Text

Radioactive Effluent Release Report
	ML040860098
Person / Time
Site:	Zion File:ZionSolutions icon.png
Issue date:	03/16/2004
From:	; Exelon Generation Co, Exelon Nuclear
To:	; NRC/FSME
References
	+kBR1SISP20051207, -RFPFR
	Download: ML040860098 (346)
	v • d • e

i .

- - -1 ZION NUCLEAR POWER STATION

- 2003 RADIOACTIVE EFFLUENT RELEASE REPORT UNIT I & 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 1 discharge vent was mechanically closed.

Airborne Yearly Dose Dose to Dose to Limit per Maximally Maximally Reactor Unit Exposed Exposed Receptor Receptor (Adult) from (Adult) from Unit 1 Unit 2 Gamma Air 10 mrad 0 mrad 0 mrad Beta Air 20 mrad 0 mrad 0 mrad Total Body 5 mrem 7.64e-5mrem 7.54e-5 mrem Skin 15 mrem 0 mrem 0 mrem Organ 15 mrem 8.55e-5 mrem 8.75E-5 mrem

. . II -.

-- . i.

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 Dose to Dose to Limit per Maximally Maximally Reactor Unit Exposed Exposed Receptor Receptor from (Teenage) from Unit 2 Unit 1

-F Total Body 3 mrem 2.48e-2 mrem 0 mrem Organ 10 mrem _

I3.93e-2 mremI 0 mrem .

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 1 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 ate not Regulatory Commitments.

oitmeit:l Vqo,.

ZION STATION Unit 2 10CFR20 Compliance Assessment

1. 10CFR 20.1301 (a) (1) Compliance Total Effective Dose Equivalent, mremlyear 1.56e-3 10 CFR 20.1301 (a) (1) limit mrem/lvr 100

% of the limit 0.002

2. Compliance Summary I0CFR20 1 ' Qtr. 2nd Qtr. 3rd Qtr. 4 th Qtr % of Limit TEDE 0 1.02e-4 0 5.85e-5 0.002%

ZION STATION Unit 1 10CFR20 Compliance Assessment

1. 10CFR 20.1301 (a) (1) Compliance Total Effective Dose Equivalent, mrem/vear 6.29e-2 10 CFR 20.1301 (a) (1) limit mremjVr 100

% of the limit 0.06

2. Compliance Summary 10CFR20 1 5sQtr. 2 nd Qtr. 3r Qtr. 4th Qtr % of Limit TEDE 0 1.Ole-4 4.14e-2 2.12e-2 0.06%

_ - RETDAS v3.6.3 <ZIO> VSSI 40C FR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range - From: 1 To: 2

=== I&P DOSE LIMIT ANALYSIS == QUARTER 1 Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit Qtr 1 - Admin. Any Organ 0.00E+00 1.00E+01 0.OOE+00 Qtr 1 - Admin. Total Body 0.00E+00 1.OOE+01 0.OOE+00 Qtr 1 - T.Spc. Any Organ 0.00E+00 1.OOE+01 0.00E+00 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compass Point: NA Critical Pathway:

Major Contributors ( 0% or greater to total)

Nuclide Percentage Qtr 1 - T.Spc. Total Body 0.OOE+00 1.00E+01 0.OOE+00 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compass Point: NA Critical Pathway:

Major Contributors ( 0% or greater to total)

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

- RETDAS v3.6.3 <ZIO> VSSI 4OCIFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

To:_____________2___

Report for: 2003 Unit Range - From: 1 To: 2

=== NG DOSE LIMIT ANALYSIS QUARTER 1 Dose Limit Max % of Quartr - Limit (mrad) (mrad) Limit Qtr_ 1_______ A_______GammaE-Qtr 1 - Admin. Gamma 0.00E+00 1.00E+01 0.OOE+00 Qtr 1 - Admin. Beta 0.00E+00 1.00E+01 0.00E+00 Qtr 1 - T.Spc. Gamma 0.OOE+00 1.OOE+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.OOE+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 - 7

. 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 == QUARTER 2

Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit Qtr 2 - Admin. Any Organ ADULT GILLI 1.08E-04 5.63E+00 1.92E-03 Qtr 2 - Admin. Total Body CHILD TBODY 9.50E-05 5.25E+00 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 1.00E+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 Date/Time: 02/25/2004 07:47 retdas Page - 8

I 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 QUARTER 2 Dose Limit Max % of Quartr - Limit (mrad) (mrad) Limit Qt r _ 2 _-_ _ _ _ _i A_ n ___m_m

__Ga a_ _ _ _ _ _ _ _ _ _ _ _ _ _ _E__ _ _ _ _ - - - - E+ -

Qtr 2 - Admin. Gamma 0.00E+00 7.50E+C'0 0.00E+00 Qtr 2 - Admin. Beta 0.00E+00 7.50E+C'0 0.00E+00 Qtr 2 - 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 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 <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 == QUARTER 3 Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit Qtr 3 - Admin. Any Organ ADULT GILLI l.11E-04 5.63E+C)0 1.98E-03 Qtr 3 - Admin. Total Body CHILD TBODY 9.82E-05 5.25E+C)0 1.87E-03 Qtr 3 - T.Spc. Any Organ ADULT GILLI 1.11E-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 Date/Time: 02/25/2004 07:47 retdas Page - 10

, 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 ==QUARTER 3 Dose Limit Max % of Quartr - Limit (mrad) (mrad) Limit

_t__3 -_______in._____Gamma ________________E______ 7.50E+C Qtr 3 - Admin. Gamma 0.00E+00 7.50E+C)0 0.00E+00 Qtr 3 - Admin. Beta 0.00E+00 7.50E+()0 0.00E+00 Qtr 3 - T.Spc. Gamma 0.00E+00 7.50E+00 Q.00E+00 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compass Point: NA Nuclide Percentage Qtr 3 - T.Spc. Beta 0.OOE+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 - 11

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 QUARTER 4 Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit Qtr 4 - Admin. Any Organ ADULT GILLI 6.32E-C)5 5.63E+C'0 1.12E-03 Qtr 4 - Admin. Total Body CHILD TBODY 5.57E-C )5 5.25E+C'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 Date/Time: 02/25/2004 07:47 retdas Page - 12

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 ==QUARTER 4 Dose Limit Max % of Quartr - Limit (mrad) (mrad) Limit Qtr _____________________________________________

4_ -_ A in Ga m--E _ _- ---- _- -

Qtr 4 - Admin. Gamma 0.OOE+00 7.50E+00 0.OOE+00 Qtr 4 - Admin. Beta 0.00E+00 7.50E+00 0.00E+00 Qtr 4 - T.Spc. Gamma 0.001E+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 0.00E+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 - 13

VS SI

RETDAS v3.6.3 RETDAS v3.6.3 (ZIO>

<ZIO> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT

_____________GASEOUS____DOSE__

SUMMARY

GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range - From: 1 To: 2

=== I&P DOSE LIMIT ANALYSIS ANNUAL 2003 Age Dose Limit Max % of Annual - 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 TBODY 2.49E-04 1.05E+01 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

j RETDAS v3.6.3 <ZIO> VSSI 40CFRl90 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Report for: 2003 Unit Range - From: 1 To: 2

=== NG DOSE LIMIT ANALYSIS ==ANNUAL 2003 Dose Limit Max % of Annual - Limit (mrad) (mrad) Limit 2003 - Admin. Gamma 0.OOE+00 1.50E+01 0.00E+00 2003 - Admin. Beta Q.OOE+00 1.50E+01 0.00E+00 2003 - T.Spc. Gamma 0.00E+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

rSETDAS v3.6.3 <ZIO> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT Report for. 2003 Unit Range - FronI: 1 To: 2

MAXIMUM DOSE ANALYSIS ANNUAL 2003 ======

Age Dose Dose Type Group Organ (mrem)

Any Organ TEEN LIVER 3.72E+00 Liquid Receptor: Liquid Receptor Gaseous Receptor: 5 Composite Crit. Receptor - IP Distance: 0.0( )o(meters) Compass Point: NA Liquid Dose: 3.72E+00 % of Total: 1.OOE+02 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 Gaseous Dose: 2.38E-04 % of Total: 6.40E-03 Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors 0% or greater to total)

Nuclide Percentage CO-60 1.00E+02

MAXIMUM DOSE ANA LYSIS ==== ANNUAL 2003 ======

Age Dose Dose Type Group Organ (mrern)

Total Body ADULT TBODY 2.351E+00 Liquid Receptor: 0 Liquid Receptor Gaseous Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compass Point: NA Liquid Dose: 2.35E+00 % of Total: 1.00E+02 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 Date/Time: 02/25/2004 07:47 retdas Page - 16

vS I

.4 U-A v36. <zO

- ;.,.i i1Z'ZDAS

1. v3.6.3 <ZIO> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT Gaseous Dose: 2.40E-04 % of Total: 1.02E-02 Critical Pathway: Ground Plane Deposition (GPD)

Major Contributors ( 0% or greater to total)

Nuclide Percentage CO-60 1.0OE+02 Date/Time: 02/25/2004 07:47 retdas Page - 17

" _ RETDAS v3.6.3 <ZIO> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT C- -

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 QUARTER 1 Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit Qtr 1 - Admin. Any Organ O.OOE+00 1.50E+C I1 0.00E+00 Qtr 1 - Admin. Total Body ADULT TBODY 0.OOE+00 1.13E+C '0 0.00E+00 Qtr 1 - T.Spc. Any Organ 0.OOE+00 3.75E+00 0.00E+00 Critical Pathway:

Major Contributors ( 0% or greater to total)

Nuclide Percentage Qtr 1 - T.Spc. Total Body ADULT TBODY 0.00E+00 1.50E+00 0.00E+00 Critical Pathway: Potable Water (PWtr)

Major Contributors ( 0% or greater to total)

Nuclide Percentage Date/Time: 02/25/2004 07:47 retdas Page - 1

S

~

RETDAS~ ~ <IO ~ v363

,7 - % -, RETDAS v3.6.3 <ZIO> VSSI 40CFRl90 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 =QUARTER 2 Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit Qtr 2 - Admin. Any Organ 0.00E+00 5.OOE+00 0.OOE+00 Qtr 2 - Admin. Total Body ADULT TBODY 0.OOE+00 1.13E+00 0.OOE+00 Qtr 2 - T.Spc. Any Organ 0.00E+00 3.75E+00 0.OOE+00 Critical Pathway:

Major Contributors ( 0% or greater to total)

Nuclide Percentage Qtr 2 - T.Spc. Total Body ADULT TBODY 0.OOE+00 1.50E+00 0.OOE+00 Critical Pathway: Potable Water (PWtr)

Major Contributors ( 0% or greater to total)

Nuclide Percentage Date/Time: 02/25/2004 07:47 retdas Page - 2

%. '. RETDAS v3.6.3 <ZIO> 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 3 Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 7.10E-01 9.78E-01 7.14E-06 3.32E-01 1.10E-01 2.31E-02 0.00E+00 6.43E-01 TEEN 7.60E-01 1.02E+00 5.25E-06 3.46E-01 1.34E-01 1.74E-02 0.O0E+00 3.57E-01 CHILD 9.57E-01 9.22E-01 7.19E-06 3.00E-01 1.08E-01 6.80E-03 0.OOE+00 1.37E-01 INFANT 1.01E-03 1.21E-03 4.91E-06 3.25E-04 1.34E-04 3.17E-05 0.00E+00 1.13E-04

=== SITE DOSE LIMIT ANALYSIS QUARTER 3 Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit Qtr 3 - Admin. Any Organ TEEN LIVER 1.02E+00 3.75E+()0 2.71E+01 Qtr 3 - Admin. Total Body ADULT TBODY 6.43E-01 1.13E+C)0 5.72E+01 Qtr 3 - T.Spc. Any Organ TEEN LIVER 1.02E+00 5.00E+00 2.04E+01 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 Qtr 3 - T.Spc. Total Body ADULT TBODY 6.43E-01 1.50E+00 4.29E+01 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 Date/Time: 02/25/2004 07:47 retdas Page - 3

. RETDAS v3.6.3 <ZIO> 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 7.83E-01 1.08E+00 6.67E-06 3.65E-01 1.21E-01 2.54E-02 0.00E+00 7.08E-01 TEEN 8.39E-01 1.12E+00 4.90E-06 3.81E-01 1.48E-01 l.91E-02 0.00E+00 3.92E-01 CHILD 1.06E+00 1.02E+00 6.71E-06 3.31E-01 1.19E-01 7.47E-03 0.OOE+00 1.51E-01 INFANT 1.12E-03 1.33E-03 4.58E-06 3.57E-04 1.47E-04 3.37E-05 0.00E+00 1.23E-04

=== SITE DOSE LIMIT ANALYSIS =QUARTER 4 -

Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit Qtr 4 - Admin. Any Organ TEEN LIVER 1.12E+00 3.75E+00 2.99E+01 Qtr 4 - Admin. Total Body ADULT TBODY 7.08E-01 1.13E+00 6.29E+01 Qtr 4 - T.Spc. Any Organ TEEN LIVER 1.12E+00 5.00E+00 2.24E+01 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 7.08E-01 1.50E+00 4.72E+01 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 Date/Time: 02/25/2004 07:47 retdas Page - 4

% I RETDAS v3.6.3 <ZIO> 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 2.60E+00 3.58E+00 2.48E-05 1.21E+00 4.03E-01 8.45E-02 0.00E+00 2.35E+00 TEEN 2.78E+00 3.72E+00 1.82E-05 1.27E+00 4.92E-01 6.35E-02 0.OOE+00 1.30E+00 CHILD 3.50E+00 3.37E+00 2.50E-05 1.10E+00 3.95E-01 2.48E-02 0.OOE+00 5.02E-01 INFANT 3.71E-03 4.42E-03 1.70E-05 1.19E-03 4.91E-04 1.15E-04 0.OOE+00 4.11E-04

=== SITE DOSE LIMIT ANALYSIS - ANNUAL 2003 Age Dose Limit Max % of Annual - Limit Group Organ (mrem) (mrem) Limit 2003 - Admin. Any Organ TEEN LIVER 3.72E+00 7.50E+00 4. 97E+01 2003 - Admin. Total Body ADULT TBODY 2.35E+00 2.25E+00 1.05E+02 2003 - T.Spc. Any Organ TEEN LIVER 3.72E+00 1.OOE+01 3.72E+01 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 2003 - T.Spc. Total Body ADULT TBODY 2.35E+00 3.OOE+00 7.84E+01 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 Date/Time: 02/25/2004 07:47 retdas Page - 5

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

INFANT RECEPTOR I Maximum Quarterly Dose (mrad, mrem) Yearly Maximum % of I QtrIy Obi I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Limit Annual Yearly Dose Dose 10CFR50 (mrad, Limit A. Airborne Appendix I mrem)

Gamma Air 5.0 mrad 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 10.0 mrad 0.OOE+00 0.00%

Beta Air 10.0 mrad 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 20.0 mrad 0.00E+00 0.00%

Total Body 2.5 mrem 0.OOE+00 4.53E-05 0.OOE+00 2.65E-05 5.0 mrem 7.18E-05 0.00%

Skin 7.5 mrem 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 15.0 mrem 0.00E+00 0.00%

Organ 7.5 mrem 0.OOE+00 4.68E-05 0.OOE+00 2.75E-05 15.0 mrem 7.43E-05 0.00%

Critical Organ Lung Lung Lung B. Aquatic Total Body 1.5 mrem 0.00E+00 0.00E+00 2.88E-06 1.46E-06 3.0 mrem 4.34E-06 0.00%

Internal Organ 5.0 mrem 0.OOE+00 9.O+00 3.09E-05 1.58E-05 10.0 mrem 4.67E-05 0.00% l Critical Organ _ Liver Liver 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 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 I (Docket Number 50-295)

CHILD RECEPTOR I Maximum Quarterly Dose (mrad, mrem Yearly Maximum % of l Qtrly Obi 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr I Limit Annual Yearly Dose Dose IOCFR50 (mrad, Limit A. Airborne Appendix I mrem)

Gamma Air 5.0 mrad 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 10.0 mrad 0.OOE+00 0.00%

Beta Air 10.0 mrad 0.00E+00 O.00E+00 0.00E+00 0.00E+00 20.0 mrad 0.00E+00 0.00%

Total Body l2.5 mrem l0.00E+00 4.75E-05 0.00E+00 2.79E-05 5.0 mrem 7.54E-05 0.00%

Skin 7.5 mrem 0.00E+00 0.00E+00 0.00E+00 0.00E+00 15.0 mreml 0.00E+00 0.00%

Organ 7.5 mrem 0.00E+00 4.99E-05 0.00E+00 2.93E-05 15.0 mrem 7.92E-05 0.00%

Critical Organ Gi-Lli Gi-Lli Gi-Lli B. Aquatic Total Body l1.5 mrem O.00E+00 O.00E+00 3.51E-03 1.80E-03 l3.0 mrem 5.31E-03 0.18%

Internal Organ 5.0 mrem 0.00E+00 0.00E+00 2.45E-02 1.26E-02 10.0 mrem 3.71E-02 0.37%

Critical Organ bone bone 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 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 1 (Docket Number 50-295)

TEENAGE RECEPTOR I Maximum Quarterly Dose (mrad, mrem) I Yearly Maximum % of I Qtrly Obj 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Limit Annual Yearly Dose Dose 10CFR50 (mrad, Limit A. Airborne Appendix I mrem)

Gamma Air 5.0 mrad 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 10.0 mrad 0.OOE+00 0.00%

Beta Air 10.0 mrad 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 20.0 mrad 0.OOE+00 0.00%

Total Body 2.5 mrem 0.OOE+00 4.62E-05 0.OOE+00 2.71E-05 5.0 mrem 7.33E-05 0.00%

Skin 7.5 mrem 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 15.0 mrem 0.OOE+00 0.00%

Organ 7.5 mrem 0.OOE+00 5.30E-05 0.00E+00 3.1 E-05 15.0 mrem 8.41 E-05 0.00%

Critical Organ __ _ Gi^Lli __ Gi-Lli Gi-Lli B. Aquatic Total BodY l 1.5 mrem O.J0E+00 0.00E+00l 9.11E-03 I 4.66E-03 3.0 mrem 1.38E-02 l0.46%

Internal Organ 5.0 mrem J.00E+00 0.00E+00l 2.60E-02 1.33E-02 110.0mrem 3.93E-02 l0.390/

Critical Organ liver I liver 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.

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

ADULT RECEPTOR Maximum Quarterly Dose (mrad, mrem) Yearly Maximum % of Qtrl Obi I 1st Qtr I 2nd Qtr I 3rd Qtr 4thQtr Limit Annual Yearly Dose Dose 10CFR50 (mrad, Limit A. Airborne Appendix I mrem)

Gamma Air 5.0 mrad O.OOE+0O 0.OOE+00 0.OOE+00 0.OOE+00 10.0 mrad 0.OOE+00 0.00%

Beta Air 10.0 mrad O.OOE+00 l.00E+0 0.OOE+00 0.00E+00 20.0 mrad 0.00E+00 0.00%

Total Body l2.5 mrem 0.OOE+00 4.95E-05 0.OOE+00 2.69E-05 5.0 mrem 7.64E-05 0.00%

Skin 7.5 mrem 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 15.0 mrem 0.00E+00 0.00%

Organ 7.5 mrem 0.OOE+00 5.39E-05 0.OOE+00 3.16E-05 15.0 mrem 8.55E-05 0.00%

Critical Organ Gi-Lli Gi-LIi GI-Lli B. Aquatic Total Body 1.5 mrem 0.OOE+00 0.OOE+00 1.64E-02 l 8.41E-03 3.0 mrem 2.48E-02 0.83%

Internal Organ 5.0 mrem 0.00E+00 0.OOE+00 2.50E-02 1.28E-02 l 0. rem 3.78E-02 0.38%

Critical Organ liver liver 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.

I - v; 1, 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) i Yearly Maximum % of QtrIl Obj I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Limit Annual Yearly Dose Dose 10CFR50 (mrad, Limit A. Airborne Appendix I mrem)

Gamma Air 5.0 mrad 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 10.0 mrad 0.OOE+00 0.00%

Beta Air 10.0 mrad 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 20.0 mrad 0.OOE+00 0.00%

Total Body 2.5 mrem 0.OOE+00 4.53E-05 0.OOE+00 2.65E-05 5.0 mrem 7.18E-05 0.00%

Skin 7.5 mrem 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 15.0 mrem O.OOE+00 0.00%

Organ 7.5 mrem 0.OOE+00 4.68E-05 0.00E+00 2.75E-05 15.0 mrem 7.43E-05 0.00%

Critical Organ I Lung Lung Lung B. Aquatic Total Body 1.5 mrem l 0.OOE+00l 0.00E+00 0.OOE+00 0.00E+00 3.0 mrem 0.00E+00 l0.00%

Internal Organ 5.0 mrem 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 l 0.re .00E+00 l0.00%

Critical Organ N/A N/A N/A N/A N/A l 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) Yearly Maximum % of Qtrly Obj 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Limit Annual Yearly Dose Dose 10CFR50 (mrad, Limit A. Airborne Appendix I mrem)

Gamma Air 5.0 mrad 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 10.0 mrad 0.00E+00 0.00%

Beta Air 10.0 mrad 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 20.0 mrad 0.00E+00 0.00%

Total Body 2.5 mrem 0.00E+00 4.75E-05 0.00E+00 2.79E-05 5.0 mrem 7.54E-05 0.00%

Skin 7.5 mrem 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 15.0 mrem 0.00E+00 0.00%

Organ 7.5 mrem 0.00E+00 4.99E-05 0.00E+00 2.93E-05 15.0 mrem 7.92E-05 0.00%

Critical Organ Gi-Lli Gi-Lli Gi-Lli B. Aquatic Total Body 1.5 mrem 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 3.0 mr;em0.00E++/-0 0.00%

Internal Organ 5.0 mrem 0.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 10.0mrem7 0.00E+00 l0.00 Critical Organ N/A N/A lN/A N/A l 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.

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

TEENAGE RECEPTOR Maximum Quarterly Dose (mrad, mrem) Yearly Maximum % of Qtrly Obj 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Limit Annual Yearly Dose Dose 10CFR50 (mrad, Limit A. Airborne Appendix I mrem)

Gamma Air 5.0 mrad 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 10.0 mrad O.OOE+00 0.00%

Beta Air 10.0 mrad 0.OOE+00 O.00E+00 O.OOE+00 0.OOE+o4 20.0 mrad 0.OOE+00 0.00%

Total Body 7 2.5 mrem 0.OOE+00 4.62E-05 0.OOE+00 2.71E-05 5.0 mrem 7.33E-05 0.00%

Skin 7.5 mrem 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 15.0 mrern 0.OOE+00 0.00%

Organ 7.5 mrem 0.OOE+00 5.30E-05 0.OOE+00 3.11 E-05 15.0 mrem 8.41 E-05 0.00%

Critical Organ Gi-Lli Gi-Lli Gi-Lli B. Aquatic Total Body 1.5 mrem 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 3.0 mrem 0.OOE+00 0.0 Internal Organ 5.0 mrem 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 l10.Omrem 0.0/E+00 0.00%

Critical Organ N/A N/A N/A N/A 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.

-- r - 1 ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 DOSE TO PUBLIC UNIT 2 (Docket Number 50-304)

ADULT RECEPTOR Maximum Quarteril Dose (mrad, mrem) I Yearly Maximum % of I Qtrly Obj 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Limit Annual Yearly Dose Dose 10CFR50 (mrad, Limit A. Airborne Appendix I mrem)

Gamma Air 5.0 mrad 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 10.0 mrad 0.00E+00 0.00%

Beta Air 10.0 mrad 0.00E+00 0.OOE+00 O.OOE+00 0.00E+00 20.0 mrad 0.OOE+00 0.00%

Total Body 2.5 mrem 0.OOE+00 4.59E-05 0.OOE+00 2.69E-05 5.0 mrem 7.28E-05 0.00%

Skin 7.5 mrem 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 15.0 mrem 0.OOE+00 0.00%

Organ 7.5 mrem 0.OOE+00 5.59E-05 0.OOE+00 3.16E-05 15.0 mrem 8.75E-05 0.00%

Critical Organ _ Gi-LIi Gi-Lli Gi-LiI B. Aquatic Total Body 1.5 mrem [0.OOE+00 l 0.00E+00 l 0.OOE+00 0.OOE+00l 0.OOE+00 0.00%

Internal Organ 5.0 mrem 70.OOE+00 0.00E+00 l 0.00E+00 0.OOE+00 1. rem 0.00E+00 7 om Critical Organ NIA l NIA j NiA NIA l 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 40CFR190 annual limits of 25 mrem DDE whole body, 75 mrem CDE thyroid, and 25 mrem CDE other organs.

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 1 -

Bone Liver Thyroid Kidney Lung GI-Lli Skin TB SITE DOSE LIMIT ANALYSIS-Age Dose Limit Max t of Period - Limit Group Organ (mrem) (mrem) Limit Qtr . - Admin. Any Organ 0.OOE+00 3.75E+00 0.OOE+00 Qtr 1 - Admin. Total Body ADULT TBODY O.OOE+00 1.l3E+0O 0.OOE+00 Qtr 1 - T.Spec Any Organ O.OOE+00 1.50E+00 O.OOE+00 Critical Pathway: Potable Water (PWtr)

Major Contributors ( 0% or greater to total)

Nuclide Percentage Qtr 1 - T.Spec Total Body ADULT TBODY 0.OOE+00 1.50E+00 0.OOE+00 Critical Pathway: Potable Water (PWtr)

Major Contributors ( 0% or greater to total)

Nuclide Percentage

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 O.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 0.OOE+00 1.50E+00 0.00E+00 Critical Pathway: Potable Water (PWtr)

Major Contributors ( 0% or greater to total)

Nuclide Percentage

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 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 0.00E+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 Dose Limit Max t of Period - Limit Group Organ (mrem) (mrem) Limit Qtr 3 - Admin. Any Organ TEEN LIVER 2.60E-02 3.75E+00 6.94E-01 Qtr 3 - Admin. Total Body ADULT TBODY 1.64E-02 1.13E+00 1.46E+00 Qtr 3 - T.Spec Any Organ TEEN LIVER 2.60E-02 5.OOE+00 5.20E-01 Critical Pathway: Fresh Water Fish - Sport (FFSP)

Major Contributors ( 0t 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 Qtr 3 - T.Spec Total Body ADULT TBODY 1.64E-02 1.50E+00 1.10E+00 Critical Pathway: Fresh Water Fish - Sport (FFSP)

Major Contributors ( 0t 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

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 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 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 Age Dose Limit Max t of Period - Limit Group Organ (mrem) (mrem) Limit Qtr 4 - Admin. Any Organ TEEN LIVER 1.33E-02 3.75E+00 3.55E-01 Qtr 4 - Admin. Total Body ADULT TBODY 8.41E-03 1.13E+00 7.48E-01 Qtr 4 - T.Spec Any Organ TEEN LIVER 1.33E-02 5.OOE+00 2.67E-01 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.Spec Total Body ADULT TBODY 8.41E-03 l.50E+00 5.S1E-01.

Critical Pathway: Fresh Water Fish - Sport (FFSP)

Major Contributors ( 0t 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

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 O.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 0.00E+00 5.31E-03 INFANT 3.92E-05 4.67E-05 1.80E-07 1.25E-05 5.19E-06 1.21E-06 O.OOE+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 4.89E-04 CO-60 2.19E-02 CS-134 1.29E+00 CS-137 9.87E+01 2003 - T.Spec Total Body ADULT TBODY 2.49E-02 3.OOE+00 8.28E-01 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

71: -

.r -3 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 t of Period-Limit Group Organ (mrem) (mrem) Limit Q1 - Admin. Any Organ 0.OOE+00 5.63E+00 O.OOE+00 Q1 - Admin. Total Body 0.OOE+00 5.25E+00 0.OOE+00 Q1 - T.Spec Any Organ 0.OOE+00 7.50E+00 O.OOE+00 Receptor: 0 Distance: O.OOE+00 (meters) Compass Point:

Critical Pathway:

Major Contributors ( 0% or greater to total)

Nuclide Percentage Q1 - T.Spec Total Body 0.OOE+00 7.50E+00 O.OOE+00 Receptor: 0 Distance: 0.OOE+00 (meters) Compas s Point:

Critical Pathway:

Major Contributors ( 0% or greater to total)

Nuclide Percentage

I 3 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 ==-QUARTER 1 -

Dose Limit % of Period-Limit (mrad) (mrad) Limit Q1 - Admin. Gamma O.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.OOE+00 0.OOE+00 Receptor: 0 Major Contributors ( 0t or greater to total)

Nuclide Percentage Q1 - T.Spec Beta O.OOE+00 1.OOE+01 0.OOE+00 Receptor: 0 Major Contributors ( 0% or greater to total)

Nuclide Percentage

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 2 Age Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q2 - Admin. Any Organ ADULT GILLI 1.08E-104 5.63E+00 1.92E-03 Q2 - Admin. Total Body CHILD 9.50E-105 5.25E+00 1.81E-03 Q2 - T.Spec Any Organ ADULT GILLI 1.08E-104 7.50E+00 1.44E-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 Q2 - T.Spec Total Body CHILD 9.50E-105 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 ( 0t or greater to total)

Nuclide Percentage CO-60 1.00E+02

RETDAS v3.6.3 VZIO> VSSI 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 0.OOE+00 3.75E+00 0.OOE+00 Q2 - Admin. Beta O.OOE+00 7.50E+00 0.OOE+00 Q2 - T.Spec Gamma 0.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 0.00E,-00 1.OOE+01 0.OOE+00 Receptor: 5 Composite Crit. Receptor - IP Major Contributors ( 0% or greater to total)

Nuclide Percentage

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 Age Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q3 - Admin. Any Organ ADULT GILLI l.llE-104 5.63E+00 1.98E-03 Q3 - Admin. Total Body CHILD 9.82E-1 25 5.25E+00 1.87E-03 Q3 - T.Spec Any Organ ADULT GILLI l.llE-1 24 7.50E+00 1.49E-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 Q3 - T.Spec Total Body CHILD 9.82E-()5 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 ( 0% or greater to total)

Nuclide Percentage CO-60 1.OOE+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 ==-QUARTER 3 -

Dose Limit % of Period-Limit (mrad) (mrad) Limit Q3 - Admin. Gamma 0.OOE+00 3.75E+00 0.OOE+00 Q3 - Admin. Beta 0.OOE+00 7.50E+00 0.OOE+00 Q3 - T.Spec Gamma 0.OOE+00 5.OOE+00 0.OOE+00 Receptor: 5 Composite Crit. Receptor - IP Major Contributors ( 0% or greater to total)

Nuclide Percentage Q3 - T.Spec Beta O.OOE+00 1.OOE+01 0.OOE+00 Receptor: 5 Composite Crit. Receptor - IP Major Contributors ( 0% or greater to total)

Nuclide Percentage

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 t of Period-Limit Group Organ (mrem) (mrem) Limit Q4 - Admin. Any Organ ADULT GILLI 6.32E-()5 5.63E+00 1.12E-03 Q4 - Admin. Total Body CHILD 5.57E-()5 5.25E+00 1.06E-03 Q4 - T.Spec Any Organ ADULT GILLI 6.32E-()5 7.50E+00 8.43E-04 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 CO-60 1.00E+02 Q4 - T.Spec Total Body CHILD 5.57E-()5 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 .ZIO> 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 0.OOE+00 3.75E+00 O.OOE+00 Q4 - Admin. Beta O.OOE+00 7.50E+00 0.00E+00 Q4 - T.Spec Gamma 0.OOE+00 5.00E+00 0.OOE+00 Receptor: 5 Composite Crit. Receptor - IP Major Contributors ( 0% or greater to total)

Nuclide Percentage Q4 - T.Spec Beta 0.OOE+00 l.OOE+01 0.OOE+00 Receptor: 5 Composite Crit. Receptor - IP Major Contributors ( 0% or greater to total)

Nuclide Percentage

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+C 1 2.51E-03 2003 - Admin. Total Body CHILD 2.49E-04 1.05E+C)1 2.37E-03 2003 - T.Spec Any Organ ADULT GILLI 2.82E-04 1.50E+C11 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 ( 0% or greater to total)

Nuclide Percentage C-________

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.OOE+02

.4 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 =- ANNUAL 2003 =========

Dose Limit % of Period-Limit (mrad) (mrad) Limit 203-_____dmin.__________Ga_____ma_____0.___________________ _______

2003 - Admin. Gamma 0.00E+00 7.50E+0 0 0.OOE+00 2003 - Admin. Beta 0.00E+00 1. 50E+0 21 0.OOE+00 2003 - T.Spec Gamma 0.00E+00 1. OOE+0 1 0.OOE+00 Receptor: 5 Composite Crit. Receptor - IP Major Contributors ( 0% or greater to total)

Nuclide Percentage 2003 - T.Spec Beta 0.OOE+00 2.OOE+01 0.OOE+00 Receptor: 5 Composite Crit. Receptor - IP Major Contributors ( 0t or greater to total)

Nuclide Percentage

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 4th (Qtr 2003

a. Total Number of Batch 0 0 0 0 0

Releases

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

_+00 0.00E+00

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

d. Average Time Period for a 0.OOE+0o 0.00E+00 0.OOE+00 0.OOE +00 Batch Release (minutes) O.OOE+00

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

6. Abnormal Releases

a. Number of Releases 0 0 0 0 0

b. Total Activity Released (Ci) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE +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 4th Qtr 2003

a. Total Number of Batch 0 0 0 0 0 Releases

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

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

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

6. Abnormal Releases

a. Number of Releases 0 0 0 0 0

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

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 UNIT I & 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 I. The off-site dose limits per reactor unit are listed below.

Quarterly Yearly (mrem) (mrem)

Gamma Air 5 10 Beta Air 10 20 Total Body 2.5 5 Skin 7.5 15 Organ 7.5 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 500 mrem/year Total Body Noble Gases 3000 mremlyear Skin 1-131, 1-133, H-3, and particulates with half-lives greater than 8 days 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 Percent of Effluent Kr-85 100 Average Gamma Energy per Decay of the Mixture (keV) 5.0 Average Beta Energy per Decay of the Mixture (keV) 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 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr 2003

a. Total Number of Batch 0 0 0 0 0 Releases

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

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

6. Abnormal Releases

a. Number of Releases 0 0 0 0 0

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

ZION NUCLEAR POWER STATION A!NtI.RADl C.WT-:VI EFL;E-NT r ~ 2-W-3 FCA;FCR7~iT

-. GASEOUS EFFLUENTS - ALL RELEASES ARE AT GROUND LEVEL UNIT 1 (Docket Number 50-295)

SUMMATION OF ALL RELEASES Units Jan Feb Mar I1st Qtr Apr May Jun 2nd Qtr Jul Aug Sep 3rd Qtr Oct Nov Dec 4th Qtr Total A. FIssIon and Activation Gases II. Total Release Activty Ci 'LID <LLD <LLD <LLD <LID <LID <LID <LID <LID <LLD -<ILD <LLD <LLD <LID <LLD <LLD 0.00E+00 12Average Release Rate uCi/sec <LLD <LLD <LLD <LLD <LID 'LID <LID <LLD <LID <LID <LID <LLD <LLD <LLD <LLD <LLD 0.00E+00 S. Iodine 1I.Total 1-1131ActiMit Ci <LID <LID <LLD 'cLID <LID <LLD <LID (LLD <LLD <LLD <LLD -'LD <LLD <LID <LID 'LLD 0.00E+00 12Avers e Release Rate I uCiisec I LID I<LDID <LID I LLD I'LDID <LDID <LLD I'<LD I <LLD I LLD ILLDID <LLD I <LLD I LDID <LID I LLD I0.0012+00 C.Partlculates (half-lives 8 days)

II. Total Release Activtyt Ci I <LLD I <LID I <LLD I <LLD I <LLD I 1.53E-061I <LLD I <LID I <LLD I <LLD t<LID I<LID I <LLD I5.95E-07 <LID I5.95E-07 I2.12E.06 12Aversge Release Rate uCilsec; <LLD I LID I<LID I'LID I<LID 5 71E-07 I<LID I <LID I<LID I<LID I<LID I<LLD I<LID I2.30E-07 <LID 7A8E.08 6.72E.09 13.Gross Alpha Actrvety I Ci I ' LLD I<LLD I <I-LLD I<LID <LLD D.Tritium 11Total Release Actiity Ci <LLD I LLD I<LLD I<LID 'LLD <LLD <LLD <LID <LLD <LID <LLD <LLD <LLD <LLD I<LID <LLD 0.00E+04 12.Aversge Release Rate I u~ilsec ID <LD ID <LLDID <LDII 'LIDD'LID <LLD <LLD 'LID <LLD <LLD <LLD <LLD <LLD <LLD <L I LD 0.00E+00 E. Sum of Iodine, Particulate (halt-lives > 8 days),

and Tritium Releases.

11.Total Release ACItivt Ci 0 .002*00 I0 002.00 I O.OE.00 I0.002+00 0 002.00 1.53E-06 0002.+00 1.5312-06 0.002+00 0 002.00 0 OOE+00 0.0012+00 0.002+00 5 952-07 0.002+00 5.95E-07 2120 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 ths page and Sr-89 and Sr-SO on the Batch and Continuous Mode data sheets are blank because monthly values are not applicable.

Lower limitof detection (LID) values are presented inthe Gaseous EffluentsLLIDValues 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. Ifthe 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 Rer 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 Feb I Mar 1st Qtr Apr May Jun 2nd Qtr I Jul I Aug Sep 3rd Qtr Oct I Nov I Dec 4th Qtr Total A. Fission and Activation Gases Ar-41 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Kr-85 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Kr-45m Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Kr487 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Kr88 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret <LLD Xe-131 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rei No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Xe-131m Ci 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 Rel No Re; No Rel <LLD Xe-133 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Xe-133m Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Xe-135 Ci No Rel No Rel No Rel No Not Noe o Rel No Re; No Ret No Re; No Re; No Rel No Ret NNoRel No Re No Re No Ret <LLD Xe-135m Ci 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 No Re; No Ret <LLD Xe-138 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD B. lodines Br-82 Ci No Rel No Re; No Rel No Ret NoRel NoRel No Rel No Rel No Rel No Re; I No Rel No Rel No Rel I No Rel j No Rel No Rel I LLD 1-131 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel l No Rel l No Rel No Rel No Rel No Rel No Rel No Rel No Ret l LLD 1-132 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 Rel No Rel No Rel No Re! No Rel l LLD 1-133 Ci No Rel No Rel NNo Re; No Ret NoRel NoRel No Rel No Rel I No Rel I No Rel I No Rel No Rel No Rel I No Rel I No Rel I No Rel I <LLD 1-134 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel l No Rel l No Rel l No Rel No Rel No Rel l No Rel l No Rel l No Rel l LLDD 1-135 Ci No Rel No Rel 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 Rel <LLD C. Particulates Na-24 Ci No Rel No Rel No Rel No Rel No Rel I No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel Cr Cil No Rel No Rel No Rel No Rel No Rel No Rel No Rel No ReI No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel Mn-54l Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel; No Rel No Rel Co-57 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel Co-58l Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel Co-60l Ci No Rel No Re; No Rel No Rel 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-65l Cl No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rell No Rel No Rel Se-75l Ci No Rel No Rel No Rel; No Rel No Rel No Rel No Rel I No Rel No Rel; No Rel No Rel No Rel No Rel No Rel I No Re; No Relt No Rel Rb-88 Ci No Rel No Rel No Rel No Ret No Re; No Rel No Rel No Ret No Re; No Re; No Re; No Ret No Rel No Rel No Re; No Ret No Ret sr.89, C No Ret No Ret No Rel No Rel No Rel Sr-90' Ci ____ No Ret No Ret Retol__ No Ret

___No No Rel Zr Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel Nb.95_ Ci No Rel No ReI No Rel No Ret No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Re No Rel No Rel No Rel No Rel No Ret Mo-99 Ci No Rel No Re; No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel Tc-99m Ci No Rel No Rel No Rel No Ret No Re No Rel No Rel No Ret No Rel No Rel No Rel No Ret No Re No Rel No Rel No Rel No Ret Ru-13 C No Rel;I No Rel No Re; No Ret No Re; No Re; No Re No Ret No Re; No Re; No Rel No Ret No Re_ No Rel No Re; No Ret No Ret Aq-110m' Ci No Rel No Rel No Re; No Ret No Rel No Re; No Rel No Ret No Re; No Rel No Rel No Ret No Rel No Re; No Rel No Ret No Ret Cs-134 Ci 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 Rel No Rel No Rel No Rel Cs-136- Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel; No Rel NoRel Cs-137 CI No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel Cs-138 Cl No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel; No Rel No Rel No Rel No Rel No Rel No Rel BaI4N i el N e oR N e oR; N R; N e oRe oR; N e NhoRe No Ret- No Rel INo Rel No Re; INo Ret No Ret La-10 Cl No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel -No Rel NoRel NoIRet NoRel NoRel NoRel NoRet NoRet Pr-144 Ci No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel I No Rel Ce.144 Ci No0Re; No Rel No Ret No Ret No Rel No Rel No Ret No Ret No Re; No Re; No Rel No Re;' No Ret No Rel No Rel No Re;- No Re No Ret W-187 Cl No Rel No Rel No Rel No Rel lNoRe; No Rel No Re; No Ret No Re; No Rel No Re; No Ret No Rel No Rel No Rel No Ret No Rel D. Tritium 1 Total Release ACtMtY Ci No Rel No Rel I No Rel I No Rel I No Rel No Rel No Rel No Rel No Rel I No Rel No Rel I No Rel I No Rel No Re; I No Rel No Rell No Re

Particulate isotope with halt-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 Units Jan Feb Mar lst Qtr Apr May I Jun I 2nd Qtr I Jul Aug Sep I 3rd Qtr Oct Nov Dec 4th Qtr Total A. Fission and Activation Gases Ar-41 Ci <LLD <LLD <LLD 'LLD <LID <LLD <LID cLLD <LLD <LLD <LLD cLLD <LLD <LLD <LLD <LLD <LLD Kr-85 Ci <LLD <LLD <LLD <LLD <LID <LLD <LID 'LD LLLD <LLD

<LD <LLD 'LLD <LLD <LLD 'LLD cLLD Kr-85m Ci <LLD <LLD <LLD <LLD <LID <LLD <LLD cLLD <LLD <LLD 'LID 'LLD <LLD <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LID -<LLD 'LID 'LID LLD <LID 'LID LDLD 'LID

<LD <LLD <LLD <LID 'LID <LLD <LLD Kr-43 Ci <LLD 'LLD <LLD cLLD LLD <LLD -<hLD LLD <LLD <LLD <LD <LLD <LLD <LLD <LLD cLLD <LLD Xe-131 Ci <LLD l<LD <LID cLLD <LLD <LID <LLD cLLD <LLD <LID <LLD <LLD <LLD <LLD <LLD 'LLD <LLD Xe-131m Ci <LLD <LLD <LLD <LLD <LLD <LID <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LID 'LID <LLD <LLD Xe-133 Ci <LLD 'LID <LLD 'LLD I<LD <LLD <LLD cLLD <LLD <LLD <LLD I LLD <LID <LiD <LiD <LtD <LID Xe-133m CI <LLD I<LD I<LD <LLD I<LD <LLD <LLD <LLD <LLD <LLD <LLD I <LLD <LID <LLD ILID <LLD <LLD Xe-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD ILID I LLD <LLD <LLD <LID <LLD ILLD ILID ILLD <LLD <LLD Xe-135m Ci 'LID dLLD 'LLD 'LID <LLD <LLD ILID I LLD ILID ILID ILLD cLLD ILID ILID ILLD cLLD <LLD Xe-138 Ci <LLD <LLD _ LID <LLD ILLD ILLD <LLD cLLD ILID ILID ILLD cLLD 'LLD I<LD ILLD 'LLD <LLD B. lodines Br-82 Ci 'LLD [ <LID <LLD l LLD l<LD l<LD <LLD l LLD l<LD <LLD l <LLD l LLD l <LLD <LLD lLLD l LLD 'LLD 1-131 Ci <LID j <LLD <LLD cLLD <LLD <LLD <LLD l'LLD <LLD l 'LLD 'LLD

< <cLLD J 'LLD <LLD l 'LID <LLD cLLD

-132 Ci 1 LLD lLLD lLID l LLD lLLD <LLD <LLD 'LLD <LLD <

'LLD <

'LLD l 'LLD l <LLD l <LLD <LID <

'LLD <LLD 1-133 Ci <LID l <LID <LLD cLLD <LLD 'LLD '<LD lLLD l<LD j <LLD <LLD <LLD <LLD '<LD <LLD l LLD <LLD 1-134 Ci <LLD I <LLD <LLD <LLD <LLD <LLD <LID cLLD <LLD I <LID I <LLD <cLLD l 'LID <

'LLD LID <LLD I cLLD 1-135 Ci <LLD <LLD lLLD l LLD <LLD lLID <LLD lLLD <LLD <LLD lLID lLLD <LLD lLLD lLID l LLD <LLD C. Particulates Na-24 Ci <LLD l<LD '<LD <LLD <LLD l<LD <LLD l LLD <LLD lLID <LLD l LLD lLLD lLID l<LD l LLD l LLD CrS1- Ci lLLD l<LD <LLD <LLD <LID <LID <LLD 'LLD l<LD l<LD <LLD sLLD <LID l<LD <LLD l LLD <LLD Mn-54 Ci LID <LLD LLD <LLD lLLD LID l<LLD 'LD l LD <LLD '<LD lLLD l<LD <LLD <LLD cLLD <LLD Co-57 Ci <LLD <LID <LID l LLD l<LD <LLD <LLD cLLD <LLD <LLD <LLD 'LLD <LLD <LLD l<LD 'LLD <LLD Co-58 Ci <LLD <LID <LLD <LLD <LLD <LLD <LID <LLD <LLD <LLD <LLD <LLD 'LD <LLD <LLD LLD <LD

",.M. Ci <LLD <LLD 'LLD <LLD 'LID 9 30E-07 'LID 9.30E-07 <LLD <LLD 'LD cLID 'LD 5.95E-07 <LLD 5.95E.07 l.53E.0i6 Zn Ci <LLD <LLD <LLD cLLD <LID <LLD <LLD cLLD <LLD <LID <LID <LLD <LLD <LD 'LD cLLD l LLD Se-75 Ci 'LD <LID lLI <LLD lLLD ILD lLD <LLD l LD <LID l LD <LLD LD <LD I cLLD LLD 'LD Rb-8l Ci <LLD <LLD '<LD l LLD <LLD l<LD <LLD <LLD <LLD <LLD l<LD IcLLD <LD <LLD '<LD 'LLD 'LID sr-895 Ci <LLD <cLLD _ <LLD - <cLLD l LLD Sr-90' C i L <LLD L <LLD LD <LLD Zr-95l C <LID lLID <LUD <LLD <LLD 'LID 'LID <LID <LLD <ULD <LLD <LLD <LLD l<LD <LLD <LLD <LLD Nb-95 Ci <LLD <LID <LID l LLD <LLD <LID <LLD <LLD <LLD <LID <LLD <LLD <LLD <LLD <LLD LLD l cLLD Mo-99 Ci l<LD <LLD <LLD <LLD <LLD <LLD l<LD lLLD <LID <LLD <LLD l LLD l<LD <LID l<LD l LLD <LLD Tc-99m Ci <LID <LID <LLD l LLD lLID 'LID <LLD l LLD lLD lLLD <LD <LLD 'LD 'LD LD 'LID LLD Ru-1036 Ci lLID lLID 'LID <LLD LID <LLD <LLD <LLD <LLD l<LD l<LD 'LLD <LLD <LLD <LLD LLD I LLD AI-110m3 C <LLD I<LD I<LD <LLD <LLD <LLD <LID I LID <LLD <LLD '<LD <LLD l<LD l<LD <LLD l LLD l LLD Cs-134 Cj <LLD l<LD ILLD <LLD <LD LID <LLD <LLD <LD <LD 'LD <LLD <LD <LLD <LD I LLD <LLD Cs-1368 CiI <LLD I<LD <LLD I LID I<LD I<LD <LLD I LLD <LLD I<LD I<LD CLLD I<LD I<LD <LLD I LLD cLLD Cs-137 Cj <LLD <LLD I<LD I LID <LLD l<LD I<LD CLLD l<LD '<LD I<LD <LLD l<LD <LLD l<LD l LLD <LLD Cs-13I Ci <LLD I<LD l<LD I LID I<LD <LLD I<LD l LLD 'LID ILID ILID <LLD LD LD <LLD LLD LLD Ba-1404 Ci LID I'LD I'LD 'LID l<LD I<LD I<LLD I D LD LD <LD I LLD I <LD <LLD I<LLD CLLD l cLLD La-W18 Ci <LLD I<LD <LLD <LLD I<LD <LLD <LLD I LLD <LLD <LLD I <LD I LLD I <LLD '<LD I<D I I ILD D Ce-l44 Ci 'LLD 'LLD <LID <LID 'LD <LD 'LD <LLD <LI <LLD 'LIWD <LLD <LD <LD <LI LDLD Pr-144 Ci 'LLD LID 'LLD <LLD <LD 'LD <LD <LD <LI <LD <LLD <LLD 'LD 'I LI LD 'I W.18? Ci <LLD 'LLD <LLD <LD 'LID <LLD 'LD <LD 'LI <LIn 'ID 'LD 'LD LD 'ID 'ID 'I D. Tritium 11TotalRelease ACtMt l Ci <LLD <LD <LD l LLD <LLD l<LD l<LLD I <LLD I <LLD I <LD I <LLD <LLD LD I <LD I <LLD I <LLD I cLLD

Particulate isotope vith 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 5O-3O4)

SUMMATION OF ALL RELEASES Units Jan Feb Mat 1st Qtr Apr May Jun 2nd Qtr Jul Aug Sep 3rd Qtr Oct Nov Dec 4th Qtr I Total A. FissIon and Activation Gases 1l.Total Release AcItivt Ci <IL LD 'LID

<LID <LLD <LLD LLD

<LD <LLD <LID <LLD <LLD -LLD <LID 'LLD <LLD <LLD I 0.00E400 12.Average Release Rate uCi/sec <LLD <LLD <LID 'LLD <LLD I LLD 'I LD I 'LLD I'LLD I LLD I <LD I 'LLD I'LLD I LLD I LLD I -LLD IO.OOE+0 S. Iodine

11. rotal 1-131 Activty Ci <LID <LID 'LID <LLD <LID I'LLD I'LLD I LLD cLLD 'LID <LLD <LLD I LID I'LLD I LLD I LLD I .OOE+00 12.Average Release Rate uCi/sec 'cLID I LLD I'LLD I'LLD I'LID 'I LD I'LLD I 'LID <LID <LLD 'LD -LLD I'LD I LD I LID I'LID ID.OOE+00 C. Particulates (half-IlIves > 8 days)

Ii. Total Release Actmtyt ICi <LID I <LID <LLD I <LLD t LID I 1 53E.06 <LID I 1.53E.06 <LLD <LLD <LLD cLLD I <LLD 59E0 'LI 5.95E1-07 I2.13E-06

12. Average Release Rate IuCi/s I 'LID I'LLD <LLD I'LLD <LID 15.7 1E-07 'LID I1.95E.08 I'LD I ID 'LD <LLD I LID 2.310E :LID 7.49E-09 6.75.0 13 Gross Alpha Activty I Cl 'I LD I II <LD I ' LLD I 'LLD 'LD D. Trltlum II. Total Release Activty Ci I 'LLD I LID I'LID I LID I'LLD I LID ' LID I'LLD I LID I LID I'LID <LLD ' LID I'LID <LID I LLD O.OOE0Oo 12Average Release Rate I uCi/sec I'LD I LLD I LID I LLD I LLD I LID I'LID I'LID I'LID I 'LD L ' LID I'LLD I'LID I LID I LID I LLD I .OOEO00 E. Sum of Iodine, Particulate (half-Ilves > 8 days),

and Trltlum Releases.

1l.Total Release Activity CiI 0 00E+0 .OO00E+00I 0 00E.00I O.OtlE+OO0I00OE+00O I 53E-06I 0 OOE+00I 1.53E.06I 0 00EsOD O.0OE+001 O.OOE+00 IO.OOE+00 0 OOE+00 I5.S9E-07I 0 00E400 5.95E.07 2.13E.06 Grass Alpha. St-89. and Sr-GO Activities are quantilied 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-GO on the Batch and Continuous Mode data sheets are blank because monthly values are not applicable.

Lower limit of detection (LID) 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 duning the applicable period was less than the LLD value for that nuclide. If the abbreviation '<LLD' is fisted for a group of radionuclides, the actrvity concentration of each radionuclide for each sample during the period was less than the LID value for the respective radionuclide.

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

The abbreviation 'No Rer 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 I Feb Mar 1st Qtr Apr May Jun 2nd Qtr Jul Aug Sep 3rd Qtr I Oct Nov I Dec 4th Qtr Total A. Fission and Activation Gases Ar.41 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Kr485 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Kr-85m Ci No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel -LLD Kr-87 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel <LLD Kr-88 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Xe-131 Ci No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel -LLD Xe-131m Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Xe-133 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret <LLD Xe-133m Ci No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rat sLLD Xe-135 Ci No Rel No Rel No Rel No Re No Ret No Ret NocLLD No Ret No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret Xe-135m Ci No Ret No Rel No Rel 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 zLLD Xe-138 Ci No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret No Ret N&Ret No Ret No Ret No Ret No Ret No Ret No Ret sLLD B. lodines Br-82 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel j No Rel No Rel No Rel No Rel No Ret -No Rel No Rel 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 No Rel No Rel No Rel No Rel No Rel No Rel No Rel l LLD 1-132 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret No RelT No Rel No Rel No Rel l LLD

-133 Ci No Rel No Rel No Ret No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel I LLD 1-134 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel l LLD 1-135 Ci No Rel No Rel No Rel No Rel No Rel No Rel -No Rel l No Rel No Rel No Rel No RelT No Rel No Rel No Rel No Rel -No Rel l LLD C. Particulates Na-24 Cl No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel l LLD CrS1-l Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel I LLD Mn-547 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel l LLD Co-57 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Co4-5 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel C No Ret I LLD Net Zn-75 No R N RLLD Ci No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel l LLD Rb-45' Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel I LLD Rb Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel l LLD Sr-89, Se5 _i Ci I No Rel NoRe

- No Re No- RelINoRl No Rel I No- Rel lNo- Rel I No Rel Rel lNo Rel lNo Rel lNo Rel NoR No Rel I No Rel lNoRe No Rel l NoRlI LLD

<LLDI Sr-909 Ci No Rel No Rel _ No Rel _ No Rel N LLD Zr-95' C No Ret No Ret No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel I LLD Nb-95' Ci No Relt No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel l LLD Mo-99 CiI No Relt No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel l LLD Tc-99m Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Relt No Rel -LLD Ru-103 _ C No Ret No Rel No Ret No Rel No Ret No Rel No Ret No Rel No Ret No Relt No Rel No Rel No Rel I No Rel No Rel No Ret <LLD A-110m1 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel l cLLD Cs-1344 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel l LLD Cs-1368 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel -LLD Cs-1371 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 Ret <LLD Cs-138 Ci INo 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 Ret <LLD Ba-140 Ci No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel

Ci No Rel No Rel No Rel No Rel l LLD No Ret No Ret No Ret No Ret N R o Ret No Re No Ret No Ret Ce-144' Ci No Ret No Ret No Ret No Rot No Ret No Ret No Ret No Ret No Ret No Ret No Ret Pr14Ci No Ret No Ret1 No Ret INo Ret INo Retl N Ret <LLD No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Re No Ret No Re NooRet No Ret No Ret No Retl LL W.187 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 Ret :LLD D. Tritium 11 Total Release Actpvty Ci INo Ret No Ret No Ret INo Ret No Ret INo Ret INo Ret No Ret No Ret No Ret No Ret INo Ret No Ret No Ret No Ret No Ret ~-LLD~

Particulate isotope v~th 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 504304)

CONTINUOUS MODE Units I Jan I Feb I Mar I IstQtr I Apr I May I Jun I 2nd Qtr I Jul I Aug I Sep I 3rd Qtr I Oct I Nov I Dec I 4th Qtr I Total l A. Fission and Activation Gases I Ci <LLD <LD I <LLD I<LD <LD I<LD <LLD <LIDI <LDI <L I LD ILLD <LLD I<LID <LLD I<DLLD I <LLDD Kr-a5 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLDI <LLLD I<LLD <LLID I<LD <LLD <LLD I<LLD <LLD Kr-85m ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 41-13 <LLDt <LLD <LLD <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LID <LLD <LLD <LLD <LLD <LLD <LID <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LID <LLD <LLD <LID <LID <LLD <LLD <LLD <LLD <LLD <LLD Xe-13 1 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LID <LLDD <LLD <LID - <LID <LID <LLD <LLD Xe-131m Ci <LLD <LLD <LID <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD <LLD <LLD <LID <LID <LLD <LLD <LLD <LLD <LL<D <LLD <LID <LLD <LLD LLD Xe-133m Ci <LID <LLD <LLD <LLD <LLD <LID <LID <LLD <LLD <LLD <LLD <LLD <LID <LLD <LLD <LLD <LLD Xe-1 3m Ci <LID <LLD <LID =LLD <LLD <LLD <LID <LLD <LLD <LLD <LLD <LLD <LLD <LID <LID <LLD <LLD Xe-135m Ci LLD I <LD <LID <LLD <LLD <LID <LID <LLD <LID <LLD <LID <LLD <LID <LLD <LID <LLD <LLD Xe-133 Ci <LLD <LLD <LLD <LID <LID LLD LLD dLLD :LLID <LLD <LID <LLD <LLD <LLD <LLD <LLD <LID B. lodines Br-82 Ci <LLD <LID <LID <LLD <LID <LLD <LLD <LLD <LID <LLD <LLD I LLD <LLD <LLD <LLD <LLD <LLD 1-131 Ci <LLD <LLD <LLD <LLD <LID <LID <LLD <LLD <LID <LLD <LLD <LID <LLD <LLD <LLD <LLD <LLD 1-132 Ci <LID <LLD <LLD <LID <LLD <LD <LLD <LLD <LLD <LLD <LLD LLD <LLD <LLD <LLD <LID <LLD 1-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LID <LLD LID <LID <LLD <LLD <LLD <LID 1-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LID <LID <LLD <LLD <LLD 1.135 Ci <LD <L LLD <LLD <LLD <LLD lLL <LLD <LD <L_ LD <L LD <L L LD cL C. Partlculates Na-24 Na-514 CiC 'LLD

<LLD <LLD

<LID <LLD

<LLD <LLD

<LLD <LID

<LLD <LLD

<LID <LLD

<LLD

<LID

<LLD

<LID

<LLD

<LID

<ILD

<LLD

<LID

<LLD Mn-54 Ci l LD <LLD <LD <LLD <LLD <LD <LID <LLD <LID <LD <LLD <LID <LLD <LD <LLD <LID <LD Co-57 Cl <LLD <LLD <LLD LLD <LLD <LD <LLD l LLD <LLD <LLD <LDD LLD <LLD <LLD <LLD I <LLD LLD

______ ____LLD <LLDI<LLD LDLLLDD <LID <LLD Co-<LD LLDLD _LLD_ LL _______6 <LD 15E0 LD LD <L LD <LD 59E0 L .9E-06 2.72E Zn-65' i <L <LLD_ __LD_ __LLD_ _LDDLD <LD <LD__D <LDL_<L <D <L <LID <LLD Se-75< LD < L <LLD <LD <LLD I LLD I LLDDLLD Rb-88 Ci <LID <LLD <LLD <LID <LLD <LLD <LID <LID <LUD <LLD <LID <LLD <LID <LLD <LID <LLD <LLD Sr-89I Ci;LLDI__LD <LLD <LLD <LLD Sr-90, Ci <LLD <LLD <LLD <LLD <LLD Zr-950 Ci <LLD <LD <LID l<LLD 'LID 'LD <LLD <LLD lLD 'LD <LID I LLD <LD <LLD <LLD <LLD <cLLD Nb.95 Ci <LID <LLD <LLD <LLD <LLD <LLD LID <LLD <LID <LD <LLD <LLD <LLD <LID <LLD <LLD <LID Mo-99 Ci <LD <LLD 'LD <LLD <LD <LLD <LLD <LLD <LLD <LID LID <LLD <LD <LD <LLD <LLD <LID Tc-99m Ci <LLD <LLD <LLD <LLD <LID <LLD <LLD I LLD <LLD <LD <LD <LLD <LID <LLD <LLD <LLD <LID Ru-103- Ci lLLD <LLD <LLD <LLD <L LD I <LLD I LLD <LLD <LID <LLD I<LLD <LLD <LLD <LLD <LLD <LLD Ag-110m Ci 'LD <LLD <LLD <LLD <LD <LLD <LD l LLLID <L D DLLL LID D <L ID <LD <LID <LD Cs-134- Ci <LLD <LLD <LLD I LID <LLD <LLD I LD <LLD <LLD <LID <LD <LLD LID <LLD <LLD <LLD <LD Cs-136 CI <LLD <LID <LLD <LLD <LLD <LLD <LLD <LLD <LD <LLD 'LID I LLD <LLD <LLD '<LD <LLD <LLD Cs.137I Ci <LLD <LID <LLD <LLD <LID <LLD <LLD <LLD <LLD <LLD <LLD <LLD LD <LID <LLD <LLD <LLD Cs-138 Ci LD <LID <LLD <LLD <LID <LD <LLD <LID <LLD <LD <LD l LLD <LLD <LLD I<LD <LLD I LLD Ba-140- Ci <LID <LID <LLD I LLD <LD <LLD <LLD <LLD <LLD <LLD <LLD <LID <LID LI <LLD <LLD LLD La-140 CI 'LID I LID <LLD <LLD <LD < LD I <LID ZLLD 'LD <LLD <LID I LID LI LD I <LLD I <LLD I <LLD Ce-144 Ci <LLD <LLD I<LID LD ILLD < LD LLD LD <LLD ILLD <LD <LLD <LLD <LLD I <LLD I LLD <LLD

<LLID L <LID I<LD <LLD <LD I <LLD I <LLD I <LLD I <LD W-187 C;I <LLD I<LD <LID <LLD <LLD <LLD <LLD LD <LID I <LLD I <LLD <LLD <LD <LD <LLD <LLD <LLD D. Tritium 1 Total Release Activity Ci <LID <LLD <LID <LLD <LLD <LLD <LLD <LLD <LD <LID I <LLD LLD <LD <LID <LLD <LLD I LID

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 Ist Otr Apr May Jun 2nd Otr Jut Aug Sep 3rd Otr Oct Nov Dec 4th Qtr Total A. Fission arnd Activation Gases

1. Total Release Activty Ci 'ILD <LID <LLD <LLD <LID <LLD <LID cl-LD <ILD <LID <LLD <LLD <LLD <LID <LLD <LLD O.OOE+00 12.Average Release Rate uCilsec <LLD <LID <LID3 <LLD <LID <LID <LID rLLD <LLD <LLD <LID <LLD <LLD <LLD <cLLD <LLD O.OOE2+00 B. Iodine 11Total 1.131 Activty C <LID <LLD <LID <LID <LID <LLD <LID <LLD <LID <LID <LID <LLD <LLD <LID <LLD <LLD O.OOEO00 12Average Release Rate uCi/sec <LID <LLD <LID <LID <LID <LID <LID <LLD <LID <clLDID <D <LLDI <LDID <L LDD<LID< ID <LLD I O.OOE400 C. Particulates (half-life > 8 days) 1i Total Release Activityl Ci I<LID I<LLD I<LLD I <cLLD I <LLD 12.02E-061 <LID I 2.02E.06 I <LID I<LID I <LID I<LLD I<LID I1.1I9E.06 I<LID I 1.19E-06 1 3.21 E-06 2 veae Release Rate uCi/sec I<LLD I<LID I<LLD I<LID I<LLD 7.54E.071 <LID I2.57E-08 I<LID <ILD I<LIDL<LID 4 59E.07 I<LID I 1.50E208 11.02E0 13.Gross Alpha Actrvty I CiI I <LLD <LID <LLD <LID <LLD

0. Trltium 11Total Release Actmty Ci I<LID <LLD <LLD <LLD <LLD <LID <LLD <LLD <LID <LID <LLD <LLD <LLD <LID <LLD <cLID O.OE+00 12.Average Release Rate IuCi/sec I<LID <LID -KLID <LLD <LID <LLD <LLD <cLLD <LID <LLD <LID <LLD <LID <LLD <LID <LLD O.OOE2+00 E. Sum of Iodine, Particulate (halt-l~ves > 8 days),

and Tritium Releases.

11Total Release Activity Cl I OOOE+00 I 00OE+00 OOOE.=00 O.OOE2+00 IOOOE+00 1202E-061 000E+00 I2.02E-06 IOOO0E*00 I OOE.200 IO.00E+00O O.OOE+00IO OOOE+00 I1. 19E-06 I0OOE+00 I1.19E.06 I3.21E-06 I 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-08 and Sr-SO. The cells for monthly activity values of Gross Alpha on ths 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 LID 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 Rer indicates that no batch releases were performed duning 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 I Mar 1st att Apr May Jun I 2nd qtr Jul Aug I Sep 3rd qtr Oct I Nov I Dec 4th atr Total A. Fission and Activation Oases Ar4l Ci No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Ret No Rel Kr485 Ca No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Ret No Rel Kr-85m Ci No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Ret No Rel Kr-87 Ci No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Ret Kr.88 Ci No Rel No Ret No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Ret No Rel No Rel No Ret No Ret Xe-131 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Ret No Ret Xe-131m Ci No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Ret Xe-133 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Ret No Ret Xe-133m Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Ret Xe-135 Ci No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Ret No Ret No Rel No Rel No Rel No Ret No Ret No Rel No Ret No Ret Xe-135m Ci No Rel No R No Ret No Ret NoNot NR No Ret NOR No R No Ret& No Ret No Ret I No Ret No Ret No Rel No Ret No Ret Xe-138 Ci No Rel No Rel No Rel No Rett NoRt No Re No Rel No Ret No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Ret No Ret B. Iodines Br-82 Ca No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel l No Rel No Relt No Rel No Rel No Ret No Ret 1-131 Ci No Rel No Rel No Rel No el No Ret No Ret No Ret No Ret No Ret No Ret No Ret [NoRet No Ret No Ret No Ret No Ret No Rel 1-132 a No Rel No Relt NoRell No Ret No Ret No Ret No Ret No Ret No RelNo Re lNoNo Retl No Ret No Ret RelNoRelNoRet No Roel 1-133 Ci No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Ret No Rel l No Rel No Rel No Ret No Rel No Rel l No Rel l No Rel l No Ret 1-134 Ci No Ret No Ret No Rel No Rel No Ret No Rel No Rel No Ret I No Rel No Rel No Rel No Rel No Rel No Ret No Rel I No Rel I No Ret 1-135 C No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Ret l No Rel l No Relt No Rel l No Rel No Rel No Retl -No Rel - No Ret l No Ret C. Particulates Na-24 Cl No Rel No Relt No Rel No Ret No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Ret No Ret Cr Ci No Ret No Relt No Relt No Ret No Rel No Rel No Ret No Rel No Rel No Ret No Ret -No Ret No Rel No Rel No Relt No Rel No Rel Mn-54 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 Ret No Ret Co-57 Ci No Rel No Rel No Relt No Ret No Rel No Rel No Relt No Ret No Rel No Rel No Rel No Ret No Relt No Rel No Rel No Ret No Ret CO-58 C No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel No Rel No Relt No Ret No Rel No Ret No Rel No Rel No Ret Ci QCo40 No Ret No Rel 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 No Ret No Ret Zn-65 Ci No Relt No Rel No Rel No Ret No Relt No Rel No Rel No Rel -No Relt No Relt No Rel No Ret No Rel No Retl -No Rel No Ret No Ret Se-75l Ci No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Relt No Relt No Rel No Rel No Rel No Rel No Rel No Rel No Ret Rb-88 Ci No Rel No Rel No Ret No Ret No Rel No Rel No Rel No Rel No Relt No Relt No Rel -No Ret No Rel No Rel No Ret No Ret No Ret Sr al No Ret lI___No Ret No Rel No Ret No Ret Sr Ci - No Retl lI___ No Rel l____ No Ret No Ret No Rel Zr Ca No Rel No Relt No Relt No Ret No Rel -No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Relt No Ret No Ret Nb-95 Ci No Rel No Relt No Rel No Ret No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Relt No Rel No Rel No Rel No Ret Mo-99 Ci No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Ret Tc-99m C 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 No Ret No Ret No Ret Ru_13 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 Relt No Rel No Relt No Ret No Rel A_-110m Ci 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 No Ret No Ret Cr,134 CA No Ret No Ret No Ret- No Ret No Re No ReI No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret Cs-136- Ci No Rel No Rel No Rel No Ret No Rel No Rel No Relt No Ret No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Ret No Rel Cs-137 _ Ci No Rel No Ret No Rel No Ret No Ret No Rel No Rel No Ret No Rel No Relt No Rel No Ret No Rel No Relt No Rel No Ret No Ret Cs-138 lC No Ret No Rel No Rel No Rel No Relt No Rel No Rel No Ret No Relt No Relt No Ret No Ret No Rel No Rel No Rel No Ret No Ret Ba-140 Ci No Ret No Ret No Retl No Ret No Ret No Ret No Ret -No Ret No Retl No Retl No Ret No Ret No Ret No Ret No Ret No Ret No Ret La-j40 Ci No Ret No Ret No Ret No et No Ret No Ret No Ret No Ret No Ret No Ret No Rel No Rel No Relt No Relt No Retl -No Ret No Ret Ce-144 Ca No Rel NoRet No Rel No Ret No Ret No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Re Ret No R No Ret o Ret Pr-144 Ci I No Ret No Re No Rel No Ret No Re No Rel No Rel No Ret No Relt No Rel No Rel No Ret No Ret No Rel No Ret No Rel No Ret W-187 Ci No Rel No Rel No Rel No Retl No Ret No Rel No Rel No Rel No Rel No Rel No Rel NoRet No Ret No Ret No Ret No Rel No Ret D. Tritium 1 Total Release ActMty Ci No Rel No Rel No Rel No Ret No Rel No Rel No Rel I No Ret No Relt No Relt No Rel I No Ret I No Rel No Rel No Rel No Ret I No Rel I Particulate isotope with halflife 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 Jan Feb Mar I1st Qtr Apr May Jun 2nd Qtr Jul Aug Sep 3rd Qtr Oct Nov Dec 4th Qtr Total A. Fission and Activation Gases Ar-41 Ci 41 <LLD <LID <LLD <L < ID LLD <LID <LLD <LLD "LD <LLD <LLD <LID <LLD <LLD <LLD <LLD <LLD Kr-85 Ci <LID <LLD <LID <LID <LID <LID <LLD ~<LLD <LLD <LLD <LLD <LID <LID <LID <LID <LLD <LLD Kr-85m Ci <LLD <LLD <LLD <LLD <LID <LLD <LID <LLD <LLD <LID <LLD <LLD <LLD <LLD <LID <ILD <LID Kr-87 Ci <LLD <LID <LID <LLD <LID <LLD <LLD <LID <LLD <LID <LID <LID <LLD <LLD <LID <LLD <LLD Kr-88 Ci <LID <LID <LLD <LLD <LID <LID <LID <LLD <LID <LLD <LLD <LID <LLD <LID <LID <LLD <LLD Xe-131 Ci <LLD <LID <LLD <LID <LLD <LLD <LID <LID <LID <LLD <LID <LLD <LLD <LID <LID <LLD <LD Xe-131m Ci <LLD <LLD <LID <LID <LID <LID <LLD <cLID <LLD <LLD <LLD <LID <LLD <LID <LID <LLD <LLD jXe-133 Ci I LID I<LID <LID I<LID I<LLD I<LLD I<LI <LDID D <LID <LID <LID <LID <IID <nIDA111I'i LIDLI Xe-133m Ci <LLD <LLD <LLD cLD ID <LLD I<LID I<LLD I<LID I<LLD I<LID <1LIDn <CLnID <IDin~ LIDr <LID <LLD <LLD Xe-135 Ci :LID 'LID <LLD <LLD <LLD I<LLD I<LID <LLD I<LID I<LLD I<LLD I<LLD <LLD -<LLD- LLD <cLD <LLD Xe-135m Ci LID <LID <LID <LID <LLD I<LLD I<LID <LID I<LLD I<LLD I<LLD < LIDLI <LL<ID LDD <LID Xe-138 Cl <LLD <LLD <LID <LLD <LLD <LLD <LID <LID I<LLD I<LLD I<LLD <-LID <LID <LLD <LLD <LLD <LID B. lodlnes Br-82 Ci J<LLD <LLD <LID <LLD <LLD <LLD <LLD <LLD <LID <LID <LID <LLD <LLD <LLD <LID <LID <LLD 1.131 JCi <7LD <LLD <LID <LLD <LID <LID <LLD <LLD <LLD <LLD <LID <LLD <LID <LLD <LLD <cLID <LLD 1-132 Ci I<LLD <LLD <LLD <LLD 'LID <LLD <LLD <LLD <LLD <LID- <LID <LLD <LLD <LID <LLD <LID <LLD 1-1334 1-135 Ci Ci I<LLD<LID

<LID <LLD <LLD -<LLD <LID <LID <LLD <LID <LLD <LLD <LLD _<LLD <LID <LLD <cLLD <LLD

<LID <LID <LLD <LLD <LLD <LLD <LLD <LID <LLD <LID <LLD <LLD <LLD <LLD <LLD <LLD C. Particulates Na-24 Ci <LLD <LLD <LID <LLD <LLD <LID <LLD <LLD <LID <LID <LID <LLD <LLD <LID <LLD <LID <LLD Cr-51V Ci <LLD <LLD <LLD <LID <LLD <LLD <LLD <LLD <LD <ID <I <I LI LD Mn5 e 'I LD <I LD <LD <I LD <I LD <I LD <LID <LLD <LID <LLD <LID <LLD <LID <cLID <cLD Mn-54' Ci <LD <LLD <LLD <LLD <LLD <LID <LID <cLID <LLD <LLD <LLD <LLD <LID- <LID <LID <LLD <LD Co-57' Ci <LID <LID <LID <LID <110<L10D 1 <LID <LLD <LLD <LID <LLD <LLD <LLD <LLD <LLD <LLI-LD C-0Ci <LID <LLD <LLD <LLD <LLD 2.02E-06 <LLD 2.02E-06 <LLD <LID <LID <LLD <LLD I19E-06 <LLD 1.191E-06 3.21 E.06-Zn-651 C <LLD <LLD <LLD <LID <LLD <LLD <LID- <LLD <LLD <LID <LLD <LLD <LID <LLD <LLD <LLD <LLD Se-75' C <LLD <LID <LLD I<LLD <LID <LLD <LLD I<LLD <LLD I<LLD <LID <LLD <LLD <LID <LLD <LID LLID Rb-88 Ci 'LLD <LID <LLD <LLD <LLD <LLD <LLD <LLD <LLD 'LLD <LLD <LLD <LLD <LID <LID <LLD <I Sr8 i<LLD <LLD ____<LLD ____<LLD <LLD Sr-901 Ci - LLD <LLD ____<LLD _______ ___ <LLD <cLD Zr-951 Ci <LLD <LID <LID <LLD <LLD I<LLD 'LID <LLD <LID <LLD <LLD <LLD <LLD <LLD <LLD <cLID <LLD Nb-95' Ci <LLD <LLD <LLD <LLD <LLD <LLD <cLID <LLD <LLD <LLD <LID <LLD <LLD <LLD <LID <LLD <LLD Mo-99 Ci <LLD <LLD 'LD <cLID <LLD <LLD <LLD <LLD <LID <LID <LID <LLD <LLD I<LID <LLD I<LLD <LLD Tc-99m Ci <LLD <LLD <LID <cLLD <LLD <LID <LLD <LLD 'LLD <LLD <LLD <LLD <LID <LLD <LLD <cLID <LLD Au-101m Ag-110m Ci CI

<LLD

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

<LLD <LLD <LLD <LLD <LID <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-1346 Ci <LID <LLD <LLD <LLD <LID I<LLD <LLD <LLD <LID <LID- <LLD <LLD <LID <LID <LLD <LLD <LLD Cs-136' Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <cLID <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-1378 Ci <LLD <LLD <LID <LLD <LLD <LID <LID <LLD <LLD 'LLD <LID cLID- <LLD <LID <LLD <LLD <LLD Cs-138 Ci 'LLD <LLID <LLD <LLD <LLD <LLD <L <LLID D <LLD <LID <LID <LLD <L ID-<LLD <LLD <LLI-ZD Ba-140' Ci <LID <LLD <LID <LLD <LLD <LLD <LID -<LLD <LID I<LLD <LLD <LLD <LLD I<LID I<LID I<LLD I <LLD Le-140 Ci <LLD <LLD <LLD <LLD <LID <LLD <LLD <LLD I<LLD <LLD <LLD <LLD <LLD <LLD <LID <LLD I <LLD 87Ci I ID LD <LLD <LLD <LID <LLD I<LID I-LID I<LID I<LLD I<LLD <LID <LLD 'LIDL LD <LLD <LID~

D. Tritium I1Total Release ActMty Cil <LLD <LLD <LLD I<LLD I<LLD I<LID I<LLD I<LLD I<LLD I<LID I<LLD I<LLD I<LLD I<LLD I<LLD I<LLD <LD Particulate isotope with half-life 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 4th Qtr 2003

a. Total Number of Batch 0 0 0 Releases 0 0

b. Total Time Period for Batch 0.00E+00 0.OOE+00 0.002+00 Releases (minutes) 0.00E+00 0.00E+00

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

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

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

6. Abnormal Releases

a. Number of Releases 0 0 0 0 0

b. Total Activity Released (Ci) 0.OOE+00 0.OOE+00 0.00E+00 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 I &2 GASEOUS EFFLUENTS SUPPLEMENTAL INFORMATION"

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

a. Total Number of Batch 0 0 0 0 0

Releases

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

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

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

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

6. Abnormal Releases

a. Number of Releases 0 0 0 0 0

b. Total Activity Released (Ci) 0.00E+00 0.OOE+0O 0.OOE+00 0.OOE E+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 I. The off-site dose limits per reactor unit are listed below.

Quarterly Yearly (mrem) (mrem)

Gamma Air 5 10 Beta Air 10 20 Total Body 2.5 5 Skin 7.5 15 Organ 7.5 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 500 mrem/year Total Body Noble Gases 3000 mrem/year Skin 1-131, 1-133, H-3, and particulates with half-lives greater than 8 days 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 Percent of Effluent Kr-85 100 Average Gamma Energy per Decay of the Mixture (keV) 5.0 Average Beta Energy per Decay of the Mixture (keV) 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 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr 2003

a. Total Number of Batch 0 0 0 0 0 Releases

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

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

d. Average Time Period for a 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Batch Release (minutes)

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

6. Abnormal Releases

a. Number of Releases 0 0 0 0 0

b. Total Activity Released (Ci) 0.OOE+00 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 1.00E-11 Co-58 1.OOE-11 Co-60 1.OOE-11 Zn-65 1.OOE-1I Sr-89 1.00E-11 Sr-90 1.OOE-11 Mo-99 1.OOE-11 Cs-134 1.OOE-11 Cs-1 37 1.OOE-11 Ce-141 1.OOE-11 Ce-144 1.OOE-11

j ^ -

re

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

ADDENDUM

1. Offsite Dose Calculation Manual (ODCM)

Changes to the ODCM are required by Zion Station Permanently Defueled Technical Specification 5.6.1. and ODCM Section 12.6.3 to be submjtted as part of, or concurrent with, the Annual Radioactive Effluent Release Report.

A summary of changes made to the ODCM during 2003 and an entire copy of the ODCM, current as of December 31, 2003.

2. Gaseous and Liquid Waste Treatment Systems and Process Control Program Zion Station ODCM Section 12.6.4 requires major changes to the Gaseous and Liquid Waste Treatment Systems to be reported in the Annual Radioactive Effluent Release Report.

The Waste Gas Hold-up System was permanently vented. In Zion's defueled configuration this system is no longer applicable.

In Zion's defueled configuration, the charcoal iodine removal system is no longer applicable.

Due to radioactive decay and no means of production, radioactive iodine is not a concern at Zion.

3. Limiting Conditions of Operation (LCOs)

Zion Station ODCM Section 12.7.2 requires explanation as to why the inoperablility of liquid or gaseous monitoring instrumentation was not corrected within the time specified in the ODCM to be submitted with the Annual Radioactive Effluent Release Report.

None

4. Liquid Holdup Tanks and Gas Storage Tanks Zion Station ODCM Section 12.7.2 requires a description of events leading to liquid holdup tanks or gas storage tanks exceeding technical specification limits to be included in the Annual Radioactive Effluent Release Report.

There was no activity present in any gas decay tanks during 2003.

No liquid holdup tanks exceeded the limits of Permanently Defueled Technical Specifications 5.6.3. during 2003.

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

ADDENDUM

5. Estimates of Total Error The following is an estimate of the total error associated with certain total values in the Annual Radioactive Effluent Release Report. The total error is determined by calculating the square root of the sum of the squares of the individual errors.

a. Gaseous Effluents Sampling Error 5%

Calibration Error 10%

Counting Statistics Error 17%

Sample Volume Error 10%

Total Error 23%

b. Liquid Effluents Sampling Error 5%

Calibration Error 10%

Counting Statistics Error 16%

Sample Volume Error 2%

Total Error 20%

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 LIQUID RELEASES UNIT 2 (Docket Numbers 50.304)

SUMMATION OF ALL RELEASES Units IJan IFeb Mar I1st Qtr Apr May Jun 2nd Otr Jul Aug Sep 3rd Qtr Oct Nov Dec Alth Qtr I Total A. Fission and Activation Products (not fncl. trltlum, gases, alpha) 11.Total Activity Released §# I Ci <L'LD I <LID I cLLD <LLD <LLD <LLD <LLD < LLD <LID <LLD <LLD <LD <LID <LLD I 'LD I<LLD I .002+00 12.Averacie Conc. Released IuCi/ml <LLD I LLD I LLD I LID CLLD 'LLD <LLD <LLD I LLD I LLD <LLD I LLD I LLD <LLD <LLD <LLD 0.002+00 13.% of Value (9E-7 uCi/mI) % <LD LLD < LLD 'LID 'LLD 'LLD 'LLD 'LLD 'LLD

< LLD < LLD <LLD 'LLD 'LLD 'LLD

<L LLD_ 0.OOE+00 B. Tritium 11.Total Actmty Released IC1 <LLD <LLD <LLD I<LLD I 'LLD <L'LD I 'LD <LLD -LLD <LLD <LLD <LID <LLD <LLD <LLD <L'LD I0020 12.Avera e Cone. Released uC/mI <LID -LLD 'LID <LLD -LLD 'LLD -,LLD <LID <LLD <LLD <LLD -LLD <LLD <ILD 'LID <LID 0.001E+00

3. % of Value (12-3 u0ilmI) % <LLD 'LID <LLD <LLD ILLD <LLD <LLD <LLD <LLD 'LID cILD <LLD <LLD 'LLD 'ILD <LLD 0.002+00 C.Dissolved and EntraIned Gases 11.Total Act"t Released 0CeI LLD <LLD <LLD <LLD <LLD <LLD <LLD I<LLD <LID <L'LD <LLD I<LLD <LLD <LLD <LLD <LLD I .001E+00 12.Avera e Cone. Released uCi/mI 'LLD <LLD I'-LID <LLD 'LLD 'LLD <LLD <LLD I LLD I'-LLD <LLD I<LLD 'LLD 'LLD I'LLD <LLD 0.00E+00 13.%of Value (7E-5 uCi/mi) % 'LID <LD 'LLD <LLD 'LD 'LLD <LLD cLLD 'LD <LLD 'LLD <LLD 'LID 'LLD <LLD <LLD 0.0012+00

0. Gross Alpha 11.Total Activity Released Ci <LD <LD <L'LD <LLD <LID <LLD <LLD I 'LLD <LLD <LLD cLID I<LLD <LLD <LLD <LID <LLD I LLD 12.Avera e Cone. Released uCmIrn 'LD -,LLD 'LLD cLLD <LLD <LLD I LLD I<LLD I'LLD I'LLD <LD <LLD 'LLD 'LLD <LD LD <LLDD 13.%of Value (2E-9 uCL/mI) % <LLD 'LID <LLD <LLD 'LLD <LD I'LLD I 'LLD I'LLD I LLD 'LLD <LLD <LLD 'LID <LLD <LLD :LID

2. Volume of Releases 11I.Volume of Waste Releasedl liters 14.92E+0614.42E+0616.352+061 1.57E+07 15.98E+0615.472+0615.53E+061 1.70E+07 j5.53E+06j4.94E+06j5.13E+6j 1m.E6+07 14972+0614.84E+0614.70E+061 1.452+07 6.28E+07 12.Volume of Dilution Water Iliters 14.46E+1012.18E+1012.752+091 6.922+10 13.49E+0913.29E+0913.172+091 9.951E.09 13.28E+0913.292+0913.172+091 9.74E+09 13.292+0913.172+0913.29E+091 9.752+09 9821 Fe.55, Sr.89, and Sr-90 Activities are quantified by quarterfy composite analyses. Therefore, the difference between the Fission and Activation Products total quarterly activty and the sum of the total activties of the three corresponding months equals the total quarterly activities of Fe-55, Sr-89, and Sr-90.

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

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

Lower limit of detection (LID) values are presented In the Liquid Effluents LLD Values for Liquid Releases section. The abbreviation "'LIDY" indicates the activty concentration of the radionuclide for each indivdual 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 activty concentration of each radionuclide for each sample during the peniod was less than the LID value for the respective radionuclide.

The abbreviation "No Rer 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 I 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 timlls for Cs-1 34 (9E2-7 uCl/mI) and Ar-.41 (7E-5 uCi/ml), respectively. Concentration limits for Dissolved and Entrained Gases are listed in ODCM Table 12.3-1.

ZION NUCLEAR POWER STAT1ON ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 LIQUID RELEASES UNIT 2 (Docket Numbers 50-304)

BATCH MODE U

Lnis I Jan I Feb I mar I lst Otr I Apr I MaY I Jun I2nd Qtr Jul IAug ISep 3rdQtr Oct I Nov I Dec I4th Qtr I Tota A. Fission and Activation Products Na-24 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 Ret <LLD Cr-51 Ci No REt1 No Ret No Ret No Rel No Ret No Ret No Ret No Ret No Ret No Retl No Ret No Ret No Ret No Ret No Ret No Rel <LLD Mn.54 Ci No Ret No Ret No Retl 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 <LLD Co-57 Ci No Rud 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 Fe-55 Ci ____ ____ ____ No Ret ___ ___ ___ No Ret No Retl___ No Rel <ILLD Fe-59 Cil- -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 <LLD Co-58 Cl No Ret No Ret No Ret No Rel No Ret No Retl No Ret No Ret No Ret No Ret No Ret No Rel No Ret No Retl No Ret No Ret -<LID Co-60 Ci No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Retl No Ret No Ret No Ret No Ret No Ret No Ret No Ret <LLD Zn-65 Ci No Ret No Ret No Ret No Ret No Ret No Ret No Retl No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel <LLD Sr-85 Ci No4Ret 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 Rb-88 Ci No Ret No Ret No Ret No Ret No Retl No Ret No Ret No Ret No Ret No Ret No Retl No Rel No Ret No Ret No Ret No Ret <LLD Sr-89 Ci ____ ___ No Rel ____No Rel ____ ____No Ret No Ret cLLD Sr-SO Ci____ No Retl ___ No Rel ____ No Retl ___ ___ No Rel <LLD Sr-92 ClI 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 No Ret No Ret No Ret <LLD Nb-95 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 Ret -<LLD Zr-95 Ci No Ret No Ret No Ret No Ret No Retl No Retl No Ret No Ret No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret <ILLD Z~r-97 Ci No Ret No Ret No Ret No Rel No Retl No Ret No Ret No Rel 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 NoRel No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Retl <LLD Tc-99m 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 -<LID Ru-103 Cc 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 No Re) <LLD A -11rn Ci No Ret No Retl No Ret No Rel No Ret No Retl No Ret No Ret No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret <LID Sn-113 Ci 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 Retl No Ret <LLD Sn-1 1rn 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 Retl No Ret No Ret No Rel <LD Sb-i122 Ci No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel INo Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret 'cLD Sb-i124 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 Retl No Ret No Ret <cLID Sb-i125 Ci No Ret No Ret No Ret No Rel No Ret No Ret No Retl No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret <LID Sb-i 26 Ci No Ret No Ret No Ret No Rel No Retl No Ret No Ret No Ret No Retl No Ret No Ret No Ret No Ret No Ret No Ret No Rel <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 Ret <LID Te-i 32 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 Retl No Ret No Ret <LLD Cs-i134 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 <LID Cs-i37 Ci No Ret No Ret No Ret No Ret No Ret No Ret No Retl No Ret No Ret No Ret No Ret No Ret No Retl No Ret No Ret No Rel <cLID Cs-i38 Ci No Ret No Retl 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 Ret <LLD Ba-i140 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 Ret <LD La-i 40 Cie 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 Ce-i 41 Ci No Ret No Ret No Ret No Ret No Ret No Retl No Ret No Ret No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel <LLD Ce-i 44 ClI No Ret No Ret No Ret No Rel N Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret <LLD Pr-i44 Ci No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret INo Ret No Ret No Ret No Retl No Ret No Ret <LLD B. lodtnes I- Rti N NoRt oRt oRe o e JN et N Rt NoRt oRt oRe o1e N e No Ret No Ret No Ret No Ret <LID 1-13 Ci No Ret No Ret No Ret No Ret No Ret INo Ret INo Ret No Ret No Ret No Ret No RetlI No Ret -No Ret NoRt N e oRt <I 1I13 Ci j No Ret No Ret No Ret I No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret I No Ret No Ret No Ret No Ret <LLD 1I13 Ci No Ret No Ret No Retl No Relt No Retl No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret <LLD 1C134 j No Ret No Ret No Ret No Ret No Retl No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Retl No Ret <LLD C. Trittium i1.Total Release Act" I .. L.I NoRl[ No Ret I No Rel No Ret I No Rel I No Rel No Rel I oj eNo RteJ No Rt elNo R etNo R etNo R el]l No Rel NoRet I NoRet <LD ]

D.Dissolved and Entrained Gases Ar-4l Ci No Ret No Ret No Retl No Retl No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Retl No Ret No Ret No Ret <LLD

[Kr-85 j cii No Ret No Ret No Retl No Retl No Ret No Ret No Ret No Ret No Re No Retl N Ret No Retl N Ret No Ret No Ret No Ret <LLD

~Xe-1 31im GI [ No Ret No Ret No Retlj No Retl No Retl No Ret No Ret No Rel No Ret No Retll No Retl No Ret No Retl No Ret No Retl No Retl <LLD,

[Xe-i 33 Ci No Ret No Ret No Ret No Retl No Ret No Ret No Ret No Ret No Retl No Retl No Retl No Ret No Ret No Ret No Ret No Ret <cLID

[Xe-i133m eli No Ret No Ret No Retl No Retl No Ret No Ret No Ret No Ret No Ret No Retl No Ret No Ret No Ret No Rel* No Retl No Ret <LLD LXe-i 35 Ci No Ret No Ret No Retl No Retl No Ret No Ret No Ret No Ret No Ret No Ret No Retl No Ret No Ret No Ret No Ret No Retl <cLID

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

CONTINUOUS MODE IUnits Jan IFeb IMar IlIst Qtr IApr Imay Jun I2nd Qtr Jul IAug Sep 3rd Otr IOct INov IDec I4th Qtr I Tota A. Fission and Activation Products Na-24 Ci No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rei No Rei No Re) No Ret No Retl No Retl No Ret No Rel 'LI Cr.51 Ci No Rel 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 Ret <LD Mn-54 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 Ret <LLD Co-57 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 Ret LLD Fe-55 Ci_ _ __ _ _ _ No Ret __ _ No Retl _ _ __ _ _ No Retl __ _ No Ret <LLD Fe-59 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 Ret 'LLD Co-58 Ci No Ret No Ret No Ret No Ret No Ret No Ret No Retl No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret <LLD CG-60 Co No Ret No Ret No Ret No Ret No Retl No Ret No Ret No Ret No Retl No Ret No Ret No Ret No Ret No Ret No Ret No Ret 'LD Zn-65 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 Ret <LD Sr-85 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 Ret 'cLD Rb-8 Ci No Ret No Ret No Ret No Ret No Ret No Ret No Retl No Ret No Ret No Ret NoR RetI No Ret No Ret No Ret No Ret No Ret <LLD Sr-89 Ci____ No Retl_ _ _ No Retl ___ No Retl___ ___ No Ret 'LD Sr.90 Ci____ ___ No Retl___ No Retl ___ No Retl___ ___ No Ret <LD Sr-92 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 Ret <LD Nb-95 Ci No Ret No Ret No Retl 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 <LD Zr-95 Ci No Ret No Ret No Ret No Ret No Retl No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret <LLD Zr-97 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 Ret <LD Mo-99 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 Ret <LLD Tc-99m Ci No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Retl No Ret No Ret No Ret No Ret No Ret -'LLD Ru-i 03 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 Ret <LLD A -i1l0in Ci No Ret No Retl 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 <LD Sn-113 GI 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 Ret <LD Sn-1i7m 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 Ret <LLD I Sb-i122 Ci No Ret No Ret No Retl No Ret No Ret No Ret No Ret No Ret No Ret No Retl 1No Retl No Ret No Ret No Ret No Retl No Ret <LLD Sb-i24 Ci No Ret No Ret No Retl No Ret No Retl No Ret No Ret No Ret No Retl No Ret No Ret No Ret INo Ret No Ret No Ret No Ret <LLD Sb-i25 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 Ret <LLD Sb-126 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 Ret <LLD Te-123m 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 Retl No Ret <LLD Te-i32 Ci No Ret No Ret No Ret No Ret No Retl No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Retl No Ret No Ret <LLD Cs-i134 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 Ret <LD Cs-i 37 Ci No Ret No Ret No Ret No Ret No Ret No Retl No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret <LLD Gs-1 38 Ci No Relt No Rel No Rel No Ret No Rel No Ret No Ret No Ret No Rel INo Rel No Relt No Ret No Rel No Ret No Rel No Ret <LD Ba-i140 Ci No Ret No Ret No Retl 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 <LID La-i 40 Ci No Ret No Ret No Ret No Ret No Retl No Ret No Retl No Ret N Ret NoRe No Ret No Ret No Ret No Ret No Ret No Ret <LLD Cei 41 Ci No Ret No Ret No Ret No Ret No Ret No Retl No Ret No Ret N Ret N Ret No Ret No Ret No Re No Ret 'NoRe NoRt LI Ce-i1 44 Ci No Ret No Ret No Ret No Ret No Ret No Ret No Ret NoRet No Ret N Ret No Ret No Ret No Ret No Rt N e oRt 'I IPr-i144 Ci No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret N Ret NoRe No Ret' oRt N e oRt N e oRt 'I S. todines 1-13 ____I No R-e TNo Rt No Ret No Ret No Retl No Ret No Ret I No Ret No Ret No Ret INo Ret No Ret No Ret NoRetI No Ret No Ret 'LID 1-13 Ci No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Retl No Ret No Ret No Ret No Ret No Ret <LLD 1-13 Co o eNo Re No t Re tNo Re tNo Re No t Re No t Re tNo Retl No Re t No Retl oe No Re tNo Re No t Re tNo Re tNo Retl 'I 1t1i Ci No Ret INo Ret No Ret No Ret No Retl No Ret No Ret No Ret N Ret NRet No Ret No Ret No Ret No Ret No Ret NoRe I 11ees oa cmy Ci No Retl No Ret No Ret No Ret No Ret No Ref No Rel No Ret No Rel No Ret No Rel No Rel No Rel No Rel No Ret No Ret LI D. Dissolved and Entrained Gases

[Ar-41 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Retl No Ret No Rel No Rel No Rel No Rel No Ret No Rel No Ret( LD mir-o5 Ii NoeIK NOI eiNOI No Re i I eeNoelINRMt I No Ret I No Ret I No Ret I No Ret I No Ret I No Rel I No Ret I No Ret I No Rel I No Rel I No Rel I <LLD-]

F

!Xe-i31 i Xei 3 -.7 CI

-j7---* . - - . .

I Nn Rp.i I Hn PM I JNP.1 I

M.

... I -

I ki 0I I No Re No Ret I.

No Ret I No Ret No Ret INo Retl I No Ret [No Ret No Ret NoRetl No Ret No Ret No Ret No Ret I No Relt No Ret INo Ret No Ret No Re

~LI

<LLD 1= 1-3 3rn I C; I~ No_~iet o Ret I No Ret No Ret~ I N _oRet No Ret No Ret I No Ret No Ret No Ret No Re No Ret No Ret I[No Rel I No Ret No Ret I '<LD LXe-135 I Ci No Ret [ No Relt No Ret No Ret I No Ret No Ret I No Ret INo Ret No Ret No Ret No Ret No Ret_ No Ret No Ret I No Ret No Ret I '<LD

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

BATCH MODE Units I Jan I Feb I Mar I 1 st Qtr I Apr I May I Jun I 2nd Qtr Jul Aug I Sep I 3rd Qtr Oct I Nov I Dec I4th Qtr I Total A. Fission and Activation Products Na-24 Cl cLLD No Rel 'LLD No Rel <LLD <LLD 'LLD No Rel <LLD cLLD <LID <LLD cLLD <LID <LLD <LLD cLLD Cr-51 Cl <LID No Rel <LLD No Rel <LLD 'LLD <LLD No Ret <LLD LcLD cLLD <LLD cLLD <LLD <LLD <LLD <LLD Mn-54 Cl cLLD No Rel cLLD No Rel <LLD <LID 'LLD No Rel <LLD cLLD 'LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-57 Cl <LLD No Rel 'LID No Ret <LID cLLD <LLD No Rel <LLD 'LLD -cLLD <LID cLLD cLLD <LLD <LLD <LLD Fe-55 Ci cLLD <LLD <LLD <LLD <LLD <LLD Fe-59 Co 'LID No Rel cLLD No Rel <LLD 'LLD 'LLD No Ret 'LLD 'LLD cLLD <LLD <LLD 'LLD 'LLD <LID <LLD Co-58 Ci <LLD No Rel <LLD No Rel 'LLD 'LLD cLLD No Rel 'LLD <LLD cLLLD <LLD 'LLD <LLD <LLD <LLD 'LLD Co-60 Cl <LLD No Rel 'LLD No Rel 'LLD 'LLD 'LID No Rel 'LLD 1.09E-5 7.OOE-06 1.79E-05 8.78E-06 'LLD 'LLD 8.78E-06 2.67E-4S Zn-65 Ca 'LLD No Rel 'LLD No Rel 'LID <LID cLLD No Ret 'LLD 'LID <LLD <LLD cLLD cLLD <LLD cLLD <LLD Sr-85 Ci <LLD No Rel <LLD No Rel <LLD cLLD 'LLD No Rel cLLD cLLD LID <LLD 'LLD cLLD 'LLD <LID 'LLD Rb-88 C0 <LLD No Rel cLLD No Rel 'LID 'LLD <LLD No Rel 'LLD <LLD 'LLD 'LLD <LLD 'LLD 'LLD <LLD <LLD Sr-89 Cl No Rel No Rel <LLD <LLD <LLD Sr-90 Ci <LLD <LLD cLLD _LLD 'LLD Sr-92 C 'LLD ILLD <LLD No Rel 'LID <LLD <LLD No Rel 'LID 'LLD 'LLD <LLD 'LD 'LLD <LLD <LLD 'LLD Nb-95 Cl <LLD <LID <LLD No Rel <LLD ILLD cLID No Rel 'LLD <LLD eLLD <LLD <LLD <LLD <LLD 'LLD 'LLD Zr-95 Ci 'LID 'LLD <LLD No Ret 'LID cLLD 'LID No Ret 'LLD <LLD 'LLD <LLD LID 'LLD 'LID <LLD 'LLD Zr-97 Cl 'LLD <LID <LLD No Rel <LLD <LLD cLLD No Rel 'LLD <LLD cLLD <LLD <LLD cLLD <LLD cLLD <LLD Mo-99 Cl <LLD <LLD 'LLD No Rel 'LLD <LLD cLLD No Rel <LLD <LLD LLD <LLD 'LID <LLD <LLD <LLD <LLD Tc-99m Cl <LLD <LLD <LLD No Ret <LLD 'LLD <LID No Ret <LLD 'LD <LLD <LLD 'LLD <LLD <LLD <LLD <LLD Ru-1 03 Cl 'LID 'LLD 'LID No Rel <LLD <LLD <LLD No Ret 'LLD <LLD 'LID cLLD 'LLD <LLD <LLD <LLD 'LLD Ag-1 1Om Ca <LLD 'LID <LLD No Rel 'LID <LLD 'LLD No Ret dLID <LLD 'LID dLID <LLD cLLD <LLD <LLD <LLD Sn-t13 Cl 'LD 'LID 'LID No Rel 'LID LLD cLID No Rel 'LLD 'LLD 'LDD <LLD <LLD 'LLD <LLD ILLD <LLD Sn-117m Cl <LLD ILLD <LLD No Rel <LLD ILLD cLLD No Rel <LLD 'LLD 'LLD ILLD <LLD ILLD <LLD <LLD <LLD Sb-122 Ci <LLD <LLD 'LID No Rel cLLD 'LLD <LLD No Rel 'LID 'LID LID <LLD <LLD <LLD <LLD <LLD <LLD Sb-124 Ca cLLD <LID 'LLD No Rel 'LLD LLD 'LID No Rel 'LID 'LID 'LLD !LLD <LLD <LLD <LLD cLLD <LLD Sb-125 Cl 'LID 'LLD <LLD No Rel 'LID 'LLD cLID No Rel <LLD 1.60E-06 8.80E-07 2.48E-06 6.20E-07 'LLD 'LID 6.20E-07 3.1OE-06 Sb-126 Cl <LLD 'LLD 'LLD No Rel 'LLD 'LLD <LLD No Retl LLD <LLD 'LID <LLD <LLD 'LLD <LLD <LLD <LLD re-123m Ca dLD <LID 'LLD No Rel <LLD 'LID cLLD No Rel cLLD 'LLD 'LID 'LID <LLD 'LLD <LID <LLD <LLD Te-132 Ci 'LLD <LLD 'LLD No Rel <LLD 'LID 'LLD No Rel 'LID 'LLD <LID 'LLD cLLD 'LLD <LLD 'LLD <LLD Cs-1 34 Cl <LID <LLD <LLD No Rel 'LLD <LLD 'LLD No Rel <LLD 2.50E-47 1.70E-07 4.20E-07 1.60E-07 <LLD <LLD 1.60E-07 5.80E-47 Cs-137 CI 'LLD 'LLD <LLD No Rel 'LLD 'LLD <LLD No Rel 'LID 2.16E-45 1.69E45 3.85E-05 1i92E-O5 <LLD <LLD 1.92E-45 5.77E-0S Cs-138 Cl <LLD <LLD <LLD No Rel <LLD 'LLD <LLD No Rel <LLD <LLD 'LID cLLD 'LLD LLD <LLD <LLD <LLD Ba-1 40 Ci 'LLD 'LLD 'LID No Rel 'LID 'LLD 'LLD No Rel 'LLD <LLD 'LID 'LID <LLD 'LLD <LLD <LLD I LLD La 140 Ca 'LLD 'LLD 'LLD No Rel 'LLD <LLD 'LLD No Rel 'LLD <LLD 'LID LLD dLID 'LD <LLD cLLD <LLD Ce-141 Ci LLD 'LLD 'LLD No Rel 'LLD 'LLD 'LLD No Rel <LLD 'LID 'LLD <LLD LLD LID <LLD <LLD <LLD Ce 144 Ci LLD cLLD 'LLD No Rel <LLD 'LID 'LID No Rel 'LID <LLD LID <LID cLLD <LID <LLD <LLD <LLD Pr-i44 Cl cLID cLID <LLD No Ret cLLD cLLD LLD No Rel cLLD <LLD cLID cLLD cLLD 'LID <LLD <LLD LID B. lodines 1-131 C 'cLLD I <LLD I <LLD I No Rel I <LLD I cLLD cLID I No Rel LID 'LLD cLLD i cLLD I cLLD I <LLD I <LLD I <LLD <LLD I-132 Ci I cLLD l <LLD cLID No Rel J CLID I CLLD 'CLLD r No ReT CLLD I cLID l 'LID 'sLID r'DLID< Il 'LD l cLID l LLD l1.133 Cl l LLD- l lLLD LLLLD- l No Rl l sLLD cL~LDLLD~: lN~o Rel LDlcL sL L LD LDIcLLLDLD < LLD I 1-134 Ci cLLD

< lLID LLD No Ret 'LID 'LLD 'LLD No Rel 'LLD 'LID 'LID ' LD lLLD 'LLD c lLLD l LLD <LLD 1-135 Ci J 'LLD 'LLD <LLD J No Rel i cLLD <LLD <LLD No Rel TLID <LLD rLID <LLD <LLD l 'LLD 'LLD <LLD <LLD C. Tritium

11. Total Release ActMtY I <LLD l cLLD [ cLLD l No Rel l cLID cLLD cLLD

< l No Ret I <LLD 14.47E-0441.18E-04]I 5.65E.04 I 2.35E-04 cLLD I <LLD I 2.35E-04 l 800E4 D. DIssolved and Entralned Gases Ar4I Co l cLLD <LLD cLLD

< No Rel l cLID lLLD lLLD l No Rel <LLD <LLD cLLD <LLD <LLD <LLD 'LID <LLD l LLD Kr-85 Ci J cLLD <LLD J 'LLD J No Rel cLID

< <LLD <LLD l No Rel cLLD

< 'LLD <LLD <LLD LLD 'LID ILID <LLD I LLD Xe-131 Ci J <LID <LID <LID JNo Ret J LD 'LD 'LD No Ret LID j LD <LID <LLD <LD <'LLD 'LLD <LLD l 'LLD Xe-1 33 Ci J 'LID 'LLD <LLD J No Rel <LLD cLID lLLD T No Rel <LLD cLLD

< cLLD <LLD 'LLD lLLD 'LLD r LLD -'LLD

[Xe-133m Cl lLLD 'LLD 'LLD

< No Rel <LLD <LLD 'LLD J No Rel cLLD

< 'LLD <LLD <LLD ILLD cLLD

< <LLD <cLLD <LLD Xe-135 Cl cLLD

< cLID 'LLD

< j No Rel <LLD <LLD 'LLD j No Rel l cLLD 'LLD

< lLLD <LLD <LLD 'LLD

< lLLD l cLLD l LLD

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

CONTINUOUS MODE Iunits IJan TF-e-b Mar I1st Ctr IApr IMa IJun I2nd Qtr IJul IAug ISep I3rd Qtr IOct INovI _Dec _4th Q~tr Toa A. Fission and Activation Products Na-24 Ci <LLD -cLLD <LLD No Rel 'LLD <LLD <LID No Ret 'LID <LLD <LID <LLD <LID <LLD <LID <LLD <LLD Cr-Si Ci <110 <LLD <LLD No Rel 'LLD 'LLD <LLD No Ret <LLD <LLD -'LID <LLD <LLD <LLD <LLD <LLD 'LD Mn-54 Ci cLLD <LLD <LLD No Ret <LLD <LLD <LLD No Ret <LLD <LLD 'LLD <LLD <LLD <LLD 'LLD <LID <LD Co-57 Ci 10D <LLD <LLD No Ret <LL0 <LLD 410D No Ret <LID <LLD <LLD <LID <LLD <LLD <LLD <LLD <LLD Fe-55 Ci_ _ _ _ _ _ _ 'cLLD __ __ _ __ _ __ LD __ _ _ _ _ _ LLD __ _ __'LD <LLD Fe-59 Ci <LID <LID- <LLD No Ret <LLD 'LLD <LLD No Ret 'LLD <LLD <LLD <LLD <LLD 'LID <LLD <LLD <LLD Co-58 Ci <LLD <LLD 'LLD No Ret 'LID <LLD 'LLD No Ret <LID 'cLLD <LLD <LID <LLD <LLD <LLD <LLD <LLD Co-60 ClI <LLD <LLD 'LID INo Rel 'LLD ' LID <LLD INo Rel 'cLID <LLD 'I LD 'LLD I <LD <LLD I'LLD <LLD <LLD Zn-65 Ci <LLD <LLD <LLD No Ret <LLD 'LID 'LLD No Ret <LLD <LLD <LID <LLD 'LLD <LID <LLD <LLD <LLD Sr-85 Ci 'LID 'LID 'LID- -No Ret <LLD <LLD 'LLD No Ret <LLD <LID 'LID <LID <LID <LLD <LLD <LLD <LID Rb-88 Ci <LLD <LLD 'LID No Ret 'LID <LLD <LLD No Ret <LLD 'LID 'LLD <LID 'LLD <LLD <LID 'LID 'LD Sr-89 Ci _____ 'LD ___ LID

<___ ___ LLD

<___ LLD

<___ <LLD Sr-SO Ci _____ LLD ___ LLD

<___ ___ LLD

<___ ____ ___ LLD <LLD Sr-92 Ci <11D cLID 'LLD No Ret <LLD 'LLD <LLD No Ret <LLD <LLD 'LLD <LLD <LLD <LLD 'LID 'LID <LD Nb-55 Ci <LLD 'LID <LLD No Ret <LLD 'LLD <LLD No Ret <LLD <LLD <LLD 'LID <LLD <LLD <LLD <LLD <LLD Zr-95 Ci <LLD <LLD <LLD INo Ret 'LLD I'LLD <LLD No Ret <LLD cLLD I'LID <LLD I'LLD <LLD <LLD 'cLLD <LLD Zr-9i Ci 'LID <LLD <LLD INo Ret <LLD <LLD <LLD No Ret 'LID 'LLD <LLD <LLD cLID <LID 'LID <LLD <LD Mo-99 Ci <LLD <LLD 'LLD INo Ret <LLD 'LD 'LD No Ret 'LID <LLD <LID <LLD <LLD 'LID <LLD <LLD <LLD Tc-S9m Ci '__LID <LLD <LLD No Ret <LLD <LLD <LLD No Ret 'LLD <LLD 'LID <LLD <LLD <LLD <LLD <LLD <LLD Ru-i 03 Ci <LLD <LLD <LLD No Ret 'LLD 'LLD <LLD No Ret 'LLD <LLD 'LLD <LID <LLD <LLD <LLD 'LLD <LLD Ag-110m CI '7LILD <LLD <LLD No Ret <LLD <LLD 'LLD No Ret <LLD <LLD 'LLD <LID <LLD <LLD <LID <LLD 'LLD Sn.113 Ci <LLD 'LLD <LLD No Ret 'LLD <LLD <LLD No Ret 'LLD <LLD <LLD 'LID <LLD 'LID <LLD <LLD <LD Sn-il17m Ci <LLD <LLD <LID No Ret <LLD <LLD <LLD No Ret <LID <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sb-122 el <LLD <LLD <LLD No Ret <LLD I'LLD 'LID No Ret 'LID <LLD <LLD <LLD I LLD <LLD ' LLD <LLD <LLD-Sb-1 24 Ci 'LID 'LID <LLD No Ret 'LID <LLD <LLD No R~et <LLD <LLD <LLD <LLD <LLD 'LLD <LLD <LLD <LLD Sb-i125 Ci <LLD <LLD <LLD No Ret <LLD 'LLD <LLD No Ret <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LD <LID Sb-i126 Ci 'LLD <LLD <LLD No Ret <LLD 'LLD <LLD No Ret 'LLD <LLD <LLD <cLLD <LLD <LLD <LLD <LLD <LID Te-123m Ci <LLD <LLD <LLD No Ret 'LLD <LLD 'LLD No Ret <LLD 'LLD <LLD <LLD <LLD 'LLD <LLD <LLD <LLD Te-1 32 Ci <LLD 'LID 'LID No Ret <LLD <LLD <LLD No Ret <LLD <LLD <LLD -<LLD- <LLD <LLD 'LLD <LLD <LLD Cs-i 34 Ci <LLD <LLD <LLD No Ret <LLD <LLD <LLD No Ret <LLD <LLD 'LLD <LID <LLD <LLD 'LLD <LLD <LD Cs-137 Ci <LLD 'LID- <LD No Ret 'LID <LLD <LLD No Ret <LLD <LLD 'LD <LLD <LLD <LLD <LLD <LD <LLD Cs.138 Ci <LLD <LLD <LLD No Ret 'LLD I'LLD <LLD No Ret <LLD <LLD 'LID <LLD <LLD <LLD I'LLD <LLD <LLD Ba-i 40 Ci <LLD <LLD <LLD No Ret 'LLD <LLD 'LID No Ret 'LLD 'LID <LLD <LLD <LLD <LLD <LLD <LLD <LD La-140 Cc <LLD <LLD 'LID No Ret 'LLD <LLD <LLD No Ret 'LLD <LD 'LLD <LLD 'LLD 'LLD <LD <LLD <LLD Ce-1 41 Ci <LLD 'LD 'LD No Ret <LLD <LLD- 'LLD No Ret <LLD <LLD <LLD <LLD <LLD 'LLD <LLD <LLD <LLD Ce-i 44 ci: <LLD 'LLD <LLD No Ret <LLD <LLD 'LILLD No Ret 'LLD <LLD <LLD <LLD <LLD <LLD <LLD <LI :LLD Pr-144 Ci 'LID1 <LID- <LLD No Ret 'LID <LIDL LD No Ret <LD 'LD

<L LD <L LD <L LD <L LD <L LD LILD LLD B. lodlnes 1-132 1-133 1-134 1-135

] __

Ce Ci l

l

'LD LID

<LLD

'LD_

'LLD

'LI:D

<LLD

'LID

'LID__

No Ret No Ret No Ret No Ret

<LLD

<LI

<LD

<LD j

LD

'I

'LD

'LD LD

'LLD

<'LLD No Ret No Ret No Ret No Ret

'LD LD <L

'LLD

<LD

'LID

<LLD

'LD

<LLD LD <

<LI

'LID

<LID

<LLD cD <LLDD___

<LLD

'LID

<LID

'LLD

<LLD

'LLD

<LLD

'LID

<LLD

<LID

<LD

'LD

<LLD

<LLD C. Tritium

[1. Total Release Activity I Ci <LLD I'LLD I <LDID No Ret I 'LLD I <LLD [ <LLD No Ret <LLD <LLD <LLD <LLD <LLD <LLD [<LLD <LLD <LLD ]

D. Dissolved and Entrained Gases rAr-41 I r-. I 'fin I 'fin I fir I .i -o. I -.. ,- I .I I _.' i kr-85 IXe-131m j~; IDt 'LI __ _ N Re 'LDK;LI LD[ oRt['LDJ'I ]1:LID ' LID [ :LLD j 'LLD ' LILLD <LID j LID I 'lLLD I LLDj __I No Ret 'LLD I 'LLD I'LLD I No Ret 'LID I cLID_ I 'LLD I LLD I 'LID I <LLD I'LLD I 'LLD I <LLD h'e-i"

. Xe.133m 0

C:

j 'LLD I :LID I 'LLD I No Ret I '1.1D0

LD LD 'LLD jNo RetI f__ ILD L

'LLD LLD I

f LLD LLD

_tNRetl N

<LLD I IRe'LLD I <LLD I LLD

'LLD I 'LID I LLD

'LID I 'LLD I 'LLD I LI <LLI-D <LLD J1 I I 'LLD I 'LLD I '<LID) <LLD I <LLD I Xei 5Cij'LDI <LLD I'LID INo Retj1 .LD I <LLD I<L I No Ret 'LLD I'LLD I 'LLD I I LLD I <LLD I<LID <LLD I'LLD I'LLD I

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 Otr Apr m Jun 2nd Otr Jul Aug Sep 3rd atr Oct Nov Dec 4th Otr Total A. Fission and Activation Products (not Incl. tritium, gases, alpha) 11.Total ActMtVy Released § I I <LLD d I <LLD I <LLD I <LLD LLD <LID L DLLD

<LL <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 0.OOE+00

2. Average Conc. Released uCilml <LID <LID <LLD <LLD <LID cLLD cLLD <LLD <LLD <LLD <LLD ILLD <LLD <LLD <LLD <LLD 0.00+00

3. % of Value (9E-7 uCi/ml) % <LLD <LLD <LLD <LLD <LLD <LD <LLD d<LD <LLD clLD <LLD <LLD <LLD LLD <LLD <LLD 0.E+00 B. Tritium l1. Total ActMtY Released l Ci <LLD <LLD l <LD l LLD l LLD D l <LID l <LLD <LLD lI LLD l LLD I LID

<LLD l LLD l lILLDLLD <LLD l 0.00E+00

2. Average Cone. Released ui/ml <LLID <LLD I <LLD <LLD <LD <LD <cLLD <LID <LID ILD I cLLD I <LLD <LD <LLD <LLD LD l0.00E+00

3. % of Value (1E-3 uCiml) h% <LLD <cLLD < I <LLD <LLD <LLD cLLD <LD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 0.00E+00 C. Dissolved and Entrained Gases j1. Total ActMty Released Ci I <LLD l <LLD <LID I <LLD <LLD i <LLD l cLLD l LLD l <LLD I <LLD <LLD

< <LLD I <LLD l <LLD l <LLD <LLD l 0.00E+00

2. Averase Cone. Released I uC/mI I <LD i <LLD i <LLD I cLLD <LLD <LLD <LLD <LLD <LLD I <LLD <LD <LLD I <LLQD I LLD I <LLD <LLD 0.00E+00

3. % of Value 7E-5 uCtIml) l% I <LD I <LLD I <LLD <LLD I <LLD I <LD I cLLD I LLD I <LLD I cLLD I <LLD <LLD <

<LLD <LLD <LLD I <LLD I 0.00E+00 D. Gross Alpha 11.Total ActMty Released l C I <LLD l <LLD I <LLD I <LLD I <LLD I <LLD I <LLD <LLD

< l <LUD <LLD

< l <LLD l LLD l <LID l <LLD l <LLD <LLD

< I <LD 12.Avers e Cone. Released IuCi/ml I<lLID <LLD I<LLD I<LLD I<LLD I<LID I<LD <cLID <LLD <LLD <LID <LLD <cLLD <LID <LLD <LID <LID

3. % of Value (2E-9 uC/ml) I % I c<LD cLLD <LlD <LL I LD <LID lI <LID LLD <cLLD <LLD dLLD <LLD <LLD <LLD <LLD <LLD <LLD E. Volume of Releases 1.VolumeofWasteReleasedi liters 14.92E+0614.42E+0616.35E+061 1.57E+07 15.98E+0615.47E+0615.53E+061 1.70E+07 15.53E+0614.94E+0615.13E+061 1.56E,+07 14.97E+0614,84E+0614.70E+061 1.45E+07 I 6.28E+07

2. Volume of Dilution WaterI liters 14.46E+1012.18E+1012.75E+091 6.92E+10 13.49E+0913.29E+0913.17E+091 9.95E+09 13.28E+0913.29E+0913.17E+091 9.74E+09 13.29E+0913.17E+0913.29E+09i 9.75E+09 I 9.862+10

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

The cells for monthly acMty 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 "cLLDE'indicates the actMty concentration of the radionuclide for each indMdual sample analyzed during the applicable period was less than the LLD value for that nuclide. If the abbreviation c<LLD" is listed for a group of radionuclides, the actMy concentration of each radionuclide for each sample during the period was less than the LLD value for the respective radionuclide.

The abbreviation "No Rer 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 limis for Cs-134 (9E-7 uCimi) and Ar.41 (7E-5 uCiml), 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 Unts Jan I Feb Mar I1st Qtr I Apr I May I Jun I 2nd Qtr Jul I Aug I Sep I 3rd Qtr I Oct I Nov Dec I 4th Qt; Total A. Fission and Activation Products Na-24 CI 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 Ret No Ret No Ret <LLD Cr-51 Cl No Ret No Rel No Ret No Rel No Ret No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Rel No Ret No Ret No Rel <LLD Mn-54 CI No Rel 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 Rel <LLD Co-57 CI 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 No Rei No Rel No Rel <LLD Fe-55 CI No Ret No Ret No Ret No Ret dLLD Fe-59 CI 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 Ret <LLD Co-58 CI 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 Ret No Rel <LLD Co-60 CI No Rel No Rel 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 Zn-65 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 Rel No Ret No Rel <LLD Sr-85 Cl No Rel 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 No Ret No Ret <LLD Rb-88 a No Ret 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 <LD Sr-89 Ci No Ret No Ret No Ret No Ret <LLD Sr-90 Ci No Ret No Ret No Ret No Ret <LLD Sr-92 CI 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 No Ret No Ret <LLD Nb-95 CI No Ret NoRet 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. No Ret <LLD Zr-95 Cl No Rel No Ret No Ret No Ret No Ret No Rel No Ret No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Retl No Rel 'LLD Zr-97 CI No Ret No Ret No Ret 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 <LLD Mo-99 CI No Rel 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 Rel <LLD Tc-99m CI 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 Rel No Ret No Rel No Ret <LLD Ru-103 Cl 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 No Ret No Rel 'ILD Aq-110m Ci 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 No Ret No Ret No Ret <LLD Sn-113 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 Rel No Rel 'LLD Sn-117m Ct 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 No Rel No Ret No Ret <LLD Sb- 122 Cl 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 No Ret No Ret No Ret 'LLD Sb-i 24 Cl No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Retl No Rel No Ret No Ret No Ret No Ret <LLD Sb- 125 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 Ret <LLD Sb-126 Ci No Rel 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 <LLD Te-123m Co 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 No Ret No Ret No Ret 'LD Te-132 Cl No Ret No Ret No Ret No Ret No Rel No Ret No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel 'LD Cs-1 34 CI No Rel 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 Ret <LLD Cs-137 CI No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Ret <LLD Cs-138 a No Rel No Ret No Ret No Ret 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 Ba-140 Ci No Ret 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 'LLD La-1 40 Cl No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No No oR No Ret No Ret No Ret No Ret No Relt- No Ret <LLD Ce-1 41 Ci No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Not No Re e No Ret No Ret No Ret No Ret No Rie 'LID Ce-i 44 ci No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Not No Ret e No Ret No Ret No Rie No Ret No Ret- LID Pr-144 Co No Rel No Rel No Ret No Ret No Ret No Ret No Ret I No Ret No Re N R No Rel No Ret No Ret No Ret No Ret No Ret 'LID B. Iodines j-132 CI No Ret No Ret I No Relt No Ret No Rei No Ret No Ret l No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret <LLD

_1-133 l Cil No Ret No Ret No Rel No Ret No Ret No Ret No Ret No Rel No Ret No Rel No Ret No Rel No Ret No Ret No Ret No Ret l LLD

_______ l_ Cl l No Ret No Rel No Ret No Rel No Rel No Rel No Ret No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Rel No Ret I LID 1_135 l Cl No Ret No Ret No Ret I No Ret No Ret No Ret No Rel No Ret No Ret No Ret No Ret No Rel No Ret No Relt No Ret No Ret l LLD C. Trittum

[1. Total Release ActMty GCI No Rel No Rei No Re No Rel No Ret No Ret No Rel No Rel No Ret No Re No Reli No Rel No Rel No Rel No Re No Ret <'LLD D. Dissolved and EntraIned Gases Ar-41 CI No Rel No Rel No R No Re Ri No R No R Re No RRi Rl No RRi No R No R Rl No RRl Re No Rel No Re No Rel R NoRi NoRel l LLD Kr-85 Ci GI No Ret No Ret No Rel No Rel No Ret l No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret l LLD Xe-131rm I3 CI No Rel No Ret No Ret No Ret No Ret l No Ret No Ret No Ret No Ret No Ret i No Ret No Ret No Ret No Ret No Ret No Ret l LLD Xe-1 33 l Ci No Rel 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 No Ret <LD Xe-133m CI G No Ret No Ret No lReNo Ret No Ret No Ret No Rel No Ret No Ret -NoRet l No Ret No Ret No Ret No Rel No Ret No Ret l LLD lXe-135 CI No Ret No Rel No Ret No Rel No Rel l No Ret No Ret No Rel No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Rel 'LD

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

CONTINUOUS MODE I Units Jan Feb I Mar 1st Qtr i Apr I Mav Jun I 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 C1 No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel l LD Cr-51 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Mn-54 Ci No Rel No Rel No Rel No Rel No ReN No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Co-57 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Fe-55 Ci No Rel No Rel No Rel No Ret <LLD Fe-59 Ci No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Co-58 Ci No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret <LLD Co-60 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Zn-65 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Sr-85 C4 No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LD Rb-88 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Sr-89 Ci . No Rel No Rel No Rel No Rel <LLD Sr-90 Cl No Rel No Rel No Rel No Rel <LLD Sr-92 Ci No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel <LLD Nb-95 Ci No Ret No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Zr-9S i No Ret No Ret 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 Ret No Ret <LID Zr-97 Ci No Rel No Rel N No t N No t NNoNot t_ No NNo NR No t N t Rl Ret No Rel <LLD Mo-99 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel <LLD Tc-99m Ci No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Ru-tO3 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel <LLD Ag-101Dm Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Sn-113 - Ci No Ret No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Sn-t1m Ci No Rel No Rel No Rel No Ret No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LD Sb- 122 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Sb-124; Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LD Sb-125 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Sb-126 Ci No Rel No Rel No Ret No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Te-123m Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel <LLD Te-132 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel CLLD Cs-134 Ci No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Cs-137 Ci No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel <LLD Cs-138 Ci No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel NoRel No Rel No Rel No Rel No Ret No Rel <LLD Ba-140 Ci No Ret No Rel No Rel No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD La-140 Ci No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel. No Rel <LLD Ce-140 Ci No Rel No Rel No Rel No Ret No Rel No Rel No Ret No Rel No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Ret <LLD Ce-144 Ci No Ret No Rel No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel <LLD Pr-144 Cic No Re No Ret No Ret No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Rel No Ret <LLD B. Iodines 1-131 Ci No Rel No Rel No Ret I No Rel I No Rel No Rel No Rel No Rel I No Rel I NoRetl NoRetI Re Ret I No Ret NoRet No Rel I No Rel <LD 1-13 Cii No Ret No Ret No Ret: No Re No

o Ret No Ret l oe!N e oRt N e oRt N~t N~t-N~t N~t- <I I1-i3 Ci l NoRelt NoRelt NoRelt NoRelt NoRel NoRet NoRei NoRel I NoRel j NoRelt NoRelt NoRel j NoRet NoRel NoRel l NoRel l LID I l1-13i Ci j No Ret No Ret No Ret No Ret I No Ret No Ret No Ret No Ret I No Ret No Ret No Ret No Ret I No Ret No Ret No Ret No Ret I <LLD I 115lCi l No Ret No Ret No Ret l No Ret No Ret No Ret No Ret No Ret l No Ret l No Ret No Ret No Ret l No Ret No Ret No Ret No Ret l LID C. Trittum l1.TotaltRelease ACtMt l a lNo Rel lNo Rell No Ret l No Ret l No Rel l No Relt No Rel l No Rel [ No Rel [ No Rel lINoRel No Ret l No Rel l No Rel l No Rel l NoRet l <LID I D. Dlssolved and Entrained Gases 1X-134 leli N oe No Rel Nol l N

[Ar41Ci o et o et o et o et o et o et o et o et No Ret [ No Ret No Ret No Ret No Ret No Ret No Ret No Ret <LID I lKr-85 ICi NoRl No Retl No Ret J No Ret lNo Ret NoRe No Ret No _e oRt N e oRt-N e N e oRt N e oRt <

lXe131m Ci lNo 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 Ret l <LLD l Xe-i31 Ci No Ret No Ret No Retl No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret No Ret Nooe Ret No Ret No Ret <LID X13 Kr-5 Ci{Nt C NoRel N~t No el Noe o Rl N oeRe N oe NoRel

-e oRl Nle N e NoRet N e Noe oRl NoRel N Re) Noe No Re_ No

_No_ Ret NoRe__No l Rel_ Re_ NoRel No ReI N No__Re Rel

<LLD Xe-133m Ci No Rel No Re No Re No R No Ret No Ret N R

SA'-

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 0f 0 6 2 8 Releases

,- I I <.1-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 0 0 0 0 0 Releases

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2003 UNIT 1 & 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 1.5 3 Organ 5 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 10CFR20.

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 0 0 6 2 8 Releases

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 LLD (uCi/ml)

Alpha 1.OOE-07 H-3 1.OOE-05 Kr-85 1.OOE-05 Mn-54 5.OOE-07 Fe-55 1.OOE-06 Co-58 5.OOE-07 Fe-59 5.OOE-07 Co-60 5.OOE-07 Zn-65 5.OOE-07 Sr-89 5.OOE-08 Sr-90 5.OOE-08 Mo-99 5.OOE-07 Cs-1 34 5.OOE-07 Cs-137 5.OOE-07 Ce-141 5.00E-07 Ce-144 5.00E-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& 2 (Docket Numbers 50-295 & 50-304)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of waste and 2. Estimate of maJor nuclide composition

a. Spent resins, filter sludges, evaporator bottoms, etc.

Waste Volume Activity Estim. Error Waste Volume Activity Estim. Error Waste Volume Actvty Estim. Error Waste Volume Acivity Estim. Error Class (m) (Ci) In Activity Class (m) (Ci) in Activy Class (m) (Co In Acthl" Class (m) (Cl) In Activity A O.OOE+00 O.OOE+0O 2.50E+01% B O.OOE+00 O.OOE+00 2.50E+01% C 0.00+00 O.OOE+OO 2.50E+01% All O.OOE+00 O.OOE+00 2.50E+01%

Nuclide Percent Acitlty Nuclide Percent Acivly Nucilde Percent Activity Nuclide Percent ActIvity Name Abundance (Cl) Name Abundance (Ci) Name Abundance (CD) Name Abundance (Ci)

H-3 0.OOE+00% O.OOE+00 H-3 0.00E+00% O.OOE+00 H-3 O.00E+00% O.OOE+00 H-3 O.00E+00% O.OOE+00 C-14 0.00E+00% 0.002+00 C-14 O.00E+00% O.00E+00 C-14 0.002+00% 0.002+00 C-14 0.002+00% 0.002+00 Cr-51 O.OOE+00% 0.OOE+00 Cr-51 0.00E+00% O.00E+00 Cr-51 O.00E+00% O.0E+00 Cr-S1 O.00E+00%OO.0E+00 Mn-54 0.00E+00%A O.OOE+00 Mn-54 O.00E+00% O.00E+00 Mn-54 O.00E+00% 0.002+00 Mn-54 O.0E+00% O.0E+00 Fe-55 O.OOE+00% O.OOE+00 Fe-55 O.00E+00% O.00E+00 Fe-55 0.002+00% 0.002+00 Fe-55 O.00E+00% O.OOE+00 Fe-59 O.OOE+00% O.OOE+00 Fe-59 O.00E+00% O.00E+00 Fe-S9 O.00E+00% O.00E+00 Fe-59 0.00E+00% O.0E+00 Co-57 0.OOE+00 O.OOE+00 Co-57 O.00E+00% O.00E+00 Co-57 O.0E+00% O.00E+00 Co-57 0.00E+00% O.0E+00 Co-58 O.OOE+00% O.OOE+00 Co-58 O.OOE+00% O.00E+00 Co-58 O.0E+00%/ O.0E+00 Co-58 0.002+00% 0.002+00 Co-60 0.00E+00%/ O.OOE+00 Co-40 O.00E+00% 0.002+00 Co-O0 O.0E+00% O.0E+00 Co-0 O.0E+00% O.00E+00 NI-59 O.OOE+00% O.OOE+00 Ni-59 O.0E+00% O.00E+00 NI-59 O.0E+00% O.OOE+00 NI-S59 O.0E+00% 0.OOE+00 N1-43 O.OOE+00% O.OOE+00 NI-63 0.00E+00% O.00E+00 NI-63 O.0E+00% O.00E+00 NI-63 0.00E+006 0.002+00 Sr-89 O.OOE+00%/9 O.OOE+00 Sr-O9 0.00E+00% O.0E+00 Sr-O9 O.0E+00% O.0E+00 Sr-49 O.0E+00% O.00E+00 Sr-90 0.00E+2400 0.00E+00 Sr-90 O.00E+00% 0.00E+00 Sr-90 O.OOE+00% 0.002+00 Sr-90 O.00E+00% 0.002+00 Zr-95 0.00E+00%/ O.0E+00 Zr-95 0.00E+00% O.00E+00 Zr-95 0.00E+00% O.OOE+00 Zr-95 O.00E+00% O.00E+00 Nb-95 O.0E+00% 0.002+00 Nb-95 0.00E+00% O.00E+00 Nb-9S 0.00E+00% O.00E+00 Nb-95 O.0E+00% O.00E+00 Tc-99 0.00E+00 0.00W2+00 Tc-99 O.00E+00% O.00E+00 Tc-99 O.00E+00% O.00E+00 Tc-99 O.OOE+00% O.0E+00 Ag-1i IOmO.0E+00% O.W0E+00 Ag-110m O.00E+00% O.W0E+00 Ag-1itOm O.OOE+00% O.W0E+00 Ag-110rn O.0E+00% O.00E+00 Sn-113 O.W0E+00% 0.002+00 Sn-113 O.00E+00% 0.002+00 Sn-113 O.00E+00% 0.002+00 Sn-113 0.00E+00% O.00E+00 Sb-125 0.002+00% O.00E+00 Sb-125 O.00E+00% 0.002+00 Sb-125 O.00E+00% O.00E+00 Sb-125 0.00E+0W0 O.0E+00 1-129 .00E+00%A O.0E+00 1-129 O.00E+00% 0.002+00 1-129 0.00E+00% 0.002+00 1-129 O.00E+00% O.0E+00 Cs-134 O.W0E+00% 0.00E+00 Cs-134 0.00E+00% O.00E+00 Cs-134 0.002+00% O.00E+00 Cs-134 O.OOE+00% O.00E+00 Cs-137 0.002+00%h O.0E+00 Cs-137 0.00E+00% O.OOE+00 Cs-137 O.OOE+00% 0.002+00 Cs-137 0.00E+00% O.0E+00 Ce-144 O.0E+% 0.002+00 Ce-144 O.00E+00% 0.002+00 Ce-144 O.00E+00% O.00E+00 Ce-144 0.002+00% O.0E+00 Pu-238 O.OOE+00% O.00E+00 Pu-238 O.OOE+00% O.00E+00 Pu-238 0.002+00% 0.002+00 Pu-238 O.0E+00% 0.002+00 Pu-239 O.00E+00% O.OOE+00 Pu-239 0.00E+00% O.00E+00 Pu-239 O.00E+00% O.00E+00 Pu-239 O.0E+00% O.0E+00 Pu-241 O.00E+00% O.00E+00 Pu-241 O.00E+00% O.00E+00 Pu-241 0.002+00% O.00E+00 Pu-241 0.002E+00 0.002+00 Pu-242 O.00E+00% O.00E+00 Pu-242 O.00E+00% O.00E+00 Pu-242 O.0E+00% 0.002+00 Pu-242 O.0E+00% 0.002+00 Am,-241 O.00E+00% 0.002+00 Arm-241 O.00E+00% O.00E+00 Am-241 O.00E+00% O.0E+00 Am-241 O.00E+00% O.00E+00 Cm-242 O.00E+00% 0.002+00 Cm-242 O.00E+00% 0.002+00 Cm-242 0.00E+00% O.0E+00 Cm-242 0.002+00% O.0E+00 Cm-243 0.00E+00% O.OOE+00 Cm-243 O.00E+00% O.00E+00 Cm-243 O.00E+00% O.0E+00 Cm-243 O.00E+00% O.0E+00 Zn-95 O.OOE+00% 0.00E+00 Zn-95 0.00E+00/ O.W0E+00 Zn-95 0.002+00% 0.00E+00 Zn-95 0QWE+00% .00E+00

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

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated fuel)

1. Type of waste and 2. Estimate of major nudide composition

b. Dry compressible waste, contaminated equipment. etc.

Waste Volume Activity Estim. Error Waste Volume Actity Estim. Error Waste Volume AcIt"y Estim. Error Waste Volume Activity Estim. Error 3 3 Class (m ) (Cl) in Ac ivit Class (m ) (Co) In Activity Class (m) (CO in Act" Class (m) (Cl) In Activity A O.OOE+00 O.OOE+00 2.501+01% B O.OOE+00 O.OOE+00 O.OOE+00% C O.OOE+00 O.OOE+00 O.OOE+00% All O.OOE+00 O.OOE+00 2.50E+01%

Nuclide Percent Activity Nucidre Percent Activity Nuclide Percent Activity Nuclide Percent Actvity Name Abundance (CI) Name Abundance (Cl) Name Abundance (Ci) Name Abundance (CD)

H-3 O.OOE+00% O.OOE+00 H-3 O.OOE+00% O.OOE+00 H-3 0.00E+00% O.OOE+00 H-3 O.OOE+00% O.OOE+00 C-14 0.OOE+00°h O.OOE+00 C-14 0.OOE+00% O.OOE+00 C-14 0.002+00% O.OOE+00 C-14 O.00E+00% 0.00E+00 Cr-51 O.OOE+00% 0.00E+00 4 Cr-51 O.OOE+00% O.OOE+00 Cr-51 0.00E+00 h O.OOE+00 Cr-51 O.OOE+00%h O.OOE+00 Mn-54 0.OOE+00°h 0.00E+00 Mn-54 0.OOE+00% 0.OOE+00 Mn-54 O.OOE+00% 0.002+00 Mn-54 O.OOE+00% O.OOE+00 Fe-55 0.00E+00% 0.00E+00 Fe-55 O.OOE+00% 0.00E+00 Fe-55 O.OOE+00% 0.00E+00 Fe-55 O.OOE+00°h O.OOE+00 Fe-59 O.OOE+00% 0.00E+00 Fe-59 0.OOE+00% O.OOE+O0 Fe-59 0.002+00% O.OOE+00 Fe-59 O.OOE+00% O.OOE+00 Co-57 0.00E+00%/ O.OOE+00 Co-57 O.OOE+00% 0.OOE+O0 Co-57 0.OOE+00% 0.00E+00 Co-57 O.OOE+00% O.OOE+00 Co-58 O.OOE+00% O.OOE+00 Co-58 O.OOE+00% O.OOE+00 Co-58 O.OOE+00% 0.00E+00 Co-58 0.002+00% 0.002+00 Co-40 O.OOE+00% 0.00E+00 Co-60 O.OOE+00% O.OOE+00 Co-60 O.OOE+00% 0.00E+00 Co-60 O.0E+00% o.00E+00 NI-59 0.00E+00% O.OOE+00 NI-59 0.OOE+00% O.OOE+00 NI-59 O.OOE+00% O.OOE+00 NI-59 0.002+00% 0.00E+00 Ni463 0.OOE+00% 0.00E+00 NI-63 O.OOE+00% O.OOE+00 NI-63 O.OOE+00% 0.00E+00 NI-63 O.0E+00% O.OOE+00 Sr-89 0.OOE+00°h 0.00E+00 Sr-89 0.00E+00% O.OOE+00 Sr-89 0.OOE+00% 0.002+00 Sr-89 0.002+00% O.OOE+00 Sr-90 0.00E+0Oh O.OOE+00 Sr-90 O.OOE+00% O.OOE+00 Sr-90 O.OOE+00% O.OOE+00 Sr-90 0.00E+00% O.OOE+00 Zr-95 O.OOE+00% 0.OOE+00 Zr-95 O.OOE+00% O.OOE+00 Zr-95 0.002+00% O.OOE+00 Zr-95 O.00E+00% 0.002+00 Nb-95 0Q00E+00° O.OOE+OO Nb-95 O.OOE+00% 0.00E+00 Nb-95 O.OOE+00% 0.00E+00 Nb-95 O.00E+00% O.00E+00 Tc-99 0.00E+00% .OOE+00 Tc-99 O.0OE+00% O.OOE+00 Tc-99 0.00E+00h 0.002E+00 Tc-99 O.0E+00% 0.002+00 Ag-110m Q.OOE+00% 0.00E+00 Ag-1 10m 0.00E+00°h 0.00E+00 Ag-110m O.OOE+00% O.OOE+00 Ag-110m O.W0E+00% .2ooE+00 Sn-113 O.OOE+00h Q.OOE+O0 Sn-113 O.OOE+00% O.OOE+00 Sn-113 O.OOE+00%h O.OOE+00 Sn-113 O.0E+00% 0.002+00 Sb-125 O.0XE+00% o.OOE+00 Sb-125 O.0OE+00% O.OOE+00 Sb-125 0.002+00% 0.00E+00 Sb-125 0.002+00% O.OOE+00 1-129 0.00E+00% 0.OOE+00 1-129 0.002+00% O.OOE+00 1-129 O.OOE+00% O.OOE+00 1-129 O.W0E+00% O.OOE+00 Cs-134 0.002+00% 0.OOE+00 Cs-134 O.OOE+00% 0.002+00 Cs-134 0.002+00%h 0.00E+00 Cs-134 O.0E+00% O.0E+00 Cs-137 o.OOE+00% 0.00E+00 Cs-137 O.OE+00%O0.00E+00 Cs-137 O.OOE+00% 0.00E+00 Cs-137 0.002+00% O.OOE+00 Ce-144 O.OOE+00% 0.002+00 Ce-144 O.OOE+OO O.OOE+00 Ce-144 0.002+00% 0.00E+00 Ce-14 0.002E+00 O.02E+00 Pu-238 O.OOE+00% 0.00E+00 Pu-238 O.OOE+00% O.OOE+00 Pu-238 0.00E+00°h O.OOE+00 Pu-238 O.0E+00% O.0E+00 Pu-239 O.OOE+00% 0.OOE+00 Pu-239 0.002+00% O.OOE+00 Pu-239 O.OOE+00% 0.00E+00 Pu-239 O.0E+00% O.00E+00 Pu-241 0.00E+00% 0.00E+00 Pu-241 O.OOE+00% 0.002+00 Pu-241 O.OOE+00% O.OOE+00 Pu-241 0.00E+00% O.OOE+00 Pu-242 0.OOE+00% 0.00E+00 Pu-242 0.00E+00% O.OOE+00 Pu-242 O.OOE+00% O.OOE+00 Pu-242 O.00E+00% 0.002+00 Am-241 0.OOE+00°h 0.00E+00 Am-241 O.OOE+00% O.OOE+00 Amn-241 0.002+00% O.OOE+00 Am-241 O.00E+00% 0.002+00 Cm-242 O.OOE+00% 0.00E+00 Cm-242 O.OOE+00% O.OOE+00 Cm-242 0.002+00% O.OOE+00 Cm-242 O.00E+00% 0.002+00 Cm-243 O.OOE+00% 0.OOE+00 Cm-243 0.002+00% O.OOE+00 Crn-243 O.OOE+00% O.OOE+00 Cm-243 0.00E+00% O.OOE+00 Zn-95 O.OOE+OO 0.OOE+00 Zn-95 O.OOE+00% Q.OOE+00 Zn-95 O.OOE+00% 0.00E+00 Zn-95 O.00E+00% 0.002+00

ZION NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT REPORT FOR 2003 UNIT 1 8 2 (Docket Numbers 50-295 & 50-304)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated fuel)

1. Type of waste and 2. Estimate of major nuclide composition

c. Irradiated components, control rods, etc.

No Irradiated component shipments were performed during 2003.

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

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 0 N/A N/A B. IRRADIATED FUEL SHIPMENTS No irradiated fuel shipments were performed during 2003.

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

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Radioactive Waste Shipments for 2003 Shipment Shipment Waste Container Solidification Activity Volume Date Number Media Receiver Class Type Agent (Ci) (M3) (ft3) 1st Quarter Sub totals: 0 0.0000000 0.000 0.00 2nd Quarter Sub totals: 0 0.0000000 0.000 0.00 3rd Quarter Sub totals: 0 0.0000000 0.000 0.00 4th Quarter Sub totals: 0 0.0000000 0.000 0.00 Totals: 0 0.0000000 0.000 0.00 Class A Class B Class C Number of Shipments 3 1 0 0 Activity (Ci) 0.00E+00 0.OOE+00 I0.OOE+00 Volume (M3 ) 0.00E+00 0.OOE+00 0.OOE+00

Zion Nuclear Station Period of Record: January - March 2003 Stability Class - Extremely Unstable - 250Ft-33Ft Delta-T (F)

Winds Measured at: 35 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 2 2 0 0 .4 NNE 0 0 13 3 0 0 16 NE 0 0 3 5 0 0 8 ENE 0 0 0 .0 0 0 0 E 0 0 2 0 0 0 2 ESE 0 1 2 0 0 0 3 SE 0 1. 3 0 0 0 4 SSE 0 1 0 0 0 0 1 S 0 0 0 0 0 *0 0 SSW 0 0 2 1 0 0 3 SW 0 0 2 2 0 0 4 WSW 0 0 3 4 0 0 7 W 0 0 11 3 0 0 14 WNW 0 1 5 3 0 0 9 NW 0 0 5 0 0 0 5 NNW 0 0 0 1 .0 0 1 Variable 0 0 0 0 0 0 0 Total 0 4 53 24 0 0 .81 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0

Zion Nuclear Station Period of Record: January - March 2003 Stability Class - Moderately Unstable - 25OFt-33Ft Delta-T (F)

Winds Measured at 35 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-122 13-18 19-24 > 24 Total N 0 0 2 0 0 0 2 NNE 0 1 1 0 0 0 2 NE 0 0 1 0 0 0 1 ENE 0 1 0 0 0 0 1 E 0 2 0 0 0 0 2 ESE 0 0 1 0 0 0 1 SE 0 0 2 0 0 0 *2 SSE 0 1. .3 0 0 0 4 S 0 0 2 . 0 0 0 .2 SSW 0 0 3 0 0 0 3 SW 0 0 2 3 0 0 5 WSW 0 1 5 3 0 0 9 W 0 0 9 4 0 0 13 WNW 0 1 9 1 0 0 11 NW 0 0 11 1 0 0 12 NNW 0 0 1 1 0 0 2 Variable 0 0 0 0 0 0 0 Total 0 7 52 13 0 0 72 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0

Zion Nuclear Station Period of Record: January - March 2003 Stability Class - Slightly.Unstable - 25OFt-33Ft Delta-T (F)

Winds Measured at. 35 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24. Total N 0 0 2 0 0 0 2 NNE 0 4 2 1 0 0 7 NE 0 0 1 6 0 . 0 7 ENE 0 2 0 0 0 0 2 E . 0 4 1 0 0 0 5 ESE 0 2 2 0 0 0 4 SE 0 3 2 0 0 0 -5 SSE 0 1 . 1 0 0 0 2 S 0 0 1 0 0 0 1 SSW 0 0 1 1 0 0 *2 SW 0 1 10 4 0 0 15 WSW 0 2 4 4 0 0 10 W 0 1 9 5 0 0 15 WNW 0 4 15 5 0 0 24 NW 0 3 16 1 0. 0 20 NNW 0 1 7 2 0 0 10 Variable 0 0 0 0 0 0. 0 Total 0 28 74 29 0 0 131 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0

Zion Nuclear Station Period of Record: January - March 2003 Stability Class - Neutral - 250Ft-33Ft Delta-T (F)

Winds Measured at 35 Feet Wind-Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 8 13 19 10 54 NNE 22 37 10 0 71 NE 4 15 43 10 74 ENE 5 5 8 4 22 E 19 2 0 0 11 ESE 6 3 0 0 11 SE 8 2 0 0 10 SSE 17 17 0 35 S 15 14 1 0 *32 SSW 15 17 2 0* 35 SW 18 37 18 1 75 WSW 17 55 22 0 95 W 25 25 10 0 61 WNW 18 52 19 0 97 NW 40 75 7 0 124 NNW 10 55 15 0 81 Variable 0 0* 0 0 0 Total 25 . 237 424 175 25 2 888 Hours of calm in this stability class:. 0 Hours of missing wind measurements in this stability. class: 0 Hours of missing stability measurements in all stability classes: '0

Zion Nuclear Station Period of Record: January - March 2003 Stability Class - Slightly Stable - 250Ft-33Ft Delta-T (F)

Winds Measured at 35 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 2 22 1 0 0 26 NNE 1 6 8 2 0. 0 17 NE 1 2 2 3 0 0 8 ENE 0 5 4 0 0 0 9 E 3 4 3 3 0 0 13 ESE 6 10 .4 1 0 0 21 SE 3 14 2 0 0 0 19 SSE 1 10 10 3 0 0 24 S 3 23 11 0 0 0 37 SSW 4 22 11 1 0 0 38 SW 7 37 23 21 0 0 88 WSW 13 29 33 3 0 0 78 W 5 37 56 11 0 0 109 WNW 12 51 48 4 0 0 115 NW 8 50 15 4 0 0 77 NNW 3 12 11 1 0 0 27 Variable 0 0 0 0 0 0 0 Total 71 314 263 58 0 0 706 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0

Zion Nuclear Station Period of Record: January - March 2003 Stability Class - Moderately Stable - 250Ft-33Ft Delta-T (F).

Winds Measured at 35 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12. 13-18 19-24 > 24 Total N 0 3 0 0 0 0 3 NNE 1 0 1 0 0 0 2 NE 0 1 0 0 0 0 1 ENE 1 0 0 0 0 0 1 E 1 1 0 0 0 0. 2 ESE 0 2 0 0 0 0 . 2 SE 0 5 1 0 0 0 6 SSE 0 5 8 0 0 0 13 S 2 14 0 0 0 0 16 SSW 2 7 1 0 0 0 10 SW 6 4 1 0 0 0 11 WSW 11 7 0 0 0 0 18 W 7 11 0 0 0 0 18 WNW 7 8 0 . 0 0 0 15 NW 0 8 0 0 0 0 8 NNW 2 0 0 0 0 0 2 Variable 0 0 0 0 0 0 0 Total 40 76 12 0 0 0 .128 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0

Zion Nuclear Station.

Period of Record: January - March 2003 Stability Class - Extremely Stable. - 250Ft-33Ft Delta-T (F)

Winds Measured at 35 Feet Wind Speed (in mph)*

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 1 0 0 0 0 3 NNE 0 0 0 0 O0 0

0 NE 0 1 0 0O 0 1 0

ENE 1 1 1 0 0 3 0

E 1 1 1 0 0 3 0

ESE 0 0 0 0 0 0 0

SE 0 1 1 0 0 -2 0

SSE 4 16 12 0 0 32 0

S 6 35 3 0 0 44 00 SSW 4 2 0 0 0 6 0

SW 3 1 0.- 0 0 4 0

WSW 4 7 0 0 0 11

. 0 W 2 14 0 0 16 0

WNW 1 11 0 0 0 12 0

NW 0 2 0 0 2 0* 0 NNW 0 1 0 0 1 0

Variable 0 0 .0 0 0 0 Total 28 94 *18 0 0 0 140 Hours of calm in this stability class: 0 Hours of missing wind measurements in.this stability class: 0 Hours of missing stability measurements in all stability classes:

Zion Nuclear Station Period of Record: January - March 2003 Stability Class - Extremely Unstable - 250Ft-33Ft Delta-T (F).

Winds Measured at 250 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N o 0 4 0 .7 NNE 0- 8 4 0 17 NE o 0 3.. 1 4 ENE 0 0 0 0 0 E 0 1. 0 2 ESE 1 1 0 0 2 SE 0 4 0 0 6 SSE 0 0 0 0 0 S 0. 0 *0' 0 .0 SSW 0 0 0 .4 SW 0 0 2 0 4 WSW 0 1 2 1 6 W 0 4 3 0 15 WNW 0 2 *2 1 8 NW 0 1 1 0 6 NNW 0 0 0 0 0 Variable 0 0 0 0 0 Total 0 1 22 33 22 3 81 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: . 0 Hours of missing stability measurements in all stability classes: 2

Zion Nuclear Station Period of Record: January - March 2003 Stability Class - Moderately Unstable - 25OFt-33Ft Delta-T (F)

Winds Measured at 250 Feet Wind Speed (in mph)'

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 2 0 0 2 NNE 0 1 0 0 1 0 2 NE 0 0 .1 0 0 0 .1 ENE 0 2 0 0 0 0 2 E 0 0 1 0 0 0 1 ESE 0 0 0 0 0 0 0 SE 0 1 3 1 0 0 .5 SSE 0 0 0 1 1 0 2 S 0 0 0 1 1 0 2 SSW 0 0 0 3 0 0. 3 SW 0 0 . 1 1 3 0 5 WSW 0 1 2 3 2 2 10 W 0 0 3 7 3. 0 13 WNW 0 0 2 8 0 1 11 NW 0 0 3 7 2 0 12 NNW 0 0 0 1 1 0 2 Variable 0 0 0 0 0 0 0 Total 0 5 16 35 14 3 73 Hours of calm in this stability class: 0.

Hours of missing wind measurements in this stability class: 0 Hours of-missing stability measurements in all stability classes: 2

Zion Nuclear Station Period of Record: January - March 2003 Stability Class - Slightly Unstable - 250Ft-33Ft Delta-T (F)

Winds Measured at 250 Feet-Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 1 1 0 2 NNE 0 0 .4 1 1 0 6 NE 0 0 0 1 0 6 7 ENE 0 3 0 0 0 0 3 E 0 3 1 .0 0 0 4 ESE 0 2 1 0 0 .0 3 SE 0 2 7 0 0 0 9 SSE 0 0 0 0 0 0 .0 S 0 0 0 2 0 0 2 SSW 0 0 0 3 1 0 . 4 SW 0 1 0 7 4 0 12 WSW 0 0 4 2 4 1 11 W 0 0 3 7 4 0 14 WNW . 0 1 7 13 3 3 27 NW 0 0 7 9 1 0 17 NNW 0 0 1 7 2 0 10 Variable 0 0 . 0 0 0 0 0 Total 0 12 35 53 . 21 10 131 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 2

Zion Nuclear Station Period of Record: January - March 2003 Stability Class - Neutral . . 250Ft-33Ft Delta-T (F)

Winds Measured at 250 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 3 6 7 5 28 50 NNE 1 2 18 22 26 9 78 NE 0 4 4 15 20 31 74 ENE 0 2 3 7 7 0 19 E 0 0 4 3 0 0 7 ESE 0 3 1 1 0 0 5 SE 0 5 16 2 0 0 23 SSE 0 3 16 15 0 0 34 S 0 2 8 14 6 0 30 SSW 1 3 14 15 2 0 35 SW 0 2 16 35 22 2 77 WSW 0 7 19 42 19 10 97 W 2 5 23 20 11 1 62 WNW 0 8 20. 35 20 11 94 NW 1 3 29 67 21 1 122 NNW 1 4 15 41 20 1 82 Variable 0 0 0 0 0 0 0 Total 7 56 212 341 179 94 889 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes:. 2

Zion Nuclear Station Period of Record: January - March 2003 Stability Class - Slightly Stable - 250Ft-33Ft Delta-T (F)

Winds Measured at 250 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 0. 3 3 9 1 17 NNE 0 1 3 6 9 2 .21 NE 1 0 3 4 5 1 14 ENE 0 6 2 2 2 0 12 E 0 2 4 2 3 3 14 ESE 0 6 9 4 4 0 23 SE 0 0 9 5 2 0 16 SSE 0 0 7 12 1 4 24 S 0 2 14 14 4 0 34 SSW 1 3 12 14 5 0 35 SW 0 5 29 25 25 5 89 WSW 1 8 20 27 22 1 79 W 0 8 15 47 -26 9 105 WNW 0 4 27 61 18 4 114 NW 0 4 31 39 6 2 82 NNW 1 3 14 16 2 0 36 Variable 0 0 0 0 0 0 0 Total 5 52 202 281 143 32 715 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 2

Zion Nuclear Station Period of Record: January - March. 2003 Stability Class - Moderately Stable - 250Ft-33Ft Delta-T (F)*

Winds Measured at 250 Feet.

Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 1 3 0 0 0 4 NNE 0 1 0 1 0 0 2 NE 0 1 0 0 0 0 .

ENE 0 0 1 0 0 0 1 E 2 0 1 0 0 0 3.

ESE 0 . 2 1 . 3 . 1 . 0 7 SE 1 0 1 0 0 0 2 SSE 1 1 4 9 5 0 20 S 0 3 7 3 0 0 13 SSW 0 2 8 8 2 0 20 SW 0 2 8 2 1 0 13 WSW 0 2 3 0 0 .0 5 W 1 2 5 2 0 0 10 WNW 0 3 2 2 0 0 7 NW 0 2 7 0 0 0 9 NNW 0 1 .7 3 0 0 11 Variable 0 0 0 0 0 0 0 Total 5 23 58 33 9 0 128 Hours of calm in this stability class: . 0 Hours of missing wind measurements in this stability class: 1 Hours of missing stability measurements in all stability classes: 2

Zion Nuclear Station' Period of Record: January - March 2003 Stability Class - Extremely Stable - 250Ft-33Ft Delta-T (F)

Winds Measured at 250 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total.

N 0 5 0 .0 0 0 5 NNE 0 2 0 0 0 0 2 NE 3 1 2 0 0: 0 6 ENE 2 1 0 0 0 0 3 E 2 1 0 0 2 0 5 ESE 0 0 0 0 2 0 2 SE 0 1 0 3 1 0 5 SSE 0 0 1 1 4 0 6 S 1 1 7 22 1 0 32 SSW 0 1 14 18 2 0 35 SW 1 1 10 3 .0 0. 15 WSW 0 2 3 1 0 0 6 W 0 2 1 0 0 0 3 WNW 1 0 0 1. 0 0 2 NW 2 0 0 2 0 0 4 NNW 4 3 1 1 0 0 9 Variable 0 0 0 0. 0 0 0.

Total 16 21 39 52 12 0 140 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 2

Zion Nuclear Station Period of Record: April - June 2003 Stability Class - Extremely Unstable. - 250Ft-33Ft Delta-T (F)

Winds Measured at 35 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 14 25 2 0 41 NNE 0 9 37 18 .0 0 64 NE 0 4 7 1 0 0 12 ENE 0 1 1 5 0 0 7 E 0 1 1 .0 0 0 2 ESE 0 0 .0 0 0 . 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 .0. 0 0 0 0 SSW 0 0 0 3 0 0 3 SW 0 0 3. 5 0 0 -8 WSW 0 0 5 2 0 0 7 W 0 0 2 2 0 0 4 WNW 0 0 9 0 0 *0 9 NW 0 1 6 0 0 0 7 NNW 0 0. 3 2 0 0 5 Variable 0 0 0 0 0 0 0 Total 0 16 88 63 2 0 169 Hours of calm in this stability class: 0 .

Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0

Zion Nuclear Station Period of Record: April - June 2003 Stability Class - Moderately Unstable - 250Ft-33Ft Delta-T (F)

Winds Measured at 35 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 8 6 0 14 NNE 16 0 0 21 NE 0. 1 0 8 ENE 0 *0

O *1 E .O-1 0 0 1 ESE 0 0 O 0

SE 0 0 0 *0 SSE 0 *0 0 0

.S 0 0 0 0 SSW 0 0 O 0

SW 1 2 0 3 WSW 0 1 0. 1 W 1 2 0 WNW 2 2 0 4 NW 2- 1 0 3 NNW 1~ 0 0 1 Variable 0 0 0 0 Total 0 15 32 15 0 62 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing.stability measurements in all stability classes: 0

Zion Nuclear Station Period of Record: April - June 2003 Stability Class - Slightly Unstable - 250Ft-33Ft Delta-T (F)

Winds Measured at 35 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18. 19-24 > 24 Total N 0 3 21 6 1 0 31 NNE 0 12 10 2 0 0 24 NE 0 8 0 0 0 0 8 ENE 0 1 0 0 0 . 0 1 E 0 2 0 1 0 0 3 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 . 0 0 0 SSE 0 0 1 0 0 0 1 S 0 0 0 0 0 0 0 SSW 0 0 0 3 0 0 3 SW 0 0 1 1 2 0 4 WSW 0 1 2 4 0 1 8 W 0 0 2 0 0 0 2 WNW 0 1 4 1 0 0 6 NW 0 0 2 4 0 0 6 NNW 0 0 2 0 0 0 2 Variable 0 0 0 0 0 0 0 Total 0 28 45 22 3 1 99 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0

Zion Nuclear Station Period of-Record: April - June .2003 Stability Class - Neutral. . - 250Ft-33Ft Delta-T (F)

Winds Measured at 35 Feet Wind Speed (in mph)..

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 25 79 34 4 .0 142 NNE 4 46 85 10 0 0 145 NE *2 32 14 28 4 0 . 80 ENE 1 18 1 7 15 0 42 E 0 10 2 1 0 0 13 ESE 0 5 0 0 0 0 5 SE 1 12 2 0 0 0 15 SSE 0 11 6 0 0 0 17 S 0 2 2 0 0 0 4 SSW 0 2 2 4 0 0 8 SW 0 2 12 5 4 0 23 WSW 1 8 21 4 12 0 46 W 2 8 8 3 2 0 23 WNW 1 6 3 7 0 0 17 NW 3 1 12 4 0 0 *20 NNW 1 6 *16 0 0 0

23 Variable 0 0 0 0 0 0 0 Total 16 194 265 107 41 0 .623 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability.classes: .0

Zion Nuclear Station Period of Record: April - June 2003 Stability Class - Slightly Stable. - 250Ft-33Ft Delta-T (F)

Winds Measured at 35 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 13 81 97 12 0 0 203 NNE 8 66 7 0 0 0 81 NE 8 38 2 0 0 0 48 ENE 0 15 3 0 0 0 18 E. 5 6 3 1 0 0 15 ESE 6 22 . .3 0 1 0 32 SE 8 23 9 0 0 0 40 SSE 6 26 16 0 0 0 48 S 9 18 5 1 0 0 33' SSW 4 8 6 6 0. 0 24 SW 3 7 6 11 0 0 27 WSW 3 22 10 2 0 0 37 W 2 22 4 0 0 0 28 WNW 9 9 4 3 0 0 25 NW 4 13 1 0 0 0 18 NNW 7 19 3 0 0 0 29 Variable 0 0 0 0 0 0 0 Total 95 395 179 36 1 0 706 Hours of calm in this stability class: 0 Hours of-missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0

Zion Nuclear Station Period of Record: April - June 2003 Stability Class - Moderately Stable - 250Ft-33Ft Delta-T (F)

Winds Measured at 35 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 7 19 0 0 0 0 26 NNE 8 5 0 0 0 0 13 NE 2 5 0 0 0 0 7 ENE 2 8 1 0 0 0 11 E 0 5 2 1 0 0 8 ESE 1 5 2. 0 0 0 8 SE 2 10 0 0 0 0 12 SSE 2 17 8 0 0 0 27 S 12 19 9 0 0 0 40 SSW 12 14 2 0 0 0 28 SW 8 5 1 0 0 0 14 WSW 6 10 0 0 0 0 16 W 3 6 0 0 0 0 9 WNW 6 7 0 0 0 0 13 NW 5 13 0 0 0 0 18 NNW 4 15 0 0 0 0 19 Variable 0 0 0 0. 0 0 0 Total 80 163 25 1 0 0 269 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0

Zion Nuclear Station Period of Record: April - June 2003 Stability Class - Extremely Stable - 250Ft-33Ft Delta-T (F)

Winds Measured at 35 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 3 0 0 0 0 5 NNE 2 2 1 0 0 0 5 NE 0 1 2 0 0 0 3 ENE 0 3 4 0 0 0 7 E 2 5 2 0 0 0 9 ESE 1 2 1 1 0. 0 5 SE 0 1 1 0 0 0 2 SSE 1 13 9 0 0 0 23 S 11 26 7 0 0 0 44 SSW 16 10 0 0 0 0 26 SW 23 11 0 0 0 0 34 WSW 12 7 0 0 0. 0 19 W 6 16 0 0 0 0 22 WNW 4 3 0 0 0 0 7 NW 1 3 0 0 0 0 4 NNW 4 0 0 . 0 0 0 .4 Variable 0 0 0 -0 0 0 0 Total 85 106 27 1 0 0 219 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0

Zion Nuclear Station Period of Record: April - June 2003 Stability Class - Extremely Unstable - 250Ft-33Ft Delta-T (F)

Winds Measured at 250 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 .8-12 13-18 19-24 > 24 Total N 0 1 . 5 21 23 22 72 NNE 0 3 23 3 3. 0 32 NE 0 1 10 0 1 0 12 ENE 0 1 1 2 3 0 7 E 0 1 0 0 0 0 1 ESE 0 0 0 0 0 .0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 2 0 1 .3 SW 0 0 0 3 4 2 9 WSW 0 0 0 3 3 0 6 W 0 0 1 6 3 0 10 WNW 0 0 1 3 0 0 4.

NW 0 0 1 6 2 0 .9 NNW 0 0 0 1 0 0. 1 Variable 0 0 . 0 0 0 . 0 0 Total 0 7 42 50 42 25 166 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 11 Hours of missing stability measurements in all stability classes: 2

Zion Nuclear Station Period of Record: April - June 2003 Stability Class - Moderately Unstable - 25OFt-33Ft .Delta-T (F)

Winds Measured at 250 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 1 1 16 7 4 29 NNE 0 1 4 2 0 0 7 NE 0 4 3 0 0 1 8 ENE 0 . 0 0 0 0 0 0 E 0 0 1 0 0 0 1 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 2 0. 1 3 WSW 0 0 0 0 1 0 1 W 0 0 2 1 0 2 -5 WNW 0 0 .0 2 0 1 3 NW 0 0 1 2 0 2 5 NNW 0 0 0 0 0 0 0 Variable 0 0 0 0 0 0 0 Total 0 6 12 25 8 11 62 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 2 Hours of missing stability measurements in all stability classes: 2

Zion Nuclear Station Period of Record: April - June 2003 Stability Class - Slightly Unstable - 250Ft-33Ft Delta-T (F)

Winds Measured at 250 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 9 19 9 42 NNE 5 11 2 0 18 NE 0 3 0 0 3 ENE 0 0 0 0 0 E 3 0 .0 1 4 ESE 0 0 0 0 0 SE 0 0 0 .0 0

. I SSE 0 0 0 1 S 0 0 0 0 0.

SSW 0 0 0 2 4 SW 0 0 1 1 5 WSW 1 1 1 3 6 W 0 0 2 0 2 WNW 0 2 4 0 7 NW 0 0 0 4 5 NNW 0 0 2 0 2 Variable 0 0 0 0 0 Total 9 26 31 21 12 99 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 2 Hours of missing stability measurements in all stability classes: 2

Zion Nuclear Station Period of Record: April - June 2003 Stability Class - Neutral - 250Ft-33Ft Delta-T (F)

Winds Measured at 250 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 7 25 68 44 24 168 NNE 2 13 34 .39 19 3 110 NE 1 14 8 7 10 17 57 ENE 0 8 .3 4 2 14 31 E . 0 7 3 2 0 0 12 ESE 0 4 0 0 0 0 4 SE 1 5 . 9 3 0 0 18 SSE 0 5 8 5 0 0 18 S 0 0 0 0 0 0 0 SSW 0 0 2 4 4 4 14 SW 1 2 1 10 4 6 24 WSW 0 1 7 24 7 11 50 W 0 1 2 5 2 3 13 WNW 0 4 3 5 5 1 18 NW 0 5 1 12 7 3 28 NNW 0 2 7 6 1 0 16 Variable 0 0 0 0 .0 0 0 Total 5 78 113 194 105 86 581 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 49 Hours of missing stability measurements in all stability classes: 2

Zion Nuclear Station Period of Record: April - June 2003 Stability Class - Slightly Stable - 250Ft-33Ft Delta-T (F).

Winds Measured at.250 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 5 26 79 50 11 173 NNE 0 17 41 33 0 0 91 NE 2 15 21 8 1 0 47 ENE 1 10 9 .4 1 1 26 E 1 3 8 1 1 2 16 ESE 0 11 13 3 1 3 31 SE 4 5 37 12 2 0 60 SSE 2 6 19. 15 5 1 48 S 1 2 4 4 2 0 13 SSW 1 1 5 9 8 4 28 SW 1 4 6 9 3 10 33 WSW 0 2 10 16 3 1 32 W 0 1. 11 13 1 0 26 WNW 2 3 3 6 2 1 17 NW 0 1 1 .14 1 2 19 NNW 1 3 *8 8 1 0 21 Variable 0 0 0 0 0 0- 0 Total 18 89 222 234 82 36 681 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 28 Hours of missing stability measurements in all stability classes: 2

Zion Nuclear Station Period of Record: April - June 2003 Stability Class - Moderately Stable - 250Ft-33Ft Delta-T (F)

Winds Measured at 250 Feet Wind Speed (in'mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 2 16 14 0 0 32 NNE 1 7 10 4 0 0 '22 NE 2 4 5 1 0 0 12 ENE .0 1 5 2 1 1 10 E 3 4 4 2 1 2 16 ESE 0 1 3 5 2 2. 13 SE 0 2 13 4 0 0 19 SSE 0 5 9 20 5 1 40 S 0 3 14 10 5 0 *32 SSW 0 0 7 9 2 0 18 SW 1 2 5 7 0 0 15 WSW 1 1 0 6 0 0 8 W 0 1 3 7 1 0 12 WNW 0 0 '3 1 0 0 4 NW 0 0 1 3 1 0 5 NNW 0 2 3 5 0 0 10 Variable 0 0 0 0 0 0 0 Total 8 35 101 100 18 6 268 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 5 Hours of missing stability measurements in all stability classes: .2

Zion Nuclear Station Period of Record: April - June 2003 Stability Class - Extremely Stable - 250Ft-33Ft Delta-T (F)

Winds Measured at 250 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 2 5 2 0 0 10 NNE 2 3 1 1 0 0 7 NE 1 2 0 1 0 0 4 ENE 0 3 1 1 3 1 9 E 1 0 0 1 . 0 1 3 ESE 0 3 . 0 1 1 3 . 8 SE 0 3 . 3 0 0 0 6 SSE 0 8 8 7 4 1 28 S 0 2 24 30 7 2 65 SSW 2 1 13 20 2 0 38 SW 0 1 7 8 1 0 17 WSW 0 2 4 2 1 0 9 W 0 1 2 4 1 0 8 WNW 1 0 1 2 0 0 4 NW 1 0 2 1 0 0 4 NNW 0 5 2 0 0 0. 7 Variable 0 0 0 0 0 0 0 Total 9 36 73 81 20 8 . 227 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class:. 1 Hours of missing stability measurements in all stability classes: 2

Zion Nuclear Station Period of Record:.October - December2003 Stability Class - Extremely Unstable - 250Ft-33Ft Delta-T (F)

Winds Measured at 35 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 . Total N 0 0 0 0 0 0 0 NNE 0 0 10 0 . 0 0 10 NE 0 0 6 0 0 0 6 ENE 0 . 1 1 0 0 0 2 E 0 3 0 0 0 0 3 ESE 0 3 0 0 0 0 3 SE 0 6 0 0 0 0 6 SSE 0 2 0 0 0 0 2 S 0 0 2 0 .0 0 2 SSW 0 0 0 0 0 0 0 SW 0 0 1 3 0 0 4 WSW 0 0 7 1 0 0 8 W 0 0 8 1 0 0 9 WNW 0 1 .4 1 0 0 6 NW 0 2 6 1 0 0 9 NNW 0 1 .1 0 0 0 2 Variable 0 0 0 0 0 0 0 Total 0 19 46 7 . 0 0 72 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0

Zion Nuclear Station Period of.Record: October - December2003 Stability Class - Moderately Unstable - 250Ft-33Ft Delta-T (F)

Winds Measured at 35 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 .19-24 > 24 Total

N 0 0 .0 0 NNE 0 4 2 *6 NE 0 0 0 .0 ENE 2 .0 0

2 E 1 0 1

.0 ESE 2 0 2 0

SE 0 0 0*

SSE 0 2 0 2 S 0 0 0 0 SSW 0 1 0 1 SW 0 3 0 3 WSW 1 6 2 9 W 1 4 2 .7 WNW 2 6 3 11 NW 2 4 0 6 NNW 0 1 1 2 Variable 0 0 0 0 Total 11 3.1 10 52 Hours of calm in this stability class: 0' Hours of missing wind measurements in this stability class: - 0 Hours of missing stability measurements in all stability classes: 0

Zion Nuclear Station Period of Record: October - December2003 Stability Class - Slightly Unstable - 25OFt-33Ft Delta-T (F)

Winds Measured at 35 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 2 0 0 0 3 NNE 2 4 0 0 0 6 NE 2 0 0 0 0 2 ENE 0 0 0 0 0 0 E 0 0 0 0 0 0 ESE 2 1 0 0 0 3 SE 3 0 1 0 *.0 4.

SSE 0 4 0 0 0 4 S 1 1 0 0 2 0

SSW 2 0 3 0 5 0

0o SW 0 3 2 0 5.-

0 WSW 1 .6 0 0 7 0

W 3 6 7 0 16 0

WNW 2 .9 4 0 15 0

NW 1 3 2 0 6 0

NNW 2 4 0 0 6 0

Variable 0 0 .0 0 0 0

Total 22 43 19 0 84 Hours of calm in this stability class: . 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0

Zion Nuclear Station Period of Record: October - December2003 Stability Class - Neutral - 250Ft-33Ft Delta-T (F)

Winds Measured at 35 Feet -

Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total

. N 13 7 4 0 28 NNE 19 18 7 0 46 NE 13 7 7 0 29 ENE 11 4 24 0 39 E 13 24 6 0 44 ESE 14 26 11 0 53 SE 2 10 3 0. 17 SSE 11 29 33 1 79 S 15 14 3 0 34 SSW 18 35 18 0 74 SW 14 32 40 0 88 WSW 24 44 19 0 88 W 32 36 22 0 97 WNW 31 39 15. 0 90 NW 12 57 9 .0 78 NNW 18 12 7 0 38 Variable .0 0 0 .0 0 Total 26 260 394 228 13 1 922 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0

Zion Nuclear Station Period of Record: October - December2003 Stability Class - Slightly Stable . - 250Ft-33Ft Delta-T (F)

Winds Measured at 35 Feet' Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 . 19-24 > 24 Total N 3 4 7 .2 0 16 NNE 3 5 6 0 0 14 NE 4 8 2 0 0 14 ENE 1 7 2 0 0 10 E 2 4 . 4 0 0 10 ESE 5 1 2 0 0 8 SE 2 6 5 0 0 13 SSE 0 17 15 11 3. 48 S 5 30 35 4 0 74 SSW 6 14 25 17 0 62 SW 7 21 20 5 0 53 WSW 6 22 19 8 0 55 W 9 50 16 3 0. 78 WNW 11 39 25 13 2 90 NW S 28 14 1 0 48 NNW 3 18 12 0 0 33*

Variable 0 0 0 0 0 0O Total 72 274 209'. 5 2 626 Hours of calm in this stability class:. 0 .

Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0

Zion Nuclear Station Period of Record: October - December2003 Stability Class - Moderately Stable - 25OFt-33Ft Delta-T (F).

. Winds Measured at 35 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 3 NNE 5 0 0 7 NE 1 0 0 5.

ENE .1 0 01 1 E 1 0. 0 1 ESE 1 0 1

.0

- SE 1 0.1 0

SSE 1 3 9 0

S 28 4 35 0

SSW 26 1 32 00 SW 11 0 17 0

WSW 14 2 22 0

W 21 6 32 0

WNW 13 0 16 0

NW 23 0 25 0

NNW 5 0 7 0

Variable 0 0 0 Total 42 152 16 2 2 0 214 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class:. 0 Hours of missing stability measurements in all stability classes: 0

Zion Nuclear Station Period of Record: October - December2003 Stability Class - Extremely Stable - 250Ft-33Ft Delta-T (F)

Winds Measured at 35 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 0 0 0 1

.0 NNE 2 0 0 0 2 0

NE 0 .0 0 0* 0 0

ENE 0 0 0 0 0 0

E 0 0 0 0 .0 0

ESE 1 01 0 0 1 0

SE 0 0 0. 0 0 SSE 0 2 2 *0 0 4 S 3 6 3 0 0 12 SSW 14 6 0 0 0 20 SW 3 3 0 0 0 6 WSW 6 12 0 0 0 18 W 16 17 0 0 .0 33 WNW 4 15 0 0 0* 19 NW 4 2 0 0 0 6 NNW 4 1 0. 0 0 5 Variable 0 0 0 0 0 0 Total 58 64 5 0 0 0 127 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0

Zion Nuclear Station Period of Record: October - December2003 Stability Class - Extremely Unstable - 25OFt-33Ft Delta-T (F)

Winds Measured at 250 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 4 0 6.

NNE 0 8 1 11 NE 1 0 0 1 ENE 0 1 0 1 E 0 2 0 2 ESE 0 3 0 3 SE 1 7 0 8 SSE 0 0 0 0 S 0 1 0 2 SSW 0 0 0 0 SW 0 0 4 11 WSW 0 1 3 9 W 0 2 2 7 WNW 0 2 1 8 NW 1 1 0 3 NNW 0 0* 0 0 Variable .0 0 0 0 Total 3 32 26 11 0 72 Hours of calm in this stability class: .0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 2

Zion Nuclear Station Period of Record: October - December2003 Stability Class - Moderately Unstable - 250Ft-33Ft Delta-T (F)

Winds Measured at 250 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 1 2 NNE 0 2 *3 NE 0 0 2 ENE 0 0 0 E 2 0 2 ESE 0 0

0 SE 0 1 SSE 0 1 I S 0 1 1 SSW 1 .0 1 SW 3 5 11 WSW 2 2 5 W 2 8 12 WNW 3 7 12 i6 NW 0 1 3 NNW 0 0 .0 Variable 0 0 6 Total 0 3 14 28 Hours of calm in this stability class: 0 .

Hours of missing wind measurements in this stability class: I Hours of missing stability measurements in all stability classes: 2

Zion Nuclear Station Period.of Record: October - December2003 Stability Class - Slightly-Unstable - 250Ft-33Ft Delta-T (F)

Winds Measured at 250 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 2 3 0 0 5 NNE 0 1 1 1 0 0 3 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 1 0 0 0 1 SE 0 2 1 1 2 0 6 SSE 0 1 1 1 0 0 . 3 S 0 0 1 1 0 0. 2 SSW 0 1 2 0 1 1 5 SW 0 0 2 3 3 0 8 WSW 0 0 8 2 3 3 16 W 0 1 1 9 2 2 15 WNW 0 0 2 5 2 1 10 NW 0 1 3 3 2 0 9 NNW 0 1 1 2 0 0 . 4 Variable 0 0 0 0 0 0 . 0 Total 0 8 26 31 15 7 87 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class:- 0 Hours of missing stability measurements in all stability classes: 2

Zion Nuclear Station Period of Record: October - December2003 Stability Class - Neutral - 250Ft-33Ft Delta-T (F)

Winds Measured at 250 Feet Wind Speed.(in mph).

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 14 10 19 3 1 47 NNE 1 4 4 .1 . 13 2 25 NE 1 8 4 3 .9 3 28 ENE 1 3 15 9 20 0 48 E 0 0 12 15 5 0 32 ESE 1 4 7 16 6 0 34 SE 0 3 6. 18 13 0 40 SSE 0 6 13 24 19 5 67 S 0 1 9 16 7 0 33 SSW 1 8 16 . 29 22 7 83 SW 1 6 24 44 36 10 121 WSW 0 8 19 43 '36 15 121 W 0 8 29 42 19 5 103 WNW 1 4 24 53 21 8 111 NW 1 6 17 32 13 1 70 NNW 0 5 9 4 2 0 20 Variable 0 0 0 0 0 0 0 Total 8 88 218 368 244 57 983 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability'class: 6 Hours of missing stability measurements in all stability classes: 2

Zion Nuclear Station Period of Record: October.- December2003 Stability Class - Slightly Stable - 250Ft-33Ft Delta-T (F)

Winds Measured at 250 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 .19-24 > 24 Total N 4 1 4 7 0 18 NNE 5 2 2 1 .0 -10 NE 6 4 2 0 .0 13 ENE 4 2 12 0 0 8 E 3 4 2 5 0 14 ESE 5 5 2 3 0 15 SE 3 4 10 4 0 21 SSE 1 10 20 15 12 59 S 7 10 19 18 6 60 SSW .8 9 25 20 3 67 SW 2 24 30 16 2 75 WSW 2 14 .32 18 4 70 W 1 17 43 15 2 *78 WNW 8 7 32 7 9 63 NW 1 7 38 1 0 48 NNW 1 5 18 2 0 27 Variable 0 0 0 0 0 0 Total 61 125 281 132 38 646 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 2 Hours of missing stability measurements in all stability classes: *2

Zion Nuclear Station Period of Record:.October - December2003 Stability Class - Moderately Stable - 250Ft-33Ft Delta-T (F)

Winds Measured at 250 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 1 2 5 0 0 8 NNE 0 2 2 0 0 .0 4 NE 0 1 6 1 0 0 8 ENE 0 1 4 2 0 0 7 E 0 0 2 0 0 0 2 ESE 0 1 2 1 0 .0 4 SE 0 1 0 0 0 0 1 SSE 0 1 3 . 12 5 3 24 S 0 1 3 17 5 1 27 SSW 0 1 3 20 1 0 25 SW 0 1 4 8 4 0 17 WSW 0 1 1o 13 7 .0 31 W 0 0 3 12 1 0 16 WNW 0 1 . 2 9 0 0 12 NW 0 1 2 14 2 0 19 NNW 0 2 5 1 0 0 8 Variable 0 0 0 0 0 0 .0 Total 0 16 53 115 25 4 213 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 4 Hours of missing stability measurements in all-stability classes: 2

Zion Nuclear Station Period of Record: October - December2003 Stability Class - Extremely Stable. - 250Ft-33Ft Delta-T (F)

Winds Measured at 250 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 12 13-18 19-24 > 24 Total N 0 3 2 0 0 0 5 NNE 0 1 1 0 0 0. 2 NE 0 0 .3 0 0 0 3 ENE 0 1 2 1 0 0 4 E 0 0 2 0 0 0 2.

ESE 0 2 2 0 0 0 . 4 SE 0 1 3 1 0 0 5 SSE 0 1 1 6 .0 0 8 S 2 8 5 5 4 0 24 SSW 2 3 . 2 4 0 0 11 SW 0 1 4 6 4 0 15 WSW 1 1 5 7 1 0 15 W 1 2 1 9 3 0 16 WNW 1 1 2 1 0 0 5 NW 0 2 0 4 1 0 7 NNW 2 3 2 0 0 0 7 Variable 0 0 0 0 0 0 0 Total 9 30 37 44 13 0 133 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 3 Hours of missing stability measurements in all stability classes: 2

Zion Nuclear Station January-March. 2003 35 ft. Wind Speed and Direction 250Ft-33Ft Delta-T (F)

Number of Observaticns - 2146 Values are Percent Occurrence SPEED ---------------------------------- WIND DIRECTION CLASSES ---------------------------------- --------- STABILITY CLASSES ----------

CLASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL EU MU SU N SS MS ES TOTAL .

EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00- 0.00 0.00 C SU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 *0.00 0.00 0.00 0.00 0.00 A N 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 L SS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MMS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1 SU 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 .0.00 '0.00 0.00 0.00 0.00 0.00 0.00

- N 0.09 0.09 0.09 0.00 0.00 0.09 0.00 0.00 0.09 0.05 0.05 0.05 0.05 0.37 0.09 0.05 1.16 1.16 3 SS 0.05 0.05 0.05 0.00 0.14 0.28 0.14 0.05 0.14 0.19 0.33 0.61 0.23 0.56 0.37 0.14 3.31 3.31 MS 0.00 0.05 0.00 0.05 0.05 0.00 0.00 0.00 0.09 0.09 0.28 0.51 0.33 0.33 0.00 0.09 1.86 1.86 ES 0.09 0.00 0.00 0.05 0.05 0.00 0.00 0.19 0.28 0.19 014 0.19 0.09 0.05 0.00 0.00 1.30 1.30 7.64 EU 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.19 0.19 MU 0.00 0.05 0.00 0.05 0.09 0.00 0.00 0.05 0.00 0.00 0.00 0.05 0.00 0.05 0.00 0.00 0.33 0.33 4 SU 0.00 0.19 0.00 0.09. 0.19 0.09 0.14 0.05 0.00 0.00 0.05 0.09 0.05 0.19 0.14 0.05 1.30 1.30

- N 0.37 1.03 0.19 0.23 0.42 0.28 0.37 0.79 0.70 0.70 0.84 0.79 1.16 0.84 1.86 0.47 11.04 11.04 7 SS 0.09 0.28 0.09 0.23 0.19 0.47 0.65 0.47 1.07 1.03 1.72 1.35 1.72 2.38 2.33 0.56 14.63 14.63 MS 0.14 0.00 0.05 0.00 0.05 0.09 0.23 0.23 0.65 0.33 0.19 0.33 0.51 0.37 0.37 0.00 3.54 3.54 ES 0.05 0.00 0.05 0.05 0.05 0.00 0.05 0.75 1.63 0.09 0.05 0.33 0.65 0.51 0.09 0.05 4.38 4.38 35.41 EU 0.09 0.61 0.14 0.00 0.09 0.09 0.14 0.00 0.00 0.09 0.09 0.14 0.51 0.23 0.23 0.00 2.47 2.47 MU 0.09 0.05 0.05 0.00 0.00 0.05 0.09 0.14 0.09 0.14 0.09 0.23 0.42 0.42 0.51 0.05 2.42 2.42 8 SU 0.09 0.09 0.05 0.00 0.05 0.09 0.09 0.05 0.05 0.05 0.47 0.19 0.42 0.70 0.75 0.33 3.45 3.45

- N 0.61 1.72 0.70 0.23 0.09 0.14 0.09 0.79 0.65 0.79 1.72 2.56 1.16 2.42 3.49 2.56 19.76 19.76 1 SS 1.03 0.37 0.09 0.19 0.14 0.19 0.09 0.47 0.51 0.51 1.07 1.54 2.61 2.24 0.70 0.51 12.26 12.26 2MS 0.00 0.05 0.00 0.00 0.00 0.00 0.05 0.37 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.56 0.56 ES 0.00 0.00 0.00 0.05 0.05 0.00 0.05 0.56 0.14 0.00 0.00 0.00 0.00 0.00 *0.00 0.00 0.84 0.84 41.75 EU 0.09 0.14 0.23 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.19 0.14 0.14 0.00 0.05 1.12 1.12 1MHU0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.14 0.19 0.05 0.05 0.05 0.61 0.61 3 SU 0.00 0.05 0.28 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.19 0.19 0.23 0.23 0.05 0.09 1.35 1.35

- N 0.89 0.47 2.00 0.37 0.00 0.00 0.00 0.05 0.05 0.09 0.84 1.03 0.47 0.89 0.33 0.70 8.15 8.15 1 SS 0.05 0.09 0.14 0.00 0.14 0.05 0.00 0.14 0.00 0.05 0.9B 0.14 0.51 0.19 .0.19 0.05 2.70 2.70 8MHS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00. 0.00 0.00 0.00 13.93

Zion Nuclear Station January-March. 2003 35 ft. Wind Speed and Direction 250Ft-33Ft Delta-T (F)

SPEED -----------------WIND DIRECTION CLASSES ------------ --------- STABILITY CLASSES ----------

CLASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W. WSd NX NNW TOTAL EU MU SU N SS MS ES TOTAL EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1MU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.,00 0.00 0.00 0.00 0.00 0.00 9 SU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

- N 0.47 0.00 0.47 0.19 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 1.16 1.16 2 SS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 4MS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.16 EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 G MU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 T SU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 N 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.09 2 SS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 4 MS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 .0.00 0.09 TOT 4.38 5.36 4.66 1.77 1.77 1.96 2.24 5.17 6.15 4.52 9.41 10.62 11.46 13.19 11.56 5.78 100.00 3.77 3.36 6.10 41.38 32.90 5.96 6.52 100.00 Wind Direction by Stability N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL -STABILITY CLASSES-0.19 0.75 0.37 0.00 0.09 0.14 0.19 0.05 0.00 0.14 0.19 0.33 0.65 0.42 0.23 0.05 3.77 Extremely Unstable 0.09 0.09 0.05 0.05 0.09 0.05 0.09 0.19 0.09 0.14 0.23 0.42 0:61 0.51 0.56 0.09 3.36 Moderately Unstable 0.09 0.33 0.33 0.09 0.23 0.19 0.23 0.09 0.05 0.09 0.70 0.47 0.70 1.12 0.93 0.47 6.10 Slightly Unstable 2.52 3.31 3.45 1.03 0.51 0.51 0.47 1.63 1.49 1.63 3.49 4.43 2.84 4.52 5.78 3.77 41.38 Neutral 1.21 0.79 0.37 0.42 0.61 0.98 0.89 1.12 1.72 1.77 4.10 3.63 5.08 5.36 3.59 1.26 32.90 Slightly Stable 0.14 0.09 0.05 0.05 *0.09 0.09 0.28 0.61 0.75 0.47 0.51 0.84 0.84 0.70 0.37 0.09 5.96 Moderately Stable 0.14 0.00 0.05 0.14 0.14 0.00 0.09 1.49 2.05 0.28 0.19 0.51 0.75 0.56 0.09 0.05 6.52 Extremely Stable Wind Direction by Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW k W WNW NW NNWTOTAL -WIND SPEED CLASSES-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CALM 0.23 0.19 0.14 0.09 0.23 0.37 0.14 0.23 0.61 0.51 0.79 1.35 0.70 1.30 0.47 0.28 7.64 < 3.5 rrph 0.65 1.54 0.37 0.65 0.98 0.98 1.49 2.38 4.05 2.14 2.84 2.94 4.10 4.38 4.80 1.12 35.41 3.6 - 7.5 mph 1.91 2.89 1.03 0.47 0.42 0.56 0.61 2.38 1.44 1.63 3.49 4.66 5.13 6.01 5.68 3.45 41.75 7.6 - 12.5 mph 1.03 0.75 2.66 0.37 0.14 0.05 0.00 0.19 0.05 0.23 2.24 1.68 1.54 1.49 0.61 0.93 13.93 12.6 - 18.5 mph 0.47 0.00 0.47 0.19 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 1.16 18.6 - 24.5 rph 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 > 24.5 mph

Zion Nuclear Station January-March. 2003 250 ft. Wind Speed and Direction 25OFt-33Ft Delta-T (F)

Nunber of Observations - 2157 Values are Percent Occurrence SPEED ---------------------------------- WIND DIREC CTION CLASSES --------------------------------- --------- STABILITY CLASSES ----------

CLASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NJ NNWTOTAL EU MU SU N SS MS ES TOTAL EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 C SU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 A N 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00. 0.00 0.00 0.00 0.00 0.00 0.00 0.00 L SS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MMS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ISU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

- N 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.09 0.00 0.05 0.05 0.32 0.32 3 SS 0.05 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.00 0.00 0.00 0.05 0.23 0.23 MS 0.00 0.00 0.00 0.00 0.09 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.23 0.23 ES 0.00 0.00 0.14 0.09 0.09 0.00 0.00 0.00 0.05 .0.00 0.05 0.00 0.00 0.05 0.09 0.19 0.74 0.74 1.53 EU 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0:00 0.00 0.00 0.00 0.00 0.05 0.05 MU 0.00 0.05 0.00 0.09 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.23 0.23 4 SUN0.00 0.00 0.00 0.14 0.14 0.09 0.09 0.00 0.00 0.00 0.05 0.00 0.00 0.05 0.00 0.00 0.56 0.56 0.14 0.09 0.19 0.09 0.00 0.14 0.23 0.14 0.09 0.14 0.09 0.32 0.23 0.37 0.14 0.19 2.60 2.60 7 SS 0.00 0.05 0.00 0.28 0.09 0.28 0.00 0.00 0.09 0.14 0.23 0.37 0.37 0.19 0.19 0.14 2.41 2.41 MS 0.05 0.05 0.05 0.00 0.00 0.09 0.00 0.05 0.14 0.09 0.09 0.09 0.09 0.14 0.09 0.05 1.07 1.07 ES 0.23 0.09 0.05 0.05 0.05 0.00 0.05 0.00 0.05 0.05 0.05 0.09 0.09 0.00 0.00 0.14 0.97 0.97 7.88 EU 0.00 0.37 0.00 0.00 0.05 0.05 0.19 0.00 0.00 0.00 0.00 0.05 0.19 0.09 0.05 0.00 1.02 1.02 MU 0.00 0.00 0.05 0.00 '0.05 0.00 0.14 0.00 0.00 0.00 0.05 0.09 0.14 0.09 0.14 0.00 0.74 0.74 8 SU 0.00 0.19 0.00 0.00 0.05 0.05 0.32 0.00 0.00 0.00 0.00 0.19 0.14 0.32 0.32 0.05 1.62 1.62

- N 0.28 0.83 0.19 0.14 0.19 0.05 0.74 0.74 0.37 0.65 0.74 0.88 1.07 0.93 1.34 0.70 9.83 9.83 1 SS 0.14 0.14 0.14 0.09 0.19 0.42 0.42 0.32 0.65 0.56 1.34 0.93 0.70 1.25 1.44 0.65 9.36 9.36 2 MS 0.14 0.00 0.00 0.05 0.05 0.05 0.05 0.19 0.32 0.37 0.37 0.14 0.23 0.09 0.32 0.32 2.69 2.69 ES 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.05 0.32 0.65 0.46 0.14 0.05 0.00 0.00 0.05 1.81 1.81 27.07 EU 0.14 0.23 0.00 0.00 0.05 0.00 0.09 0.00 0.00 0.14 0.09 0.09 0.37 0.14 0.19 0.00 1.53 1.53 ImU 0.09 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.05 0.14 0.05 0.14 0.32 0.37 0.32 0.05 1.62 1.62 3 SU 0.05 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.09 0.14 0.32 0.09 0.32 0.60 0.42 0.32 2.46 2.46

- N 0.32 1.02 0.70 0.32 0.14 0.05 0.09 0.70 0.65 0.70 1.62 1.95 0.93 1.62 3.11 1.90 15.81 15.81 1 SS 0.14 0.28 0.19 0.09 0.09 0.19 0.23 0.56 0.65 0.65 1.16 1.25 2.18 2.83 1.81 0.74 13.03 13.03 8MS 0.00 0.05 0.00 0.00 0.00 0.14 0.00 0.42 0.14 0.37 0.09 0.00 0.09 0.09 0.00 0.14 1.53 1.53 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.05 1.02 0.83 0.14 0.05 0.00 0.05 0.09 0.05 2.41 2.41 38.39

Zion Nuclear Station January-March. 2003 250 ft. Wind Speed and Direction 25OFt-33Ft Delta-T (F)

SPEED ---------------------------------- WIND DIRECTION CLASSES ------------ .......... STABILITY CLASSES ----------

CLASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL EU MU SU N SS MS ES TOTAL EU 0.19 0.19 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.09 0.14 0.09 0.05 0.00 1.02 1.02 1MU 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.14 0.09 0.14 0.00 0.09 0.05 0.65 0.65 .

9 SU 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.00* 0.00 0.05 0.19 0.19 0.19 0.14 0.05 0.09 0.97 0.97

- N 0.23 1.21 0.93 0.32 0.00 0.00 0.00 0.00 0.28 0.09 1.02 0.88 0.51 0.93 0.97 0.93 8.30 8.30 2 SS 0.42 0.42 0.23 0.09 0.14 0.19 0.09 0.05 0.19 0.23 1.16 1.02 1.21 0.83 0.28 0.09 6.63 6.63 4ES 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.23 0.00 0.09 0.05 0.00 0.00 0.00 0.00 0.00 0.42 0.42 ES 0.00 0.00 0.00 0.00 0.09 0.09 0.05 0.19 0.05 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.56 0.56 18.54 EU 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0..00 0.05 0.00 0.00 0.14 0.14 G MU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.05 0.00 0.00 0.14 0.14 T SU 0.00 0.00 0.28 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.14 0.00 0.00 0.46 0.46 N 1.30 0.42 1.44 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.46 0.05 0.51 0.05 0.05 4.36 4.36 2 SS 0.05 0.09 0.05 0.00 0.14 0.00 0.00 0.19 0.00 0.00 0.23 0.05 0.42 0.19 0.09 0.00 1.48 1.48 4 MS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 .0.00 6.58 TOT 4.03 5.93 4.96 1.85 1.67 1.95 3.06 3.99 5.24 6.31 9.97 9.92 10.29 12.19 11.68 6.95 100.00 3.76 3.38 6.07 41.21 33.15 5.93 6.49 100.00 Wind Direction by Stability N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL -STABILITY CLASSES-0.32 0.79 0.19 0.00 0.09 0.09 0.28 0.00 0.00 0.19 0.19 0.28 0.70 0.37 0.28 0.00 3.76 Extremely Unstable 0.09 0.09 0.05 0.09 0.05 0.00 0.23 0.09 0.09 0.14 0.23 0.46 0;60 0.51 0.56 0.09 3.38 Moderately Unstable 0.09 0.28 0.32 0.14 0.19 0.14 0.42 0.00 0.09 0.19 0.56 0.51 0.65 1.25 0.79 0.46 6.07 Slightly Unstable 2.32 3.62 3.43 0.88 0.32 0.23 1.07 1.58 1.39 1.62 3.57 4.50 2.87 4.36 5.66 3.80 41.21 Neutral 0.79 0.97 0.65 0.56 0.65 1.07 0.74 1.11 1.58 1.62 4.13 3.66 4.87 5.29 3.80 1.67 33.15 Slightly Stable 0.19 0.09 0.05 0.05 0.14 0.32 0.09 0.93 0.60 0.93 0.60 0.23 0.46 0.32 0.42 0.51 5.93 Moderately Stable 0.23 0.09 0.28 0.14 0.23 0.09 0.23 0.28 1.48 1.62 0.70 0.28 0.14 0.09 0.19 0.42 6.49 Extremely Stable Wind Direction by Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL -WIND SPEED CLASSES-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CALM 0.09 0.05 0.19 0.09 0.19 0.00 0.05 0.05 0.05 0.09 0.05 0.05 0.14 0.05 0.14 0.28 1.53 < 3.5 mph 0.42 0.32 0.28 0.65 0.28 0.65 0.42 0.19 0.37 0.42 0.51 0.93 0.79 0.74 0.42 0.51 7.88 3.6 - 7.5 mph 0.56 1.53 0.46 0.28 0.56 0.60 1.85 1.30 1.67 2.23 2.97 2.41 2.50 2.78 3.62 1.76 27.07 7.6 - 12.5 mph 0.74 1.62 0.93 0.42 0.28 0.37 0.60 1.76 2.60 2.97 3.48 3.57 *4.22 5.70 5.93 3.20 38.39 12.6 - 18.5 mph 0.88 1.90 1.30 0.42 0.23 0.32 0.14 0.51 0.56 0.60 2.64 2.27 2.18 1.99 1.44 1.16 18.54 18.6 - 24.5 mph 1.34 0.51 1.81 0.00 0.14 0.00 0.00 0.19 0.00 0.00 0.32 0.70 0.46 0.93 0.14 0.05 6.58 > 24.5 nph

Zion Nuclear Station April-June. 2003 35 ft. Wind Speed and Direction 25OFt-33Ft Delta-T (F)

Nuiber of Observations - 2147 Values are Percent Occurrence SPEED ---------------------------------- IWIND DIRECTION CLASSES --------- STABILITY CLASSES ----------

CLASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WWd NX NNWTOTAL EU MU SU N SS MS ES TOTAL EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00' 0.00 0.00 0.00 0.00 C SU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 A N 0.00 0.00 0.00 .0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 L SS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 M MS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1 SU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

- N 0.00 0.19 0.09 0.05 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.05 0.09 0.05 0.14 0.05 0.75 0.75 3 SS 0.61 0.37 0.37 0.00 0.23 0.28 0.37 0.28 0.42 0.19 0.14 0.14 0.09 0.42 0.19 0.33 4.42 4.42 MS 0.33 0.37 0.09 0.09 0.00 0.05 0.09 0.09 0.56 0.56 0.37 0.28 0.14 0.28 0.23 0.19 3.73 3.73 ES 0.09 0.09 0.00 0.00 0.09 0.05 0.00 0.05 0.51 0.75 1.07 0.56 0.28 0.19 0.05 0.19 3.96 3.96 12:86 EU 0.00 0.42 0.19 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.75 0.75 MU 0.00 0.23 0.33 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.70 0.70 4 SU 0.14 0.56 0.37 0.05 0.09 0.00 0.00 0.00 0.00' 0.00 0.00 0.05 0.00 0.05 0.00 0.00 1.30 1.30

- N .1.16 2.14 1.49 0.84 0.47 0.23 0.56 0.51 0.09 0.09 0.09 0.37 0.37 0.28 0.05 0.28 9.04 9.04 7 SS 3.77 3.07 1.77 0.70 0.28 1.02 1.07 1.21 0.84 0.37 0.33 1.02 1.02 0.42 0.61 0.88 18.40 18.40 MS 0.88 0.23 0.23 0.37 0.23 0.23 0.47 0.79 0.88 0.65 0.23 0.47 0.28 0.33 0.61 0.70 7.59 7.59 ES 0.14 0.09 0.05 0.14 0.23 0.09 0.05 0.61 1.21 0.47 0.51 0.33 0.75 0.14 0.14 0.00 4.94 4.94 42.71 EU 0.65 1.72 0.33 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.14 0.23 0.09 0.42 0.28 0.14 4.10 4.10 MU 0.37 0.75 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.09 0.09 0.05 1.49 1.49 8 SU 0.98 0.47 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.05 0.09 0.09 0.19 0.09 0.09 2.10 2.10

- N 3.68 3.96 0.65 0.05 0.09 0.00 0.09 0.28 0.09 0.09 0.56 0.98 0.37 0.14 0.56 0.75 12.34 12.34 1 SS 4.52 0.33 0.09 0.14 0.14 0.14 0.42 0.75 0.23 0.28 0.28 0.47 0.19 0.19 0.05 0.14 8.34 8.34 2 MS 0.00 0.00 0.00 0.05 0.09 0.09 0.00 0.37 0.42 0.09 0.05 0.00 0.00 0.00 0.00 0.00 1.16 1.16 ES 0.00 0.05 0.09 0.19 0.09 0.05 0.05 0.42 0.33 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.26 1.26 30.79 EU 1.16 0.84 0.05 0.23 0.00 0.00 0.00 0.00 0.00 0.14 0.23 0.09 0.09 0.00 0.00 0.09 2.93 2.93 1MU 0.28 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.05 0.09 0.09 0.05 0.00 0.70 0.70 3 SU 0.28 0.09 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.14 0.05 0.19 0.00 0.05 0.19 0.00 1.02 1.02

- N 1.58 0.47 1.30 0.33 0.05 0.00 0.00 0.00 0.00 0.19 0.23 0.19 0.14 0.33 0.19 0.00 4.98 4.98 1 SS 0.56 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.05 0.28 0.51 0.09 0.00 0.14 0.00 0.00 1.68 1.68 8MS 0.00 0.00 0.00 0.00 0.05 '0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 ES 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 11.41

Zion Nuclear Station April-June. 2003 35 ft. Wind Speed and Direction 25OFt-33Ft Delta-T (F)

SPEED - -- .---.------------------ WIND DIRECTION CLASSES ------------ --------- STABILITY CLASSES ----------

CLASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WhW NW NNWTOTAL EU MU SU N SS MS ES TOTAL EU 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.09 1MU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 9 SU 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.14 0.14

- N 0.19 0.00 0.19 0.70 0.00 0.00 0.00 0.00 0.00 0.00 0.19 0.56 0.09 0.00 0.00 0.00 1.91 1.91 2 SS 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 4MS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ' 0.00 2.19 EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 GMU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 T SU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.05 0.05 N 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2 SS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 4MS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0:00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 TOT 21.52 16.44 7.73 4.05 2.38 2.33 3.21 5.40 5.64 4.29 5.26 6.24 4.33 3.77 3.54 3.87 100.00 7.87 2.89 4.61 29.02 32.88 12.53 10.20 100.00 Wind Direction by Stability N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW'TOTAL -STABILITY CLASSES-1.91 2.98 0.56 0.33 0.09 0.00 0.00 0.00 0.00 0.14 0.37 0.33 0.19 0.42 0.33 0.23 7.87 Extremely Unstable 0.65 0.98 0.37 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.14 0.05 0.23 0.19 0.14 0.05 2.89 Moderately Unstable 1.44 1.12 0.37 0.05 0.14 0.00 0.00 0.05 0.00 0.14 0.19 0.37 0.09 0.28 0.28 0.09 4.61 Slightly Unstable 6.61 6.75 3.73 1.96 0.61 0.23 0.70 0.79 0.19 0.37 1.07 2.14 1.07 0.79 0.93 1.07 29.02 Neutral 9.46 3.77 2.24 0.84 0.70 1.49 1.86 2.24 1.54 1.12 1.26 1.72 1.30 1.16 0.84 1.35 32.88 Slightly Stable 1.2i 0.61 0.33 0.51 0.37 0.37 0.56 1.26 1.86 1.30 0.65 0.75 0.42 0.61 0.84 0.88 12.53 Moderately Stable 0.23 0.23 0.14 0.33 0.42 0.23 0.09 1.07 2.05 1.21 1.58 0.88 1.02 0.33 0.19 0.19 10.20 Extremely Stable Wind Direction by Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W W N' R NNWTOTAL -WIND SPEED CLASSES-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CALM 1.02 1.02 0.56 0.14 0.33 0.37 0.51 0.42 1.49 1.49 1.5B 1.02 0.61 0.93 0.61 0.75 12.86 < 3.5 ph 6.10 6.75 4.42 2.19 1.35 1.58 2.14 3.12 3.03 1.58 1.16 2.24 2.52 1.21 1.44 1.86 42.71 3.6 - 7.5 irph 10.20 7.27 1.16 0.47 0.51 0.28 0.56 1.86 1.07 0.47 1.12 1.77 0.79 1.02 1.07 1.16 30.79 7.6 - 12.5 rrph 3.87 1.40 1.40 0.56 0.19 0.05 0.00 0.00 0.05 0.75 1.12 0.61 0.33 0.61 0.42 0.09 11.41 12.6 - 18.5 mph 0.33 0.00 0.19 0.70 0.00 0.05 0.00 0.00 0.00* 0.00 0.28 0.56 0.09 0.00 0.00 0.00 2.19 18.6 - 24.5 mph 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.05 > 24.5 mph

Zion Nuclear Station April-June. 2003 250 ft. Wind Speed and Direction 250Ft-33Ft Delta-T (F)

Nurber of Observations - 2084 Values are Percent Occurrence SPEED . . . . . -------

. . . --------- WIND DIRECTION CLASSES --------- STABILITY CLASSES ---------- -

CLASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NN TOTAL EU HU SU N SS MS ES TOTAL EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 C SU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00* 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 A N 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 L SS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 M MS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 I SU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

- N 0.00 0.10 0.05 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.24 0.24 3 SS 0.10 0.00 0.10 0.05 0.05 0.00 0.19 0.10 0.05 0.05 0.05 0.00 0.00 0.10 0.00 0.05 0.86 0.86 MS 0.00 0.05 0.10 0.00 0.14 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0; 00 0.00 0.00 0.38 0.38 ES 0.05 0.10 0.05 0.00 0.05 0.00 0.00 0.00 0.00 0.10 0.00 0.00 0.00 0.05 0.05 0.00 0.43 0.43 1.92 EU 0.05 0.14 0.05 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.34 0.34 MU 0.05 0.05 0.19 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.29 0.29 4 SU 0.00 0.24 0.00 0.00 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.43 0.43

- N 0.34 0.62 0.67 0.38 0.34 0.19 0.24 0.24 0.00 0.00 0.10 0.05 0.05 0.19 0.24 0.10 3.74 3.74 7 SS 0.24 0.82 0.72 0.48 0.14 0.53 0.24 0.29 0.10. 0.05 0.19 0.10 0.05 0.14 0.05 0.14 4.27 4.27 MS 0.10 0.34 0.19 0.05 0.19 0.05 0.10 0.24 0.14 0.00 0.10 0.05 0.05 0.00 0.00 0.10 1.68 1.68 ES 0.10 0.14 0.10 0.14 0.00 0.14 0.14 0.38 0.10 0.05 0'.05 0.10 0.05 0.00 0.00 0.24 1.73 1.73 12.48 EU 0.24 1.10 0.48 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.05 0.00 2.02 2.02 MU 0.05 0.19 0.14 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.10 0.00 0.05 0.00 0.58 0.58 8 SU 0.43 0.53 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.10 0.00 0.00 1.25 1.25

- N 1.20 1.63 0.38 0.14 0.14 0.00 0.43 0.38 0.00 0.10 0.05 0.34 0.10 0.14 0.05 0.34 5.42 5.42 1 SS 1.25 1.97 1.01 0.43 0.38 0.62 1.78 0.91 0.19 0.24 0.29 0.48 0.53 0.14 0.05 0.38 10.65 10.65 2MS 0.77 0.48 0.24 0.24 0.19 0.14 0.62 0.43 0.67 0.34 0.24 0.00 0.14 0.14 0.05 0.14 4.85 4.85 ES 0.24 0.05 0.00 0.05 0.00 0.00 0.14 0.38 1.15 0.62 0.34 0.19 0.10 0.05 0.10 0.10 3.50 3.50 28.26 EU 1.01 0.14 0.00 0.10 0.00 0.00 0.00 0.00 0.00 0.10 0.14 0.14 0.29 0.14 0.29 0.05 2.40 2.40 IMU 0.77 0.10 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.10 0.00 0.05 0.10 0.10 0.00 1.20 1.20 3 SU 0.91 0.10 0.00. 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.10 0.19 0.00 0.10 1.49 1.49

- N 3.26 1.87 0.34 0.19 0.10 0.00 0.14 0.24 0.00 0.19 0.48 1.15 0.24 0.24 0.58 0.29 9.31 9.31 1 SS 3.79 1.58 0.38 0.19 0.05 0.14 0.58 0.72 0.19 0.43 0.43 0.77 0.62 0.29 0.67 0.38 11.23 11.23 8M5 0.67 0.19 0.05 0.10 0.10 0.24 0.19 0.96 0.48 0.43 0.34 0.29 0.34 0.05 0.14 0.24 4.80 4.80 ES 0.10 0.05 0.05 0.05 0.05 0.05 0.00 0.34 1.44 0.96 0.38 0.10 0.19 0.10 0.05 0.00 3.89 3.89 34.31

Zion Nuclear Station April-June. 2003 250 ft. Wind Speed and Direction 250Ft-33Ft Delta-T (F)

SPEED ---------------------------------- WIND DIRECTION CLASSES ------------ --------- STABILITY CLASSES ----------

CLASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL EU MU SU N SS MS ES TOTAL EU 1.10 0.14 0.05 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.19 0.14 0.14 0.00 0.10 0.00 2.02 2.02 IMU 0.34 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.38 0.38 9 SU 0.43 0.00 0.00 0.00 0.05 0.00 0.00 0.05 0.00 0.10 0.05 0.14 0.00 0.00 0.19 0.00 1.01 1.01

- N 2.11 0.91 0.48 0.10 0.00 0.00 0.00 0.00 0.00 0.19 0.19 0.34 0.10 0.24 0.34 0.05 5.04 5.04 2 SS 2.40 0.00 0.05 0.05 0.05 0.05 0.10 0.24 0.10 0.38 0.14 0.14 '0.05 0.10 0.05 0.05 3.93 3.93 4MS 0.00 0.00 0.00 0.05 0.05 0.10 0.00 0.24 0.24 0.10 0.00 0.00 0.05 0.00 0.05 0.00 0.86 0.86 ES 0.00 0.00 0.00 0.14 0.00 0.05 0.00 0.19 0.34 0.10 0.05 0.05 0.05 0.00 0.00 0.00 0.96 0.96 14.20 EU 1.06 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.10 0.00 0.00 0.00 0.00 0.00 1.20 1.20 GMU 0.19 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0;10 0.05 0.10 0.00 0.53 0.53 T SU 0.24 *0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.10 0.14 0.00 0.00 0.05 0.05 0.00 0.58 0.58 N 1.15 0.14 0.82 0.67 0.00 0.00 0.00 0.00 0.00 0.19 0.29 0.53 0.14 0.05 0.14 0.00 4.13 4.13 2 SS 0.53 0.00 0.00 0.05 0.10 0.14 0.00 0.05 0.00 0.19 0.48 0.05 0.00 0.05 0.10 0.00 1.73 1.73 4 MS 0.00 0.00 0.00 0.05 0.10 0.10 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.29 0.29 ES 0.00 0.00 0.00 0.05 0.05 0.14 0.00 0.05 0.10 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.38 0.38 8.83 TOT 25.24 13.77 6.86 3.98 2.54 2.69 4.94 6.48 5.28 5.04 5.09 5.37 3.65 2.74 3.60 2.74 100.00 7.97 2.98 4.75 27.88 32.68 12.86 10.89 100.00 Wind Direction by Stability N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL -STABILITY CLASSES-3.45 1.54 0.58 0.34 0.05 0.00 0.00 0.00 0.00 0.14 0.43 0.29 0.48 0.19 0.43 0.05 7.97 Extremely Unstable 1.39 0.34 0.38 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.14 0.05 0.24 0.14 0.24 0.00 2.98 Moderately Unstable 2.02 0.86 0.14 0.00 0.19 0.00 0.00 0.05 0.00 0.19 0.24 0.29 0.10 0.34 0.24 0.10 4.75 Slightly Unstable 8.06 5.28 2.74 1.49 0.58 0.19 0.86 0.86 0.00 0.67 1.15 2.40 0.62 0.86 1.34 0.77 27.88 Neutral 8.30 4.37 2.26 1.25 0.77 1.49 2.88 2.30 0.62 1.34 1.58 1.54 1.25 0.82 0.91 1.01 32.68 Slightly Stable 1.54 1.06 0 .58 0.48 0.77 0.62 0.91 1.92 1.54 0.86 0.72 0.38 0.58 0.19 0.24 0.48 12.86 Moderately Stable 0.48 0.34 0.19 0.43 0.14 0.38 0.29 1.34 3.12 1.82 0.82 0.43 0.38 0.19 0.19 0.34 10.89 Extremely Stable Wind Direction by Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WN!M NW NNWTOTAL -WIND SPEED CLASSES-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CALM 0.14 0.24 0.29 0.05 0.24 0.00 0.24 0.10 0.05 0.14 0.14 0.05 0.00 0.14 0.05 0.05 1.92 < 3.5 urh 0.86 2.35 1.92 1.10 0.86 0.91 0.72 1.15 0.34 0.10 0.43 0.34 0.19 0.34 0.29 0.58 12.48 3.6 - 7.5 mph 4.17 5.95 2.40 0.91 0.77 0.77 2.98 2.11 2.02 1.30 0.91 1.06 1.01 0.62 0.34 0.96 28.26 7.6 - 12.5 mph 10.51 4.03 0.82 0.62 0.29 0.43 0.91 2.26 2.11 2.11 1.92 2.50 1.82 1.10 1.82 1.06 34.31 12.6 - 18.5 mph 6.38 1.06 0.58 0.48 0.14 .0.19 0.10 0.72 0.67 0.86 0.62 0.86 0.38 0.34 0.72 0.10 14.20 18.6 - 24.5 mph 3.17 0.14 0.86 0.82 0.24 0.38 0.00 0.14 0.10 0.53 1.06 0.58 0.24 0.19 0.38 0.00 8.83 > 24.5 mph

Zion Nuclear Station October-Decerber. 2003 35 ft. Wind Speed and Direction 250Ft-33Ft Delta-T (F)

Nurber of Observations - 2097 Values are Percent Occurrence SPEED ---------------------------------- WIND DIRECTION CLASSES - STABILITY CLASSES ----------

CLASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL EU MU SU N SS MS ES TOTAL EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00' 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 C SU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 A N 0.00 *0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 L SS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MMS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00*

EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 mu 0.00 0.00 0.00 0.00 0.00 0.00 '0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1 SU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

- N 0.14 0.10 0.10 0.00 0.05 0.10 0.10 0.10 0.10 0.14 0.05 0.05 0.10 0.10 0.00 0.05 1.24 1.24 3 SS 0.14 0.14 0.19 0; 05 0.10 0.24 0.10 0.00 0.24 0.29 0.33 0.29 0.43 0.52 0.24 0.14 3.43 3.43 MS 0.14 0.10 0.19 0.00 0.00 0.00 0.00 0.10 0.10 0.24 0.29 0.29 0.24 0.14 0.10 0.10 2.00 2.00 ES 0.05 0.10 0.00 0.00 0.00 0.05 0.00 0.00 0.14 0.67 0.14 0.29 0.76 0.19 0.19 0.19 2.77 2.77 9.44 EU 0.00 0.00 0.00 0;05 0.14 0.14 0.29 0.10 0.00 0.00 0.00 0.00 0.00 0.05 0.10 0.05 0.91 0.91 MU 0.00 0.00 0.00 0.10 0.05 0.10 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.10 0.10 0.00 0.52 0.52 4 SU 0.05 0.10 0.10 0.00 0.00 0.10 0.14 0.00 0.05 0.10 0.00 0.05 0.14 0.10 0.05 0.10 1.05 1.05 N 0.62 0.91 0.62 0.52 0.62 0.67 0.10 0.52 0.72 0.86 *0.67 1.14 1.53 1.48 0.57 0.86 12.40 12.40 7 SS 0.19 0.24 0.38 0.33 0.19 0.05 0.29 0.81 1.43 0.67 1.00 1.05 2.38 1.86 1.34 0.86 13.07 13.07 MS 0.00 0.24 0.05 0.05 0.05 0.05 0.05 0.05 1.34 1.24 0.52 0.67 1.00 0.62 1.10 0.24 7.25 7.25 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.10 0.29 0.29 0.14 0.57 0.81 0.72 0.10 0.05 3.05 3.05 38.25 EU 0.00 0.48 0.29 0.05 0.00 0.00 0.00 0.00 0.10 0.00 0.05 0.33 0.38 0.19 0.29 0.05 2.19 2.19 MU 0.00 0.19 0.00 0.00 0.00 0.00 0.00 0.10 0.00 0.05 0.14 0.29 0.19 0.29 0.19 0.05 1.48 1.48 8 SU 0.10 0.19 0.00 0.00 0.00 0.05 0.00 0.19 0.05 0.00 0.14 0.29 0.29 0.43 0.14 0.19 2.05 2.05

- N 0.33 0.86 0.33 0.19 1.14 1.24 0.48 1.38 0.67 1.67 1.53 2.10 1.72 1.86 2.72 0.57 18.79 18.79 1 SS 0.33 0.29 0.10 0.10 0.19 0.10 0.24 0.72 1.67 1.19 0.95 0.91 0.76 1.19 0.67 0.57 9.97 9.97 2M1S 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.19 0.05 0.00 0.10 0.29 0.00 0.00 0.00 0.76 0.76 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.10 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.24 0.24 35.48 EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.05 0.05 0.05 0.05 0.00 0.33 0.33 1 MU 0.00 0.10 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00.- 0.10 0.10 0.14 0.00 0.05 0.48 0.48 3 SU 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.14 0.10 0.00 0.33 0.19 0.10 0.00 0.91 0.91

- N 0.19 0.33 0.33 1.14 0.29 0.52 0.14 1.57 0.14 0.86 1.91 0.91 1.05 0.72 0.43 0.33 10.87 10.87 1 SS 0.10 0.00 0.00 0.00 0.00 0.00 0.00 0.52 0.19 0.81 0.24 0.38 0.14 0.62 0.05 0.00 3.05 3.05 8 MS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.00 C.00 0.00 0.10 0.10 ES 0.00 0.00 0.00 0.00 0.00 0.00 *0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

.15.74

Zion Nuclear Station October-December. 2003 35 ft. Winrd Speed and Direction 250Ft-33Ft Delta-T (F)

SPEED ---------------------------------- WIND DIRECTION CLASSES ---------------------------------- --------- STABILITY CLASSES ----------

CLASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNX TOTAL EU MU SU N SS MS ES TOTAL EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 IMU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 9 SU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

- N 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.05 0.00 0.24 0.14 0.00 0.00 0.62 0.62 2 SS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.00 0.00 0.10 0.00 0.00 0.24 0.24 4MHS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.10 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.10 0.10 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.95 EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 G MU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 T SU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 N 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 2 SS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.10 0.00 0.00 0.00 0.00 0:00 0.00 0.00. 0.00 0.10 0.10 4 MS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 TOT 2.43 4.34 2.67 2.58 2.81 3.39 1.96 7.06 7.58 9.25 8.39 9.87 12.97 11.78 8.49 4.43 100.00 3.43 2.48 4.01 43.97 29.85 10.21 6.06 100.00 Wind Direction by Stability N .NNE NE ENE E ESE SE SSE S SSW SW WSW W WNdA NW NNWTOTAL -STABILITY CLASSES-0.00 0.48 0.29 0.10 0.14 0.14 0.29 0.10 0.10 0.00 0.19 0.38 0.43 0.29 0.43 0.10 3.43 Extremely Unstable 0.00 0.29 0.00 0.10 0.05 0.10 0.00 0.10 0.00 0.05 0.14 0.43 0.33 0.52 0.29 0.10 2.48 Moderately Unstable 0.14 0.29 0.10 O.O0 0.00 0.14 0.19 0.19 0.10 0.24 0.24 0.33 0.76 0.72 0.29 0.29 4.01 Slightly Unstable 1.34 2.19 1.38 1.86 2.10 2.53 0.81 3.77 1.62 3.53 4.20 4.20 4.63 4.29 3.72 1.81 43.97 Neutral 0.76 0.67 0.67 0.48 0.48 0.38 0.62 2.29 3.53 2.96 2.53 2.62 3.72 4.29 2.29 1.57 29.85 Slightly Stable 0.14 0.33 0.24 0.05 0.05 0.05 0.05 0.43 1.67 1.53 0.81 1.05 1.53 0.76 1.19 0.33 10.21 Moderately Stable 0.05 0.10 0.00 0.00 0.00 0.05 0.00 0.19 0.57 0.95 0.29 0.86 1.57 0.91 0.29 0.24 6.06 Extremely Stable Wind Direction by Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL -WIND SPEED CLASSES-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CAL M 0.48 0.43 0.48 0.05 0.14 0.38 0.19 0.19 0.57 1.34 0.81 0.91 1.53 0.95 0.52 0.48 9.44 < 3.5 mph 0.86 1.48 1.14 1.05 1.05 1.10 0.86 1.57 3.81 3.15 2.34 3.53 5.91 4.91 3.34 2.15 38.25 3.6 - 7.5 mph 0.76 2.00 0.72 0.33 1.34 1.38 0.72 2.62 2.81 2.96 2.81 4.01 3.62 3.96 4.01 1.43 35.48 7.6 - 12.5 mph 0.29 0.43 0.33 1.14 0.29 0.52 *0.19 2.15 0.38 1.81 2.38 1.43 1.67 1.72 0.62 0.38 15.74 12.6 - 18.5 mph 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.38 0.00 0.00 0.05 0.00 0.24 0.24 0.00 0.00 0.95 18.6 - 24.5 mph 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 > 24.5 mph

Zion Nuclear Station October-December. 2003 250 ft. Wind Speed and Direction 25OFt-33Ft Delta-T (F)

Number of Observations - 2190 Values are Percent Occurrence SPEED ..............--.--..------------- WIND DIRECTION CLASSES --------- STABILITY CLASSES ----------

CLASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL EU MU SU N SS MS ES TOTAL EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 C SU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 A N 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 L SS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MMS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 *0.00 0.00 0.00 0.00 0.00 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 o.od 0.00 0.00 0.00 0.00 0.00 EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1 SU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

- N 0.00 0.05 0.05' 0.05 0.00 0.05 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.05 0.05 0.00 0.37 0.37 3 SS 0.09 0.00 0.05 0.00 0.00 0.00 0.00 0.05 0.00 0.09 0.05 0.00 0.00 0.00 0.05 0.05 0.41 0.41 MS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.09 0.00 0.05 0.05 0.05 0.00 0.09 0.41 0.41 1.19 EU 0.00 0.00 0.05 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.14 0.14 MU 0.00 0.00 0.09 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.14 4 SU 0.00 0.05 0.00 0.00 0.00 0.00 0.09 0.05 0.00 0.05 0.00 0.00 0.05 0.00 0.05 0.05 0.37 0.37

- N 0.64 0.18 0.37 0.14 0.00 0.18 0.14 0.27 0.05 0.37 0.27 0.37 0.37 0.18 0.27 0.23 4.02 4.02 7 SS 0.18 0.23 0.27 0.18 0.14 0.23 0.14 0.05 0.32 0.37 0.09 *0.09 0.05 0.37 0.05 0.05 2.79 2.79 MS 0.05 0.09 0.05 0.05 0.00 0.05 0.05 0.05 0.05 0.05 0.05 0.05 0.00 0.05 0.05 0.09 0.73 0.73 ES 0.14 0.05 0.00 0.05 0.00 0.09 0.05 0.05 0.37 0.14 0.05 0.05 0.09 0.05 0.09 0.14 1.37 1.37 9.54 EU 0.18 0.37 0.00 0.05 0.09 0.14 0.32 0.00 0.05 0.00 0:00 0.05 0.09 0.09 0.05 0.00 1.46 1.46 MU 0.05 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.05 0.14 0.09 0.09 0.14 0.00 0.00 0.64 0.64 B SU 0.09 0.05 0.00 0.00 0.00 0.05 0.05 0.05 0.05 0.09 0.09 0.37 0.05 0.09 0.14 0.05 1.19 1.19

- N 0.46 0.18 0.18 0.68 0.55 0.32 0.27 0.59 0.41 0.73 1.10 0.87 1.32 1.10 0.78 0.41 9.95 9.95 1 SS 0.05 0.09 0.18 0.09 0.18 0.23 0.18 0.46 0.46 0.41 1.10 0.64 0.78 0.32 0.32 0.23 5.71 5.71 2MS 0.09 0.09 0.27 0.18 0.09 0.09 0.00 0.14 0.14 0.14 0.18 0.46 0.14 0.09 0.09 0.23 2.42 2.42 ES 0.09 0.05 0.14 0.09 0.09 0.09 0.14 0.05 0.23 0.09 0.18 0.23 0.05 0.09 0.00 0.09 1.69 1.69 23.06 EU 0.09 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.32 0.23 0.14 0.23 0.05 0.00 1.19 1.19 1IMU 0.05 0.09 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.23 0.09 0.37 0.32 0.05 0.00 1.28 1.28 3 SU 0.14 0.05 0.00 0.00 0.00 0.00 0.05 0.05 0.05 0.00 0.14 0.09 0.41 0.23 0.14 0.09 1.42 1.42 MN 0.87 0.05 0.14 0.41 0.68 0.73 0.82 1.10 0.73 1.32 2.01 1.96 1.92 2.42 1.46 0.18 16.80 16.80 1ISS 0.18 0.09 0.09 0.09 0.09 0.09 0.46 0.91 0.87 1.14 1.37 1.46 1.96 1.46 1.74 0.82 12.83 12.83 8MS 0.23 0.00 0.05 0.09 0.00 0.05 0.00 0.55 0.78 0.91 0.37 0.59 0.55 0.41 0.64 0.05 5.25 5.25 ES 0.00 0.00 0.00 0.05 0.00 0.00 0.05 0.27 0.23 0.18 0.27 0.32 0.41 0.05 0.18 0.00 2.01 2.01 40.78

Zion Nuclear Station October-Decerrber. 2003 250 ft. Wind Speed and Direction 25OFt-33Ft Delta-T (F)

SPEED ---------------------------------- WIND DIRECTION CLASSES ------------ - --------- STABILITY CLASSES ----------

CLASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL EU IU SU N SS MS ES TOTAL 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.18 0.14 0.09 0.05 0.00 0.00 0.50 0.50 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.05 0.05 0.00 0.09 0.00 0.27 0.27 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.05 0.14 0.14 0.09 0.09 0.09 0.00 0.68 0.68 0.14 0.59 *0.41 0.91 0.23 0.27 0.59 0.87 0.32 1.00 1.64 1.64 0.87 0.96 0.59 0.09 11.14 11.14 0.32 0.05 0.00 0.00 0.23 0.14 0.18 0.68 0.82 0.91 0.73 0.82 0.68 0.32 0.05 0.09 6.03 6.03 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.23 0.23 0.05 0.18 0.32 0.05 0.00 0.09 0.00 1.14 1.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.18 0.00 0.18 0.05 0.14 0.00 0.05 0.00 0.59 0.59 20.37 EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 G MU 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.09 0.00 0.00 0.23 0.23 T SU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.14 0.09 0.05 0.00 0.00 0.32 0.32 N 0.05 0.09 0.14 0.00 0.00 0.00 0.00 0.23 0.00 0.32 0.46 0.68 0.23 0.37 0.05 0.00 2.60 2.60 2 SS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.55 0.27 0.14 0.09 0.18 0.09 0.41 0.00 0.00 1.74 1.74 4 MS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.18 0.18 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 5.07.

TOT 4.16 2.65 2.51 3.11 2.47 2.79 3.74 7.40 6.80 8.77 11.78 12.19 11.28 10.09 7.26 3.01 100.00 3.29 2.56 3.97 44.89 29.50 9.73 6.07 100.00 Wind Direction by Stability N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL -STABILITY CLASSES-0.27 0.50 0.05 0.05 0.09 0.14 0.37 0.00 0.09 0.00 0.50 0.41 0.32 0.37 0.14 0.00 3.29 Extremely Unstable 0.09 0.14 0.09 0.00 0.09 0.00 0.05 0.05 0.05 0.05 0.50 0.23 0.55 0.55 0.14 0.00 2.56 Moderately Unstable 0.23 0.14 0.00 0.00 0.00 0.05 0.27 0.14 0.09 0.23 0.37 0.73 0.68 0.46 0.41 0.18 3.97 Slightly Unstable 2.15 1.14 1.28 2.19 1.46 1.55 1.83 3.06 1.51 3.79 5.53 5.53 4.70 5.07 3.20 0.91 44.89 Neutral 0.82 0.46 0.59 0.37 0.64 0.68 0.96 2.69 2.74 3.06 3.42 3.20 3.56 2.88 2.19 1.23 29.50 Slightly Stable 0.37 0.18 0.37 0.32 0.09 0.18 0.05 1.10 1.23 1.14 0.78 1.42 0.73 0.55 0.87 0.37 9.73 Moderately Stable 0.23 0.09 0.14 0.18 0.09 0.18 0.23 0.37 1.10 0.50 0.68 0.68 0.73 0.23 0.32 0.32 6.07 Extremely Stable Wind Direction by Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL -WIND SPEED CLASSES-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CALM 0.09 0.05 0.09 0.05 0.00 0.05 0.00 0.05 0.09 0.23 0.09 0.05 0.05 0.09 0.09 0.14 1.19 < 3.5 mph 1.00 0.59 0.82 0.41 0.14 0.55 0.55 0.46 0.78 0.96 0.46 0.55 0.55 0.64 0.55 0.55 9.54 3.6 - 7.5 nph 1.00 0.82 0.78 1.10 1.10 0.91 0.96 1.28 1.32 1.51 2.79 2.69 2.51 1.92 1.37 1.00 23.06 7.6 - 12.5 mph 1.55 0.37 0.27 0.64 0.78 0.87 1.37 2.92 2.74 3.56 4.70 4.75 5.75 5.11 4.25 1.14 40.78 12.6 - 18.5 mph 0.46 0.68 0.41 0.91 0.46 0.41 0.87 1.78 1.55 2.01 3.15 3.15 1.96 1.42 0.96 0.18 20.37 18.6 - 24.5 mph 0.05 0.14 0.14 0.00 0.00 0.00 0.00 0.91 0.32 0.50 0.59 1.00 0.46 0.91 0.05 0.00 5.07 > 24.5 mph

Zion Nuclear Station January-Decenibr. 2003 35 ft. Wind Speed and Direction 250Ft-33Ft Delta-T (F)

Nwrrber of Observations - 8326 Values are Percent Occurrence SPEED ------------------ WIND DIRECTION CLASSES------------------ STABILITY CLASSES------ -

CLASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL EU MU SUN Ss MS ES TOTAL.

EU 0.00 0.00 0.00 I2.00I 0.00 0.00 0.00 0.00 0.00 0.00I D.00 0.00 0.00 0.00I 1.00 0.00 0.00 0.00 MUi 0.00 0.00 0.00 I2.00I 0.00 0.00 0.00 0.00 0.00 0.00I D.00 0.00 0.00 0.00I D. 00 0.00 0.00 0.00 C SU 0.00 0.00 0.00I 2.00 0.00 0.00 0.00~ 0.00 0.00 0.00I 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 A N 0.00 .0.00 0.00I 2.00 D.00 0.00 0.00 0.00 0.00 0.00I 0.00 0.00 0.00 0.00I 0.00 0.00 0.00 0.00 L SS 0.00 0.00 0.00I D.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MMS 0.00 0.00 0.00I D.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ES 0.00 0.00 0.00 1.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 EU 0.00 0.00 0.00 0.01 0.01 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.02 0.06 0.06 MU 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.02 0.02 1 SU 0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.01 0.01 0.00 0.01 .0.01 0.00 0.00 0.06 0.06

- N 0.07 0.13 0.12 0.01 0.04 0.12 0.10 0.04 0.07 0.05 0.02 0.05 0.06 0.14 0.12 0.06 1.20 1.20 3 SS 0.31 0.23 0.22 0.01 0.18 0.23 0.18 0.18 0.38 0.30 0.29 0.30 0.23 0.56 0.31 0.22 4.13 4.13 MS 0.18 0.16 0.11 0.06 0.05 0.05 0.04 0.06 0.30 0.60 0.43 0.38 0.44 0.37 0.23 0.16 3.62 3.62 ES 0.06 0.06 0.00 0.01 0.04 0.04 0.00 0.10 0.34 0.70 0.60 0.53 0.60 0.31 0.08 0.11 3.57 3.57 12.66 EU 0.05 0.36 *0.30 0.23 0.25 0.20 0.23 0.14 0.02 0.00 0.04 .0.02 0.12 0.13 0.08 0.04 2.22 2.22 MU 0.01 0.10 0.11 0.06 0.04 0.10 0.04 0.05 0.01 0.01 0.02 0.02 0.08 0.05 0.04 0.00 0.73 0.73 4 SU 0.07 0.23 0.16 0.06 0.11 0.12 0.13 0.07 0.05 0.04 0.05 0.05 0.08 .0.11 0.06 0.05 1.43 1.43

- N 0.65 1.24 0.65 0.44 0.47 0.40 0.55 0.79 0.62 0.48 0.54 0.68 0.98 0.79 0.83 0.47 10.59 10.59 7 SS 1.33 1.02 0.67 0.44 0.31 0.58 0.88 0.91 1.42 0.85 1.00 1.17 1.81 1.49 1.29 0.66 15.83 15.83 MS 0.32 0.12 0.11 0.11 0.08 0.17 0.22 0.32 1.19 0.90 0.48 0.49 0.67 0.40 0.61 0.26 6.46 6.46 ES 0.05 0.02 0.02 0.05 0.07 0.11 0.04 0.37 0.90 0.29 0.22 0.37 0.64 0.54 0.12 0.04 3.84 3.84 41.11 EU 0.37 1.09 0.24 0.04 0.04 0.06 0.18 0.11 0.05 0.06 0.26 0.32 .0.41 0.38 0.24 0.06 3.92 3.92 MU 0.13 0.26 0.01 0.01 0.01 0.01 0.04 0.13 0.02 0.08 0.10 0.23 0.25 0.28 0.23 .0.05 1.85 1.85 8 SU 0.36 0.20 0.02 0.00 0.01 0.04 0.04 0.18 0.04 0.01 0.25 0.18 0.29 0.38 0.30 0.16 2.46 2.46

- N 1.57 1.72 0.61 0.28 0.34 0.42 0.22 0.92 0.40 0.74 1.17 1.53 1.06 1.37 1.96 1.03 15.33 15.33 1 Ss 1.60 0.26 0.17 0.14 0.12 0.20 0.31 0.67 0.65 0.64 0.74 0.85 1:1o 0.96 0.43 0.37 9.24 9.24 2MS 0.00 0.01 0.00 0.01 0.02 0.02 0.05 0.29 0.20 0.06 0.04 0.04 0.08 0.00 0.00 0.00 0.83 0.83 ES 0.00 0.01 0.02 0.06 0.04 0.01 0.05 0.29 0.16 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.64 0.64 34.25 EU 0.32 0.25 0.07 0.06 0.00 0.00 0.00 0.00 0.00 0.05 0.16 0.08 0.08 0.06 0.02 0.04 1.20 1.20 1MU 0.07 0.02 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.07 0.07 0.10 0.07 0.02 0.02 0.47 0.47 3 SU 0.07 0.04 0.07 0.00 0.01 0.00 0.01 0.00 0.00 0.08 0.11 0.10 0.14 0.12 0.08 0.02 0.86 0.86

- N 0.70 0.32 0.94 0.48 0.08 0.13 0.04 0.42 0.05 0.29 0.84 0.54 0.42 0.52 0.25 0.26 6.28 6.28 1ISs 0.18 0.02 0.04 0.00 0.05 0.01 0.01 0.18 0.06 0.29 0.44 0.17 0.17 0.24 0.OE;0.01 1.93 .1.93 8MS 0.00 0.01 I0.00 0.00 0.01 .0.00 0.00 0.01 0.01 0.00 0.00 0.00 0.00 0.00 0.0cc I0.00 0.04 0.04 ES 0.00 0.01I0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.cc I0.00 0.01 0.01 10.80

Zion Nuclear Station January-December. 2003 35 ft. Wind Speed and Direction 250Ft-33Ft Delta-T (F)

SPEED ------------------ WIND DIRECTION CLASSES ------------ --------- STABILITY CLASSES ----------

CLASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL EU MU SU N SS MS ES TOTAL EU 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 '0.00 0.02 0.02 I MU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 9 SU 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.02 0.00 0.00 0.00 0.00 0.00 0.04 0.04

- N 0.18 0.00 0.17 0.23 0.00 0.00 0.00 0.04 0.00 0.00 0.07 0.14 0.08 0.04 0.00 0.00 0.95 0.95 2 SS 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.04 0.00 0.00 0.00 0.00 0.00 0.02 0.00 0.00 0.07 0.07 4MS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.02 0.02 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 *0.00 0.00 0.00 0.00 0.00 1.10 EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 GMU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 T SU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.01 *0.01 N 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.04 0.04 2 SS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.02 0.00 0.00 0.00 p.00 0.00 0.00 0.00 0.00 0.02 0.02 4MS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.07 TOT B.73 7.89 4.85 2.B2 2.38 3.05 3.33 6.38 6.94 6.53 7.98 8.34 9.93 9.36 7.37 4.12 100.00 7.42 3.07 4.86 34.39 31.23 10.97 8.06 100.00 Wind Direction by Stability N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW Rd NNWTOTAL -STABILITY CLASSES-0.77 1.71 0.61 0.34 0.30 0.28 0.41 0.25 0.07 0.11 0.46 0.43 0.61 0.58 0.35 0.16 7.42 Extremely Unstable 0.22 0.38 0.14 0.07 0.05 0.11 0.07 0.18 0.04 0.10 0.19 0.32 0.43 0.40 0.29 0.08 3.07 Moderately Unstable 0.52 0.47 0.25 0.07 0.13 0.16 0.18 0.25 0.08 0.14 0.44 0.34 0.53 0.62 0.44 0.23 4.86 Slightly Unstable 3.19 3.41 2.49 1.44 0.92 1.07 0.90 2.22 1.14 1.56 2.64 2.94 2.61 2.86 3.16 1.83 34.39 Neutral 3.42 1.54 1.09 0.60 0.66 1.03 1.38 2.01 2.51 2.08 2.47 2.49 3.31 3.28 2.09 1.26 31.23 Slightly Stable 0.50 0.29 0.22 0.18 0.17 0.24 0.30 0.71 1.71 1.56 0.95 0.91 1.20 0.77 0.84 0.42 10.97 Moderately Stable 0.11 0.10 0.05 0.12 0.14 0.17 0.08 0.76 1.39 0.98 0.82 0.90 1.24 0.85 0.20 0.14 8.06 Extremely Stable Wind Direction by Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW . NW NNW TOTAL -WIND SPEED CLASSES-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CALM 0.62 0.58 0.46 0.12 0.31 0.44 0.31 0.37 1.09 1.66 1.36 1.26 1.35 1.41 0.74 0.58 12.66 c 3.5 mph 2.49 3.09 2.02 1.39 1.33 1.67 2.08 2.67 4.22 2.57 2.34 2.81 4.40 3.51 3.03 1.51 41.11 3.6 - 7.5 mph 4.04 3.57 1.08 0.54 0.58 0.77 0.88 2.59 1.51 1.60 2.56 3.15 3.19 3.37 3.16 1.67 34.25 7.6 - 12.5 rph 1.35 0.66 1.13 0.54 0.16 0.16 0.06 0.61 0.12 0.71 1.62 0.96 0.91 1.01 0.44 0.36 10.80 12.6 -18.5 ,ph 0.22 0.00 0.17 0.23 0.00 0.01 0.00 0.10 0.00 0.00 0.10 0.14 0.08 0.06 0.00 0.00 1.10 18.6 -24.5 mph 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.04 0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.07 > 24.5 miph

Zion Nuclear Station January-December. 2003 250 ft. Wind Speed and Direction 250Ft-33Ft Delta-T (F)

Number of Observations - 8403 Values are Percent Occurrence SPEED ---------------------------------- WIND DIRECTION CLASSES ---------------------------------- --------- STABILITY CLASSES ----------

CLASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL EU MJ SU N SS MS ES TOTAL EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MJ 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 C SU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 A N 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 L SS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 M MS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 EU 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.02 0.02 MU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.01 0.01 1 SU 0.00 0.00 0.01 0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.02 0.00 0.00 0.00 0.01 0.00 0.06 0.06

- N 0.02 0.05 0.05 0.04 0.00 0.01 0.06 0.01 0.00 0.04 0.02 0.00 0.02 0.01 0.04 0.01 0.38 0.38 3 SS 0.06 0.00 0.07 0.01 0.01 0.00 0.06 0.07 0.02 0.06 0.06 0.01 0.00 0.02 0.02 0.05 0.54 0.54 MS 0.00 0.02 0.02 0.00 0.07 0.02 0.01 0.02 0.01 0.00 0.02 0.01 0.01 0.01 0.00 0.00 0.25 0.25 ES 0.01 0.04 0.05 0.02 0.04 0.00 0.00 0.01 0.06 0.06 0.01 0.01 0.02 0.05 0.05 0.10 0.52 0.52 1.79 EU 0.02 0.07 0.08 0.06 0.12 0.06 0.06 0.04 0.01 0.00 0.02 0.02 0.05 0.01 0.02 0.01 0.67 0.67 MU 0.01 0.05 0.10 0.02 0.00 0.05 0.04 0.00 0.01 0.00 0.00 0.02 0.00 0.00 0.00 0.01 0.31 0.31 4 SU 0.01 0.08 0.05 0.04 0.08 0.05 0.05 0.04 0.00 0.02 0.01 0.01 0.02 0.05 0.01 0.01 0.54 0.54

- N 0.30 0.30 0.32 0.15 0.11 0.14 0.30 0.26 0.05 0.14 0.13 0.23 0.20 0.23 0.19 0.15 3.20 3.20 7 SS 0.14 0.38 0.31 0.29 0.13 0.33 0.13 0.15 0.17 0.21 0.25 0.15 0.14 0.21 0.07 0.13 3.21 3.21 MS 0.10 0.20 0.11 0.04 0.06 0.07 0.10 0.17 0.11 0.04 0.07 0.11 0.07 0.08 0.06 0.07 1.44 1.44 ES 0.12 0.12 0.05 0.06 0.05 0.07 0.07 0.14 0.17 0.14 0.07 0.07 0.10 0.06 0.07 0.23 1.58 1.58 10.95 EU 0.24 0.69 0.31 0.17 0.10 0.11 0.39 0.06 0.02 0.01 0.08 0.10 0.15 0.13 0.04 0.01 2.61 2.61 MU 0.04 0.06 0.05 0.00 0.05 0.01 0.07 0.05 0.01 0.02 0.08 0.07 0.12 0.07 0.05 0.00 0.75 0.75 8 SU 0.14 0.20 0.04 0.01 0.01 0.06 0.15 0.10 0.02 0.04 0.06 0.18 0.05 0.14 0.12 0.04 1.36 1.36

- N 0.56 0.75 0.21 0.25 0.24 0.17 0.63 0.67 0.29 0.43 0.60 0.68 0.80 0.61 0.63 0.40 7.90 7.90 I SS 0.44 0.65 0.35 0.25 0.29 0.42 0.94 0.69 0.42 0.49 0.89 0.60 0.64 0.57 0.61 0.40 8.64 8.64 2 MS 0.32 0.18 0.13 0.14 0.10 0.17 0.24 0.43 0.49 0.29 0.36 0.30 0.24 0.10 0.17 0.31 3.94 3.94 ES 0.12 0.04 0.06 0.04 0.06 0.06 0.11 0.18 0.60 0.48 0.35 0.20 0.15 0.05 0.04 0.08 2.59 2.59 27.79 EU 0.68 0.26 0.00 0.04 0.04 0.00 0.10 0.08 0.01 0.12 0.29 0.31 0.27 0.19 0.13 0.02 2.53 2.53 1MU 0.24 0.06 0.00 0.01 0.00 0.00 0.02 0.07 0.02 0.06 0.14 0.13 0.26 0.25 0.13 0.02 1.43 1.43 3 SU 0.33 0.05 0.02 0.00 0.01 0.00 0.02 0.06 0.05 0.04 0.23 0.13 0.26 0.31 0.15 0.13 1.80 1.80

- N 1.38 0.83 0.37 0.36 0.29 0.24 0.37 0.76 0.42 0.63 1.26 1.54 0.99 1.42 1.38 0.63 12.85' 12.85 1 SS 1.19 0.57 0.29 0.19 0.15 0.23 0.37 0.77 0.76 0.88 1.07 1.25 1.64 1.30 1.23 0.51 12.40 12.40 8MS 0.24 0.06 0.02 0.05 0.04 0.13 0.05 0.60 0.70 0.63 0.48 0.31 0.39 0.14 0.25 0.15 4.24 4.24 ES 0.04 0.01 0.01 0.02 0.01 0.07 0.07 0.17 0.77 0.63 0.45 0.15 0.18 0.07 0.08 0.05 2.80 2.80 38.05

Zion Nuclear Station January-Decerber. 2003 250 ft. Wind Speed and Direction 250Ft-33Ft Delta-T (F)

SPEED ---------------------------------- WIND DIRECTION CLASSES .------------ --------- STABILITY CLASSES ----------

CLASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL EU MU SU N SS MS ES TOTAL EU 0.38 0.10 0.05 0.04 0.00 0.00 0.00 0.00 0.01 0.02 0.18 0.12 0.13 0.11 0.04 0.00 1.17 1.17 IHU 0.08 0.01 0.00 0.00 0.00 0.00 0.00 0.01 0.01 0.02 0.07 0.06 0.06 0.00 0.05 0.01 0.39 0.39 9 SU 0.13 0.01 0.00 0.00 0.01 0.00 0.04 0.02 0.00 0.05 0.12 0.13 0.07 0.07 0.08 0.02 0.76 0.76

- N 0.82 0.69 0.57 0.39 0.06 0.08 0.17 0.31 0.18 0.38 0.87 0.75 0.43 0.65 0.50 0.27 7 13 7.13 2 SS 0.88 0.13 0.10 0.04 0.12 0.14 0.19 0.36 0.30 0.39 0.69 0.61 0.55 0.35 0.11 0.07 5.01 5.01 4MS 0.00 0.00 0.00 0.01 0.01 0.06 0.01 0.32 0.17 0.06 0.15 0.10 0.02 0.00 0.04 0.00 0.95 0.95 ES 0.00 0.00 0.00 0.04 0.04 0.07 0.02 0.12 0.15 0.05 0.06 0.02 0.05 0.00 0.01 0.00 0.63 . 0.63 16.04 EU 0.26 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.02 0.01 0.00 0.01 0.00 0.00 0.33 0.33 G MU 0.05 0.01 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.02 0.02 0.04 0.05 0.02 0.00 0.23 0.23 T SU 0.06 0.00 0.07 0.00 0.00 0.00 0.00 0.00 0.00 0.04 0.04 0.05 0.02 0.06 0.01 0.00 0.35 0.35 N 0.63 0.17 0.61 0.17 0.00 0.00 0.00 0.06 0.00 0.14 0.21 0.43 0o11 0.26 0.06 0.01 2.86 2.86 2 SS 0.14 0.02 0.01 0.01 0.06 0.07 0.04 0.20 0.07 0.08 0.20 0.08 0.13 0.17 0.05 0.00 1.34 1.34 4 MS 0.00 0.00 0.00 0.01 0.02 0.02 0.04 0.06 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.17 0.17 ES 0.00 0.00 0.00 0.01 0.01 0.04 0.02 0.01 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.12 0.12 5.39 TOT 10.19 6.87 4.50 2.96 2.37 2.96 4.94 7.07 6.12 6.70 9.68 8.97 8.40 7.81 6.53 3.94 100.00 7.33 3.12 4.86 34.32 31.14 10.98 8.25 100.00 Wind Direction by Stability N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW N NNWTOTAL -STABILITY CLASSES-1.58 1.12 0.45 0.30 0.25 0.18 0.55 0.18 0.06 0.17 0.60 0.56 0.61 0.45 0.24 0.05 7.33 Extremely Unstable 0.42 0.19 0.15 0.04 0.05 0.06 0.13 0.13 0.06 0.11 0.32 0.31 0.48 0.37 0.26 0.05 3.12 Moderately Unstable 0.68 0.35 0.19 0.05 0.12 0.11 0.27 0.21 0.07 0.18 0.48 0.50 0.43 0.63 0.39 0.20 4.86 Slightly Unstable 3.71 2.78 2.13 1.36 0.69 0.64 1.52 2.07 0.93 1.76 3.09 3.62 2.55 3.18 2.80 1.49 34.32 Neutral 2.86 1.76 1.12 0.79 0.76 1.19 1.73 2.25 1.74 2.12 3.17 2.70 3.11 2.62 2.08 1.17 31.14 Slightly Stable 0.65 0.46 0.29 0.25 0.30 0.48. 0.44 1.59 1.49 1.01 1.08 0.82 0.74 0.33. 0.51 0.54 10.98 Moderately Stable 0.29 0.20 0.17 0.19 0.20 0.31 0.30 0.63 1.77 1.36 0.94 0.46 0.50 0.23 0.25 0.45 8.25 Extremely Stable Wind Direction by Wind Speed N NNE NE ENE E ESE SE SSE S SSW. SW WSW . W WNW NW NNW TOTAL -WIND SPEED CLASSES-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CALM 0.10 0.11 0.20 0.07 0.12 0.05 0.14 0.12 0.10 0.15 0.14 0.04 0.06 0.10 0.14 0.15 1.79 < 3.5 mph 0.70 1.20 1.01 0.65 0.55 0.77 0.74 0.80 0.51 0.56 0.56 0.62 0.58 0.64 0.43 0.62 10.95 3.6 - 7.5 rph 1.86 2.57 1.14 0.86 0.83 0.99 2.53 2.17 1.84 1.75 2.42 2.12 2.15 1.67 1.64 1.25 27.79 7.6 - 12.5 mph 4.09 1.84 0.71 0.67 0.54 0.67 1.00 2.51 2.74 2.99 3.92 3.82 4.00 3.68 3.36 1.52 38.05 12.6 - 18.5 mph 2.30 0.94 0.71 0.51 0.24 0.36 0.43 1.14 0.82 0.98 2.14 1.79 1.31 1.18 0.82 0.38 16.04 18.6 - 24.5 mph 1.14 0.20 0.71 0.20 0.10 0.13 0.10 0.33 0.11 0.27 0.50 0.60 0.30 0.55 0.14 0.01 5.39 > 24.5 mph

1%

ATTACHMENT 3 Radioactive Effluent Release Report Summary of Changes to the ODCM During the calendar year of 2003 there were three changes made to the ODCM. The data processed for 2003 was in accordance with the methodology in this document.

Included in this Annual Report is a copy a ODCM at an end date of 12/31/2003. There were three changes made to the ODCM during the 2003 calendar year and can be tracked by the technical review numbers assigned by the station. The technical review numbers are 1.) TR/006/2003 2.) TR/008/2003 3.) TR/O 10/2003 and there are copies of the complete technical review attached to this report.

f..

April 18,2003 TR No: TR/006/2003 To: Art Daniels Decommissioning Plant Manager

Subject:

Qualified Technical Review of Offsite Dose Calculation Manual (ODCM)

Revision Pursuant to ODCM Section 12.7.3 and Technical Specifications 5.6.1 and 5.9.1, the following provides the basis for the revisions to the ODCM and documentation of the';; - -

Qualified Technical Review. Section 12.7.3 of the ODCM requires a Qualified Technical Review for revisions to the ODCM.

This review shall be performed by individual(s) with the appropriate ANSI disciplines and approved by the Decommissioning Plant Manager, thereby satisfying the requirements of the Qualified Technical Review.

This change will become effective once Exempt Change 341418, Bypass Lake Discharge Tank and Piping, has been-declared operational.

Prepared by: ! ia a -t /e -a

/.i£ Ashley Date

TI TR No: TR/006/2003 Qualified Technical Review: Disciplines Required: A, B, D, G Signatur- < 92:---_'03 Signature Disciplines Date Da e D3I; Signature Disciplines Date Signature Disciplines Date 4 .,

I -concur and 'approve: l I 6 Daniels

Decommissioning Plant Manager I; - , Zion Station Distribution

Ron Schuster Ray Landrum Jim Ashley ,

Bob Adams Mike Petersen (SRC Coordinator) _,

Master File

TR No: TR/006/2003 Technical Justification This ODCM revision is necessary to reflect the installation of Exempt Change No.

341418. This exempt change reroutes liquid effluent from the Boric Acid Monitor Tanks (BAMT) through ORT-PRO5 and OFCV-WDIO prior to release into the lake discharge canal. The Lake Discharge Tank (LDT) and associated piping have been abandoned due to excessive Microbiologically Induced Corrosion (MIC). The exempt change was subject to the site 10 CFR 50.59 review process.

The function of the liquid waste management system, as discussed in DSAR Section 4.5.2, is to collect, store, process, monitor, and dispose of liquid radioactive waste from the station. The overall purpose is to ensure releases to the lake do not exceed any concentration release limit and liquid releases to the public are ALARA. Control of the liquid waste releases will remain unchanged as a result of this design change. A radiation detector will continue to monitor the effluent prior to release to the lake. Upon detection of abnormal radiation levels by the process radiation dttector, a valve closes to isolate the release to the lake and an associated alarm signal is actuated. Additionally, administrative procedural controls equivalent to those currently in pldce for the Lake Discharge Tanks releases will be in place to ensure proper control of liquid effluent releases to the lake.

Minor revisions to the DSAR and the ODCM are necessary to reflect the new system configuration resulting from this design change.

DSAR Section 4.5.2 discusses how liquid waste releases are performed and controlled.

Controls are required to ensure all inputs to the tank being released are isolated prior to sampling the tank for release. The tank must be recirculated prior to sampling to ensure uniformity of the sample being analyzed for radio-isotopic profile. The discharge flow path is also isolated using positive control measures when a release is not in progress.

Discharge flow rates are controlled to ensure that liquid effluents leaving the plant do not exceed any concentration release limits. Procedure changes are required and will be in place to ensure that these controls are maintained. These procedure changes will account for the altered release configuration which utilizes the BAMT for effluent storage prior to release to the lake. The BAMT essentially will provide the same function previously provided by the abandoned LDTs. These procedural controls will ensure that there is no adverse affect on how liquid waste releases are performed and controlled.

The methodology used to ensure the liquid waste releases do not exceed any concentration release limits is defined in ODCM Chapter 1O. The altered system configuration resulting from this design change essentially only changes the storage location for the batch releases being analyzed for discharge to the lake. It does not adversely impact or invalidate the methodology described in the ODCM. Minor revisions to the DSAR and the ODCM are necessary to reflect the new system configuration resulting from this design change.

TR No: TRJ006/2003 Radiological control of the liquid effluent using the altered release configuration remains unchanged. Continuous radiation monitoring and automatic isolation of releases remain in place for the liquid being processed. This change will maintain the required level of radioactive effluent control and does not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

The following Table summarizes the ODCM changes:

Page/Section Change Summary 10-iii Replace LDT reference with BAMT.

10-iv Delete 10-3. Pump flow capacity chart is no longer required.

10-4/10.2.1.1 Replace LDT reference with BAMT. Change tank capacity from 30,000 gallons to 21,600 gallons to reflect BAMT capacity. Change two LDTs to four BAMTs to reflect the number of BAMTs available.

10-4/10.2.2.1 Replace LDT reference with BAMT. Delete reference to Radiation Monitor ORT-PRO4 which has been abandoned in place.

10-5/10.2.3.1 Replace LDT reference with BAMT.

10-6/10.2.3.2.1 Replace LDT reference with BAMT.

10-7/10.2.3.6 Delete Liquid Dilution Flow Rate discussion. It is no longer necessary to determine dilution flow by summing running pumps. Dilution flow is determined by the flow through the CC Hx as identified in ZCP 421-1 10-10/Table 10-3 Delete Table 10-3. Pump flow capacity chart is no longer required. It is no longer necessary to determine dilution flow by summing flows from running pumps. Dilution flow is determined by the flow through the CC Hx as identified in ZCP 421-1.

12-6/Table 12.2-1 Replace LDT references with BAMT. Delete reference to Radiation monitor ORT-PRG4 which has been abandoned in place. Delete references to Flow Indicators OF-WD63 and OF-WD67 which have been abandoned in place.

12-7/Table 12.2-1 Replace LDT reference with BAMT.

12-8/Table 12.2-2 Replace LDT reference with BAMT. Delete reference to Radiation Monitor ORT-PRO4 which has been abandoned in place. Delete references to Flow Indicators OF-WD63 and OF-WD67 which have been abandoned in place.

12-20/Table 12.3-2 Replace LDT reference with BAMT.

12-54/12.7.4 Change DSAR update frequency from annual to biennial to reflect current DSAR update requirements.

ATTACHMUEN'T C: 50.59 REVIEW COVERSHEET FORM Station: Zion Station Activity/D)ocumcnt Numl)er: Misc. document revisions associated with EC No. 341418 Reision Number: 0 Titic: Misc document revisions due to FC No. 34141 ;. iypass Lake Dischargc Tank and Associated Lipin NOTE: For 50.59 Evaluations, information on this form will provide the basis for preparing the biennial summary report submitted to the NRC in accordance with the requirements of 10 CFR 50.59(d)(2).

Description of Activity:

(Provide a brief, concise description of what the proposed activity involves.)

Revise sitc documents to reflect the installation of Exempt Change No. 341418. This exempt change will reroute liquid effluent releases from the Boric Acid Monitor Tanks through ORT-PRO5 and OFCV-WDIO prior to release into the discharge canal. The Lake Discharge Tank and associated discharge piping will be bypassed and abandoned due continued Microbiologically Induced Corrosion (MIC). Impacted documents are: ODCM Chapters 10 and 12, DSAR Chapter 4, OR-PRO5, ZCP 421-1, PT-26, SOI-3V series, S01-3 Appendix C, SOI-67E1, SO1 67E2, SOI-67F1, SOI-67F2, Unit OARM (Section OEL-AN 13), and AOP 5.1.

Reason for Activity:

(Discuss why the proposed activity is being performed.)

The Lake Discharge Tank and associated piping has degraded due to MIC. The degradation is extensive and system repairs are not recommended. The document changes are being made to reflect the design change.

Effect of Activity:

(Discuss bow the activity impacts plant operations, design bases, or safety analyses described in the UFSAR.)

Radiological control of the liquid effluent using the altered release configuration remains unchanged. Continuous radiation monitoring and automatic isolation of releases remain in place for the liquid being processed. Minor changes to address the altered configuration will need to be made to the DSAR and the ODCM. Additionally, site procedure changes are required to address th.z new configuration.

Summary of Conclusion for the Activity's 50.59 Rcview:

(Provide justification for the conclusion, including sufficient detail to recognize and understand the essential arguments leading to tile conclusion. Provide more than a simple statement that a 50.59 Screening, 50.59 Evaluation, or a License Amendment Request, as applicable, is not required.)

A 50.59 screening has been prepared to assess the impact of the design change. It has been concluded that the overall function of the liquid effluent system is not changed by this modification. The document changes are necessary to address the new effluent relcase configuration.

Attachments:

Attach all 50.59 Reviews forms completed. as appropriate.

(NOTE: if both a Screening and Evaluation are completed, no Screening No. is required.)

ATTACHMENT C: 50.59 REVIEW COVERSHEET FORM Station: Zion Station Activity/Document Number: Misc. document revisions associated with EC No. 34141 8 Revision Number: 0

Title:

Misc documncti revisions due to ECNo. 341418. Byvnass lake Discliarge Tank and Associatcd Piinig c _ , _

Forms Attached: (Check all that apply.)

H

_- Applicability Review 50.59 Screening 50.59 Evaluation 50.59 Screening No.

50.59 Evaluation No.

2003-0009 Rev.

Rev.

0

ATTACHMENT E: 50.59 SCREEINING FORM 50.59 Screening No. 2003-0009 Rev. No. 0 Activity/Document Number: Misc. document revisions due to IEC No. 341418 Revision Number: 0

1. 50.59 Screening Qucstions (Check correct response and provide separate written response providing the basis for the answer to cach question) (Sec Section 5 of the Resource Manual (RM) for additional guidance):

I Does the proposed Activity involve a change to an SSC that adversely affects an UFSAR YES X NO described design function? (See Section 5.2.2.1 of the RM)

The function of the liquid waste management system, as discussed in DSAR Section 4.5.2, is to collect, store, process, monitor, and dispose of liquid radioactive waste from the station. The overall purpose is to ensure releases to the lake do not exceed any concentration release limit (IOCFR20 limits) and liquid releases to the public are ALARA. Control of the liquid waste releases will remain unchanged as a result of this modification. A radiation detector will continue to monitor the effluent prior to release to the lake. Upon detection of abnormal radiation levels by the process radiation detector, a valve closes to isolate the release to the lake and an associated alarm signal is actuated.

Additionally, administrative procedural controls equivalent to those currently in place for the Lake Discharge Tanks releases will be in place to enspre proper control of liquid .

effluent releases to the lake. Minor revisions to the DSAR and the ODCM are necessary to reflect the new system configuration resulting from this design change.

2. Does the proposed Activity involve a change to a procedure that adversely affects how _ YES XNO UFSAR described SSC design functions are performed or controlled? (See Section 5.2.2.2 of the RM)

DSAR Section 4.5.2 discusses how liquid waste releases are performed and controlled.

Controls are required to ensure all inputs to the tank being released are isolated prior to sampling the tank for release. The tank must be recirculated prior to sampling to ensure uniformity of the sample being analyzed for radio-isotopic profile. The discharge flow path is also isolated using positive control measures when a release is not in progress.

Discharge flow rates are controlled to ensure that liquid effluents leaving the plant do not exceed any concentration release limits. Procedure changes are required and will be in place to ensure that these controls are maintained. These procedure chances will account for the altered release configuration which utilizes the BAMT for effluent storage prior to release to the lake. The BAMT essentially wvill provide tile same function previously provided by the abandoned LDTs. These procedural controls will ensure that there is no adverse affect on how liquid waste releases are performed and controlled.

3. Does the proposed Activity involve an adverse change to an element of a UFSAR _ YES X NO described evaluation methodology, or use of an alternative evaluation methodology, that is used in establishing the design bases or used in the safety analyses? (See Section 5.2.2.3 of tile RM)

The methodology used to ensure thc liquid waste releases do not exceed any concentration release limits is defined in ODCM Chapter 10. The altered system configuration resulting from this design change essentially only changes the storace location for thle batch releases being, analyzed for discharge to the lake. It does not adversely impact or invalidate the methodology described in the ODCM. Minor revisions to the DSAR and the ODCM are necessary to reflect the new svsteim configuration resulting from this design change.

50.59 Sereening No. 2003-0009 lRc-. No. ()

Activity/D)ocurnent Numbner: Misc. document rcvisions due to F C No. 3414 1 Revision Numbcr: 0 4 I)oes the proposed Activity involve a test or experiment not descrihed in tile I I:SA It, YlES X NC) where an SSC is utilized or controlled in a manner that is outsidc the reference bounds of the design for tlhait SSC or is inconsistent with analyses or descl iplolls in hil JIFSAR?

(See Section 5.2.2.4 of the RM)

rhis activity does not involve a test or experiment not described in tlhe )SAR. It -aliers the liquid waste managcmienc system such that the 13AMTs will provide the storage and control function previously performed by the LDTs. Tie design function of tlie liquid waste management system is maintained. The system is not being tised or controlled in a manner that is outsidc tile design parameters or analyses described in tile DSAR and tlie ODCM. Minor revisions to the DSAR aid tile ODCM are necessary to reflect the new system configuration resulting fromii this design change.

5. Does the proposed Activity require a change in the Technical Specifications or Operating YES X NO License? (See Section 5.2.2.5 of the RM)

A review of the operating licenses and the Defueled Technical Specifications has determined that no changes to these documents are necessary as a result of this activity.

11. List the documents (e.g., UJSAR, Tcchnical Specifications, other licensing basis, technical, commitments, etc.)

reviewed, including sections numbers where relevant information wvas found (if not identified in the response to each question).

111. Select the appropriate conditions:

x If all questions are answered NO, then complete the 50.59 Screening and implement the Activity per the applicable governing procedure.

If question 1,2, 3, or 4 is answered YES and question 5 is answered NO, then a 50.59 Evaluation shall be performed.

If questions 1, 2, 3. and 4 are answered )!Q and question 5 is ansvecred YES, then a License Amendment is required prior to implementation of the Activity.

If question 5 is answered YES for any portion of an Activity, then a license Amendment is required prior to implementation of that portion of the Activity. In addition. if question 1. 2. 3, or 4 is answvered YES for the remaining portions of thie Activity, then a 50.59 Evaluation shall be perforiied for the remaining portions of the Activity.

IN'. Screcning Signoffs:

50.59 Screener: J.C. AshIc%' Sign: K.t n@tti _ D)ate: I//_I__

50.5() ReVieWet:.off (Print name) j 4 IZW0Dd V .

d /

Si,-,IIlll~

( itlll Da;te': ,+, ,1 I ./".

(Prinlt niamlc)

ZION Revision 6 June 2003 ZION ANNEX INDEX CHAPTER 10 REVISION 6 10-i

ZION Revision 6 June 2003 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENS PAGE 10.1 AIRBORNE RELEASES 10-1 10.1.1 System Descriptions 10-1 10.1.1.1 Ventilation Exhaust Treatment System 10-1 10.1.2 Radiation Monitors 10-1 10.1.2.1 Aux Ventilation Stack Effluent Monitors 10-1 10.1.2.2 Fuel Building Effluent Monitor 10-1 10.1.2.3 Containment Purge Effluent Monitors 10-2 10.1.3 Alarm and Trip Setpoints 10-2 10.1.3.1 Setpoint Calculation 10-2 10.1.3.2 Release Limits 10-2 10.1.3.3 Release Mixture 10-2 10.1.3.4 Conversion Factors 10-2 10.1.3.5 HVAC Flow Rates 10-3 10.1.4 Allocation of Effluents from Common Release Points 10-3 10.2 LIQUID RELEASES 104 10.2.1 System Description 10-4 10.2.1.1 Boric Acid Monitor Tanks 104 10.2.1.2 Turbine Building Fire Sump 10-4 10.2.2 Radiation Monitors 104 10.2.2.1 Boric Acid Monitor Tank Monitors 104 10.2.2.2 Turbine Building Fire Sump Monitor 104 10.2.3 Alarm and Trip Setpoints 10-5 10.2.3.1 Setpoint Calculation 10-5 10-ii

ZION Revision 6 June 2003 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS (Cont'd)

PAGE 10.2.3.2 Discharge Flow Rates 10-6 10.2.3.2.1 Boric Acid Monitor Tank Discharge Flow Rate 10-6 10.2.3.2.2 Turbine Building Fire Sump Discharge Flow Rate 10-6 10.2.3.3 Release Limits 10-6 10.2.3.4 Release Mixture 10-6 10.2.3.5 Conversion Factors 10-7 10.2.3.6 Liquid Dilution Flow Rates 10-7 10.2.4 Allocation of Effluents from Common Release Points 10-7 10.3 SOLIDIFICATION OF WASTE/PROCESS CONTROL PROGRAM 10-7 10-iii

i ZION Revision 6 June 2003 CHAPTER 10 LIST OF TABLES NUMBER TITLE PAGE 10-1 Assumed Composition of the Zion Station Noble Gas Effluent 10-8 10-2 HVAC Exhaust Fan Capacities 10-9 10-iv

ZION Revision 6 June 2003 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1 System Description During operation of the ventilation systems, the principal release points for potentially radioactive airborne effluents are the two auxiliary building ventilation stacks (Unit 1 and Unit 2) and the fuel building roof exhaust. Each is classified as a ground level release.

These ventilation systems maintain acceptable ambient air temperatures for equipment operation and personnel habitability, they provide air flow as needed for contamination control purposes, from lesser contamination potential to areas of greater contamination potential, and they provide bulk exhaust flow for ease of effluent control, sampling, and quantification.

The Aux Bldg (AB) ventilation stacks provide the release points for airborne effluent from the Aux Bldg and the containments. Operation of the AB ventilation system is administratively controlled to ensure that at least one (of 6) exhaust fan is operating when a supply fan is running.

Gaseous effluent flow paths via the ventilation systems are described in the Defueled Safety Analysis Report (DSAR).

10.1.1.1 Ventilation Exhaust Treatment System Ventilation exhaust treatment systems are designed and installed to reduce radioactive material in particulate form in gaseous effluents by passing ventilation through HEPA and/or pre-filters prior to release to the environment. Such a system is not considered to have any effect on noble gas effluents.

10.1.2 Radiation Monitors Pertinent information and available diagram(s) are provided in the DSAR.

10.1.2.1 Auxiliary Building Ventilation Stack Effluent Monitors 1RIA-PR49 (Unit 1) and 2RIA-PR49 (Unit 2) continuously monitor the final effluent from the Aux Bldg for beta, particulate and noble gas when the release paths are available.

The monitor outputs data and alarms to the central control console in the control room. The monitor also outputs flow and instrument fail indications.

10.1.2.2 Fuel Building Effluent Air Monitor The fuel building exhaust monitors, ORT-PR30A&B, continuously monitor fuel building ventilation exhaust for noble gas and radioactive particulate. The monitors provide specific information on the dispersion and concentration of radioactivity during a radiological event in the fuel building. Local and remote indication are provided.

10-1

ZION Revision 6 June 2003 10.1.2.3 Containment Purge Effluent Monitors 1RIA-PR40 (Unit 1) and 2RIA-PR40 (Unit 2) are designed to supply Operating personnel with information on the beta particulate activity in the respective containment during purging operations. The monitors prevent abnormal or unanticipated effluent release from containment to the public. A high alarm from the monitor automatically initiates containment isolation by closing the pressure and vacuum relief isolation valves and the purge isolation valves. The requirements of the monitor are applicable only when containment is being purged.

10.1.3 Alarm and Trip Setpoints 10.1.3.1 Setpoint Calculation The effluent noble gas monitor setpoints are conservatively based on the assumption that a release is occurring simultaneously for all gaseous release points at the maximum expected flow rate for each pathway. Furthermore, the setpoints are chosen such that an occurrence of simultaneous high alarms on all pathways would correspond to a station release rate of less than or equal to one half of the applicable release limit.

PMPS0.5xQ x1 /FPxKP xCi' (10-1)

PMP Setpoint for mionitor, M, on release path, P. [cpm]

0.5 = Factor to reduce release rate by 50%.

O, = Total Allowed Release Rate, Vent Release [pCi/sec]

FP = Flow rate through Release Path, P. [ cc/sec]

K = Factor to apportion a fraction of the total release rate, Q., to release path, P.

CM = Conversion Factor for monitor, M [cpm per pCi/cc]

10.1.3.2 Release Limits Alarm and trip setpoints for noble gas effluent monitors are established to indicate serious radiological events that coincide with Defueled Station Emergency Plan (DSEP) EALs and associated emergency classification.

10.1.3.3 Release Mixture In the determination of alarm and trip setpoints, the noble gas mixture in the station gaseous effluent is assumed to be 100% Kr85. Zion Station has not operated since February of 1997 and is permanently defueled. Subsequent, decay and lack of production results in the presence of only the longer lived Kr85 in the spent fuel rods.

10.1.3.4 Conversion Factors Calibration factors/monitor response variables for noble gas monitors are based on the energy characteristics of 100% Kr85.

10-2

ZION Revision 6 June 2003 10.1.3.5 HVAC Flow Rates Flow rates for aux vent stack release are provided by flow measuring instrumentation.

However, flow rates out the vent stack can be calculated based on the number of operating fans in the monitored flow path.

FM = Fjp x N, (10-4)

FM = Total Flow In Monitored Flow Path [cc/sec]

Fjp Flow from fan i in path p. [cc/sec]

Nj = Number of fans, in operation The maximum flow for each fan is used for setpoint calculations because this maximizes the flow, establishing a conservative, 'worst case" release rate/concentration for setpoint determination.

Pertinent data for the fans is provided in Table 10-2.

HVAC flows for the remaining monitors are conservatively fixed at upper bound values.

Fuel building exhaust flow is based on whether the system is operating in 'high' or 'low' mode.

Fan Speed Flow in cc/sec High Mode 7.08E+6 Low Mode 3.54E+6 10.1.4 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the fuel building are comprised of contributions from both units. Subsequently, allocation of effluent releases is made evenly between the units.

10-3

ZION Revision 6 June 2003 10.2 LIQUID RELEASES 10.2.1 System Description Available liquid waste processing diagrams are provided in the DSAR.

The liquid radwaste treatment system was designed and installed to allow for a reduction if needed, in the concentration of radioactive liquid effluents by filtration, providing for retention or holdup and/or providing for treatment by demineralizers. The overall purpose is to ensure releases to the lake do not exceed any concentration release limit, and liquid effluent releases to the public are ALARA.

10.2.1.1 Boric Acid Monitor Tanks There are four Boric Acid Monitor Tanks (21,600-gallon capacity each) which receive liquid waste before discharge to Lake Michigan.

10.2.1.2 Turbine Building Fire Sump The turbine building floor and equipment drain tanks and the fuel pool cooling tower blowdown are discharged to the fire sump for processing by the waste water treatment facility and ultimate discharge into Lake Michigan. The discharge constitutes a potential for very low level radioactive release.

10.2.2 Radiation Monitors 10.2.2.1 Boric Acid Monitor Tank Monitors ORT-PRO5 monitors releases from the Boric Acid Monitor Tanks. On high alarm, the monitor automatically initiates closure of a valve to prevent further releases. The valve is located over 250 feet downstream of the monitor to allow closure prior to exceeding release limits. The monitor setpoints are found by solving Equation 10-5 for release setpoint P.

Available information is provided in the DSAR.

10.2.2.2 Turbine Building Fire Sump Monitor ORT-PR25 continuously monitors the discharge line from the fire sump pumps to the waste water treatment facility. On high alarm, the monitor automatically trips all of the fire sump pumps, thereby containing the liquid in the turbine building. The monitor setpoints are found by solving Equation 10-5 for release setpoint P.

Available information on the monitor is provided in the DSAR.

10-4

ZION Revision 6 June 2003 10.2.3 Alarm and Trip Setpoints 10.2.3.1 Setpoint Calculation Alarm and trip setpoints of liquid effluent monitors at the principal release points are established to ensure that the concentration limits of the Technical Specifications and 10 CFR 20 are not exceeded in the unrestricted area. The monitor setpoints are found by solving Equation 10-5 for a conservative mixture of radionuclides found in liquid effluents.

P s K x (Cmpc)(Fd/Fr) (10-5)

P Release Setpoint [piCi/mL]

The alarm setpoint for radioactivity to be released in liquid effluents.

CmpC Maximum Permissible Concentration [pCi/mL]

F Dilution Flow Rate [gpm]

The flow rate of the radwaste dilution stream (condenser cooling water).

Fr Discharge Flow Rate [gprw]

The flow rate from the Boric Acid Monitor Tank or fire sump as appropriate.

K Factor of conservatism.

K = 0.5 for Boric Acid Monitor Tank K = 1.0 for sump 10-5

ZION Revision 6 June 2003 10.2.3.2 Discharge Flow Rates 10.2.3.2.1 Boric Acid Monitor Tank Discharge Flow Rate Prior to each batch release, the water is recirculated, sampled, and analyzed.

'"The results of the analysis of the waste sample determine the discharge rate of each batch as follows:

F'rs (Cmrpc)(Fdact/C) (106)

FrMaX Maximum Permitted Discharge Flow Rate [gpm]

The maximum permitted flow rate from the Boric Acid Monitor Tank. [gpm)

F48,, Actual Dilution Flow Rate (gpm]

The actual flow rate of the radwaste dilution stream.

MC Sample Radioactivity Concentration jpCi/mLJ The concentration of radioactivity in the Boric Acid Monitor Tank based on measurements of a sample drawn from the tank.

Cmp, has the same definition as in Equation 10-5.

10.2.3.2.2 Turbine Building Fire Sump Discharge Flow Rate This release path is a continuous discharge. Consequently, the release rate Fr in Equation 10-6 is set equal to maximum design capacity for the pumps on the effluent of the waste water treatment facility.

10.2.3.3 Release Limits Release limits are determined from 10 CFR 20.

10.2.3.4 Release Mixture The release mixture used for setpoint determination is based on a composition of 100% of a nuclide with a conservative concentration discharge limit to the lake (e.g., Sr9O)

" A more conservative discharge rate may be calculated based on concentration limits for NPDES constituents (e.g., boron concentration). In either case, discharge procedures verify that all discharge limits to the lake are below applicable limits.

10-6

I ZION Revision 6 June 2003 10.2.3.5 Conversion Factors The conversion factor for ORT-PR25 (fire sump monitor) is based on detector response to Cs-137. The conversion factors for monitor ORT-PR05 are based on detector response curves for Cs-1 37.

10.2.4 Allocation of Effluents from Common Release Points Radioactive liquid effluents released from the Boric Acid Monitor Tank and turbine building fire sump are comprised of contributions from both units. Under normal operating conditions, it is difficult to apportion the radioactivity between the units. Consequently, allocation is based on the unit discharge canal used for dilution.

10.3 SOLIDIFICATION OF WASTE/PROCESS CONTROL PROGRAM The process control program (PCP) contains the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is ensured.

10-7

ZION Revision 6 June 2003 Table 10-1 Assumed Composition of the Zion Station Noble Gas Effluent Isotope Percent of Effluent Kr85 100%

Note: Based on time since last unit operation and permanently defueled condition.

10-8

ZION Revision 6 June 2003 TABLE 10-2 HVAC EXHAUST FAN CAPACITIES FAN CC/SEC CFM CFH

1 Aux. Bldg I OA Exh. Fan 3.16 x 10 7 6.70 x 10 4 4,020,000 OB Exh. Fan 3.16 x 10 7 6.70 x 104 4,020,000 OC Exh. Fan 3.16 x 107 6.70 x 104 4,020,000

2 Aux. Bldg.

OD Exh. Fan 3.16 x 107 6.70 x 104 4,020,000 OE Exh. Fan 3.16x 10 7 6.70 x 104 4,020,000 OF Exh. Fan 3.16 x 10 7 6.70 x 104 4,020,000

1 Purge Exh.

1A Purge Fan 1.46 x 107 3.10 x 104 1,860,000 1B Purge Fan 1.46x 107 3.10x 104 1,680,000 H2 Purge Fan 1A 1.70 x 105 3.60 x 102 21,600 H2 Purge Fan 1B 1.75 x 105 3.40 x 102 22,200

2 Purge Exh.

2A Purge Fan 1.65 x 10 7 3.50 x 104 2,102,400 2B Purge Fan 1.72 x 107 3.65 x 104 2,188,800 H2 Purge Fan 2A 1.82 x 105 3.85 x 102 23,100 H2 Purge Fan 2B 1.75 x 105 3.71 x 102 22,260 Hot Lab Exh. OA 1.50 x 106 3.18 x 103 191,000 Hot Lab Exh. OB 1.18 x 106 2.51 x 103 150,600 10-9

I; r-ZION Revision 10 June 2003 SPECIAL NOTE The requirements of Permanently chapter, should any differences Defueled Technical Specifications occur. shall take precedence over this z12rS.doc 12-i

v i_

ZION Revision 10 June 2003 CHAPTER 12 REVISION 10 I k '.7 * ,. * .

'4..

1 zi 2r6.doc 12-ii

ZION Revision 10 June 2003 CHAPTER 12 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS (RETS)

TABLE OF CONTENTS PAGE 12.1 DEFINITIONS 12-1 12.2 INSTRUMENTATION

1. Radioactive Liquid Plant Monitoring Instrumentation 12-5

2. Radioactive Plant Monitoring Instrumentation 12-9 12.3 LIQUID EFFLUENTS

1. Concentration *12-17

2. Dose 12-23

3. ' Liquid Radwaste Treatment System 12-25 GASE OU E .

12.4 'GASEOUS EFFLUENTS

1.

Dose Rate : 12-26

2. Dose - Noble Gases 12-30

3. D'ose- 1-131, 1-133, Tritium, and Radioactive Material in Particulate Formi'... - 12-32

4. 'Gaseou&'Effluent Treatment System ;12-34 RADILGIA ENIRNENA MOIORN PROGRAM 12.5 RADIOLOGICAL

. .i .. , ENVIRONMENTAL MONITORING PROGRAM

1. Monitoring Program I :.- 12-35

2. Land Use Census c:."

J ; I2-47

3. Interlaboratory Comparison Program ~12-48 2.~,'~%

12.6 PROCESS CONTROL PROGRAM (PCP)

1. PCP Program Requirement 12-49 '

2. Changes to the PCP .-- , 12-49 12.7 REPORTING REQUIREMENTS

1. Annual Radiological Environmental Operating Report 12-50

2. Annual Radioactive Effluent Release Report 12-51

3. Offsite Dose Calculation Manual (ODCM) 12-53

4. Major Changes to Liquid and Gaseous Effluent Treatment Systems 12-54 zl 2r6.doc 12-iii

ZION Revision 10 June 2003 CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)

LIST OF TABLES PAGE 12.1-1 Surveillance Frequency Notations 12-4 12.2-1 Radioactive Liquid Plant Monitoring Instrumentation 12-6 12.2-2 Radioactive Liquid Plant Monitoring Instrumentation Surveillance 12-8 122-3 Radioactive Plant Monitoring Instrumentation '--*::. : 12-10 12.2-4 Radioactive Plant Monitoring Instrumentation Surveillance 12-14 12.3-1' ';Allowable Concentration of Dissolved or Entrained Noble Gases Rele'ased from the

- w;*'",Site to Unrestricted Areas in Liquid Effluents .12-19 12.3-2 Radioactive Liquid Effluent Sampling and Analysis Surveillance - 12-20 12:4-1' - Radioactive Gaseous Effluent Sampling and Analysis Progtam . 12-27

~- t e'..? :' ' ' ;

12.5-1'- ': Radiological Environmental Monitoring Program 12-38 12.5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 12-43 12.5-3 ' Detection Cap'abilities for Environmental Sample Analysis"' - ' 12-44

., . 4s .

zi 2r6.doc 12-i

ZION Revision 10 June 2003 12.1 DEFINITIONS 12.1.1 A BATCH RELEASE is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated and then thoroughly mixed to assure representative sampling.

12.1.2 A CHANNEL CALIBRATION, shall be the adjustment, as necessary, of the channel such that it responds with the necessary range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors (where possible),

alarm interlock and/or trip functions and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

12.1.3 A CHANNEL CHECK shall be the qualitative-assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications andlor status derived from independent INSTRUMENT CHANNELS measuring the same parameter.

12.1.4 A CHANNEL FUNCTIONAL CHECK shall be:

a. Instruments-The injection of.a simulated signal(s) into the channel as close to the primary sensor(s) as practicable to verify OPERABILITY, including all channel

- 'outputs, as appropriate.

b. Logics-The application of input signals, or the operation of relays or switch contacts, in all the combinations required to produce the required decision

.;l. outputs including the operation of all ACTUATION DEVICES. Where

- practicable, the test shall irfclude the operation of the ACTUATED EQUIPMENT

- as well (i.e. pumps will be started,,valves operated, etc.).

12.1.5 A COMPOSITE SAMPLE is one in which the quantity of liquid sample is proportional to the

' ;quantity of liquid waste discharged and inhwhich the method of sampling employed results in a specimen which is representative of the liquids released.

12.1.6 A CONTINUOUS RELEASE is the discharge of.liquid or gaseous wastes of a nondiscrete volume (e.g. from a volume or system that has an input flow during the release).

12.1.7 CONTINUOUS SAMPLING is uninterrupted sampling with the exception of sampling interruptions of short duration for routine activities (e.g. filter replacements).

12.1.8 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcurie/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The Thyroid Dose Conversion factors used for this calculation shall be those listed in Table IlIl of TID-14844, "Calculation of Distance Factors for Power and Test Reactor Sites" or Table E-7 of NRC Regulatory Guide 1.109 Rev. 1, dated October, 1977. This definition is not used in the defueled condition. Decay has eliminated all concerns related to radioactive iodine.

12.1.9 MEMBER OF THE PUBLIC means any individual except when that individual is receiving an occupational dose.

z12r6.doc 12-1

ZION Revision 10 June 2003 12.1.10 OCCUPATIONAL DOSE means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation and/or radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include dose from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the public.

12.1.11 OPERABLE - A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).

12.1.12 OPERATING is defined as performing the intended function in the intended manner. ,;

12.1.13 The OPERATING CYCLE: DELETED : .

12.1.14 An OPERATIONAL MODE: DELETED 12.1.15 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to-ensure that processing and packaging of solid k

f radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes -

will be accomplished in such a way as to assure compliance with 10CFR Parts 20, 61, and 71,- . -:.

State regulations, burial ground requirements, and other requirements governing the disposal of "n solid radioactive waste.

12.1.16 PURGE OR PURGING isthe'controlled process of discharging airorgasfroma confinement toi, t;E. .o maintain temperature, pressure, humidity, concentration or other operating condition, in such a .

manner, that replacement air or gas is required to purify the confinement. -;: r !

12.1.17 RATED THERMAL POWER: DELETED .'

12.1.18 The REACTOR PRESSURE: DELETED , B- :

12.1.19 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased or otherwise controlled by the licensee:'

12.1.20 SOLIDIFICATION shall be the conversion of radioactive liquid, resin and sludge wastes from ., i.r liquid systems into a form that meets shipping and burial site requirements.

12.1.21 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel.. ,,,:

sensor is exposed to a radioactive source. . :.

z12r6.doc 12-2

ZION Revision 10 June 2003 12.1.22 SURVEILLANCE shall be those parts of the sections which prescribe remedial measures required under designated conditions, activities required to demonstrate instrument operability, and activities performed to ensure applicable offsite dose limits are not exceeded.

12.1.23 The SURVEILLANCE FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 12.1-1.

12.1.24 THERMAL POWER: DELETED 12.1.25 UNRESTRICTED AREA means an area, access to which is neither limited nor'controlled by the licensee.

12.1.26 GASEOUS EFFLUENT TREATMENT SYSTEM shall be any system designed and installed to reduce radioactive material in particulate form in effluents by passing ventilation through HEPA filters for the purpose of removing particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any affect onnoble gas effluents: The iodine removal function is no longer used in the defueled condition. :!,.

12.1.27 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during venting. Vent, used in system names, does not imply a venting process. , -.

12.1.28 WASTE GAS HOLDUP SYSTEM: DELETED ;

. - . i*v* .- . . . -:. . .

z1 2r6.doc 12-3

ZION Revision 10 June 2003 TABLE 12.1-1 SURVEILLANCE FREQUENCY NOTATIONS NOTATION FREQUENCY

S (Shiftly) At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D (Daily) At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months W (Weekly) At least once per 7 days-

.,(Monthly) At least once p'er 31 .days Q (Quarterly) At least once per 92 days SA .. (Semiannually) At least once per 184 days-,.

.A - (Annually) At least once per 366 days R. At least once per 18 months P (Prior) Complete prior-to start bf release NIA. Not Applicable." '.

Each Surveillance Requirement shall be performed within the specified tnme interval with a maximum allowable extension not to exceed 25% of the surveillance interval.-.These frequency notations do not apply to the Radiological Environmental Monitoring Program as described in SectioR 12.5. .\

zi 2r6.doc 12-4

ZION Revision 10 June 2003 12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Plant Monitoring Instrumentation Operability Requirements 12.2.1.A The radioactive liquid plant monitoring instrumentation channels shown in Table 12.2-1 shall be OPERABLE AND, the radioactive liquid effluent monitoring instrumentation channels shall have their alarm/trip setpoints set to ensure that the limits of Section 12.3.1.A are met.

Applicability: As indicated in Table 12.2-3.

Action

1. With a radioactive liquid effluent monitoring instrument channel trip setpoint less ; .-

conservative than the value necessary to prevent violating the limits of Section 12.3.1A immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

2. With one or more radioactive liquid plant monitoring instrumentation channels inoperable, initiate the SURVEILLANCE requirement delineated in Table 12.2-1.

Surveillance Requirements 12.2.1.B.1 The liquid effluent monitor setpoints shall be determined in accordance with procedures as described in the ODCM.

12.2.1.B.2 Each radioactive liquid plant monitoring instrumentation channel shall be demonstrated OPERABLE by performance of a CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 12.2-2.

Bases .-

12.2.1.C The radioactive liquid plant monitoring instrumentation is provided to indicate abnormal radiological conditions within the plant, AND, The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the release of radioactive materials in liquid effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of RETS. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10CFR Part 50.

z12r6.doc 12-5

ZION Revision 10 June 2003 TABLE 12.2-1 RADIOACTIVE LIQUID PLANT MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE SURVEILLANCE # CONDITION

1. Liquid Effluent Monitors Providing Automatic Termination of Release A. Boric Acid Monitor Tank (BAMT)

1. OR-PRO5 See SURVEILLANCE 1, .1 Liquid Release through this Pathway B. Turbine Bldg.

1. OR-PR25 Liquid Release through this Pathway

.. .. 2. .

2. Effluent Continuous Composite Sampler A. Turbine Building Fire Sump All Times

3. Effluent Flow Rate Monitor I A. Boric Acid Monitor Tank

1. OFI-WD005 1 3 Liquid Release through this Pathway

4. Plant System Monitors NONE z12r6.doc 12-61

! , 4. : . . I* ' X -

I ...

ZION Revision 10 June 2003 TABLE 12.2-1 RADIOACTIVE LIQUID PLANT MONITORING INSTRUMENTATION (Cont'd)

SURVEILLANCE 1 If the monitor is inoperable, effluent releases from the tank may continue for up to l 14 days, provided that prior to initiating the release:

1. At least two independent samples of the tank's contents are analyzed, in accordance with Section 12.3.1.B.1, and

2. At least two technically qualified members of the facility staff independently verify the release-rate calculations and discharge flow path valving; Otherwise, suspend release of radioactive effluents via this pathway. .

SURVEILLANCE 2 With the number of channels OPERABLE less the minimumrnnumber required,.

effluent releases via this pathway may continue, provided that at least once~per day grab samples are analyzed for gross radioactivity (beta Igamma or isotopic) at a lower limit of detection (LLD) as specified in Table 12.3-2. Restore the channel to operable status within 30 days or conduct a station review to determine a plan of action to restore the channel to operable status. Is SURVEILLANCE 3 With the number of channels OPERABLE less than the minimum number,,...

required, effluent releases via this pathway may continue, for up to 30 days, provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual ;..

releases. Pump curves may be used to estimate flow. rel .

z12fi.doc 12-7

ZION Revision 10 June 2003 TABLE 12.2-2 RADIOACTIVE LIQUID PLANT MONITORING INSTRUMENTATION SURVEILLANCE CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION(1) TEST (2)

1. Liquid Effluent Monitors Providing Automatic Termination Of Release A. Boric Acid Monitor Tank (BAMT)

1. OR-PRO5 P P R Q B. Turbine Bldg.

1. OR-PR25 D M R Q

2. Effluent Continuous Composite Sampler A. Turbine Building Fire Sump D N/A N/A N/A

3. Effluent Flow Rate Monitor A. Boric Acid Monitor Tank (BAMT)

1. OFI-WD005 D(3) N/A R(4) N/A

4. Plant System Monitors NONE (1) CHANNEL CALIBRATION shall include performance of a CHANNEL FUNCTIONAL TEST.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that any automatic isolation of this pathway occurs and that control room alarm annunciation occurs if any of the following conditions exist. (if the capability is installed):

a) Instrument indicates levels above the alarm setpoints.

b) Circuit failure.

c) Instrument indicates a downscale failure.

d) Instrument controls not set Inoperate mode.

(3) CHANNEL CHECK shall consist of verifying Indications of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or BATCH RELEASES are made. *

(4) Does not Include flow sensor.

z12r6.doc 12-8

ZION Revision 10 June 2003 12.2.2 Radioactive Plant Monitoring Instrumentation Operability Requirements 12.2.2.A The radioactive plant monitoring instrumentation channels shown in Table 12.2-3 shall be OPERABLE, AND, the radioactive gaseous effluent monitoring instrumentation shall have their alarm/trip setpoints set in accordance with the method prescribed in the ODCM to ensure that the limits of Section 12.4.1.A are met.

Applicability: As indicated in Table 12.2-3.

Action

1. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Section, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.

2. With one or more radioactive plant monitoring instrumentation channels inoperable, initiate the SURVEILLANCE requirement as delineated in Table 12.2-3.

Surveillance Requirements . :

12.2.2.B.1 The effluent monitor setpoints shall be determined in accordance with procedures as described in the ODCM.

12.2.2.B.2 Each radioactive plant monitoring instrumentation channel shall be demonstrated OPERABLE, when in its APPLICABLE CONDITION, by performance of a CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 12.2-4.

Bases 12.2.2.C The radioactive plant monitoring instrumentation is provided to indicate abnormal radiological conditions within the plant, AND, The radioactive gaseous effluent instrumentation is provided to monitor, record and control, as applicable, the release of radioactive materials in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR Part 20.

An Auxiliary Building (AB) ventilation stack is considered available as a release path from radiologically controlled areas of the Auxiliary Building when any AB exhaust fan is discharging to that stack, or any one of the AB exhaust fan dampers is open on that stack.

An Auxiliary Building ventilation stack is unavailable as a release path from radiologically controlled areas of the Auxiliary Building when all AB exhaust fan dampers for that stack are mechanically blocked closed.

zl2r6.doc 12-9

ZION Revision 10 June 2003 TABLE 12.2-3 RADIOACTIVE PLANT MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE SURVEILLANCE CONDITION

1. Effluent Containment Purge or Vent A. Particulate Monitor 1 2

1. 1R-PR40A (Channel 1) I 6,7 Venting or Purging 1 2

2. 2R-PR40A (Channel 1) 1 6.7 Venting or Purging

2. Aux Building Effluent Monitorinq A. Gas Activity Monitor

1. I R-PR49E (Channel 5) I 10

2. 2R-PR49E (Channel 5) 1 10 B. Particulate Monitor

1. 1R-PR49A (Channel 1) I 11

2. 2R-PR49A (Channel 1) I 11 **

C. Flow Rate Monitor

1. 1LP-084 1 8

2. 2LP-084 1 8

- Whenever the Unit 1 stack is available as a release path from the Auxiliary Building.

Whenever the Unit 2 stack is available as a release path from the Auxiliary Building.

3. Fuel Building Monitorin-q A. Gas Activity Monitor

1. ORT-PR30A I 10 All Times B. Particulate Monitor

1. ORT-PR30B 1 11 All Times C. Area Monitoring

1. ORT-AR03(3 ) 1 12 When fuel is present

2. ORE0005 1 14 When fuel is present 3 ORT-AR13 1 13 When fuel building crane is operated with a load on either hook in the bypass mode IDuring VENTING 2

During PURGING z12r6.doc 12-10

ZION Revision 10 June 2003 The auto control function on high alarm is no longer required for this monitor (i.e., does not need to be maintained operable for the monitor to be operable).

z12r6.doc 12-11

ZION Revision 10 June 2003 TABLE 12.2-3 RADIOACTIVE PLANT MONITORING INSTRUMENTATION (Cont'd)

MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE SURVEILLANCE CONDITION

4. Emergency Monitoring A. Ventilation

1. 1RIA-PR49 (Channel 7) I 9

2. 2RIA-PR49 (Channel 7) 1 9

3. 1RIA-PR49 (Channel 9) 1 9

4. 2RIA-PR49 (Channel 9) 1 9 Whenever the Unit 1 stack is available as a release path from the Auxiliary Building.-

Whenever the Unit 2 stack is available as a release path from the Auxiliary Building.

z12r6.doc 12-12

ZION Revision 10 June 2003 TABLE 12.2-3 RADIOACTIVE PLANT MONITORING INSTRUMENTATION (Cont'd)

TABLE NOTATIONS SURVEILLANCE 6 - With the number of channels OPERABLE less than the minimum number required, effluent releases via this pathway may continue for up to 30 days provided grab samples are obtained and analyzed for gross activity at least once per day.

SURVEILLANCE 7 - With the number of channels OPERABLE less than the minimum number required.

and no redundant monitor OPERABLE in this flow path, immediately suspend PURGING of radioactive effluents via this pathway.

SURVEILLANCE 8 - Effluent releases via this pathway may continue provided the effluent flow rate is estimated at least once per day while a release is in progress. Restore the inoperable panel to OPERABLE status within 30 days OR conduct a station review to determine a plan of action to restore the panel to OPERABLE status.

SURVEILLANCE 9 - With the number of channels OPERABLE less than the minimum number required, restore the inoperable monitor to OPERABLE status within 30 days OR conduct a station review to determine a plan of action to restore the channel to OPERABLE status.

SURVEILLANCE 10 - With the number of OPERABLE channels less than the minimum number required, restore the channel to OPERABLE status within 30 days or conduct a station review to determine a plan of action to restore the channel to OPERABLE status. Effluent releases via this pathway may continue provided grab samples are obtained and analyzed for gross activity at least once per day, OR for the case when the associated LP-084 panel is inoperable, continuous sampling is maintained with a portable pump and Operations performs a Channel Check Daily. Compensatory sampling does not return the monitor to an OPERABLE status.

SURVEILLANCE 11- With the number of OPERABLE channels less than the minimum number required, restore the channel to OPERABLE status within 30 days or conduct a station review to determine a plan of action to restore the channel to OPERABLE status. Effluent releases via this pathway may continue provided samples are continuously collected as required in Table 12.4-1. For the case when the associated LP-084 panel is inoperable, continuous sampling can be maintained with a portable pump and Operations shall perform a Channel Check Daily. Compensatory sampling does not return the monitor to an OPERABLE status.

SURVEILLANCE 12- With the number of channels OPERABLE less than the minimum required, stop all movement of fuel within the spent fuel pool and crane operation with loads over the spent fuel pool AND perform area surveys of the monitored area at least once per day.

SURVEILLANCE 13 With the number of channels OPERABLE less than the minimum required, stop operation of overhead crane in bypass after placing loads in safe condition.

SURVEILLANCE 14 Perform area surveys of the monitored area at least once per day.

z12r6.doc 12-13

ZION Revision 10 June 2003 TABLE 12.2-4 RADIOACTIVE PLANT MONITORING INSTRUMENTATION SURVEILLANCE CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL CHECK CHECK CALIBRATION (1) TEST (2) 1 Effluent Containment Purge or Vent A. Particulate Monitor

1. I R-PR40A (Channel 1) D M R Q

2. 2R-PR40A (Channel 1) D M R Q

2. Aux Building Effluent Monitoring A. Gas Activity Monitor

1. IR-PR49E (Channel 5) D M R Q

2. 2R-PR49E (Channel 5) D M R Q B. Particulate Monitor

1. 1R-PR49A (Channel 1) D M R Q

2. 2R-PR49A (Channel 1) . D M R Q C. Flow Rate Monitor

1. I LP-084 D N/A R Q

2. 2LP-084 D N/A R Q

3. Fuel Building Monitoring A. Gas Activity Monitor

1. ORT-PR30A D M A N/A B. Particulate Monitor

1. ORT-PR30B D M A N/A C. Area Monitoring

1. ORT-AR03 D M(4) R Q

2. ORE0005 D M R Q

3. ORT-AR13 D M(3) R Q z1 2r6.doc 12-14

ZION Revision 10 June 2003 TABLE 12.2-4 RADIOACTIVE PLANT MONITORING INSTRUMENTATION SURVEILLANCE (Cont'd)

CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION (1) TEST (2)

4. Emergency Monitoring A. Ventilation

1. IRIA-PR49 (Channel 7) N/A N/A R Q

2. 2RIA-PR49 (Channel 7) N/A N/A R Q

3. IRIA-PR49 (Channel 9) NIA N/A R Q

4. 2RIA-PR49 (Channel 9) r N/A N/A -R Q z12r6.doc 12-15

ZION Revision 10 June 2003 Table 12.2-4 RADIOACTIVE PLANT MONITORING INSTRUMENTATION SURVEILLANCE (Contd)

TABLE NOTATIONS (1) CHANNEL CALIBRATION shall include performance of a CHANNEL FUNCTIONAL TEST.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that any automatic isolation occurs; and that Control Room alarm annunciation occurs if any of the following conditions exist (if the capability is installed):

a) Instrument indicates measured levels above the alarm setpoint.

b) Circuit failure.

C) Instrument indicates a downscale failure. .

cJ) Instrument controls not set in "operate" mode.

(3) Daily during operations of overhead crane in bypass mode.

(4) Daily during fuel handling operations or load handling operations in or above Vie spent fuel pool.

zl2rS.doc 12-16

ZION Revision 10 June 2003 12.3 LIQUID EFFLUENTS 12.3.1 Concentration Operability Requirements 12.3.1.A.1 The concentration of radioactive material released from the site to UNRESTRICTED AREAS (see Zion Station ODCM Annex, Appendix F, Figure F-I) shall be limited to 10 times the concentrations specified in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentrations shall be limited to the values listed in Table 12.3-1.

12.3.1.A.2 During the release of radioactive liquid wastes, the combination of dilution water flow and waste water discharge flow shall be established to ensure the discharge concentration limits of 12.3.1.A.1. are not exceeded.

Applicability: At all times.

Action

1. With the concentration of radioactive materials released from the site to UNRESTRICTED AREAS exceeding the limits specified in Section 12.3.1.A.1.

immediately decrease the release rate of radioactive materials and/or increase the dilution flow rate to restore the concentration to within the above limits.

Surveillance Requirements 12.3.1.B.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 12.3-2. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Section 12.3.1.A.1.

12.3.1.B.2 Post-release analyses of samples composited from BATCH RELEASES shall be performed in accordance with Table 12.3-2. The results of the previous post-release analyses shall be used with the calculational methods in the OQCM to assure that the concentrations at the point of release were maintained within the limits of Section 12.3.1.A.1.

12.3.1.B.3 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 12.3-2.

The results of the analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Section 12.3.1.A.1.

12.3.1.B.4 Appropriate discharge and dilutions flows for each batch radioactive liquid release shall be determined with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Section 12.3.1.A.1.

z12r6.doc 12-17

I*

ZION Revision 10 June 2003 Bases 12.3.1.C This Section is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to UNRESTRICTED AREAS will be less than ten (10) times the concentration levels specified in Appendix B, Table 2, Column 2 to 10CFR 20.1001-20.2402.

This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section I.A design objectives of Appendix 1,10 CFR 50, to a MEMBER OF THE PUBLIC, and (2) the limits of IOCFR20.1301.

z12r6.doc 12-18

ZION Revision 10 June 2003 TABLE 12.3-1 ALLOWABLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID EFFLUENTS NUCLIDE A(tLCi/ml)*

Kr-85m 2 X 104 Kr-85 5 X 104 Kr-87 4 X 105 Kr-88 9 X 1o' ArM1 7X 10O Xe-131m 7 X 104 Xe-133m 5 X 10 4 Xe-133 6X 104 Xe-135m , 2X 104 Xe-135 . 2 X 104

Computed from Equation 20 of ICRP.Publication 2(1959), adjusted for infinite cloud submersion in water, and R = 0.01 rem/week, density = 1.0 glcc and Pw/Pt = 1.0. ... ;.

zi 2r6.doc 12-19

ZION Revision 10 June 2003 TABLE 12.3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE MINIMUM ANALYSIS LOWER LIMIT OF LIQUID RELEASE SAMPLING FREQUENCY TYPE OF DETECTION (LLD)

TYPE FREQUENCY ACTIVITY ANALYSIS (pCilml) (a,e)

A. Boric Acid Monitor Prior to Each Release Prior to Each Principal Gamma 5E-7 Tank (c) Release Emitters (e)

P M Dissolved and 1E-5 One Batch/M(c) Entrained Gases (Gamma Emitters)

P M Tritium 1E-5 Each Batch (c) Composite (b)

Gross Alpha 1E-7 P a Sr-89, Sr-90 5E-8 Each Batch (c) Composite (b)

Fe-55 I E-6 B. Turbine Building Continuous During W Principal Gamma 5E-7 Fire Sump (f) Release (d) Emitters(e)

Dissolved and 1E-5 Entrained Gases (Gamma Emitters)

Continuous (d) M Tritium 1E-5 Composite (b)

Gross Alpha 1E-7 Continuous (d) a Sr-89, Sr-90 5E-8 Composite (b)

Fe-55 1E-6 C. Waste Neutralizing Prior to each Release Prior to each Release Principal Gamma -: 5E-7 Tank , Emitters (e)

P M Tritium 1E-5 Each Batch (c) Composite (b) _

. Gross Alpha 1E-7 zi 2r6.doc 12-20

ZION Revision 10 June 2003 TABLE 12.3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE (Cont'd)

TABLE NOTATIONS

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

LLD = 4.66 Sb A-E*V*2.22*Y *exp(-XAt)

Where:

LLD is the lower limit of detection as defined above in picocuries (pCi) per unit mass or volume, SD is the square root of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

A is the number of gamma rays emitted per disintegration for gamma ray radionuclide analysis (A = 1.0) for gross alpha, strontium, and tritium measurement.

E is the counting efficiency (as counts per gamma),

V is the sample size (in units of mass or volume).

2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield when applicable (otherwise Y = 1.0)

X is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental sample).

The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples.

Typical values of E, V. Y, and At shall be used in the calculation. The background count rate is calculated from the background counts that are determined to be within + one FWHM (Full Width at Half Maximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radionuclide.

z12r6.doc 12-21

ZION Revision 10 June 2003 TABLE 12.3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE (Contd)

TABLE NOTATIONS For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near their sensitivity limits when other nuclides are present in the sample in much greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentrations of such radionuclides using observed ratios with those radionuclides which are measurable.

b. A COMPOSITE SAMPLE is one in which thequantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

1) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

2) The weekly and monthly Proportional Composite samples are not required provided that (1) the analysis required for each of these composite samples has been run on each batch discharged, and (2) a monthly record of radionuclides discharged (isotope and quantity) is maintained.

c. A BATCH RELEASE is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.

d. A CONTINUOUS RELEASE is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the continuous release.

e. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141. Ce-144 shall also be measured, but with an LLD of 5E-06. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses shall be reported as "less than" the nuclide's LLD, and shall not be reported as being present at the LLD level for that nuclide. The "less than" values shall not be used in the required dose calculations.

f. If the fire sump composite sampler is inoperable, grab samples shall be taken from the turbine building fire sump once per day.

zi 2r6.doc 12-22

ZION Revision 10 June 2003 12.3.2 Dose Operability Requirements 12.3.2.A The dose or dose commitment to a MEMBER OF THE PUBLIC above background from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS (see Zion Station ODCM Annex, Appendix F, Figure F-1) shall be limited:

1. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and

2. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

Applicability: At all times.

Action

1. With the calculated dose from the release of radioactive materials in liquid effluents exceeding twice the limits specified in Section 12.3.2.A, limit the subsequent releases such that the dose or dose commitment to a MEMBER OF THE PUBLIC from all uranium fuel cycle sources is limited to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months. Demonstrate that radiation exposures to all MEMBERS OF THE PUBLIC from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40CFR Part 190 and 40CFR Part 141 Standard, otherwise obtain a variance from the Commission to permit releases which exceed the 40CFR Part 141 or 190 Standard. The radiation exposure analysis shall use methods prescribed in the ODCM.

Surveillance Requirements 12.3.2.B Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodologiesand parameters of the ODCM at least once per 31 days.

z12r6.doc 12-23

ZION Revision 10 June 2003 Bases 12.3.2.C This Section is provided to implement the requirements of Sections JI.A, III.A and IV.A of Appendix 1,10CFR Part 50. The limiting Condition of Operation implements the guides set forth in Section I.A of Appendix I. The ACTION statements provide the required OPERATING flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies, which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are excess of the requirements of 40CFR 141. The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the dose due to the actual release rate of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109; Calculation of Annual Doses to Man from Routine Releases of Radioactive Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guides 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

This Section applies to the release of liquid effluents from each unit at the site. For shared radwaste treatment systems, the liquid effluents from the shared systems are proportioned among the units sharing the system. - I z12r6.doc 12-24

ZION Revision 10 June 2003 12.3.3 Liquid Radwaste Treatment System Onerability Requirements 12.3.3.A The Liquid Radwaste Treatment System shall be OPERABLE* and appropriate portions of the system shall be used to reduce the radioactive materials in liquid effluents prior to discharge when the projected doses due to liquid effluent, from each unit, to UNRESTRICTED AREAS (see Zion Station ODCM Annex, Appendix F, Figure F-I) would exceed 0.06 mrem to the total body or 0.20 to any organ in a 31-day period.

The liquid Radwaste Treatment System shall be considered OPERABLE, if liquid waste can be held up and/or discharged within applicable limits.

Applicability: At all times.

Action With the Liquid Radwaste Treatment System inoperable for more than 30 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, return the system to OPERABLE status and place the appropriate portions of the system in use.

Surveillance Requirements 12.3.3.B Doses due to liquid releases from the site to UNRESTRICTED AREAS, shall be projected at least once per 31 days in accordance with the methodologies and parameters of the ODCM when the Liquid Radwaste Treatment System is not being fully utilized.

Bases 12.3.3.C The OPERABILITY of the Liquid Radwaste Treatment System ensures that the system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This Section implements the requirements of IOCFR Part 50.36a, General Design Criterion of Appendix A to 10CFR Part 50 and the design objective given in Section I1.D of Appendix I to 10CFR Part 50.

The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a 2% fraction of the dose design objectives set forth in Section I.A of Appendix I, 10CFR Part 50, for liquid effluents.

z12r6.doc 12-25

ZION Revision 10 June 2003 12.4 GASEOUS EFFLUENTS 12.4.1 Dose Rate Operating Requirements 12.4.1.A The dose rate due to radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY (see Zion Station ODCM Annex, Appendix F, Figure F-1), shall be limited to the following:

1. For noble gases: Less than or equal to 500 mrem/yr to the whole body and less than or equal to 3000 mrem/yr to the skin, and

2. For lodine-131, Iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem/yr to any organ.

ApplicabilitV: At all times.

Action With a release exceeding the above limits, immediately reduce the release rate to within the above limits.

Surveillance Requirements 12.4.1.B The dose rate due to radioactive materials in gaseous effluents shall be determined to be within the prescribed limits in accordance with the methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 12.4-1.

Bases 12.4.1.C This Section is provided to ensure that radioactive material discharged in gaseous effluents will not result in the exposure of a Member of the Public in an Unrestricted Area, either at or beyond the Site Boundary in excess of the design objectives of appendix I to 10 CFR part 50. This section is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled. It provides operational flexibility for releasing gaseous effluents to satisfy the Section I.A and 11.design objectives of appendix I to 10 CFR part 50. The specified release-rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the SITE BOUNDARY to 500 mrem/year to the total body or to less than or equal to 3000 mrem/year to the skin. These release-rate limits also restrict, at all times, the corresponding organ dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year. For purposes of calculating dose resulting from airborne releases, the stack is considered a ground-level release.

The Sampling and Analysis Program requirements prescribed in Table 12.4-1 are established to provide representative and appropriate sampling of the radiologically controlled areas. The method and frequency of sampling is based on the effluent flowrate. Continuous Releases are defined for areas with forced ventilation release points. Unventilated Building Releases are defined for areas with no specific release point.

z12r6.doc 12-26

ZION Revision 10 June 2003 TABLE 12.4-1 RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM MINIMUM TYPE OF LOWER LIMIT OF GASEOUS RELEASE SAMPLING ANALYSIS ACTIVITY DETECTION (LLD)

TYPE METHOD FREQUENCY ANALYSIS (pCi/cc) (L A. Deleted B. Containment Vent Grab (b) Prior to Each Noble Gases 1E-4 and Purge Release Principal Gamma Emitters (d)

Tritium 1E-6 C. Continuous Grab (b) Monthly Noble Gases 1E-4 Releases~ Principal Gamma I Aux Building Emitters (d)

Ventilation Stack for both (2) units And Tritium 1 E-6 Continuous (b)(h) Weekly(c) Particulate 1E-1I Fuel Building Principal Gamma Ventilation Emitters (e)

I Composite Quarterly Sr-89 Particulate 1E-11 Sr-90 Particulate 1E-1 1

. Gross Alpha 1E-11 Continuous (g)(h) N.A. Noble Gases, 1 E-6 Gross Beta or Noble Gas Monitor Gamma (1) The requirements listed in this table for Continuous Releases are applicable for release paths that are available.

z1 2r6.doc 12-27

ZION Revision 10 June 2003 TABLE 12.4-1 RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM (Cont'd)

MINIMUM TYPE OF LOWER LIMIT Of GASEOUS RELEASE SAMPLING ANALYSIS ACTIVITY DETECTION TYPE METHOD FREQUENCY ANALYSIS (LLD) (pCi/cc) (f)

D. Unventilated Grab Daily Noble Gases 1E-4 Building 2 I

Reileases( ) Principal Gamma ReleasesEmitters (d)

Aux Building Above Ground Elevations(i)

And Tritium 1E-6 Continuous (h) Daily(c) Particulate 1E-11 Fuel Building (j) Principal Gamma Emitters (e)

I Composite Quarterly Sr-89 Particulate 1E-11 Sr-90 Particulate 1E-11 Gross Alpha IE-11 (2) The requirements listed in this table for Unventilated Building Releases are applicable for buildings with the normal ventilation release paths isolated.

z12r6.doc 12-28

ZION Revision 10 June 2003 TABLE 12.4-1 RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM (Cont'd)

TABLE NOTATIONS

a. Deleted

b. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period in Section 12.4.1.

c. The particulate filter(s) shall be saved for a quarterly composite analysis for Sr-89 and Sr-90.

d. For gaseous emissions, the principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138.

Other peaks which are measurable and identifiable by gamma-ray spectrometry, together with the above nuclides, shall also be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being at the LLD level for that nuclide.

e. For particulate emissions, the principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Co-60, Zn-65, Co-58, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. Other peaks which are measurable and identifiable by gamma-ray spectrometry, together with the above nuclides, shall also be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being at the LLD level for that nucfide.

f. The LLD is defined in Notation a of Table 12.3-2.

9. Refer to Table 12.2-3 for required actions when the noble gas monitor is not in service.

h. Sampling interruptions of short duration for routine activities, e.g. filter replacement, do not constitute a deviation from the requirements for continuous sampling.

i. The effluent flowrate for Unventilated Building Releases from the Aux Bldg shall be estimated by FAB (cfm) = 72900 f (in of water). When the Aux Bldg pressure can not be determined, the maximum flowrate of one exhaust fan, 67000 cfm, shall be used as the effluent flowrate.

j. The effluent flowrate for Unventilated Building Releases from the Fuel Bldg shall be estimated by FFB (cfm) = 24300 iIdiP (in of water). When the Fuel Bldg pressure can not be determined, the maximum flowrate of the exhaust fan, 15000 cfm, shall be used as the effluent flowrate.

z12r6.doc 12-29

ZION Revision 10 June 2003 12.4.2 Dose - Noble Gases Operability Requirements 12.4.2.A The air dose due to noble gases released in gaseous effluents from each unit to areas at or beyond the SITE BOUNDARY (see Zion Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the following:

1. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and

2. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

Applicability: At all times Action

1. With the calculated air dose from gaseous effluents exceeding the above limits, define the ccvrective action(s) to be taken to ensure that future releases are in compliance with Section 12.4.2.A.

2. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding twice the limits of Section 12.4.2.A:

a. Limit subsequent releases such that the dose or dose commitment to a MEMBER OF THE PUBLIC from all uranium fuel cydle sources is limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months.

b. Prepare an analysis which demonstrates that radiation exposures to all MEMBERS OF THE PUBLIC from all uranium fuel cycle sources (including all effluents pathways and direct radiation) are less than the 40 CFR Part 190 Standard.

Surveillance Requirements 12.4.2.B Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodologies and parameters of the ODCM at least once every 31 days.

z12r6.doc 12-30

ZION Revision 10 June 2003 Bases 12.4.2.C This Section implements the requirements of Sections II.B, III.A and IV.A of Appendix I, 10CFR Part 50. The Operability Requirements implement the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculation procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated.

zI 2r6.doc 12-31

ZION Revision 10 June 2003 12.4.3 Dose 131,1-133, Tritium, and Radioactive Material in Particulate Form Operability Requirements 12.4.3.A The dose to a MEMBER OF THE PUBLIC from 1-131,1-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas at or beyond the SITE BOUNDARY (see Zion Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the following:

1. During any calendar quarter: Less than or equal to 7.5 mrem to any organ, and

2. During any calendar year: Less than or equal to 15 mrem to any organ.

Applicability: At all times.

Action With the calculated dose from the release of lodine-1 31, lodine-1 33, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents exceeding twice the limits of Section 12.4.3.A:

1. Limit subsequent releases such that the dose or dose commitment to a MEMBER OF THE PUBLIC from all uranium fuel cycle sources to less than or equal to 25 mrem to the total body or organ (except the thyroid which is limited to less than or equal to 75 mrem) over 12 consecutive months.

2. Prepare an analysis which demonstrates that radiation exposures to all MEMBERS OF THE PUBLIC from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40CFR Part 190 Standard. Otherwise, request a variance from the Commission to permit release which exceeds the 40CFR Part 190 Standard. The radiation exposure analysis shall use the methods prescribed in the ODCM.

Surveillance Requirements 12.4.3.B Cumulative dose contribution for the current calendar quarter and current calendar year for 1-131, 1-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodologies and parameters in the ODCM at least once per 31 days.

z12r6.doc 12-32

ZION Revision 10 June 2003 Bases 12.4.3.C This Section implements the requirements of Sections II.C, III.A and IV.A of Appendix I.

10CFR Part 50. The Operability Requirements are the guides set forth in Section I.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time, implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculation methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The release-rate specifications for radioiodines, radioactive material in particulate form and radioiodines other than noble gases are dependent on the existing radionuclide pathways to man, at or beyond the SITE BOUNDARY. The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides, 2) disposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man.

z12r6.doc 12-33

ZION Revision 10 June 2003 12.4.4 Gaseous Effluent Treatment System Operability Requirements 12.4.4.A The GASEOUS EFFLUENT TREATMENT SYSTEM shall be OPERABLE' and appropriate portions of these systems shall be used to reduce radioactive materials in gaseous effluents when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at or beyond the SITE BOUNDARY (see Zion Station ODCM Annex, Appendix F, Figure F-1) would exceed:

1. 0.2 mrad to air from gamma radiation, or

2. 0.4 mrad to air from beta radiation, or

3. 0.3 mrem to any organ.

The installed GASEOUS EFFLUENT TREATMENT SYSTEM shall be considered OPERABLE by meeting Sections 12.4.1, 12.4.2 and/or 12.4.3, as applicable.

Applicability: At all times.

Action: With the Gaseous Effluent Treatment System inoperable for more than 30 days or with radioactive gaseous waste being discharged without treatment and in excess of the above limits, return the system to OPERABLE status and place the appropriate portions of the system in use.

Surveillance Requirements 12.4.4.B Doses due to gaseous releases from each unit to areas at or beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodologies and parameters in the ODCM when the Gaseous Effluent Treatment Systems are not being fully utilized.

Bases 12.4.4.C The OPERABILITY of the GASEOUS EFFLUENT TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment.

The requirement that the appropriate portions of this system be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable.' This section implements the requirement of 10CFR50.36a, General Design Criterion 60 of Appendix A to 10CFR50 and the design objective given in Section I1.D of Appendix I to 10CFR50. The specified limits governing the use of appropriate portions of the Gaseous Effluent Treatment System were specified as a 2% fraction of the dose design objectives set forth in Section 11.B and II.C of Appendix I, 10CFR50, for gaseous effluents.

zl 2r6.doc 12-34

ZION Revision 10 June 2003 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Monitoring Program Operability Requirements 12.5.1.A The Radiological Environmental Monitoring Program shall be conducted as specified in Table 12.5-1.

Applicability: At all times.

Action

1. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 12.5-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting a program as required and the plans for preventing a recurrence.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of sampling equipment, if a person who participates in the program goes out of business or no longer can provide sample, or contractor omission which is corrected as soon as discovered. If the equipment malfunctions, corrective actions shall be completed as soon as practical. If a person/business supplying samples goes out of business, a replacement supplier shall be found as soon as possible. All deviations from the sampling schedule shall be described in the Annual Radiological Environmental Operating Report.

2. With the level of radioactivity as a result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 12.5-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of Section 12.3.2, 12.4.2, or 12.4.3.

When more than one of the radionuclides in Table 12.5.2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) + concentration (2) + ... > 1.0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 12.5-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Section 12.3.2, 12.4.2, or 12.4.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such a event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

'The methodology and parameters used to estimate the potential dose to a MEMBER OF THE PUBLIC shall be indicated in the report.

z12r6.doc 12-35

ZION Revision 10 June 2003

3. If the sample type or sampling location(s) required by Table 12.5-1 become(s) permanently unavailable, identify suitable alternative sampling media for the pathway of interest and/or specific locations for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program as soon as practicable. The specific locations from which samples were unavailable may then be deleted from the program.

Prepare and submit a controlled version of the ODCM within 180 days including a revised figure(s) and table reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of new location(s) for obtaining samples.

Surveillance Requirements 12.5.1.B.1 The Radiological Environmental Monitoring samples shall be collected from the locations specified in the ODCM and analyzed pursuant to Table 12.5-1 and the detection capabilities required by Table 12.5-3.

Bases 12.5.1.C The Radiological Environmental Monitoring Program required by this section provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10CFR50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The specified monitoring program is based on baseline/historical conditions for direct radiation measurements, soil, biota, and sediments established over years of operational experience and current site conditions/operating activities. The REMP need only be re-evaluated for major changes to site conditions/configuration (e.g., prior to site decommissioning, if a significant release occurs, changing baseline data...). Program changes may be initiated at any time based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLD). The LLDs required by Table 12.5-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement' Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, LA., 'Limits for Qualitative Detection and Quantitative Determination-Application to Radiochemistry," Anal. Chem.

40, 586-93 (1968), and Gartwell, J.K., 'Detection Limits for Radioanalytical Counting Techniques,' Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

z1 2r=.doc 12-36

ZION Revision 10 June 2003 Interpretations 12.5.1.D Table 12.5-1 requires "one sample of each community drinking water supply downstream of the plant within 10 kilometers (6.2 miles)." Drinking water supply is defined as water taken from river, lakes, or reservoirs (not well water) which is used for drinking. Since Lake Michigan has no designated downstream or upstream direction, two drinking water locations (one northlone south) within 10 kilometers shall be sampled as drinking water indicator locations, and two other locations (one north/one south) beyond 10 kilometers shall be sampled as control locations.

zi 2r6.doc 12-37

ZION Revision 10 June 2003 TABLE 12.5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND FREQUENCY OF AND/ OR SAMPLE AND SAMPLE LOCATIONS(1) FREQUENCY ANALYSIS

1. Airborne Samples from a total of three locations: Particulate Sampler:

Contnuou samler peraion Gross beta analysis following

a. Indicator- Near Field with particulate sample collection weekly filter chan e(3)and gamma weekly (or more frequently if isotopic analysis( quarterly on Three samples from locations within 4 km required due to dust loading), copoi afilters byaloctio on (2.5 mi) in different sectors. cmoieflesb oaino near field samples.

z12r6.doc 12-38

ZION Revision 10 June 2003 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND FREQUENCY OF AND/ OR SAMPLE AND SAMPLE LOCATIONS(') FREQUENCY ANALYSIS

2. Direct Radiation(5 ) Seventeen routine monitoring stations with thermoluminescent dosimeters (TLD), placed with at least one monitoring location in each meteorological sector, as follows:

a. Indicator- Inner Ring (100 Series TLD) in the general area of the SITE BOUNDARY (0.1 to 1.5 mi); Quarterly Gamma dose on each TLD quarterly.

b. Other One at each Airborne location given in part 1.a.

Other TLDs may be placed at special interest locations beyond the Restricted Area where either a MEMBER OF THE PUBLIC or Commonwealth Edison employees have routine access.

(300 Series TLD)

. . J..

i2-z1 2ff.doc .. .12-39

ZION Revision 10 June 2003 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND FREQUENCY OF AND/ OR SAMPLE AND SAMPLE LOCATIONS"' FREQUENCY. ANALYSIS

3. Waterbomnet--*..!,..S,:-'_' -.

a. Drinking Water Indicator(6 ) - -.. . -

One Sample from each community Gross beta and gamma isotopic drinking water supply that could be analyses 4( ) on monthly composite; affected by the station discharge within 10 Weekly grab samples. tritium analysis on quarterly km (6.2 mi) of discharge (north/south). composite.

b. Control("

e sGross beta and gamma isotopic One sample upstream and downstream Weekly grab samples, analyses(4) on monthly composite; (north/south) of discharge. tritium analysis on quarterly composite.

c. Sediments At least one sample within 10 km (6.2 mi) Semiannually. Gamma isotopic analysis (4) of discharge semiannually.

~~~. -; . ',. A..

':il'. . ., .0 z12r6.doc 12-40

ZION Revision 10 June 2003 TABLE 12.5-1 (Continued)

RADIOLOGICAL- ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND FREQUENCY OF AND/ OR SAMPLE AND SAMPLE LOCATIONSM FREQUENCY ANALYSIS

4. Ingestion

a. Fish Indicator Representative samples of commercially and recreationally important species in discharge Semiannually Gamma isotopic analysisz4 ' on edible area. portions.

b. Control Representative samples of commercially and Semiannually Gamma isotopic analysis 4 ) on edible recreationally important species not influenced portions.

by plant discharge.

lt .

._ ;-I

. _C .: .: . . . _- . ...

.7 - . --. . . .

z12r6.doc 12-41

ZION Revision 10 June 2003 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS (1) Specific parameters of distance and direction from the centerline of the midpoint of the two units and additional description where pertinent, shall be provided for each and every sample location in Table 11-1 of the ODCM Station Annexes. Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979.

(2) Deleted - No longer applicable.

(3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thorium daughter decay. If gross beta activity in any individual air particulate sample is greater than 10 times the 1999 mean of control samples, then, a gamma isotopic analysis shall be performed on that elevated individual sample.

(4) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station.

(5) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The number of locations is not an absolute number. The number of direct radiation monitoring-stations may be reduced according to geographical limitations; e.g., If a station is adjacent to a lake (i.e. Zion), some sectors may be over water thereby reducing the number of dosimeters which could be placed at the indicated distances. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.

(6) Refer to Section 12.5.1.D for interpretation on the applicability of "downstream" and upstream". If no community drinking water supply exists within 6.2 miles of the discharge, surface water sampling shall be performed.

(7) Deleted - No longer applicable.

(8) Deleted - No longer applicable.

(9) DELETED (10) Deleted - No longer applicable.

zi2r6.doc 242

.a..

ZION Revision 10 June 2003 TABLE 12.5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES*

WATER AIRBORNE PARTICULATE FISH ANALYSIS (pCi/I) OR GASES (pCi/m 3 ) (pCi/kg, wet)

H-3 20,000 ()

Mn-54 1,000 301;00 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 Cs-134 30 10 1,000 Cs-1 37 50 20 2,000 Ba-La-140 200 (1) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/I may be used.

This table contains reporting levels for analyses beyond the requirements of Table 12.5-1.

:j f .'

1, z12r6.doc 112-43

ZION Revision 10 June 2003 TABLE 12.5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS( 1 "

LOWER LIMIT OF DETECTION (LLD)(')

AIRBORNE WATER PARTICULATE FISH SEDIMENT ANALYSIS (pCi/) OR GASES (pCi/m 3 ) (pCi/kg, wet) (pCi/kg, dry)

Gross Beta 4 0.01 1000 H-3 2,000(7)

Mn-54 15 130 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 Cs-1 34 15 0.01 100 150 Cs-1 37 18 0.01 100 180 I If Lilly* . .:L- i I .

K z12r6.doc 12-44

ZION Revision 10 June 2003 TABLE 12.5-3 (Continued)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS (1) This table contains lower limits of detection for analyses beyond the requirements of Table 12.5-1. This table does not imply that only these nuclides are to be detected and reported; other peaks which are measurable and identifiable in the analyses required by Table 12.5-1 shall be reported in the Annual Radiological Environmental Operating Report.

(2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.

(3) The Lower Limit of Detection (LLD) is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 950/o probability with only 5%

probability of falsely concluding that a blank observation represents a "real" signal.

-For a particular measurement system, which may include radiochemical separation, the LLD is defined as follows

4.6 6 Sb + 3

/tb LLD= ----------------------

(E) (V) (2.22) (Y) (exp (-XAt))

4.66 Sb

-*LLD - ----------------------

(E) (M)(2.22) (Y) (exp (-XAt))

Where: 4.66 Sb >> 3 /tb LLD = the "a priori" Lower Limit of Detection (picocuries per unit mass or volume),

Sb = the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate (counts par minute),

NITotal Counts tb E = the counting efficiency(counts per disintegration),

V = the sample size (units of mass or volume),

2.22 = the number of disintegrations per minute per picocurie, Y = the fractional radiochemical yield, when applicable, X = the radioactive decay constant for the particular radionuclide (sec 1 ),

tb = counting time of the background or blank (minutes), and z12r5.doc 12-45

I . .I .%

ZION Revision 10 June 2003 TABLE 12.5-3 (Continued)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS at = the elapsed time between sample collection, or end of the sample collection period, and the time of counting (sec).

Typical values of E, V. Y, and at should be used in the calculation.

It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement.

Analyses shall be performed iri such a manner that the stated LLDs will be achieved under routine conditions. Occasionally, background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

(4) Deleted - No longer applicable.

(5) Deleted - No longer applicable.

(6) Deleted - No longer applicable.,

(7) This is the minimum required LLD, however, environmental samples analyzed off-site will [U.

be required to use 200 pCin. .

z12r6.doc 12-46

ZION Revision 10 June 2003 12.5.2 LAND USE CENSUS Operability Requirements 12.5.2.A A Land Use Census shall be conducted and shall identify within a distance of 10 km (6.2 mi) the location, in each of the following meteorological sectors, A, J. K, L, M, N, P. Q.

and R*, the nearest residence. For dose calculation, a garden will be assumed at the nearest residence.

Applicability: At all times.

Action:

With a Land Use Census identifying location(s) that yields a calculated dose or dose commitment, via the same exposure pathway 20% greater than at a location from which samples are currently being obtained in accordance with Section 12.5.1, add the new location(s) within'30 days to the Radiological Environmental Monitoring Program given in.

Chapter 11 of the ODCM Station Annexes. The sampling location(s), excluding the control location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Submit in the next Annual Radiological Environmental Operating Report documentation for a change in the ODCM!,

including revised fidure(s) and table(s) for the ODCM reflecting the new location(s) with ,

information supporting the change in sampling locations.

- The nearest industrial facility shall also be documented if closer than the nearest,',.'.

residence.

Surveillance Requirements 12.5.2.B The Land Use Census shall be conducted, between June 1 and October 1, at least once per calendar year using that information that will provide the best results, such as by a .

door-to-door survey or aerial survey. The result of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report.

Bases 12.5.2.C This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of this census.

This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.

An annual garden census will not be required since the licensee will assume that there is a garden at the nearest residence in each sector for dose calculations.

z12M.doc 12-47

I - I .

ZION Revision 10 June 2003 12.5.3 INTERLABORATORY COMPARISON PROGRAM Operability Requirements 12.5.3.A Analyses shall be performed on radioactive materials supplied as part of an interlaboratory comparison program that correspond to samples required by Table 12.5.1.

Applicability: At all times.

Action:

1. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

Surveillance Requirements 12.5.3.B . A summary of the results obtained as part of the above required interlaboratory comparison program shall be included in the Annual Radiological Environmental Operating Report.

Bases 12.5.3.C The requirement for participation in an interlaboratory comparison prograrr~is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the

-- results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

z12r6.doc 12-48

ZION Revision 10 June 2003 12.6 PROCESS CONTROL PROGRAM (PCP) 12.6.1 PCP Program Requirements Contains the requirements and methodology for the current formulas, sampling, analyses, tests, and determinations performed to ensure the processing and packaging of solid radioactive wastes based on actual or simulated wet solid wastes is accomplished in compliance with:

10CFR Parts 20, 61, and 71 State Regulations

-Burial Site Requirements

Other Requirements Governing the Shipping and Burial of Radioactive Waste 12.6.2 Changes to the PCP Changes to the PCP include those changes that affect the process or methodology, by which wastes are solidified, packaged to meet burial site form requirements, classified, or dewatered.

12.6.2.1. Shall be documented and records of reviews performed shall be retained, and Shall contain sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s), and Shall contain a determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations, and Shall become effective after review and acceptance by the Onsite Review and Investigative Function and the approval of the Decommissioning Plant Manager.

z12r6.doc 1249

ZION Revision 10 June 2003 12.7 REPORTING REQUIREMENTS 12.7.1 Annual Radiological Environmental Operating Report*

Routine Annual Radiological Environmental Operating Report covering the operation of the Unit(s) during the previous calendar year shall be submitted according to the Permanently Defueled Technical Specifications. The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including, as found appropriate, a comparison of preoperational studies with operational controls or with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment The Annual Radiological Environmental Operating Report shall include the results of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures in the Chapter 11 of the ODCM Station Annexes, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; legible maps covering all sampling locations keyed to a table giving distances and directions from the midpoint between the two units; reasons for not conducting the Radiological Environmental Monitoring Program as required by Section 12.5.1, and discussion for all deviations from the sampling schedule of Table 11.1-1; a Table of Missed Samples and a Table of Sample Anomalies for all deviations from the sampling schedule of Table 11.1-1; discussion of environmental sample measurements that exceed the reporting levels of Table 12.5-2 but are not the result of plant effluents; discussion of all analyses in which the LLD required by Table 12.5-3 was not achievable; results of the Land Use Census required by Section 12.5.2; and the results of licensee participation in an interlaboratory comparison program and the corrective actions being taken if the specified program is not being performed as required by Section 12.5.3.

The Annual Radiological Environmental Operating Report shall also include an annual summary of hourly meteorological data collected over the applicable year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Annual Radiological Environmental Operating Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

A single submittal may be made for a multiple unit station.

z12.doc 12-50

ZION Revision 10 June 2003 The Annual Radiological Environmental Operating Report shall also include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the Unit or Station during the previous calendar year. This report shall also include an assessment of radiation doses to the most likely exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM and in compliance with 10 CFR 20 and 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation."

12.7.2 Annual Radioactive Effluent Release Reports The Annual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, wMeasuring, Evaluating, and Reporting Radioactivity in Solid.Wastes and Releases of Radioactive Material in Liquid and Gaseous Effluent from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The Annual Radioactive Effluent Release Report shall include a list and description of unplanned releases of radioactive material in liquid effluents from the site to UNRESTRICTED AREAS and of unplanned releases of radioactive material in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY during the reporting period.

The Annual Radioactive Effluent Release Report shall include any changes made during the reporting period to the Process Control Program as well as any major changes to Liquid, Gaseous or Solid Radwaste Treatment Systems, pursuant to Section 12.7.4.

The Annual Radioactive Effluent Release Report shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Section 12.2.1 or 12.2.2, respectively; and description of the events leading to liquid holdup tanks exceeding the limits of to the Permanently Defueled Technical Specifications.

12.7.2.1 Exceptions to Regulatory Guide 1.21 Reporting Requirements:

a. All references to "semiannual" are not applicable. The report will be submitted according to Technical Specifications.

b. Hourly meteorological data is recorded for all periods throughout the year, and quarterly summaries will be reported. Separate meteorological data for periods of batch releases are not required to be included.

c. Total body and significant organ doses to the maximally exposed individual from receiving-water-related exposure pathways will be provided. Associated population dose is not required to be included.

zl2r6.doc 12-51

83 FROM: X FAX NO.: 8477314266 - 2 4-84e9:5eA P.82 ZION 0- ,U-. . AP0 October 2003 12.7.3 Offsite Dose Calculation Manual (ODCM1 12.7.3.1 Changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as required by Permanently Defueled Technical Specifications. This documentation shall contain;

1. Sufficient Information to support the change together with the appropriate analyses or evaluations justifying the change(s); and

2. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent dose, or setpoint calculations,

3. Documentation of the fact that the change has been reviewed and found acceptable by a Qualified Technical Review.

b. Shall become effective after the approval of the Plant Manager on the date specified by the Qualified Technical Review.

c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed. and shall indicate the date (e.g.,

monthlyear) the change was implemented.

z12r6.doc 12-52

ZION Revision 10 June 2003 12.7.3 Offsite Dose Calculation Manual (ODCM) 12.7.3.1 Changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as required by Permanently Defueled Technical Specifications. This documentation shall contain:

1. Sufficient Information to support the change together with the appropriate analyses or evaluations justifying the change(s); and

2. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302. 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent dose, or setpoint calculations.

3. Documentation of the fact that the change has been reviewed and found acceptable by a Qualified Technical Review.

b. Shall become effective after the approval of the Plant Manager on the date specified by the Qualified Technical Review.

c. :-. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g.,

month/year) the change was Implemented.

z12r6.doc 12-53

ZION Revision 10 June 2003 12.7.4 Malor Changes to Liquid and Gaseous Effluent Treatment Systems***

Licensee-initiated major changes to the Effluent Treatment Systems (liquid and gaseous):

a. Shall be reported to the Cotmiriission in the Annual Radioactive Effluent Release Report for the period inwhih the evaluation was reviewed by a Qualified Technical Review. The discussion of each change shall contain:

1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;

2) Sufficient detailed information to totally support the reason for the change without benefit of additional and supplemental information;

3) A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems.

4) An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the License application and amendments thereto;

5) An -evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC and to the general population that differ from those previously estimated in the License application and amendments thereto;

6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, to the actual releases for the period prior to when the changes are to be made;

7) An estimate of the exposure to plant operating personnel as a result of the change; and

8) Documentation of the fact that the change was reviewed and found acceptable by a Qualified Technical Review.

b. Shall become effective upon review and acceptance by the Qualified Technical Review.

Licensees may choose to submit the information called for in this standard as part of the biennial DSAR update. l zl2r6.doc 12-54

June 12, 2003 Qualified Technical Review= TR/008/2003 To: Mr. Artice Daniels Jr.

Subject; Qualified Technical Review of Chapter 12 Revision 10 to the Offsite Dose Calculation Manual (ODCM).

Pursuant to the ODCM Section 12.7.3 and Technical Specifications 5.6.1 and 5.9.1, the following basis for revisions to the ODCM and the documentation of the Qualified Technical review is attached.

Section 12.7.3 of the ODCM requires a Qualified Technical Review be performed. This review will be performed by at least two qualified individuals with the appropriate ANSI disciplines and approved by the Decommissioned Plant Manager.

Engineering Assigned Disciplines for this Qualified Technical Review are:

Disciplines are assigned by - -Date 3 Qualified Technical Reviewers Discipli signat an'ae Disciplines

1*5 Si Dat 6-d Signature and Date Disciplines Signature and Date Disciplines L~2 I Concur and Approve DAe Artice Daniels Jr.

Decomniissioning Plant Manager Zion Station

ATTACHMENT C: 50.59 REVIEW COVERSHEET FORM Station: Zion Station_

Activily/Document Number: ODCM Chapter 12 Revision Number: 10

Title:

Offsite Dose Calculation Manual_

NOTE: For 50.59 Evaluations, information on this form will provide the basis for preparing the biennial summary report submitted to the NRC in accordance with the requirements of 10 CFR 50.59(d)(2).

Description of Activity:

(Provide a brief, concise description of what the proposed activity involves.)

The ODCM provides a method to sample, collect, analyze, and calculate the effluent streams in the determination of Radiological dose to the public.

The activity associated with this revision is to replace 2 area rad monitors and to remove the word "portable" when referring to a pump that provides flow to the associated rad monitors. Remove the associated footnote that applied to the old monitor.

Remove the word "portable" from the compensatory measures in maintaining flow to rad monitors.

Add the phrase "with a load suspended from the hook." For the source check operations of the fuel building crane rad monitor.

Reason for Activity:

(Discuss why the proposed activity is being performed.)

The rad monitors are being changed so that an interface with a new computer system can occur. The end result will be the transmission of data to the Illinois Department of Nuclear Safety. Footnote associated with the "old" rad monitor is no longer applicable.

The removal of the word portable from the compensatory measures will allow the installation of any pump that can provide the required flow to the monitor.

Define the expectations for source check of the rad monitor.

Effect of Activity:

(Discuss how the activity impacts plant operations, design bases, or safety analyses described in the UFSAR.)

The rad monitor change will provide an upgrade in technology that will interface with existing computer system. Remove a footnote that is no linger applicable.

The removal of the word "portable" will allow for the station to provide the required sample flow to the unit specific PR49 rad monitor using the existing sample pump during trouble shooting, testing or repairs.

Describe the circumstances in which the rad monitor shall be source checked.

Summary of Conclusion for the Activity's 50.59 Review:

(Provide justification for the conclusion, including sufficient detail to recognize and understand the essential arguments leading to the conclusion. Provide more than a simple statement that a 50.59 Screening, 50.59 Evaluation, or a License Amendment Request, as applicable, is not required.)

The area rad monitors that are currently in place provide an analog readout that is not compatible with the computer that interfaces with the Illinois Department of Nuclear Safety. It became the objective of this plant modification to purchase and install area rad monitors that provide a digital output that input into the computer system that provides data for the Illinois Department of Nuclear Safety. Remove a footnote that is no longer applicable to a rad monitor that is being removed from the ODCM.

The removal of the word "portable" from the compensatory measures allows the station the flexibility to maintain regulated flow to the appropriate rad monitor during repairs, trouble shooting, or calibration so that the instrumentation can be verified to meet all operational criteria prior to the termination of the work request and cancellation of the out of Service.

Give better directions as to when the rad monitor associated with the Fuel Building Crane shall have a source check performed.

Screening of this change to the ODCM is not required. Using attachment D section 1-8 Programs controlled by the Operating License or.

the Technical Specifications (such as the ODCM) have an establish criteria for changes to be made to this documentation.

Attachments:

Attach all 50.59 Review forms completed, as appropriate.

(NOTE: if both a Screening and Evaluation are completed, no Screening No. is required.)

ATTACHMENT C: 50.59 REVIEW COVERSHEET FORM Station: Zion Station_

Acti-vity/Document Number: ODCM Chapter 12_ Revision Number: 10

Title:

Offsite Dose Calculation Manual_

H Forms Attached: (Check all that apply.)

Applicability Review 50.59 Screening 50.59 Screening No. Rev.

50.59 Evaluation 50.59 Evaluation No. Rev.

ZAP-1 00-06 Revision 18 Information Use ATTACHMENT D: 50.59 APPLICABILITY REVIEW FORM Activity/Document Number: 6'nw CIz"pr /,- Revision Number:_ _ __

Address the questions below for all aspects ofthe Activity. If the answer is yes for any portion of the Activity, apply the identified process(es) to that portion of the Activity. Note that it is not unusual to have more than one process apply to a given Activity.

See Section 4 of the Resource Manual (RM) for additional guidance.

_ Does the proposed Activity involve a change:

1. Technical Specifications or Operating License (IOCFR50.90)? NO _ YES See Section 4.2.1.1 ofthe RM

2. Conditions of License Quality Assurance program (I OCFR5O.54(a))? ;NO _ YES Security Plan (IOCFR50.54(p))? -NO _ YES See Section 4.2.1.2 of the RM Emergency Plan (I OCFR5O.54(q))? NO YES

3. Codes and Standards IST Program Plan (I OCFRSO.55a(o)? ,XNO . YES See Section 4.2.1.3 oftheRM ISI Program Plan (10CFR5O.55a(g))? _XNO - YES

4. ECCS Acceptance Criteria (1 OCFR5O.46)? XNO _ YES See Section 4.2.1.4 of the RM

5. Specific Exemptions (I OCFR50.12)? YES See Section 4.2.1.5 of the RM

6. Radiation Protection Program (I OCFR20)? )(NO _ YES See Section 4.2.1.6 of the RM

7. Fire Protection Program (applicable UFSAR or operating license KNO _ YES See Section 4.2.1.7 of the RM condition)? _

8. Programs controlled by the Operating License or the Technical NO BYES See Section 4.2.1.7 of the RM Specifications (such as the ODCM). -_ 'C-

9. Environmental Protection Program _4O YES See Section 4.2.1.7 ofthe RM

10. Other programs controlled by other regulations. ,CNO _ YES See Section 4.2.1 of the RM II. Does the proposed Activity involve maintenance which restores SSCs to their original condition or involve a temporary alteration supporting _Ž(NO YES See Section 4.2.2 of the RM maintenance that will be in effect during at-power operations for 90 days or less? -

111. Does the proposed Activity involve a change to the:

I. UFSAR (including documents incorporated by reference) that is excluded from the requirement to perform a 50.59 Review by NEI 96-07 YNO - YES See Section 4.2.3 of the RM orNEI 98-03?

2. Managerial or administrative procedures governing the conduct of facility operations NO _ YES See Section 4.2.4 of the RM

3. Procedures for performing maintenance activities (subject to 10 CFR ,zlNO _ YES See Section 4.2.4 of the RM 50.65(a)(4))? ________

4. Regulatory commitment not covered by another regulation based change ,2%10 - YES See Section 42.3/4.2.4 of the RM proc ss (see NEI 99.04)? ANO_ ESSe Scton4..34..4ofth R IV. Does the proposed Activity involve a change to the Independent Spent Fuel X - YES See Section 4.2.6 of the RM Storage Installation (ISFSI) (subject to control by 10 CFR 72.48) ,2_o YES

_ See Sction 42. the R

_of Check one of the following:

If all aspects of the Activity are controlled by one or more of the above processes, then a 50.59 Screening is nnot required and the Activity may be implemented in accordance with its governing procedure.

If any portion of the Activity is not controlled by one or more of the above processes, then process a 50.59 Screening for the portion not covered by any of the above processes. The remaining portion of the activity should be implemented in accordance Signoff: with its governing procedure.

50.59 Screener/SO. Evaluao _________ _Sign: _Date:_/_____

(Circle (Print name) (Signature) 21 of 24

Summary of the Changes made to Zion Station Offsite Dose Calculation Manual ODCM Change the numeric nomenclature for the. installation of new area rad monitors.

Table 12.2-3 3.C.I. Change ORT-AR03 to ORT-AR21 3.C.2. Change ORE-005 to ORT-AR22 Footnote to this table:

3The auto control function on high alarm is no longer required for this monitor ( i.e., does not need to be maintained operable for the monitor to be operable).

This footnote is was applicable to the ORT-AR03, which is being removed from the ODCM.

Remove the word portable for the maintaining of sample flow to the monitor or sample point.

Table 12.2-3 Surveillance 10 Rev 9 l Rev 10 With the number of OPERABLE channels less With the number of OPERABLE channels less than the minimum number required, restore the than the minimum number required, restore the channel to OPERABLE status within 30 days or channel to OPERABLE status within 30 days or conduct a station review to determine a plan of conduct a station review to determine a plan of action to restore the channel to OPERABLE action to restore the channel to OPERABLE status. Effluent releases via this pathway may status. Effluent releases via this pathway may continue provided grab samples are obtained continue provided grab samples are obtained and analyzed for gross activity at least once and analyzed for gross activity at least once per day, OR for the case when the associated per day, OR for the case when the associated LP-084 panel is inoperable, continuous LP-084 panel is inoperable, continuous sampling is maintained with a portable pump sampling is maintained with a pump and and Operations performs a Channel Check Operations performs a Channel Check Daily.

Daily. Compensatory sampling does not return Compensatory sampling does not return the the monitor to an OPERABLE status. monitor to an OPERABLE status.

Remove the word portable for the maintaining of sample flow to the monitor or sample point.

Table 12.2-3 Surveillance 11 1 Rev 9 . Rev 10 With the number of OPERABLE channels less With the number of OPERABLE channels less than the minimum number required, restore the than the minimum number required, restore the

channel to OPERABLE status within 30 days or channel to OPERABLE status within 30 days or conduct a station review to determine a plan of conduct a station review to determine a plan of action to restore the channel to OPERABLE action to restore the channel to OPERABLE status. Effluent releases via this pathway may status. Effluent releases via this pathway may continue provided samples are continuously continue provided samples are continuously collected as required in Table 12.4-1. For the collected as required in Table 12.4-1. For the case when the associated LP-084 panel is case when the associated LP-084 panel is inoperable, continuous sampling can be inoperable, continuous sampling can be maintained with a portable pump and maintained with a pump and Operations shall Operations shall perform a Channel Check perform a Channel Check Daily.

Daily. Compensatory sampling does not return Compensatory sampling does not return the the monitor to an OPERABLE status. monitor to an OPERABLE status.

Change the numeric nomenclature for the installation of new area rad monitors.

Table 12.2-4 3.C.1. Change ORT-AR03 to ORT-AR21 3.C.2. Change ORE-005 to ORT-AR22 Table 12.2-4 Notations (3) Daily during operations of overhead crane in by pass mode.

Change to "Daily during operations of overhead crane in by pass mode with a load suspended from the hook."

Letter to File:

Date: July 1, 2003 Subject; Implementation of the ODCM Rev 11 In the process of changing the Offsite Dose Calculation Manual it has been discovered that there were two independent changes occurring simultaneously. This letter is being used to capture the sequence of events.

At the beginning of the process this change was being implemented to account for the change out of the new area monitors in the Fuel building. During this process another change to the ODCM was being performed for the discharge of effluents to lake Michigan.

All of the paper work associated with the area monitors was to change Rev. 9 to Rev 10.

In actuality this change should have been Rev. 10 to Rev. 11.

After consultation with the Department Head of Administration this cover letter was generated to capture the changes and the discrepancy in the paperwork as submitted.

Ron Schuster RPM

ZION

Revision 11 July 2003 SPECIAL NOTE The requirements of Permanently Defueled Technical Specifications shall take precedence over this chapter, should any differences occur.

z12r6.doc 12-i

ZION Revision 11 July 2003 CHAPTER 12 REVISION 11 I zl2r6.doc 12-ii

ZION Revision 11 July 2003 CHAPTER 12 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS (RETS)

TABLE OF CONTENTS PAGE 12.1 DEFINITIONS 12-1 12.2 INSTRUMENTATION

1. Radioactive Liquid Plant Monitoring Instrumentation 12-5

2. Radioactive Plant Monitoring Instrumentation 12-9 12.3 LIQUID EFFLUENTS

1. Concentration 12-17

2. Dose 12-23

3. Liquid Radwaste Treatment System 12-25 12.4 GASEOUS EFFLUENTS

1. Dose Rate 12-26

2. Dose - Noble Gases 12-30

3. Dose 131,1-133, Tritium, and Radioactive Material in Particulate Form 12-32

4. Gaseous Effluent Treatment System . 12-34 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

1. Monitoring Program 12-35

2. Land Use Census 12-47

3. Interlaboratory Comparison Program 12-48 12.6 PROCESS CONTROL PROGRAM (PCP)

1. PCP Program Requirement 12-49

2. Changes to the PCP 12-49 12.7 REPORTING REQUIREMENTS

1. Annual Radiological Environmental Operating Report 12-50

2. Annual Radioactive Effluent Release Report 12-51

3. Offsite Dose Calculation Manual (ODCM) 12-53

4. Major Changes to Liquid and Gaseous Effluent Treatment Systems 12-54 zl2r6.doc 12-iii

Revision II ZION ZION Revision 11 July 2003 CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)

LIST OF TABLES PAGE 12.1-1 Surveillance Frequency Notations 12-4 12.2-1 Radioactive Liquid Plant Monitoring Instrumentation 12-6 12.2-2 Radioactive Liquid Plant Monitoring Instrumentation Surveillance 12-8 12.2-3 Radioactive Plant Monitoring Instrumentation 12-10 12.24 Radioactive Plant Monitoring Instrumentation Surveillance 12-14 12.3-1 Allowable Concentration of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Effluents 12-19 12.3-2 Radioactive Liquid Effluent Sampling and Analysis Surveillance 12-20 12.4-1 Radioactive Gaseous Effluent Sampling and Analysis Program 12-27 12.5-1 Radiological Environmental Monitoring Program 12-38 12.5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 12-43 12.5-3 Detection Capabilities for Environmental Sample Analysis 12-44 z12r6.doc 12-iv

ZION Revision 11 July 2003 12.1 DEFINITIONS 12.1.1 A BATCH RELEASE is the discharge of liquid wastes of a discrete volume. Priorto sampling for analyses, each batch shall be isolated and then thoroughly mixed to assure representative sampling.

12.1.2 A CHANNEL CALIBRATION, shall be the adjustment, as necessary, of the channel such that it responds with the necessary range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors (where possible),

alarm interlock and/or trip functions and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

12.1.3 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent INSTRUMENT CHANNELS measuring the same parameter.

12.1.4 A CHANNEL FUNCTIONAL CHECK shall be:

a. Instruments-The injection of a simulated signal(s) into the channel as close to the primary sensor(s) as practicable to verify OPERABILITY, including all channel outputs, as appropriate.

b. Logics-The application of input signals, or the operation of relays or switch contacts, in all the combinations required to produce the required decision outputs including the operation of all ACTUATION DEVICES. Where practicable, the test shall include the operation of the ACTUATED EQUIPMENT as well (i.e. pumps will be started, valves operated, etc.).

12.1.5 A COMPOSITE SAMPLE is one in which the quantity of liquid sample is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

12.1.6 A CONTINUOUS RELEASE is the discharge of liquid or gaseous wastes of a nondiscrete volume (e.g. from a volume or system that has an input flow during the release).

12.1.7 CONTINUOUS SAMPLING is uninterrupted sampling with the exception of sampling interruptions of short duration for routine activities (e.g. filter replacements).

12.1.8 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcurielgram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131,1-132,1-133, 1-134, and 1-135 actually present. The Thyroid Dose Conversion factors used for this calculation shall be those listed in Table IlIl of TID-14844, "Calculation of Distance Factors for Power and Test Reactor Sites" or Table E-7 of NRC Regulatory Guide 1.109 Rev. 1, dated October, 1977. This definition is not used in the defueled condition. Decay has eliminated all concerns related to radioactive iodine.

12.1.9 MEMBER OF THE PUBLIC means any individual except when that individual is receiving an occupational dose.

z12r6.doc 12-1

ZION Revision 11 July 2003 12.1.10 OCCUPATIONAL DOSE means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation and/or radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include dose from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the public.

12.1.11 OPERABLE - A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).

12.1.12 OPERATING is defined as performing the intended function in the intended manner.

12.1.13 The OPERATING CYCLE: DELETED 12.1.14 An OPERATIONAL MODE: DELETED 12.1.15 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

12.1.16 PURGE OR PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner, that replacement air or gas is required to purify the confinement.

12.1.17 RATED THERMAL POWER: DELETED 12.1.18 The REACTOR PRESSURE: DELETED 12.1.19 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased or otherwise controlled by the licensee.

12.1.20 SOLIDIFICATION shall be the conversion of radioactive liquid, resin and sludge wastes from liquid systems into a form that meets shipping and burial site requirements.

12.1.21 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

z12r6.doc 12-2

ZION Revision 11 July 2003 12.1.22 SURVEILLANCE shall be those parts of the sections which prescribe remedial measures required under designated conditions, activities required to demonstrate instrument operability, and activities performed to ensure applicable offsite dose limits are not exceeded.

12.1.23 The SURVEILLANCE FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 12.1-1.

12.1.24 THERMAL POWER: DELETED 12.1.25 UNRESTRICTED AREA means an area, access to which is neither limited nor controlled by the licensee.

12.1.26 GASEOUS EFFLUENT TREATMENT SYSTEM shall be any system designed and installed to reduce radioactive material in particulate form in effluents by passing ventilation through HEPA filters for the purpose of removing particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any affect on noble gas effluents. The iodine removal function is no longer used in the defueled condition.

12.1.27 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during venting. Vent, used in system names, does not imply a venting process.

12.1.28 WASTE GAS HOLDUP SYSTEM: DELETED z12r6.doc 12-3

ZION Revision 11 July 2003 TABLE 12.1-1 SURVEILLANCE FREQUENCY NOTATIONS NOTATION FREQUENCY

S (Shiftly) At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D (Daily) At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months W (Weekly) At least once per 7 days M (Monthly) At least once per 31 days 0 (Quarterly) At least once per 92 days SA (Semiannually) At least once per 184 days A (Annually) At least once per 366 days R At least once per 18 months p (Prior) Complete prior to start of release N/A Not Applicable

Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. These frequency notations do not apply to the Radiological Environmental Monitoring Program as described in Section 12.5.

z12r6.doc 12-4

ZION Revision 11 July 2003 12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Plant Monitoring Instrumentation Operabilitv Requirements 12.2.1.A The radioactive liquid plant monitoring instrumentation channels shown in Table 12.2-1 shall be OPERABLE AND, the radioactive liquid effluent monitoring instrumentation channels shall have their alarm/trip setpoints set to ensure that the limits of Section 12.3.1.A are met.

Arplicabilitv: As indicated in Table 12.2-3.

Action

1. With a radioactive liquid effluent monitoring instrument channel trip setpoint less conservative than the value necessary to prevent violating the limits of Section 12.3.1A, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

2. With one or more radioactive liquid plant monitoring instrumentation channels inoperable, initiate the SURVEILLANCE requirement delineated in Table 12.2-1.

Surveillance Requirements 12.2.1.B.1 The liquid effluent monitor setpoints shall be determined in accordance with procedures as described in the ODCM.

12.2.1.B.2 Each radioactive liquid plant monitoring instrumentation channel shall be demonstrated OPERABLE by performance of a CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 12.2-2.

Bases 12.2.1.C The radioactive liquid plant monitoring instrumentation is provided to indicate abnormal radiological conditions within the plant, AND The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the release of radioactive materials in liquid effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of RETS. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10CFR Part 50.

z12r6.doc 12-5

ZION Revision 11 July 2003 TABLE 12.2-1 RADIOACTIVE LIQUID PLANT MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE SURVEILLANCE # CONDITION

1. Liquid Effluent Monitors Providing Automatic Termination of Release A. Boric Acid Monitor Tank (BAMT)

1. OR-PRO5 See SURVEILLANCE I I Liquid Release through this Pathway B. Turbine Bldg.

1. OR-PR25 1 2 Liquid Release through this Pathway

2. Effluent Continuous Composite Sampler A. Turbine Building Fire Sump 1 2 All Times

3. Effluent Flow Rate Monitor A. Boric Acid Monitor Tank

1. OFI-WD005 1 3 Liquid Release through this Pathway

4. Plant System Monitors NONE z12r6.doc 12-6

1:

ZION Revision 11 July 2003 TABLE 12.2-1 RADIOACTIVE LIQUID PLANT MONITORING INSTRUMENTATION (Cont'd)

SURVEILLANCE I If the monitor is inoperable, effluent releases from the tank may continue for up to 14 days, provided that prior to initiating the release:

1. At least two independent samples of the tank's contents are analyzed, in accordance with Section 12.3.1.B.1, and

2. At least two technically qualified members of the facility staff independently verify the release-rate calculations and discharge flow path valving; Otherwise, suspend release of radioactive effluents via this pathway.

SURVEILLANCE 2 With the number of channels OPERABLE less the minimum number required, effluent releases via this pathway may continue, provided that at least once per day grab samples are analyzed for gross radioactivity (beta /gamma or isotopic) at a lower limit of detection (LLD) as specified in Table 12.3-2. Restore the channel to operable status within 30 days or conduct a station review to determine a plan of action to restore the channel to operable status:

SURVEILLANCE 3 With the number of channels OPERABLE less than the minimum number required, effluent releases via this pathway may continue, for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump curves may be used to estimate flow.

z12r6.doc 12-7

ZION Revision 11 July 2003 TABLE 12.2-2 RADIOACTIVE LIQUID PLANT MONITORING INSTRUMENTATION SURVEILLANCE CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION(1) TEST (2)

1. Liquid Effluent Monitors Providing Automatic Termination Of Release A. Boric Acid Monitor Tank (BAMT)

1. OR-PRO5 P P R Q B. Turbine Bldg.

1. OR-PR25 D M R Q

2. Effluent Continuous Composite Sampler A. Turbine Building Fire Sump D NIA NIA N/A

3. Effluent Flow Rate Monitor A. Boric Acid Monitor Tank (BAMT)

1. OFI-WD005 D(3) NIA R(4) N/A

4. Plant System Monitors NONE (1) CHANNEL CALIBRATION shall include performance of a CHANNEL FUNCTIONAL TEST.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that any automatic isolation of this pathway occurs and that control room alarm annunciation occurs if any of the following conditions exist. (if the capability Isinstalled):

a) Instrument Indicates levels above the alarm setpoints.

b) Circuit failure.

c) Instrument Indicates a downscale failure.

d) Instrument controls not set Inoperate mode.

(3) CHANNEL CHECK shall consist of verifying Indications of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or BATCH RELEASES are made.

(4) Does not include flow sensor.

z12r6.doc 12-8

ZION Revision 11 July 2003 12.2.2 Radioactive Plant Monitoring Instrumentation Operabilitv Requirements 12.2.2.A The radioactive plant monitoring instrumentation channels shown in Table 12.2-3 shall be OPERABLE, AND, the radioactive gaseous effluent monitoring instrumentation shall have their alarm/trip setpoints set in accordance with the method prescribed in the ODCM to ensure that the limits of Section 12.4.1.A are met.

Applicability: As indicated in Table 12.2-3.

Action

1. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Section, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.

2. With one or more radioactive plant monitoring instrumentation channels inoperable, initiate the SURVEILLANCE requirement as delineated in Table 12.2-3.

Surveillance Requirements 12.2.2.B.1 The effluent monitor setpoints shall be determined in accordance with procedures as described in the ODCM.

12.2.2.B.2 Each radioactive plant monitoring instrumentation channel shall be demonstrated OPERABLE, when in its APPLICABLE CONDITION, by performance of a CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 12.2-4.

Bases 12.2.2.C The radioactive plant monitoring instrumentation is provided to indicate abnormal radiological conditions within the plant, AND, The radioactive gaseous effluent instrumentation is provided to monitor, record and control, as applicable, the release of radioactive materials in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR Part 20.

An Auxiliary Building (AB) ventilation stack is considered available as a release path from radiologically controlled areas of the Auxiliary Building when any AB exhaust fan is discharging to that stack, or any one of the AB exhaust fan dampers is open on that stack.

An Auxiliary Building ventilation stack is unavailable as a release path from radiologically controlled areas of the Auxiliary Building when all AB exhaust fan dampers for that stack are mechanically blocked closed.

zl2r6.doc 12-9

ZION Revision 11 July 2003 TABLE 12.2-3 RADIOACTIVE PLANT MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE SURVEILLANCE CONDITION

1. Effluent Containment Purge or Vent A. Particulate Monitor 12

1. IR-PR40A (Channel 1) 1 6, 7 Venting or Purging

2. 2R-PR40A (Channel 1) 1 6,127 Venting or Purging

2. Aux Building Effluent Monitoring A. Gas Activity Monitor

1. IR-PR49E (Channel 5) 1 10

2. 2R-PR49E (Channel 5) 1 10 **

B. Particulate Monitor

1. 1R-PR49A (Channel 1) 1 11

2. 2R-PR49A (Channel 1) I 11 **

C. Flow Rate Monitor

1. 1LP-084 1 8 *

2. 2LP-084 I 8 **

- Whenever the Unit 2stack is available as a release path from the Auxiliary Building.

Whenever the Unit 2 stack is available as a release path from the Auxiliary Building.

3. Fuel Building Monitoring A. Gas Activity Monitor

1. ORT-PR30A 1 10 All Times B. Particulate Monitor

1. ORT-PR30B 1 I11 All Times C. Area Monitoring

1. ORT-AR21 1 12 When fuel is present

2. ORT-AR22 I 14 When fuel is present

3. ORT-AR13 I 13 When fuel building crane is operated with a load on either hook in the bypass mode During VENTING 2During PURGING z12r6.doc 12-10

ZION

Revision 11 July 2003 TABLE 12.2-3 RADIOACTIVE PLANT MONITORING INSTRUMENTATION (Cont'd)

MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE SURVEILLANCE CONDITION

4. Emergency Monitoring A. Ventilation

1. I RIA-PR49 (Channel 7) 1 9 **

2. 2RIA-PR49 (Channel 7) I 9

3. 1RIA-PR49 (Channel 9) I 9

4. 2RIA-PR49 (Channel 9) 1 9

Whenever the Unit 1 stack is available as a release path from the Auxiliary Building.

Whenever the Unit 2 stack is available as a release path from the Auxiliary Building.

z12r6.doc 12-11

ZION Revision 11 July 2003 TABLE 12.2-3 RADIOACTIVE PLANT MONITORING INSTRUMENTATION (Cont'd)

TABLE NOTATIONS SURVEILLANCE 6 - With the number of channels OPERABLE less than the minimum number required, effluent releases via this pathway may continue for up to 30 days provided grab samples are obtained and analyzed for gross activity at least once per day.

SURVEILLANCE 7 - With the number of channels OPERABLE less than the minimum number required, and no redundant monitor OPERABLE in this flow path, immediately suspend PURGING of radioactive effluents via this pathway.

SURVEILLANCE 8 - Effluent releases via this pathway may continue provided the effluent flow rate is estimated at least once per day while a release is in progress. Restore the inoperable panel to OPERABLE status within 30 days OR conduct a station review to determine a plan of action to restore the panel to OPERABLE status.

SURVEILLANCE 9 - With the number of channels OPERABLE less than the minimum number required, restore the inoperable monitor to OPERABLE status within 30 days OR conduct a station review to determine a plan of action to restore the channel to OPERABLE status.

SURVEILLANCE 10- With the number of OPERABLE channels less than the minimum number required, restore the channel to OPERABLE status within 30 days or conduct a station review to determine a plan of action to restore the channel to OPERABLE status. Effluent releases via this pathway may continue provided grab samples are obtained and analyzed for gross activity at least once per day, OR for the case when the associated LP-084 panel is inoperable, continuous sampling is maintained with a pump and I Operations performs a Channel Check Daily. Compensatory sampling does not return the monitor to an OPERABLE status.

SURVEILLANCE 11 - With the number of OPERABLE channels less than the minimum number required, restore the channel to OPERABLE status within 30 days or conduct a station review to determine a plan of action to restore the channel to OPERABLE status. Effluent releases via this pathway may continue provided samples are continuously collected as required in Table 12.4-1. For the case when the associated LP-084 panel is inoperable, continuous sampling can be maintained with a pump and Operati6ns shall perform a Channel Check Daily. Compensatory sampling does not return the monitor to an OPERABLE status.

SURVEILLANCE 12- With the number of channels OPERABLE less than the minimum required, stop all movement of fuel within the spent fuel pool and crane operation with loads over the spent fuel pool AND perform area surveys of the monitored area at least once per day.

SURVEILLANCE 13 With the number of channels OPERABLE less than the minimum required, stop operation of overhead crane in bypass after placing loads in safe condition.

SURVEILLANCE 14 Perform area surveys of the monitored area at least once per day.

z12r6.doc 12-12

ZION Revision 11 July 2003 TABLE 12.2-4 RADIOACTIVE PLANT MONITORING INSTRUMENTATION SURVEILLANCE CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL CHECK CHECK CALIBRATION (1) TEST (2) 1 Effluent Containment Purge or Vent A. Particulate Monitor

1. IR-PR40A (Channel 1) D M R Q

2. 2R-PR40A (Channel 1) D M R Q

2. Aux Building Effluent Monitoring A. Gas Activity Monitor

1. IR-PR49E (Channel 5) D M R Q

2. 2R-PR49E (Channel 5) D M R Q B. Particulate Monitor

1. 1R-PR49A (Channel 1) D M R Q

2. 2R-PR49A (Channel 1) D M R Q C. Flow Rate Monitor

1. 1LP-084 D N/A R Q

2. 2LP-084 D N/A R Q

3. Fuel Building Monitoring A. Gas Activity Monitor

1. ORT-PR30A D M A N/A B. Particulate Monitor

1. ORT-PR30B D M A N/A C. Area Monitoring

1. ORT-AR21 D M(4) R Q

2. ORT-AR22 D M R Q

3. ORT-AR13 D M(3) R Q z1 2r6.doc 12-13

ZION Revision 11 July 2003 TABLE 12.2-4 RADIOACTIVE PLANT MONITORING INSTRUMENTATION SURVEILLANCE (Contd)

CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION (1) TEST (2)

4. Emergency Monitoring A. Ventilation

1. 1RIA-PR49 (Channel 7) N/A N/A R Q

2. 2RIA-PR49 (Channel 7) N/A N/A R Q

3. 1RIA-PR49 (Channel 9) N/A N/A R Q

4. 2RIA-PR49 (Channel 9) N/A N/A R Q zl2r6.doc 12-14

ZION Revision 11 July 2003 Table 12.2-4 RADIOACTIVE PLANT MONITORING INSTRUMENTATION SURVEILLANCE (Cont'd)

TABLE NOTATIONS (1) CHANNEL CALIBRATION shall include performance of a CHANNEL FUNCTIONAL TEST.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that any automatic isolation occurs; and that Control Room alarm annunciation occurs if any of the following conditions exist (if the capability is installed):

a) Instrument indicates measured levels above the alarm setpoint.

b) Circuit failure.

c) Instrument indicates a downscale failure.

d) Instrument controls not set in "operate" mode.

(3) Daily during operations of overhead crane in bypass mode with a load suspended from the hook.

(4) Daily during fuel handling operations or load handling operations in or above the spent fuel pool.

zl2r6.doc 12-15

ZION Revision 11 July 2003 12.3 LIQUID EFFLUENTS 12.3.1 Concentration Operability Requirements 12.3.1.A.1 The concentration of radioactive material released from the site to UNRESTRICTED AREAS (see Zion Station ODCM Annex, Appendix F, Figure F-1) shall be limited to 10 times the concentrations specified in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentrations shall be limited to the values listed in Table 12.3-1.

12.3.1.A.2 During the release of radioactive liquid wastes, the combination of dilution water flow and waste water discharge flow shall be established to ensure the discharge concentration limits of 12.3.1.A.1. are not exceeded.

Applicability: At all times.

Action

1. With the concentration of radioactive materials released from the site to UNRESTRICTED AREAS exceeding the limits specified in Section 12.3.1.A.1.

immediately decrease the release rate of radioactive materials and/or increase the dilution flow rate to restore the concentration to within the above limits.

Surveillance Requirements 12.3.1.B.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 12.3-2. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Section 12.3.1.A.1.

12.3.1.B.2 Post-release analyses of samples composited from BATCH RELEASES shall be performed in accordance with Table 12.3-2. The results of the previous post-release analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Section 12.3.1.A.1.

12.3.1.B.3 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 12.3-2.

The results of the analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Section 12.3.1.A.1.

12.3.1.B.4 Appropriate discharge and dilutions flows for each batch radioactive liquid release shall be determined with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Section 12.3.1.A.1.

zl2r6.doc 12-16

ZION Revision 11 July 2003 Bases 12.3.1 .C This Section is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to UNRESTRICTED AREAS will be less than ten (10) times the concentration levels specified in Appendix B, Table 2, Column 2 to 10CFR 20.1001-20.2402.

This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section IL.A design objectives of Appendix I, 10 CFR 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10CFR20.1301.

z12r6.doc 12-17

ZION

Revision 11 July 2003 TABLE 12.3-1 ALLOWABLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID EFFLUENTS NUCLIDE A(yCi/mI)*

Kr-85m 2 X10-4 Kr-85 5 X 1I-4 Kr-87 4 X10'5 Kr-88 9x 10 5 Ar-41 7XI -5 Xe-131m 7 X I0 4 Xe-133m 65X10-4 Xe-1 33 Xe-135m 2 X10-4 Xe-135 2 X10-4

Computed from Equation 20 of ICRP Publication 2(1959), adjusted for infinite cloud submersion in water, and R = 0.01 rem/week, density = 1.0 glcc and Pw/Pt = 1.0.

z12r6.doc 12-18

ZION Revision 11 July 2003 TABLE 12.3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE MINIMUM ANALYSIS LOWER LIMIT OF LIQUID RELEASE SAMPLING FREQUENCY TYPE OF DETECTION (LLD)

TYPE, FREQUENCY ACTIVITY ANALYSIS (pCi/ml) (a,e)

A. Boric Acid Monitor Prior to Each Release Prior to Each Principal Gamma 5E-7 Tank (c) Release Emitters (e)

P M Dissolved and 1E-5 One Batch/M(c) Entrained Gases (Gamma Emitters)

P M Tritium 1E-5 Each Batch (c) Composite (b)

Gross Alpha 1E-7 P Q Sr-89, Sr-90 5E-8 Each Batch (c) Composite (b)

Fe-55 1E-6 B. Turbine Building Continuous During W Principal Gamma 5E-7 Fire Sump (f)Release (d) Emitters(e)

Dissolved and 1E-5 Entrained Gases (Gamma Emitters)

Continuous (d) M Tritium I E-5 Composite (b)

Gross Alpha I E-7 Continuous (d) Q Sr-89, Sr-90 5E-8 Composite (b)

Fe-55 1E-6 C. Waste Neutralizing Prior to each Release Prior to each Release Principal Gamma 5E-7 Tank Emitters (e)

P M Tritium I E-5 Each Batch (c) Composite (b)

. Gross Alpha 1E-7 z1 2r6.doc 12-19

ZION Revision 11 July 2003 TABLE 12.3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE (Cont'd)

TABLE NOTATIONS

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

LLD = 4.66 sh A

E

V

2.22

Y

exp (-XAt)

Where:

LLD is the lower limit of detection as defined above in picocuries (pCi) per unit mass or volume, Sb is the square root of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

A is the number of gamma rays emitted per disintegration for gamma ray radionuclide analysis (A= 1.0) for gross alpha, strontium, and tritium measurement.

E is the counting efficiency (as counts per gamma),

V is the sample size (in units of mass or volume),

2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield when applicable (otherwise Y = 1.0)

Xis the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental sample).

The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples.

Typical values of E, V, Y, and At shall be used in the calculation. The background count rate is calculated from the background counts that are determined to be within + one FWHM (Full Width at Half Maximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radionuclide.

zl2r6.doc 12-20

ZION Revision 11 July 2003 TABLE 12.3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE (Cont'd)

TABLE NOTATIONS For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near their sensitivity limits when other nuclides are present in the sample in much greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentrations of such radionuclides using observed ratios with those radionuclides which are measurable.

b. A COMPOSITE SAMPLE is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

1) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

2) The weekly and monthly Proportional Composite samples are not required provided that (1) the analysis required for each of these composite samples has been run on each batch discharged, and (2) a monthly record of radionuclides discharged (isotope and quantity) is maintained.

c. A BATCH RELEASE is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.

d. A CONTINUOUS RELEASE is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the continuous release.

e. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141. Ce-144 shall also be measured, but with an LLD of 5E-06. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses shall be reported as "less than" the nuclide's LLD, and shall not be reported as being present at the LLD level for that nuclide. The "less than" values shall not be used in the required dose calculations.

f. If the fire sump composite sampler is inoperable, grab samples shall be taken from the turbine building fire sump once per day.

zi 2r6.doc 12-21

ZION Revision 11 July 2003 12.3.2 Dose Operability Requirements 12.3.2.A The dose or dose commitment to a MEMBER OF THE PUBLIC above background from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS (see Zion Station ODCM Annex, Appendix F, Figure F-1) shall be limited:

1. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and

2. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

Applicability: At all times.

Action

1. With the calculated dose from the release of radioactive materials in liquid effluents exceeding twice the limits specified in Section 12.3.2.A, limit the subsequent releases such that the dose or dose commitment to a MEMBER OF THE PUBLIC from all uranium fuel cycle sources is limited to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months. Demonstrate that radiation exposures to all MEMBERS OF THE PUBLIC from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40CFR Part 190 and 40CFR Part 141 Standard, otherwise obtain a variance from the Commission to permit releases which exceed the 40CFR Part 141 or 190 Standard. The radiation exposure analysis shall use methods prescribed in the ODCM.

Surveillance Requirements 12.3.2.B Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodologies and parameters of the ODCM at least once per 31 days.

z12r6.doc 12-22

ZION Revision 11 July 2003 Bases 12.3.2.C This Section is provided to implement the requirements of Sections II.A, IlI.A and IV.A of Appendix I, 10CFR Part 50. The limiting Condition of Operation implements the guides set forth in Section I.A of Appendix I. The ACTION statements provide the required OPERATING flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies, which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are excess of the requirements of 40CFR 141. The dose calculations in the ODCM implement the requirements in Section IlI.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the dose due to the actual release rate of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109; Calculation of Annual Doses to Man from Routine Releases of Radioactive Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guides 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

This Section applies to the release of liquid effluents from each unit at the site. For shared radwaste treatment systems, the liquid effluents from the shared systems are proportioned among the units sharing the system.

z12r6.doc 12-23

ZION Revision 11 July 2003 12.3.3 Liquid Radwaste Treatment System Operability Requirements 12.3.3.A The Liquid Radwaste Treatment System shall be OPERABLE* and appropriate portions of the system shall be used to reduce the radioactive materials in liquid effluents prior to discharge when the projected doses due to liquid effluent, from each unit, to UNRESTRICTED AREAS (see Zion Station ODCM Annex, Appendix F, Figure F-1) would exceed 0.06 mrem to the total body or 0.20 to any organ in a 31-day period.

The liquid Radwaste Treatment System shall be considered OPERABLE, if liquid waste can be held up and/or discharged within applicable limits.

Applicability: At all times.

Action With the Liquid Radwaste Treatment System inoperable for more than 30 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, return the system to OPERABLE status and place the appropriate portions of the system in use.

Surveillance Requirements 12.3.3.B Doses due to liquid releases from the site to UNRESTRICTED AREAS, shall be projected at least once per 31 days in accordance with the methodologies and parameters of the ODCM when the Liquid Radwaste Treatment System is not being fully utilized.

Bases 12.3.3.C The OPERABILITY of the Liquid Radwaste Treatment System ensures that the system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This Section implements the requirements of 10CFR Part 50.36a, General Design Criterion of Appendix A to 10CFR Part 50 and the design objective given in Section I.D of Appendix I to I OCFR Part 50.

The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a 2% fraction of the dose design objectives set forth in Section I.A of Appendix I, 10CFR Part 50, for liquid effluents.

z12r6.doc 12-24

ZION Revision 11 July 2003 12.4 GASEOUS EFFLUENTS 12.4.1 Dose Rate Operating Requirements 12.4.1.A The dose rate due to radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY (see Zion Station ODCM Annex, Appendix F, Figure F-1), shall be limited to the following:

1. For noble gases: Less than or equal to 500 mrem/yr to the whole body and less than or equal to 3000 mremlyr to the skin, and

2. For Iodine-131, lodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mremlyr to any organ.

Applicability: At all times.

Action With a release exceeding the above limits, immediately reduce the release rate to within the above limits.

Surveillance Requirements 12.4.1.B The dose rate due to radioactive materials in gaseous effluents shall be determined to be within the prescribed limits in accordance with the methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 12.4-1.

Bases 12.4.1.C This Section is provided to ensure that radioactive material discharged in gaseous effluents will not result in the exposure of a Member of the Public in an Unrestricted Area, either at or beyond the Site Boundary in excess of the design objectives of appendix I to 10 CFR part 50. This section is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled. It provides operational flexibility for releasing gaseous effluents to satisfy the Section II.A and 11.design objectives of appendix I to 10 CFR part 50. The specified release-rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the SITE BOUNDARY to 500 mrem/year to the total body or to less than or equal to 3000 mrem/year to the skin. These release-rate limits also restrict, at all times, the corresponding organ dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year. For purposes of calculating dose resulting from airborne releases, the stack is considered a ground-level release.

The Sampling and Analysis Program requirements prescribed in Table 12.4-1 are established to provide representative and appropriate sampling of the radiologically controlled areas. The method and frequency of sampling is based on the effluent flowrate. Continuous Releases are defined for areas with forced ventilation release points. Unventilated Building Releases are defined for areas with no specific release point.

z12r6.doc 12-25

ZION Revision 11 July 2003 TABLE 12.4-1 RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM MINIMUM TYPE OF LOWER LIMIT OF GASEOUS RELEASE SAMPLING ANALYSIS ACTIVITY DETECTION (LLD)

TYPE METHOD FREQUENCY ANALYSIS (PCi/cc) (e A. Deleted B. Containment Vent Grab (b) Prior to Each Noble Gases 1E-4 and Purge Release Principal Gamma Emitters (d)

Tritium 1E-6 C. Continuous Grab (b) Monthly Noble Gases 1E-4 Releases(1) Principal Gamma Aux Building Emitters (d)

Ventilation Stack for both (2) units And Tritium I E-6 Continuous (b)(h) Weekly(c) Particulate 1E-11 Fuel Building Principal Gamma Ventilation Emitters (e)

Composite Quarterly Sr-89 Particulate 1E-11 Sr-90 Particulate 1E-11 Gross Alpha 1E-1 I Continuous (g)(h) N.A. Noble Gases, IE-6 Gross Beta or Noble Gas Monitor Gamma (1) The requirements listed in this table for Continuous Releases are applicable for release paths that are available.

z12r6.doc 12-26

ZION Revision 11 July 2003 TABLE 12.4-1 RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM (Contfd)

MINIMUM TYPE OF LOWER LIMIT 01 GASEOUS RELEASE SAMPLING ANALYSIS ACTIVITY DETECTION TYPE METHOD FREQUENCY ANALYSIS (LLD) (pCi/cc) (e)

D. Unventilated Grab Daily Noble Gases 1E-4 Building 2 . Principal Gamma Releases )Emitters (d)

Aux Building Above Ground Elevations(i)

And Tritium I E-6 Continuous (h) Daily(c) Particulate IE-11 Fuel Building 0 Principal Gamma Emitters (e)

Composite Quarterly Sr-89 Particulate IE-11 Sr-90 Particulate IE-11 Gross Alpha 1E-11 (2)

The requirements listed in this table for Unventilated Building Releases are applicable for buildings with the normal ventilation release paths isolated.

z12r6.doc 12-27

ZION Revision 11 July 2003 TABLE 12.4-1 RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM (Cont'd)

TABLE NOTATIONS

a. Deleted

b. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period in Section 12.4.1.

c. The particulate filter(s) shall be saved for a quarterly composite analysis for Sr-89 and Sr-90.

d. For gaseous emissions, the principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-1 33, Xe-1 33m, Xe-1 35, and Xe-1 38.

Other peaks which are measurable and identifiable by gamma-ray spectrometry, together with the above nuclides, shall also be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being at the LLD level for that nuclide.

e. For particulate emissions, the principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Co-60, Zn-65, Co-58, Mo-99, Cs-1 34, Cs-1 37, Ce-141, and Ce-144. Other peaks which are measurable and identifiable by gamma-ray spectrometry, together with the above nuclides, shall also be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being at the LLD level for that nuclide.

f. The LLD is defined in Notation a of Table 12.3-2.

9. Refer to Table 12.2-3 for required actions when the noble gas monitor is not in service.

h. Sampling interruptions of short duration for routine activities, e.g. filter replacement, do not constitute a deviation from the requirements for continuous sampling.

i. The effluent flowrate for Unventilated Building Releases from the Aux Bldg shall be estimated by FAB (cfm) = 72900 V (in of water). When the Aux Bldg pressure can not be determined, the maximum flowrate of one exhaust fan, 67000 cfm, shall be used as the effluent flowrate.

The effluent flowrate for Unventilated Building Releases from the Fuel Bldg shall be estimated by FFB (cfm) = 24300 d (in of water). When the Fuel Bldg pressure can not be determined, the maximum flowrate of the exhaust fan, 15000 cfm, shall be used as the effluent flowrate.

z12r6.doc 12-28

ZION Revision 11 July 2003 12.4.2 Dose - Noble Gases Operability Requirements 12.4.2.A The air dose due to noble gases released in gaseous effluents from each unit to areas at or beyond the SITE BOUNDARY (see Zion Station ODCM Annex,. Appendix F, Figure F-1) shall be limited to the following:

1. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and

2. During any calendar year. Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

Applicabilitv: At all times Action

1. With the calculated air dose from gaseous effluents exceeding the above limits, define the corrective action(s) to be taken to ensure that future releases are in compliance with Section 12.4.2.A.

2. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding twice the limits of Section 12.4.2.A:

a. Limit subsequent releases such that the dose or dose commitment to a MEMBER OF THE PUBLIC from all uranium fuel cycle sources is limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months.

b. Prepare an analysis which demonstrates that radiation exposures to all MEMBERS OF THE PUBLIC from all uranium fuel cycle sources (including all effluents pathways and direct radiation) are less than the 40 CFR Part 190 Standard.

Surveillance Requirements 12.4.2.B Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodologies and parameters of the ODCM at least once every 31 days.

z1 2r6.doc 12-29

ZION Revision 11 July 2003 Bases 12.4.2.C This Section implements the requirements of Sections II.B, III.A and IV.A of Appendix 1, IOCFR Part 50. The Operability Requirements implement the guides set forth in Section 11.1 of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculation procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated.

z12r6.doc 12-30

ZION Revision 11 July 2003 12.4.3 Dose 131, 1-133, Tritium, and Radioactive Material in Particulate Form Operabilitv Requirements 12.4.3.A The dose to a MEMBER OF THE PUBLIC from 1-131,1-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas at or beyond the SITE BOUNDARY (see Zion Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the following:

1. During any calendar quarter Less than or equal to 7.5 mrem to any organ, and

2. During any calendar year Less than or equal to 15 mrem to any organ.

Applicabilitv: At all times.

Action With the calculated dose from the release of lodine-131, Iodine-1 33, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents exceeding twice the limits of Section 12.4.3.A:

I. Limit subsequent releases such that the dose or dose commitment to a MEMBER OF THE PUBLIC from all uranium fuel cycle sources to less than or equal to 25 mrem to the total body or organ (except the thyroid which is limited to less than or equal to 75 mrem) over 12 consecutive months.

2. Prepare an analysis which demonstrates that radiation exposures to all MEMBERS OF THE PUBLIC from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40CFR Part 190 Standard. Otherwise, request a variance from the Commission to permit release which exceeds the 40CFR Part 190 Standard. The radiation exposure analysis shall use the methods prescribed in the ODCM.

Surveillance Requirements 12.4.3.B Cumulative dose contribution for the current calendar quarter and current calendar year for 1-131, 1-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodologies and parameters in the ODCM at least once per 31 days.

z12r6.doc 12-31

ZION Revision 11 July 2003 Bases 12.4.3.C This Section implements the requirements of Sections II.C, IlI.A and IV.A of Appendix I, 10CFR Part 50. The Operability Requirements are the guides set forth in Section I.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time, implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculation methods specified in the Surveillance Requirements implement the requirements in Section IlI.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The release-rate specifications for radioiodines, radioactive material in particulate form and radioiodines other than noble gases are dependent on the existing radionuclide pathways to man, at or beyond the SITE BOUNDARY. The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides, 2) disposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man.

zl2r6.doc 12-32

ZION Revision 11 July 2003 12.4.4 Gaseous Effluent Treatment System Operability Requirements 12.4.4.A The GASEOUS EFFLUENT TREATMENT SYSTEM shall be OPERABLE* and appropriate portions of these systems shall be used to reduce radioactive materials in gaseous effluents when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at or beyond the SITE BOUNDARY (see Zion Station ODCM Annex, Appendix F, Figure F-1) would exceed:

1. 0.2 mrad to air from gamma radiation, or

2. 0.4 mrad to air from beta radiation, or

3. 0.3 mrem to any organ.

The installed GASEOUS EFFLUENT TREATMENT SYSTEM shall be considered OPERABLE by meeting Sections 12.4.1, 12.4.2 and/or 12.4.3, as applicable.

Applicability: At all times.

Action: With the Gaseous Effluent Treatment System inoperable for more than 30 days or with radioactive gaseous waste being discharged without treatment and in excess of the above limits, return the system to OPERABLE status and place the appropriate portions of the system in use.

Surveillance Requirements 12.4.4.B Doses due to gaseous releases from each unit to areas at or beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodologies and parameters in the ODCM when the Gaseous Effluent Treatment Systems are not being fully utilized.

Bases 12.4.4.C The OPERABILITY of the GASEOUS EFFLUENT TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment.

The requirement that the appropriate portions of this system be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This section implements the requirement of 10CFR50.36a, General Design Criterion 60 of Appendix A to IOCFR50 and the design objective given in Section 11.0 of Appendix I to 10CFR50. The specified limits governing the use of appropriate portions of the Gaseous Effluent Treatment System were specified as a 2% fraction of the dose design objectives set forth in Section Il.B and I1.C of Appendix I, 10CFR50, for gaseous effluents.

zl2rS.doc 12-33

ZION Revision 11 July 2003 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Monitoring Program ODerability Requirements 12.5.1.A The Radiological Environmental Monitoring Program shall be conducted as specified in Table 12.5-1.

Applicability: At all times.

Action

1. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 12.5-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting a program as required and the plans for preventing a recurrence.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of sampling equipment, if a person who participates in the program goes out of business or no longer can provide sample, or contractor omission which is corrected as soon as discovered. If the equipment malfunctions, corrective actions shall be completed as soon as practical. If a person/business supplying samples goes out of business, a replacement supplier shall be found as soon as possible. All deviations from the sampling schedule shall be described in the Annual Radiological Environmental Operating Report.

2. With the level of radioactivity as a result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 12.5-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBLIC is less than the calendar year limits of Section 12.3.2, 12.4.2, or 12.4.3.

When more than one of the radionuclides in Table 12.5.2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) + concentration (2) + ... > 1.0 reporting level (1) reporting level (2)

When radionuclides other than those in Table ,12.5-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Section 12.3.2, 12.4.2, or 12.4.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such a event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

The methodology and parameters used to estimate the potential dose to a MEMBER OF THE PUBLIC shall be indicated in the report.

zl2r6.doc 12-34

ZION Revision 11 July 2003

3. If the sample type or sampling location(s) required by Table 12.5-1 become(s) permanently unavailable, identify suitable alternative sampling media for the pathway of interest and/or specific locations for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program as soon as practicable. The specific locations from which samples were unavailable may then be deleted from the program.

Prepare and submit a controlled version of the ODCM within 180 days including a revised figure(s) and table reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of new location(s) for obtaining samples.

Surveillance Requirements 12.5.1.B.1 The Radiological Environmental Monitoring samples shall be collected from the locations specified in the ODCM and analyzed pursuant to Table 12.5-1 and the detection capabilities required by Table 12.5-3.

Bases 12.5.1.C The Radiological Environmental Monitoring Program required by this section provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10CFR50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The specified monitoring program is based on baseline/historical conditions for direct radiation measurements, soil, biota, and sediments established over years of operational experience and current site conditions/operating activities. The REMP need only be re-evaluated for major changes to site conditions/configuration (e.g., prior to site decommissioning, if a significant release occurs, changing baseline data...). Program changes may be initiated at any time based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLD). The LLDs required by Table 12.5-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, LA., "Limits for Qualitative Detection and Quantitative Determination-Application to Radiochemistry," Anal. Chem.

40, 586-93 (1968), and Gartwell, J.K., *Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

Z12r6.doc 12-35

ZION Revision 11 July 2003 lnterpretations 12.5.1.D Table 12.5-1 requires 'one sample of each community drinking water supply downstream of the plant within 10 kilometers (6.2 miles)." Drinking water supply is defined as water taken from river, lakes, or reservoirs (not well water) which is used for drinking. Since Lake Michigan has no designated downstream or upstream direction, two drinking water locations (one northlone south) within 10 kilometers shall be sampled as drinking water indicator locations, and two other locations (one northlone south) beyond 10 kilometers shall be sampled as control locations.

z1VrM.doc 12-36

ZION Revision 11 July 2003 TABLE 12.5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND FREQUENCY OF AND/ OR SAMPLE AND SAMPLE LOCATIONS(') FREQUENCY ANALYSIS

1. Airborne Samples from a total of three locations: Particulate Samoler a.Idcao-NarFedContinuous sampler operatibn Gross beta analysis following

a. Indicator- Near Field ith particulate sample collection weekly filter change(3)and gamma weekly (or more frequently if isotopic analysis (4 quarterly on Three samples from locations within 4 km required due to dust loading), composite filters by location on (2.5 mi) in different sectors. near field samples.

z12r6.doc 12-37

ZION Revision 11 July 2003 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND FREQUENCY OF AND/ OR SAMPLE AND SAMPLE LOCATIONS(') FREQUENCY ANALYSIS

2. Direct Radiation 5) Seventeen routine monitoring stations with thermoluminescent dosimeters (TLD), placed with at least one monitoring location in each meteorological sector, as follows:

a. Indicator-Inner Ring (100 Series TLD) in the general area of the SITE BOUNDARY (0.1 to 1.5 mi); Quarterly Gamma dose on each TLD quarterly.

b. Other One at each Airborne location given in part l.a.

Other TLDs may be placed at special Interest locations beyond the Restricted Area where either a MEMBER OF THE PUBLIC or Commonwealth Edison employees have routine access.

(300 Series TLD) z12r6.doc 12-38

ZION Revision 11 July 2003 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND FREQUENCY OF AND/ OR SAMPLE AND SAMPLE LOCATIONS(1 ) FREQUENCY ANALYSIS

3. Waterbome

a. Drinking Water lndicator~e)

One Sample from each community Gross beta and gamma isotopic drinking water supply that could be analyses(4) on monthly composite; affected by the station discharge within 10 Weekly grab samples. tritium analysis on quarterly km (6.2 mi) of discharge (north/south). composite.

b. Control(6 )

Gross beta and gamma isotopic One sample upstream and downstream Weekly grab samples. analyses(4) on monthly composite; (north/south) of discharge. tritium analysis on quarterly composite.

c. Sediments At least one sample within 10 km (6.2 mi) Semiannually. Gamma isotopic analysis (4) of discharge semiannually.

z1 2r6.doc 12-39

ZION Revision 11 July 2003 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND FREQUENCY OF AND/ OR SAMPLE AND SAMPLE LOCATIONS('" FREQUENCY ANALYSIS

4. Ingestion

a. Fish Indicator Representative samples of commercially and recreationally important species in discharge Semiannually Gamma isotopic analysis~4 ' on edible area. portions.

b. Control Representative samples of commercially and Semiannually Gamma isotopic analysis(4) on edible recreationally important species not influenced portions.

by plant discharge.

zi 2r6.doc 12-40

ZION Revision 11 July 2003 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS (1) Specific parameters of distance and direction from the centerline of the midpoint of the two units and additional description where pertinent, shall be provided for each and every sample location in Table 11-1 of the ODCM Station Annexes. Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979.

(2) Deleted - No longer applicable.

(3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thorium daughter decay. If gross beta activity in any individual air particulate sample is greater than 10 times the 1999 mean of control samples, then, a gamma isotopic analysis shall be performed on that elevated individual sample.

(4) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station.

(5) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The number of locations is not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., If a station is adjacent to a lake (i.e. Zion), some sectors may be over water thereby reducing the number of dosimeters which could be placed at the indicated distances. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose Information with minimal fading.

(6) Refer to Section 12.5.1.D for interpretation on the applicability of "downstream" and "upstream". If no community drinking water supply exists within 6.2 miles of the discharge, surface water sampling shall be performed.

(7) Deleted - No longer applicable.

(8) Deleted - No longer applicable.

(9) DELETED (10) Deleted - No longer applicable.

z1 2r6.doc 12-41

ZION Revision 11 July 2003 TABLE 12.5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES*

WATER AIRBORNE PARTICULATE FISH ANALYSIS (pCin) OR GASES (pCI/m 3 ) (pCi/kg, wet)

H-3 20,000 (t)

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 Cs-1 34 30 10 1,000 Cs-1 37 50 20 2,000 Ba-La-140 200 (1) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/I may be used.

This table contains reporting levels for analyses beyond the requirements of Table 12.5-1.

z12r6.doc 12-42

ZION Revision 11 July 2003 TABLE 12.5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS" 1 )

LOWER LIMIT OF DETECTION (LLD)(2)(3)

AIRBORNE WATER PARTICULATE FISH SEDIMENT ANALYSIS (pCi/) OR GASES (pCi/m 3 ) (pCiUkg, wet) (pCi/kg, dry)

Gross Beta 4 0.01 1000 H-3 2,000m Mn-54 15 130 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 Cs-134 15 0.01 100 150 Cs-137 18 0.01 100 180 z1 2r6.doc 1243

ZION Revision 11 July 2003 TABLE 12.5-3 (Continued)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS (1) This table contains lower limits of detection for analyses beyond the requirements of Table 12.5-1. This table does not imply that only these nuclides are to be detected and reported; other peaks which are measurable and identifiable in the analyses required by Table 12.5-1 shall be reported in the Annual Radiological Environmental Operating Report.

(2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.

(3) The Lower Limit of Detection (LLD) is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5%

probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation, the LLD is defined as follows:

4.66 Sb + 3 /tb LLD = ----------------------

(E) (V) (2.22) (Y) (exp (-XAt))

4.66 Sb LLD - ----------------------

(E) (V) (2.22) (Y) (exp (-XAt))

Where: 4.66 Sb >> 3/tb LLD = the "a priori" Lower Limit of Detection (picocuries per unit mass or volume),

Sb = the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate (counts per minute),

- Total Counts tb E = the counting efficiency(counts per disintegration),

V = the sample size (units of mass or volume),

2.22 = the number of disintegrations per minute per picocurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (sec&),

tb = counting time of the background or blank (minutes), and z12r5.doc 12-44

ZION Revision 11 July 2003 TABLE 12.5-3 (Continued)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS At = the elapsed time between sample collection, or end of the sample collection period, and the time of counting (sec).

Typical values of E, V, Y, and At should be used in the calculation.

It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally, background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

(4) Deleted - No longer applicable.

(5) Deleted - No longer applicable.

(6) Deleted - No longer applicable.

(7) This is the minimum required LLD, however, environmental samples analyzed off-site will be required to use 200 pCi/I.

z12r6.doc 12-45

ZION Revision 11 July 2003 12.5.2 LAND USE CENSUS Operabilitv Requirements 12.5.2.A A Land Use Census shall be conducted and shall identify within a distance of 10 km (6.2 mi) the location, in each of the following meteorological sectors, A, J, K, L, M, N, P, Q, and R**, the nearest residence. For dose calculation, a garden will be assumed at the nearest residence.

Applicability: At all times.

Action:

With a Land Use Census identifying location(s) that yields a calculated dose or dose commitment, via the same exposure pathway 20% greater than at a location from which samples are currently being obtained in accordance with Section 12.5.1, add the new location(s) within 30 days to the Radiological Environmental Monitoring Program given in Chapter 11 of the ODCM Station Annexes. The sampling location(s), excluding the control location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Submit in the next Annual Radiological Environmental Operating Report documentation for a change in the ODCM including revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.

- The nearest industrial facility shall also be documented if closer than the nearest residence.

Surveillance Requirements 12.5.2.B The Land Use Census shall be conducted, between June 1 and October 1, at least once per calendar year using that information that will provide the best results, such as by a door-to-door survey or aerial survey. The result of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report.

Bases 12.5.2.C This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of this census.

This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.

An annual garden census will not be required since the licensee will assume that there is a garden at the nearest residence in each sector for dose calculations.

z12r6.doc 12-46

ZION Revision 11 July 2003 12.5.3 INTERLABORATORY COMPARISON PROGRAM Operability Requirements 12.5.3.A Analyses shall be performed on radioactive materials supplied as part of an interlaboratory comparison program that correspond to samples required by Table 12.5.1.

Applicability: At all times.

Action:

1. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

Surveillance Requirements 12.5.3.B A summary of the results obtained as part of the above required interlaboratory comparison program shall be included in the Annual Radiological Environmental Operating Report.

Bases 12.5.3.C The requirement for participation in an interlaboratory comparison program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

z12r6.doc 12-47

ZION Revision 11 July 2003 12.6 PROCESS CONTROL PROGRAM (PCP) 12.6.1 PCP Program Requirements Contains the requirements and methodology for the current formulas, sampling, analyses, tests, and determinations performed to ensure the processing and packaging of solid radioactive wastes based on actual or simulated wet solid wastes is accomplished in compliance with:

10CFR Parts 20, 61, and 71

State Regulations

Burial Site Requirements

Other Requirements Governing the Shipping and Burial of Radioactive Waste 12.6.2 Changes to the PCP Changes to the PCP include those changes that affect the process or methodology, by which wastes are solidified, packaged to meet burial site form requirements, classified, or dewatered.

12.6.2.1. Shall be documented and records of reviews performed shall be retained, and Shall contain sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s), and Shall contain a determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations, and Shall become effective after review and acceptance by the Onsite Review and Investigative Function and the approval of the Decommissioning Plant Manager.

zl2r6.doc 12-48

ZION Revision 11 July 2003 12.7 REPORTING REQUIREMENTS 12.7.1 Annual Radiological Environmental Operating Report*

Routine Annual Radiological Environmental Operating Report covering the operation of the Unit(s) during the previous calendar year shall be submitted according to the Permanently Defueled Technical Specifications. The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including, as found appropriate, a comparison of preoperational studies with operational controls or with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

The Annual Radiological Environmental Operating Report shall include the results of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures in the Chapter 11 of the ODCM Station Annexes, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; legible maps covering all sampling locations keyed to a table giving distances and directions from the midpoint between the two units; reasons for not conducting the Radiological Environmental Monitoring Program as required by Section 12.5.1, and discussion for all deviations from the sampling schedule of Table 11.1-1; a Table of Missed Samples and a Table of Sample Anomalies for all deviations from the sampling schedule of Table 11.1-1; discussion of environmental sample measurements that exceed the reporting levels of Table 12.5-2 but are not the result of plant effluents; discussion of all analyses in wvhich the LLD required by Table 12.5-3 was not achievable; results of the Land Use Census required by Section 12.5.2; and the results of licensee participation in an interlaboratory comparison program and the corrective actions being taken if the specified program is not being performed as required by Section 12.5.3.

The Annual Radiological Environmental Operating Report shall also include an annual summary of hourly meteorological data collected over the applicable year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Annual Radiological Environmental Operating Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

A single submittal may be made for a multiple unit station.

z12r6.doc 12-49

ZION Revision 11 July 2003 The Annual Radiological Environmental Operating Report shall also include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the Unit or Station during the previous calendar year. This report shall also include an assessment of radiation doses to the most likely exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM and in compliance with 10 CFR 20 and 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation."

12.7.2 Annual Radioactive Effluent Release Report**

The Annual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Material in Liquid and Gaseous Effluent from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The Annual Radioactive Effluent Release Report shall include a list and description of unplanned releases of radioactive material in liquid effluents from the site to UNRESTRICTED AREAS and of unplanned releases of radioactive material in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY during the reporting period.

The Annual Radioactive Effluent Release Report shall include any changes made during the reporting period to the Process Control Program as well as any major changes to Liquid, Gaseous or Solid Radwaste Treatment Systems, pursuant to Section 12.7.4.

The Annual Radioactive Effluent Release Report shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Section 12.2.1 or 12.2.2, respectively; and description of the events leading to liquid holdup tanks exceeding the limits of to the Permanently Defueled Technical Specifications.

12.7.2.1 Exceptions to Regulatory Guide 1.21 Reporting Requirements:

a. All references to 'semiannual' are not applicable. The report will be submitted according to Technical Specifications.

b. Hourly meteorological data is recorded for all periods throughout the year, and quarterly summaries will be reported. Separate meteorological data for periods of batch releases are not required to be included.

c. Total body and significant organ doses to the maximally exposed individual from receiving-water-related exposure pathways will be provided. Associated population dose is not required to be included.

z12r6.doc 12-50

ZION Revision 11 July 2003

d. Organ doses to the maximally exposed individual in unrestricted areas from radioactive iodine and radioactive material in particulate form from all exposure pathways will be provided. Associated population dose is not required to be included.

e. Total body doses to the maximally exposed individual in unrestricted areas from direct radiation from the facility should be included in the report. Associated population dose is not required to be included.

f. Total body doses to the population and average doses to individuals in the population from all receiving-water-related pathways are not required to be included.

g. Total body doses to the population and average doses to individuals in the population from gaseous effluents to a distance of 50 miles from the site and beyond will not be included.

- A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

z12r6.doc 12-51

ZION Revision 11 July 2003 12.7.3 Offsite Dose Calculation Manual (ODCM) 12.7.3.1 Changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as required by Permanently Defueled Technical Specifications. This documentation shall contain:

1. Sufficient Information to support the change together with the appropriate analyses or evaluations justifying the change(s); and

2. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

3. Documentation of the fact that the change has been reviewed and found acceptable by a Qualified Technical Review.

b. Shall become effective after the approval of the Plant Manager on the date specified by the Qualified Technical Review.

c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g.,

month/year) the change was implemented.

z12r6.doc 12-52

ZION Revision 11 July 2003 12.7.4 Major Changes to Liquid and Gaseous Effluent Treatment Systems' Licensee-initiated major changes to the Effluent Treatment Systems (liquid and gaseous):

a. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by a Qualified Technical Review. The discussion of each change shall contain:

1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;

2) Sufficient detailed information to totally support the reason for the change without benefit of additional and supplemental information;

3) A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems.

4) An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the License application and amendments thereto;

5) An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC and to the general population that differ from those previously estimated in the License application and amendments thereto;

6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, to the actual releases for the period prior to when the changes are to be made;

7) An estimate of the exposure to plant operating personnel as a result of the change; and

8) Documentation of the fact that the change was reviewed and found acceptable by a Qualified Technical Review.

b. Shall become effective upon review and acceptance by the Qualified Technical Review.

Licensees may choose to submit the information called for in this standard as part of the biennial DSAR update.

zi 2r6.doc 12-53

November 20,2003 Qualified Technical Review = TR/010/2003

Additional signature letter to comply with Technical Review 5.9.1 .a.

To: Mr. Artice Daniels Jr.

Subject; Qualified Technical Review of Chapter 12 Revision 12 to the Offisitc Dose Calculation Manual (ODCM).

Pursuant to the ODCM Section 12.7.3 and Technical Specifications 5.6.1 and 5.9.1, the following basis for revisions to the ODCM and the documentation of the Qualified Technical review is attached.

Section 12.7.3 of the ODCM requires a Qualified Technical Review be performed. This review will be performed by at least two qualified individuals with the appropriate ANSI disciplines and approved by the Decommissioned Plant Manager.

Engineering Assigned Disciplines for this Qualified Technical Review are:_AL4.E Disciplines are assigned by - Date I/-2Co ?

Qualified Technical Revi wers nt ur da tXl I'll24 Dic, 6i Signatur and Date/ Dis'cipline's S igntur'a wt eXDa te7 I\ - Cz,- 05 Signlatur ' nd Date i Disciplines Sigtature and Date Disciplines I1I /c1 /C; 3 I Concur and Approve Dae Artice Daniels Jr.

Decommissioning Plant Manager Zion Station

October 3, 2003 Qualified Technical Review = TR/010/2003 To: Mr. Artice Daniels Jr.

Subject; Qualified Technical Review of Chapter 12 Revision 12 to the Offsite Dose Calculation Manual (ODCM).

Pursuant to the ODCM Section 12.7.3 and Technical Specifications 5.6.1 and 5.9.1, the following basis for revisions to the ODCM and the documentation of the Qualified Technical review is attached.

Section 12.7.3 of the ODCM requires a Qualified Technical Review be performed. This review will be performed by at least two qualified individuals with the appropriate ANSI disciplines and approved by the Decommissioned Plant Manager.

Engineering Assigned Disciplines for this Qualified Technical Review are:

Disciplines are assigned by 'el',10 Date /0-12-03 Qualified Technical Reviewers Discpln s Signature and Date Disciplines Sign ure andate Dis'ciptlineis Signature and Date Disciplines t6 I ZZ1 I on~cur dg e Date Artice Daniels Jr.

Decommissioning Plant Manager Zion Station

ATTACHMENT C: 50.59 REVIEW COVERSHEET FORM S.. on: Zion Station_

Activitv/(Document Number: ODCM Chapter 12 Revision Number: 12

Title:

Offsite Dose Calculation Manual_

NOTE: For 50.59 Evaluations, information on this form will provide the basis for preparing the biennial summary report submitted to the NRC in accordance with the requirements of 10 CFR 50.59(d)(2).

Description of Activity:

(Provide a brief, concise description of what the proposed activity involves.)

This Document set forth the requirements for sampling, collecting, analyzing, and calculating the radiological effluent pathways in the determination of dose to the public. Specific to this revision is the removal of the requirement to perform a Quarterly Functional Test on an area radiation monitor that does not have an associated action other than the purpose it was designed.

Reason for Activity:

(Discuss why the proposed activity is being performed.)

Table 12.24 section 3 required a functional test of the area rad monitor be performed on a quarterly basis. The area rad monitors installed do not have the capability to 1. Inject a simulated input or 2. Operate actuation devices. The area monitors provide area dose rates in the vicinity of the Spent Fuel Pool. Modification installed by the station does not provide any function, (i.e. switching Fuel Building ventilation to charcoal mode, starting a pump, or shutting off a damper) no functional test is required..

The station needed to provide a method of transferring data (dose rates in the Fuel Building) to a remote location via a computer network system. This data was requested by the Illinois Emergency Management Agency.

Ex..it of Activity:

(Discuss how the activity impacts plant operations, design bases, or safety analyses described in the UFSAR.)

No effect on plant activities. This modification was used to replace old rad monitors with newer models that provide digital data that is to be transmitted to the Illinois Emergency Management Agency via a computer network system.

Summary of Conclusion for the Activity's 50.59 Review:

(Provide justification for the conclusion, including sufficient detail to recognize and understand the essential arguments leading to the conclusion. Provide more than a simple statement that a 50.59 Screening, 50.59 Evaluation, or a License Amendment Request, as applicable, is not required.)

These area radiation monitors provide local readout and there is no action associated with this rad monitor. The area rad monitors were changed out to provide digital readout. The new rad monitors do not have the capability to 1. Inject a simulated input or 2. Operate actuation devices, therefore no functional test is required.

Attachments:

Attach all 50.59 Review forms completed, as appropriate.

(NOTE: if both a Screening and Evaluation are completed, no Screening No. is required.)

Forms Attached: (Check all that apply.)

8 Applicability Review 50.59 Screening 50.59 Screening No. Rev.

50.59 Evaluation 50.59 Evaluation No. Rev.

ZAP-1 00-06 Revision 18 Information Use ATTACHMENT D: 50.59 APPLICABILITY REVIEW FORM Activity/Document Number: 6 6 9 4...l /R ° /2 Revision Number:__

Address thc questions below for all aspects of the Activity. If the answer is yes for any portion of the Activity. apply the identified process(es) to that portion of the Activity. Note that it is not unusual to have more than one process apply to a given Activity.

See Section 4 of the Resource Manual (RM) for additional guidance.

.. JTDoes thcp mPQrosed Activity involve a chan e:

I. Tcchnical Specifications or Operating License (IOCFR50.90)? . _ YES !see Section 4.2.1.1 of the RM

2. Conditions of License Quality Assurance program (IOCFR50.54(a))? NO _ YES Se. nirity Plan (I OCFR11.I t(p)-

_

- IS See Section 4 2 of i 1 Emergency Plan (IOCI:R50.54(q))? NO - YES _

3. Codes and Standards I IST Program Plan (JOCFR50.55a(f))? CNO YES Y See Section 4.'.1.3 ofte kM ISI Pro-ram Plan (IOCFR50.55a(g))? Ago - YES

. _ ._ , __ _____ ___ __________ __*N _,S Se Seto 4... of the_ _

4. ECCS Acceptance Criteria (I OCFR50.46)? _* RM

____ _ _ _ _ __ ___ _~I Spcfn(IOCFR5.12)? IN _ YES fSee Section 4.2.1.5 of the RM l6. Radiation Protection Program (IOCFR2O)? *NO _ YES See Section 4.2.1.6 ofthe RM

17. Fire Protection Program (applicable UFSAR or operating license >CNO YES See Section 4.2.1.7 of the RM I condition)? _

18. Programs controlled by the Operating License or the Technical NO 3ES See Section 4.2.1.7 of the RM peclfications (such as the ODCM). __

19. Environmental Protection Program AsO _ YES iSee Section 4.2.1.7 of the RM

10. Other programs controlled by other regulations. YES IINO See Section 4 2.1 of the RM

__O E IS---cton4 I.IDoes the proposed Activity involve maintenance vhich restores SSCs to their original condition or involve a temporary alteration supportingX O maintenance that will be in effect during at-power operations for 90 days or -_ O YES See Section 4.2.2 of the RM

, lsess?___ I_ _ __

_ liI.IPQe the proposed _ Activ;tv involve a change to the: _ ______-

1. UFSAPI Liri-lding docurients incorporated by reference) that is excluded from the requirement to perform a 50.59 Review by NEI 96-07 f qO _ YES ISee Section 4.2.3 of the RM or NE! 98-03? I . _ _ --

l2. Managerial or administrative procedures governing the conduct of XNO YES See Section 4.2.4 of the RM

_jifaciityvperations I

3. Procedures for performing maintenance activities (subject to 10 CFR LCNO YES ISee Section 4.2.4 of the RM

!4. Regulatory commitment not covered by another regulation based change !NO NO

_YES YES 1 See Section 4.2.3/4.2.4 of the RN11 ce Section__2_3_4_2_4_oftheR 1-- rccs(-eqlTE!9---49---- ----- -.- - - -------.- -_ .I__.

_= . . . . .-.- _ .

IVJDoes the proposed Activity involve a change to the Independent Spent Fuel '\NO YES 'See Section 4.2.6 ofthe Ri

.SgoragejInstallation (ISFSI) (subject to control byj OCFR 72.48) -__ _ <_- _

Check one of the followin-:

If all aspects of the Activity are controlled by one or more of the above processes, then a 50.59 Screening is not required and the Activity mav be implemented in accordance with its governing procedure.

If an' nortion of the Activity is not controlled by one or more of the above processes. then process a 50.59 Screening for the portion not covered by any of the above processes. The remaining portion of the activity should be implemented in accordance with its coverning procedure.

Signoff: D C//

50.5) Screencr!50.59).valuator: - H Sign: __ __ _ _I)ate:/° 3 (Circle One) (Print flame) (Si-naturej 21 of 24

Summary of the Changes made to Zion Station Offsite Dose Calculation Manual ODCM Removed Channel functional test for area radiation monitors ORT-AR21 and ORT-AR22 from Table 12.2-4 "Radioactive Plant Monitoring Instrumentation Surveillance".

Page 12-14 Revision 11

3. Fuel Building Monitoring C. Area Monitoring

1. ORT-AR21 Quarterly Functional Test

2. ORT-AR22 Quarterly Functional Test Revision 12

3. Fuel Building Monitoring C. Area Monitoring

1. ORT-AR21 N/A

2. ORT-AR22 N/A

ZION Revision 12 October 2003 SPECIAL NOTE The requirements of Permanently Defueled Technical Specifications shall take precedence over this chapter, should any differences occur.

z12r6.doc 12-i

ZION Revision 12 October 2003 CHAPTER 12 REVISION 12 l z12r6.doc 12-ii

ZION Revision 12 October 2003 CHAPTER 12 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS (RETS)

TABLE OF CONTENTS PAGE 12.1 DEFINITIONS 12-1 12.2 INSTRUMENTATION

1. Radioactive Liquid Plant Monitoring Instrumentation 12-5

2. Radioactive Plant Monitoring Instrumentation 12-9 12.3 LIQUID EFFLUENTS

1. Concentration 12-17

2. Dose 12-23

3. Liquid Radwaste Treatment System 12-25 12.4 GASEOUS EFFLUENTS

1. Dose Rate 12-26

2. Dose - Noble Gases 12-30

3. Dose 131,1-133, Tritium, and Radioactive Material in Particulate Form 12-32

4. Gaseous Effluent Treatment System 12-34 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

1. Monitoring Program 12-35

2. Land Use Census 12-47

3. Interlaboratory Comparison Program 12-48 12.6 PROCESS CONTROL PROGRAM (PCP)

1. PCP Program Requirement 12-49

2. Changes to the PCP 12-49 12.7 REPORTING REQUIREMENTS

1. Annual Radiological Environmental Operating Report 12-50

2. Annual Radioactive Effluent Release Report 12-51

3. Offsite Dose Calculation Manual (ODCM) 12-53

4. Major Changes to Liquid and Gaseous Effluent Treatment Systems 12-54 z12r6.doc 12-Iiii

ZION Revision 12 October 2003 CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)

LIST OF TABLES PAGE 12.1-1 Surveillance Frequency Notations 12-4 12.2-1 Radioactive Liquid Plant Monitoring Instrumentation 12-6 12.2-2 Radioactive Liquid Plant Monitoring Instrumentation Surveillance 12-8 12.2-3 Radioactive Plant Monitoring Instrumentation 12-10 12.2-4 Radioactive Plant Monitoring Instrumentation Surveillance 12-14 12.3-1 Allowable Concentration of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Effluents 12-19 12.3-2 Radioactive Liquid Effluent Sampling and Analysis Surveillance 12-20 12.4-1 Radioactive Gaseous Effluent Sampling and Analysis Program 12-27 12.5-1 Radiological Environmental Monitoring Program 12-38 12.5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 1243 12.5-3 Detection Capabilities for Environmental Sample Analysis 1244 z12r6.doc 12-iv

ZION Revision 12 October 2003 12.1 DEFINITIONS 12.1.1 A BATCH RELEASE is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated and then thoroughly mixed to assure representative sampling.

12.1.2 A CHANNEL CALIBRATION, shall be the adjustment, as necessary, of the channel such that it responds with the necessary range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors (where possible),

alarm interlock and/or trip functions and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

12.1.3 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent INSTRUMENT CHANNELS measuring the same parameter.

12.1.4 A CHANNEL FUNCTIONAL CHECK shall be:

a. Instruments-The injection of a simulated signal(s) into the channel as close to the primary sensor(s) as practicable to verify OPERABILITY, including all channel outputs, as appropriate.

b. Logics-The application of input signals, or the operation of relays or switch contacts, in all the combinations required to produce the required decision outputs including the operation of all ACTUATION DEVICES. Where practicable, the test shall include the operation of the ACTUATED EQUIPMENT as well (i.e. pumps will be started, valves operated, etc.).

12.1.5 A COMPOSITE SAMPLE is one in which the quantity of liquid sample is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

12.1.6 A CONTINUOUS RELEASE is the discharge of liquid or gaseous wastes of a nondiscrete volume (e.g. from a volume or system that has an input flow during the release).

12.1.7 CONTINUOUS SAMPLING is uninterrupted sampling with the exception of sampling interruptions of short duration for routine activities (e.g. filter replacements).

12.1.8 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcurie/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132,1-133, 1-134, and 1-135 actually present. The Thyroid Dose Conversion factors used for this calculation shall be those listed in Table IlIl of TID-14844, "Calculation of Distance Factors for Power and Test Reactor Sites" or Table E-7 of NRC Regulatory Guide 1.109 Rev. 1, dated October, 1977. This definition is not used in the defueled condition. Decay has eliminated all concerns related to radioactive iodine.

12.1.9 MEMBER OF THE PUBLIC means any individual except when that individual is receiving an occupational dose.

z12r6.doc 12-1

ZION Revision 12 October 2003 12.1.10 OCCUPATIONAL DOSE means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation and/or radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include dose from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the public.

12.1.11 OPERABLE - A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).

12.1.12 OPERATING is defined as performing the intended function in the intended manner.

12.1.13 The OPERATING CYCLE: DELETED 12.1.14 An OPERATIONAL MODE: DELETED 12.1.15 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

12.1.16 PURGE OR PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner, that replacement air or gas is required to purify the confinement.

12.1.17 RATED THERMAL POWER: DELETED 12.1.18 The REACTOR PRESSURE: DELETED 12.1.19 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased or otherwise controlled by the licensee.

12.1.20 SOLIDIFICATION shall be the conversion of radioactive liquid, resin and sludge wastes from liquid systems into a form that meets shipping and burial site requirements.

12.1.21 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

z12r6.doc 12-2

ZION Revision 12 October 2003 12.1.22 SURVEILLANCE shall be those parts of the sections which prescribe remedial measures required under designated conditions, activities required to demonstrate instrument operability, and activities performed to ensure applicable offsite dose limits are not exceeded.

12.1.23 The SURVEILLANCE FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 12.1-1.

12.1.24 THERMAL POWER: DELETED 12.1.25 UNRESTRICTED AREA means an area, access to which is neither limited nor controlled by the licensee.

12.1.26 GASEOUS EFFLUENT TREATMENT SYSTEM shall be any system designed and installed to reduce radioactive material in particulate form in effluents by passing ventilation through HEPA filters for the purpose of removing particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any affect on noble gas effluents. The iodine removal function is no longer used in the defueled condition.

12.1.27 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during venting. Vent, used in system names, does not imply a venting process.

12.1.28 WASTE GAS HOLDUP SYSTEM: DELETED z12r6.doc 12-3

ZION Revision 12 October 2003 TABLE 12.1-1 SURVEILLANCE FREQUENCY NOTATIONS NOTATION FREQUENCY

S (Shiftly) At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D (Daily) At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months W (Weekly) At least once per 7 days M (Monthly) At least once per 31 days Q (Quarterly) At least once per 92 days SA (Semiannually) At least once per 184 days A (Annually) At least once per 366 days R At least once per 18 months P (Prior) Complete prior to start of release N/A Not Applicable

Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. These frequency notations do not apply to the Radiological Environmental Monitoring Program as described in Section 12.5.

zl2rM.doc 12-4

ZION Revision 12 October 2003 12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Plant Monitoring Instrumentation Operabilitv Requirements 12.2.1.A The radioactive liquid plant monitoring instrumentation channels shown in Table 12.2-1 shall be OPERABLE AND, the radioactive liquid effluent monitoring instrumentation channels shall have their alarm/trip setpoints set to ensure that the limits of Section 12.3.1.A are met.

Applicability: As indicated in Table 12.2-3.

Action

1. With a radioactive liquid effluent monitoring instrument channel trip setpoint less conservative than the value necessary to prevent violating the limits of Section 12.3.1A immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

2. With one or more radioactive liquid plant monitoring instrumentation channels inoperable, initiate the SURVEILLANCE requirement delineated in Table 12.2-1.

Surveillance Requirements 12.2.1.8.1 The liquid effluent monitor setpoints shall be determined in accordance with procedures as described in the ODCM.

12.2.1.B.2 Each radioactive liquid plant monitoring instrumentation channel shall be demonstrated OPERABLE by performance of a CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 12.2-2.

Bases 12.2.1.C The radioactive liquid plant monitoring instrumentation is provided to indicate abnormal radiological conditions within the plant, AND, The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the release of radioactive materials in liquid effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of RETS. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10CFR Part 50.

z12M.doc 12-5

( C.'- Revis( .2 October 2003 TABLE 12.2-1 RADIOACTIVE LIQUID PLANT MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE SURVEILLANCE # CONDITION

1. Liquid Effluent Monitors Providing Automatic Termination of Release A. Boric Acid Monitor Tank (BAMT)

1. OR-PRO5 See SURVEILLANCE I I Liquid Release through this Pathway B. Turbine Bldg.

1. OR-PR25 I 2 Liquid Release through this Pathway

2. Effluent Continuous Composite Sampler A. Turbine Building Fire Sump I 2 All Times

3. Effluent Flow Rate Monitor A. Boric Acid Monitor Tank

1. OFI-WD005 1 3 Liquid Release through this Pathway

4. Plant System Monitors NONE z12r6.doc 12-6

ZION Revision 12 October 2003 TABLE 12.2-1 RADIOACTIVE LIQUID PLANT MONITORING INSTRUMENTATION (Cont'd)

SURVEILLANCE 1 If the monitor is inoperable, effluent releases from the tank may continue for up to 14 days, provided that prior to initiating the release:

1. At least two independent samples of the tank's contents are analyzed, in accordance with Section 12.3.1.B.1, and

2. At least two technically qualified members of the facility staff independently verify the release-rate calculations and discharge flow path valving; Otherwise, suspend release of radioactive effluents via this pathway.

SURVEILLANCE 2 With the number of channels OPERABLE less the minimum number required, effluent releases via this pathway may continue, provided that at least once per day grab samples are analyzed for gross radioactivity (beta /gamma or isotopic) at a lower limit of detection (LLD) as specified in Table 12.3-2. Restore the channel to operable status within 30 days or conduct a station review to determine a plan of action to restore the channel to operable status.

SURVEILLANCE 3 With the number of channels OPERABLE less than the minimum number required, effluent releases via this pathway may continue, for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump curves may be used to estimate flow.

z12r6.doc 12-7

( (LION Revision 12 (

October 2003 TABLE 12.2-2 RADIOACTIVE LIQUID PLANT MONITORING INSTRUMENTATION SURVEILLANCE CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION(1) TEST (2)

1. Liquid Effluent Monitors Providing Automatic Termination Of Release A. Boric Acid Monitor Tank (BAMT)

1. OR-PRO5 P P R Q B. Turbine Bldg.

1. OR-PR25 D M R Q

2. Effluent Continuous Composite Sampler A. Turbine Building Fire Sump D N/A N/A N/A

3. Effluent Flow Rate Monitor A. Boric Acid Monitor Tank (BAMT)

1. OFI-WD005 D(3) N/A R(4) N/A

4. Plant System Monitors NONE (1) CHANNEL CALIBRATION shall include performance of a CHANNEL FUNCTIONAL TEST.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that any automatic isolation of this pathway occurs and that control room alarm annunciation occurs if any of the following conditions exist. (if the capability is installed):

a) Instrument indicates levels above the alarm setpoints.

b) Circuit failure.

c) Instrument indicates a downscale failure.

d) Instrument controls not set in operate mode.

(3) CHANNEL CHECK shall consist of verifying indications of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or BATCH RELEASES are made.

(4) Does not Include flow sensor.

z12r6.doc 12-8

ZION Revision 12 October 2003 12.2.2 Radioactive Plant Monitoring Instrumentation Operability Requirements 12.2.2.A The radioactive plant monitoring instrumentation channels shown in Table 12.2-3 shall be OPERABLE, AND, the radioactive gaseous effluent monitoring instrumentation shall have their alarm/trip setpoints set in accordance with the method prescribed in the ODCM to ensure that the limits of Section 12.4.1.A are met.

Applicability: As indicated in Table 12.2-3.

Action

1. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Section, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.

2. With one or more radioactive plant monitoring instrumentation channels inoperable, initiate the SURVEILLANCE requirement as delineated in Table 12.2-3.

Surveillance Requirements 12.2.2.B.1 The effluent monitor setpoints shall be determined in accordance with procedures as described in the ODCM.

12.2.2.8.2 Each radioactive plant monitoring instrumentation channel shall be demonstrated OPERABLE, when in its APPLICABLE CONDITION, by performance of a CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 12.2-4.

Bases 12.2.2.C The radioactive plant monitoring instrumentation is provided to indicate abnormal radiological conditions within the plant, AND, The radioactive gaseous effluent instrumentation is provided to monitor, record and control, as applicable, the release of radioactive materials in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR Part 20.

An Auxiliary Building (AB) ventilation stack is considered available as a release path from radiologically controlled areas of the Auxiliary Building when any AB exhaust fan is discharging to that stack, or any one of the AB exhaust fan dampers is open on that stack.

An Auxiliary Building ventilation stack is unavailable as a release path from radiologically controlled areas of the Auxiliary Building when all AB exhaust fan dampers for that stack are mechanically blocked closed.

z12r6.doc 12-9

ZION *Revision 12 October 2003 TABLE 12.2-3 RADIOACTIVE PLANT MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE SURVEILLANCE CONDITION

1. Effluent Containment Puroe or Vent A. Particulate Monitor

1. 1R-PR40A (Channel 1) 1 61 72 Venting or Purging

2. 2R-PR40A (Channel 1) 1 61, 72 Venting or Purging

2. Aux Building Effluent Monitoring A. Gas Activity Monitor

1. 1R-PR49E (Channel 5) I 10 *

2. 2R-PR49E (Channel 5) I 10 **

B. Particulate Monitor

1. 1R-PR49A (Channel 1) I 11 *

2. 2R-PR49A (Channel 1) I 11 **

C. Flow Rate Monitor

1. 1LP-084 1 8

2. 2LP-084 1 8 **

Whenever the Unit I stack is available as a release path from the Auxiliary Building.

Whenever the Unit 2 stack is available as a release path from the Auxiliary Building.

3. Fuel Building Monitoring A. Gas Activity Monitor

1. ORT-PR30A 1 10 All Times B. Particulate Monitor

1. ORT-PR30B I 11 All Times C. Area Monitoring

1. ORT-AR21 1 12 When fuel is present

2. ORT-AR22 I 14 When fuel is present

3. ORT-AR13 I 13 When fuel building crane is operated with a load on either hook in the bypass mode 1 During VENTING 2 During PURGING zl2r6.doc 12-10

ZION Revision 12 October 2003 TABLE 12.2-3 RADIOACTIVE PLANT MONITORING INSTRUMENTATION (Cont'd)

MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE SURVEILLANCE CONDITION

4. Emergency Monitoring A. Ventilation

1. 1RIA-PR49 (Channel 7) 1 .9

2. 2RIA-PR49 (Channel 7) I 9

3. 1RIA-PR49 (Channel 9) I 9 **

4. 2RIA-PR49 (Channel 9) I 9

Whenever the Unit 1 stack is available as a release path from the Auxiliary Building.

Whenever the Unit 2 stack is available as a release path from the Auxiliary Building.

z12r6.doc 12-11

ZION Revision 12 October 2003 TABLE 12.2-3 RADIOACTIVE PLANT MONITORING INSTRUMENTATION (Cont'd)

TABLE NOTATIONS SURVEILLANCE 6 - With the number of channels OPERABLE less than the minimum number required, effluent releases via this pathway may continue for up to 30 days provided grab samples are obtained and analyzed for gross activity at least once per day.

SURVEILLANCE 7 - With the number of channels OPERABLE less than the minimum number required, and no redundant monitor OPERABLE in this flow path, immediately suspend PURGING of radioactive effluents via this pathway.

SURVEILLANCE 8- Effluent releases via this pathway may continue provided the effluent flow rate is estimated at least once per day while a release is in progress. Restore the inoperable panel to OPERABLE status within 30 days OR conduct a station review to determine a plan of action to restore the panel to OPERABLE status.

SURVEILLANCE 9 - With the number of channels OPERABLE less than the minimum number required, restore the inoperable monitor to OPERABLE status within 30 days OR conduct a station review to determine a plan of action to restore the channel to OPERABLE status.

SURVEILLANCE 10- With the number of OPERABLE channels less than the minimum number required, restore the channel to OPERABLE status within 30 days or conduct a station review to determine a plan of action to restore the channel to OPERABLE status. Effluent releases via this pathway may continue provided grab samples are obtained and analyzed for gross activity at least once per day, OR for the case when the associated LP-084 panel is inoperable, continuous sampling is maintained with a pump and Operations performs a Channel Check Daily. Compensatory sampling does not return the monitor to an OPERABLE status.

SURVEILLANCE 11 - With the number of OPERABLE channels less than the minimum number required, restore the channel to OPERABLE status within 30 days or conduct a station review to determine a plan of action to restore the channel to OPERABLE status. Effluent releases via this pathway may continue provided samples are continuously collected as required in Table 12.4-1. For the case when the associated LP-084 panel is inoperable, continuous sampling can be maintained with a pump and Operations shall perform a Channel Check Daily. Compensatory sampling does not return the monitor to an OPERABLE status.

SURVEILLANCE 12- With the number of channels OPERABLE less than the minimum required, stop all movement of fuel within the spent fuel pool and crane operation with loads over the spent fuel pool AND perform area surveys of the monitored area at least once per day.

SURVEILLANCE 13 With the number of channels OPERABLE less than the minimum required, stop operation of overhead crane in bypass after placing loads in safe condition.

SURVEILLANCE 14 Perform area surveys of the monitored area at least once per day.

z12r6.doc 12-12

(

C ZION Revision 17--

October 20, TABLE 12.2-4 RADIOACTIVE PLANT MONITORING INSTRUMENTATION SURVEILLANCE CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL CHECK CHECK CALIBRATION (1) TEST (2) 1 Effluent Containment Purge or Vent A. Particulate Monitor

1. IR-PR40A (Channel 1) D M R Q

2. 2R-PR40A (Channel 1) D M R Q

2. Aux Building Effluent Monitoring A. Gas Activity Monitor

1. IR-PR49E (Channel 5) D M R Q

2. 2R-PR49E (Channel 5) D M R Q B. Particulate Monitor

1. IR-PR49A (Channel 1) D M R Q

2. 2R-PR49A (Channel 1) D M R Q C. Flow Rate Monitor

1. 1LP-084 D N/A R Q

2. 2LP-084 D N/A R Q

3. Fuel Building Monitoring A. Gas Activity Monitor

1. ORT-PR30A D M A N/A B. Particulate Monitor

1. ORT-PR30B D M A N/A C. Area Monitoring

1. ORT-AR21 D M(4) R N/A

2. ORT-AR22 D M R N/A

3. ORT-AR13 D M(3) R Q z12r6.doc 12-13

ZION Revision 12 t~ ( October 2t TABLE 12.2-4 RADIOACTIVE PLANT MONITORING INSTRUMENTATION SURVEILLANCE (Cont'd)

CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION (1) TEST (2)

4. Emergencv Monitoring A. Ventilation

1. I RIA-PR49 (Channel 7) N/A N/A R Q

2. 2RIA-PR49 (Channel 7) N/A N/A R Q

3. 1RIA-PR49 (Channel 9) N/A N/A R Q

4. 2RIA-PR49 (Channel 9) N/A N/A R Q z12r6.doc 12-14

ZION Revision 12 October 2003 Table 12.2-4 RADIOACTIVE PLANT MONITORING INSTRUMENTATION SURVEILLANCE (Cont'd)

TABLE NOTATIONS (1) CHANNEL CALIBRATION shall include performance of a CHANNEL FUNCTIONAL TEST.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that any automatic isolation occurs; and that Control Room alarm annunciation occurs if any of the following conditions exist (if the capability is installed):

a) Instrument indicates measured levels above the alarm setpoint.

b) Circuit failure.

c) Instrument indicates a downscale failure.

d) Instrument controls not set in "operate" mode.

(3) Daily during operations of overhead crane in bypass mode with a load suspended from the hook.

(4) Daily during fuel handling operations or load handling operations in or above the spent fuel pool.

z12r6.doc 12-15

ZION Revision 12 October 2003 12.3 LIQUID EFFLUENTS 12.3.1 Concentration Operabilitv Requirements 12.3.1.A.1 The concentration of radioactive material released from the site to UNRESTRICTED AREAS (see Zion Station ODCM Annex, Appendix F, Figure F-1) shall be limited to 10 times the concentrations specified in Appendix B, Table 2, Column 2 to IOCFR20.1001-20.2402, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentrations shall be limited to the values listed in Table 12.3-1.

12.3.1.A.2 During the release of radioactive liquid wastes, the combination of dilution water flow and waste water discharge flow shall be established to ensure the discharge concentration limits of 12.3.1.A.1. are not exceeded.

Applicability: At all times.

Action

1. With the concentration of radioactive materials released from the site to UNRESTRICTED AREAS exceeding the limits specified in Section 12.3.1.A.1.

immediately decrease the release rate of radioactive materials and/or increase the dilution flow rate to restore the concentration to within the above limits.

Surveillance Requirements 12.3.1.B.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 12.3-2. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Section 12.3.1.A.1.

12.3.1.B.2 Post-release analyses of samples composited from BATCH RELEASES shall be performed in accordance with Table 12.3-2. The results of the previous post-release analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Section 12.3.1.A.1.

12.3.1.B.3 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 12.3-2.

The results of the analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Section 12.3.1.A.1.

12.3.1.B.4 Appropriate discharge and dilutions flows for each batch radioactive liquid release shall be determined with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Section 12.3.1.A.1.

z12r6.doc 12-16

ZION Revision 12 October 2003 Bases 12.3.1.C This Section is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to UNRESTRICTED AREAS will be less than ten (10) times the concentration levels specified in Appendix B, Table 2, Column 2 to 10CFR 20.1001-20.2402.

This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section I.A design objectives of Appendix I, 10 CFR 50, to a MEMBER OF THE PUBLIC, and (2) the limits of IOCFR20.1301.

zl2r6.doc 12-17

ZION Revision 12 October 2003 TABLE 12.3-1 ALLOWABLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID EFFLUENTS NUCLIDE A(uCi/ml)*

Kr-85m 2X104 Kr-85 5 X 104 Kr-87 4 X le-Kr-88 9 X 10-5 Ar-41 7 X 10-5 Xe-131m 7 X 10o4 Xe-133m 5 X 104 Xe-133 6 X 104 Xe-I 35m 2 X 104 Xe-135 2X10 4

Computed from Equation 20 of ICRP Publication 2(1959), adjusted for infinite cloud submersion in water, and R = 0.01 remnweek, density = 1.0 g/cc and Pw/Pt = 1.0.

z1 2r6.doc 12-18

ZION Revision 12 October 2003 TABLE 12.3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE MINIMUM ANALYSIS LOWER LIMIT OF LIQUID RELEASE SAMPLING FREQUENCY TYPE OF DETECTION (LLD)

TYPE FREQUENCY ACTIVITY ANALYSIS (pCi/ml) (a,e)

A. Boric Acid Monitor Prior to Each Release Prior to Each Principal Gamma 5E-7 Tank (C) Release Emitters (e)

P M Dissolved and 1E-5 One Batch/M(c) Entrained Gases (Gamma Emitters)

P M Tritium 1E-5 Each Batch (c) Composite (b)

Gross Alpha I E-7 P Q Sr-89, Sr-90 5E-8 Each Batch (c) Composite (b)

Fe-55 I E-6 B. Turbine Building Continuous During W Principal Gamma 5E-7 Fire Sump (f) Release (d) Emitters(e)

Dissolved and 1E-5 Entrained Gases (Gamma Emitters)

Continuous (d) M Tritium I E-5 Composite (b)

Gross Alpha 1E-7 Continuous (d) Q Sr-89, Sr-90 5E-8 Composite (b)

Fe-55 1E-C. Waste Neutralizing Prior to each Release Prior to each Release Principal Gamma 5E-7 Tank Emitters (e)

P M Tritium I E-5 Each Batch (c) Composite (b)

_Gross Alpha IE-7 z12r6.doc 12-19

ZION Revision 12 October 2003 TABLE 12.3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE (Cont'd)

TABLE NOTATIONS

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "rear' signal.

For a particular measurement system (which may include radiochemical separation):

LLD = 4.66 s.

A

E

V

2.22

Y

exp (-XAt)

Where:

LLD is the lower limit of detection as defined above in picocuries (pCi) per unit mass or volume, sb is the square root of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

A is the number of gamma rays emitted per disintegration for gamma ray radionuclide analysis (A = 1.0) for gross alpha, strontium, and tritium measurement.

E is the counting efficiency (as counts per gamma),

V is the sample size (in units of mass or volume),

2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield when applicable (otherwise Y = 1.0)

X is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental sample).

The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples.

Typical values of E, V, Y, and At shall be used in the calculation. The background count rate is calculated from the background counts that are determined to be within + one FWHM (Full Width at Half Maximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radionuclide.

z12r6.doc 12-20