ML20029A971
| ML20029A971 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 12/31/1990 |
| From: | Fey F NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9103050170 | |
| Download: ML20029A971 (14) | |
Text
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Northern States Power Company 414 Nicoliet Mat Mnneapnbs, %nnesota 5!.401 Teicphone (6121010M00 February 27, 1991 Monticello Technical Specification TS6.7 4A U.S. Nuclear Regulatory Commission Document Control Desk
)
Washington, D.C.
20555 Monticello Nuclear Generating Plant Docket No. 50-623 License No. DPR-22 Effluent and Waste Disposal Semiannual Report for July 1.
1990 through December 31. 1990 In accordance with the Monticello Technical Specifications, Appendix A to Operating License DPR-22, we are submitting the Effluent and Waste Disposal Semiannual Report covering the last half year of 1990.
An evaluation of the effects of Hydrogen Water Chemistry (HWC) has also been enclosed.
The Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP) Manual are not attached since they remained unchanged during the reporting period.
.. /Wh S Ah Fred L.
Fey, Jr., Manager Nuclear Radiological Services Attachment 1
4 i
i I
/
9103050170 901231
[
\\
PDR ADOCK 05000263 R
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- NORTHERN-STATES POWEA-COMPANY MONTICELLO NUCLKAR GENiiRATING PLANT License-No. DPR-22
>i ErrLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT
.i Period': Jul - Dec 1990 i
supplemental Information 1.'RQgulatory Limits - Quarterly levels requiring reporting to 3
Nuclear Regulatery Commission iA. Noble Gases :
.5 mrad / quarter gamma radiation 10 mrad / quarter beta radiation B.
Long Lived Iodines, Particulates,-and Tritium :
7.5 mrem / quarter dose to any organ C.fLiquid Effluents :
1.5 mrem / quarter dose to the-total body 5.0 mrem / quarter dose to any organ
-2.-Maximum Permissible: Concentrations iA.--Noble Gases :-
10 CFR Part 20_,' Appendix B, Table II, Column 1 B. Long-Lived Iodines, Particulates, and-Tritium :
-10LCFR;Part20, Appendix B, Table II, Column 1
-C; Liquid cffluents :-
~
101CFR Part 20,-Appendix B, Table.II,' Column 2 2'.0,E-41uci/ml_for dissolved-andl entrained gases 3._ Average Energy _
.( No t'. Appli cable ).
PQge 3
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1990 Supplemental Information (continued)
- 4. MQasurements and Approximations of Total Radioactivty A.-Noble Gases :
Continuous gross activity monitors in Rea0 tor Building Vent and Plant Stack exhaust streams.
Weekly isotopic analysis of exhaust streams.
B.
Iodines in Gaseous Effluent :
Continuous monitoring with charcoal cartridges-in Reactor Building
-Vent and Plant Stack exhaust streams with weekly analysis.
C.
Particulates in Gaseous Effluent :
Continuous monitoring with particulate filters in Reactor Building Vent and Plant Stack exhaust streams with weekly analysis.
D.
Tritium in Gaseous Effluent :
Continous monitoring with silica gal cartridges in Reactor Building Vent'and Plant Stack exhaust streams with weekly analysis.
E.
Liquid Effluents :
Tank sample analyzed prior to each planned release and continuous monitoring of gross activity during planned release.
- 5. Batch Releases A.
Liquid :
- 1. Number of Batch Releases 0
- 2. Total Time Period for Batch Releases NA min
- 3. Maximum Time Period for a Batch Release NA min
- 4. Average Time Period for a Batch Release NA min
- 5. Minimum Time Period for a Batch Release NA min
- 6. Average River Flow During Release NA cf/sec B.
Gaseous :
- 1. Number of Batch Releases 5
- 2. Total Time Period for Batch Releases 12877.0 min
- 3. Maximum Time Period for a Batch Release 6628.0 min
- 4. Average Time Period for a Batch Release 2575.4 min
- 5. Minimum Time Period for a Batch Release 450.0 min
Pago 3
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1990 Supplemental Information (continued)
- 6. Abnormal Releases A.
Liquid i
- 1. Number of Releases 0
- 2. Total Activity Released NA Ci B.
Gaseous :
- 1. Number of Releases 3
- 2. Total Activity Released 202.1 Ci
'Page' 4
' EFFLUENT AND WASTE DISPOSAL-SEMIANNUAL REPORT Period : Jul - Dec 1990
_i Table 1A Gaseous Effluents - Summation of all Releases Units 3rd Qtr 4th Qtr Est._ Total Error, %
A.JFission-& Activation gases
- 1. Total Release Ci 8.27E+02 7.55E+02 2.00E+01 l 2.
Average Release Rate uci/sec 1.04E+02 9.50E+01 3.
Percent Tech Spec Qttly Reporting Level Gamma Radiation 2.63E+00 1.12E+00 Beta Radiation 6.56E-01 2.89E-01_
J B. ~ Iodines 1
1.
Total I-131 Release Ci 1.98E-02 7.54E-03 1.00E+01 l
- 2. Average I-131-Release Rate uci/sec 2.49E-03 9.48E-04 C.
Particulates 1.
Total Particulates Ci 2.59E-03 1.49E-03 3.00E+01 l
~~2.
Average' Release Rate uci/sec 3.26E-04 1.87E-04
- 3. Gross Alpha Radioactivity Ci 7.08E-06 6.21E-06 D.
Tritium 1.
Total Release Ci 4.30E+01 1.21E+01 1.00E+01 l
- 2. Average Release Rate uc4/sec
-5.40E+00 1.52E+00 E. Percent QtrlyLTech SpecLReporting Levels
- 1.
Iodines,.Particulates,
- and Tritium-4.12E+00 1.34E+00 2
Page' S L
EFTLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1990 Table 1B Gaseous Effluents - Elevated Releases Continuous Mode Batch Mode Nuclides Released Unit 3rd Otr i 4th Otr 3rd Otr l 4th Otr
- 1. Tission Gases KR-85 Ci 0.00E+00 0.00E+00 0.00E+00 3.71E-10 KR-85M Ci 8.60E-01 1.18E+00-0.00E+00 0.00E+00
-KR-87 Ci 5.32E+00 6.72E+00 0.00E400 0.00E+00 KR-88 Ci 2.42E+00 3.29E+00 0.00E+00 0.00E+00 KR-89 Ci 0.00E+00 8.91E+00 0.00E+00 0.00E+00 XE-133 Ci 1.30E+02 1.60E+02 4.49E-03 5.50E-03 XE-133M Ci 1.98E+00 3.02E+00 0.00E+00 0.00E+00
-XE-135 Ci 1.61E+01 1.48E+01 5.06E-03 0.00E+00 XE-135M Ci 3.94E+01~
4.32E+01 6.66E-04 0.00E+00 XE-137 Ci 2.04E+02 2.36E+02 0.00E+00 0.00E+00 XE-138 Ci 9.72E+D1 1.19E+02 0.00E+00 0.00E+00 AR-41 Ci 0.00E+00 0.00E+00 3.71E-10 4.35E-09 Total-for Period Ci 4.98E+02 5.96E^02 1.02E-02 5.50E-03
- 2. Iodines I-131 Ci 7.29E 5.06E-03 4.37E-09 7.83E-08 I-133 Ci 8.61E-03 1.35E-02 0.00E+00 1.65E I-135 Ci 9.37E-03 6.41E-03 0.00E+00 0.00E+00 Total fo. 7eriod Ci 2.53E-02 2.50E-02 4.37E-09 9.49E-08 3.
Particulates CR-51 Ci 4.35~E-09 0.00E+00 0.00E+00 0.00E+00 MN-54 Ci-8.97E-07 1.00E-06 0.00E+00-3.79E-08 CO-60 Ci 6.42E-06 5.66E-05 0.00E+00
-6.31E-08 ZN-65 Ci 4.57E-07 0.00E+00 1.00E+00 0.00E+00 L
ZR 95 Ci 0.00E+00 1.85E-07' O.00E+00 0.00E+00 CS-137-
-Ci 5.18E-06 1.36E-05 0.00E+00 0.00E+00 BA-140 Ci 5.00E-04 6.75E-04 0.00E+00 0.00E+00 CE-141 Ci 3.03E-07 0.00E+03~
0.00E+00 0.00E+00 SR-89 Ci 2.15E-04 3.71E-04 0.00E+00 0.00E+00 SR Ci 7.75E-07 1.17E-06 0.00E+00 0.00E+00 Total for. Period Ci 7.29E-04 F.07E-03 0.00E+00 1.01E-07
Page 6
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1990 Table lc Gaseous Effluents - Building Vent Releases
{~ ~~
Continuous Mode l
Batch Mode Nuclides Released l Unit 3rd_Qtr I 4th Qtr I 3rd Qtr l 4th Qtr
- 1. rission Gases KR-85 Ci 0.6VE~DV~
0.00E+00 0.00E+00 7.33E I KR B5M Ci 67V3E+00
~0TV3E+00 0.03E+00 9.92E-01~
Xt-133 Ci 3.57ETUO 1 47E+01 6.47E~01 3.890-01 XE-135 Ci 1TT5E+02 5.16E+01 6.27E-01 6.32E-01 XE-135M Ci 77671402 9.2EE~D1 5.79E-02 2.75E-01 XE-138 CI 7.9FFTE6 0.UEt+00 0.00E+00 0.00E+06~
AR-4I~
Ci 0.031 30 0.00E+00 7.33E-08 1.151-10 Total for Period Ci 3.28E+02 E.59E+02 1.33E+00 1.33E+00
- 2. Iodines I-131 C1 1.25E-02 2.06E-03 1.41E-12 4.14E-04 I-133 Ci 9.661-02 1.22E-02 5.43E-05 2.06E-03 I-135 C1 1.56E-01 1.4BE-02 0.00E+00 2.63E-03
~
Total for Period Ci 77FTE-01 2.90E-02 5.43E-05 5.10E-03
- 3. Particulates CR-51 C1 1.15E-10 0.00E+00 0.00E+00 l 0.00E+00 MN-54 Ci 5.39E-06 1.82E-06 0.00E+00 0.00E+00
~~
CO-60 Ci 1.30E-04 8.73E-05 0.00E+00 4.06E-33~
ZN-65 C1 CITE-04 2.27E-05 0.00E+00 8.03E-05 CS-137 Ci 57Frt-05 3.02E-05 0.00E+00
~0.00E+00 BA-140 C1 1.34E-03 1.20E-04 0.00E+00 0.00E+00 CE-141 Ci 7.67E-05 0.00E+00 0.00E+00 0.00E+00 SR-89 Ci 9.26E-05 3737E 33 0.00E+00 0.00E+00 Total for Period C1 1.86E-03, 2.98E-04 0.00E+00 1.21E-04 l
i l
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'PagQJ 7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period-Jul - Dec 1990 4
- Table 2A Liquid Effluents - Summation of all Releases Units.
3rd Qtr 4th Qtr Est. Total Error, %
A.' Fission &l Activation products 1.
Total Release (not-including tritium, gases, alpha)
Ci 0.00E+00 0.00E+00 0.00E+00 2.
Avg Diluted Concentration uci/ml 0.00E+00 0.00E+00 lei. Tritium 1.-Total Release Ci 0.00E+00 0.00E+00 0.00E+00-l_
'2.-Avg Diluted Concentration uci/ml 0.00E+00 0.00E+00 C.
Dissolved'and Entrained Gases 1.
Total Release l
aCi 0.00E+00 0.00E+00 0.00E+00 l
- 2. Avg Diluted Concentration I uci/ml 0.00E+00 0.00E+00
- D._ Percent._0trly Tech Spec Reporting Level 1.
Whole Body Dose 0.00E+00 0.00E+00 2.
Organ-Dose =
0.00E+00 0.00E+00 LE. Gross: Alpha Radioactivity l
.l.
Total Release l
Ci 1 0.00E+00 l 0.00E+00 l 0.00E+00-l-
_lF.-Volume of Waste Released-l-
Liters l-0.00E+00 l 0.00E+00 l 0.00E+00 l1
'lr.oVolume of Dilution Water Used I Liters l--0.00E+00-l-0.00E+00-l 0.00E+00-l j
Table 2B Liquid _ Effluents
-Continuous Mode 1
Batch-Mode ENuclides Released Unit 3rd Otr I-4th Otr-l 3rd Otr.
I 4th'Otr None_Reletsed This Period
..~
. - - -.. ~ -.
Page 8
ErrLUENT AND WASTE DISPOSAL: SEMIANNUAL REPORT
' Period Ju1~- Dec 1990 R
Table 3 Solid Waste and Irradiated ruel Shipments
-A'.' Solid Waste-Shipped Offsite for Burial-or Disposal (not irradiated fuel)-
r
'71.
Type-of Waste Units 6-month Est. Total Period Error, %
-a.-Spent resins, filter-sludges, Cu. Meter 2.43E+01 evaporator bottoms, etc.
C1 8.96E+02 3.70E+01 b.. Dry compressible: waste, Cu. Meter 1.88E+01 contaminated equipmenta-etc.
Ci 8.76E+00 3.50E+01
- c.. Irradiated components, Cu. Meter, 0.00E+00
. control rods, etc.
Ci 0.00E+00-0.00E+01'
- d. Other (describe)
Cu, Meter 0.00E+6D Ci 0.00E+00 0.00E+01 2.
Estimate-of major nuclide Nuclide
-l Percent composition'(by type of waste) 1 A
Mn-54 3.25E+00 Fe-55 4.43E+01-Co-58 2.27E-02 Co-60 4.26E+01 Ni-63 1.77E-01 Zn-65 4.58E+00 Sr-89 8.64E-01 Sr-90 1.72E-01 I-131 7.85E-02 Cs-134 8.56E-01 Cs-137 2.89E+00 Ba-140-3.97E-02 La-140-9.08E-03 Ce-141 1.51E-02 B
Cr-51 4.06E+00 Mn-54 6.74E+00 Fe-55 3.17E+0; 3 Co-58 8.50E 01 i Fe-59 l'.02E+00 l Co-60 3.69C+ul
'~
Ni-63 2.54E-01 Zn-65 3.02E+00 Sr-89:
1.54E+00 l
Sr-90 1.06E-01 l
I-131-
-5,38E-01 Cs-134 3.82E+00 Cs-137 3.67E+00 Da-140-3.82E-01 La-140 1.06E-01 l
-Ce-141~
1.00E-01
-l I
. ~. -.
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'PagQ 9-EFFLUENT ANDl WASTE DISPOSAL'SEM2 ANNUAL REPORT-Period Juli-Dec 1990
-Table-3 Solid Waste and-Irradiated Fuel Shipments
- 3. Solid-waste; disposal Number of.
Mode of
~~64stination
~ Shipments ~
Transportation-3 Truck Chem-Nuc Inc.. Barnwell, SC.
4 Railway US Ecology, Richland, WA.
1
_P.
Irradiated Fuel Shipments
- 1. Disposition
. Number-of Mode-of.
Destination Shipments-Transportation None This Period' C. Shipping Container and Solidification Method
-No.-
Volume Activity Type of Container Solidification M3 ci-Waste Code Code 90-30 5.83E+00 4.08E+01 A
A D
90 -5.83E+00:
2.21E+01' A
-A D
190-40 5'.03E+00 2.12E+01 A
' A-D 90-41
.5.84E+00 8.05E+00 B
A N
90 3.41E+00 3.39E+02 A
A D
90-44~
-3.41E+00 4.73E+02 A
A D
90-33 1 30E+01 7.08E-01 B
L N
iContainer Codes l'
Solidification Codes :
'L~
1LSA C - Cement-
.Al Type A U - UreaLFormaldehyde B - Type-B D - Dewatering-0 - Large Quantity N - Not Applicalble
- N -.-
m-,-
g-,.,n.
4 NORTHERN DTATES POWER COMPANY MORTLCELLO_MECLEAR DIRERATlRQ_ELANI QI.E.-HTRlhDIATl9R D91E_MHHMERT_F.0B 1AnRRty_l DRM Mh9I_.114._Lfl9 An assessment of radiation doro due to relonso from the Monticello Nuclear Goncreting Plant (MNG P) during 1990 was performed in accordanco with the Technical Specifications. Computed doson woro well below tho 40 CFR Part 190 Standards and 10 CFR Part 50 Appendix I Guidelines.
Of f-sito doso calculation formulau and meteorological data f rom the Off-sito Doso Calculation Manual were used in makirig this assessment. Sourco terms were obtained from the two Effluent and Wasto Disposal Semlannual Reports prepared for NRC review during the year of 1990.
Off-211.t_.DAs e frRp 0afLe9_Ra_ReinA a Computed dosos due to gaseous releases are reported in Table J.
Critical receptor location and pathways for organ donos are reported in Table 2.
Dosos, both whole body and organ, are a small porcentage of Appendix I Guidelines.
Dif-e.iic_DAPos IISm 1dsRLC_RelaAaa There were no 4 iquid releases nado f rom the Monticello Plant during the 1990 calendar year.
DSaps to IDAAY_idMalA_.93e to hg3ivitiap_InaidA_thg_.Rif.q_Daund3ry occasionally sportsmen ontor thn Monticello sito for recreational activities, in addition, a Fishery Study Station operated by the University of Minnesota (formally Environmental Protection Agoney Field Station) is located at the MonticOlo site (800 Figuro 3.8.I and rigure 3.8.2 of Monticello Technical Specifications). The most exposed general public within the rostricted area are those workers at this Field Station who spend an averago of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> /wock. Whole body donos to these individuals have been computed using stack and vont X/Q values ~for the Field Station location. Annual computed dosos were reducod by the factor of 40/168 to account for the limited occupancy for workers at this location. Organ dosos to workers at the EPA Field Station due to gaseous roloasos have boon computed for inhalation pathway (no other pathway exists). Dosos at this location woro reported in Table 1.
4
Dann._t.q_ lie.pt Expay1LKenk_qr of thq.J1gngral Publiq_,fraltLRgagigt Enl.qAanA_AnLQiliar UraniVA_F.nLRysle_ERRraan There are no other uranium fuel facilitics in the vicinity of the Monticello si?o. The only other artificini source of exposure to the general pt.blic in addition to the plant offluent releases is the direct radiation from the reactor and the steam turbines. M!1GP started a hydrogen water chemistry (llWC) program in February 1989.
Prior to the installation of HWC, a study was conducted to detorniine the direct and skyshino radiation contribution from !!WC.
This study determined the maximum exposed member of the public from direct and skyshino radiation to be a residence located 0.6 mile from the reactor at the SW sector. Using conservative assumptions, calculations indicated a maximum annual dose of 4 mrem to this residence, llowever, a review of TLD results from 1987, 1988
- 1989, and 1990 revealed no noticeable increaso in direct and skyshino radiation as a result of the HWC program installed in early 1989.
A calculation of the total annual dose to this residence from all existing pathways of radioactive offluents woro performed by running GASPAR computer codes. Adding the 4 mrom/ year to this calculation results in a
maximum whole body dono of 4.133 mrom/your.
Thereforo, the rast expused member of the gnneral public will not receive an annual radiation doso f rom reactor of fluent releason and all other fuel cycle activities in c.t x c e s s of 40 CFR Part 190 standards of 25 mrem to the whole body, 75 trxem to the thyroid, and 25 mrom to any other organ.
~
TABLE 1 OYF-SITE RADIATION DOSE ASSESSMENT - HONTICELLO PERIOD: JAMUARY 1 thtgug)1_QRREMEER 31, itiq 10 CFR Part 50 bppendix I Guidelines per unit por year anseous Ralta.E9.a Maximum Site Boundary Gamma Air Dose (mrad) 0.324 10 Maximum Site Boundary Beta Air DoGo (mrad) 0.197 20 Maximum Off-site Dose to Any Organ (mrom)*
Total 0.307 15 EPA Field Station (Krem, 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> /wco):)
Whole Body 0.162 5
Organ 0.257 15
.kiERLd Re1eJAg_a Maximum Off-sito Dose Wholo Body (mrom) 0.0 3
Maximum Off-site Dono Organ, Total 0.0 10 Long-lived Particulates, I-131, and H-3
4 TADLE 2 0FF-SITE RAD 1ATION DODE ASSESSMENT - HONTICELLO SUPPLEMENTAL INFORMATION PERIOD: JAWARLLthrmgh_DECEMEILu.4_1910 G M A O R R _ B R 1 9J!lA # 1 Maximum Site Boundary l
Dose Location (from building vents)
Sector SSE Distanco (milos) 0.43 EPA Field Station Sector ESE Distanco (milos) 0.31 Maximum off-site Dose Location Sector ESE Distanco (miles) 2.6 Pathways
- Plume, Ground, Inhalation, Cow.; ilk Age Group Infant Organ Thyroid Llquid Rc1q_aAqa Maximum Off-sito Doso Location Downstream Pathways Drinking Water Drinking Water Fish Age Group Infant Adult organ Wholo Body GI-LLI Dilution Factor 7.1 7.1 (drinking water)
_._ -.