ML19347A753
| ML19347A753 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/16/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML19347A754 | List: |
| References | |
| DPR-51-A-046, NPF-06-A-015 NUDOCS 8009300148 | |
| Download: ML19347A753 (19) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION C
WASHINGTON, D. C. 20555
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ARKANSAS POWER AND LICHT COM,aNY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE, UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 46 License No. DPR-51 h
4 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Arkansas Power and Light Company (the licensee) dated October 31, 1979, conplies with the standards and requirenents of the Atomic Energy Act of 1954, as amended t
(the Act), and the Commission's rules and regulations set forth I'
in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the
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provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
a 9009300148
T 65)
- 2.
Accordingly, the license is anended by changes to the Technical Specifications as indicated in the attachment to this license amendnent, and paragraph 2.C.(2) of Facility Operating License No. DPR-51 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices l
A and B, as revised through Amendment No. 46, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifica-tions.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Ou :l D
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'&t Rdbert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: Septen.be r 16, 1980 e
e l
ATTACHMENT TO LICENSE AMENDMENT NO. 46 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET N0. 50-313 Replace ine following pages of the Appendix B Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment Number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document com-pleteness.
Pages 2-9 2-12 2-14a (new) k 6
e d
A
l 2-9 I
i 2.4 Radioactive Discharge Objective I
4 To define the limits and conditions for the controlled release of radioactive effluents to the env tons to ensure that these releases e
are as low as practicable.
These releases should not result in radiation exposures in unrestricted areas greater than a few per-cent of natural background exposure.
The release rate for all effluent discharges should be within the limits specified in 10 CFR Part 20.
To assure that the release of radioactive material to unrestricted areas meets the as-low-as practicable concept, the following objectives ;
apply:
For Liquid Wastes:
The annual total quantity of radioactive materials in liquid a.
waste, excluding tritium and dissolved gases, should not exceed 5 curies; b.
The annual average concentration of radioactive caterials t{
in liquid waste upon release from the Restricted Area, ex-cluding tritium and dissolved noble gases, shall not exceed
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2 x 10-8 uCi/ml; and The annual average concentration of dissolved gases in liquid c.
i vaste, upon release from the Restricted Area, shall not exceed 2 x 10-6 uCi/ml.
For Caseous Wastes:
a.
Averaged over a yearly interval, the release rate of noble p
gases and other radioactive isotopes, except I-131 and par-ticulate radioisotopes with half-lives greater' than eight days, discharged from the plant should be limited as follows:
1
{10 mrad /yr g
'F
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IK Q i i i -
20 mrad /yr 8 i
Where Q, is the release rate in Ci/sec for radionuclide i and Ki is tiie gamma air dose factor or the beta r.ir dose factor for each identified noble gas radionuclide, in mrad /yr per Ci/sec, defined as follows:
Ky = 4.0 x 106 (air dose factor for 1), where
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the air dose factor for radionuclide i is per Table B-1 of Regulatory Guide 1.109, Rev.1, D
October 1977.
},
L Amendment No. 46
2-10 J
b.
Averaged c ver a yearly interval, the ' release rate of I-131 and other particulate ' radioisotopes with half lives longer than eight days
[
discharged from the plant should result in a dose in the unrestricted area of less than 15 mrem to the thyroid of a child through the 1
1 gras s-cow-cilk chaitt.
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2.
.1 Liould Discharge fp N $fCation 1.
The rate of release of radioactive r.aterials in liquid ~ waste from the plant shall be controlled such that the instantaneous concentrations of radioactivity in liquid waste, upon. releaise from the Restricted Area, do not exceed the values listed in 10 CFR 20, Appendix B, Table II, Cole = 2.:
2.
If the cumulative release of radioactive materials in liquid
- effluents, excluding trit'ium and dissolved gases, over a calendar quarter, exceeds 2.5 curies, the Licensee shall
Make an investigati:2 to identify the causes for such a.
release rates; b.
Define and u tiate a progrs= of action to reduce'such.
release rates to the design levels; a:dd, Uctify the Dire:::r, Oirectorate of Licensing within. 30 c.
days, identif ying f.e tauses and describing the proposed prog-s::s of actic c
educe such release rates.
3.
Tne release rate of radicactive liquid effluents, excluding tritius and dissolved gases, shall not exceed 10 curies during any calendar quarter.
4.
During release of liquid radioactive aste, the follcwing con-ditions shall be ret:
a.
At least twe (2) condenser circulatint water pu=ps shall be in operation to provide a r.inist--
.lon flow of approximately 333,000 gpa in the di_,s
- e canal for the liquid waste effluent; b.
The etfluent control =onitor shall be set to alarm and auto-matienlly close the vaste discharge valve such that the re-quirements of Specification 2.4.1 are met; and,
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l 2-11 The gross liquid waste activity and flow rate shall be con-c.
tinuously monitored and recorded during release.
If this requirement cannot be met, continued release of liquid effluents shall be permitted only during the succeeding 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided that during this 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, two independent samples of each tank shall be analyzed and two station personnel shall independently dheck valving prior to the discharge.
5.
The equipment installed in the liquid radioactive waste system shall be maintained and operated to process all liquids prior to their discharge when it appears that the projected cumulative discharge rate excluding tritium and dissolved noble gases, released during any calendar quarter will exceed 1.25 curies.
6.
The maximum activity to be contained in one liquid radwaste tank that can be discharged directly to the environs (Treated Waste Monitor and Filtered Waste Monitor Tanks only), shall not exceed 10 curies.
Monitoring Requirements 1.
Facility records shall be maintained of the radioactive concentrations and volume before dilution of cach batch of liquid effluent released, and of the averag dilution flow and length of time over which each discharge occurred.
2.
Prior to release of each batch of liquid effluent, s sample shall be taken from that batch and analyzed in accordance with Table 2-2 to demons.trate compliance with Specification 2.4.1, 3.
Radioactive liquid waste sampling and activity analysis shall be performed in accordance with 1chle 2-2.
4.
The liquid effluent radiation monitors shall be calibrated at least quarterly by means of a known radionctive source.
Each monitor shall be tested monthly and when ciecharging checked daily.
S.
The performance of automatic isolation valves c.nd discharge tank selection valves shall be checked annually.
B ases Releases of radioactivity in liquid wastes within the design objective levels provide reasonable assurance that the resulting 1
~
i I 2-12 annual exposure from liquid wastes to the whole body or any organ of an individual will not exceed 5 mrem per year.
At the same time, the Licenser, is permitted the flexibility of operation, compatible with considerations of i
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health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily resulc in I
releases higher than the design objective levels, but still within the. con-centracion limits specified in 10 CFR 20.
It is expected that using this operational flexibility under unusual operating conditions, the Licensee shall exert every effort to keep levels of rade., active materials as low as practicable, and that annual releases will not exceed a small fraction of the annual average concentration limits specified in 10 CFR 20.
2.4.2 Gaseous Discharge Specification 1.
When the release rate of radioactive materials in gaseous wastes averaged over a calendar quarter is such that the quentities of noble gases and other radioactive isotopes, except I-131 and particulate radioisotopes with half-lives greater than eight days, e.:cced twice the design objective as stated in 2.4.a, or when the release rate of I-131 and particulates with half-lives greater than eight days exceeds 2% of 2.4.2.3.b, the Licensee shall notify the Commission within 30 days, identifying the causes of the excessive activity and describing the proposed program of action to reduce such releases to design objective levels.
2.
The maximum activity to be contained in one Waste Gas Decay tank shall be limited to 15,480 Ci.
3.
a.
The rate of rele:se of radioactive ca:erials and gaseous vastes from the plant (except I-131 and particulate radioisotopes with I
half-lives greater than eight days) averaged over any one-hour period shall not exceed:
t 91
<1 2.5 x 105,3/sec (MPC)i Where Qi is the release rate in Ci/sec for isotope i and (MPC)1 is the maximum permissible concentration of isotope i as defined in Appendix B, Table II, Column 1, 10 CFR Part 20.
b.
The release rate of I-131 and particulates with half-lives greater than eight days released to the environs as part of airborne effluents, shall not exceed 0.96 uCi/sec.
4.
a.
The release rate of gross gaseous activity averaged over a calendar quarter shall not be such that the quantities of noble gases and other radioactive isotopes, except I-131 and particulate radioisotopes with half-lives greater than eight days, exceed. eight times the design objective as stated in 2.4.a.
Amendment No. 46
2-14a The noble gas release rates stated in the objectives are based on a X/Q value from the annual meterological data.
The dispersion factor used.
4 x 10-6 eec/m 3 at 1046 meters, is conservative and the release rate is controlled to a small fraction of 10 CFR 20 requirements at the exclusion area boundary (.02 of 10 CFR 20 =
10 mrem per year).
'Ihe dispersion factor is taken from annual meterological data taken at the ANO site (see ANO-2 FSAR Section 2.3.5) and is based on the majority of the gaseous activity released from the site will be released from the waste gas decay tanks and reactor building purges, within the time frame of 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 6 I'
- i Amendment No. 46 l
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UNITED STATES (gg NUCLEAR REGULATORY COMMISSION y
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WASHINGTON, D. C. 20555 s, v. f;8
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t ARKANSAS POWER AND LIGHT COMPANY DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Anendment No. 15 License No. NPF-6 l
1.
The Nuclear Regulatory Conmission (the Commission) has found that:
A.
The application for amendment by Arkansas Power and Light Company (the licensee) dated October 31, 1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Conmission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the a
provisions of the Act, and the rules and regulations of the Commi ssion; C.
There is reasonable assurance (i) that the activities authorized
't by this ami.ndment can be conducted without endangering the health l
and safety of the public, and (ii) that such activities will be 4.,
conducted in compliance with the Commission's regulations; i
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendaent is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-6 is hereby amended to read as follows.
The second paragraph of 2.C.(2) has not changed.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.15, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifica-tions.
3.
This license amendment is effective as of its date of issuance.
.i FOR THE NUCLEAR REGULATORY COMMISSION W
o\\'ertA. Clark, Chief Operating Reactors Branch #3 Division of Licensing a"
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 16, 1980
I f
ATTACHMENT TO LICENSE AMENDMENT NO.15 FACILITY OPERATIfiG LICENSE NO. NPF-6 DOCKET NO. 50-368 e
1 Replace the following pages of the Appendix B Technical Specifications i
with the enclosed pages.
The revised pages are identified by Amendment Number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document con-pleteness.
Pages 2-2 2-6 2-7 i
l 2-10 l
4 i
i l
~.
2.0 LIMITING CONDITIONS FOR OPERATION 2.1 Non-Radiological Not Applicable 2.2 Radiological Applicability Applies to the controlled release of radioactive liquids and gases from Arkansas Nuclear One (ANO), Unit No. 2.
Objective To define the limits and conditions for the controlled release of radioactive effluents to the environs and to ensure that these releases are as low as reasonably achievable (ALARA).
These releases should not result in radiation exposures in unrestricted areas greater than a few percent of natural background exposure.
The release rate for all effluent discharges should be within the limits specified in 10 CFR Part 20.
To assure that the release of radioactive material to unrestricted areas meet the as-low-as' rea'sonably achievable concept, the following objectives apply:
For liquid wastes:
The annual total quality of radioactive matericls in a.
liquid waste released to unrestricted areas, excluding tritium and dissolved gases, should not exceed 5 curies.
b.
The annual doses to an individual from the site in unrestricted areas shall not exceed 5 mrem to the whole body or to any organ.
2-1 i
i
Th2 cnnual cvar:33 crucentration of radicactiva matcricio in liquid waste upon release from the Restricted Area, excluding trittum and dissolved noble gases, should not exceed 2 x 10-8 uCi/ml.
c The annual average concentration of dissolved gases in liquid waste, upon release from the Restricted Area, should not exceed 2 x 10-6 uC1/ml.
For Gaseous Wastes:
Averaged over a yearly interval, the release rate of noble gases a.
and other radioactive isotopes, except I-131 and particulate radioisotopes with half-lives greater than eight days, dis-charged from the station should be li=ited as follows:
EKiQi<(I Y# D 20 mrad /yr B g
Where Qi is the release rate in Ci/sec for radionuclide i and Ki is the gamma air dose factor or beta air dose factor for each identified noble gas radionuclide, in mrad /yr per Ci/sec defined as follows:
Ki = 4.0 x 10 6 (air dose factor for 1),
where the air dose factor for radionuclide i is per Table B-1 of Regulatory Guide 1.109, Revision 1, October 1977.
b.
Averaged over a yearly interval, the release rate of I-131 and other particulate radioisotopes with half-lives longer than eight days discharged from the station, should result in a dose in the unrestricted area of less than 15 mrem to the thyroid of a child through the grass-cow-milk chain; and the total annual quantity of iodine-131 discharged from ANO-2 should not exceed 1 Ci.
2.2.1 Liquid Discharge Specification 1.
The rate of release of radioactive materials in liquid l
l waste from the station shall be centrolled such that t
Amendment No. 15 2-2
l cf the average dilution flow and length of I
time over which each discharge' occurred.
2.
Prior to release of each batch of liquid effluent, a sample shall be taken from that batch and analyzed in accordance with Table i
2-1 to demonstrate compliance with Specifi-cation 2.2.1.
3.
Radioactive liquid waste sampling and activity anilysis shall be performed in accordance with Table 2-1.
4.
The liquid effluer.t radiation monitors shall be calibrated at least quarterly by means of a known radioactive source.
Each monitor shall be tested monthly and when discharging checked daily.
5.
The performance of automatic isolction valves and discharge tank. selection valves shall be checked annually.
Bases Releases of radioactivity in liquid wastes within the design objective levels provide reasonable assurance that the resulting annual exposure from liquid wastes to the whole body or any organ of an individual will not exceed 5 mrem per year.
At the same time the Licensee is permitted the flexibility of operation, compatible with considerations of health and safety, 2-5 1
1
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1
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_.. m.
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a to escuro that tha public is providsd a dcpcndable source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels but still within the concentration limits specified in 10 CFR 20.
It is expected that using this operational fleri-bility under unusual operating conditions, the Licensee shc11 exert every effort to keep levels of radioactive material as low as reasonably achieve-able and that annual releases will not exceed a small fraction of the annual avertge concentra:1ca limits specified in 10 CFR 20.
2.2.2 Gaseous Discharge Specification 1.
When the. release rate of radioactive caterials in gaseous wastes, averaged over a calendar cuarter is such that the quantities of ncble gases and other radioactive isotopes, except I-131 and par-ticulate radioisotopes with half-lives greater that eight days, exceed twice the design objective as stated in 2.2.a. or when the release rate of I-131 and particulates with half-lives greater than eight days exceeds 2% of 2.2.2.3.b, the Licensee shall notify the Commission within 30 daya, identifying the causes of the excessive activity, and describe the proposed program of action to reduce such releases to design objective levels.
2.
The maximum activity to be contained in one Waste Gas Decay Tank shall be limited to 15,480 Ci.
Amendment No. 15 2-6 e=.
e
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3.
c.
Tha rcto cf ralacco cf rcdionctiva matsricle and gaseous wastes from the static: (except
(
I-131 and particulate radioisotopes with half-lives greater than eight days) averaged over any one-hour period shall not exceed:
I Oi 1
5 3
2.5 x 10
_3L__
(MPC)1 sec Where Qi is the release rate in C1/sec for isotope i i
and (MPC)1 is the maximum per=issible concentration of isotope as defined in Appendix 3, Table II,'Colu=n 1, 10 CFR Part 20.
b.
The release rate of I-131 and particulates with half-lives greater than eight days released to the environs from the station, as part of airborne effluents shall not exceed 0.96 uCi/sec.
4.
a.
The release rate of gross gaseous activity averaged over a calendar quarter shall not be such that the quantities of noble gases and other radioactive isotopes, except I-131 and particulate radioisotopcs with half-lives greater than eight days, exceed eight times the design objective as stated in 2.2.a.
b.
The release rate of I-131 and particulates with half-lives greater than eight days shall not exceed.8% of the values specified in 2.2.2.2.b when averaged over a calendar quarter.
Amendment No. 15 2-7
5.
During release of radioactive gaseous wastes from the gaseous waste discharge header to the plant ventilation exhaust plenum, the following t
conditions shall be met:
a.
The gaseous radioactivity monitor, iodine and the particulate samplers in the plant vents shall be operating; and b.
Automatic isolation devices capable of limiting gaseous release rates to within the values specified in 2.2.2.3.a shall be operating.
6.
During containment purge, the effluent control monitor shall be set to alarm and automatically I
close the containment purge penetrations on a high activity alarm.
1 7.
Gases discharged through the unit vent to the f
I atmosphere shall be continuously monitored and b
recorded for gross (S,29 activity.
U g
Whenever these monitors are inoperable, appropriate ll grab samples shall be taken and ar.alyzed each shif t.
d Monitorina Requirement i
l.
Radioactive gaseous waste sampling and analysis shall be performed in m:co dance with Table 2-1.
2.
All waste gas monitors stall be calibrated at least quarterly by means of a known r:dioactive source.
Each monitor shall have an ins trument channel test at least monthly and when dis-charging checked at least daily.
2-8
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3.
During power optration, the condenser vacuum pump discharge shall be continuously monitored l
(;
for gross radiogas activity.
The monitor shall l
not be inoperable for more than 7 days.
When-ever this monitor is inoperable, grab samples 4
shall be taken and analyzed for gross (8,5) radio-activity daily.
[u.
y 4.
Records shall be maintained and reports of the
(-
sampling and analysis results shall be sub-mitted in accordance with Specification 5.6.
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5.
The Waste Gas Decay Tank effluent monitor shall be tested prior to any release of radioactive gas from a decay tank and shall be calibrated at 5'-
least once every 18 months.
Bases:
It is expected that the releases of radioactive materials and gaseous wastes will be kept within the design objective levels and will not exceed on an instantaneous basis the dose rate limits specified in 10 CFR 20.
These levels provide reasonable assurance that the resulting annual exposure from noble gases to the whole body or any organ of an individual will not exceed 10 mrem per year.
At that same time the Licensee is perinitted the flexibility of operation, i
compatible with considerations of health and safety, i
to assure that the public is provided a dependable 2-9
~
sourceofpowerunderunusualoperatingconditionswhichbay I
temporarily result in releases higher than the design objective levels but still within the concentration li=its specified in 10 CpR 20.
It is expected that using this operational flex-ibility under unusual operating conditions, the Licensee shall exert every effort to keep levels of radioactive materials and gaseous wastes as low as reasonably achievable and that annual releases will not exceed a small fraction of the annual average concentration limits specified in 10 CFR 20.
These efforts shall include consideration of meteorological conditions during releases.
l The noble gas release rates stated in the objectives are based on a X/Q value from the annual meteorological data.
The dis-
-6 persion factor used, 4.0 x 10 sec/m at 1046 meters, is conservative o
and the release rate is controlled to a small fraction of 10 CFR 20 requirements at the exclusion area boundary (.02 of 10 CFR 20 3
I 10 mrem per year).
The dispersion factor is taken from annual 9
)
meteorological data taken at the ANO site (see ANO-2 FSAR Section f
2.3.5) and is based on the majority of the gaseous activity released a
I from the site will be released from the waste gas decay tanks and reactor building purges, within the time frame of 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Amendment No. 15 2-10
.