ML19332A680
| ML19332A680 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/31/1980 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19332A677 | List: |
| References | |
| NUREG-0664, NUREG-0664-R01, NUREG-664, NUREG-664-R1, NUDOCS 8009160663 | |
| Download: ML19332A680 (59) | |
Text
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O O
I APPENDIX B TO FACILITY OPERATING LICENSE NO. NPF-7 NORTH ANNA POWER STATION
'JNIT 2 l
i VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-339 O
ENVIRONMENTAL TECHNICAL SPECIFICATIONS PART I - RADIOLOGICAL
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\\..J' TABLE OF CONTENTS
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&a_g,e 1.0 DEFINITIONS.................................................
1-1 2.0 LIMITING CONDITIONS FOR 0PERATION...........................
2-1 2.1 Non-Radiological.......................................
2-1 2.2 Radioa ctive E f fl u en ts..................................
2-1 2.2.1 Specifications for Liquid Waste Effluents.......
2-2 2.2.2 Specifications for Liquid Waste Sampling and Monitoring................................
2-3 2.2.3 Specifications for Gaseous Waste Effluents......
2-7 2.2.4 Specifications for Gaseous Waste S=mpling and Monitoring................................
2-13 2.2.5 Specifications for Solid Waste Handling and Disposal..................................
2-17 3.0 ENVIRONMENTAL SURVEILLANCE..................................
3-1 3.1 Nonradiological Surveillance...........................
3-1 3.1.1 Ab io ti c - Aq ua ti c...............................
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3.1.2 B i o ti c Aq u a ti c.................................
3-1 3.1.3 Ab i o ti c - Te r re s t ri al..........................
3-1 3.1.4 On si te Me teorology Moni tori ng..................
3-1 3.2 Radiological Envi ronmental Moni toring.................
3-2 4.0 SPECI AL SURVEILLANCE AND STUDY ACTIVITIES..................
4-1 5.0 ADMINISTRA*IVE CONTR0LS.....................................
5-1 5.1 Responsibility.........................................
5-1 5.2 Organization...........................................
5-1 5.3 Review anJ Audit.......................................
5-1 5.3.1 Station Nuclear Safety and Operating Committes (SNS0C).......................................
5-1
- 5. 3.1.1 Function....................................
5-1
- 5. 3.1. 2 Responsibility..............................
5-1
- 5. 3.1. 3 Authority...................................
5-3 5.3.1.4 Records.....................................
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TABLE OF CONTENTS (Cont'd) 5.3.2 Supervisor, Quality Assurance, Operation and Maintenance......................................
5-4 5.3.2.1 Function....................................
5-4 5.3.2.2 Audits......................................
5-4 5.3.2.3 Records.....................................
5-4 5.3.3 System Nuclear Safety and Operating Committee (SyNS0C).......................................
5-4 5.3.3.1 Function..................................'..
5-4 5.3.3.2 Review......................................
5-4 5.3.3.3 Responsibility..............................
5-5 5.3.3.4 Authority...................................
5-5 5.3.3.5 Records.....................................
5-5 5.4 State and Federal Permits and Certificates.............
5-5 5.5 Procedures.................................,............
5-5 5. 5.1 W r i t t en P roc ed u re s..............................
5-5 5.5.2 Operating Procedures............................
5-5 5.5.3 Procedures for Environmental Surveillance -
Radiological..................................
5-6 5.5.4 Procedures for Environmental Surveillance -
Nonradiological.................................
5-6 5.5.5 Quali ty As surance of Program Resul ts..............
5-6 5.5.6 Changes in Procedures, Station Design or 0peration.......................................
5-5 5.5.7 Consistency with Initially Approved Programs......
5-7 5.6 Station Reporting Requirements...........................
5-7 5.6.1 Routine Reports...................................
5-7 5.6.1.1 Annual Environmental Operating Report.........
5-7 5.6.l.2 Radioactive Ef fluent Release Report...........
5-8 5.6.2 Nonroutine Reports................................
5-9 5.6.2.1 Nonroutine Non-Radiological Environmental Operating Report............................
5-9 5.6.2.2 Nonroutine Radiological Environmental Operating Reports...........................
5-10 5.6.3 Changes in Environmental Technical Specifications.
5-11 5.6.4 Changes in Permits and Certifications.............
5-11 5.7 Records Retention........................................
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1.0 DEFINITIONS Accuracy: Refers to the deviation of a result obtained by a particular method from the value accepted as true.
Annually: Annually is once per calendar year at intervals of taelve calendar months, plus or minus 30 days.
Batch Release: A batch release is the discharge of fluid wastes of a discrete volume.
Calibration: An instrument or device calibration shall be the adjust-ment, as necessary, of the output such that it responds with the neces-sary range and accuracy to known values of the parameter (s) which the instrument sensor or device monitors. The calibration shall encompass the entire circuit including the sensor, indicatory control feature, alarm and/or trip function (s), and shall include the functional test.
The calibration may be performed by any series of sequential, overlapping or total circuit steps such that the entire circuit is calibrated as specified.
Composite Sample: A combination of individual samples obtained at regular intervals over a time period. The volume of each individual sample is proportional to the flow rate discharge at the time of sampling x
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or the number of equal volume samples is proportional to the time period
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used to produce the composite.
Condenser Discharce Structure: Located at the beginning of canal "A".
Effluent water from Unit Nos. I and 2 exits through this structure to canal "A".
-Continuous Monitors: As applied to in place monitors and flow indicators does not prevent the~ devices from being periodically taken out of service for calibration or maintenance for periods not to exceed four hours.
Continuous Release: A continuous release is the discharge of fluid waste of a non-discrete volume, e.g., from a volume or system that has an input flow during the continuous release.
1 1-1 f
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O Daily Average Concentration: Daily averace concentration means the aritnmetic average of all daily determinations of concentration made during a calendar month. Daily determinations of concentration using a comoosite sample shall be the concentration of the composite sample.
When grab samples are used, the daily determination of concentration shall be the arithmetic average of all the samples collected during that calendar day.
Daily Maximum Concentration: Daily maximum concentration means the maximum concentration recorded for any calendar day.
Functional Check: A functional check shall be the qualitative assessment of cnannel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
Functional Test: A functional test shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.
Grab Sample: A grab sample is an ind.ividual sample collected in less than fifteen minutes.
o nthl y: Monthly is once during every calendar month at intervals of ~30 days plus or minus three days.
Normal Operation: Operation of the station at greater than 5% of rated thermal power in other than a safety emergency situation.
Precision: Relates to the reproducibility of measurements within a set, that is, to the scatter or dispersion of a set about its central value.
Quarterly: Quarterly is once during each successive three month ceriod of tne calendar year, counting from January 1, at intervals of 13 weeks plus or minus 9 days.
Semi-Monthly: Semi-monthly is twice during each calendar month at intervals of 15 days plus or minus 2 days.
Soectrai dand: A width, generally expressed in wavelength or frequency of a particular portion of the electromagnetic spectrum. A given sensor (e.g., radiometer detector or camera film) is designed to measure or be sensitive to energy received from that part of the spectrum.
Station and Unit: Station refers to North Anna Power Station, Units Nos. I and 2.
Unit
- refers only to Unit No.1 or Unit No. 2.
Weekly: Weekly is once during each calend. e week at intervals of 7 days plus or minus 1 days.
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2.0 LIMITING CONDITICNS FOR OPERATION -
2.1 Non-Radiological - Mone 2.2 Radioactive Effluents Objective To define the limits and conditions for the release of radioactive materials in liquid and gaseous effluents to the environs to ensure that these releases are as low as is reasonably achievable in con-formance with 10 CFR Part 50.34a, and to ensure that concentrations of radioactive materials in effluents released to unrestricted areas are within the limits specified in 10 CFR Part 20.
To ensure that the releases of radioactive material above background to unrestricted areas be as low as is reasonably achievable, the following design objectives, as defined in the Annex to Appendix I to 10 CFR Part 50 apply:
'The annual dose above background to the total body or any organ of p) a.
an individual from liquid releases from all reactors at a site
('s should not exceed 5 mrem in an unrestricted area.
b.
The annual total quantity of radioactive materials in liquid releases, excluding tritium and dissolved gases, discharged from each reac. tor should not exceed 5 Ci.
c.
The annual total quantity of noble ga'ses above backgrdund dis-charged in gaseous effluents from the site should result in an air dose due to garna radiation of less than 10 mrad, and an air dose due to beta radiation of less than 20 mead, at any location near ground level which could be occupied by individuals at or beyond the boundary of the site.
d.
The annual total quantity in gaseous effluents of all radiciodines and radioactive material in particulate forms with half-lives j
greater than eight days, above background, from all reactors at a site should not result in an annual dose to any organ of an indivi-dual in an unrestricted area from all pathways of exposure in excess of 15 mrem.
The annual total quantity of iodine-131 discharged in gaseous a
releases from each reactor at a site should not exceed 1 C1.
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O 2.2.1 Soecifications for Licuid 'Jaste Effluents a.
The concentration of radioactive materials released in liquid waste effluents to unrestricted areas fron all reactors at the site shall not exceed the values specified in 10 CFR Part 20,. appendix 3, Table 5
II, Column 2, for radionuclides other than nccle gases and 4 x 10 uCi/ml for noble gases.
b.
The cumulative release of radioactive materials in liquid waste effluents, excluding tritium and dissolved gases, shall not exceed 10 Ci/ reactor / calendar quarter.
c.
The cumulative release of radioactive materials in liquid waste effluents, excluding tritium and dissolved gases, shall not exceed 20 Ci/ reactor in any 12 consecutive months.
d.
During release of radioactive wastes, the clarifier effluent monitor shall be set to alarm and to initiate the automatic closure of the clarifier discharge valve (LW-ll5) prior to exceeding the limits specified in 2.2.l'.a above, e.
The operability of valve LW-ll5 in the liquid radwaste discharge lines shall be demonstrated at least quarterly.
f.
The equipment installed in the liquid radioactive waste system shall be maintained and shall be operated to process radioactive liquid wastes prior to their discharge when the projected cumulative release could exceed 1.25 Ci/ reactor / calendar cuarter, excluding tritium and dissolved gases.
g.
The maximum radioactivity to be contained in any liquid radwaste tank that can be discharged directly to the environs shall not exceed 10 C1, excluding tritium and dissolved gases.
h.
If the cumulative release of radioactive materials in liquid effluents, excluding tritium and dissolved gases, exceeds 2.5 Ci/ reactor / calendar quarter, the licensee shall make an investiga-tion to identify the causes for such releases, define and initiate a program of action to reduce such releases to the design objective levels listed in Section 2.2, and report these actions to the NRC in accordance with Specification 5.6.2.2.c(1).
i.
An unplanned or uncontrolled offsite release of radioactive materials in liquid effluents in excess of 0.5 curies requires notification.
This notification shall be in accordance with Specification 5.6.2.2.c(3).
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v 2.2.2 Scecifications for Licuid Waste Samoli g and Mon.toring a.
Station records shall be maintained of the radioactive concentra-tion and volume before di'ution of licuid waste intended for discharge and the average dilution ficw and length of tire over which each discharge occurred. Samole analysis results and other reports shall be submitted as required by Section 5.6.1 of these Specifications. Estimates of the sampling and analytical errors, as described in Regulatory Guide 1.21, associated with each reported value shall be included, b.
A continuous representative sample of all radioactive liquid waste shall be taken at the liquid waste disposal-clarifier system release point and analyzed for the concentratien of each significant gamma energy ceak in accordance with Table 2.2-1 to demonstrate compliance with Scecification 2.2.1 using the flow rate into which the waste is discharced during the period of discharge.
If the continuous representative sample system is inocerative, an alternate fixed flow sampler shall be provided to collect continuous samples in the continuous representive samole collection tanks and the proportion of sample to effluent deter-mined each 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or valve LW-ll5 shall be closed, c.
Sampling and analysis of undiluted liquid radioactive waste shall
("N be perforr:ed in accordance with Table 2.2-1.
Prior to taking
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I samples from a continuous representative samole collection tank, V
the tank shall be mixed for at least 10 minutes using the mixer 4
provided in the tank, d.
The radioactivity in. undiluted liquid wastes including steam generator blowdown shall be continuously monitored and the gross activity (gamma) recorded during release. Whenever this monitor is inoperative, valve LW-il5 shall be cicsed, or any clarifier treatment system bypass shall be terminated and grab samples shall be taken at the liquid waste disposal-clarifier system release point and analyzed every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to demonstrate cor'oliance with Specification 2.2.1.a.
If this monitor is inoperative for a period exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, valve LW-ll5 shall be closeo and these releases terminated.
e.
The flow rate of undiluted liquid radioactive waste shall be con-tinuously measured and recorded during release. The total dilu-tion water flow will be calculated based on pump run. times and i
known circulating water pump characteristics.
f.
The clarifier effluent radiation monitor shall be calibrated at least quarterly by means of a known radioactive source. All laboratory analyses and other liquid effluent radiation monitors shall be calibrated at least once per 18 months by means of a known radioactive source. The source used to calibrate the kncwn source sball be calibrated by a measurement system which is
.l n) traceable to the National Bureau of Standards. Each monitor Ad shall also have a functional test at least monthly and an instru-ment check prior to making a release.
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O TABLE 2.2-1 RADI0 ACTIVE LIQUID WASTE SAMPLI.NG AND ANALYSIS L'iquid Release Sampling Analysis ype of Cetection c
Type Frequency Frequency Activity Analysis Capacilitjes
(.Ci/ml)
Principal Gamma b
Plant Releases including Continuous Daily Emitters S x 10'7 d
Steam Generator Slowdo.,n Composite Ba-La-la0, I-131 10 Grab Sample Monthly Dissolved and Entrained Gases 10-'
d 4
Continuous Monthly H-3 10 d
Composite Gross a 10~7 d
~7 Continuous Quarterly P-32 5 x 10 Comoosite Sr-89, Sr-90 5 x 10'8 d
aihe nominal lower limit of detection is defined in HASL 300 (Rev. 8/71), pp. D-08-01, 02, 03 at the 95". confidence level. The LLO levels are decay corrected to the end of the total sampling period. The LLD for racionuclides analyzed by gama spectrometry will vary according to the number of radionuclides encountered in effluent samples.
These LLD levels should be used as minimum criteria for objectives for instr =entation and analytical procedure selection, bFor certain mixtures of gama emitters, it may not be possible to measure radionuclides in concentrations near their sensitivity limits when other nuclides are present in the same sample in much greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentrations of such radionuclides using measured ratios with these radionuclides which are r' utinely identified and measured.
o cA composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
dTo be representative of the average quantities and c:,ncentrations of radioactive materials in liquid effluents, samples should be continuously collected in propor-tion to the rate of ficw of the effluent stream. Prior to analyses, all samples taken for the composite should be thoroughly mixed in order for the composite sample to be representative of the average effluent release.
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The manual valve on the 4-inch-diameter LW-221-152 line shall be closed and locked whenever a release is in progress. The position of this valve shall be checked and recorded each shift unless otherwise secured in position (i.e., locked or sealed).
h.
Samples shall be taken from the Liquid Waste Evaporator Test.
Contaminated Drain and low Level Waste Drain Tanks and frem releases from the Steam Generator Blowdown System and analyzed at least weekly for principal gama emitters. Samples shall be taken from the clarifier and analyzed at least daily for principal ganna emitters.
Bases The release of radioactive riaterials in liquid waste effluents to a
unrestricted areas shall not exceed the concentration limits specified in 10 CFR Part 20 and should be as icw as is reasonably achievable in accordance with the requirements of 10 CFR Part 50.34a. These specifica-tions provide reasonable assurance that the resulting annual dose to the total body or any organ of an individual in an unrestricted area will not exceed 5 mrem. At the same time, these specifications pemit the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily
[O result in releases higher than the design objective levels but still
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within the concentration limits specified in 10 CFR Part 20.
It is expected that by using this operational flexibility under unusual operating conditions, and exerting every effort to keep levels of radioactive material in liquid wastes as low as is reasonably achievable, the annual release will not exceed a small fraction of j
the concentration limits specified in 10 CFR Part 20.
The design objectives have been developed based on operating experience, taking into account a ccmbination of variables including defective fuel, primary system leakage, primary to secondary leakage, steam generator blowdown and the performance of the various waste treatment systems, and are consistent with Appendix I to 10 CFR Part 50.
Specification 2.2.1.a requires the licensee to limit the concentration of radioactive materials in liquid waste effluents released from the site to' levels specified in 10 CFR Part 20, Appendix B. Table II, Column 2, for unrastricted areas. This specification provides assurance that no member of the general public will be exposed to liquid con-taining radioactive materials in excess of limits considered permissible under the Comission's Regulations.
Specifications 2.2.1.b and 2.2.1.c establish the upper limits for the release of radioactive materials in liquid effluents. The interest of these Specifications is to permit the licensee the flexibility of operation to assure that the public is provided a dependable source of
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power under unusual operating conditions which may temporarily result
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in releases higher tTian the levels normally achievable when the plant v
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l and the liquid waste treatment systems are functioning as designed.
Releases of up to these levels will result in concentrations of radio-active material in liquid waste effluents at small percentages of the limits specified in 10 CFR Part 20.
Consistent with the requirements of 10 CFR Part 50 Appendix A, Design Cri terion 64, Specifications 2.2.1.d and 2.2.1.e require operation of suitable equipment to control and monitor the releases of radioactive materials in liquid wastes during any period that these releases are taking place.
Specification 2.2.1.f requires that the licensee naintain and operate the equipment installed in the liquid waste systems to reduce the release of radioactive materials in liquid effluents to as low as is reasonably achievable consistent with the requirements of 10 CFR Part 50.3da. Normal use and maintenance of installed equipment in the iiquid waste system provides reasonable assurance that the quantity released will not exceed the design objective.
In order to keep releases of radioactive materials as low as is reasonably achievable, the specification requires operation of equipment whenever it appears that the projected cumulative discharge rate will exceed one-fourth of this design objective annual quantity during any calendar quarter.
Scecification 2.2.19 restricts the amount of radioactive material that could be inadvertently released to the environment to an amount that will not exceed the Technical Specification limit.
In addition to limiting conditions for operation listed under Specifica-tions 2.2.1.b and 2.2.1.c, the reporting requirements of Specification 2.2.1.h delineate that the licensee shall identify the cause whenever the cumulative release of radioactive materials in liquid waste effluents exceeds one-half the design objective annual quantity during any calendar quarter and describe the proposed program of action to reduce such releases to design objective levels on a timely basis. This report must be filed within 30 days following the calendar quarter in which the release occurred as required by Specification 5.6.2 of these Technical Specifications.
Specification 2.2.1.1 provides for reporting spillage or release events which, while below the limits of 10 CFR Part 20, could result in releases higher than the design objectives.
The sampling and monitoring requirements given under Specification 2.2.2 provide assurance that radioactive materials in liquid wastes are properly controlled and monitored in conformance with the require-ments of Design Criteria 60 and 64. These requirements provide the data for the licensee and the Comission to evaluate the plant's performance relative to radicactive liquid wastes released to the environment. Reports on the quantities of radioactive materials released in liquid waste effluents are furnished to the Comission according to Section 5.6.1 of these Technical Specifications. On the basis of such reports and any additional information the Comission may obtain from the licensee or others, the Comission may from time to time require the licensee to take such action as the Comission deems appropriate.
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The points of release to the environment to be tronitcred in Section 2.2.2 include all the monitored release points as provided for in Table 2.2-2.
Scecifications for Gasecus Saste Effluents 2.2.3 The terms used in these Specificaticns are as folicws:
Subscripts y, refers to vent releases frca the Process Vent and the Building Ventilation Vent i, refers to individual noble gas nuclide (Refer to Table 2.2-3 for the noble gas nuclides considered) l QT = the total ncble gas release rate (Ci/sec)
=fQ sum of the individual noble gas radionuclides determined 4
to be present-by isotopic analysis
-l E = the average total body dose factor due to gama emission (rem /yr per Ci/sec)
C = the averace skin dose factor due to beta emissions (rem /yr per Ci/sec) s R = the average air dose factor due to beta emf ssions (rad /yrperCi/sec)
E = the average air dcse factor due to garrea emissions (rad /yr per Cf/sec)
The values of I, C, R and E are to be detennined each time isotopic analysis is required as delineated in Specification 2.2.4 Determine
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a' the following using the results of_ the ' noble gas radionuclide analysis:
E=(1/Q)k0k T
ii C=(1/Q)j0l T
it E=(1/Q')j0M T
ii T=(1/Q)j0N T
ii where the values of K, L, M, N
- are site dependent gama dnd deta dose factors.g.are provided in Table 2.2-3, and 4
Q = the measured release rate of the radienuclides and radioactive materials in particulate forms with half-lives greater than eight days (C1/sec).
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TABLE 2.2-2 NORTil ANNA POWER STATION LIQUID WASTE SYSTEM LOCATION OF PROCESS AND EFFLUENT}iONITORS AND DEVICES REqlli, RED liiY,]TYCilNICAL, SPfCIFICATION".
Continuous Monitoring Instrumentation Grab Release liigh Liquid Radiation Process System or Sample P int Level or Monitor Release Point Gross Auto Control Station Continuous Overflow Plant Gross Activity Radiation to Isolation Flow Rate Cnmposite Alann Instrument Activity Recorder Alarm Valve Indicator Sampler humber Component Cooling System X
X X
X CC-120 Refueling Water Stg. Tanks X
X Boron Recovery Test Tanks X
X 7 PG Water Storage Tanks X
X ro
& LW Evaporator Test Tanks X
X Contaminated Drain Tanks X
X Low Level Waste Drain Tanks X
X Steam Generator Blowdown X
X X
X X
a Service Water Discharge X
X X
X X
SW-108 c
Turbine Building Floor Drain Sumps b
X X
Liquid Radwaste Effluent Line, LW-220 X
X X
X X
X X
LW-ill X-Required a-Six monitors: 55-122, SS-123, SS-124, SS-222, 55-223, 55-224 b-Whenever the secondary coolant activity exceeds 10~5 pc/ML the sump pumps shall be placed in manual operation and samples shall be taken and analyzed prior to release.
c-Determined by monitoring pump run times.
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TABLE 2.2-3 GAF?A AND SETA COSE FACTCRS FCP.
fiORTH Alit A PC'4ER STATION, UNIT f;05.1 A?;D 2 X/0 = 1.3 x 10-6 sec/m at 1370 meters NNE direction 3
Dose Factors for ' lent E
L M
fi Noble Gas iv iv jy gy Radionuclide Total Body Skin Beta Air Gan=a Air rem /yr rem /yr rad /yr rad /yr Ci/see Ci/sec Ci/sec Ci/sec Kr-83m 6.4E-05 0
0.38 0.0034 Kr-8Em 0.75 1.9 02.6 0.78 Kr-85 0.0091 1.8 2.6 0.0097
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Kr-87 2.2 13.
13.
2.4 Kr-88 5.7 3.1 3.8 6.0 Kr-89 0.72 13.
14.
0.76 Xe-131m 0.27 0.62 1.5 0.34 Xe-132m 0.21 1.3 1.9 0.28 i
Xe-133 0.24 0.40 1.4 0.30 l
Xe-135m 0.97 0.93 0.97 0.93 t
Xe-135 1.1 2.4 3.2 1.2 Xe-137 0.10 16.
17.
0.11 Xe-138 2.0 5.4 6.2 2.1 l
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(1) The release rate limit of ncble gases frca the site shall be such that 7yK,]11 2.0[Q and 0.33[Q
+I*
v)31I Tv v (2) The release rate limit of all radioicdine and radicactive materials in particulate fom with half-lives greater than eight days, released to the environs as part of the gaseous wastes frcm the site, shall be such that 5
4.1[10 g3) b.
(1) The average release rate of ncble gases frcm the sita during any calendar quarter shall be such that 3 I 13[QTv v 1 and 6.3[QTv v 13I (2) The average release rate of noble gases from the site during any 12 consecutive mcnths shall be 25[Q W 31I Tv y and 13[Q F 31I Tv v (3) The average release rate.per site of all radiciodines and radicactive materials in particulate form with half-lives greater than eight days during any calendar quarter shall be such that 13[4.1 x 10 Q ]il y
(4) The average release rate per site of all radioicdines and radioactive materials in partculate fem with half-lives grester than eight days during any period of 12 consecutive months shall be such that 5
25[4.1 x 10 g gi) y (5) The amount cf iodine-131 released during any calendar quarter shall not exceed 2 Ci/ reactor.
I 2-10
kms (6) The amount of f odine-131 released during any period of 12 consecutive months shall not exceed a C1/ reactor.
c.
Should any of.the conditions of 2.2.3.c(1), (2) or (3) listed beloa exist, the licensee shall make an investigation to identify the causes of the release rates, define and initiate a program of action to reduce the release rates to design objective levels listed in Section 2.2.
A written report of these actions shall be submitted to the NRC within 30 days from the end of the quarter during which the release occurred.
(1)
If the average release rate of noble gases from the site during any calendar quarter is such that 50[Q li ]>l 7y y or 25[QTv v]'I fs (2)
If the average release rate per site of all radionuclides
)
(V and radioactive materials in particulate form with half-lives greater than eight days during any calendar quarter is such that 5
50[4.1 x 10 g ),)
(3)
If the amount of iodine-131 released during any calendar quarter is greater than 0.5 Ci/ reactor.
d.
During the release of gaseous wastes from the waste gas decay tank the process vent monitor (as listed in Table 2.2-4) shall be operating and set to alarm and to initiate automatically the closure of the waste gas discharge valve prior to exceeding the limits specified in 2.2.3.a above. The operability of each automatic isolation valve shall be demonstrated at least at least quarterly.
e.
The maximum activity to be contained in one waste gas storage tank _ shall not exceed 25,000 curies (considered as Xe-133).
f.
An unplanned or uncontrolled offsite release of radioactive materials in gaseous effluents in excess of 150 curies of noble gas or 0.05 curie of radioiodine in gaseous form requires notifica-tion. This notification shall be in accordance with Specifica-tion 5.6.2.2.c(3).
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TABLE 2.2-4 i v iH ANNA POWER STATION r.ASF005 WASTE SYSTEM LOCATION OF PROCESS AND tTFIVEhTHONTTORnNiTM'Lt H) uty0 Tutu ur itCHNICAL SPECIFICATIONS Release Point Continuous Monitoring Instrumentation Continuous Radiatinii Munitor Sampler Grab P i er.t Process Stream or Release Point Particulate Activity Radia t'lon Auto ToIitroTto flow Rate
~ - ~ Particulate Station No.
Sample Ins t riunenta t ion Noble C.as Recorder Alarm Isolation Valve Indicator l
Activity Process Vent
- X X
X X
X X
X X
rM-10l, Particu-I late y
GW-102, Gaseous b
d Ventilation Vent A g
x x
x X
X X
VG-103', P.irticu-late 7
VG-104, Gaseous C
d VG-11/,Particu-Ventilation Vent B X
X X
X X
X X
late VG-il/, G.neous N
N Reactor Containment (During Purging)
X X
X X
KMS-159, 259 Particulate Ri%-160, 260 Gaseous Cordenser Air Ejector X
X X
X X
SV-1?l, 2/1 Gioss Activity Steam Generator Blowdown Tank Condenser Vent e
g X - Required a - Exhausts waste gas decay t;nk and waste evaporator condenser b - Exhausts Auxiliary Building Central and General Areas,llot Laboratory.
c - Exhausts Safeguards Areas, Decon Bld9., Solidification Bldg., Reactor Containment and Fuel Bldg.
d - Flow element and recorder and integrator provided.
e - Radiolodine and Particulate samules shall be continuously collectepic
)
Sediment Discharge: 8 collection, Sr 89-90 North Anna River: 11 annually Shoreline Vicinity of: 9 INGESTION a
d 7
milk Nearest Dairies:
12, 13, 14 Monthly Radiciodine '", G.uuna isotopic monthly, Sr y
H9-90 quarterly Non-dairy activity Calculated dose Radiciodine"'", Gannaa b
b t
b dependent isotopic) Sr 89-90 Fish Reservoir: 9 Annually, near Ganana isotopic (Bass, or sunfish Discharge: 8 beginning of season or crappie and catfish)
Green Leafy 21, 23 Annually during Ganiaa isotopic on c
collection vegetation, harvest cultivated or weeds. Natural'y occurring O
O O
m.
_ _=-
4
_(
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i TABLE 3.2-1 (Continued)
NORTil ANNA POWER STATION OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM S
EXPOSURE PATHWAY'
' SAMPLE LOCATION AND/OR SAMPLING AND TYPE AND FREQUENCY AND/0R SAMPLE-MAP NUMBER DESIGNATION COLLECTION FREQUENCY OF ANALYSIS a.
.0nce each month 1,and 2 mrem thyroid isodose llnes will be calculated using the preJious month's release data.
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based on;the cow-milk-child. pathway. Should a dairy be located within the 1 mrem isoduse line the sompling and analysis frequency for radioiodine will be modified to semimonthly for the month following the month for 4
which the calculation was made. A similar sampling program will be for the ~2 mrem isodose line except on a weekly, frequency.
E ya b.
Monthly updates of the current year's annual accumulated calculated thyroid 15 mrem isodose lines based on the goat-milk-child and the cow-milk-child pathway will be done. Should the isodose line extend beyond the site
'n boundary, a survey to locate goats.or cows within the isodose line will be carried out within 30 days. Should goats. or cows be observed, efforts to obtain samples fran the owners of the animals will be put forth, if samples are obtainable, a sampling program similar to "a" above will be initiated. If sr ples are unobtainable, i
the annual report will document such and include the calculated doses, c.
Monthly updates of an annual'15 mrem isodose line (using release data and ma'ximum organ dnse in each of the 16 sectors) based on the grass-cattle-beef-man pathway will be done. Should the isodose line extend beyond the site boundary, sampling and analyses will be modified to monthly for the current year.
i d.
famples will be taken from the Environmental Laboratory well.
e.
Radioiodine analyses will be done by chemical separation.
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G.O'.A S?ICTRCSCCPY ENVIRCY.: NTAL S A?LES
'a'ater (1 li:er)
Soil & Vegetation Filters Nuclide eCi/l
(.'.0 0 m) pCi/m pCi/ total filter 3e 8E41 2E-01 2E+01 0
K 2E42 SE-01 S E+01 Cr el-01 2E-01 SE+01 Mn 8
2E-02 2
38 Co 8
2E-02 2
Fe lE401 4E-02 3
Co 8
2E-02 2
95 Zr lE+01 4E-02 3
Ru 8
2E-02 2
Ku 8E441 2E-01 SE4 1 I
10 3E-02 2
1 Cs'34 9
2E-02 2
137 Cs 9
2E-02 2
0 Ba 3E+01 SE-02 6
La 2E+01 4E-02 2E4 1 Ce'41 2E+01 4E-02 3
1 Ce 8E+01 2E-01 2E+01 Ra"6 6E+01 1E-01 1E+01 Th'28 1E+01 2E-02 lE+01 0
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s TABLE 3.2-3 LOWER LIMITS OF DETECTION L.L.D. &
Sampled Volume Samole Analysis Recortino Units Recuired 125 m3 1.
Airborne Particulate 3
Gross Alpha 2.5 x 10 3pCi/m Gross Beta 7.6 x 10 3 Ci/iT.3 p
Ge(Li) 3-isotopic See Table 3.?-2 2.
Airborne Iodine 125 m3 Charcoal Cartridge I-131 2.4 x 10 2pCi/m 3 3.
Direct Radiation TLD Environmertal Badge 2mR i 2mR 4.
Milk 4 liters 4
Sr-90 0.8 pCi/t fsg 4
s}
I 131 by Chemical Separation 0.5 pCi/t Total Calcium Ge(Li) y-isotopic (Cs-137)
See Table 3.2-2 Cs-137 Chemical Separation 3 pC1/t S.
Well Water 2 liters Gross Alpha
.5 pCi/t i
Gross Beta 0.5 pCi/1 Tritium (gas count) 100 pCi/t 1.
Ge(Li) y-isotopic See Table 3.2-2 2
6.
Surface Water 2 liters Gross Beta 0.5 oCi/t j
Tritium (gas count) 100 pCi/t j
Ge(Li) y-isotopic See Table 3.2-2 7.
Fish: Flesh (2) 1 Kg l
Gross Beta plus K-40 0.1 pCi/gm wet Ge(Li) Y-isotopic See Table 3.2-2 Sr-89 0.8 pCi/gm*
j Sr-90 0.5 pCi/gm*
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Samoled '!cl'.re Sa ole Analysis Recortir.g L'r.i ts Recuired 8.
Vegetation Samoles (2) 1 Kg A.
Corn See Table 3.2-2 Ge(Li),-isotopic 0.5 pCi/gm" Sr-90 B.
Leaf Vegetation (2) 1 Kg Ge(Li)
See Table 3.2-2 Sr-39 0.8 pCi/ga" Sr-90 0.5 pCi/gm*
C.
Food / Garden Crocs (e.g. Lettuce)
(2) 1 Kg Ge(li)
See Table 3.2-2 Sr-39 0.8 pCi/gm*
Sr-90 0.5 pCi/gm*
D.
Terrestrial Vegetation 1 Kg Ge(Li)
See Table 3.2-2 E.
Acuatic Vegetation Ge(Li) y-isotopic See Table 3.2-2 Sr-99 0.3 pC1/gm*
Sr-90 0.5 pC1/gm*
9.
Soil 1 Kg Ge(Li) y-isotopic See Table 3.2-2 10.
Silt (2) 1 Kg Ge(Li) y-isotopi.c See Table 3.2-2 Sr-89 0.S oCi/gm Sr-90 0.5 pCi/gm
- Detection in limits as stated are per gram of ashed traterial. The actual detection limits in pCi/gm (wet) will vary by a factor of 10-100, depending on the wet versus ash weight factor.
O I 3-10
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on stated sensitivities and sample size up to a 255 deviation. All deviations from the sampling schedule shall be described in the annual report.
Recortino Recuirenent Routine and nonroutine reports shall be submitted in accordance with the requirements of Section 5.
Bases These specifications ensure that releases of radionuclides to the environcent are properly controlled and monitored.
The data obtained as a result of these requirements enable the licensee and the Commis-sion to evaluate the performance of the station in terms of radio-nuclides released to the environment.
The environmental monitoring program requires sufficient numbers, types of samples, and sensitivity of analysis which, with preoperational and background data, will provide verification of the effectiveness of station effluent control, an indication of measureable changes in radiation and radioactivity levels in the environment.
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4,0 SPECIAL SURVEILLANCE AND STUDY ACTIVITIES t
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.t 5.0 ADMINISTRATIVE CONTROLS.
Administrative controls below apply to Appendix B Part I only.
5.1 Responsibility The responsibility 'for implementing the Environmental Technical Specifications-is assigned to the Manager-Nuclear Operations and Maintenance'at the corporate level and to the Station Manager at the station level. The Superintendent.-
Operations shall be responsible for ensuring that the station is operated in accordance with the Limiting Conditions of Operation.
The Station Supervisor :
Health Physics shall be responsible for the radiological environmental surveillance requirements.- The executive Manager of Environmental Services shall be responsible for providing services which will fulfill the non-radiological environmental surveillance requirenents.
5.2 Organization The relationship between-the Nuclear Operations Department and the Environmental Services Department is shown in Figure 5.2-1.
D 5.3 Review and Audit 5.3.1_
Staticn Nuclear Safety and 0::erating Cormittee (5:iSOC)
'5.3.1.1 Function _
The SNSOC, as described in Section 6.5.1 of Appendix A cf this license, shall Tunction to advise the Station Manager en r:atters related to the envircreental impact of the station.
'n' hen the Sl450C is exercising its responsibility for non-radiological aspe' cts of the ETS, the Station Biologist or his alternate shall be consulted.
5.3.1.2 Responsibility, The SNSOC.shall be responsible fcr:
a.-
Coordinatica of the Envircnrental' Technical Specifications with the Safety Technical Specifications (Appendix A) to avoid con-flicts and maintain consistency.
,b.
Review of changes to the.Envircr: ental Tecnnical Specifications and the evaluation of the envircr ental impact of the change.
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Figure 5.2-1 ORGAllI7ATZ0H CliART q
ENVIR0lMEliTAL TECH SPEC IMPLEMEliTATION 2@
l EXECUTIVE VICE PRESIDENT PO'w'ER f
~>
l EXECUTIVE MANAGER !
EXECUTIVE MANAGER LICENSING & QUALITY EllVIR0llMENTAL SERVICES A.MUMNCc, i
l I
7 MANAGER MANAGER DIRECTOR WATER QUALITY AIR QUALITL MANAGER w
i 4
NUCLEAR QUALITY j
OPERATIONS 6 MAINT.
A$$ URAL {CE j
SUPEiivlaux GI0 LOGICAL S.T&II.O.y,M_A!!AGER t
OPERATIONS l t
I SUPERINTENDENT SUPERINTENDEllT s
l 0PEJATiGNS TECHNICALSERVICES SUPERVIS03 SUPERVISOR
'SUPEgvlSORi QUALITY ASSURANCE HETE0a0 LOGICAL Am i
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- OPERATiolis i MO:J7T0a!! G j
~ SUPERVISOR
"~
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. PilYSICS O
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a ss' c.
Review of proposed written pr:cedures required by Sections 5.5.2 and 5.5.3 belcw and changes thereto, which affect the environrental impact of the staticn.
d.
Review of proposed changes to station systems to determine the environmental impact of the changes.
e.
Investigation of all reported instances of violation of the Environmental Technical Specifications; and where the investiga-tion indicates, evaluation and formulaticn of recomendations to prevent recurrence, f.
Review of environmental monitoring programs to detect potential or existing significant adverse environmental impacts that have not been evaluated, or that are significantly greater tnan that evaluated by the Ccmission.
5.3.1.3 Authori ty The SNSOC shall:
n, a.
Review the environmental evaluation of all changes described in
(\\s)
Section 5.3.1.2 a, b and c, above. When the evaluation indicates that such activity may result in a significant adverse envircn-mental impact that was not evaluated, or that is significantly greater than that evaluated by the Commission, the SNSOC shall ensure that a written evaluation of such activities is provided to and prior approval is obtained from the Director of Nuclear Reactor Regulation for the activities.
4 If the SNSOC determines that unexpected harnful effects or evidence of irreversible damage are occurring as a result of operation of the station, the SNSOC shall ensure that an acceptable analysis of the problein and a plan of action to eliminate or significantly reduce the harmful effects or damage is submitted to the Comission for review and approval, c.
Review written reports prepared as a result of investigations and rrviews conducted under 5.3.1.2 a, e and f.
- 5. 3.1.4 Records The SNSOC shall maintain written minutes of each meeting and copies shall be provided to the Chairman of the System Nuclear Safety and Operating Comittee (SyNSOC).
O t
I. 5 -3
O 5.3.2 Sucervisor, Ouality Assu ance, Ocerations and Paintenance 5.3.2.1 Functicn The Superviser, Cuality Assurz.nce, Operations and Maintenance shall cerform independen: audits of the implementa:icn of the Environmentai Technical Specifications.
5.3.2.2 Audits The following audits shall be completed:
a.
The conformance of facility cperation to provisicns ccntained within these Environmental Technical Specifications and applica-tie license conditions at least once per 12 mcnths.
b.
The performance, training and qualifications of the facility staff involved in ensuring and monitoring compliance with tnese Environmental Technical Specifications at least once per 12 months.
c.
The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect the environmental impact of the station at least once per 12 months.
5.3.2.3 Records Provide a written report of the results of the audits required by 5.3.?.2 above to the SNSOC, the SyNSCC and tne Station Manager.
5.3.3 System Nuclear Safety and Ooeratinc Cemittee (SyNSCC) 5.3.3.1 Function The SyNSOC as described in Section 6.5.2 of Appendix A of this license, shall function to provide indecendent review of designated activities related to the environmental impact of the station.
5.3.3.2 Review The SyNSOC shall review and, wnere necessary, coment on the results of the reviews conducted by the SNSOC and the independent audits conducted by the Supervisor, Quality Assurance, Operations and Maintenance.
O I-5-4
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3
..g 5!3.3.31 ' :ss::es'bility The Sy'.50C has the res; nsibility f;r er.surin; t: at the sta;' n is 0: era:ed in at:Ordance with the re: Lire ents of tr.is li arss and t
3;pli:a:le.'.?C regulati:ns.
5.3.3.4
' Authori ty The SyNSOC shall report to and advise the Executive Manager-
~
Licensing and. Quality Assurance, who shall advise the Executive lice President-Power on -those : areas relating to. the environmental impact of the station.
5.3.3.5
,Reco rds The SyNSOC shall maintain written minutes of each meeting and a copy shall be provided to the' committee members and the Executive Vice President-Power on those areas relating-to the
- environmental-. impact of the station.
5.4'
' state and Federal 'Fermits and Certificam
.)Q None 5.5 Frocedures 5.5.1
'4r'itten Procedures Detailed written procedures, including applicable checklists and instructions,. shall be prepared and.foll:wed for all activities invcived in carrying out = the Environrental Technical Scecificaticns as defir.ed in Sections-5.5.2, 5.5.3, and.5.5.4, belcw.
Frocebres shall include sampling, data, recording and storage,-instrument calibration, measure-cents and analyses, and actions to be taken when limits are appr: ached or exceeded. Testing frequency of any alarm shall be included. These frequencies shall be deterrained from experience with similar instru-ments -in similar enviror. cents and from nanufacturer's technical ranuals.
'5.5.2
-Oceratino Procedures
- Plant standard operating procedures shall include provisions, in
-addition 'to. the proc 5dures-- specified in Section 5.5.1, to ensure that all pla'nt systems and components are operated in compliance with the Limiting Conditions of Operations established as part of the Environ-mental Technical Specifications.
.( 7
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t u-I-5-5
O 5.5.3 Precedures for Envircemental S;rveillance - Radioloaical Procedures to inplement the radiological envir r. mental monitoring crogram shall be prepared and maintained in a manual for that purpcse.
Securing samoles, scneduling, transporting of samoles, required anal-ysis and reporting will be included.
5.5.4 Procedures for Environmental Surveillance - Nonradiological Not applicable.
5.5.3 Ouality Assurance of Procram Results The procedures document shall provide for assurance of the quality of program results, including analytical measurements. This portion of the procedures document shall document the program in' policy directives, designate a responsible organization or individuals, include purchased services (e.g., contractual lab or other contract services), include audits by licensee personnel, and include procedures for revising programs, systems to identify and correct deficiencies, investigate anomalous or suspect results, and review and evaluate program results and reports.
5.5.6 Chances in Procedures, Statior Design or Oceration Changes in procedures, station design or cperation may be made subject to conditions described below, provided such changes are approved by the SNSCC (Review and Audit responsibility per Section 5.3).
a.
The licensee may (1) make changes in the station design and operation as described in the FES, FES Addendum and the Environ-rcental Report, (2) make changes in the procedures described in the document developed in accordance with Subsection 5.5, and (3) conduct tests and experiments not described in the document developed in accordance with Subsection 5.5, without prior Commis-sion approval, unless the proposed change, test or experiment involves a change in the objectives of the ETS, an unreviewed environmental question of substantive impact, or affects the requirements of Subsection 5.5.7 of these ETS.
b.
A proposed change, test, or experiment shall be deemed to involve an unreviewed environmental question (1) if the probability of magnitude of environmental impact may be increased; cr (2) if a possibility for a substantive environmental impact of a different type than any evaluated previously in the FES or FES Addendum may be created.
1-5-6
I P)-
.c._
The licensee shall main ain records of chances in crocedures and jD
.in facility: design or operation ::ade pursuant to this Subsectic.,--
to ~ the extent that such changes. constitute changes.in procetares as described in.tne document deveicped in 'acccrdance with Section -
5.5 or in the FES, FES Addendun.and EP.
The licensee-shall also
' maintain' records of tests and experiments carried out pursuant
.to paragraph "a" of this Subsection.
These records-shall include a written evaluation which provides the bases for the dete-mination that the change,; test, or experiment does not involve an unreviewed i
environmental question of substantive impact or constitute a change
.in the objectives of these ETS,lor-affect the requirements of
~
j:
Section 5.5.7 of these ETS.
The licensee shall furnish-to the
' Commission, annually or at such shorter intervals as nay be i
specified in the license, a' report containing descriptions, analyses, interpretations, and evaluations of such changes, tests and.exper,iments.
d.
Changes in the procedures developed in accordance with Subsection 5.5 which affect sampling frequency, location, gear, or replication shall be reported to the NRC within 30 days after their implementa-tion. These reports shall describe the changes made, the reasons for making the changes, an evaluation of the environmental l
impact of these changes,' and the statement required under the provisions-of Subsection 5.5.7.
5.5.7 Consistency with Initially Approved Programs
. O
- 1]
Any modifications or.. changes of the procedures developed in
.j accordance with Subsection 5.5 must be governed by the need to maintain consistency with previously used procedures so that 4
direct comparisons' of data are technically. valid. Such modifications or changes must be justified-and supported by j
adequate comparative sampling programs or studies demonstrating 1
the comparability of.results.or which provide a basis for making l
adjustments that would permit direct comparisons.
These demonstrations.of comparability shall be submitted to the NRC in accordance with the provision of Subsection 5.5.6 and 5.6.1 of these ETS.
'5.6 Station Reporting Reouirements 5.6.l_
Routine Reports 5. 6.1. l '
Annual Environmen'tal Operating Report 1
A report on the radiological environmental sur'veillance programs for the previous calendar year shall be submitted to the Director of the
' NRC Region II Office (with a copy to the Director, Office of Nuclear Reactor Regulation) as a separate document by April 1 of each year. The period-of the first report shall begin with the date of initial criti-cality of Unit No. _l. The reports shall include summaries, interpre-
.f]
tations, and statistical evaluation of the results of the radiological l
y 1
I-5.
- "L g
environ ental surveillance activities for the report period, including a ccrpariscn with pre:;erational studies, operational controls (as accropriate), and previous envircnr. ental surveillance re; orts and an assessment of the cbserved impacts of the plant oceration on the envirencent.
The reports shall also include the resalts of any land use censuses required by Section 5.6.1.2.
If haraful effects or evidence of irreversible darage are detected by the conitoring, the licensee shall provide an analysis of the problem and a proposed course of ac:fon to alleviate the problem.
Results of all radiciogical environmental sanples taken shall be summarized and tabulated on an annual basis.
In the event that sore results are not available within the 90-day period, the report shall be submitted noting and explaining the reasons for the missing result" The missing data shall be submitted as soon as possible in a supple-mentary report.
5. 6.1. 2 Radioactive Effluent Re. :se Report A report on the radicactive discharges released frcm the site for the previous semi-annual period (January-June and July-Cecember) shall be submitted to the Director of the tiRC Region II Office (with a copy to the Director, Of fice of Nuclear Reactor Regulation) by March I and Septerber 1.of each year.
The ceriod of the first report shall begin with the date of the initial criticality of Unit 1.
The report shall include a sumary of tne quantities of radioac:ive liquid and gaseous effluents and solid waste eleased fecm the statien as cutlir.ed in Re;ulatory Guide 1.21, " Measuring, Evaluating, ard Reporting Radio-ac.ivity in Solid Wastes and Releases of Radioactive "aterials in i. quid Ga s eous E f fluents frca Light '<.'a:er-Ccol ed I;uc' ear Pc.;er Flants,"
witn da ta sum.arized on a quarterly basis.
The re:essiry data and forcat are listed in Appendix 8, Tables 1 A,1C, 2A, 23, and 3 of Regulatory Guide 1.21.
Table 4A should be duplicated for continuous and intermittent relcases, so that the ap;ropriate correlati:n of ef fluents with tre:ecrolo;ical data can be rade in the calculation of offsite doses.
The report shall include a surary of the r:ete;r;;;gical conditions concurrent with the release of gasecus effluen'.: durine each quarter as outlined in Regulatory Guide 1.21, with data s'c.ari:ed on a quarterly basis following the for at of A;;endix B thereof. The licensee will follow Reg Guides 1.21 and 1.109 through 1.113 (revisions in effect at the beginning of the report pericd) to calculate and report the expi sures to individuals and copulations from the effluents.
In connection with this, the locations of the follonin: critical receptors should be redetermined at the beginning of the ;r; sinc / grazing season in each sector (out to five miles from Unit 1), tr.e nearest housino unit (including trailers and su rer homes), garder., cow, and sat ar.imal (including chickens where they are used extensively for food).
O I-5-8 L-
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5.6.2 fionroutine Reports 5.6.2.1 flonroutine Non-Radiological Environmental Operating Report flone.
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0 5.6.2.2 Nonroutine Radiological Environmental Operating Reports a.
Anomalous fieasurement Report.
If a confirmed measured level of radioactf vity in any environmental medium exceeds ten times the control station value, a written report shall be submitted within 30 days after confirmation.* This report shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous result.
b.
Pathway Measurerent Recort.
If pathway sa oles collected over a calendar quarter sr.ow average levels of radicactivity greater than 10 times the trend established by previcus ronitoring, a written report shall be included in the report required by Secticn 5.6.1.2.
c.
flonroutine Radioactive Effluent Reoorts (1)
FWR Liquid Radicactive Wastes Report.
If the cumulative releases of radioactive materials in liquid effluents, excluding tritium and dissolved gases, should exceed one-half the design i
objective annual quantity during any calendar quarter, the licensee shall make an investigation ts.dentify the causes of such releases and define and initiate a program of action to reduce such releases to the design objective levels. A written report of these actions shall be submitted to the f;RC within 30 days from the end of the quarter during which the release occurred.
(2) PWR Gasecus Radicactive Wastes Report.
See Section 2.2.3c.
OA confirmatory reanalysis of the original, a duplicate or a new sample may be desirable, as appropriate. The results of the confirmatory analysis shall be conpleted at the earliest time consistent with the analysis, but in any case within 30 days. If the anomalous value is confirmed, the report to the fiRC shall be submitted.
I 5-10
-(3)
P'.!R ifnplanned cr Uncentrolled Release Re:0 t.
Any un;12ined or uncontrolled offsite release of radicactive materials in excess of 0.5 Curie in liquid or in er.cass of 150 Curies of
,[mN noble gases or 0.05 Curie of radiciodines in gaseous fo m requires notification.
This notification must be nade by a written report within 30 days to the NRC. The report shall describe the event, identify the causes of the uno!cnned or uncontrolled release and report actions taken to prevent 1
t recurrence, d.
Written 30-day reports will be submitted to the following addresses:
(1) Region II, Office of Inspection and Enforcement, USNRC, Atlanta, Georgia (2 copies)
(2) Director Office of Inspection and Enforcement, USNRC, Washington, D. C.
(20 copies)
(3)
Director, Office of Management Information and Program Control, USNRC, Washington, D. C. (2 copies) 1 (4) Director, Office of Nuclear Reactor Regulation, USNRC, Washington, D. C. (1 copy) 5.6.3 Chances in Environmental Technical Specifications A report shall be made to the NRC prior to imple.entation of a change in plant design, in plant operation, or in procedures described in m
)
Section 5.5 if the change would have a significant effect on the x/
environment or involves an environmental matter or question not previously reviewed and avaluated by the NRC. The report shall include a description and evaluation of the change and a supporting benefit-cost analysis.
Request for changes in environmental technical specifications shall I,e submitted to the Director Office of Nuclear Reactor Regulation, for review and authorization.- The request shall include an 4
evaluation of the environmental impact of the proposed changes and a supporting benefit-cost-analysis.
5.6.4 Changes in Permits and Certifications None.
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-Records Retention Records and logs relative to the following areas shall be made end retained for the life of the station:
a.
Records and drawings detailing plant design changes and modifica-tions made to. systems and equipment as described in Section 5.6.3.
b.
Reports from environmental monitoring, surveillance, and special
' surveillance and study activities required by these Environmental gd(
Technical Specifications.
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i APPENDIX B l
TO FACILITY OPERATING LICENSE NO. NPF-7 NORTH ANNA POWER STATION j
UNIT 2 l
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l VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-339 i
I ENVIRONMENTAL TECHNICAL SPECIFICATIONS PART II - NON-RADIOLOGICAL k
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x NORTH ANNA POWER STATION UNIT 2 i
ENVIRONMENTAL TECHNICAL SPECIFICATIONS (NON-RADIOLOGICAL)
TABLE OF CONTENTS 1
Section Pg 1.
Definitions................................................
1-1 2.
Limiting Conditions for Operation..........................
2-1 4
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Environmental Monitoring...................................
3-1
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4.
Special Studies and Requirements...........................
4-1 4.1 Exceptional Occurrences...............................
4-1 i
4.2 Special Studies.......................................
4-1 5.
Administrative Controls....................................
5-1 5.1 Responsibility........................................
5-1 5.2 Review and Audit......................................
5-1 5.3 Changes in Station Design or Operation................
5-1 5.4 Station Reporting Requirements........................
5-2
- 5. 5 Changes in Environmental Technical Specifications and Permits.........................................
5-4 5.6 Records Retention.....................................
5-4 1
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DEFINITIONS
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Annually: Annually is once per calendar year at intervals of twelve calendar months + 30 days.
Clean Water Act:
Federal Water Pollution Control Act (FWPCA) as amended.
NPDES Permit:
NPDES permit is the National Pollutant Discharge Elimination System Permit No. VA0052451 issued by the Commonwealth of Virginia to Virginia Electric and Power Company (VEPC0).
This permit authorizes VEPC0 to discharge controlled waste water from the North Anna Power Station into waters of the Commonwealth of Virginia.
Site:
Onsite includes any area within the 1075 acre site and exclusion area as specifically described in the North Anna EIS Section 2.1.
Offsite includes all other areas.
Station:
Station refers to North Anna Power Station Units 1 and 2.
Unit:
Unit refers only to Unit 1 or Unit ? of the North Anna Power Station, as defined by its usage.
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2.
LIMITING CONDITIONS FOR OPERATION
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None required.*
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. ln consideration of the; provisions of the Clean Water Act (33 USC S 1251, A
et seq.) and in the interest of avoiding duplication of effort, the conditions and monitoring requirements related to water quality and aquatic biota are specified in the National Pollution Discharge Elimination System (NPDES) Permit j
No.-VA0052451 issued by the Commonwealth of Virginia to the Virginia Electric and Power Company (VEPC0).. This permit authorizes VEPC0 to discharge controlled waste water from the North Anna Power Station into waters of Virginia.
l The Nuclear Regulatory Commission will be relying on the NPDES permit limita-
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tions for protection of the aquatic environment from non-radiological effluents.
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3.
ENVIRONMENTAL MONITORING None required.*
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^In consideration of the provisions of the Clean Water Act (33 USC $ 1251, et seq.) and in the interest of avoiding duplication of effort, the conditions i.
and monitoring requirements related to water quality and aquatic biota are specified in the National Pollution Discharge Elimination System (NPDES)-Permit i
No.-VA0052451 issued by the Commonwealth of Virginia to the Virginia Electric and Power Company (VEPCO).
This permit authorizes VEPC0 to discharge controlled waste water from the North Anna Power Station into waters of Virginia.
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The Nuclear. Regulatory Commission will be relying on the NPDES permit limita-O tions for protection'of the aquatic environment from non-radiological effluents.
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4.
SPECIAL STUDIES AND REQUIREMENTS 4.1 Exceptional Occurrences 4.1.1 Unusual or Important Environmental Events Specification The licensee shall record any occurrence of unusual or important events.
Unusual or important events are those that potentially could cause or indicate environmental impact causally related with station operation.
The following are examples:
excessive bird impaction events; onsite plant or animal disease outbreaks; unusual occurrence or nortality of any species protected by the Endangered Species Act of.1973; fish kills near the plant site; unanticipated or emergency discharges of waste water or chemical substances.
Reporting Requirement Should an unusual or important event occur, the licensee shall make a prompt report to the NRC in accordance with the provisions of Subsections 5.4.2.a and 5.4.2.c or Subsection 5.4.2.d.
4.1.2 Exceeding Limits of Other Relevant Permits Specification
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The licensee shall notify the NRC of occurrences in which the limits specified
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in relevant permits and certificates issued by other Federal, State, and local agencies are exceeded and which are reportable to those agencies.
Reporting Requirement The licensee shall make a report to the NRC in accordance with the provisions l
of Subsections 5.4.2.b and 5.4.2.c or Subsection 5.4.2.d in the event that a limit specifi.ed in a relevant permit or certificate issued by another Federal, State, or local agency is exceeded.
4.2 Special Studies 4.2.1 Transmission Line Rights-of-Way Herbicide Management Objective The objective of the monitoring program is to determine impact of herbicide applications on the environment.
Specification The use of herbicides to control undesirable vegetation in the transmission rights-of-way associated with North Anna Power Station will conform to the approved use of selected herbicides'as registered by the Environmental
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Protection Agency and the Virginia Department of Agriculture.
The rates of v
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application will follow recommendations by the Agricultural Extension Service of the Virginia Polytechnic Institute and State University.
The application of herbicides to rights-of-way must be controlled so as to prevent drift.
No herbicides may be applied on rights-of-way over pasture, cropland, or irrigation ditches or near water bodies, homes, or recreation areas.
Reporting Requirements The Annual Environmental Operating Report (Section 5.4.1) will include a statement as to whether herbicides were used.
In addition, a brief description of the type (s), volume (s), concentration (s), maraer, and frequency of applica-tion will be included.
Field logs summarizing weather conditions, location of applications, and rates of application f,hould be kept and be available for a period of five years.
Inspections should confirm that restricted areas have not been sprayed, unauthorized releases have not taken place, and accidents such as spills have been documented and cleaned up if possible.
A summary of the application and inspection programs will appear in the Annual Environmental Operating Report (Section 5.4.1).
Bases Herbicides, unless judiciously applied, can destroy bird and mammal habitat and cause changes in the chemistry of soil, ground, and surface waters.
Use of herbicides will conform to variaus local and Federal regulations.
This informtion will provide surveiliance information to the staff to ensure that herbicide applications conform to current regulations and thereby minimize environmental impact due to right-of-way maintenance procedu es.
4.2.2 Transmission Line Right-of-Way Erosion Control Inspection Objective Periodic maintenance activities or severe weather may cause instances along the transmission line corridors associated with North Anna Power Station where soil or slope stabilization will be necessary.
A yearly record during normal line surveillance activities will indicate any areas showing erosion or vegetation damage and all reasonable steps shall be taken to stabilize such occurrences.
Specifications All areas along the corridors showing evidences of erosion should be recorded during normal line surveillance.
All actions taken to stabilize such occurrences will be recorded.
Reporting Requirements The Annual Environmental Operating Report (Section 5.4.1) will include a summary of the field inspection programs.
Field logs summarizing locations of erosion damage and appropriate actions taken to rectify erosion problem areas II-4-2 1
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should be kept and be available for a period of five years.
A summary of the
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inspection program and corrective actions taken will appear in the Annual i
Environmental Operating Report (5.4.1).
Bases Periodic maintenance activities or severe weather conditions may cause instances along the transmission line corridors when reseeding or other appropriate erosion control activities will be necessary.
Routine corridor surveillance techniques will identify erosion problem areas and coupled with appropriate erosion control steps will ensure that such areas become stabilized.
4.2.3 Vegetation Studies Objective The objective of this monitoring program is to evaluate the effects of power station operation on the vegetation types and vegetation production in two plots adjacent to the Waste Heat Treatment Facility, two plots adjacent to Lake Anna, and one plot downstream near the Lake Anna Dam.
Specifications The initial vegetation surveys were conducted to determine plant gm (1) density
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(2) productivity kJ (3) diversity on both the community and species levels.
Each of the five plots were sampled in the same manner using methods commonly employed in the ecological analysis of vegetation.
The initial survey has been summarized and will be used as the base. for studies to be conducted at the end of the growirig seasons in 1979 and 1981.
This study will terminate after 1981.
If an adverse environmental impact is identified, then approval from the NRC must be obtained before this study is terminated.
Reporting Requirements Any adverse environmental impact identified by this study shall be reported in the Annual Environmental Operating Report (Section 5.4.1).
Bases The responses of the floral community to possible envircnmental alterations due to the impoundment of Lake Anna and the Waste Heat Treatment Facility will l
be monitored in the dominant oak pine forest typical of the area.
- Growth, development, and population structure may be modified due to the proximity of a water body having temperatures above the natural equilibrium level.
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The monitoring program has been designed to detect changes in various components of the dominant vegetation types and to assess the cause and effect of the changes.
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_ 5.
ADMINISTRATIVE CONTROLS
\\j Administrate controls below apply to Appendix B - Part II only.
5.1 Responsibility The responsibility for implementing the Environmental Technical Specifications is assigned to the Director of Nuclear Operations at the corporate level and to the Station Manager of the Station Level.
The Executive Manager of Environ-mental Services shall be responsible for providing servicas which will fulfill the non-radiological environmental surveillance requirements.
5.2 Review and Audit 5.2.1 Review The Station Nuclear Safety and Operating Committee (SNSOC) is responsible for the review of procedures for meeting these environmental technical specifications.
The above mentioned review shall be conducted on the following:
A.
Proposed changes to the Environmental Technical ' specifications and any evaluation of the environmental impact of the changes.
B.
Proposed changes to station operating procedures, which affect the
, O environmental effects of the station, and any evaluation of the environ-
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mental impact of the changes.
C.
Proposed changes or modifications'to station or unit equipment, or systems which might have an environmental impact, and any evaluation of the environmental' impact of the changes.
D.
Investigations of all reported instances of noncompliance with Environmental Technical Specifications, associated corrective actions, and measures taken to prevent recurrence.
5.2.2 Audit The_ supervisor, Quality Assurance, Operations and Maintenance, shall conduct
- an annual audit of the implenntation of these Environmental Technical Specifications.
5.3 Changes in Station Design or Operation
-Changes in procedures, station design or operation may be made subject to conditions described below, provided such changes are approved by the SNSOC (Review and Audit' responsibility per'Section 5.2).
' A.
The licensee may (1) make changes'in the station design and operation as described in the FES, FES Addendum and the Environmental Report, and (2) conduct tests and experiments not described in this document without
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prior Commission approval, unless the proposed change, test, or experiment II 5-1
involves a change in the objectives of the ETS, or an unreviewed environ-mental question of substantive impact.
B.
A proposed change, test, or experiment shall be deemed to involve an unreviewed environmental question (1) if the probability of magnitude of environmental impact may be increased; or (2) if a possibility for a substantive environmental impact of a differt:nt type than any evaluated previously in the FES or FES Addendum may be created.
C.
The licensee shall maintain records of changes in facility design or operation made pursuant to this Subsection to the extent that such changes constitute changes in procedures as described in the FES, FES Addendum and ER.
The 'icensee shall also maintain records of tests and experiments carried out pursuant to paragraph "a" of this Subsection.
These records shall include a written evaluation which provides the bases for the determination that the change, test, or experiment does not involve an unreviewed environmental question of substantive impact or constitute a change in the objectives of these ETS.
The licensee shall furnish to the Commission, annually or at such shorter intervals as may be specified in the license, a report containing descriptions, analyses, interpretations, and evaluations of such changes, tests, and experiments.
D.
Changes in the special studies, if required in Section 4.2, which affect sampling freq-cy, incation, gear, or replication shall be reported to the NRC withir. 30 days after their implemeritation.
These reports shall describe the changes made, the reasons for naking the changes, and an evaluation of the environmental impact of these changes.
Such changes must be governed by the need to maintain consistency with previously used procedures so that direct comparisons of data are technically valid.
Such modifications or changes must be justified and supported by adequate comparative sampling programs or studies demonstrating the comparability of results or which provide a basis for making adjustments that would permit direct comparisons.
5.4 Station Reporting Requirements 5.4.1 Routine Reports Annual Environmental Operating Report A report on the non radiological environmental monitoring programs for the previous year shall be submitted to the NRC separate from other NRC reporting requirements by May 1 of each year.
The period of the first report shall begin with the date of issuance of the operating license.
The report shall include summaries, analyses, interpretations, and statistical evaluation of the results of the enviromental monitoring required by special studies and requirements (Section 4) for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous non-radiological environmental monitoring reports, and an assessment of the observed impacts of the station operation on the environment.
If harmful effects or evidence of irreversible damage are suggested by the monitoring programs, the licensee shall provide a more detailed analysis of the data and a proposed course of action to alh.viate the problem.
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m For those programs concerned with water quality or protection of aquatic
(~ V) biota, which are regulated under the Clean Water Act, the requirements of this section shall be satisfied by submitting to the NRC copies of the reports as required by the NPDES permit (or otherwise required pursuant to the Clean Water Act), and in accordance with the frequency, content, and schedules set forth by the agencies responsible for implementing the Clean Water Act.
In'the event that some results are not available by the report due date, the report shall be submitted noting and explaining the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
The Annual Report shall also include a summary of:
1.
All ETS noncompliances and the corrective actions taken to remedy them.
2.
Changes made to applicable State and Federal permits and certifications.
3.
Changes in station design which could involve an environmental impact or change the findings of the FES.
4.
All ncaroutine reports submitted per ETS Section 4.1.
5.
Changes in approved ETS.
5.4.2 Nonroutine Reports
{N A report shall be submitted in the event that an " Unusual or Important Environ-y) mental Event," as specified in Section 4.1.1 occurs, or if another relevant permit is violated as specified in Section 4.1.2.
The schedule and content for these nonroutine reports are described below:
5.4.2.a Prompt Report Those events specified as requiring prompt reporting shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone, telegraph, or facsimile transmission to the NRC followed by a written report to the NRC within 30 days.
5.4.2.b Thirty-Day Report Those events not requiring a prompt report as described in Subsection 5.4.2.a shall be reported to the NRC within 30 days of their occurrence.
5.4.2.c Content of Nonroutine Reports Written 30-day reports and, to the extent possible, the preliminary telephone, telegraph, or facsimile reports shall (a) describe, analyze, and evaluate the occurrence, including extent and magnitude of the impact, (b) describe the cause of the occurrence, (c) indicate the action taken to correct the reported occurrence, and (d) indicate the corrective action taken (including any signifi-cant changes made in procedures) to preclude repetition of the occurrence and to prevent similar occurrences involving similar components or systems.
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5.4.2.d Exceptions for Matters Regulated Under the Clean Water Act
. For matters regulated under the Clean Water Act, the report schedules and content requirements described in Subsections 5.4.2.a, 5.4.2.b, and 5.4.2.c shall be satisfied by submitting, to the NRC, copies of reports as required by the NPDES permit (or other regulations pursuant to the Clean Water Act) and in accordance with the schedules and content requirements imposed thereby.
5.5 Changes in Environmental Technical Specifications and Permits 5.5.1 Char.ges in Environmental Technical Specifications Requests for changes in environmental technical specifications shall be submitted to the NRC for review and authorization per 10 CFR 50.90.
The request shall include an evaluation of the environmental impact of the proposed change and a supporting justification.
Implementation of such requested changes in ETS shall not commence prior to incorporation by the NRC of the new specifications in the license.
5.5.2 Changes in Permits and Certifications Changes and additions to required Federal (other than NRC), State, local, and regional authority permits and certificates for the protection of the environment shall be reported to the NRC within 30 days.
In the event that the licensee initiates or becomes aware of a reques' for changes to any of the water quality requirements, limits, or values stipulated in any certification or permit issued pursuant to the Clean Water Act, the NRC shall be notified within 30 days.
If a r emit or certification, in part or in its entirety, is appealed and stayed, the NRC shall be notified within 30 days.
If, as a result of the appeal process, the permit or certification requirements are changed, the change shall be dealt with as described in the previous paragraph of this section.
5.6 Records Retention Records and logs relative to the environmental aspects of station operation shall be made and retained in a manner convenient for review and inspection.
These records and logs shall be made available to NRC on request.
5.6.1 The following records shall be retained for the life of the station:
(a) Record of changes to these Environmental rechnical Specifications including, when applicable, records of NRC approval of such changes.
(b) Record of modifications to station structures, systems, and components determined to potentially affect the continued protection of the environment.
(c) Record of changes to permits and certification required by Federal (other than NRC), State, local, and regional authorities for the protection of the environment.
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w (d) Routine reports submitted to the NRC.
5.6.2 Records of tre following shall be retained for a minimum of five years:
(a) Review and audit activities.
(b) Events, and the reports thereon, which are the subjects of nonroutine reports to the NRC.
5.6.3 Records associated with requirements of Federal (other than NRC),
State, local and regional authorities' permits and certificates for the protection of the environment shall be retained for the period established by the respective permit or certificate.
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NRC FoRu 335
- 1. REPORT NUMBE R (Assepsed t'y ODCJ U.S. NUCLE AR REGUL ATORY COMMIS$10N g,
NUREG-0664 BIBLIOGRAPHIC DATA SHEET Revision 1
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GiTLTANo SusisiLE (Add votame no.. ur worwenaan)
- 2. (Leave Diemkj
. \\g North Anna Power Station Unit 2 Technical Specifications a RECIPIENT'S ACCESS ON NO.
Appendix "A" to License No..NPF-7
- 7. AUTHOR (S)
- 5. DATE REPORT COMPLETE D
- l Y$ AR MONTw August 1980
- 9. PERFORMING ORGANIZATION NAME AND MAILING ADDRESS linclude lip Codel DATE REPORT ISSUED Division of Operating Reactors Mours lve4R
-Office of Nuclear Reactor Regulation August 1980 U. S. Nuclear Regulatory Commission
- s. n,,ve bene)
Washington, D. C. 20555
- 8. (Leave bimk)
- 12. SPONSORING ORGANIZATION NAME AND MAILING ADDRESS (/nclude Zip Code)
- 10. PROJECT / TASK / WORK UNIT NO (Same as 9.)
- 11. CONT T NO.
- 13. TYPE OF REPORT PE RIOD COVE RED //nclus ve defes)
Technical Report N/A
- 15. SlUPPLEMENTARY NOTES
- 14. (Leave birk)
- 4. A3STRACT (200 words orlessj
)
The North Anna Unit 2 Technical Specifications, which were prepared by the
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U. S. Nuclear Regulatory Commission, set forth the limits, operating conditions and other requirements applicable to nuclear reactor facility operation as set forth in 10 CFR 50.36 for the protection of the health and safety of the
- public, t
- 17. KEY WORDS AND DOCUMENT ANALYSIS 17a. DESCRIPTORS N/A N/A i
- ?b. 'OENTIFIE RS/OPEN-ENC 40 TERMS N/A
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- 18. AVAILABILITY STATEMENT -
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- 19. SE CURITY CLASS (Th4s report),
- 21. NO. OF PAGES h/A u;n ed
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20.S C RITY CLASS (Thes papel.
- 22. P RICE
- NRC FORM 335 (7 77)-
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