ML20062E915
| ML20062E915 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/29/1982 |
| From: | Clark R, Stolz J Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML20062E920 | List: |
| References | |
| DPR-51-A-066, NPF-06-A-034 NUDOCS 8208100372 | |
| Download: ML20062E915 (15) | |
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o UNITED STATES g{
NUCLEAR REGULATORY COMMISSION
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j WASHINGTON, D. C. 20555
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ARKAtlSAS POWER AND LIGHT COMPAfiY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amerdment No. 66 License No. DPR-51 1.
The Nuclear Regulatiory Commission (the Commission) has found that:
A.
The application for amendment by Arkansas Power and Light Company (the licensee) dated December 1, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 Commission'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 issuan'ce of this amendment is in accordance with 10 CFR Part 51.of the Commission's regulations and all applicable requirements have been satisfied.
DESIGNATED ORIGINAL A
V M Certified By a
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. 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. DPR-51 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 66, 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 vg l - ^" h A John F. St z, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: July 29, 1982 O
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ATTACHMENT TO LICENSE AMEN 0 MENT NO. 66 FACILITY OPERATING LICENSE NO. OPR-El DOCKET No. 50-313 Replace the following page of the Appendix B Technical Specifications with the enclosed page.
The revised page is identified by Amendment Number and contains vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document com-pleteness.
Page 2-14 1
E 2-13 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 2.4.2.3.b when averaged over a calendar quarter.
5.
During release of radioactive gaseous wastes from the gaseous waste discharge header to the plant ventilation exhaust planum, the following conditions shall be met:
The gaseous radioactivity monitor, iodine and the particulate a.
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 2.4.2.3.a shall be operating.
6.
Radioactive gaseous vastes collected in the gas decay tanks shall be held up a minimum equivalent decay time of 45 days, except when the calculated activity concentration of each identified radioisotope of the site boundary is less than 1% of the MPC specified in 10 CFR Part 20, Appendix B, Table II, based on a X/Q of 1.5 x 10-5, 7.
Purging of the reactor building shall be governed by the following conditions:
a.
Reactor building purge shall be through the high efficiency particulate filters and charcoal filters until the activity concentration is below the occupational limit inside the reactor building, at which time bypass may be initiated; and b.
Reactor building p' urge shall be through the high efficiency particulate filters and charcoal filters whenever irradiated fuel is being handled or any objects are being handled over irradiated fuel in the reactor building.
Cases disbarged through the unit vent shall be continuously, 8.
monitored and recorded for gross (8,y) activity.
Whenever these monitors are inoperable, appropriate grab samples shall be taken and analyzed each shif t.
The monitor shall not be inoperable for more than 7 days.
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2-14 Monitoring Requirement 1.
Radioactive gaseous waste sampling and analysis shall be performed in accordance with Table 2-2.
2.
All waste gas monitors shall be calibrated at least quarterly by means of a known radioactive Jource.
Each monitor shall have an instrument channel test at least monthly and when discharging checked at least daily.
3.
During power operation, the condenser vacuum pump discharge shall be,
continuously monitored for gross radiogas activity.
The monitor shall not be inoperable for more than 7 days.
Whenever this monitor is inoperable, grab samples shall be taken and analyzed for gross radioactivity daily.
4.
Records shall be maintained and reports of the sampling and analysis results shall be submitted in accordance with 10CFR50.36a.
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 refueling intervals.
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 10CFR20.
- C These levels provide reasonable assurance that the resulting annual exposure from noble gases to the whole body or any organ on an individual l
will not exceed 10 mrem per year.
At the same time the Licensee is permitted the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable l
source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels but still.
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within the concentration limits specified in 10CFR20.
It is expected that using this operational flexibility under unusual operating conditions, the Licensee shall exert every effort to keep levels of-radioactive materials and gaseous wastes as low as practicable and that annual releases will not exceed a small fraction of the annual average concentration limits specified in 10CFR20.
These efforts shall include consideration of meteorlogical conditions during releases.
Amendment No. 66 4
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aseg tg UNITED STATES g
NUCLEAR REGULATORY COMMISSION
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ARKANSAS POWER AND LIGHT COMPANY DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT N0. 2 AMENDMENT T0. FACILITY OPERATING LICENSE Amendment No. 34 License No. NPF-6 l.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The applicatio'n for amendment by Arkansas Power and Light Company (the licensee) dated December 1, 1981, complies with the standards and requirements of the Atomic Energy Act of.1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The. facility will operate in confonnity with the application, the 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 Commission's regulations; D.
The issuance of this amendment will,not be inimical to the comon defense and security or to the health and safety of the public; I
and E.
The issuance of this amendment is in accordance with 10 CFR Part 51.of the Commission's regulations and all applicable requirements have been satisfied.
O DESIcnnro onic1 nt Cort 1r1ca ll,/
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. 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.
Technical Specifications The Technical Specifications contained in Appendix B, as revised through Amendment No. 75
, are hereby incor-porated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 29, 1982 l
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i ATTACHMENT TO LICENSE AMENDMENT NO. 34 FACILITY OPERATING LICENSE NO. NPF-6, DOCKET NO. 50-368 Replace the 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 1
2-9 3-2 3-3 e
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TABLE OF CONTENTS Section Page 1.0 Definitions 1-1 2.0 Limiting Conditions for Operation 2-1 2.1 Non-Radiological (not applicable) 2.2 Radiological 2-1 2.2.1 Li. quid Discharge 2-2 2.2.2 Gaseous Discharge 2-6 3.0 Environmental Surveillance 3-1 3.1 Surveillance for ANO 3-1
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3.2 Additional Environmental Surveillance for Unit 2 3-1 3.2.1 Dilution of ANO-2 Discharges During ANO-1 Outages 3-l 3.2.2 Deleted 3.3 Aerial Remote Sensing 3-4 4.0 Special Studies 4-1 4.1 Unusual or Important Environmental Events 4-1 5.0 AdministrhtiveControls 5-1 5.1 Responsibility 5-1 5.2 Organization 5-1 5.3 Review 5-1 5.3.1 Plant Safety Committee 5-1 5.3.2 Safety Review Connittee 5-2' Amendment No. 34 i
TABLE OF CONTENTS (continued)
Page Section 5-3 5.4 State and Federal Permits and Certificates 5.5 Procedures 5-3 5.6 Station Reportino Reouirements 5-4 5.6.1 Routine Reports,
5-4 5.6.2 Nonroutine Reports 5-5 5.6.2.a Prompt Report 5.6.2.b Thirty Day Report 5.6.2.c Content of Non-routine Reports 5.7 Changes 5.7.1 Changes in Environmental Technical Specifications 6 5.7.2 Changes in Permits and Certifications 5-6 5.7.3 Changes in Procedures, Station Design or Operation 5-7 5.7.4 NRC Authority to Require Revisions 5-8 5.8 Records Retention 5-8 5.9 Special Requirements 5-9 APPENDIX 4.1.A Descripticn of Bird Collision Monitoring on ANO-2 Cooling Tower 5-11 I
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a 3.
During power operation, the condenser vacuum pump discharge shall be continuously monitored for gross raciogas activity.
The monitor shall not be inoperable for more than 7 days.
Whenever this monitor is' inoperable, grab samples shall be taken and analyzed for gross (p, y) radioactivity daily.
4.
Records shall b,e maintained and reports of the sampling and analysis results shall be submitted in accordance with 10CFR50.36a.
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 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
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levels and will not exceed on an instantaneous basis the dose rate limits specified in 10CFR20.
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 permitted the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable Amendment No. 34 2-9 e
9
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 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.
The noble gas release rates stated in the objectives are based on a X/Q value from the annual meteorological data. The dis-
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persion factor used, 4.0 x 10 sec/m 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).
The dispersion factor is taken from annual meteorological 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 />.
Amendment No.15 2-10
3.0 ENVIRONMENTAL SURVEILLANCE 3.1 Surveillance for ANO The surveillance program associated with ANO-1 (Docket No.
50-313) operation provides an examination of the adequatic ecosystem of Lake Dardanelle in the Vicinity of the plant as well as providing information on air, precipitation, ground water, soil, vegetation and milk by radiological analysis of samples in the area of the plant.
That program will provide adequate information for ANO-2 operation and shall be carried out at all times that the ANO-2 Environmental Technical Specifications apply.
3.2 Additional Environmental Surveillance for Unit 2 3.2.1 Dilution of ANO-2 Discharges During ANO-1 Outages Objective:
To assure that waste streams from Unit 2 are diluted before l
entering the discharge embayment on Dardanelle Reservoir.
l Environmental Monitoring Requirements When Unit 2 is making discharges during Unit 1 outages, the licensae will record the number of Unit 1 circulating pumps in operation.
Unit 2 releases and l
Unit 1 circulating water pump operation during Unit 1. outages shall be l
sumuarized, and reported in accordance with Subsection 5.6.1.
Action:
A non-routine report, as 'specified in Subsection 5.6.2.b, shall be made if less than two Unit 1 circulating water pumps are operated while Unit 2 releases or discharges are occurring.
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3-1 i
Bases:
Unit 2 circulating water is concentrated by evaporation to a concentration factor ranging from 3 to 14 (FES p. 5-2).
In order to minimize impact of the blowdown during Unit 1 outages, and to minimize impact of other* low volume discharges and of waste heat from. Unit 2 during such outages, a minimum dilution flow equivalent to one-half (approximately 383,000 gpm) the
' full-flow of the Unit 1 circulating water pumps should be maintained during all Unit 2 releases or discharges (FES p.5-2).
3.2.2 Deleted i
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Amendment No. 34 3-2
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This page deliberately left blank.
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3.3 Aerf al Remote Sensing Objective Vegetation communities of the site and vicinity shall be aerially photographed annually to detect and assess the significance of damage, or lack thereof, as related to cooling tower drift dispersions.
Environmental Monitoring Requirements Photography shall be done by aerial overflight.
Aerial photography shall be conducted once per year during late summer or early fall.
Timing of aerial photography and ground truthing should be selected to coincide with periods of maximum predicted drif t deposition damage, preferably from August 15 to September 15, meteorological conditions permitting.
This i
surveillance program shall cobnence at initial criticality of l
Unit 2 and shall continue for two years.
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l Amendment No. 34 3-4 l
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