ML22055A547
ML22055A547 | |
Person / Time | |
---|---|
Site: | BWX Technologies |
Issue date: | 02/18/2022 |
From: | Freudenberger R BWXT |
To: | Office of Nuclear Material Safety and Safeguards |
References | |
22-010 | |
Download: ML22055A547 (9) | |
Text
BWX Technologies, Inc.
February 18, 2022 22-010
ATTN: Document Control Desk Director, Office of Nuclear Material Safety & Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Reference:
License No. SNM-42, Docket 70-27
Subject:
Semi-Annual Effluent Monitoring Report
Dear Sir or Madam:
The Semi-Annual Effluent Report for the BWXT Nuclear Operations Group, Inc., Lynchburg (NOG-L) facility covering the second semi-annual effluent monitoring period for 2021 is enclosed. This report is being submitted in accordance with the requirements of 10 CFR 70.59.
If you have questions or require additional information, please* contact Chris Terry, Manager of Licensing and Safety Analysis, at ctterry@bwxt.com or 434-522-5202.
Sincerely,
,-,u... Jf1-~
Richard J. Freudenberger Manager, Environment, Safety, Health & Safeguards BWXT Nuclear Operations Group, Inc. - Lynchburg
Enclosure
cc: NRC, Region II NRC, Resident Inspector
BWXT Nuclear Operations Group, Inc. People Strong
P.O. Box 785 Lynchburg, VA 24505 USA INNOVATION DRIVEN >
t: +1.434.522.6000 www.bwxt.com ENCLOSURE
7 pages
BWXT Nuclear Operations Group, Inc. People Strong
P.O. Box 785 Lynchburg, VA 24505 USA INNOVATION DRIVEN >
t: +1.434.522.6000 www.bwxt.com L GASEOUS EFFLUENTS (Continuously Sampled Stacks)
Reporting Period: 6/29/21 to 1/02/22 (Weeks Ending 7/04/21 to 1/02/22)
Stack: WASTE MGMT CENTER (# 39)
Average Flow Rate: 1.33 cubic meters/second
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml) (µCi/ml) (µCi/ml) (µCi) (mrem)
U-234 (S) <l.0E-14 <l.0E-14. <l.0E-14 2.0E-02 l.lE-05
Stack: 2A STACK (# 23)
Average Flow Rate: 0.97 cubic meters/second
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml) (µCi/ml) (µCi/ml) (µCi) (mrem)
U-234 (S) 4.0E-14 l.0E-14 3.0E-14 5.7E-0l 3.lE-04
Stack: 2A PRODUCTION SUPPORT (# 44)
Average Flow Rate: 1.02 cubic meters/second
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml) (µCi/ml) (µCi/ml) (µCi) (mrem)
U-234 (S) <l.0E-14 <l.0E-14 <l.0E-14 3.0E-02 l.6E-05
Stack: IA MAINTENANCE (# 43)
Average Flow Rate: 5.12 cubic meters/second
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml) (µCi/ml) (µCi/ml) (µCi) (mrem)
U-234 (S) <l.0E-14 <l.0E-14 <l.0E-14 l.SE-01 3.4E-04
Page 1 I. GASEOUS EFFLUENTS (Continuously Sampled Stacks)
Reporting Period: 6/29/21 to 1/02/22 (Weeks Ending 7/04/21 to 1/02/22)
Stack: 3A PHARMACY (# 24)
Average Flow Rate: 1.23 cubic meters/second
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml) (µCi/ml) (µCi/ml) (µCi) (rnrem)
U-234 (S) lE-14 <l.0E-14 <1.0E-14 l.3E-01 7.0E-05
Stack: Bay 17 (# 42)
Average Flow Rate: 0.83 cubic meters/second
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml) (µCi/ml) (µCi/ml) (µCi) (rnrem)
U-234 (S) <l.0E-14 <l.0E-14 <1.0E-14 6.0E-02 6.2E-05
Stack: MET LAB (# 26)
Average Flow Rate: 4.77 cubic meters/second
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml) (µCi/ml) (µCi/ml) (µCi) (rnrem)
U-234 (S) lE-14 <l.0E-14 <1.0E-14 4.0E-01 2.lE-04
Stack: U-MOL (# 45)
Average Flow Rate: 5.49 cubic meters/second
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml) (µCi/ml) (µCi/ml) (µCi) (rnrem)
U-234 (S) <l.0E-14 <l.0E-14 <1.0E-14 1.3E-01 6.3E-05
Page 2 I. GASEOUS EFFLUENTS (Continuously Sampled Stacks)
Reporting Period: 6/29/21 to 1/02/22 (Weeks Ending 7/04/21 to 1/02/22)
Stack: RTRT (# 1_6)
Average Flow Rate: 6.79 cubic meters/second
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml) (µCi/ml) (µCi/ml) (µCi) (mrem)
U-234 (S) l.0E-14 <l.0E-14 <l.0E-14 8.lE-01 3.9E-04
Stack: SFF ( # 11)
Average Flow Rate: 9.05 cubic meters/second
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml) (µCi/ml) (µCi/ml) (µCi) (mrem)
U-234 (S) l.2E-14 <l.0E-14 1.0E-14 l.2E+00 7.4E-04
Stack: 13A/14A/15A DRY (# 38)
Average Flow Rate: 16.15 cubic meters/second
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml) (µCi/ml) (µCi/ml) (µCi) (mrem)
U-234 (S) l.0E-14 l.0E-14 2.0E-14 3.6E+00 2.lE-03
Stack: CHEM LAB SCRUBBER (# 37)
Average Flow Rate: 11.06 cubic meters/second
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml) (µCi/ml) (µCi/ml) (µCi) (mrem)
U-234 (S) l.0E-14 <l.0E-14 1.00E-14 1.4E+00 8.0E-04
Stack: 14A MAINTENANCE (# 35)
Average Flow Rate: 2.86 cubic meters/second
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml) (µCi/ml) (µCi/ml) (µCi) (mrem)
U-234 (S) l.0E-14 l.0E-14 2.0E-14 5.7E-01 3.4E-04
Page 3 I. GASEOUS EFFLUENTS (Continuously Sampled Stacks)
Reporting Period: 6/29/21 to 1/02/22 (Weeks Ending 7/04/21 to 1/02/22)
Stack: RECOVERY (# 15)
Average Flow Rate: 10.17 cubic meters/second
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml) (µCi/ml) (µCi/ml) (µCi) I (mrem)
U-234 (F) 2.20E-13 3.00E-14 8.00E-14 3.61E+0l 2.40E-04
Stack: LAUNDRY STACK (# 30)
Average Flow Rate: 2.74 cubic meters/second
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml) (µCi/ml) (µCi/ml) (µCi) (mrem)
U-234 (S) 6.0E-14 l.0E-14 2.0E-14 2.7E+O0 l.8E-03
Stack: COMPACTOR (# 32)
Average Flow Rate: 1.55 cubic meters/second
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml) (µCi/ml) (µCi/ml) (µCi) (mrem)
U-234 (S) <l.0E-14 <1.0E-14 <1.0E-14 6.0E-02 3.9E-05
Stack: RETENTION TANKS (# 36)
Average Flow Rate: 0.52 cubic meters/second
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml) (µCi/ml) (µCi/ml) (µCi) (mrem)
U-234 (S) <l.0E-14 <l.0E-14 <l.0E-14 3.0E-02 l.9E-05
Stack: WT SCRUBBER (# 31)
Average Flow Rate: 1.17 cubic meters/second
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml) (µCi/ml) (µCi/ml) (µCi) (mrem)
U-234 (S) 4.20E-13 2.00E-14 3.00E-14 8.00E+00 4.90E-03
Page 4 I. GASEOUS EFFLUENTS (Continuously Sampled Stacks)
Reporting Period: 6/29/21 to 1/02/22 (Weeks Ending 7/04/21 to 1/02/22)
Stack: DECON (# 33)
Average Flow Rate: 2.42 cubic meters/second
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml) (µCi/ml) (µCi/ml) (µCi) (mrem)
U-234 (S) <l.0E-14 <l.0E-14 <l.0E-14 2.0E-01 l.3E-04
Stack: LTC 50 METER STACK Average Flow Rate: 16.80 cubic meters/second
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml) (µCi/ml) (µCi/ml) (µCi) (mrem)
Ni-59 <l.00E-14 <l.00E-14 <l.00E-14 4.03E-01 6.30E-07 Tc-99 <l.00E-14 <l.00E-14 <l.00E-14 l.32E-01
Stack: LTC ACL STACK Average Flow Rate: 1.48 cubic meters/second
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml). (µCi/ml) (µCi/ml) (µCi) (mrem)
ND 0.00E+O0 0.00E+00 0.00E+00 0.00E+00 0.0OE+00
Stack: LTC RCL STACK 1.67 cubic meters/second Average Flow Rate:
Quantity Off-Site Concentration Error Estimate MDC Released Dose Radionuclide (µCi/ml) (µCi/ml) (µCi/ml) (µCi) (mrem)
U-234 <l.00E-14 <l.00E-14 l.00E-14 1.60E-02 4.S0E-05 U-235 <l.00E-14 <l.00E-14 l.00E-14 l.60E-02 *Note U-238 <l.00E-14 <l.00E-14 l.00E-14 l.21E-02 Th-228 <l.00E-14 <l.00E-14 l.00E-14 l.29E-02
Page 5 I. GASEOUS EFFLUENTS (Continuously Sampled Stacks)
Reporting Period: 6/29/21 to 1/02/22 (Weeks Ending 7/04/21 to 1/02/22)
NOTES:
(1) The total exposure from all stacks is 1.2E-2 mrem. Doses were.determined using the EPA COMPLY code. Actual stack and building heights were used. A distance from source to receptor of 540 meters was used, with wind blowing towards the receptor at a speed of2 meters/sec, 25% of the time. Other default parameters such as temperature were used if prompted. Comply itself is conservative.
(2) All alpha activity is conservatively reported as U-234 for the NOG-L Stacks as this is the predominant uranium nuclide and has the most conservative dose conversion factor of the various uranium isotopes. No nuclides other than Uranium were found in the NOG-L Stack Semi Annual Composite Samples. For the LTC Stacks each nuclide above MDC is reported.
(3) Beta/Gamma nuclides are not reported unless they exceed the respective MDC based on isotopic analysis.
(4) Average concentrations, errors and MDCs are quoted as lE-14 µCi/ml for stacks when these values are between 5E-15 µCi/ml and lE-14
µCi/ml, and they are quoted as <lE-14 µCi/ml when the values are less than 5E-15 µCi/ml.
(5) Activities are quoted as lE-02 µCi when these values are between 5E-03 µCi and lE-02 µCi, and they are quoted as <lE-02 µCi when the values are less than 5E-03 µCi. 5E-03 µCi is conservatively used to calculate the offsite dose when the activity is <lE-02 µCi.
(6) The error estimate is the daily error at the 95% confidence interval propagated over the six month period.
(7) Quantity released (µCi) is the sum of the activities calculated daily based on the calculated daily concentration for all concentrations> 0.
(8) Twenty two (22) stacks were monitored during this monitoring period.
(9) Average concentrations, errors and MDCs are quoted to one significant digit except for the Recovery, Waste Treatment, and three LTC stacks.
Page 6
II. LIQUID EFFLUENT
A Reporting Period: 07/01/21 to 12/31/21
B. Location of Sample: Collection Prior to Discharge into the James River.
C. Total Liquid Flow: 2.95E+08 liters
D. Sample Collection: Batch composite sampler.
Quantity Radionuclide Concentration Error Estimate MDC Released Total Dose (pCi/1) (+/-pCi/1) (pCi/1) (µCi) (mrem)
U-234 1.51E+0l 3.35E+00 1.70E-0l 4,465.06 4.91E-02 U-235 3.IOE-01 4.00E-01 l.S0E-01 91.75 9.47E-04 U-236 l.20E-01 2.S0E-01 l.40E-0l 34.79 3.63E-04 U-238 1.S0E-01 3.00E-01 l.40E-0l 52.89 5.23E-04
Total 5.09E-02 NOTES:
(1) The total dose calculated for liquid release uses a dilution factor of 18:1. Regulatory Guide 1.109 was used as guidance, with conservative assumptions to estimate the exposure.
(2) The semi-annual concentration reported above is a volume-weighted average for the six months and may be less than the averaged MDC for the same period.
(3) Isotopic analysis is performed on the monthly composite samples for the most commonly utilized beta/gamma nuclides such as Sr-90, Tc-99 and Cs-137.
The analysis of these nuclides typically indicates results less than minimum detectable concentration (MDC). No nuclide with a concentration above the respective MDC was reported.
Page 7