ML18018B012
| ML18018B012 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/18/2018 |
| From: | Niagara Mohawk Power Corp |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18018B012 (60) | |
Text
NINE MILE POINT NUCLEAR STATION - UNIT 1 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JULY - DECEMBER 1999 NIAGARAMOHAWKPOWER CORPORATION
..0036897)9
Page 1 of 2 NINEMILEPOINT NUCLEARSTATION - UNIT 1 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JULY DECEMBER 1999 SUPPLEMENTAL INFORMATION P~neittt:
Nine MilePoint Unit ttt Liccnscc:
Niagara Mohawk Power Corporation TECHNICALSPECIFICATION LIMITS A)
FISSION ANDACTIVATIONGASES e
1.
The dose rate limitof noble gases released in gaseous effluents from the site to areas at and beyond the site boundary shall be less than or equal to 500 mrem/year to the total body and less than or equal to 3000 mrem/year to the skin.
2.
The air dose due to noble gases released in gaseous effluents from Nine Mile Point Unit 1 to areas at and beyond the site boundary shall be limited during any calendar quarter to less than or equal to 5 milliroentgen for gamma radiation and less than or equal to 10 mrad for beta radiation, and during any calendar year to less than or equal to 10 milliroentgen for gamma radiation and less than or equal to 20 mrad for beta radiation.
B&C) TRITIUM,IODINES AND PARTICULATES, HALFLIVES ) 8 DAYS 1.
The dose rate limitof Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days, released in gaseous effluents from the site to areas at and beyond the site boundary shall be less than or equal to 1500 mrem/year to any organ.
2.
The dose to a member of the public from Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released from Nine Mile Point Unit 1 to areas at and beyond the site boundary shall be limited during any calendar quarter to less than or equal to 7.5 mrem to any organ and, during any calendar year to less than or equal to 15 mrem to any organ.
D)
LIQUIDEFFLUENTS 1.
The concentration of radioactive material released in liquid cffluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-04 microcuries/ml total activity.
2.
The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released from Nine Mile Point Unit 1 to unrestricted areas shall be limited during any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and during any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
Page2of2 2.
MEASUREMENTS AND APPROXIMATIONSOF TOTALRADIOACTIVITY Described below are the methods used to measure or approximate the total radioactivity and radionuclide composition in effluents.
A)
FISSION AND ACTIVATIONGASES Noble gas effluent activity is determined by on-line gamma spectroscopic monitoring (intrinsic germanium crystal) or gross activity monitoring (calibrated against gamma isotopic analysis of a 4.0L Marinelli grab sample) of an isokinetic stack sample stream.
B)
IODINES Iodine effluent activity is determined by gamma spectroscopic analysis (at least weekly) of charcoal cartridges sampled from an isokinetic stack sample stream.
C)
PARTICULATES Activityreleased from the main stack is determined by gamma spectroscopic analysis (at least weekly) of particulate filters sampled from an isokinetic sample stream and composite analysis of the filters for non-gamma emitters.
D)
TRITIUM Tritium effluent activity is measured by liquid scintillation or gas proportional counting of monthly samples taken with an air sparging/water trap apparatus.
E)
EMERGENCY CONDENSER VENT EFFLUENTS The effluent curie quantities are estimated based on the isotopic distribution in the Condensate Storage Tank water and the Emergency Condenser shell water.
Actual isotopic concentrations are found via gamma spectroscopy.
Initial release rates of Sr-89, Sr-90 and Fe-55 are estimated by applying scaling factors to release rates of gamma emitters and actual release rates are determined from post offsite analysis results.
The activity of fission and activation gases released due to tube leaks is based on reactor steam leak rates using offgas isotopic analyses.
F)
LIQUIDEFFLUENTS Isotopic contents of liquid effluents are determined by isotopic analysis of a representative sample of each batch and composite analysis of non-gamma emitters.
G)
SOLID EFFLUENTS Isotopic contents of waste shipments are determined by gamma spectroscopy analysis of a representative sample of each batch.
Scaling factors established from primary composite sample analyses conducted off-site are applied, where appropriate, to find estimated concentration of non-gamma emitters.
For low activity trash shipments, curie content is estimated by dose rate measurement and application of appropriate scaling factors.
ATTACHMENT1 Summar Data Pa e1 of 2 Unit 1 X
Unit2 Liquid Effluents:
Reporting Period Jul - December 1999 10CFR20, Appendix B, Table II, Column 2 Average MPC - uCi/ml (Qtr. 3)
= N/A Average MPC - uCi/ml (Qtr. 4)
~
N/A Average Energy (Fission and Activation gases Mev):
Liquid:
Qtr. 3 Qtr. 4 By
- mZuu, B - Xaam, By
= N/A Bp
~
NIA Number of batch releases Total time poriod for batch roloasos (hrs) 0 N/A Maximum time period for a batch release (hrs):
N/A Avorago time period for a batch roloaso (hrs)
Minimum time period for a batch roloaso (hrs)
NIA NIA Total volume of water used to diiuto tho liquid effluent during release period (L)
Total volume of water used to dilute tho liquid effluent during reporting poriod (L)
NIA 2.69E+ 11 Gaseous (Emergency Condenser Vent):
Thoro wore no releases from tho operation of the Emergency Condonsor Vent.
Numbor of batch releases 0
Total time period for batch reloasos (hrs)
N/A Maximum time period for a batch release (hrs):
N/A Avorage time period for a batch release (hrs)
NIA Minimum timo period for a batch reloaso (hrs):
N/A Gaseous (Primary Containment Purge):
Number of batch releases Total timo period for batch releases (hrs)
Maximum time period for a batch roloaso (hrs)
Avorago time period for a batch roloaso (hrs)
Minimum time period for a batch release (hrs) 3 2.27E+ 01 1.21E+01 7.55E+ 00 4.43E+ 00
ATTACHMENT1 Summar Data Page 2 of 2 Unit 1 X
Unit 2 Reporting Period Jul December 1999 Abnormal Releases:
There were no abnormal releases during the reporting period.
A.
Liquids:
Number of releases 0
Total activity released N/A Ci B.
Gaseous:
Number of releases 0
Total activity released N/A Ci
ATTACHMENT2 Unit 1~
Unit 2 Reporting Period A.
GASEOUS EFFLUENTS SUMMATIONOF ALLRELEASES'LEVATED AND GROUND LEVEL EKEDRQ9 QRLBIKE QEUHEB
~B~O as 1.
Total release 2.
Average release rate
~od's 1.
Total Iodine-131 2.
Average release rate for period P~i~i 1.
Particulates with half-lives >8 days 2.
Average release rate for period 3.
Gross alpha radioactivity CI pG/sec Cl s 0/sec Ci g Ci/sec Ci WiM 18338 5.00E+01 3.00E+01 3.00E+01 2.50E+01 1.
Total release 2.
Average release rate for period o
e 5
0 Percent of Quarterly Gamma AirDose Umit (5 mR)
Percent of Quarterly Beta AirDose Umit (10 mrad)
Percent of Annual Gamma AirDose Umit to Date (10 mR)
Percent of Annual Beta AirDose Umitto Date (20 mrad)
Percent of Whole Body Dose Rate Umit (500 mrem/yr)
Percent of Skin Dose Rate Umit (3000 mrem/yr) i a d l
half-iv s r
r h Percent of Quarterly Dose Limit (7.5 mrem)
Percent of Annual Dose Umit (15 mrem)
Percent of Organ Dose Rate Umit (1500 mrem/yr)
Ci pO/sec X2HHti
? 9.'>Ji XERIC 0 'iQHE 5.00E+01 Concentrations less than the lower limitof detection of the coundng system used are indicated with a double asterisk.
2 Tritium, Iron-55, and Strontium results for the fourth quarter were not received from the off-site vendor at the time of this report. These numbers include estimates, and actual numbers willbe provided in the next Semi-Annual Report.
ATTACHMENT3 Unit1 X Unit 2 Reporting Period GASEOUS EFFLUENTS - ELEVATED RELEASE CONTINUOUS MODE Nuclides Released
- 1. fifo~G~
Argon-41 Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-127 Xenon-133 Xenon-133m Xenon-135 Xenon-135m Xenon-137 Xenon-138 Ci Ci CI Ci Ci Ci Ci Ci Ci Ci Ci Ci 2'UAf~g Iodine-131 Iodine-133 Iodine-135 Ci Ci Ci U9&%
Strontium-89 Strontfum-90 Cesium-134 Cesium-137 Cobalt-60 Cobalt-58 Manganese-54 Barium.Lanthanum-1%
AnUmony-125 Niobium-95 Cerium-141 Cerium-140 Iron-59 Cesium-136 Chromium-51 Zinc-65 Iron-55 Molybdenum-99 CI Ci Ci Ci Ci Ci CI Ci Ci Ci CI Ci Ci G
G Ci Ci Ci g ig 1 'iZUHi 122' Ci 3 3 E+00 Concentrations less than the lower limitof detection of the counting system used are indicated with a double asterisk.
A lower limitof detecUon of 1.00E-04 pG/ml for required noble gases, 1.00E-11 g Ci/ml for required parUculates, 1.00E-12 pG/mf for required Iodines, and 1.00E-06 pCI/ml forTritium, as required by Technical Specifications, has been verified.
2 Tritium, Iron-55, and StronUum results for the fourth quarter were not received from the off-site vendor at the time of this report. These numbers include estimates and actual numbers willbe included in the next Semi-Annual Report.
Contributions from purges are Included.
ATTACHMENT4 Unit 1~
Unit 2 Reporting Period GASEOUS EFFLUENTS - GROUND LEVELRELEASES Ground level releases are determined in accordance with the Off-Site Dose Calculation Manual and Chemistry procedures.
KninSa~~
Argon-41 Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-133 Xenon-133m Xenon-135 Xenon-135m Xenon-137 Xenon-138 Xenon-127 Ci Ci 0
Ci Ci Ci Ci Ci Ci0 Ci Ci CONTINUOUS MODE BATCH MODE There were no batch Releases during the reporting period.
~rd
~th QELfUXB Q/BBIEE Iodine-131 Iodine-133 Iodine-135 Emi&h&'i CI Ci Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 0
Cobalt-58 0
Manganese-54 Ci Barium-Lanthanum-140 0
Antimony-125 0
Niobium-95 0
Cerium-141 0
Cerium-144 0
Iron-59 0
Cesium-136 0
Chromium-51 Ci Zinc-65 Ci Iron-55 0
Molybdenum-99 Ci Ci 2 8252 LQMZ LH~JIIZ 2 SEQZ Z~Z Concentrations less than the lower limitof detection of the counting system used are Indicated with a double asterisk.
2 Tritium, Iron-55, and Strontium results for the fourth quarter were not received from the off-site vendor at the time of this re rt. These numbers Include estimates and actual numbers willbe included in the next Semi-Annual Re rt.
ATTACHMENT5 Pa e1of2 Unit 1~
Unit 2 Reporting Period LIQUIDEFFLUENTS SUMMATIONOF ALLRELEASES A.
i v 'o 1.
Total release (not including Tritium, gases, alpha) 2.
Average diluted concentration during reporting period B.
1.
Total release 2.
Average diluted concentration during reporting period C.
i solved and ntrained Gases 1.
Total release 2.
Average diluted concentration during reporting period D.
o I
ad'oa 1.
Total release E.
~l 1.
Prior to dilution g
'e 2.
Volume of dilution water used during release period 3.
Volume of dilution water available during reporting period:
Ci pCi/ml CI pCi/ml Ci pCi/ml Ci Uters Uters Uters E&chmu RhBdaum 5.00E+01 5.00E+01 5.00E+01 5.00E+01 5.00E+01 5.00E+01 5.00E+01 F.
r o
c I
Percent of Quarterly Whole Body Dose Umit (1.5 mrem)
Percent of Quarterly Organ Dose Umit (5 mrem)
Percent of Annual Whole Body Dose Umit to Date (3 mrem)
Percent of Annual Organ Dose Umit to Date (10 mrem)
Percent of 10CFR20 Concentration Umit Percent of Dissolved or Entrained Noble Gas Umit (2.00E-04 pCi/ml)
E~hnas HuEdrmw
ATI'ACHMENT5 Pa e2of2 Unit 1~
Unit 2 LIQUIDEFFLUENTS RELEASED Reporting Period BATCH MODE Nuclides Released Strontium-89 Strontium-90 Cesium-130 Cesium-137 Iodine-131 Cobalt-58 Cobalt-60 Iron-59 Zinc-65 Manganese-54 Chromium-51 Zirconium-Niobium-95 Molybdenum-99 Technetium-99m Barium-Lanthanum-140 Cerium-141 Tungsten-187 Arsenic-76 Iodine-133 Iron-55 Neptunium-239 Praseodymium-144 Iodine-135 Ci0 Ci Ci 0
Ci Ci0 Ci Ci Cl 00 Ci CI 0
Ci000 Ci00 2DI U
E Hung m:I EM&aaz U
E Rhfhhmrs
%&&mrna Rh3&wm Dissolved or Entrained Gases Tritium Ci No continuous mode release occurred during the report period.
ATTACHMENT6 Pa e1of7 Unit 1~
Unit 2 A.1 TYPE
- 1. Spent Resins, Rlter Sludges, Concentrated Waste, Evaporator Bottoms, etc.
(Dewatered)
~CI s
~vi (Ci)
Reporting Period SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS
- 2. Dry Active Waste (Compactible and Non-Cornpactible)
RKF~+
ZZLF~+
- 3. Irradiated Components (Non.Combustible Solid)
- 4. Other:
(to vendor for processing or consolidation) a.
Asbestos (Compactible) b.
Irradiated Comonents c.
Dry Active Waste (Compactible and Non-Compactible) d.
Resins (Dewatered) e.
Metal (scrap)
(Compactible and Non-Com actible 9JBJ~+
@LUKE'he estimated total error Is 5.00E+01%.
gglg:
No items from Unit 1 were placed in Interim storage at Unit 1
ATTACHMENT6 Pa e2of7 Unit 1~
Unit 2 A.l TYPE Reporting Period SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS Solidification
~co&
1.
Spent Resins, Rlter Sludges, Concentrated Waste, Evaporator Bottoms, etc. (Dewatered) 2.
Dry Active Waste (Compactible and Non-Compactible) 3.
Irradiated Components (Non.Combustible Solid):
There were no shipments.
Other:
(To Vendor for Processing or Consolidation) a, Asbestos (Compactible) b.
Irradiated Components c.
DiyActive Waste (Compactible and Non-Compactible) d.
Resins (Solidified)
(Dewatered) e.
Metal (scrap)
(Compactible and Non-Compactible)
ATTACHMENT6 Pa e3of7 Unit I~
Unit 2 Reporting Period SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.2 ESTIMATE OF MA30R NUCLIDECOMPOSITION (BYTYPE OF WASTE) a.
Spent Resins, Filter Sludges, Concentrated Waste:
~li (1) Co-60 (2) Fe-55 (3) Cs-137 (4) Ni-63 (5) Mn-54 (5) Other 5.61E+01 2.12E+01 I 40E+01 3.80E+00 3.08E+00 1.82E+00 b.
Dry Compactible Waste, Dry Non-Compactible Waste (Contaminated Equipment):
Halide (1) Co-60 (2) Cs-137 (3) Mn-54 (4) Fe-55 (5) Ce-144 (6) Co-58 (7) Other Brmt 6.09E+01 1.68E+01 1.64E+01 2.67E+00 1.22E+00 1.00E+00 1.01E+00 c.
Irradiated Components:
There were'no shipments for direct burial.
d.
Other:
1.
Asbestos (Solid)
~ulid (1) Co-60 (2) Mn-54 (3) Cs-137 (4) Fe-59 (5) Cr-51 (6) Sr-90 (7) Co-58 (8) Other Emend 4.55E+01 1.69E+01 1 46E+01 1.13E+01 5 40E+00 1.72E+00 1.70E+00 2.88E+00 2.
Irradiated Components
~ucli (1) Co-60 (2) Mn-54 (3) Cs-137 (4) Cs-134 (5) Ni-63 (6) Ce-144 (7) Other Eecml 8.03E+01 6.96E+00 5.25E+00 3.23E+00 2.01E+00 1.84E+00 4.10E-01
ATTACHMENT6 Pa e4of7 Unit1~
Unit 2 d.
Other:
(Cont) 3.
DAW Reporting Period SOLID WASTE AND IRRADIATEDFUEl SHIPMENTS
~l'1) Co-60 (2) Mn-54 (3) Cs-137 (4) Fe-59 (5) Cr-51 (6) Co-58 (7) Sr-90 (8) Other Peerc g 4.50E+01 1.69E+01 1.45E+01 1.17E+01 5.75E+00 1.74E+00 1.70E+00 2.71E+00 4
Resins
~uclid (1) Co-60 (2) Mn-54 (3) Ni-63 (4) Cs 137 q( (jl +JjA (5) Other
~e 8.96E+01 447E+00 2.34E+00 2.00E+00 1.59E+00 5.
Metal (Scrap)
Halide (1) Co-60 (2) Mn-54 (3) Cs-137 (4) Fe-59 (5) Cr-51 (6) Co-58 (7) Sr-90 (8) Other 4.54E+01 1.69E+01 1 46E+01 1.14E+01 5.51E+00 1.72E+00 1.71E+00 2.76E+00
~ ~l(e
ATTACHMENT6 Pa e5of7 Unit1~
Unit 2 Reporting Period SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS A.3.
SOUD WASTE DISPOSITION:
DmtinnIIgn
~
Barnwell Facility QnrnndLRQ ATG BMundMh CNSI Consolidation Facility Garnbol~
GTS Duratek QalsRhLm~
B.
IRRADIA'TEDFUEL SHIPMENIS (DISPOSITION):
There were no shipments.
4>> ~
ATTACHMENT6 Pa e6of7 Unit1~
Unit 2 Reporting Period SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS C.
SOUD WASTE SHIPPED OFF-SITE TO VENDORS FOR PROCESSING ANDSUBSEQUENT BURIAL Below is a summaiy of NMP-1radwaste buried by vendor facilities during
. These totals were reported separately from "10CFR61 Solid Waste Shipped for Burial" since (a) waste classification and burial was performed by the vendors, and (b) Technical Specification 6.9.1 requires reporting of "information for each class of solid waste (as defined by 10CFR61) shipped off-site during the reporting period." The following data represents the actual shipments made from the off-site vendors of our radwaste (e.g., non-compacted trash, dry non-compressible waste, asbestos and resins) that was processed and commingled prior to burial.
C.l.
TYPE OF WASTE - Noncompacted trash, and/or dry non-compressible waste, asbestos and resins processed by vendor facilities prior to burial.
Burial Volume
~3 Activity
~i Est. Total grIoOs C.2.
ESTIMATE OF MATORNUCLIDECOMPOSITION (1) Co-60 (2) Cs-137 (3) Mn-54 (4) C-14 (5) Fe-55 (6) Ce-144 (7) Co-5S (8) Ni-63 (9) Cs-134 (10) Other
~er n"
>>((
6.%2E+01 1.55E+01 6 46E+00 4.35E+00
'.93E+00 1.97E+00 1.45E+00 1.33E+00 1:17E+00 6.40E-01 C.3.
SOUD WASTE DISPOSITION bro i
Mode f n
ATTACHMENT6 Pa e7of7 Unit 1~
Unit 2 Reporting Period SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS D.
SEWAGE WASTES SHIPPED TO ATREATMENTFACILITYFOR PROCESSING AND BURIAL There were no shipments of sewage sludge with detectable quantities of plant-related nuclides from NMP to the treatment facilityduring the reporting period.
ATTACHMENT7 Unit1~
Unit 2 Reporting Period
SUMMARY
OF CHANGES TO THE OFF-SITE DOSE CALCULATIONMANUAL
'The Unit 1 Offsite Dose Calculation Manual (ODCM) was revised during the reporting period to reflect the actual plant configuration. The ODCM changes willnot reduce the accuracy or reliabilityof the dose calculations or setpoint determinations in accordance with Technical Specifications.
A copy of the ODCM, Revision 20 is attached and a summary of the changes presented to and approved by the Station Operations Review Committee In September 1999 is provided below. The summary also includes the ustiflication for the chan es.
Old Page 0 New Page 0 New/Amended Section 0 Change Reason for Change D.l Figure D-1 Remove the blank flange shown in the Waste Sample Tanks'ischarge line fust before the discharge flowcontrol valves.
This change revises Figure D-1 to more accurately depict the equipment associated with radioactive waste liquid discharge piping. This change does not reduce the defense-in-depth for an inadvertent discharge because there are locked closed valves before and after the discharge monitoring equipment as well as the two blank fianges after the discharge flow control valves.
jl
ATTACHMENT8 Unit 1~
Unit 2 Reporting Period
SUMMARY
OF CHANGES TO THE PROCESS CONTROL PROGRAM There were no changes to the Unit 1 PCP during the reporting period.
0
ATTACHMENT9 Unit I~
Unit 2 Reporting Period
SUMMARY
OF INOPERABLE MONITORS There were no inoperable monitors for a period greater than 30 days during the reporting period.
ATTACHMENT10 1of4 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT (1999)
NINE MILE< POINT NUCLEARSTATIONUNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY JANUARY-DECEMBER 1999 Doses to members of the public (as defined by the Technical Specifications) from the operation of the NMP1 facility as a result of activity inside the site boundary are based on activities at the Energy Center located approximately one quarter mile west of NMP1. This facility is open to the public and offers educational information, summer picnicking activities and fishing. Any possible doses received by a member of the public by utilizing the private road that transverses the east and west site boundaries are not considered here since it takes a matter of minutes to travel the distance.
The activity at the Energy Center that is used for the dose analysis is fishing near the shoreline adjacent to the NMP site.
Dose pathways considered for this activity include direct radiation, inhalation and external ground (shoreline sediment or soil) doses.
Other pathways, such as ingestion pathways, are not considered because they are either not applicable, insignificant, or are considered as part of the evaluation of the total dose to a member of the public located off-site. In addition, only releases from the NMP1 stack and vent were evaluated for the inhalation pathway.
The direct radiation pathway is evaluated in accordance with the methodology found in the Off-Site Dose Calculation Manual (ODCM). This pathway considers three components: direct radiation from the generating facilities, direct radiation from any possible overhead plume and direct radiation plume submersion.
The direct radiation pathway is evaluated by the use of high sensitivity environmental Theimoluminescent Dosimeters (TLDs). Since any significant fishing activity near the Energy Center occurs between Aprilthrough December, environmental TLD data for the approximate period of April 1 - December 31, 1999 were considered.
Data from environmental TLDs from the approximate area where the fishing occurs were compared to control environmental TLD locations for the same time period.
The average fishing area TLD dose rate was 7.8E-03 mRem per hour for the period.
The average control TLD dose rate was 6.5E-03 mRem per hour for the period (approximate second, third and fourth calendar quarters of the year).
The average increase in dose as a result of fishing in this area at a conservative frequency of eight hours per week for thirty-nine weeks is 4.0E-01 mRem from direct radiation for the period in question.
The majority of the dose from this pathway is from the NMP1 facility because of its proximity to the fishing area.
A small portion may be due to the NMP2 facility.
ATTACHMENT10 Page 2 of 4 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT (1999)
NINEMILEPOINT NUCLEARSTATION UNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE< SITE< BOUNDARY JANUARY-DECEMBE<R 1999 The inhalation dose pathway is evaluated by utilizing the inhalation equation in the ODCM, as adapted from Regulatory Guide 1.109.
The equation basically gives a total inhalation dose in mRem for the time period in question (April-December).
The total dose equals the sum, for all applicable radionuclides, of the NMP1 stack and vent release concentrations, times the average NMP1 stack and vent flowrate, times the applicable five-year average calculated X/Q, times the inhalation dose factors from Regulatory Guide 1.109, Table E-7, times the Regulatory Guide 1.109 annual air intake, times the fractional portion of the year in question.
In order to be slightly conservative, no radiological decay is assumed.
1999 calculation utilized the following information:
NMP1 Stack:
~
Unit 1 average stack flowrate = 1.12E+02 m'/sec
~
X/Q value = 8.9E-06 (annual NWN sector, historical average)
~
Inhalation dose factor = Table E-7 of Regulatory Guide 1.109
~
Annual air intake = 8000 m'er year (adult)
~
Fractional portion of the year = 0.0356 (312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br />)
~
Co-60 = 4.50E-01 pCi/m' Fe-55 = 2.15E-01 pCi/m' Sr-89 = 1.46E-01 pCi/m' Sr-90 = 1.65E-02 pCi/m' H-3 = 1.04E+04 pCi/m' I-131 = 7.28E-02 pCi/m' I-133 = 2.63E-01 pCi/m' Cs-137 = 1.01E-02 pCi/m' Cr-51 = 5.58E-02 pCi/m' Co-58 = 1.35E-02 pCi/m' Mn-54 = 1.06E-01 pCi/m' Fe-59 = 2.80E-02 pCi/m'
ATTACHMENT10 Page 3 of 4 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT (1999)
NINEMILEPOINT NUCLE<AR STATIONUNIT 1 DOSES TO ME<MBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY JANUARY-DECEMBER 1999 Emergency Condenser Vent:
~
Average vent flowrate = 3.02E-04 m'/sec
~
X/Q value = 6.63E-06 (conservative ground level value)
~
Inhalation dose factor = Table E-7 of Regulatory Guide 1.109
~
Annual Air intake = 8000 m'er year (adult)
~
Fractional portion of the year = 0.0356 (312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br />)
~
Sr-89 = 3.17E+01 pCi/m' Sr-90 = 7.58E+00 pCi/m' Co-60 = 6.04E+02pCi/m'II
~
Mn-54 = 4.32E+01 pCi/m' Fe-55 = 3.99E+02 pCi/m' H-3 = 5.29E+09 pCi/m' Cr-51 = 1.69E+01 pCi/m' Cr-58 = 1.65E+01 pCi/m'he inhalation dose to a member of the public from NMP1 as a result of activities inside the site boundary is 1.1E-03 mRem to the lung (maximum organ dose) and 9.3E-04 mRem to the whole body.
The dose from standing on the shoreline while fishing is based on the methodology in the ODCM, as adapted from Regulatory Guide 1.109.
During 1999, it was noted that fishing was performed from the shoreline on many occasions although waders were also utilized. In order to be conservative, it is assumed that the maximum exposed individual fished from the shoreline at all times.
The use of waders, of course, would result in a dose of zero from this pathway.
The ODCM equation gives the total dose to the whole body and skin from the sum of all plant-related radionuclides detected in shoreline sediment samples.
The plant-related radionuclide concentration is adjusted for background sample results, as applicable.
The equation, therefore, yields the whole body and skin dose by multiplying the radionuclide concentration adjusted for any background data (as applicable), times a usage factor, times the sediment or soil density in grams per square meter (to a depth of one centimeter), times the applicable shore width factor, times the regulatory guide dose factor, times the fractional portion of the year over which the dose is applicable.
In order to be conservative and to simplify the equation, no radiological decay is assumed since the applicable radionuclides are usually long lived.
ATTACHMENT10 Page 4 of 4 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT (1999)
NINE MILEPOINT NUCLEARSTATION UNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE< SITE BOUNDARY JANUARY-DE<CE<MBER 1999 The calculation utilized the following information:
~
Usage factor = 312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br />
~
Density in grams per square meter = 40,000
~
Shore width factor = 0.3
~
Whole body and skin dose factor for each radionuclide = Regulatory Guide 1.109, Table E-6
~
Fractional portion of the year =
1 (used average radionuclide concentration over total time period)
~
Average Cs-137 concentration = 0.21 pCi/g The total whole body and skin dose from standing on the shoreline to fish is 3.3E-03 mRem whole body and 3 ~ 8E-03 mRem skin dose for the period.
Doses to members of the public relative to activities inside the site boundary from aquatic pathways other than ground dose from shoreline sediment/soil are not applicable.
In summary, the total dose to a member of the public as a result of activities inside the site boundary from the direct radiation, inhalation and shoreline dose pathways is 4.0E-Ol mRem to the whole body and 1.1E-03 mRem to the maximum exposed internal organ (lung). The dose to the skin of an adult is 3 ~ 8E-03 mRem.
These doses are generally a result of the operation of NMP1. However, a portion of these doses for the direct radiation pathway may be attributable to the NMP2 facility.
ATTACHMENT11 Page 1 of 4 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT (1999)
NINEMILEPOINT NUCLEARSTATIONUNIT 1 DOSE<S TO MEMBERS OI<'HE< PUBLIC DUE TO THE<IR ACTIVITIES OUTSIDE< THE SITE BOUNDARY JANUARY-DE<CEMBER 1999 Radiation doses to the likely most exposed member of the public outside of the site boundary are evaluated relative to 40CFR190 requirements.
The dose limits of 40CFR190 are 25 mRem (whole body or organ) per calendar year and 75 mRem (thyroid) per calendar year.
The intent of 40CFR190 also requires that the effluents of NMP1, as well as other nearby uranium fuel cycle facilities, be considered.
In this case, the effluents of NMP1, NMP2 and the James A.
FitzPatrick (JAF) facilities must be considered.
Doses to the likely most exposed member of the public as a result of effluents from the site can be evaluated by using calculated dose modeling based on the accepted methodologies of the facilities'ff-Site Dose Calculation Manuals (ODCMs) or may, in some cases, be calculated from the analysis results of actual environmental samples.
Acceptable methods of calculating doses from environmental samples are also found inthe facilities'DCMs.
These methods are based on Regulatory Guide 1.109 methodology.
Dose calculations from actual environmental samples are, at times, difficultto perform for some pathways.
Some pathway doses should be estimated using calculational dose modeling.
These pathways include noble gas air dose, inhalation dose, etc.
Other pathway doses may be calculated directly from environmental sample concentrations using Regulatory Guide 1.109 methodology.
Since the effluents from the generating facilities are low, the resultant gaseous and liquid effluent doses are anticipated to be low. In view of this, doses can be based on calculated data.
Doses are not based on actual environmental data for 1999 with the exception of doses from direct radiation, fish consumption and shoreline sediment.
In addition, in order to be conservative and for the sake of simplicity, it is assumed in the dose calculations that the likely most exposed member of the public is positioned in the maximum receptor location for each pathway at the same time. This approach is utilized because the doses are very low and the computations are greatly simplified.
ATTACHMENT11 Page 2 of 4 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT (1999)
NINEMILEPOINT NUCLEARSTATION UNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY JANUARY-DECEMBER 1999 The following pathways are considered:
1.
The inhalation dose is calculated at the critical residence because of the high occupancy factor. In order to be conservative, the maximum whole body and organ dose assumes no correction for residing inside a residence.
2.
The milk ingestion dose is calculated utilizing the critical milk cow location.
As noted previously, in order to be conservative and for the sake of simplicity, the likely most exposed member of the public is assumed to be at all critical receptors at one time. In this case, the member of the public at the critical residence is assumed to consume milk from the critical milk location.
3.
The maximum dose from the milk ingestion pathway as a result of consuming goat's milk is based on the same criteria established for item "2", above (ingestion of cow's milk).
4.
The maximum dose associated from consuming meat is based on the critical meat animal.
The likely most exposed member at the critical residence is assumed to consume meat from the critical meat animal location.
5.
The maximum site dose associated with the consumption of vegetables is calculated from the critical vegetable garden location.
As noted previously, the likely most exposed member of the public is assumed to be located at the critical residence and is assumed to consume vegetables from the critical garden location.
The dose, as a result of direct gamma radiation from the site, encompasses doses from direct "shine" from the generating facilities, direct radiation from any overhead gaseous plumes, plume submersion and from ground deposition.
This total dose is measured by environmental TLDs. The critical location is based on the closest year-round residence from the generating facilities as well as the closest residence in the critical downwind sector in order to evaluate both direct radiation from the generating facilities and gaseous plumes as determined by the local meteorology.
During 1999, the closest residence and the critical downwind residence were at the same location.
Page 3 of 4 ATTACHMENT11 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT (1999)
NINE MILEPOINT NUCLEARSTATION UNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY JANUARY-DECEMBER 1999 The measured average dose rate for 1999 at'the critical residence was 13.9 mRem/qtr.
The average control dose rate was also 13.9 mRem/qtr.
The dose at the critical residence can be considered representative of the background dose since the control location dose rate and the critical residence dose rate were the same.
Therefore, no net dose was calculated and was assumed to be zero for this pathway.
The dose, as a result of fish consumption, is considered as part of the aquatic pathway.
The dose for 1999 is calculated from actual results of the analysis of environmental fish samples.
For the sake of being conservative, the average plant-related radionuclide concentrations were utilized from fish samples taken near the site discharge points.
The only plant-related radionuclide detected in fish samples was Cs-137.
This nuclide was detected in one sample taken from Nine Mile Point. Utilizingthe methodology given in the ODCMs, as adapted from Regulatory Guide 1.109, doses were calculated.
The calculations yielded doses of 3.7E-02 mRem to the liver and 2.4E-02 mRem to the whole body.
8.
The shoreline sediment pathway is considered relative to recreational activities.
The dose due to recreational activities from shoreline sediment is based on the methodology in the ODCM, as adapted from Regulatory Guide 1.109.
The ODCM gives the total dose to the whole body and skin from the sum of plant-related radionuclides detected in actual shoreline sediment samples.
The plant-related radionuclide concentration is adjusted for background sample results, as applicable. The total whole body and skin dose from shoreline recreational activities are 2.5E-04 mRem whole body and 2.9E-04 mRem skin dose for the period.
In summary, the maximum dose to the likely most exposed member of the public is 4.2E-02 mRem to the thyroid (maximum organ dose) and 4.2E-02 mRem to the whole body. It should be noted that the maximum organ dose and maximum whole body doses are based on the sum of the maximum doses observed for all three facilities regardless of age group.
This results in some conservatism.
The maximum organ and whole body doses were a result of gaseous effluents.
ATTACHMENT11 Page 4 of 4 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT (1999)
NINEMILEPOINT NUCLEARSTATIONUNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Doses as a result of liquid effluents were secondary.
The total whole body and skin dose from shoreline recreational activities are 2.5E-04 mRem whole body and 2.9E-04 mRem skin dose for the period.
The direct radiation dose to the critical residence from the generating facilities was insignificant or zero.
The dose to an individual as a result of fish consumption was 3.7E-02 mRem to the liver and 2.4E-02 mRem to the whole body.
These maximum total doses are a result of operations at the NMP1, NMP2 and the JAF facilities. The maximum organ dose and whole body dose are below the 40CFR190 criteria of 25 mRem per calendar year to the maximum exposed organ or the whole body, and below 75 mRem per calendar year to the thyroid.
ATTACHMENT12 Update of Actual Data for the Second Quarter 1999
Unit1~
Unit 2 Reporting Period Pa elof1 UPDATE OF RELEASE AND DOSE DATAFOR GASEOUS (ELEVATEDAND GROUND LEVEL)AND LIQUIDEFFLUENTS Update of data using actual results from the off-sito vendors for Strontium, Tritium, and Iron-55 for the second quarter 1999.
GASEOUS LIQUID nd Sr-89 Sr-90 H-3 Fe-55
- 1. Particulates with half-lives >8 days
- 2. Average release rate for period
- 1. Total release
- 2. Average release rate for period Ci pO/sec (gaseous)
PCI/ml (liquid)
Ci pCI/sec (gaseous) pCI/ml (liquid) f&K~+
- KEEU, GAAj=OIJ) 2 HH5 9 SKl2 1.
Percent of Quarterly Dose Umit 2.
Percent of Annual Dose Umitto Date'.
Percent of Organ Dose Rate Limit (Gaseous)(Quarterly)
-Dose Umit (Uquid)
(Quarterly &Annual)
Percent of 10CFR20 Concentration Umit'Uquid) 5.
Percent of Dissolved or Entrained Noble Gas (Uquid)
XKIUL1 (Quarterly) 289K~
(Annual)
Z HHQ (Quarterly)
(Quarterly) 18~
(Annual)
- R2ZUU, (Quarterly)
- XJHM, (Annual)
Concentrations less than the lower limitof detection, as required by Technical Specifications or station procedures are Indicated with a double asterisk.
The dose is to the whole body for liquid effluents and to the maximally exposed organ for gaseous effluents.
'The ercent of the 10CFR20 concentration limitis based on the avera e concentration durin the uarter.