3F0403-08, 2002 Radioactive Effluent Release Report

From kanterella
Jump to navigation Jump to search
2002 Radioactive Effluent Release Report
ML031150420
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 04/17/2003
From: Franke J
Progress Energy Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
3F0403-08
Download: ML031150420 (18)
v • d • e


Text

C4 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 17, 2003 3F0403-08 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Crystal River Unit 3 - 2002 Radioactive Effluent Release Report

Dear Sir:

Progress Energy Florida, Inc. hereby submits the 2002 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 2002. 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 TV.B. 1.

ITS 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 2002, no changes were made to the ODCM since the previous submittal of the 2001 Radioactive Effluent Release Report.

If you have any questions regarding this submittal, please contact Mr. Sid Powell, Supervisor, Licensing and Regulatory Programs at (352) 563-4883.

Incery, A. Franke Plant General Manager JAF/ff

Attachment:

2002 Radioactive Effluent Release Report 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, FL34428

PROGRESS ENERGY FLORIDA, INC.

CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 ATTACHMENT 2002 Radioactive Effluent Release Report

RADIOACTIVE EFFLUENT RELEASE REPORT 2002 PROGRESS ENERGY FLORIDA, INC.

CRYSTAL RIVER UNIT 3 Facility Operating License No. DPR-72 Docket No. 50-302 Prepai red By: P) czsQ Q~

Sr. Environmental Specialist Appro' ved By: qlkuixfiIM Superintendent Environmental and Chemistry Date: 4-111i(103

CONTENTS Introduction 1 Tabular Data Summaries Gaseous Effluents - Quarters 1 & 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.l.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.

1

TABLE 1 EFFLUENT AND WASTE DISPOSAL REPORT - 2002 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES I Unit I Quarter I Quarter Est. Total l 1 2 l Error %

A. Fission and activation gases

1. Total release J i7.81E- 3.58E+OO 301 1
2. Average release rate for period jiCilsec 1.OOE-01 4.55E1-1 .
3. Percent of technical specification limit 1.26E-03 4.171-03 B. lodmes
1. Total lodme-131 Cl O.OOE+OO 0 OOE+00 1 30
2. Average release rate for period jiCi/sec O.OOE+00 0 00E+00 J
3. Percent of technical specification limit  % O.OOE+00 O.OOE+00 J C. Particulates*
1. Particulates with half-lives > 8 days Cl 1.70E-07 7.85E-08 30
2. Average release rate for period fCi/sec 2.19E-08 9.99E-09 3 Percent of technical specification limit 3.34E-03 2.60E-03
4. Gross alpha radioactivity Ci 0.OOE+00 0 OOE+00 D. Tritium
1. Total release Ci 1.O1E+O0 8.13E-01 30 I2 Average release rate for period I uCi/sec I 1.3013-01 I 1.03E-01 I
3. Percent of technical specification limit I  % I 3.34E-03 I 2.60E-03 ]
  • 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 - 2002 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES A. Fission gases Argon-41 Ci Krypton-85 Ci 6 34E-01 1 64E+00 Krypton-85m Ci Krypton-87 C1 4 64E-04 Krypton-88 Ci Xenon-131mn Ci 8.20E-03 Xenon-133 Ci 8 12E-01 6 15E-03 1.09E+00 Xenon-133m Ci Xenon-135 C. 1.41E-01 2.25E-02 Xenon-135m Ci Xenon-138 Ci Total for period Ci 1 41E-01 8.12E-01 6 40E-01 2.77E+00 B. lodines Iodine-131 Ci Iodine-132 Ci Iodine-133 Ci Iodine-135 Ci Total for period Ci 0 OOE+00 0 OOE+00 0 OOE+00 0OOOE+00 C. Particulates Zinc-72 Ci .

Cobalt-58* Ci Cobalt-60* Ci Strontium-89* Ci Strontium-90* Ci Niobium-95m Ci Technicium-99m C1 4 35E-08 Tellurnum-132 Ci Cesium-134* Ci .

Cesium-137* Ci 1.70E-07 Cesium-138 Ci Barium-139 Ci .

Lanthanum-142 Ci Cerium-143 Ci 2.73E-07 3.30E-07 Cernum-144* Ci 7.85E-08 Rhenuum-188 Ci Total for period Ci 4.87E-07 3.30E-07 0.OOE+00 7.85E-08

  • > 8 day half-life 3

TABLE3 EFFLUENT AND WASTE DISPOSAL REPORT - 2002 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 3 4 Error %

A. Fission and activation gases

1. Total release C 1 2.89E+00 4 54E+00 Z 30i l
2. Average release rate for period FCi/sec 3.63E-01 5 71E-01
3. Percent of technical specification limit 3.53E-03 6 08E-03 B. lodines
1. Total Iodine-131 Ci 0 OOE+00 O.OOE+00 l 30
2. Average release rate for period LCi/sec 0 OOE+00 O.OOE+00
3. Percent of technical specification limit 0 OOE+00 0.OOE+00 C. Particulates*
1. Particulates with half-lives > 8 days Ci 6 35E-07 1.74E-07 30
2. Average release rate for period puCi/sec 7.99E-08 2.19E-08 3 Percent of technical specification limit 1.83E-03 3 30E-03 4 Gross alpha radioactivity Ci 1.46E-07 0 OOE+00 D. Tritium
1. Total release l Ci l 5.50E-01 l l.0lE+00 l 30Il l 2. Average release rate for period I pCi/sec l 6 91E-02 I 1.28E-01 I
3. Percent of technical specification limit I _ _ I 1.83E-03 I 3.30E-03
  • 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 - 2002 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES A. Fission gases Argon41l Ci ___ __ __ _ _ _

Krypton-85 Ci 4 57E-01 3 24E+00 Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-131m Ci 2 09E-03 1.53E-02 Xenon-133 Ci 5.23E-01 5.48E-02 7.56E-01 Xenon-133m Ci 2.37E+00 Xenon-135 Ci 4.75E-04 Xenon-135m C1 Xenon-138 Ci Total for period Ci 2.37E+00 5 23E-01 5.14E-01 4 02E+00 B. Iodines Iodine-131 Ci lodmne-132 Ci Iodine-133 Ci Iodine-135 Ci Total for period Ci 0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 C. Particulates Zinc-72 Ci 5 09E-08 Cobalt-58* Ci Chromium-51* Ci Strontium-89* Ci Strontlum-90* Ci Niobium-95m Ci _

Tin-113* Ci Indium-113m Ci Barium-133m Ci Cesium-137* Ci 1.17E-07 8.76E-08 Cesium-138 Ci Barium-139 Ci Lanthanum-142 Ci Cenum-141 Ci 8.62E-08 Cenum-143 Ci 1.21E-07 Cenum-144* Ci 5.18E-07 Rhenium-188 C, Total for period Ci 7.56E-07 2.25E-07 0.OOE+00 0 OOE+00

  • > 8 day half-life 5

TABLE 5 EFFLUENT AND WASTE DISPOSAL REPORT - 2002 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total I I 1 l 2 l Error %

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 2.84E-03 l 1.OOE-03 25 l
2. Average diluted concentration during period iCilml 5.36E-12 1.67E-12 I-
3. Percent of applicable limit  % 6 03E-05 6 90E-05 B. Tritium
1. Total release
2. Average diluted concentration during period 3 Percent of applicable limit C. Dissolved and entrained gases
1. Total release Ci 2 03E-03 4 95E-03 I 5 Z
2. Average diluted concentration during period uCi/mI 3 83E-12 8 26E-12
3. Percent of applicable limit _ _1.78E-04 3.86E-04 D. Gross alpha radioactivity
1. Total release Ci 5.99E-04 8.20E-05 30 E. Volume of waste released (prior to dilution)
1. Batch and continuous modes Liters 5.22E+06 4.84E+06 10 l F. Volume of dilution water used during period
1. Batch and continuous modes Liters 5.30E+1l 5.99E+11 l 10 6

TABLE6 EFFLUENT AND WASTE DISPOSAL REPORT - 2002 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Fission and activation products Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Sodium-24 Ci Chromuum-51 Ci 5 95E-05 Manganese-54 Ci 2 04E-06 Manganese-56 Ci Iron-55 Ci 9.72E-05 4.29E-05 Iron-59 Ci Cobalt-57 Ci Cobalt-58 Ci 1 46E-04 5.62E-05 Cobalt-60 Ci 8 78E-05 7.51E-05 Zinc-72 Ci Strontium-85 Ci .

Strontium-89 Ci Strontium-90 Ci Yttrium-91m Ci Yttrium-92 Ci Yttrium-93 Ci Nioblum-95 Ci Niobium-95m Ci Niobium-97 Ci Zircomum-95 Ci Zirconuum-97 Ci 8.25E-07 Molybdmnum-99 Ci Technetium-99m Ci Technetium-101 Ci Ruthemuum-103 Ci Ruthemum-106 Ci Silver-1Orm Ci 4 08E-05 1.89E-05 Tin-1 13 Ci Indium-113m Ci .

Antimony-122 Ci Antimony-124 Ci 1.56E-05 Antimony-125 Cx 2 37E-03 7.71E-04 Tellunum-129 Ci Tellurium-132 Ci 1.16E-06 Iodmne-131 Ci 1.67E-06 Iodxne-133 Cl _ 2.54E-07 Iodmne-135 Cl Cesium-134 Cx 3 30E-06 3 20E-06 Cesium-137 Ci 1 87E-05 2 35E-05 Cesium-138 Ci Barium-139 Ci Banum-140 Ci 2.22E-06 1.30E-06 Lanthanum-140 Ci Cerium-143 Ci Cenum-144 Ci Rhenium-188 Ci Tungsten-187 Ci Neptunium-239 Ci Total for period Ci O.OOE+00 0.00+00 2 84E-03 1.OOE-03 7

TABLE 6 (CONTINUED)

EFFLUENT AND WASTE DISPOSAL REPORT - 2002 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Dissolved and entrained gases Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Argon-41 ci Krypton-85 ci 1.41E-03 2.92E-03 Krypton-85m Cl Krypton-87 Cl Krypton-88 Cl Xenon-131m Cl Xenon-133 Cl 5.93E-04 1 98E-03 Xenon-133m Cl Xenon-135 Ci 3.38E-05 4 64E-05 Xenon-135m Cl Total for period Cl 0 OOE+00 0 OOE+00 2.03E-03 4.95E-03 Tritium Ci 0OOE+00 6 05E-02 1.59E+01 2.50E+01 8

TABLE 7 EFFLUENT AND WASTE DISPOSAL REPORT - 2002 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total I I 1 3 l 4 l Error % I A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 1.1E-03 4.43E-04 JI 25
2. Average diluted concentration during period CIi/mI 1.81E-12 7.73E-13
3. Percent of applicable limit  % 4.03E-04 3.05E-04 B. Tritium
1. Total release Ci 2.17E+02 1.81E+02 30
2. Average diluted concentration during period j MCi/ml 3.55E-07 3.16E-07
3. Percent of applicable limit J _3.58E-01 3.04E-01 C. Dissolved and entrained gases
1. Total release Ci 1.78E-02 2.24E-02 25
2. Average diluted concentration during period pCI/ml 2.91E-11 3.91E-I3 I 3 Percent of applicable limit  % 1.47E-03 1.881E-03 D Gross alpha radioactivity
1. Total release C l 9.75E-05 8.44E-05 7 30 E. Volume of waste released (prior to dilution)
1. Batch and continuous modes Liters 4-80E+06 5.77E+06 10 F. Volume of dilution water used during period
1. Batch and continuous modes Liters 6 12E+11 5.73E+11 10 9

TABLE 8 EFFLUENT AND WASTE DISPOSAL REPORT - 2002 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Fission and activation products Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Sodium-24 Ci Chromium-51 Ci Manganese-54 Ci 1.20E-06 Manganese-56 Ci Iron-55 Cl 1.54E-04 1.75E04 Iron-59 Ci Cobalt-57 Ci 7.40E-07 Cobalt-58 Ci 8.29E-05 6 34E-06 Cobalt-60 Ci 2.16E-04 9.13E-05 Zinc-69 Cl Zinc-72 Cl 6 81E-06 Strontium-85 C_

Strontium-89 Ci Strontium-90 Ci Strontium-92 Ci Yttrnum-91 Ci Yttrnum-92 Ci 4 75E-06 Yttrum-93 Ci Rubidium-88 Ci Niobium-95 Ci 5 87E-06 5 29E-07 Zirconium-95 Ci Zirconmum-97 Ci 6 59E-07 Molybdinum-99 Ci Technetium-99m Ci 6 98E-06 Technetium-101 Ci Ruthenuum-106 Ci .-

Silver-1Orm C 1 03E-04 2 70E-05 Tin-113 Ci 148E-06 Indium-113m Ci 3.78E-06 Antimony-122 C. 1 73E-06 1 89E-07 Antimony-124 Ci Antimony-125 Ci 4.79E-04 9.OOE-05 Tellurium-129 Ci Tellurium-132 Ci Iodine-131 Ci 7.41E-06 1.24E-06 Iodine-132 Ci Iodme-133 Ci 4.27E-06 2.34E-07 Iodine-135 Ci Cesium-134 Ci 4.03E-06 5.31E-06 Cesium-136 Ci Cesium-137 Ci 2.60E-05 2.04E-05 Barium-133m Ci Barium-139 Ci 1.31E-05 Barium-140 Ci Lanthanum-140 Ci Cenum-143 Ci Cenum-144 Ci Praseodymium-144 Ci Neodymium-147 Ci 6 65E-06 7 36E-07 Rhenium-188 Ci .-

Total for period Ci O.OOE+00 0 OOE+00 1.l1E-03 4.43E-04 10

TABLE 8 (CONTINUED)

EFFLUENT AND WASTE DISPOSAL REPORT - 2002 LIQUID EFFLUENTS I.

CONTINUOUS MODE BATCH MODE Dissolved and entrained gases Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Argon-41 Ci Krypton-85 Ci 7.06E-03 5 42E-03 Krypton-85m Cl 8.14E-06 Krypton-87 Cl Krypton-88 Cs Xenon-131m Ci 3.16E-05 1.94E-04 Xenon-133 Ci 9.83E-03 1 66E-02 Xenon-133m Ci 1.20E-04 1 32E-04 Xenon-135 Cl 7.53E-04 1.07E-04 Xenon-135m Cl Total for period Cx O.OOE+00 O.OOE+OO 1.78E-02 2.24E-02 Tritium Ci 0 OOE+00 8 O1E-02 2.17E+02 1. 8E+02 11

TABLE 9 EFFLUENT AND WASTE DISPOSAL REPORT - 2002 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR PROCESSING OR BURIAL (Non-irradiated fuel)

1. Type of waste UmIt 12 month period Est. Total Error %
a. Spent resins, filter sludges, evaporator bottoms, etc. m3 4.60E+01 25 Ci 2.36E+02 2 b Dry compressible waste, contaminated equipment, etc Ci 2.36E+00 25 C3 2036E+00 2
c. Irradiated components, control rods, etc. Cl 0 OOE+00 25 C3 0 OOE+0102
d. Other (describe): CRDMs Cl 3 44E+00 25 Ci 3.78E+00 ________
2. Estimate of major nuclide composition (by type of waste in %)*

Ni-63 42.1 Cs-134 10 2 a Cs-137 18.4 Fe-55 80 Co-60 13.3 Co-58 5 7 Fe-55 51.2 Cs-137 3 5 b Ni-63 22 2 Co-60 15 1 C.

Fe-55 50 0 Ni-63 9.5

d. Co-60 16.2 Mn-54 3.5 Co-58 13 2 3 Solid Waste Disposition Number of Shipments Mode of Transportation Destination 5 Exclusive use truck Barnwell Waste Mngmt (SC) 4 Exclusive use truck Duratek (TN) 2 Exclusive use truck Envirocare (UT)

B. IRRADIATED FUEL SHIPMENTS (Disposition)

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

  • Curie values and principle radionuclides are estimates based on a combination of direct and indirect methods.

12

Unplanned Releases There was one unplanned release in April 2002. An estimated 3900 gallons containing 1.6E-06 Curies of gamma emitters and 3.7E-03 Curies of tritium were released. The release path was from the Nuclear Services Closed Cycle Cooling System (SW) to the Nuclear Services and Decay Seawater System (RW) by way of a leak in SW heat exchanger ID. The RW system discharges to the site discharge canal. The SW system contains residual contamination due to a primary coolant leak into the system in 2001, prior to Refuel 12 (ref NCR 58934).

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

Annual Land Use Census The 2002 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 2002.

ODCM & PCP Changes The ODCM was not revised during 2002.

The PCP was not revised during 2002.

Emergency Feed Pump 2 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 2002 due to operation of this pump. The results of this evaluation are given below in units of Curies/year.

Xe-133 3.20E-07 I-131 4.00E-09 Cs-137 1.20E-08 Xe-135 2.OOE-07 1-133 4.OOE-08 Cs-137 1.20E-08 H-3 3.60E-06 These values are not included in Tables 1 through 4.

Errors in Past Reports Review of effluent analytical methodology indicates that Strontium 85 was incorrectly identified in some liquid effluent samples, and was subsequently reported as being present in several previous effluent reports. This was due to Strontium 85 having same primary gamma energy as Krypton 85, and the analytical software used for gamma ray analysis not being set up to make this distinction. Strontium 85 is not a fission product while Kr-85 is a common fission product known to be present at CR3. These reporting errors overestimated the quantity of fission and activation products released by an amount on the order of I % or less (well within accepted analytical error), and are therefore not significant. (ref. NCR 90625) 13

2002 Appendix I Dose Summary Maximum Hypothetical Individual Liquid Effluent Dose Limits Total Body: 1.5 mrem/quarter, 3 mrem/year Any Organ: 5 mrem/quarter, 10 mrem/year Liquid Effluent Dose Summary Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Total Total Body Dose (mrem) 9.05E-07 1.03E-06 6.05E-06 4.58E-06 1.26E-05 Maximum Organ Dose (mrem) 2.67E-06 1.46E-06 1.34E-05 6.04E-06 2.36E-05 Maximum Organ was GI Gaseous Effluent Dose Limits Gamma Air Dose: 5 mrad/quarter, 10 mrad/year Beta Air Dose: 10 mrad/quarter, 20 mrad/year Any Organ: 7.5 mrem/quarter, 15 mrem/year Gaseous Release Dose Summary Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Total Gamma Air Dose (mrad) 2.25E-05 5.92E-05 6.37E-05 4.04E-05 1.86E-04 Beta Air Dose (mrad) 1.26E-04 4.17E-04 3.53E-04 6.09E-04 1.51E-03 Total Body Dose (mrem) 2.45E-04 1.95E-04 1.33E-04 2.44E-04 8.17E-04 Maximum Organ Dose (mrem) 2.50E-04 1.95E-04 1.37E-04 2.47E-04 8.30E-04 Maximum Organ was Liver 14

Retrieved from "https://kanterella.com/w/index.php?title=3F0403-08,_2002_Radioactive_Effluent_Release_Report&oldid=2693594"