ML023020340
| ML023020340 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 10/17/2002 |
| From: | St.Pierre G North Atlantic Energy Service Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NYN-02067 | |
| Download: ML023020340 (23) | |
Text
North Atlantic Energy Service Corporation "P.O. Box 300 Nort Seabrook, NH 03874 Atlantic (603) 474-9521 The Northeast Utihties System October 17, 2002 Docket No. 50-443 NYN-02067 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Seabrook Station Correction to Annual Radioactive Effluent Release Report Letters In a letter dated April 30, 2002 (NYN-02043), North Atlantic Energy Service Corporation (North Atlantic) submitted the Annual 'Radioactive Effluent Release Report.
A subsequent North Atlantic review of the calculation supporting the letter identified a minor error in Enclosure 3, Radiation Dose Assessment, Page 8, Table A, "Maximum Offsite Doses and Dose Commitments to Members of the Public." Enclosure 1 provides a copy of the originally submitted pages with the incorrect information annotated. Revised pages are provided in Enclosure 2.
In letters dated April 27, 2000 (NYN-00037), April 27, 2001 (NYN-01038), and April 30, 2002 (NYN-02043), North Atlantic submitted the Annual Radioactive Effluent Release Reports for the years 1999, 2000, and 2001. During a quality assurance audit, it was determined that material shipped to a waste processing vendor and subsequently disposed of at a licensed burial site was not reported in Enclosure 1, "Effluent Release Data as Required by Regulatory Guide 1.21,"
Table 3, "Effluent and Waste Disposal Annual Report... Solid Waste and Irradiated Fuel Shipments." Enclosure 3 provides a copy of the originally submitted pages with the changed information annotated. Revised pages are provided in Enclosure 4.
Should you require further information regarding this matter, please contact Mr. Peter J. Harvey, Manager - Chemistry Department at (603) 773-7320.
Very truly yours, NORTH ATLANTIC ENERGY SERVICE CORP.
Gene F. St. Pierre Station Director
U.S. Nuclear Regulatory Commission "NYN-02067/Page 2 cc:
H. J. Miller, NRC Region I Administrator R. D. Starkey, NRC Project Manager, Project Directorate 1-2 G. T. Dentel, NRC Senior Resident Inspector
ENCLOSURE 1 TO NYN-02067
Table A Seabrook Station 2001 Annual Radioactive Effluent Release Report Maximum(a) Off-Site Doses and Dose Commitments to Members of the Public Dose (nrem)_
Release Type ist 2nd 3rd 4th Quarter Quarter Quarter Quarter Year(0 Liquid Effluents:
Total Body Dose 1.51E-04 4.28E-05 4.22E-05 8.45E-05 3.21E-04 (1)
(2) 1 (1)
Organ Dose 6.1 IE-04 1.88E-04
.62E-04 2.50E-04 (3)
(3)
(3)
(4)
Airborne Effluents:
Organ Dose from Iodines, 6.13E-03 6.56E-03 3.66E-03 2.66E-03 1.90E-02 Tritium, and Particulates (5)
(5)
(6)
(7)
Noble Gases Beta Air 6.90E-05 1.07E-05 1.05E-03 4.85E-04 1.61E-03 (mrad)
(8)
(9)
(10)
(11)
Gamma 1.15E-04 1.46E-05 4.27E-04 1.84E-04 7.41E-04 Air (12)
(10)
(10)
(11)
(mrad)
Doses (torem) at Receptor Locations Inside Site Boundary(d):
Science and Nature Center (SW, 488m):
5.1 8E-06 5.26E-06 2.18E-06 1.69E-06 1.43E-05 Organ Dose (mrem)
(d])
(dl)
(dl)
(dl)
The "Rocks" (NE/ENE, 244m):
Organ Dose (mrem)
Direct Dose From Plant Operation(')
1.32E-04 (dl) 8 1.30E-04 (dl) 1.77E-04 (dl) 1.73E-04 (dl) 6.12E-04
Table B Seabrook Station 2001 Annual Radioactive Effluent Release Report Total Dose to Maximum Off-Site Individual (40CFRI90)
(a) Maximum organ includes consideration of the thyroid.
10
- "x.oe...+i Release Source Total Body Maximum Organ(a)
(nmrem)
(mrem)
Liquids 3.21E-041 Noble Gases 4.54E-04 4.54E-04 Gas lodines, Tritium &
1.90E-02 1.90E-02 Particulates Direct Radiation 0.OOE+00 0.00E+00 Annual Total 1.98E-02 2.07E-02
Table C Seabrook Station 2001 Annual Radioactive Effluent Release Report Calculated 2001 Maximum Doses Versus Applicable Limits Applicable ODCM Calculated Percent ODCM Annual Annual (2001) of Receptor Control Limit Dose 0
Limit Offsite Liquid Effluents Whole Body Dose C.6.2.l.b 3
mrem 3.21e-04 mrern 0.01%
Organ Dose C.6.2.1.b 10 mrem 1.21e-03 mrem 0.01%
Airborne Effluents Organ Dose (iodines, tritium, and part.)
C.7.3.1.b 15 mrrm 1.90e-02 mrem 0.13%
Gamma Air Dose (noble gases)
C.7.2.1.b 1 0 mrad 7.41e-04 mrad 0.007%
Beta Air Dose (noble gases)
C.7.2.1.b 20 mrad 1.61e-03 mrad 0.008%
All Plant Sources (a)
Whole Body Dose C.8.1.1 25 mrem 1.98e-02 mrem 0.08%
Organ Dose C.8.1.1 25 mrem 2.07e-02 mrem 0.08%
Onsite (Science and Nature Center, 488m SW)
Airborne Effluents Organ Dose (iodines, tritium, and part.)
C.7.3.1.b(b) 15 mrem 1.43e-05 mrem 0.0001%
Onsite (The "Rocks", 244m NE/ENE)
Airborne Effluents Organ Dose (iodines, tritium, and part.)
C.7.3.1.b(b) 15 mrem 6.12e-04 mrem 0.004%
(a) The "all plant sources" doses are the sum of the whole body doses and maximum organ doses from liquid, noble gas, and iodinesltritium/particulate releases as well as direct radiation from fixed station sources.
(b) ODCM Part A, Section 10.2 states that the annual effluent report shall include an assessment of the radiation doses from radioactive liquids and gaseous effluents to members of the public due to their activities inside the site boundary during the report period. The referenced limits (C.7.2.1.b & C.7.3.1.b) are the acceptable doses from liquid and gaseous effluents to areas at and beyond the site boundary and are considered to be appropriate for comparison purposes.
11
ENCLOSURE 2 TO NYN-02067
Revision 1, July, 2002 I Table A Seabrook Station 2001 Annual Radioactive Effluent Release Report Maximum(') Off-Site Doses and Dose Commitments to Members of the Public 8
Dose (mrem)°')
Release Type 1it 2nd 3rd 4th Quarter Quarter Quarter Quarter Year~c)
Liquid Effluents:
Total Body Dose 1.51E-04 4.28E-05 4.22E-05 8.45E-05 3.21E-04 (1)
(2)
(1)
(1)
Organ Dose 6.11E-04 1.88E-04 1.98E-04 2.50E-04 1.25E-03 (3)
(3)
(4)
(4)
Airborne Effluents:
Organ Dose from Iodines, 6.13E-03 6.56E-03 3.66E-03 2.66E-03 1.90E-02 Tritium, and Particulates (5)
(5)
(6)
(7)
Noble Gases Beta Air 6.90E-05 1.07E-05 1.05E-03 4.85E-04 1.61E-03 (mrad)
(8)
(9)
(10)
(11)
Gamma 1.15E-04 1.46E-05 4.27E-04 1.84E-04 7.41E-04 Air (12)
(10)
(10)
(11)
(mrad)
Doses (mrem) at Receptor Locations Inside Site Boundary(."
Science and Nature Center (SW, 488m):
5.18E-06 5.26E-06 2.18E-06 1.69E-06 1.43E-05 Organ Dose (mrem)
(dl)
(dl)
(dl)
(dl)
The "Rocks" (NE/ENE, 244m):
1.32E-04 1.30E-04 1.77E-04 1.73E-04 6.12E-04 Organ Dose (mrem)
(dl)
(dl)
(dl)
(dl)
Direct Dose From Plant Operation(e) 0
Revision 1, July, 2002 1 Table B Seabrook Station 2001 Annual Radioactive Effluent Release Report Total Dose to Maximum Off-Site Individual (40CFRI90)
Release Source Total Body Maximum Organ(a)
(mrem)
(mrem)
Liquids 3.21E-04 1.25E-03 Noble Gases 4.54E-04 4.54e-04 Gas Jodines, Tritium &
1.90E-02 1.90E-02 Particulates Direct Radiation 0.OOE+00 0.OOE+00 Annual Total 1 1.98e-02 2.07e-02 (a) Maximum organ includes consideration of the thyroid.
10
Revision 1, July, 2002 Table C Seabrook Station 2001 Annual Radioactive Effluent Release Report Calculated 2001 Maximum Doses Versus Applicable Limits 7Applicable ODCM Receptor Control Offsite Liquid Effluents Whole Body Dose C.6.2..b Organ Dose C.6.2.1.b Airborne Effluents Organ Dose (iodines, tritium, and part.)
C.7.3. l.b Gamma Air Dose (noble gases)
C.7.2.1.b Beta Air Dose (noble gases)
C.7.2.1.b All Plant Sources (a)
Whole Body Dose C.8.1.1 Organ Dose C.8.1.1 Onsite (Science and Nature Center, 488m SW)
Airborne Effluents Organ Dose (iodines, tritium, and part.)
C.7.3.1.b(b)
Onsite (The "Rocks", 244m NE/ENE)
Airborne Effluents Organ Dose (iodines, tritium, and ODCM Annual Limit 3
mrem 10 mrem 15 mrem 10 mrad 20 mrad 25 mrem 25 mrem 15 mrem Calculated Annual (2001)
Dose 3.21e-04 1.25e-03 1.90e-02 7.41e-04 1.6le-03 mrem mrem mrem mrad mrad 1.98e-02 mrem 2.07e-02 mrem I.43e-05 mrem I 0.0001%
I I
I part.)
C.7.3.1.b(b) 15 mrem 6.12e-04 mrem 0.004%
(a) The "all plant sources" doses are the sum of the whole body doses and maximum organ doses from liquid, noble gas, and iodines/tritium/particulate releases as well as direct radiation from fixed station sources.
(b) ODCM Part A, Section 10.2 states that the annual effluent report shall include an assessment of the radiation doses from radioactive liquids and gaseous effluents to members of the public due to their activities inside the site boundary during the report period. The referenced limits (C.7.2.1.b & C.7.3.l.b) are the acceptable doses from liquid and gaseous effluents to areas at and beyond the site boundary and are considered to be appropriate for comparison purposes.
11 Percent of Limit 0.01%
0.01%
0.13%
0.007%
0.008%
0.08%
0.08%
i
ENCLOSURE 3 TO NYN-02067
TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1999 Corcteftj SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Fpw A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)
- 1. Type of waste (no shipment made)
Unit Est. total error %
- a. Spent resins, filter sludges, evaporator 23.3 m' 2.00 E+01 bottoms, etc.
82.1 Ci
- b. Dry compressible waste, contaminated equip., etc.
NA 0 ci
- c. Irradiated components, control rods, etc.
0 ms NA S 0 Ci
- d. Other (describe)
Dewatered Cartridge Filters 65.3 Ci
. 1Pcf af+ rf tmf nr nir'l;Ap on rv ;finin (t in
.n nf'11nt '#
Nuclide'
/
C i H-3 0.84 6.93E-01 Mn-54 0.10 8.28E-02 Fe-55 6.00 4.93E+00 Co-57 0.04 3.64E-02 Co-58 4.95E-03 4.06E-03 Co-60 5.76 4.73E+00 Ni-63 86.84 7.13E+01 Sb-125 0.09 7.34E-02 Cs-134 0.12 9.89E-02 Cs-137 0.19 1.59E-01 Zr-95 6.54E-07 5.37E-07 Nb-95 1.89E-08 1.55E-08
%%vartW J1 V
.7 VP
- b.
Nuclide I
NA NA NA
-POP' C.
NA NA d
H-3 0.01 19E-03 Cr-51 0.07 4.73E-02 Mn-54 0.62 4.04E-01 Fe-55 64.76 4.23E+01 Fe-59 2.77E-03 1.81E-03 Co-57 0.05 3.54E-02 Co-58 1.01 6.57E-01 Co-60 12.77 8.34E+00 Ni-63 18.29 1.20E+01 Zr-95 0.05 3.13E-02 Nb-95 0.03 1.68E-02 Ag-110m 1.86E-03 1.21E-03 Sn-113 0.01 9.14E-03 Sb-125 0.01 6.54E-03 Cs-134 0.02 1.43E-02 Cs-137 2.30 1.50E+00
- 3. Solid Waste Disposition Number of shipments Mode of Transportation Destination 6
Flatbed Truck Chem Nuclear - Bamwell, S.C.
B. IRRADIATED FUEL SIPMENTS (Disposition)
XA.ýr Number of Shipments Mode of Transportation NA Destination NA
ý ýe
!TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2000 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)
- 1.
Type of waste Unit Est. Total Error, %
- a.
Spent resins, filter sludges, evaporator 21.9 m' 2.00E+01 Bottoms, etc:
403.2 Ci
- b.
Dry compressible.waste, contaminated 0 m NA Equip, etc.
0 Ci
- c.
Irradiated components, control 0 m NA Rods, etc.
-0 Ci
- d.
Other (describe) 0 M, NA 0 Ci 0.v6d4k TyAcLue at~
6 w.,~se.
Q"OVw &W-d
- 3.
Solid Waste Disposition Number of Shipments Mode of Transportation 5
Flatbed Truck Chem-Nuclear Barnweil, SC B. IRRADIATED FUEL SHIPMeENTS(Disposvition)
.I-,
Number of Shipments Mode of Transportation Destination t
v I aE NA NA NA 11 Destination
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2001 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2001 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) wKI4%
11 A.
- 1.
Type of waste Unit Est. Total Error, %
- a.
Spent resins, filter sludges, evaporator 6.81 mi3 2.OOE+01 Bottoms, etc.
77.6 Ci
- b.
Dry compressible waste, contaminated 25.28 m 2.50E+01 Equip, etc.
5.0 Ci
- c.
Irradiated components, control 0 m3 NA Rods, etc.
0 Ci
- d.
Other (describe): Dewatered Cartridge Filters 7.09 n3 2.88E+01 "122.8 Ci
- 3.
Solid Waste Disposition Number of Shipments Mode of Transportation 7
Truck Truck B. IRRADIATED FUEL SHIPMENTS (Disposition)
Destination Chem-Nuclear Barnwell, SC Duratek, Oak Ridge, TN Number of Shipments NA Mode of Transportation NA 12 Destination NA
ENCLOSURE 4 TO NYN-02067
TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1999 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Rev.01)
A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 1 year Et oa
- 1.
Type of waste Unit Period Est. Total Period
- _Error,
- a.
Spent resins, filter sludges, evaporator m3 2.33E+01 Bottoms, etc.
Ci 8.21E+01
- b.
Dry compressible waste, contaminated NA NA Equip, etc.
Ci
- c.
Irradiated components, control NA NA Rods, etc.
Ci
- d.
Other (describe) m3 4.72E+00 2.88E+01 Dewatered Cartridge Filters Ci 6.53E+01
- 2.
Estimate of major nuclide composition (by type of waste)
- a.
- b.
C.
d.
8.40E-01 Mn-54 1.00E-01 Fe-55 6.00E+00 Co-57 4.OOE-02 Co-58 4.95E-03 Co-60 5.76E+00 Ni-63 8.68E+01 Sb-125 9.00E-02 Cs-134 1.20E-01 Cs-137 1.90E-01 Zr-95 6.54E-07 Nb-95 1.89E-08 I%I H-3 1.00E-02 Cr-51 7.OOE-02 Mn-54 6.20E-01 Fe-55 6.48E+01 Fe-59 2.77E-03 Co-57 5.00E-02 Co-58 1.01E+00 Co-60 1.28E+01 Ni-63 1.83E+01 Zr-95 5.OOE-02 Nb-95 3.00E-02 Ag-110m 1.86E-03 Sn-i 13 1.001E-02 Sb-125 1.OOE-02 Cs-134 2.OOE-02 Cs-137 2.30E+00
- 3.
Solid Waste Disposition Number of Shipments 6
15 1
Mode of Transportation Flatbed Truck Flatbed Truck Flatbed Truck Destination Chem-Nuclear Barnwell, SC GTS Duratek Oak Ridge, TN GTS Duratek Kingston, TN B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments Mode of Transportation NA NA Destination NA
TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2000 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Rev.01)
A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 1 year Et oa
- 1.
Type of waste Unit Period Est. Total Error, %
- a.
Spent resins, filter sludges, evaporator m3 4.00E+01 2.88E+01 Bottoms, etc.
Ci 4.04E+02
- b. Dry compressible waste, contaminated 1.78E+01 2.88E+01 Equip, etc.
Ci 5.77E+00
- c.
Irradiated components, control NA NA Rods, etc.
C i I
I
-: : :j
- d.
Other (describe):
In NA NA Ci
- 2.
Estimate of major nuclide composition (by type of waste) a H-3 b.
1.01E-01 C-14 3.83E-02 Mn-54 1.31E+00 Fe-55 1.19E+01 Co-57 7.89E-02 Co-58 1.07E-01 Co-60 1.15E+01 Ni-59 1.24E-01 Ni-63 6.83E+01 Sr-89 1.16E-04 Sr-90 1.58E-02 Zr-95 2.09E-08 Nb-95 3.88E-10 Sb-125 1.77E-01 Cs-134 1.88E+00 Cs-137 3.94E+00 Ce-144 4.64E-01 Pu-238 6.08E-05 Pu-239 4.40E-05 Pu-241 4.01E-03 Am-241 1.83E-05 Cm-242 6.711E-06 Cm-243 1.58E-05 H-3 1.38E-02 Cr-51 7.02E-05 Mn-54 4.59E-02 Fe-55 3.76E+00 Fe-59 2.52E-04 Co-57 3.71E-03 Co-58 1.96E-01 Co-60 9.40E-01 Ni-63 9.18E+01 Ila ofllb
- b.
C.
d.
- 3.
Solid Waste Disposition Number of Shipments 5
4 Mode of Transportation Flatbed Truck Truck Destination Chem-Nuclear Barnwell, SC Duratek Oak Ridge, TN B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments NA Mode of Transportation NA Ilb ofllb Zn-65 5.38E-04 Zr-95 1.28E-02 Nb-95 5.21E-03 Ag-I10m 1.04E-03 Sn-i 13 5.65E-03 Sb-124 1.58E-04 Sb-125 1.73E-02 Cs-134 1.10E+00 Cs-137 2.08E+00 Destination NA
TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2001 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Rev.01)
A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)
- 1.
Type of waste Unit 1 year Est. Total Period Error, %
- a.
Spent resins, filter sludges, evaporator In 1.85E+01 Bottoms, etc.
Ci 7.83E+01
- b.
Dry compressible waste, contaminated mW 3.01E+01 Equip, etc.
Ci 1.16E+01
- c.
Irradiated components, control NA NA Rods, etc.
Ci
- d.
Other (describe): Spent cartridge filters 7.09E+00 2.88E+01 mCi 1.23E+02
- 2.
Estimate of major nuclide composition (by type of waste)
- a.
2.711E-01 C-14 1.24E-02 Mn-54 1.95E+00 Fe-55 1.90E+00 Co-57 8.55E-02 Co-58 6.15E-02 Co-60 9.51E+00 Ni-59 4.11E-01 Ni-63 6.92E+01 Zr-95 6.09E-07 Nb-95 1.13E-08 Sr-89 3.40E-05 Sr-90 2.34E-02 Sb-125
%_ 1 3.18E-01 Cs-134 4.54E+00 Cs-137 1.11E+01 Ce-144 5.83E-01 Pu-238 4.55E-05 Pu-239 2.35E-05 Pu-241 2.84E-03 Am-241 1.22E-05 Cm-242 4.09E-06 Cm-243 1.52E-05 H-3 4.52E-02 Cr-51 3.67E-24 Mn-54 2.37E-01 Fe-55 1.26E+01 Fe-59 7.85E-22 Co-57 2 12E-02 Co-58
%_ 1 7.82E-01 Co-60 2.43E+00 Ni-63 8.10E+01 11
_o
- b.
C.
d.
- 3.
Solid Waste Disposition Number of Shipments 7
2 Mode of Transportation Truck Truck Destination Chem-Nuclear Bamwell, SC Duratek Oak Ridge, TN B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments NA Mode of Transportation NA 12 Zr-95 5.20E-02 Nb-95 2.48E-02 Sn-I 13 2.26E-02 Sb-125 1.15E-01 Cs-137 1.91E+00 Cs-134 8.16E-01 Ag-10mn 3.96E-03 H-3 5.43E-01 Cr-51 3.63E-04 Mn-54 1.13E+00 Fe-55 6.07E+01 Fe-59 1.40E-04 Co-57 9.60E-02 Co-58 4.17E-01 Co-60 1.11E+01 Ni-63 2.51E+01 Zr-95 1.20E-02 Nb-95 9.13E-05 Sn-i 13 1.41E-03 Sb-125 1.43E-01 Cs-137 7.85E-01 Destination NA