ML19256D702
| ML19256D702 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/07/1977 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19256D696 | List: |
| References | |
| NUDOCS 7910220619 | |
| Download: ML19256D702 (10) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET N0.
50-289 METROPOLITAN EDISON COMPANY NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSES AND NEGATIVE DECLARATION The U.S. Nuclear Regulatory Commission (the Commission) has issued Amendment No.
to Facility Operating License No. DPR-50, issued to Metropolitan Edison Company, for revised Technical Specifications for operation of the Three Mile Island Nuclear Station, Unit No.1, located in Dauphin County, Pennsylvania. The amendments are effective as of the date of issuance.
This ame,ndment to tne Technical Specifications will (1) implement the requirements of Appendix I to 10 CFR Part 50, (2) establish new
~
limiting conditions for operation (LCO) for the quarterly and annual average release rates, and (3) revise environmental monitoring programs to assure confonnance with Commission regulations.
The application for the amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment.
Prior public notice of this amendment was not required since the an.9ndment does not involve a significant hazara consideration.
1453 080 7910220 6/7
, The Commission has prepared an envirc-mantal impact appraisal for the revised Technical Specifications and has concluded that an environ-mental impact statement for the particular action is not warranted because there will be no significant effect on the quality of the human environment beyond that which has already been predicted and described in the Commission's Final Environmental Statement for the facility dated For further details with respect to this r.ction, see (1) the applica-tion for amendments dated
, (2) Amendment No.
to License No. DPR-50, and (3) the Commission's related Safety Evaluation and Environ-mental Impact Appraisal. All of these items are available for public inspection at the Commission's Public Document Room,1717 H Street, N.W.,
Washington, D.C., and at the State Library of Pennsylvania, Government P6blication Section, Education Building, Harrisburg, Pennsylvania. A copy of items (2) and (3) may be obtained upon request addressed to the U.S.
Nuclear Regulatory Commission, Washington, D.C., 20555, Attention:
- Director, Division of Operating Reactors.
Dated at Bethesda, Maryland this day of FOR THE NUCLEAR REGULATORY COMMISSION Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors 1453 081
Table 1 CALCULATED RELEASES OF RADIOACTIVE MATERIALS IN LIQUID EFFLUENTS FROM THREE MILE ISLAND NUCLEAR STATION, UNIT NO.1 FOR APPENDIX I EVALUATIONS Nuclide Ci/Yr Nuclide Ci/yr Corrosion / Activation Products Fission Products (continued)
Cr-51 1.9 (-4)
Te-129 8 (-5)
Mn-54 1(-3)
I-130 7(-5)
Fe-55 2 (-4)
Te-131m 4 (-5)
Fe-59 1(-4)
I-131 5(-2)
Co-58 5.8(-3)
Te-132
- 1. l (-3)
Co-60 8.9(-3)
I-132 1.6 (-3)
Zr-95 1.4 (-3)
I-133 1.7 (-2)
Nb-95 2 (-3)
I-134 1(-5)
~
6 (-5)
Cs-134 2.9 (-2)
Np-239
~1 Fission Products Cs-136 3.3 (-3)
Br-83 3 (-5)
Cs-137 3.5(-2)
Rb-86 2(-5)
Ba-137m 9.1 (-3)
Sr-89' 4 (-5)
Ba-140 2(-5)
Sr-91 1(-5)
La-140 1(-5)
Mo-99 3.9 (-2)
Cc-144 5.'2 (-3)
Tc-99m 2.4 (-2)
All Others
- 6(-5)
Ru-103 1.4( 4)
Total
- 2.5 (-1)
Ru-106 2.4 (-3) except H-3 Ag-110m 4.4 (-4)
.H-3 5(+2)
Te-127m 3(-5)
Te-127 4 (-5)
~
Te-129m 2.3 (-4) 1453 082
TABLE 2 CALCULATED RELEASES OF RADIOACTIVE MATERIAL IN GASEGUS EFFLUENTS FROM THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 Ci/Yr Radio d Reactor Auxiliary Turbine Air Decay Nuclide Building Building Building Ejector Tanks Total Kr-83m a
a a
a e
a Kr-85m 1
1 a
a a
2 Kr-85 320 7
a 4
560 890 Kr-87 a
a a
a a
a Kr-88 2
2 a
1 a
5 Kr-39 a
a a
a a
a Xe-131m 54 2
a 1
6 63 Xe-133m 33 3
a 2
a 38 Xe-133 5500 240 a
150 25 5900 Xe-135m a
a a
a a
a Xe-135 9
4 a
3 a
16 Xe-137 a
a a
a a
a Xe-138 a
a a
a a
a TOTAL NOBLE GASES 6,900 I-131 0.00039 0.0049 0.001 0.031 a
0.037 I-133 0.00031 0.0053 0.0011 0.032 a
0.039 Mn-54
- 2. 6 (-6) 1.8(-4) c c
- 4. 5 (-5) 2.3(-4)
Fe-59 8.7(-7) 6 (-5) e c
1.5 (-5) 7.6(-5)
Co-58 8.7(-6) 6(-4) e c
1.5(-4) 7.6(-4)
Co-60 4(-6) 2.7(-4) c c
7(-5)
- 3. 4 (-4)
Sr-89 2 (-7) 1.3(-5) e c
3.3 (-6) 1.6(-5)
- 3. 5 (-8)
- 2. 4 (-6) e c
6(-7) 3 (-6)
Cs-134 2.6(-6) 1.8(-4) e c
4.5(-5)
- 2. 3 (-4)
- 4. 4 (-6) 3(-4) e c
- 7. 5 (-5) 3.8(-4)
TOTAL PARTICULATES 2(-3)
e e
c 7
8 Ar-41 25 e
e c
c 25 less than 1.0 Ci/yr/ reactor for noble gases and carbon-14, less than 10'# Ci/
a 4
yr/ reactor for iodine,
-6 b = exponential nota: ion; 2.6(-6) = 2.6 x 10 c = less than 1% of total for this nuclide.
d = radionuclides not listed are released in quantities less than those specified in notes a and c from all sources.
1453 083
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TABLE 3 PRINCIPAL PARAMETERS AND CONDITIONS USED IN CALCULATING RELEASES OF RADIOACTIVE MATERIAL IN LIQUID AND GASEOUS EFFLUENTS FROM THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 Reactor Power Level (MWt) 2535 Plant Capacity Factor 0.80 "
Failed Fuel 0.12'6 Primary System 5
Mass of Coolant (1bs) 7.4 x 10 Letdown Rate (gpm) 45 Shim Bleed Rate (gpd) 100 480 Leakage to Secondary System (1b / day)
Leakage to Containment Building b
Leakage to Auxiliary Buildings (1bs/ day) 160 Frequency of Degassing for Cold Shutdowns (per yr) 2 Secondary System 7
Steam Flow Rate (1bs/hr) 1.1 x 10.,
Mass of Steam / Steam Generator (1bs) 1.4x10j Mass of Liquid / Steam Generator (1bs) 2.7 x 106 Secondary Coolant Mass (1bs) 2 x 10 3 Rate of Steam Leakage to Turbine Bldg (1bs/hr) 1.7 x 10 3
6 Containment Building Volume (ft )
2 x 10 Annual Frequency of Containment Purges (shutdown) 4 Annual Frequency of Containment Purges (at power) 20 Iodine Partition Factors (gas / liquid)
Leakage to Auxiliary Building 0.0075 Steam Generator (carryover) 1.0 Main Condenser Air Ejector (volatile species) 0.15 Decontamination Factors (liquid wastes)
Shim Bleed Miscellaneous Laundry And And Eq. Drain Waste Chain Hot Shower Drain I
1 x 10 1 x 10 1
1 x 10*5 Cs, Rb 2 x 10 l
Others 1 x 10 1 x 10 1
All Nuclides Except Iodine Iodine Miscellaneous (Dirty) Waste 10 10 Evaporator DF 3
Shim Bleed 6 Equipment Drain 10 10' Evaporator DF Anions Cs, F.b Other Nuclides Letdown Coolant Waste 10 2
10 Deminerali:ers DF Evaporator Condensate Polishing 10 10 10 Demineralizers DF Condensate-Feedwater Deminerali:ers 10 2
10 (PONDEX) DF 1453 084
TABLE ;
(Continued) Auxiliary and Fuel Handling Building Charcoal Adsorber DF and Containment Recirculating 10 Cleanup System Charcoal Adsorber DF (Iodine Removal)
HEPA Filter DF and Containment Recirculating Cleanup System HEPA Filter DF 100 1453 085 9
e
TABLE 4
SUMMARY
OF OPERATING EXPERIENCE FOR EREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 DOCKET NC. 50-289 Liould Release Data July 1, 1974 through December 31, 1974 1975 1976 (6 months) Curies
- Curies
- Curies **,
- Total Fission 5 Activation Products 0.04 0.065 0.1 Total Iodine-131 0.0092 0.0046 0.0022 Total Tritium 130 460 190 Gaseous Effluent Release Data Total Noble Gases 916 3600 2800 Total Indine-131 0.0028 0.00092 0.0061 Total Halogens 0.0031 0.00094 0.0061 Total Particulates 0.00025 0.00009 0.0044 Total Tritium 13 40 720
- Source:
Semi-Annual Operating Reports for Three Mile Island Nuclear Station, Unit No.1, for periods Julv, 1974 through December 31, 1974, January 1, 1975 through June 30, 1975, July 1, 1974 through December 31, 1975, and January 1, 1976 thrcugh June 30, 1976.
- Source: Semi-Annual Effluent Release Report for Three Mile Island Nuclear Station, Unit No. 1, for period July 1, 1976 through December 31, 1976.
1453 086
TABLE 5 TilREE MILE ISI.AND, UNIT NO. 1 RELATIVE CONCENTitATION (X/Q) AND DEPOSITION VALUES (D/Q)
USED FOR DOSE CALCULATIONS Distance X/Q D/Q,,
Receptor Type Direction (miles)
Release Type (sec/ met ers'3)
(meters ')
-6 Site Boundary W
0.11 Reactor Bldg Vent #1 - continuous 1.8 x 10 1.5 x 10' Reactor Bldg Vent #1 - Purge 7.6 x lo-6.3 x l' '
Reactor Bldg Vent #2 - Purge 3.1 x 10 1.7 x 10 Turbine Bldg Air Ejector Vent - cont.
3.7 x 10 5.4 x 10 Turbine Bldg Vent - continuous 3.7 x 10~
5.4 x 10' Maximum Individual N
1.0 Reactor Bldg Vent #1 - continuous 1.2 x 10-2.2 x 10-Reactor Bldg Vent #1 - Purge 4.3 x 10-7.9 x 10~
-6 Reactor Bldg Vent #2 - Purge 1.2 x 10 1.1 x 10~
-6 Turbine Bldg Air Ejector Vent - cont.
6.0 x 10 9.6 x 10~
-6 Turbine Bldg Vent - continuous 6.0 x 10 9.6 x 10' O
LD U
CD CD N
/
/
s
/
TABLE &
[
CC:@ARISON OF CALCUIJTED DCSES FP.CM OPEPATICN
./
WITH SECTIONS II.A, II.B, AND II.C CF APPENDIX I TO 10 CFR PART 50 (Dose to Maxist=t Individual)
Appendix I Dose Calculated Criterion Desi m O'ojective Doses Liquid Effluents Dose to total body from all pathways 3 mres/yr 1.8 mrem /yr Dose to any organ frcm all pathways 10 mres/yr 2.4 mrem /yr Noble Gas Effluents Gamma dose in air 10 mrad /yr 3.1 mrad /yr Beta dose in air 20 mrad /yr 8.9 mrad /yr Cose to total body of an individual 5 mrem /yr
, _ _ _ _ _ 1,8 mrea/yr Dose.to skin of an individual 15 mrem /yr 5.5 mrea/yr i
Radiciodine and Particulates" Dose to any organ frem all pathways 15 = rem /yr 6.1 mrea/yr
" Carbon-14 and Tritium have been added to this category.
1453 088'
TAB LE 7 '
CALCULATED PCPULATION DOSES (MAN-REM) FOR COST-SENEFIT ANALYSIS, SECT!ON II.D CF APPENDIX I TO 10 CFR PART 50*
Pat _hway Total Body Th5roid Liquid
_6.a t
~
12 Gas eous 6.6 14
- Based on the population reascnably expected to be within a 50 mile radius of the reactor.
TABLE 8 PRINCIPAL PARAMETERS USED IN THE COST-BENEFIT ANALYSIS Labor Cost Correction Factor, FPC Region I )
1.6 E
~
Cost of Money )
10%
~
Chpital Recovery Factor 0.1061 a)Frem Regulatory Guide 1.110, Cost-Benefit Analysis for Radwaste Systems
~
for Light-Nater-Cooled Nuclear Reactors C4 arch 1976).
b) The licensee 'did not provide a value for his cost of money; the value of 10% was derived from a recent annual report and prosp=.ctus, c)The licensee provided a value of 16% as his Capita 1 Recovery Factor.
The value of 16% is not consistent with the licensee's cost of money and a 30-year recovery period, and would be more appropriate as a fixed charge rate; therefore the staff assumed a value of 0.1061 for the Capital Recovery Factor. This assumption does not change the results of the staff's evaluation.
1453 ONB9
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