ULNRC-05140, Annual Radioactive Effluent Release Report

Annual Radioactive Effluent Release Report

ML051890073
Person / Time
Site:	Callaway
Issue date:	06/23/2005
From:	Keith Young AmerenUE
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
FOIA/PA-2010-0209, ULNRC-05140
Download: ML051890073 (10)

Text

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AmerenUE PO Box 620 Cal/away P/ant Fulton, MIO65251 June 23, 2005 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 Ladies and Gentlemen: ULNRC-05164 DOCKET NUMBER 50483 CALLAWAY PLANT UNIT 1 WAmeren UNION ELECTRIC CO.

FACILITY OPERATING LICENSE NPF-30 IIE 2004 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

Reference:

ULNRC-05140, dated April 29, 2005 Please find enclosed a revision of the referenced 2004 Annual Radioactive Effluent Release Report for the Callaway Plant. Revised are Tables IA and IB for the first and second Quarters of 2004. Tables 5, 6, 7, and section 6 were also revised.

The revisions were made following discovery of a discrepancy with Auxiliary Boiler Release Permit UR03-2004-G0036;2. The revisions are provided as attachments to this letter. These documents are submitted in accordance with Sections 5.6.3 and 5.5.1 of the Technical Specifications.

Very truly yours, Manager, Regulatory Affairs DJW/jdg Attachments: 1. Table lA, Semiannual Summation of Gaseous Releases, All Airborne Effluents 1st and 2 nd Quarter 2004

2. Table IB, Semiannual Airborne Continuous and Batch Releases, Ground Level Releases 1st and 2nd Quarter 2004

3. Table 5, Dose at the Site Boundary and to the Nearest Resident from Gaseous Effluents

4. Table 6, Dose to the Member of the Public from Activities within the Site Boundary

5. Table 7, Total Dose Due to the Uranium Fuel Cycle (Member of the Public)

6. Section 6, Related Information - Unplanned Releases '-- tu;j, i16 7 L--

a subsidiary of Ameren Corporation

ULNRC-05164 June 23, 2005 Page 2 cc: U.S. Nuclear Regulatory Commission (Original and I copy)

Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 Mr. Bruce S. Mallett Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Jack N. Donohew (2 copies)

Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 7E1 Washington, DC 20555-2738 Manager, Electric Department Missouri Public Service Commission PO Box 360 Jefferson City, MO 65102-0360 Mr. Bob Oliveira ANI Account Engineer 95 Glastonbury Glastonbury, CT 06033 Regional Administrator Department of Natural Resources Central Regional Office P.O. Box 176 Jefferson City, MO 65102-0176

Table IA Semiannual Summation of Gaseous Releases All Airborne Effluents TABLE IA SEMIANNUAL SUMMATION OF GASEOUS RELEASES ALL AIRBORNE EFFLUENTS QUARTERS 1 AND 2.2004 FIRST SECOND ESTTOTAL TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a)

A. FISSION AND ACTIVATION GASES

1. TOTAL RELEASE l CURIES 3.01E+02 4.72E+02 I Z20 1

2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 3.83E+01 6.01E+01

3. PERCENT OF TECH SPEC LIMiT  % N/A N/A B. RADIOIODINES 1.TOTAL IODINE-131 CURIES 6.40E-O5 2.30&03 l I 23

2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC l 8.14E-06 2.93E-04 l

3. PERCENT OF TECH SPEC LIMIT l  % N/A N/A 1 C. PARTICULATES

1. PARTICULATE (HALF-LIVES > 8 DAYS) CURIES 1.29E-04 6.32E-05 30 2.AVERAGE RELEASE RATE FOR PERIOD UC_/SEC 1.64ES 8.03E-06

3. PERCENT OF TECH SPEC LIMFT  % N/A N/A

4. GROSS ALPHA RADIOACTIVITY CURIES 4.71E-07 4.1 1E-07 D. TRITIUM I1. TOTAL RELEASE CURIES 6.09E+O0 1.31E+01 14

12. AVERAGE RELEASE RATE FOR PERIOD I UCi/SEC I 7.75E.01 I 1.66E+O0 I

13. PERCENT OF TECH SPEC LIMIT I IN/A IN/A (a) Safety Analysis Calculation 87-063-00, January 6. 1988 Page 1 of 1 18

Table IB Semiannual Airborne Continuous and Batch Releases, Ground Level Releases TABLE IB SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES. IODINES, AND PARTICULATES QUARTERS 1 AND 2,2004 I CONTINUOUS RELEASES I BATCH RELEASES I FIRST SECOND FIRST SECOND NUCLIDE I UNITS _ QUARTER -QER QUA RT RER lQUARTER

1. FISSION GASES AR-41 CURIES O.OOE+00 O.OOE+00 6.621-02 . 1.17E-01 XE-133 CURIES 2.77E+02 4.42E+02 2.09E-01 1.53E+01 XE-135 CURIES 1.08E+01 5.25E+00 1.47E-03 4.52E-02 KR-85M CURlES 2.89E+00 4.71 E-01 0.00E+O0 2.76E-03 XE-135M CURIES 0.001E+00 3.76E-01 2.63E-06 0.00E+00 KR-87 CURIES 9.03E-01 1.04E-01 0.00EtO0 0.00E+00 XE-131M CURIES 1.60E+00 1.71 E+00 1.16E-03 1.15SE-01 XE-133M CURIES 2.54E+00 5.25E+00 9.20E-04 4.54E-02 KR-88 CURIES 3A2E+00 4.54E-01 0.OOE+00 1.43E-02 KR-85 CURIES 0.OOE+00 Q.OOE+00 2.10E+00 3.26E-01 XE-138 CURIES 0.00E+00 2.06E-01 O.00E.+00 O.OOE+00 TOTAL FOR PERIOD CURIES 2.99E+02 4.56E+02 2.38E+00 1.59E+01

2. IODINES I-133 CURIES 0.00E+00 1.86E-05 2.17E-05 9.16E-06 1-131 CURIES 5.30E-06 1.15E-03 5.87E-05 1.15E-03 1-132 CURIES O.OOE+00 1.04E-05 5.7 1E-06 1.2 1E-04 1-135 CURIES O.OOE+00 0.00E+00 4.66E-06 O.OOE+00 TOTAL FOR PERIOD CURIES 5.30E-06 1.18E-03 9.08E-05 1.28E-03

3. PARTICULATES CS-137 CURIES 1.05E-06 2.99E-07 1.62E-05 3.86E-06 SB-125 CURIES 2.61E-06 5.54E-07 0.00E+00 0.00E+W0 BA-140 CURIES 0.OOE+00 Q00EE+00 5.13E-07 3.57E-07 CS-134 CURIES 0.00E+00 0.OOE+00 2.44E-05 1.26E-05 CS-136 CURIES 0.OOE+00 0.00E+00 2.61E-06 5.64E-07 NA-24 CURIES 0.00E+00 O.OOE+00 4.30E-08 0.00E+00 CO-S8 CURIES O.OOE+00 5.58E-06 2.55E-07 3.79E-06 CO-60 CURIES 4.67E-07 0.OOE+00 8.07E-05 3.36E-05 NB-95 CURIES 0.00E+00 O.OOE+00 0.OOE+00 4.25E-07 CR-S1 CURIES 0.00E+00 O.OOE+00 0.00E+00 ISIE-06 ALPHA CURIES 4.7 1E-07 4.1 IE-07 0.OOE+00 Q.OOE+00 TOTAL FOR PERIOD CURIES 4.60E-06 6.84E-06 125E-04 5.67E-05 Page 1 of 2 20

Table 1B Semiannual Airborne Continuous and Batch Releases, Ground Level Releases Fission Gases, lodines, and Particulates TABLE lB (continued)

SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES

-GROUND LEVEL RELEASES FISSION GASES. IODINES. AND PARTJCULATES QUARTERS I AND 2.2004 CONTINUOUS RELEASES BATCH RELEASES FIRST SECOND FIRST SECOND INUCLIDE IUNITS QUARTER IQUARTER QUARTER QUARTER

4. TRITIUM

[H-3 ICURIES I6.OOE+00 L1201E-01O I 8.6013-02 I .02E,+W=

Page 2 of 2 21

Table 5 Dose at the Site Boundary and to the Nearest Resident From Gaseous Effluents Table 5 DOSEATTHE SITE BOUNDARYAND TO THE NEAREST RESIDENT FROM GASEOUS EFFLUENTS SITE BOUNDARY I NEAREST RESIDENT LOCATION

2.20 km NNW I LOCATION: 2.90 km NNW A d-VO rDe II. 1Ig11 r% I AGE GROUP: CHILD ORGAN UNITS DOSE  % LIMIT (a) l DOSE  % LIMIT (b)

GAMMAAIR DOSE* MRAD 1.29E-02 0.13 8.50E-03 NfA BETAAIR DOSE

• MRAD 3.03E-02 0.15 1.99E-02 N/A WHOLE BODY ** MREM 1.17E-02 N/A 7.69E-03 N/A SKIN *** MREM 2.50E-02 N/A 1.65E-02 N/A BONE MREM 4.86E-04 N/A 1.73E-03 0.01 LIVER ** MREM 1.75E-03 N/A 9.33E-03 0.06 TOTAL BODY' MREM 1.75E-03 N/A 8.25E-03 0.05 THYROID MREM 2.90E-03 N/A 2.23E-01 1.49 KIDNEY ** MREM 1.75E-03 N/A 9.06E-03 0.06 LUNG ** MREM 1.78E-03 N/A 7.81 E-03 0.05 GI-LLI MREM 1.75E-03 N/A 7.77E-03 0.05

• Dose from Noble Gases only.

• • Dose from Tritium, Radioiodines, and Particulates only.

• • • Dose from Noble Gases plus Ground Plane dose.

(a) Annual dose limits of Offsite Dose Calculation Manual (APA-ZZ-01003) of 10 mrad gamma air dose and 20 mrad beta air dose.

(b) Annual dose limits of Offsite Dose Calculation Manual (APA-ZZ-01003) of 15 mrem to any organ from 1-131,1-133, H-3, and particulate radionuclides with half-lives greater than 8 days.

Table 6 Dose to the Member of the Public From Activities within the Site Boundary Table 6 DOSE TO THE MEMBER OF THE PUBLIC FROM ACTIVITIES WITHIN THE SITE BOUNDARY (MEMBER OF THE PUBLIC)

EFFLUENT DIRECT DIRECT DIRECT EFFLUENT TOTAL DOSE WITHIN RADIATION RADIATION RADIATION DOSE DOSE THE SITE FROM THE FROM OUTSIDE FROM RAM FROM FOR THE ORGAN UNITS BOUNDARY UNiT TANKS STORAGE - CLG. TWR YEAR SKIN lMREM 5.80E-03 N/A N/A N/A N/A 5.80E-03 BONE MREM 1.41 E-04 8.79E-03 1.36E-03 1.82E-03 N/A 1.21 E-02 LIVER MREM 5.05E-04 8.79E-03 1.36E-03 1.82E-03 2.08E-05 1.25E-02 TOTAL BODY MREM 3.15E-03 8.79E-03 1.36E-03 1.82E-03 2.08E-05 1.51 E-02 THYROID. MREM 7.19E-04 8.79E-03 1.36E-03 1.82E-03 2.08E-05 1.27E-02 KIDNEY MREM 5.05E-04 8.79E-03 1.36E-03 1.82E-03 2.08E-05 1.25E-02 LUNG MREM 5.l0E-04 8.79E-03 1.36E-03 1.82E-03 2.08E-05 1.25E-02 GI-LLU MREM 5.04E-04 8.79E-03 1.36E-03 1.82E-03 2.08E-05 1.25E-02 46

Table 7 Total Dose Due to the Uranium Fuel Cycle (Member of the Public)

Table 7 TOTAL DOSE DUE TO THE URANIUM FUEL CYCLE (MEMBER OF THE PUBLIC)

EFFLUENT DOSE FROM DOSE FROM TOTAL DOSE DOSEATTHE ACTIVITIES CLG TWR H-3 TO THE RESIDENCE WITHIN SITE AT NEAREST MEMBER OF UNITS LOCATION BOUNDARY RESIDENCE THE PUBLIC  % LIMITS -

SKIN MREM 1.62E-02 5.80E-03 N/A 2.20E-02 0.09 l BONE MREM 6.61E-04 1.21E-02 N/A 1.28E-02 0.05 LIVER MREM 5.38E-03 1.25E-02 1.42E-05 A1.7E-02 1 0.07 TOTALBODY MREM 1.26E-02 1.51 E-02 1.42E-05 2.77E-02 0.11 THYROID MREM 7.98E-02 I 1.27E-02 1.42E-05 9.25E-02 0.12 KIDNEY MREM 5.30E-03 I1.25E-02 1.42E-05 1.78E-02 0.07 LUNG MREM 4.85E-03 1.25E-02 1.42E-05 1.73E-02 0.07 GI-LLI MREM 4.92E-03 1.25E-021 1.42E-05 1.74E-02 0.07

'Annual dose limits from 40CFR190.1 0(a) of 25 mrem whole body, 75 mrem to the thyroid, and 25 mrem to any other organ.

47

5.0 Solid Wastes 5.0 Solid Wastes The quantities of radioactive material released of each nuclide listed in Table 3 was determined in shipments of solid waste for burial and as the product of the fractional abundance and the irradiated fuel transported from the site during the total curies shipped. Those nuclides which year are summarized in Table 3. The total quantity comprise at least 1% of the total activity for a and radioactivity reported in Table 3 for each particular waste type are presented in Table 3.

waste type was forwaste buried and includes wastes buried by waste reprocesses after volume reduction. The activity and fractional abundance of each nuclide was determined for each waste type based upon radiochemical analysis by an independent laboratory. The curie concentration 6.0 Related Ini ormation 6.1 Unplanned Releases of contamination leached from the sludge and were detected in the boiler water.

Unplanned releases are:

An investigation was performed to locate the

1) Inadvertent or accidental source of the contamination. No miss-positioned releases of radioactive material. valves or leaks were identified. The results of

2) Releases of radioactive material sampling different system components were via normal pathways without a inconclusive, but may indicate a small leak in the release permit, proper. SLWE heat exchanger. During refueling authorization, or proper sampling operations, the concentration of radioactive and analysis. nuclides in the SLWE system can be a factor of

3) Releases which are conducted in 1000 times higherthan normal operations. The such a manner as to result in size of the leak may be small enough to only be significant deviation from the recognized when these high concentrations are requirements of the release present. Increased monitoring was initiated in an permit. attempt to identify the source of the contamination.

No additional contamination was identified.

Auxiliary Boiler Contamination A I OCFR50.59 evaluation concluded that the resulting dose to a Member of the Public from the On April 10, 1998, during a refueling outage, release of radioactive material to the radioactivity was detected in the Auxiliary Boiler feed watersystem. The boilerwas flushed and environment would be a small fraction of the cleaned several times in an attempt to regulatory dose limits. Therefore, continued operation of the Auxiliary Boiler would not pose decontaminate the unit. Small amounts of any significant safety or environmental concern.

contamination remained in the sludge. During subsequent operation of the boiler small amounts 7

6.0 Related Information 6.0The Auxiliary Boiler was operated Related Information To prevent reoccurence, Radiation Protection II II intrritantv EllIML I II LILy

~lInn

%A%AI II it AneThmnm:vim iom tnfl s T I I Il AI #"^II I IIl~AILal procedures were revised to provide a continuously Ibody dose to a Member of the Public from these open Auxiliary Boiler release permit to allow the Ireleases was 4.85E-05 mrem during 2004. This Callaway Operations staff increased operating iis negligible compared to the quarterly and flexibility.

annual effluent control limits. The total activity Ireleased from the Auxiliary Boiler in 2004 was Antimony-122 In Liquid Effluents 1.04E-01 Curies.

Antimony-1 22 (Sb-1 22) was discovered in IContainment Equipment Hatch liquid effluent release permits during Health Physicist review (CAR 200409000). Sb-122 was initially discovered in reactor coolant samples and Air samples taken outside of the Containment added to the effluent release library based on the Equipment hatch during RF012 indicated comparison. After the radionuclide was added to Ireactor produced isotopes (CAR 200207059).

the release library, an interference with Cs-134 at Releases of radioactivity from the IContainment Equipment hatch in 2004 (RFO1 3) the 564 keV energy was noticed. All of the liquid Iwere quantified and are included in this report. release permits from 2004 were evaluated for Sb-I 122. The evaluation revealed 10 batch liquid The total amount of activity released from the release permits where Sb-1 22 was present. The Containment Equipment hatch was affected release permits were revised to account approximately 13.9 Curies, primarily consisting Iof Noble gases.

for Sb-122.

Sb-1 22 was also added to Table 2.1, Ingestion The maximum total body dose to a Member of Dose Commitment Factor (A.) forAdultAge the Public from these releases was 2.65E-04 Group, ofAPA-ZZ-01 003, Callaway ODCM. The mrem during 2004. This is negligible compared to the quarterly and annual effluent control limits. total amount of Sb-1 22 activity released in liquid effluents was 1.29E-03 Curies. The dose from The activity released from the Containment Sb-1 22 was well below 1% of the total dose from Equipment hatch during 2004 is included in Tables 1A, 1B, 5,6, and 7. liquid effluents in 2004.

Auxiliary Boiler Operated w/o Release Permit 'A' Mixed Bed Demineralizer Flush On 4/6/04, the control room commenced On 1/27/04, the Auxiliary Boiler was started a flush of 'A' Mixed Bed Demineralizer in prior to release permit generation (CAR accordance with plant procedures. Shortly 200400644). Control room procedures require after the flush began, the Auxiliary Building release permit generation prior to operation. ventilation exhaust particulate monitorr GL-Approximately 30 minutes after operation began, RE-60 alarmed in the control room (CAR the Count Room technicians were notified and a 200402553). Trends on GL-RE-60 release permit was generated. The total activity indicated a step increase in activity. As a released during this release was 1.82E-03 Curies result of the alarm, the control room decided and the Total Body dose to a Member of the Public: to secure the flush of 'A' Mixed Bed was 3.28E-07 mrem. As expected, the activity Demineralizer.

and dose from this release was well below regulatory limits.

8