ULNRC-05140, Annual Radioactive Effluent Release Report

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Annual Radioactive Effluent Release Report
ML051890073
Person / Time
Site: Callaway Ameren icon.png
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)
v • d • e


Text

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AmerenUE Cal/away P/ant PO Box 620 Fulton, MIO 65251 June 23, 2005 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 WAmerenIIE Ladies and Gentlemen:

ULNRC-05164 DOCKET NUMBER 50483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.

FACILITY OPERATING LICENSE NPF-30 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 2nd Quarter 2004

2.

Table IB, Semiannual Airborne Continuous and Batch Releases, Ground Level Releases 1 st 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

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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

23 I

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 A

d-VO rDe II.

1Ig11 r%

I ORGAN UNITS DOSE

% LIMIT (a) l GAMMAAIR DOSE*

MRAD 1.29E-02 0.13 BETAAIR DOSE

  • MRAD 3.03E-02 0.15 WHOLE BODY **

MREM 1.17E-02 N/A SKIN ***

MREM 2.50E-02 N/A BONE MREM 4.86E-04 N/A LIVER **

MREM 1.75E-03 N/A TOTAL BODY' MREM 1.75E-03 N/A THYROID MREM 2.90E-03 N/A KIDNEY **

MREM 1.75E-03 N/A LUNG **

MREM 1.78E-03 N/A GI-LLI MREM 1.75E-03 N/A LOCATION: 2.90 km NNW AGE GROUP: CHILD DOSE

% LIMIT (b) 8.50E-03 NfA 1.99E-02 N/A 7.69E-03 N/A 1.65E-02 N/A 1.73E-03 0.01 9.33E-03 0.06 8.25E-03 0.05 2.23E-01 1.49 9.06E-03 0.06 7.81 E-03 0.05 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 DOSEATTHE RESIDENCE UNITS LOCATION DOSE FROM ACTIVITIES WITHIN SITE BOUNDARY DOSE FROM CLG TWR H-3 AT NEAREST RESIDENCE TOTAL DOSE TO THE MEMBER OF 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 in shipments of solid waste for burial and irradiated fuel transported from the site during the year are summarized in Table 3. The total quantity and radioactivity reported in Table 3 for each 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 of each nuclide listed in Table 3 was determined as the product of the fractional abundance and the total curies shipped. Those nuclides which comprise at least 1% of the total activity for a particular waste type are presented in Table 3.

ormation 6.1 Unplanned Releases Unplanned releases are:

1) Inadvertent or accidental releases of radioactive material.
2) Releases of radioactive material via normal pathways without a release permit, proper.

authorization, or proper sampling and analysis.

3) Releases which are conducted in such a manner as to result in significant deviation from the requirements of the release permit.

Auxiliary Boiler Contamination On April 10, 1998, during a refueling outage, radioactivity was detected in the Auxiliary Boiler feed watersystem. The boilerwas flushed and cleaned several times in an attempt to decontaminate the unit. Small amounts of contamination remained in the sludge. During subsequent operation of the boiler small amounts of contamination leached from the sludge and were detected in the boiler water.

An investigation was performed to locate the source of the contamination. No miss-positioned valves or leaks were identified. The results of sampling different system components were inconclusive, but may indicate a small leak in the SLWE heat exchanger. During refueling operations, the concentration of radioactive nuclides in the SLWE system can be a factor of 1000 times higherthan normal operations. The size of the leak may be small enough to only be recognized when these high concentrations are present. Increased monitoring was initiated in an attempt to identify the source of the contamination.

No additional contamination was identified.

A I OCFR50.59 evaluation concluded that the resulting dose to a Member of the Public from the release of radioactive material to the environment would be a small fraction of the regulatory dose limits. Therefore, continued operation of the Auxiliary Boiler would not pose any significant safety or environmental concern.

7

6.0 Related Information 6.0 Related Information The Auxiliary Boiler was operated intrritantv ~lInn AneThmn m:vim iom tnfl I

I i

I I

I I

I I

I II II El lIML I II LILy

%A %AI II it s

T I I Il AI #"^II I

l~AI II Lal body dose to a Member of the Public from these releases was 4.85E-05 mrem during 2004. This is negligible compared to the quarterly and annual effluent control limits. The total activity released from the Auxiliary Boiler in 2004 was 1.04E-01 Curies.

Containment Equipment Hatch Air samples taken outside of the Containment Equipment hatch during RF012 indicated reactor produced isotopes (CAR 200207059).

Releases of radioactivity from the Containment Equipment hatch in 2004 (RFO1 3) were quantified and are included in this report.

The total amount of activity released from the Containment Equipment hatch was approximately 13.9 Curies, primarily consisting of Noble gases.

The maximum total body dose to a Member of the Public from these releases was 2.65E-04 mrem during 2004. This is negligible compared to the quarterly and annual effluent control limits.

The activity released from the Containment Equipment hatch during 2004 is included in Tables 1A, 1B, 5,6, and 7.

Auxiliary Boiler Operated w/o Release Permit On 1/27/04, the Auxiliary Boiler was started prior to release permit generation (CAR 200400644). Control room procedures require release permit generation prior to operation.

Approximately 30 minutes after operation began, the Count Room technicians were notified and a release permit was generated. The total activity released during this release was 1.82E-03 Curies and the Total Body dose to a Member of the Public:

was 3.28E-07 mrem. As expected, the activity and dose from this release was well below regulatory limits.

To prevent reoccurence, Radiation Protection procedures were revised to provide a continuously open Auxiliary Boiler release permit to allow the Callaway Operations staff increased operating flexibility.

Antimony-122 In Liquid Effluents Antimony-1 22 (Sb-1 22) was discovered in liquid effluent release permits during Health Physicist review (CAR 200409000). Sb-122 was initially discovered in reactor coolant samples and added to the effluent release library based on the comparison. After the radionuclide was added to the release library, an interference with Cs-134 at the 564 keV energy was noticed. All of the liquid release permits from 2004 were evaluated for Sb-122. The evaluation revealed 10 batch liquid release permits where Sb-1 22 was present. The affected release permits were revised to account for Sb-122.

Sb-1 22 was also added to Table 2.1, Ingestion Dose Commitment Factor (A.) forAdultAge Group, ofAPA-ZZ-01 003, Callaway ODCM. The total amount of Sb-1 22 activity released in liquid effluents was 1.29E-03 Curies. The dose from Sb-1 22 was well below 1 % of the total dose from liquid effluents in 2004.

'A' Mixed Bed Demineralizer Flush On 4/6/04, the control room commenced a flush of 'A' Mixed Bed Demineralizer in accordance with plant procedures. Shortly after the flush began, the Auxiliary Building ventilation exhaust particulate monitorr GL-RE-60 alarmed in the control room (CAR 200402553). Trends on GL-RE-60 indicated a step increase in activity. As a result of the alarm, the control room decided to secure the flush of 'A' Mixed Bed Demineralizer.

8

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