3F0405-04, Transmittal of 2004 Radioactive Effluent Release Report

Transmittal of 2004 Radioactive Effluent Release Report

ML051250348
Person / Time
Site:	Crystal River
Issue date:	04/28/2005
From:	Franke J Progress Energy Florida
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
3F0405-04
Download: ML051250348 (29)

Text

Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: 10 CFR 50.36(a)(2)

ITS 5.7.1.1(c)

April 28, 2005 3F0405-04 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Crystal River Unit 3 - 2004 Radioactive Effluent Release Report

Dear Sir:

Florida Power Corporation, doing business as Progress Energy Florida, Inc., hereby submits the 2004 Radioactive Effluent Release Report for Crystal River Unit 3 (CR-3) in accordance with 10 CFR 50.36(a)(2) and the CR-3 Improved Technical Specifications (ITS), Section 5.7.1.1(c). The attached report includes a summary of the quantities of radioactive liquid and gaseous effluents, and solid waste released from the CR-3 site during 2004. The material provided is consistent with the objectives outlined in the Off-Site Dose Calculation Manual (ODCM) and the Process Control Program (PCP), and is in conformance with 10 CFR 50, Appendix I, Section IV.B.1.

The CR-3 ITS, Section 5.6.2.3.3, requires submittal of licensee initiated changes to the ODCM as part of the Radioactive Effluent Release Report for the period of the report in which any changes were made. During 2004, no changes were made to the ODCM, since the previous submittal of the 2003 Radioactive Effluent Release Report. The PCP, revised during 2004, is included as part of this submittal If you have any questions regarding this submittal, please contact Mr. Sid Powell, Supervisor, Licensing and Regulatory Programs at (352) 563-4883.

Si ly,

/.A. Franke Plant General Manager JAF/ff Attachments:

A. Radioactive Effluent Release Report 2004 B. Process Control Program, Revision 6 xc: NRR Project Manager Regional Administrator, Region II Senior Resident Inspector Progress Energy Florida, Inc.

Crystal River Nuclear Plant 15760 W. Powerline Street Crystal River, FL 34428

PROGRESS ENERGY FLORIDA, INC.

CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 ATTACHMENT A RADIOACTIVE EFFLUENT RELEASE REPORT 2004

RADIOACTIVE EFFLUENT RELEASE REPORT 2004 PROGRESS ENERGY FLORIDA, INC.

CRYSTAL RIVER UNIT 3 Facility Operating License No. DPR-72 Docket No. 50-302 Prepared By: _ o C= LaQQ _

Sr. gnvijunmental Specialist Approved By:

Date:

CONTENTS I n t r o d u c ti o n................................................................................................ I Tabular Data Summaries Gaseous Effluents - Quarters I & 2 . ....................................................... 2 Gaseous Effluents - Quarters 3 & 4 . ....................................................... 4 Liquid Effluents - Quarters 1 & 2........................................................... 6 Liquid Effluents - Quarters 3 & 4........................................................... 9 Radwaste Shipments .............................................................. 12 Unplanned Releases .............................................................. 13 Radioactive Waste Treatment Systems .............................................................. 13 Annual Land Use Census .................... .......................................... 13 Effluent Monitor Instrument Operability .............................................................. 13 ODCM & PCP Changes.................................................................................

.13 Emergency Feed Pump 2 .............................................................. 13 Appendix I Dose Summary ......................... ..................................... 14

INTRODUCTION This report is submitted as required by the Offsite Dose Calculation Manual, section 6.5, and Technical Specfications 5.6.2.3.3 and 5.7. .1.c.

The scope of this report includes:

• A summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the plant.

• Quarterly and annual dose summaries.

• A list and description of unplanned releases to unrestricted areas.

• A description of any changes to the:

Process Control Program (PCP), and Offsite Dose Calculation Manual (ODCM).

• Significant changes to any radioactive waste treatment system.

• A list of new dose calculation location changes identified by the annual land-use census.

• Information relating to effluent monitors or required supporting instrumentation being inoperable for 30 or more days.

I

TABLE 1 EFFLUENT AND WASTE DISPOSAL REPORT - 2004 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit I Quarter I Quarter Est. Total I 1 2 I Error % I A. Fission and activation gases

1. Total release Ci 4. 90E+00 J 1.82E+00

2. Average release rate for period pCi/sec 6.24E-01 l 2.322-01

3. Percent of technical specification limit  % . 7.40E-03 j 2.78E-03 B. lodines

1. Total Iodine-131 l Ci J_0.001+00 l 0.001+00 30

2. Average release rate for period l pCi/sec J 0.001+00 0.0012+00

3. Percent of technical specification limit  % T .001E+00 j O.OOE+00 C. Particulates*

1. Particulates with half-lives > 8 days Ci 0.00E+00 0.002+00 3

2. Average release rate for period pCi/sec 0.002+00 0.002+00

3. Percent of technical specification limit  % 0.0023+00 0.002+00

4. Gross alpha radioactivity Ci 0.002+00 0.001+00 D. Tritium

[1. Total release l Ci l 9.34E-01 l 1.59E+00 lI 30 l 2. Average release rate for period I pCi/sec I 1.19E-01 I 2.0'E-01 l

[3. Percent of technical specification limit I  % I 2.99E-03 I 5.09E-03 I

• The sum of the particulates reported on this page may be less than the sum from Table 2, as Table 2 includes all particulates, while this table includes only those with half-lives greater than 8 days.

2

TABLE2 EFFLUENT AND WASTE DISPOSAL REPORT - 2004 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES A. Fission gases Argon-41 Ci __________ 5.95E 1.761E-03 Krypton-85 Ci 4.44E+00 1.7813+00 Krypton-85m Ci 2.421E-01 5.4912-04 Krypton-87 Ci _ _ _ _ _ _ _ _ _

Krypton-88 Ci Xenon-131m Ci Xenon-133 Ci 1.54E-01 3.67E-02 Xenon-133m Ci _ _ _ _ _ _ _

Xenon-135 Ci 1.4013-021 3.74E244 Xenon-135m Ci _ _ _ _ _ _ __ _ _ _ _ _ _

Xenon-138 Ci Totala for period Ci 2.421E-01 0.0012+00 4.66E+00 1.82E+00

13. Iodines Iodine-131 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Iodine-132 Ci ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Iodine-133 Ci j _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Iodine-135 Ci 1 Totai for period Ci 0.00E3+00 j 0.0012+00 0.0013+00 0.00E+00 C. Particulates Zinc-72 Ci Cobalt-58* Ci _ _ _ _ _ _ _ _ _

Cobalt-60* Ci _ _ _ _ _ _ _

Strontium-89* Ci _ _ _ _ _ _ _ _ _ _

Strontium-90* Ci __ _______

Niobium-95m Ci _ _ _ _ _ _ __ _ _ _ _ _ _

Technicium-99in Ci _________

Tellurium-132 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Cesium -134* Ci _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _

Ccsiumn-137* Ci _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _

Cesium-138 Ci Blarium-139 Ci _ _ _ _ _ _ _ _ _

Lanthanumn-142 Ci Ccrium-141* Ci Ccrium-143* Ci __________

Rh cnium -188 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Total for period Ci 0.002+00 0.002+00 0.002+00 0.002+00

• > 8 day Half-life 3

TABLE 3 EFFLUENT AND WASTE DISPOSAL REPORT - 2004 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter I Est. Total I 1 3 l 4 Error% I A. Fission and activation gases

1. Total release

2. Average release rate for period

3. Percent of technical specification limit B. lodines

1. Total lodine-131 . Ci 0.001+00 9.302-07 30

2. Average release rate for period pCi/sec O.OOE+00 1.171-07

3. Percent of technical specification limit ._ _ 0.001+00 1.28E-02 C. Particulates*

1. Particulates with half-lives > 8 days Ci 2.78E-07 0.OOE+00 30

2. Average release rate for period 14i/sec 3.50-08 O 0.002+00.

3. Percent of technical specification limit . 5.272-03 0.OOE+00

4. Gross alpha radioactivity Ci 0.002+00 0.001+00 D. Tritium

1. Total release Ci l 1.602+00 I 1.542+00 l 30 l l 2. Average release rate for period I pCi/sec I 2.012-01 I 1.942-01 I l 3. Percent of technical specification limit I  % I 5.272-03 I 1.282-02 I

• The sum of the particulates reported on this page may be less than the sum from Table 4, as Table 4 includes all particulates, while this table includes only those with half-lives greater than 8 days.

4

TABLE4 EFFLUENT AND WASTE DISPOSAL REPORT - 2004 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES A. Fission gases Argon-4l Ci _ _ _ _ _ _ _ _ _ 6.85E-02_ __ _ __ _ __ _ _

Kryptor-85 Ci __ _____ 8.57E+00 3.63E+00 Krypton-85m Ci 3.041E-01 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Krypton-87 Ci _ _ _ _ _ _ _ __ _ _ _ _ _ _

Krypton-88 Ci _ _ _ _ _ _ _ __ _ _ _ _ _ _

Xenon-131m Ci _________ 8.382 9.4312-03 Xenon-133 Ci _________ 6.4512+00 4.4612-01 Xenon-133m Ci ________8.00E-02 Xenon-135 Ci __________1.731E-02 2.17E-04 Xenon-135m Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Xenon-138 Ci _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _

Totat for period Ci 3.041E-01 0.00E+00 1.531E+01 4.09E+00 B. lodincs Iodime-131 Ci __ _ _ _ _ _ _ _ _9.3012-07 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Iodine-132 Ci J __ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _

Iodine-133 Ci j _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _1.7612-07 Iodine-135 Ci J

Total for period Ci 0.00E+00 9.30E-07 0.001E+00 1.7612-07 C. Particulates Zinc-72 Ci _ _ _ _ _ _ _ _ _ _ _ _ _

Cobalt.57* Ci _ _ _ _ _ _ _ _ _

Chromium-5 I *Ci _________

Strontium -89* Ci _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Strontium-90* Ci __________

Niobium-95m Ci Tin-113* Ci _ _ _ _ _ _ _ _ _

Indium-113m Ci Barium-133m Ci Cesium-137* Ci 2.74E-07 _ _______

Cesium-138 Ci Barium-139 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Lardhanum-142 Ci ______________

Cerium -141 Ci _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _

Cerium-143 Ci _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _

C erium -144* Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Rhenium -188 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Total for period Ci 2.7412-07 0.0012+00 0.002+00 0.002+00

• > 8 day half-life 5

TABLE5 EFFLUENT AND WASTE DISPOSAL REPORT - 2004 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total I I 1 1 2 I Error% I A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 8.23E-03 1.26E-03 25

2. Average diluted concentration during period pCi/ml 1.63E-12 2.21E-12

3. Percent of applicable limit 2.31E-04 1.23E-04 B. Tritium

1. Total release Ci 4.36E+01 4.51E+01 l 30

2. Average diluted concentration during period ACi/ml 8.62E-08 7.90E-48

3. Percent of applicable limit  % 8.05E-02 7.89E-02 C. Dissolved and entrained gases

1. Total release Ci 4.14E-03 1.31E-02 25

2. Average diluted concentration during period l Ci/ml 8.19E-12 2.30E-11

3. Percent of applicable limit  % 3.82E-04 1.15E-03 D. Gross alpha radioactivity

1. Total release Ci 1.16E-04 3.10E-04 30 E. Volume of waste released (prior to dilution)

1. Batch and continuous modes Liters 7.94E+06 6.51E+06 10 F. Volume of dilution water used during period

1. Batch and continuous modes Liters 5.06E+11 5.71E+11l 10 6

TABLE 6 EFFLUENT AND WASTE DISPOSAL REPORT - 2004 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Fission and activation products Unit Quarter 1 Quarter 2 Quarter I Quarter 2 Sodium-24 Ci Chromium-51 Ci 1.82E-04 Manganese-54 Ci 1.92E-06 Manganese-56 Ci Iron-55 Ci 1.9 1E-04 1.35E-04 Iron-59 Ci Cobalt-57 Ci 4.21E-06 Cobalt-58 Ci 9.83E-04 2.11 E-04 Cobalt-60 Ci 7.752-05 6.25E-05 Zinc-69 Ci 1 .84E-06 Strontium-S5 Ci .

Strontium-89 Ci Strontium-90 Ci Yttrium-91m Ci Yttrium-92 Ci _

Yttrium-93 Ci Niobium-95 Ci 1.1 OE-05 2.65E-06 Niobium-95m Ci Niobium-97 Ci Zirconium-95 Ci Zirconium-97 Ci Molybdinum-99 Ci Technetium-99m Ci Teclmetium-101 Ci Ruthenium-103 Ci _

Ruthenium-106 Ci 1.84E-05 1.05E-05 Silver-lOmn Ci 1.04WE-04 1.052-04 Tin-113 Ci Indium-113m Ci Antimony-122 Ci 7.68E-07 Antimom-124 Ci Antimom-125 Ci 6.64E-03 7.16E-04 Tellurium-129 Ci Tellurium-132 Ci Iodine-131 Ci Iodine-133 Ci lodine-135 Ci Cesium-134 Ci 1.76E-06 2.98S-06 Cesium-137 Ci 1.69E-05 9.96E-06 Cesium-138 Ci Barium-139 Ci Barium-140 Ci Lanthanum-140 Ci Cerium-143 Ci 2.54E-06 Cerium-144 Ci _ _ _

Neodymium-147 Ci Tungsten-187 Ci _

Neptunium-239 Ci Total for period Ci O.OOE+00 0.00+00 8.23E-03 1.26E-03 7

TABLE 6 (CONTINUED)

EFFLUENT AND WASTE DISPOSAL REPORT - 2004 LIQUID EFFLUENTS CONTINUOUS MODE BATCH NIODE Dissolved and entrained gases Unit Quarter 1 Quarter 2 Quarter I Quarter 2 Argon-41 Ci Krypton-85 Ci 2.211E-03 9.34E-03 Krypton-85m Ci 2.41 E-05 Krypton-87 Ci Krypton-88 Ci _

Xenon-131m Ci 1.02E-04 Xenon-133 Ci 1.73E-03 3.46E-03 Xenon-133m Ci 7.68E-06 6.97E-06 Xenon-135 Ci 1.71E-04 1.76E-04 Xenon-135m Ci Total for period Ci O.OOE+00 O.OOE+00 4.14E-03 1.31 E-02 Tritium Ci 9.8213-0 0.00+00 4.35E+01 4.51E+01 8

TABLE 7 EFFLUENT AND WASTE DISPOSAL REPORT - 2004 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total I I 1 3 1 4 I Error % I A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 9.04E-04 5.49E-04

2. Average diluted concentration during period pCi/ml I.51E-12 9.60E-13

3. Percent of applicable limit  % 1.982-03 5.36E-04 B. Tritium

1. Total release [ Ci 9.0413+01 J 3.27E+02l 30Z I

2. Average diluted concentration during period [ pCi/ml 1.51E-07 5.72E-Il 1

3. Percent of applicable limit  % 1.62E-01 { 5.93E-01 C. Dissolved and entrained gases I. Total release Ci 2.84E-02 5.41E-02 2S

2. Average diluted concentration during period 11Ci/ml 4.74E- 1 9.462-11

3. Percent of applicable limit X 2.54E-03 4.91E-03 D. Gross alpha radioactivity

1. Total release Ci 3.101E-05 1.97E-05 l 30 E1. Volume of waste released (prior to dilution)

1. Batch and continuous modes Liters 1.87E+07 7.282+06 10 F. Volume of dilution water used during period

1. Batch and continuous modes Liters 5.99E+11 l 5.72+ 1 10 l 9

TABLE 8 EFFLUENT AND WASTE DISPOSAL REPORT - 2004 LIQUID EFFLUENTS

'I CONTINUOUS MODE BATCH MODE Fission and activation products Unit- Qure Quarter 4 Qatr3Quarter 4 Sodium --24 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Chromium-51I Ci __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _5.55E-06 5.511E-06 M angancsc-54 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

M anganese-56 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Iron-55 Ci ___ ____ 5.06E-05 6.922E-05 Iron-59 Ci _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _

Cobalt-57 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Cobalt-5S Ci 1.4212-OS 2.9412-05 Cobalt-60 Ci __ _____ 5.50E3-06 4.712E-05 Zinc-69 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _

Zinc-72 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Strontium-85 Ci __ _______

Strontiumi-89 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Strontium-90 Ca _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Strontium-921 Ci __________

Yttrium-91 Ci _ _ _ _ _ _ _ _ _

Yttrium-92 Ci _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _

Yttrium-93 Ci _ _ _ _ _ _ _ _ _

Rubidium-88 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Niobium-95 Ci _________ 7.82E-07 Niobium-95mn Ci _______ _______4.OOE-06 Zirconium-97 Ci __ _______

M olybdinum-99 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Tecimctium-99in Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Tecclnctium-101 Ci _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _

Ruthenium-106 Ci _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _

Silver-110mn Ci _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _

Tin-113 Ci__ _ __ _ _ _ _ _ _ _ _

Indiumn-1 13m Ci _ _ _ _ _ _ _ _ _ _ _ _ _

Antimony-122 Ci ________2.6613-06 Antimrroy-124 Ci ______________

Aritimony-125 Ci __ ______ 3.01E-04 1.581E-05 Telluriumn-129 Ci _ _ _ _ _ _ _ _ _

Telluriumn-132 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Iodine-131 Ci ____ _____ 1.15E-06 Iodine-132 Ci _ _ _ _ _ _ _ _ _

lodine-133 Ci _ _ _ _ _ _ _ _ _ _

Iodinc-135 Ci _ _ _ _ _ _ _ _ _

Cesium-134 Ci __________2.5512-05 1.4523-04 Ccsium-136 Ci ___ ______

Cesium-137 Ci 4.36E-05 2.2823-04 Barium-133mi Ci __________

Barium-139 Ci ___ ______

Barium -140 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Latuhanumn-140 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _

Cerium-141 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Cerium-143 Ci __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _2.8123-06 _ _ _ _ _ _ _ _

Praseodymiumi-144 Ci _________

Ncodymium-147 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _

Rlicnium -188 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Total for period Ci 0.0012+00 0.00E2+00 9.0412-04 5.491E-04 10

TABLE 8 (CONTINUED)

EFFLUENT AND WASTE DISPOSAL REPORT - 2004 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Dissolved and entrained gases Unit Qure 3Quarter 4Qure3Qatr4 Argon-4 l Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Krypton-85 Ci ________ ________ 1.841E-02 2.992-02, Krypto i-.85m Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

K rypto "- 7 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Krypto "- 8 Ci _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Xenon-131m Ci _______ 2.06E-04 1.4712-04 Xenon-133 Ci ___________ 9.561E-03 2.3613-02 Xenon-133m Ci ___________ 2.3013-05 7.7712-05 Xenon-135 Ci __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 1.831E-04 3.82E-04 X enon-135m c i _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Total for period Ci 0.0013+00 1.1513-0 2).84E-W2 5.41E-0-2 Tritium Ci 0.OOE+00 2.0512-0 9.0412+01 3.2723+021 I 11

TABLE 9 EFFLUENT AND WASTE DISPOSAL REPORT - 2004 SOLID WASTE AND IRRADIATED FUEL SHIPNIENTS A. SOLID WASTE SHIPPED OFFSITE FOR PROCESSING OR BURIAL (Non-irradiated fuel)

1. Type of waste

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

b. Dry compressible waste, contaminated equipment, etc.

c. Irradiated components, control rods, etc.

d. Other (describe): Combined DAW package

2. Estimate of major nuclide composition (by type of waste in %)*

H-3 21.0 Cs-134 21.3

a. Cs-137 32.3 Fe-55 15.7 Ni-63 8.7 Fe-55 28.1 Cs-137 8.8 Cs-134 3.5

b. Ni-63 15.7 Sb-125 3.2 H-3 2.4 Co-60 22.2 Ag-ilOm 8.1 C-14 2.9 C.

Fe-55 27.4 Ni-63 26.1

d. Co-60 17.6 Cs-134 6.0 Cs-137 10.4 C-14 5.1 Curie values and principle radionuclides are estimates basea on a combination or direct and inairect metnous.

3. Solid Waste Disposition Number of Shipments Mode of Transportation

• Destination 5 Hittman Duratek (TN) 4 Southern Pines Trucking Envirocare (UT) 1 Southern Pines Trucking RACE, LLC 1 Hittman Studsvik Processing Facility (TN) 2 TAG Transport Duratek (TN)

• All exclusive use trucks B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination 0 N/A N/A 12

Unplanned Releases There were no unplanned releases in 2004.

Radioactive Waste Treatment Systems There were no significant changes to the radioactive waste treatment systems.

Annual Land Use Census The 2004 land-use census did not identify any new dose calculation locations.

Effluent Monitor Instrument Operability Required effluent monitor instrumentation was not out of service for more than 30 days during 2004.

ODCM & PCP Changes The ODCM was not revised in 2004.

The PCP was revised in 2004. There were no significant changes. A copy of the PCP, including a summary of changes, has been submitted with this report.

Emergency Feed Pump 2 & Steam Releases Emergency Feed Pump 2 (EFP-2) overspeed testing is performed quarterly using steam from CR-3's steam generators. Due to a small primary to secondary leak, an evaluation was performed to estimate the quantity of radioactive material which was released during 2004 due to operation of this pump. In addition, radioactive releases due to other steam releases (plant trip and valve leaks) have been estimated and included. The results are given below in units of Curies/year.

Xe-133 7.20E-07 1-131 1.68E-08 Cs-134 5.28E-08 Xe-135 5.76E-07 1-133 1.54E-07 Cs-137 4.32E-08 H-3 2.1 1E-05 These values are not included in Tables I through 4.

13

.2004 Appendix I Dose Surmnra Maximum Hypothetical Individual Liquid Emuent Dose Limits Total Body: 1.5 mrernfquarter, 3 mrem/year Any Organ: 5 mrem/quarter, 10 mrem/year Liquid Emuent Dose Summary Quarter I Quarter 2 Quarter 3 Quarter 4 Annual Total Total Body Dose (mrem) 2.011E-06 1.37E3-06 1.831E-05 8.031E-06 2.97E3-05 Maximum Organ Dose (mrem) 2.57E3-06 1.72E-06 9.911E-05 1.OIE3-05 1.141E-04 Maximum Organ was Bone Gaseous Effluent Dose Limits Gamma Air Dose: 5 mrad/quarter, 10 mradlyear Beta Air Dose: 10 mrad/quarter, 20 mradlyear Any Organ: 7.5 mremlquarter, 15 mremlyear Gaseous Release Dose Summary Quarter I Quarter 2 Quarter 3 Quarter 4 Annual Total Gamma Air Dose (mrad) 3.62E-05 3.511E-06 2.28E-04 1.76E-05 2.85E-04 Beta Air Dose (mrad) 7.40E-04 2.78E-04 1.93E-03 5.99E-04 3.545-03 Total Body Dose (mrem) 2.24E-04 3.82E-04 3.86E-04 3.70E-04 1.36E-03 Maximum Organ Dose (mrem) 2.24E-04 3.82E-04 3.86E-04 9.62E-04 1.95E-03 Maximum Organ was Thyroid 14

PROGRESS ENERGY FLORIDA, INC.

CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 ATTACHMENT B PROCESS CONTROL PROGRAM REVISION 6

I2 Primogrss.Energy PROGRESS ENERGY CRYSTAL RIVER NUCLEAR POWER PLANT Miscellaneous General Manual (MGM)

VOLUME 1 PART 1 Process Control Program REVISION 6 I PCP I Rev. 6 l Pae 1 of 10

TABLE OF CONTENTS 1.0 PURPOSE .. 3......................3

2.0 REFERENCES

...................... .. 3 2.1 Developmental References ......................... 3 3.0 PERSONNEL INDOCTRINATION ....................... 3 3.1 Description ................ 3 3.2 Definitions .................. 6 3.3 Responsibilities ................ 6 3.4 Limits and Precautions ................ 7 3.5 Prerequisites ................ 8 4.0 INSTRUCTIONS ............................. 9 4.1 Process Control Program (PCP) ............................. 9 5.0 FOLLOW-UP ACTIONS ........................... 9 5.1 Reporting of Non-conformance ............................. 9 5.2 Revisions ............................ 9 5.3 Record Retention ............................. 9 PCP Rev. 6 Page 2 of 10

1.0 PURPOSE The purpose of the Process Control Program (PCP) is to describe the envelope within which processing and packaging of low-level radioactive wastes will be accomplished to provide reasonable assurance of compliance for low-level waste disposal requirements.

2.0 REFERENCES

2.1 Developmental References 2.1.1 CAP-NGGC-0200, Corrective Action Program 2.1.2 FSAR Chapter 1Table 1-3 FPC Quality Program Commitments item 29 Paragraph C.1 2.1.3 Crystal River Unit 3 Improved Technical Specifications 2.1.4 NUREG 0472, Radiological Effluent Technical Specifications for PWR's 2.1.5 OP-407 (A through S) is a series of procedures detailing the operation of the liquid radwaste systems.

2.1.6 South Carolina Department of Health and Environmental Control, Radioactive Materials License #097 2.1.7 U.S. Nuclear Regulatory Commission Generic Letter 91-02, "Reporting Mishaps Involving LLW Forms Prepared for Disposal 2.1.8 U.S. Nuclear Regulatory Commission, Technical Position on Waste Form, Revision 1,January 1991 2.1.9 HPS-NGGC-0001, Radioactive Material Receipt And Shipping Procedure 2.1.10 WP-204, Condensate Resin Dewatering 2.1.11 WP-204A, Dewatering High Integrity Containers 2.1.12 10CFR61, Licensing Requirements for Land Disposal of Radioactive Waste 3.0 PERSONNEL INDOCTRINATION 3.1 Description 3.1.1 The purpose of the Process Control Program (PCP) at Crystal River Unit 3 is to establish an acceptable method to demonstrate waste stability to assure that waste streams are processed into an acceptable waste form for off-site disposal using plant procedures for the following waste streams:

• radioactive liquid wastes

• dewatered bead resin wastes

• dewatered activated carbon wastes

• filter cartridge wastes lPCP I Rev. 6 Page 3 of 10

3.1.2 An objective of the Process Control Program (PCP) is to use qualified vendors to perform the solidification of various low-level radioactive waste liquids and slurries (including oily wastes) for off-site disposal using vendor PCP solidification and testing procedure(s). The quality of the solidified and or dewatered product shall meet or exceed regulatory requirements and the disposal site criteria.

3.1.3 The qualified vendor will perform the solidification of various low-level radioactive waste liquids and slurries (including oily wastes) for off-site disposal. The quality of the solidified or dewatered product shall meet or exceed regulatory requirements and the disposal site criteria.

3.1.4 Bead Resin Waste 3.1.4.1 Primary Resin Three different bead resin waste streams are generated at CR3. Primary, secondary, and waste processing which consists of bead resins and charcoal.

Primary resins are dewatered and disposed of in High Integrity Containers (HIC).

Primary resin will meet applicable Department of Transportation (DOT) regulations for the following:

• Shipment to a vendor for further processing or waste reduction based on available options, or

• Shipment to a burial site for disposal and shall meet the burial site criteria, or

• Stored on-site.

3.1.4.2 Due to the present disposal options, primary bead resin solidification is not performed at CR3.

3.1.4.3 WP-204A, Dewatering High Integrity Containers will be used for dewatering Primary Bead Resin Wastes. WP-204A contains the acceptance criteria for dewatered primary bead resin wastes.

3.1.4.4 HPS-NGGC-0001, Radioactive Material Receipt and Shipping Procedure will be used to package, store, and ship radioactive material.

3.1.5 Waste processing resin and charcoal waste 3.1.5.1 Waste processing bead resin and charcoal waste is dewatered and disposed of in High Integrity Containers (HIC). Waste processing resin will meet applicable Department of Transportation (DOT) regulations for the following:

• Shipment to a vendor for further processing or waste reduction based on available options, or

• Shipment to a burial site for disposal and shall meet burial site criteria, or

• Stored on-site.

3.1.5.2 Due to processing and disposal options, processing bead resin waste and charcoal waste solidification is not performed at CR3.

3.1.5.3 WP-204A, Dewatering High Integrity Containers will be used for dewatering processing bead resin waste and charcoal waste. WP-204A contains the I PCP I Rev. 6 l Page 4 of 10 I

acceptance criteria for dewatered processing bead resin waste and charcoal waste.

3.1.5.4 HPS-NGGC-0001, Radioactive Material Receipt and Shipping Procedure will be used to package, store, and ship radioactive material.

3.1.6 Secondary Resin Waste 3.1.6.1 Secondary resin is dewatered and will be disposed of in approved waste containers and shall meet applicable Department of Transportation (DOT) regulations to a:

• Vendor for further processing or waste reduction based on available options, or

• A burial site for disposal and shall meet burial site criteria, or

• Stored on-site.

3.1.6.2 Due to processing and disposal options, secondary resin solidification is not performed at CR3.

3.1.6.3 WP-204, Secondary Resin Dewatering will be used for dewatering secondary bead resin waste. WP-204 contains the acceptance criteria for dewatered Secondary Bead Resin Waste.

3.1.6.4 HPS-NGGC-0001, Radioactive Material Receipt and Shipping Procedure will be used to package, store, and ship radioactive material.

3.1.7 Filter Wastes 3.1.7.1 Filters are generated from the Make Up & Purification System, Spent Fuel Cooling System, and Waste Processing filters. Spent Filters are removed from the system(s), drip drained, and stored in filter canisters. The filter canisters are placed into filter canister racks and stored in the Auxiliary Building. The filter canisters are then:

• Placed into a High Integrity Container (HIC) where absorbent material will be placed in the bottom of the HIC for absorption of any remaining residual water draining from the filter canisters. The HIC is then shipped off-site and shall meet applicable Department of Transportation (DOT) regulations and shall meet burial site criteria, or

• Placed into other approved container(s) for processing where absorbent material such as absorption pads is placed in the bottom of the container for absorption of any remaining residual water draining from the filters. The container(s) is then shipped off-site, and shall meet applicable Department of Transportation (DOT) regulations, or

• Stored on-site.

3.1.7.2 Due to processing and disposal options, spent filter waste is not solidified at CR3.

3.1.7.3 OP-407 (A through S) is a series of procedures detailing the operation of the liquid Radwaste systems and will be used to replace spent filter(s).

3.1.8 HPS-NGGC-0001, Radioactive Material Receipt and Shipping Procedure will be used to package, store, and ship radioactive material.

I PCP I Rev. 6 1 Page 5of 10 I

3.2 Definitions 3.2.1 Batch - For the purpose of this PCP relating to solidification, sampling or processing, a batch is defined as any quantity of waste stream feed material that is from a single homogeneous source (e.g., a holding tank), that is processed as a single batch (even though it maybe subdivided in more than one unit waste form, and that, therefore, possesses unvaried, single operation, batch characteristics.

3.2.2 Process Control Program (PCP) - A program that contains the methodology and controls to ensure that radioactive liquid wastes, dewatered bead resin wastes, dewatered carbon wastes, filter wastes are processed into an acceptable waste form that meets regulatory and disposal requirements using plant procedures.

3.3 Responsibilities 3.3.1 The Senior Radiation Control Specialist is responsible for:

• Revisions to the CR3 Process Control Program (PCP).

• Ensuring that revisions to the PCP are submitted to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report covering the period of time the PCP was modified.

• Evaluating the adequacy of vendor proposed contractual agreements for waste solidification.

• Evaluating the adequacy of vendor solidification procedure to ensure there are provisions for each specific type of waste to be solidified. This includes the use of Environstone for Class A Unstable waste solidification.[NOCS 040183]

• Evaluating the adequacy of vendor quality assurance validation testing method for the solidification media to be used for each type of waste to be solidified to eliminate the possibility or potential of using deteriorated media for waste solidification. [NOCS 040183]

• Approving vendor proposed contractual agreements for waste solidification.

• Review and approval of vendor process control program solidification procedure(s) prior to commencement of solidification or dewatering activities to ensure compliance with burial site criteria requirements and regulations.

• Obtaining concurrent approval from the Superintendent, Radiation Protection for vendor to perform solidification/dewatering activities.

• Ensuring vendor compliance with solidification procedure. If not, suspend shipments of defectively processed or defectively packaged solid radioactive waste from the site.

• Retaining vendor-supplied documentation for NRC inspection and review.

• Shipping solidified and dewatered wastes.

• Maintain shipping and vendor documentation.

I PCP I Rev. 6 l Page 6 of 10 l

3.3.2 The Superintendent of Radiation Protection is responsible for:

Final review and approval of vendor process control program solidification or dewatering procedure(s) prior to commencement of solidification or dewatering activities to ensure compliance with burial site criteria requirements and regulations.

3.4 Limits and Precautions Specifications for qualified Solidification/ Dewatering Vendor The qualified solidification/dewatering vendor will:

1. Provide and use a Waste Solidification and Testing Procedure that has been approved by the Senior Radiation Control Specialist for each batch of waste to be solidified including the use of Environstone for Class A Unstable waste solidification.

2. Provide and use a Waste Solidification and Testing Procedure that will ensure compliance with burial site criteria requirements and regulations.

3. Be accountable to the Senior Radiation Control Specialist.

4. Provide and use a quality assurance validation testing method for the solidification media to be used for each type of waste to be solidified to eliminate the possibility or potential of using deteriorated media for waste solidification. [NOCS 040183]

5. Ensure the waste tanks or containers will be recirculated to obtain a representative, homogenous sample. A volume of waste is considered to be homogenous when three (3) tank volumes have been recirculated on an isolated batch of material. The waste tanks should be maintained on recirculation until sampling is complete. If the previously analyzed waste tanks receive additional material, the new mixture must be recirculated, resampled, and reanalyzed, unless it has been documented that the additional material is chemically and radiologically similar to the analyzed waste. Samples and analyses are necessary to prepare waste for solidification and disposal. Those samples include sample for isotopic analysis and curie content and samples for chemistry parameters and PCP test solidification.

6. Provide documentation to demonstrate compliance with solidification requirements to the Senior Radiation Control Specialist.

7. Solidify/dewater waste in accordance with the vendor approved solidification procedure or dewatering procedure.

8. Perform analytical tests to verify the solidification of at least one representative test specimen from at least every tenth batch of each type of wet radioactive wastes (e.g. filter sludges, spent resins, and boric acid solutions). [NOCS 009716]

9. Suspend the solidification of the batch under test if any specimen as required by the vendor's solidification procedure fails to verify solidification until such time as additional test specimens can be obtained. Alternate solidification parameters and solidification of the batch may be resumed as permitted by the Vendor's solidification procedure.

IPCP I Rev.66 Page7of 10I

3.5 Prerequisites 3.5.1 Acceptance criteria for waste processing for radioactive liquid wastes, dewatered bead resin wastes, dewatered activated carbon wastes, filter cartridge wastes is provided in plant procedures.

3.5.2 Acceptance criteria for waste solidification will be provided in applicable sections of this PCP, and in the vendor's solidification and testing procedure.

3.5.3 Solidification test specimens will only be considered acceptable if they meet the free standing liquid requirements of 10 CFR 61 and the Radioactive Material License #097 issued to the Barnwell disposal facility by the South Carolina Department of Health and environmental Control.

3.5.3.1 Class A unstable waste test specimens must maintain shape after removal from the waste container (i.e., must be a free standing monolith). Class A Stable wastes and Class B and C wastes must meet all the applicable stability requirements referenced in 10 CFR 61 and the Radioactive Material License #097 issued to the Barnwell disposal facility by the South Carolina Department of Health and Environmental Control. [NOCS 009716]

3.5.3.2 If any specimen fails to pass the Acceptance Criteria, the applicable actions of section 3.5.4 must be met.

3.5.4 Ifthe initial test specimens from a batch of waste fail to verify solidification, additional test specimens shall be collected. The process and/or additives shall be modified as required until an acceptable test specimen solidification is documented.

If any test specimen fails to verify solidification, the solidification of the batch under test shall be suspended until such time as additional test specimens can be obtained. Alternate solidification parameters can be determined in accordance with the Vendor's Process Control Program solidification procedures, and a subsequent test verifies solidification. Solidification of the batch may then be resumed using the alternative solidification parameters.

3.5.5 The following commitments have been relocated from the Radiological Effluent Technical Specifications (RETS) Section 3.7.13.4 by Amendment #141 to the Process Control Program (PCP) and shall apply:

3.5.5.1 Specification -The solid waste processing system shall be used at all times in accordance with a Process Control Program to process wet radioactive wastes to meet shipping and burial ground requirements. [NOCS 009715]

3.5.5.2 Action - With the provisions of the Process Control Program not satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive wastes from the site. [NOCS 009715]

3.5.5.3 Surveillance - If solidification is performed, at least one representative test specimen from at least every tenth batch of each type of wet radioactive waste (e.g., filter sludges, spent resins, and boric acid solutions) shall be verified for solidification.

[NOCS 009716]

I PCP I Rev. 6 l Page8of 10 I

4.0 INSTRUCTIONS 4.1 Process Control Program (PCP)

The Process Control Program is not intended to be used as an operating waste procedure. Actual plant procedures are referenced where applicable.

5.0 FOLLOW-UP ACTIONS 5.1 Reporting of Non-conformance 5.1.1 Reporting of nonconformance under the PCP.is to be done in accordance with CAP-NGGC-0200, Corrective Action Program.

5.1.2 Waste form mishaps should be reported to the NRC's Director of the Division of Low-Level Waste Management and Decommissioning and the designated State disposal site regulatory authority within 30 days of knowledge of the incident.

5.2 Revisions 5.2.1 Records of reviews and changes to the Process Control Program shall be documented and those records shall be retained. This documentation shall contain and/or be performed in accordance with:

5.2.2 Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s), and

• A determination that the change will maintain the overall conformance of the Process Control Program.

• REG-NGGC-0010, 10 CFR 50.59 Reviews.

• FSAR Chapter 1Table 1-3 FPC Quality Program Commitments item 29 Paragraph C.1

• CP-252 Commitment Management 5.2.3 PRO-NGGC-0204 will be utilized as the control mechanism for changes to the PCP.

5.3 Record Retention 5.3.1 Records Management shall maintain vendor solidification and vendor PCP dewatering procedures for the life of plant.

5.3.2 Vendor solidification, PCP dewatering procedures, data sheets, and enclosures shall be routed to Records Management after the waste(s) has been solidified.

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Summary of Changes Throughout Editorial corrections 2.1.1 Replaced CP-111 with CAP-NGGC-0200 throughout procedure 2.1.9 Replaced WP-101 with HPS-NGGC-0001 throughout procedure 2.1.10 Deleted reference to WP-1 02.

2.1.11 Corrected title of WP-204 to Condensate Resin Dewatering 3.2.2 Replaced Chem-Rad Specialist II with Senior Radiation Control Specialist and throughout procedure 3.3.1, 3.3.2 Replaced Manager with Superintendent 5.2.1 Replaced bullet on CP-213 with REG-NGGC-0010, 10 CFR 50.59 reviews I PCP I Rev. 6 l Page 10 of 10 I