI I I

I V

I WL X I

-V s ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 LIQUID RELEASES UNIT 1 (Docket Numbers 50-295)

CONTINUOUS MODE I Units Jan Feb I

Mar 1st Qtr I

Apr I

May Jun 2nd Qtr Jul I

Aug SeP 3rd Qtr Oct Nov Dec 4th Qtr Total A. Fission and Activation Products Na-24 Ci

<LLD

<LLD No Rel

'LLD

<LID cLID No Rel

<LD

<LID

<LLD

<LLD l

LID

<LLD

<LLD cLLD Cr-51 Ci

<LID

'ILD

<LID No Rel

<LLD

<LID No Rel

<LLD

<LLD cLLD

<LLD

<LD

<LLD cLLD Mn-54 Ci

<LD

<LID

<LLD No Rol

<LD

<LID

<LD No Rel

<LLD

'LLD

<LID

<LLD

<LD

<LID

<LLD

<LLD Co-57 CI

<LLD

<LID

<LLD No Rel

<LID

<ILD

<ILD No Rel

<LLD

<LD

<LID

<LLD

<LLD LID

<LLD

<LLD Fe-55 Ci

<LLD

<LLD Fe-59 Ci

<LD

'LID

<LLD No Rl

<LLD CLLD

<ILD No Rel

<LLD

<LID

<LLD

<LLD Co-58 Ci

<LID

<LD

'LID No Rel

<LLD

'LD

<LID No Rel

<dLD

'LD

'LID

<LLD

<LLD LLD

<LLD

<LLD Co-60 Ci

<LLD

'LID

<LD No Rel

<LID

<LLD

<LLD No Rel

'LLD

<LLD

'LLD

<LLD LLD

<LLD

<LID

<LLD

<LLD Zn-65 Ci

<LD

<LLD

<LLD No Rel

<LLD

'LID

<LLD No Rel

<LLD cLLD LID

<LLD

'LLD

<LLD

<LLD Sr-85 Ci

<LID

<LLD No Rel

<LLD

'LID No Rel cLLD

<LD

'LLD cLLD

<LLD

<LLD Rb-88 Ci

<LID

<LD

<LLD No Rel cLID

'LLD

<LLD No Rol

'LD

'LID

<LLD cLLD

<LLD

<LLD Sr-89 Ci L_

<LD L__

cLD

< <LLD

<LLD

<LLD Sr-90 Ci cLLD

<LLD

<LD cLLD

<LLD

<LLD Sr-92 Ci

<LLD

'LD

<LLD No Rel

<LLD

<LID

<LID No Rel

<LD

'LLD

<LLD

<LLD Nb-95 Cl

<LID

'LID -

LLD No Rel

<LLD

-LLD

<LID No Rel

<LLD

<LLD cLLD

<LID

'LD

<LLD cLLD Zr-95 Ci

<LLD

'LID cLLD No Rel

<LD

<LLD

<LLD No Rel

<LLD

<LLD LID

<LLD

<LLD LID

LLD

<LLD

<LLD Zr-97 Ci

<LLD

<LD No Rel

<LLD cLID LID No Rel

<LLD

<LID

<LLD

<LLD eLID

<LLD

<LLD MO-99 Ci

<LLD

<LID

<LLD No Rel LID LID cLLD No Rei

'LLD LID

<LID

<LLD LID

<LID

<LLD

<LLD Tc-991 Ci

'LD

<LD

<LLD No Rel

<LID

<LD

<LLD No Rel

<LLD

'LLD

<LLD

'LID LID LLD

<LLD

<LLD Ru-103 Cl

<LLD

'LD No Rel LID cLID

<LID No Rel

<LID LLD

<LID

<LLD

<LID

<LLD

<LLD AS-113m Ci

<LLD LID cLLD No Rol

<LD

<LLD

'LD No Rel

<LLD LID

<LLD

<LLD Sn-113 Ci

<LLD

<LD No Rel

<LLD

<LID

<LD No Rel

<LLD I

LLD LID

<LLD

'LLD

<LLD

<LLD Sn-117m Cl

<LLD

<LLD cLID No Rol

<LD

<LLD

<LLD No Rel

<LLD

<LLD LID

<LLD

<LD

<LLD

<LLD Sb-122 Ci

<LLD ILID

'LID No Rel

<LLD

<LID

'LD No Rel

'LLD

<LD

<LID

<LLD

<LID LID

<LLD

<LLD Sb-124 Ci

<LLD

<LID

<LID No Rei

<LLD cLLD

<LLD No Rel

<LLD

<LLD cLLD

<LID

<LLD ILID

<LLD

<LLD Sb-125 CI

<LLD ILID LID No Rel LID cLLD

<LLD No Rol

'LLD

<LID

<LLD

<LLD LID

<LID

<LLD

<LLD Sb-126 Ci LID

<LLD cLID No Rel LID

<LLD

<LLD No Rel LLD

<LID cLID

<LLD sLLD

<LLD LID

<LLD

<LID Te-123m Ci LID

<LLD

<LID No Rel

<LLD cLLD

<LLD No Rel

<LLD

<LLD LID

<LLD

<LID

'LID

'LLD

<LLD

<LLD Te-132 Ci

<LLD

<LLD No Rel

<LLD

<LLD cLID No Rel

<LLD

'LLD ILID

<LLD

<LD

<LLD

<LLD Cs-134 Ci cLID

'LLD 10LD No Rel

<LLD

<LID No Rel

'LID LID

<LID

<LLD

<LID

<LLD

<LLD Cs-137 Ci

<LLD cLID

<LD No Rel

<LLD

<LID

<LLD No Rel LID

<LLD

'LLD

<LLD

'LLD

<LID

'LID

<LLD

<LLD Cs-138 Ci

<LLD

<LID LID No Rel

<LLD

<LLD No Rel

-LLD

<LLD

<LID

<LLD

<LLD Ba-140 Ci

<LID

'LID LID No Rel

<LID

<LLD

<LLD No Rel

<LILDLD LLD

<LLD LD LD LLD

<LLD

<LLD La-140 Ci

'LID

'LID LID No Rel

<LID LID cLLD No Rel LID

'LLD

<LLD

<LID

<LLD

<LLD Ce-1 41 Ci

'LID LID

<LLD No Rei

<LLD

<LID

<LLD No Rel LID

<LLD

<LID

<LLD

<LD LID

<LID

<LLD

<LD Ce-144 Ci

<LLD LID

'LID No Rei

'LID

<LID

<LD No Rol

<LID

<LI

<I

<LID

<LI Pr-144 Ci

'LD

<LLD LID No Rel

<LLD LID LID No Rel

<LLD

<LLD LID

<LID

'LID

<LLD

<LID

<LID B. Iodines I-131 Ci

<LLD LID

'LD No Rel

<LD

<LID

<LLD No Rel

<LLD

<LLD lLID

<LLD

<LLD 1-132 Ci C

LID

<LLD LID No Rel

<LD

<LLD

<LID No Rel ILLD I LLD ILLD

<LLD ILID

<LLD

<LLD 1-133 Ci

<LID

'LID

<LLD No Rel

<LLD cLID LLD No Rel

<LLD

'LLD I

LID

<LLD jLLD lLID

'LID

<LLD j

<LLD 1-134 Ci

<LLD

<LLD No Rel

<LLD

'LLD

<LID No Rel LID

<LLD I <LLD

<LLD LID

<LID l

<LLD l

LLD

< LLD 1-135 Ci

<LID LID

<LID No Rel

<LLD

<LD No Rel lLID LID l

LLD

<LLD

<LID

<LLD

<LLD C. Tritium 1[ Total Release Activity Ci]

LID

< 'LLD l

'LID l

No Rel l <LID l

'LID

<LLD l

No Rel

<LID [ <LLD LD LD

<LLD

<LID

<LID I

<LLD

<LLD D. Dissolved and Entrained Gases Ar-41 l

Cl l

'LID

<LID lLLD l No Rel lLLD lLLD lLID l

No Rel lLID

<LID

<LLD cLID l

LLD

'LID

< cLLD

<LLD Kr-85 Ci

<LLD

<LID I

No Rel

<LLD ILLD ILID No Rel I

LLD ILLD

<LLD I

<LLD ILID

'LLD

<LID

< cLLD

<LLD Xe-131m Cl ILID ILID ILID I

No Rel ILID eLLD cLLD No Rel

<LLD

'LLD

'LID

<LLD cLD

< LID

<LLDJ

<LLD

<LLD Xe-133 CT

<LLD

<LID

'LLD l

No Rel

'LID lLID

'LID No Rel

< eLLD lLLD lLLD l

<LLD

< 'LLD cLID cLLD

<LLD Xe-133m Ci ILID ILID ILID I

No Rel ILID ILID ILID No Rel

<LD

<LLD I 'LID IcLLD LLD I

LD ILLD LLD

< LLD Xe-135 Cl jLLD jLLD

'LLD j

No Rol

<LLD

<LLD No Rel lLID

-LLD lLLD

<LLD

<LID

'LLD

<LLD cLLD

<LLD

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 UNIT 1 & 2 (Docket Numbers 50-295 & 50-304)

LIQUID EFFLUENTS LOWER LIMIT OF DETECTION (LLD) VALUES FOR LIQUID RELEASES Isotope Alpha H-3 Kr-85 Mn-54 Fe-55 Co-58 Fe-59 Co-60 Zn-65 Sr-89 Sr-90 Mo-99 Cs-1 34 Cs-137 Ce-141 Ce-144 LLD (uCi/ml) 1.00E-07 1.00E-05 1.OOE-05 5.0OE-07 1.OOE-06 5.00E-07 5.OOE-07 5.OOE-07 5.OOE-07 5.00E-08 5.OOE-08 5.00E-07 5.OOE-07 5.OOE-07 5.OOE-07 5.OOE-07 NOTE:

LLDs for other liquid effluent isotopes included in the Annual Radioactive Effluent Release Report were not available for submittal.

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 UNIT 1 (Docket Number 50-295)

LIQUID EFFLUENTS SUPPLEMENTAL RELEASE INFORMATION I

Batch Releases 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr 2003

a. Total Number of Batch Releases 0

0 O

6 2

8

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 UNIT 2 (Docket Number 50-304)

LIQUID EFFLUENTS SUPPLEMENTAL RELEASE INFORMATION

4.

Batch Releases 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr 2003

a.

Total Number of Batch Releases 0

0 0

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 UNIT I & 2 (Docket Numbers 50-295 & 50-304)

LIQUID EFFLUENTS SUPPLEMENTAL RELEASE INFORMATION

1. Regulatory Limits The calculated annual total quantity of all radioactive material above background released from each unit at Zion Station to unrestricted areas is limited by off-site dose restrictions stated in the station technical specifications, Off-site Dose Calculation Manual (ODCM), and 10CFR50 Appendix I. The off-site dose limits per reactor unit are listed below.

Quarterly Yearly (mrem)

(mrem)

Total Body Organ 1.5 5

3 10

2.

Maximum Permissible Concentrations Zion Station technical specifications limit concentrations of radioactive material released in liquid effluents to unrestricted areas to ten times the concentration values in Appendix B, Table 2, Column 2 to 1 OCFR20.

3. Measurements and Approximations of Total Radioactivity

a. Fission and Activation Products Gamma Spectroscopy, Liquid Scintillation Low-energy Photon Spectroscopy (LEPS, for Fe-55)

b. Tritium Liquid Scintillation

c. Noble Gases Gamma Spectroscopy

d. Gross Alpha Gas Flow Proportional Counting Composite sample analyses for Fe-55, Sr-89, and Sr-90 are performed by off-site vendor.

4.

Batch Releases 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr 2003

a. Total Number of Batch Releases 0

0 6

2 8

ML041320541

Text

Reference:

Subject:

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====== QUARTER 1

SUMMARY

========= QUARTER 1

SUMMARY

============

====== QUARTER 2

SUMMARY

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== NG DOSE LIMIT ANALYSIS

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2

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