3F0311-11, 2010 Radioactive Effluent Release Report
| ML110940075 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/31/2011 |
| From: | Holt J, Pinner R Progress Energy Florida |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 3F0311-11 | |
| Download: ML110940075 (26) | |
Text
Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: 10 CFR 50.36a(a)(2)
ITS 5.7.1.1(c)
March 31, 2011 3F031 1-11 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Crystal River Unit 3 - 2010 Radioactive Effluent Release Report
Reference:
Crystal River Unit 3 - 2009 Radioactive Effluent Release Report (Accession No. ML101250163)
Dear Sir:
Florida Power Corporation (FPC), doing business as Progress Energy Florida, Inc., hereby submits the 2010 Radioactive Effluent Release Report for Crystal River Unit 3 (CR-3) in accordance with 10 CFR 50.36a(a)(2) and the CR-3 Improved Technical Specifications (ITS),
Section 5.7.1.1(c). The subject report (Attachment A) includes a summary of the quantities of radioactive liquid and gaseous effluents, and solid waste released from the CR-3 site during 2010.
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, 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. The ODCM and the PCP were not revised in 2010.
Included in this submittal are three amended pages from the above referenced report that corrects a transposition error that discovered after the 2009 Radioactive Effluent Release Report was submitted last year. This error was entered into the CR-3 Corrective Action Progam.
This letter establishes no new regulatory commitments.
If you have any questions regarding this submittal, please contact Mr. Dan Westcott, Superintendent, Licensing and Regulatory Programs at (352) 563-4796.
Sincerely, mes W. Holt Plant General Manager JWH/ff Attachments:
A.
Radioactive Effluent Release Report 2010 B.
Amended Partial Annual Radioactive Effluent Release Report 2009 xc:
NRR Project Manager Regional Administrator, Region II Senior Resident Inspector Progress Energy Florida. Inc.
Crystal River Nuclear Plant 15760 W. Power Line 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 2010
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2010
& Progress Energy PROGRESS ENERGY FLORIDA, INC CRYSTAL RIVER UNIT 3 Facility Operating License No. DPR-72 Docket No. 50-302 Pinner, Rudolph W.
I am the author of this document.
2011.03.23 08:57:54 -04'00' Prepared By: _
Approved By:
Sr. Nuclear Plant Chemistry Specialist Hughes, Lee 2011.03.23 09:52:50 -04'00' Superintendent Environmental & Chemistry Date:
March 22, 2011
CONTENTS Introduction.................................................................................................................................
1 Tabular Data Summaries G aseous Effl uents - Q uarters 1 & 2............................................................................
2 G aseous Effl uents - Q uarters 3 & 4............................................................................
4 Liquid Effluents - Q uarters 1 & 2...............................................................................
6 Liquid Effluents - Q uarters 3 & 4...............................................................................
9 Radw aste Shipm ents.................................................................................................................
12 U nplanned Releases....................................................................................................................
13 Radioactive W aste Treatm ent System s.....................................................................................
13 Annual Land U se Census..........................................................................................................
13 Effl uent M onitor Instrum ent O perability.................................................................................
13 O D CM & PCP Changes...........................................................................................................
13 Em ergency Feed Pum p 2...........................................................................................................
14 Carbon-14 Evaluation................................................................................................................
14 A ppendix I D ose Sum m ary.......................................................................................................
15 N EI 07-07 Required D ata.........................................................................................................
16 Amended 2009 Partial Annual Radioactive Effluent Release Report....................................
18
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 5.7.1.1.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.
Information required to be included in this report per NEI 07-07 Industry Ground Water Protection Initiative-Final Guidance Document issued in August 2007.
I
TABLE 1 EFFLUENT AND WASTE DISPOSAL REPORT - 2010 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total I 1 2
Error %
A.
Fission and activation gases
- 1.
Total release
- 2.
Average release rate for period
- 3.
Percent of technical specification limit B.
lodines I.
Total Iodine-131
- 2.
Average release rate for period
- 3.
Percent of technical specification limit C.
Particulates*
I.
Particulates with half-lives > 8 days Ci 9.90E-08 9.19E-09 30
- 2.
Average release rate for period itCi/sec 1.27E-08 1.1 7E-09
- 3.
Percent of technical specification limit 6.65E-03 7.90E-03
- 4.
Gross alpha radioactivity Ci I1.25E-08 7.43E-08 D.
Tritium I.
Total release Ci 2.08E+00 2.47E+00
- 2.
Average release rate for period RCi/sec I
2.67E-01 3.14E-0OI
- 3.
Percent of technical specification limit 6.65E-03 7.90E-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
TABLE 2 EFFLUENT AND WASTE DISPOSAL REPORT - 2010 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES A.
Fission gases Argon-4l Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-l13l1m Ci Xenon-133 Ci Xenon-l33m Ci Xenon-135 Ci Xenon-l 5m Ci Xenon-l38 Ci Total for period Ci O.OOE+OO O.OOE+0O O.OOE+OO O.OOE+OO B.
lodines C.
Particulates Mangasiese-54*
Ci Zinc-72 Ci 2.0713-07__________
Cobalt-58*
Ci 9.90E-08 9.19E-09_____
Cobalt-6O*
Ci Strontium-89*
Ci Strontium-9O*
Ci Niobium-95m Ci Technicium-99m Ci Tellurium-I 32 Ci Cesium-l34*
Ci Cesium-l37*
Ci Cesium-138 Ci Barium-I 39 Ci Lanthanum-142 Ci Cerium-141 Ci Cerium-143 Ci 6.17E-07__________
Rhenium-I 88 Ci Total for period Ci 7.1 6E-07 2.1 6E-07 O.OOE+0O O.OOE+OO
- > 8 day half-life 3
TABLE3 EFFLUENT AND WASTE DISPOSAL REPORT - 2010 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 3
4 Error %
A.
Fission and activation gases I.
Total release
- 2.
Average release rate for period
- 3.
Percent of technical specification limit B.
lodines
- 11.
Total Iodine-131
- 2.
Average release rate for period
- 3.
Percent of technical specification limit C.
Particulates*
I.
Particulates with half-fives > 8 days Ci 1.68E-07 1.83E-07 30
- 2.
Average release rate for period g.Ci/sec 2.11 E-08 2.29E-08
- 3.
Percent of technical specification limit 8.28E-03 8.33E-03
- 4.
Gross alpha radioactivity Ci O.OOE+00 O.OOE+00 D.
Tritium I.
Total release Ci 2.56E+00 2.57E+00 30
- 2.
Average release rate for period jICi/sec 3.22E-01 3.24E-01
- 3.
Percent of technical specification limit
[
8.28E-03 8.33E-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-fives greater than 8 days.
4
TABLE4 EFFLUENT AND WASTE DISPOSAL REPORT - 2010 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE Nuclides Released Unit j Quarter 3 Quarter 4 J Quarter 3 Quarter 4 A.
Fission gases Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-13 1 m Ci Xenon-133 Ci Xenon-133m Ci Xenon-l35 Ci Xenon-135m Ci Xenon-13 8 C i Total for period
]Ci O.OOE+0O O.OOE+OO O.OOE+OO O.OOE+OO B.
Todines lodine-131 Ci
__________I__________
Iodine-132 Ci
__________I__________
Iodine-l33 Ci I____________
Iodine-135 Ci Total for period Ci O.OOE+OO O.OOE+0O O.OOE+OO O.OOE+OO C.
Particulates Manganese-54*
Ci Zinc-72 Ci Cobalt-58*
Ci Cobalt-6O*
Ci Chromnium-5 1 Ci Strontium-89*
Ci Strontium-9O*
ai Niobium-95*
Ci Tin-ll3*
Ci Zireonium-95
- Ci Bariurn-133m Ci Cesium-l37*
Ci 1.68E-07 1.32E-07 5.05E-08 Barium-l39 Ci Cerium-141 Ci Cerium-l43 C~i 9.09E-07 Cerium-l44*
Ci Ruthenium-103 Ci Total for period Ci 1.08E-06 1.32E-07 O.OOE+OO 5.05E-08
- > 8 day half-life 5
TABLE 5 EFFLUENT AND WASTE DISPOSAL REPORT - 2010 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total I
1 2
Error %
A.
Fission and activation products
- 1.
Total release (not including tritium, gases, alpha)
- 2.
Average diluted concentration during period
- 3.
Percent of applicable limit B.
Tritium I.
Total release
- 2.
Average diluted concentration during period
- 3.
Percent of applicable limit C.
Dissolved and entrained gases I.
Total release
- 2.
Average diluted concentration during period
- 3.
Percent of applicable limit D.
Gross alpha radioactivity I.
Total release E.
Volume of waste released (prior to dilution)
- 1.
Batch and continuous modes F.
Volume of dilution water used during period
- 1.
Batch and continuous modes Ci 7.84E-03 2.09E-03 IiCi/ml 2.48E-11 6.57E-12 3.12E-04 1.30E-04 25 1
Ci 2.3 1E-04 5.73E-04 30:
I Liters 9.98E+06 4.86E+06 10 Liters 3.17E+1 I 3.18E+11 10 6
TABLE 6 EFFLUENT AND WASTE DISPOSAL REPORT - 2010 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Fission and activation products Unit Quarter 1 Quarter 2 Quarte Quarter 2 Sodium-24 Ci Chromium-51 ICi 5.2113-05 Manganese-54 Ci Manganese-56 Ci Lron-55 Ci lron-59 Ci Cobalt-57 Ci Cobalt-58 Ci 1__________
.05E-04 1.98E-05 Cobalt-60 Ci 2.99E-05 2.3313-04 Zinc-69 Ci Strontium-85 Ci Strontium-89 Ci Strontium-90 Ci Yttrium-91m Ci Yttrium-92 Ci Yttrium-93 Ci Niobium-95 Ci 9.05E-07 Niobium-95m Ci Niobium-97 Ci Zirconium-95 Ci Zirconium-97 Ci Molybdinum-99 Ci Technetium-99m Ci Technetium-l0l Ci Ruthenium-103 C i Ruthenium-106 C i Silver-1I lOin Ci Tin-I 13 Ci Indium-1 13m Ci Antimony-122 Ci Antimony-124 Ci Antimony-125 Ci 7.50E-03 1.64E-03 Tellurium-129 Ci Tellurium-132 Ci Iodine-131 Ci Iodine-133 Ci Iodine-135 Ci Cesium-134 Ci Cesium-137 Ci 1.96E-05 7.14E-05 1.23E-04 Cesium-138 Ci Barium-133m Ci Barium-140 Ci Lanthanum-140 Ci Cerium-141 Ci Cerium-143 Ci Neodynmium-147 Ci Tungsten-187 Ci Neptunium--239 Ci I_________
Nickle-63 Ci 6.3 1lE-05 7.25E-05 Total for period Ci I
1.96E-05 O.OOE+OO 7.82E-03 2.09E-03 7
TABLE 6 (CONTINUED)
EFFLUENT AND WASTE DISPOSAL REPORT - 2010 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 Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-131m Ci Xenon-l33 Ci Xenon-133m Ci Xenon-135 C i Xenon-135m C i Total for period Ci O.OOE+0O O.OOE+OO O.OOE+OO O.OOE+0O Tritium Ci 3.65E-03 O.OOE+OO 1.93E+00 2.OOE+O 8
TABLE 7 EFFLUENT AND WASTE DISPOSAL REPORT - 2010 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 3
4 Error %
A.
Fission and activation products I.
Total release (not including tritium, gases, alpha)
- 2.
Average diluted concentration during period
- 3.
Percent of applicable limit B.
Tritium I.
Total release
- 2.
Average diluted concentration during period
- 3.
Percent of applicable limit C.
Dissolved and entrained gases I.
Total release Ci O.OOE+00 O.OOE+00 25
- 2.
Average diluted concentration during period lsCi/ml O.OOE+00 O.OOE+00
- 3.
Percent of applicable limit 0.00E+00 0.00E+00 D.
Gross alpha radioactivity I.
Total release Ci O.OOE+0 I
O.OOEIoo 300 E.
Volume of waste released (prior to dilution)
I.
Batch and continuous modes Liters 5.26E+06 6.06E+06 10 F.
Volume of dilution water used during period I1. Batch and continuous modes Liters 3.33E+1l1 2.60E+1 1 10 9
TABLE 8 EFFLUENT AND WASTE DISPOSAL REPORT - 2010 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 4.87E-06 2.06E-04 Manganese-56 Ci lron-55 Ci Iron-59 Ci Cobalt-57 Ci Cobalt-58 ci 8.47E-06
- 1. 19E-04 Cobalt-60 Ci 7.33E-05 2.18E-03 Zinc-69 Ci Zinc-72 Ci Strontium-85 Ci Strontium-89 Ci Strontium-90 Ci Strontium-92 Ci Yttrium-91 ci Yttrium-92 ci Yttrium-93 Ci Rubidium-88 Ci Niobium-95 Ci Niobium-95m Ci Zirconium-95 Ci
___________2.97E-05 Zirconium-97 Ci
___________9.50E-07 Molybdinuni-99 Ci Technetiwm-99m Ci Technetiumn-l0l Ci Ruthenium-106 Ci Silver-I I Gm Ci 1.29E-05 7.23E-04 Tin-1 13 Ci Indiuin-1l3m Ci Antimony-122 Ci Antimony-124 Ci Antimony-125 Ci 2.23E-04 1.82E-04 Tellurium-129 Ci Tellurium-132 Ci lodine-131 C0_____________________
Iodine-133 Ci Todine-1 35 Ci Cesiwn-134 Ci
- 1. 14E-05 3.94E-06 Cesium-137 Ci 1.52E-04 1.03E-04 Barium-133m Ci Bariwn-139 Ci Barium-140 Ci Lanthanum-140 Ci Cerium-141 Ci Cerium-143 Ci Praseodymium-144 Ci Neodymium-147 Ci Neptunium-239 Ci Nickel-63 Ci 9.17E-05 1.02E-04 Rheniuin-188 Ci Total for period Ci O.OOE+OO O.OOE+OO 5.78E-04 3.65E-03 10
TABLE 8 (CONTINUED)
EFFLUENT AND WASTE DISPOSAL REPORT - 2010 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Dissolved and entrained gases Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Total for period Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Tritium Ci O.OOE+00 O.OOE+00 1.93E+00 1.53E+0l 11
TABLE9 EFFLUENT AND WASTE DISPOSAL REPORT - 2010 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.
SOLID WASTE SHIPPED OFFSITE FOR PROCESSING OR BURIAL (Non-irradiated fuel)
Type of waste Unit 12 month period Est. Total Error %
m3 4.38E+01 25
- a.
Spent resins, filter sludges, evaporator bottoms, etc.
Ci 7.96E+01 25 m3 6.48E+02 25
- b.
Dry compressible waste, contaminated equipment, etc.
Ci 8.04E-01 25 m3 0.00E+00 25
- c.
Irradiated components, control rods, etc.
m3 0.00E+00 25 Ci 0.00E+00
- d.
Other (describe): Combined DAW package m3 3.00E+01 25 Ci 1.72E+00
- 2.
Estimate of major nuclide composition (by type of waste in %)*
Fe-55 9.55 Co-58 0.18 Cs-134 5.23
- a.
Sb-125 0.25 Co-60 6.68 Cs-137 27.93 Mn-54 0.46 Ni-63 49.13 C-14 0.23 Ni-63 19.29 Co-58 9.97
- b.
Fe-55 37.23 Mn-54 3.94 Ce-144 2.28 Co-60 20.77 Cs-137 2.50 Cs-134 0.87 Nb-95 1.95
- c.
N/A N/A N/A Fe-55 29.36 Sb-125 3.33 Mn-54 1.49
- d.
Co-60 13.68 Cs-134 1.81 H-3 5.98 Ni-63 29.83 Cs-137 9.40 C-14 0.42 Co-58 2.28 Ce-144 1.29 Ag-110m 0.70
- Curie values and principle radionuclides are estimates based on a combination of direct and indir
- 3.
Solid Waste Disposition Number of Shipments Mode of Transportation rect methods.
12 02 11 01 05 Highway Highway Highway Highway Highway Destination EnergySolutions-Bear Creek EnergySolutions-LLC.
IMPACT Services, Inc.
IMPACT Services, Inc.
Studsvik Processing Facility, LLC Destination N/A B.
IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments Mode of Transportation 0
N/A 12
Unplanned Releases There were no unplanned releases in 2010.
Radioactive Waste Treatment Systems There were no significant changes to the radioactive waste treatment systems in 2010. A different mixed bed resin with 1:1 cation to anion ratio was added to two of the five waste processing demineralizers to provide added capacity to target removal of Sb-125 in support of plant start up activities.
Annual Land Use Census The 2010 land-use census did not identify any new dose calculation locations.
Effluent Monitor Instrument Operability During 2010, WD-19-FQI, waste gas effluent flow element, was declared inoperable on 3-4-10 due to improper flow indication. This instrumentation is used to measure flow during release of Waste Gas Decay Tanks. During the course of the extended refuel 16 outage at Crystal River Unit 3, the waste gas system is presently aligned to the auxiliary building ventilation. The waste gas decay tanks are not in service and are empty. A post maintenance test cannot be performed until the waste gas system is realigned to service with the waste gas decay tanks, therefore this instrumentation remains inoperable. This instrumentation will be tested and verified satisfactory prior to the plant heat up, which remains on hold due to the reactor building containment wall repair. Nuclear Condition Report 391053 and Work Request 422663 are tracking the repair and return to service of this instrument. There have been no waste gas decay tank releases performed that require use of this instrument during this time period.
ODCM & PCP Changes The ODCM was not revised in 2010. Revision 32, performed in 2009, incorporated the following changes:
- 1.
The replacement of the CR-3 steam generators in refuel 16 outage require cutting a sizeable hole in the reactor building wall to facilitate removal and installation of these large components. Verbiage was added to page 97 under the section for representative sampling method 3.1-5 dealing with the reactor building equipment hatch and personnel hatch being in the open position to also include the steam generator replacement access hole.
Under certain wind flow conditions outside air might flow into the reactor building through one open hatch and out the other open hatch. ODCM sampling specification 3.1-5 was established to provide guidance for controlling these hatches (personal and equipment hatches) to minimize the chances of releasing airborne radioactive material. This guidance is not a commitment and is not a required part of the ODCM.
The SG replacement project requires an opening in the Reactor Building that is equivalent to having another hatch opening. This new opening is not practical to control in the same way the personnel and equipment hatches have been controlled in the past. Consequently, the sampling specification is being revised to recognize this new opening and to provide for flexibility in the application of the guideline.
- 2.
Also on page 97 under the section for representative sampling method 3.1-6 dealing with sampling to support the reactor building integrated leak rate test, verbiage was added that describes use of RM-A6 samples prior to pressurizing the RB or use of RM-A1 samples from the previous RB purge permit as long as the source term has not changed.
- 3.
On page I Ithe footnote of table 2-3 for requirements of when the RM-AI automatic isolation function is required was updated to state that this function is not required during periods of "no mode" due to no gas source term being located in the RB during the "no mode" plant condition.
- 4.
On page 140, the direction for station C14H was changed from NW to N as we moved the collection of surface water slightly east to eliminate dilution effects of units CR l&2. Also footnote I was added to the vegetation collection areas to provide an alternate means of collecting required media if adequate vegetation is not available.
The PCP was not revised in 2010.
13
Emergency Feed Pump 2 & Steam Releases Emergency Feed Pump 2 (EFP-2) over-speed testing is performed quarterly using steam from CR-3's steam generators. Due to a historical small primary to secondary leak, an evaluation is normally performed to estimate the quantity of radioactive material which would be released during 2010 due to operation of this pump. In addition, radioactive releases due to other steam releases are normally estimated and included. These values normally include any plant trips with associated secondary plant atmosphere steam relief valve initiation. The results are given below in units of Curies/year.
Due to the extended plant shutdown for refueling outage 16, which began in September of 2009, the plant is still shutdown for the containment building wall repair. The emergency feed pump 2 has not operated and there were no secondary plant steam releases during 2010.
Xe-133 0.OOE+00 1-131 0.00E+00 Cs-137 0.OOE+00 Xe-135 0.OOE+00 1-133 0.00E+00 H-3 0.OOE+00 These values are not included in Tables 1 through 4.
Carbon-14 Evaluation During the entire year of 2010, Crystal River Unit 3 has been in a cold shutdown mode. The plant was taken off line in September of 2009 for refueling outage 16. The plant was degassed, the reactor building was purged of radioactivity, waste gas decay tanks were released, a construction opening was made in the side of the reactor building containment wall, and both once through steam generators were replaced. All of these activities were completed in 2009. Since the plant has been in cold shutdown for the entire year of 2010, there is no source term generation for carbon-14 production in 2010. Once the plant restarts, C-14 source term and resultant dose will be estimated and reported utilizing the EPRI (or similar methodology) model for B&W reactors as discussed in the 2010 C-14 workshop sponsored by EPRI in February of 2011.
14
2010 Appendix I Dose Summary Maximum Hypothetical Individual Liquid Effluent Dose Limits Total Body:
Any Organ:
1.5 mrem/quarter, 3 mremryear 5 mrem/quarter, 10 mrem/year Liquid Effluent Dose Summary Total Body Dose (mrem)
Maximum Organ Dose (mrem)
Maximum Organ was GI Gaseous Effluent Dose Limits Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Total 3.06E-04 1.42E-04 1.88E-04 4.64E-04 1.1OE-03 3.68E-04 5.13E-04 3.35E-04 1.36E-02 1.47E-02 Gamma Air Dose:
Beta Air Dose:
Any Organ:
5 mrad/quarter., 10 mrad/year 10 mrad/quarter, 20 mrad/year 7.5 mrem/quarter, 15 mrem/year Gaseous Release Dose Summary Note: There were no noble gases released in 2010 due to the extended plant shutdown from refueling outage 16 that began in September 2009. The plant is still shutdown in mode 5 in 2011 due to reactor building containment wall repairs.
Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Total Gamma Air Dose (mrad)
Beta Air Dose (mrad)
Total Body Dose (mrem)
Maximum Organ Dose (mrem)
Maximum Organ was Liver 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.99E-04 5.93E-04 6.16E-04 6.18E-04 2.33E-03 4.99E-04 5.93E-03 6.2 1E-04 6.25E-04 2.34E-03 15
Nuclear Electric Institute (NEI) Required Information The following environmental data is being included in this report per objective 2.4.b.i and 2.4.b.ii of NEI 07-07 Industry Ground Water Protection Initiative, as this groundwater well data is used to evaluate groundwater at the site, but is not officially included in the Radiological Environmental Monitoring Program (REMP) or the Offsite Dose Calculation Manual (ODCM).
These 2 graphs are of tritium measurements in units of pCi/l, taken from groundwater monitoring wells located west of CR-3 on either side of the settling ponds.
There are many other groundwater monitoring wells included in the REMP that are used for evaluating the groundwater in the vicinity of the CR-3 site.
These 2 wells are providing supplemental information. The LLD for tritium measurement of these environmental well samples is -150 pCi/l.
16
Tritium Measurements GW Well # MWC-IF2 600 500 1400 200 W,
1000 8OO 1010/06 04128107 11/4107 06101108 12118/08 07/06/09 01122110 0810/10 02126/11 09/14111 Trftlum Measurements GW Well # MWC-27 1400 1200 1000 800 ch.
600 400
__AA_<_D 200 10/10/06 0-4/28107 11/14/07 06/01/08 12118/08 07/06/09 01122110 08110110 02/26/11 09/14111 17
PROGRESS ENERGY FLORIDA, INC.
CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 ATTACHMENT B AMENDED PARTIAL ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2009
AMENDED PARTIAL ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2009 PROGRESS ENERGY FLORIDA, INC CRYSTAL RIVER UNIT 3 Facility Operating License No. DPR-72 Docket No. 50-302 Corrections Prepared as a Supplement to the 2010 Report 18
TABLE 3 EFFLUENT AND WASTE DISPOSAL REPORT - 2009 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 1
3 4
Error%
C.
Fission and activation gases
- 14.
Total release
- 5.
Average release rate for period
- 6.
Percent of technical specification limit D.
- 4.
Total lodine-131 Ci 0.OOE+00 0.OOE+00 30
- 5.
Average release rate for period
ýtCi/sec 0.OOE+00 0.OOE+00
- 6.
Percent of technical specification limit 0.00E+00 0.OOE+00 D.
Particulates*
- 5.
Particulates with half-lives > 8 days Ci 1.10E-06 1.04E-055A 3
- 6.
Average release rate for period iiCi/sec 1.38E-07 1.3 0E-06A
- 7.
Percent of technical specification limit 8.40E-03 1.1 5E-02
- 8.
Gross alpha radioactivity Ci 2.3 1 E-09 1.48E-07 E.
- 4.
Total release
- 5.
Average release rate for period
- 6.
Percent of technical specification limit The sum of the particulates reported on this page may be less ti includes only those with half-lives greater than 8 days.
A Corrected value.
19
TABLE 5 EFFLUENT AND WASTE DISPOSAL REPORT - 2009 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 1
2 Error %
B.
Fission and activation products
- 4.
Total release (not including tritium, gases, alpha)
- 5.
Average diluted concentration during period
- 6.
Percent of applicable limit C.
Tritium 4.
5.
6.
D.
4.
Total release Average diluted concentration during period Percent of applicable limit Dissolved and entrained gases Total release Average diluted concentration during period Percent of applicable limit Gross alpha radioactivity 5.
6.
E.
- 2.
Total release Ci 0.00E+oO O.OOE+Oo 30 F.
Volume of waste released (prior to dilution)
- 2.
Batch and continuous modes Liters 9.58E+06 1.00E+07 10
[
G.
Volume of dilution water used during period
- 2.
Batch and continuous modes Liters 5.31E+llI 5.70E+11 10 A Corrected Value 20
TABLE 6 EFFLUENT AND WASTE DISPOSAL REPORT - 2009 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Fission and activation products Unit Quarter I Quarter 2 Quarter 1 Quarter 2 Sodium-24 Ci Chromnium-SI Ci Manganese-54 Ci Manganese-56 Ci lron-55 Ci 2.33E-04 lron-59 Ci Cobalt-57 Ci Cobalt-58 Ci 9.47E-07 7.22E-07 Cobalt-60 Ci 1.05_______
OE-05 2.10E-05 Zinc-69 Ci Strontium-85 Ci Strontium-89 Ci Strontium-90 Ci Yttrium-9Im Ci Yttrium-92 Ci Yttrium-93 Ci Niobium-95 Ci Niobium-95m Ci Niobium-97 Ci Zirconium-95 Ci Zirconium-97 Ci Molybdinum-99 Ci Technetium-99m Ci Technetium-10 1 Ci Ruthenium-103 Ci Ruthenium-I 06 Ci Silver-I l10m Ci Tin-1 13 Ci Indium-I 13m Ci Antimony-122 Ci Antimony-124 Ci Antimony-125 Ci 7.04E-06 3.11IE-04 Tellurium-I 29 Ci Tellurium-132 Ci Iodine-131 Ci Iodine-I 33 Ci Iodine-135 Ci Cesium-134 Ci Cesium-I 37 CG 4.49E-05 6.79E-05 3.47E-05 Cesium-138 Ci Bariumn-133m Ci I1.67E-06 Barium-140 Ci Lanthanum-140 Ci Cerium-141 Ci Cerium-143 Ci Neodymium-147 Ci Tungsten-] 87 Ci Neptunium--239 Ci Nickle-63 Ci 5.17E-04 4.42E-06 Total for period Ci 4.49E-05 0.OOE+00 8.3 6E-0 4A 3.73E-04 A Corrected value.
21