ML19309H417
| ML19309H417 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/11/1980 |
| From: | Virginia Power (Virginia Electric & Power Co) |
| To: | |
| Shared Package | |
| ML19309H415 | List: |
| References | |
| NUDOCS 8005130185 | |
| Download: ML19309H417 (60) | |
Text
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8005180 I
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APPENDIX B TO FACILITY OPERATING LICENSE NO. NPF-7 NORTH ANNA POWER STATION i
UNIT 2 i
i VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-339 1
i ENVIRONMENTAL TECHNICAL SPECIFICATIONS I
PART I - RADIOLOGICAL i
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TABLE OF CONTENTS pa.g,e 1.0 DEFINITIONS.................................................
1-1 2.0 LIMITING C0tDITIO.15 FOR 0PERATION...........................
2-1 2.1 Non-Radiological.......................................
27 2.2 Radioactive Effluents..................................
2-1 2.2.1 Specifications for Liquid Waste Effluents.......
T.- 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 Sampling 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...............................
3-1 3.1.2 B i o ti c Aq u a ti c.................................
3-1 3.1.3 Abi o ti c - Te r re s tri al..........................
3-1 3.1.4 Onsi te Meteorology Mani tori ng..................
3-1 3.2 Radiological Envi ronmental Moni tori ng..,..............
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4.0 SPECIAL SURVEILLANCE AND STUDY ACTIVITIES..................
4-1 r
t 5.0 ADMINISTRATIVE CONTR0LS.....................................
5-1 t
5.1 Responsibility.........................................
5-1 5.2 Organization...........................................
5-1 l
5.3 Review and Audit.......................................
5-1
- 5. 3.1 Station Nuclear Safety and Operating Committee (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.....................................
5-3 I1
o TABLE OF CONTENTS (Cont'dl Page 5.3.2 Supervisor, Quality Assurance, Operation and 5-4 Maintenance......................................
5-4 5.3.2.1 Function....................................
5-4 5.3.2.2 Audits......................................
5-4 5.3.2.3 Records.....................................
5.3.3 System Nuclear Safety and Operating Committee 5-4 (SyNS0C).......................................
5.3.3.1 Function..................................'..
5-4 5-4 5.3.3.2 Review......................................
5-5 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 Written Procedures..............................
5-5 5.5.2 Operating Procedures............................
5.5.3 Procedures for Environmental Surveillance -
5-6 Radiological..................................
g' 5.5.4 Procedures for Environmental Surveillance -
Nonradiological.................................
5-6 5.5.5 Quality Assurance of Program Resul ts..............
5-6 3.5.6 Changes in Procedures, Station Design or 5-6 0peration.......................................
5.5.7 Consistency with Initially Approved Programs......
5-7 5.6 Sta tion Reporting Requirements...........................
5-7 5-7 5.6.1 Routine Reports...................................
- 5. 6.1.1 Annual Environmental Operating Report.........
5-7 5.6.1.2 Radioactive Ef fluent Release Report...........
5-8 5.6.2 Nonroutine Reports................................
5-9 5.6.2.1 Nonroutine Non-Radiological Environmental
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Operating Report............................
5-9 5.6.2.2 Nonroutine Radiological Environmental 5-10 Operating Reports...........................
5.6.3 Changes in Environmental Technical Specifications.
5-11 5.6.4 Changes in Permits and Certifications.............
5-11 5.7 Records Retention........................................
5-11 I 11
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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 twelve 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 or the number of equal volume samples is proportional to the time period 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.
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Daily average concentration means the Daily Averaoe Concentration:
aritnmetic average of all daily determinations of concentration made Daily determinations of concentration using a during a calendar month.
composite 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 Cuncentration: Daily maximum concentration means the maximum concentration recorded for any calendar day.
Functional Check: A functional check shall be the qualitative assessment of channel 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 i
instrument channels measuring the same parameter.
A functional test shall be the injection of a simulated Functional Test _:
signal into the channel as close to the primary sensor as practicable to verify OPERABIt.ITY including alarm and/or trip functions.
i Grab Sample: A grab sample is an individual sample collected in less than fifteen minutes.
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Monthly: Monthly is once during every calendar month at intervals of 30 days plus or minus three days.
Operation of the station at greater than 5'; of rated Normal Operation:
tnermal power in other than a safety emergency situation.
Relates to the reproducibility of measurements within a set, Precision _:
that is, to the scatter or dispersion of a set about its central value.
l Quarterly is once during each successive three month period Quarterly:
j of the calendar year, counting from January 1, at intervals of 13 weeks plus or minus 9 days.
Semi-monthly is twice during each calendar month at Semi-Monthly:
intervals of 15 days plus or minus 2 days.
Soectral Band: A width, generally expressed in wavelenc.a or frequency A given sensor of a particular portion of the electromagnetic spectrum.
1 (e.g., radiometer detector or camera film) is designed to measure or be j
j sensitive to energy received from that part of the spectrum.
Station refers to North Anna Power Station, Units Station and Unit:Unit ~ refers only to Unit No.1 or Unit No. 2.
Nos. I and 2.
Weekly: Weekly is once during each calendar week at intervals of 7 days
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plus or minus 1 days.
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o 2.0 LIMITING CONDITIONS FOR OPERATION _ -
2.1 Non-Radiological - None 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 folloving 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 a.
an individual from liquid releases from all reactors at a site should not exceed 5 mrem in an unrestricted area.
The annual total quantity of radioactive materials in liquid b.
releases, excluding tritium and dissolved gases, discharged from each reac. tor should not exceed 5 C1.
The annual total quantity of noble ga'ses above background dis-c.
charged in gaseous effluents from the site should result in an air dose due to gamma 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 radioiodines and radioactive material in particulate forms with half-lives 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 e.
releases from each reactor at a site should not exceed 1 Ci.
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2.2.1 Soecifications for Liouid Waste Effluents The concentration of radioactive materials released in liquid waste a.
effluents to unrestricted areas from all reactors at the site shall not exceed the values specified in 10 CFR Part 20, Appendix B, Table 5
II, Column 2, for radionuclides other than noble gases and 4 x 10 uCi/mi for noble gases.
b.
The cumulative release of radioactive materials in 1; quid waste effluents, excluding tritium and dissolved gases, shall not exceed 10 Ci/ reactor / calendar quarter.
The cumulative release of radioactive materials in liquid waste c.
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 va.1ve (LW-ll5) prior to exceeding the limits speci fied in 2.2.l'.a above.
The operability of valve LW-il5 in the liquid radwaste discharge e.
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 quarter, excluding tritiura 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 w'th 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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Specifications for Liouid Waste Samolina and Monitoring 2.2.2 Station records shall be maintained of the radioactive concentra-a.
tion and volume before dilution of liquid waste intended for discharge and the average dilution flow and length of time over 4
which each discharge occurred. Sample analysis results and other reports shall be submitted as required by Section 5.6.1 of these Estimates of the sampling and analytical errors, Specifications.
as described in Regulatory Guide 1.21, associated with each reported value shall be included.
A continuous representative sample of all radioactive liquid b.
waste shall be taken at the liquid waste disposal-clarifier system release point and analyzed for the concentration of each significant gamma energy peak in accordance with Table 2.2-1 to demonstrate compliance with Specification 2.2.1 using the flow rate into which the waste is discharged during the pericd of If the continuous representative sample system is discharge.
inoperative, an alternate fixed flow sampler shall be provided to collect continuous samples in the continuous representive sample 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-il5 shall be closed.
Sampling and analysis of undfluted liquid radioactive waste shall c.
be performed in accordance with Table 2.2-1.
Prior to taking samples from a continuous representative sample collection tank, the tank shall be mixed for at least 10 minutes using the mixer 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 closed, 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 compliance with Specification 2.2.1.a.
If this monitor is inoperative for a 1
period exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, valve LW-il5 shall be closed and these releases terminated.
The flow rate of undiluted liquid radioactive waste shall be con-e.
tinuously measured and recorded during release. The total dilu-tion water flow will be calculated based on pump run times and known circulating water pump characteristics.
f.
The clarifier effluent radiation monitor shall be calibrated at All least quarterly by means of a known radioactive source.
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
traceable to the National Bureau of Standards. Each monitor shall also have a functional test at least monthly and an.instru-
{
ment check prior to making a release.
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- ABLE 2.2-1 i
RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS 4
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Liquid Release Sampling Analysis Type of Detection c
i Type Frequency Frequency Activity Analysis Capabilitjes
( Ci/al) b Principal Gamma
~7 d
Emitters 5 x 10 Plant Releases including Continuous Daily d
-6 Steam Generator BicwJown Composite Ba-la-140, I-131 10 Grab Sample Monthly Dissolved and Entrained Gases 10~5 d
4 1
Continuous Monthly H-3 10 d
Composite i
Gross a 10"7 d
-7 Continuous Quarterly P-32 5 x 10 Comoosite Sr-89, Sr-90 5 x 10-8 d
aThe nominal lower limit of detection is defined in HASL 300 (Rev. 8/74), pp. 0-08-01, 02, 03 at the 95% confidence level. The LLD levels are decay corrected to the end of the total sampling period. The LLD for radionuclides analyzed by gama spectrcmetry will vary according to the number of radionuclides enccuntered in effluent samples.
These LLD levels should be used as minimum criteria for objectives for instrumentation 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 j
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 those radionuclides which are rbutinely identified and measured.
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 cc,ncentrations of radioactive materials in liquid effluents, samples should be continuously collected in propor.
i tion to the rate of flow 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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o The manual valve on the 4-inch-diameter LW-221-152 line shall be g.
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 from 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 gamma emitters.
Bases The release of radioactive materials in liquid waste effluents to unrestricted areas shall not exceed the concentration Ifmits specified i
in 10 CFR Part 20 and should be as 1cw 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 permit 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 result in releases higher than the design objective levels but still within the concentration limits specified in 10 CFR ? art 20.
It is expected that by using this operational flexibility under unusual operating conditions, and exerting every effort G keep levels of radioactive material in liquid wastes as low as'is reasonably achievable, the annual release will not exceed a small fraction of the ccncentration limits specified in 10 CFR Part 20.
The design objectives have been developed based on operating experience, taking into account'a combination 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.
i 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 unrestricted 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 power under unusual operating conditions which may temporarily result in releases higher thn the levels nonnally achievable when the plant I-2-5 i
and the li:;uid 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.
i Consistent with the requirements of 10 CFR part 50, Appendix A, Design l
Criterion 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 maintain 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 50.34a. Normal use and maintenance of installed equipment in the liquid 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.
1 Specification 2.2.1.g 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-4 tions 2.2.1.b and 2.2.1.c, the. reporting requirements of 5pecification 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 i
report must be filed within 30 days following the calendar ouarter in which the release occurred as required by Specification 5.6.2 of these Technical Specifications.
l 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 4
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 radioactive liquid wastes released to the l
environment. Reports on the quantities of radioactive materials l
released in liquid waste effluents are furnished to the Comission i
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 Commission 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 monitored in Section 2.2.2 include all the monitored release points as provided for in Table 2.2-2.
2.2.3 Soecifications for Gaseous Saste Effluents The terms used in these Specifications are as follows:
Subscripts v, refers to vent reieases 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)
Q = the total noble gas release rate (Ci/sec)
T
=fQ sum of the individual noble gas radionuclides determined 9 to be present by isotopic analysis E = the average total body dose factor due to gama emission (rem /yr per C1/sec)
C = the average skin dose factor due to beta emissions (rem /yr per Ci/sec)
R = the average air dose factor due to beta emissions (rad /yr per Ci/sec)
T = the average air dose factor due to gama emissions (rad /yr per Ci/sec)
The values of E, C,'R and R are to be determined each time isotopic analysis is required as delineated in Specification 2.2.4.
Determine the following using the results of the noble gas radionuclide analysis:
E=(1/Q) OK T
ii C=(1/Q){0l T
ii R=(1/Q){0M T
ii T=(1/Q)j0N T
i9 where the values of X, L, M, N are provided in Table 2.2-3, and 9
are site dependent gaba $nd data dose factors.
Q = the measured release rate of the radionuclides and radicactive materials in particulate forms with half-lives greater than eight days (Ci/sec).
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f TABLE 2.2-2 f
NORTil ANNA P0hiR STATION LIQUID WASTE SYSTEM LOCATION OF PROCESS AND EFFLiiETINNlTORS ANil DEVICESXQiLRE,0,l(YECllNICAL,SPF_CIFICATIO,NS
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Continuous Monitoring Instrumentation Grab Release High Liquid Radiation Sample Point Level or Monitor Process System or Gross Auto Control Station Continuous Overflow Plant Release Point Gross Activity Radiation to Isolation Flow Rate Composite Alarm Instrument Activity Recorder Alarm Valve Indicator Sampler Ntsnber Component Cooling System X
X X
X CC-120 X
X Refueling Water Stg. Tanks X
X Baron Recovery Test Tanks X
X Y PG Water Storage Tanks m
X X
- f. LW Evaporator Test Tanks X
X Contaminated Drain Tanks X
X Low Level Waste Drain Tanks
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a Steam Generator Slowdown X
X X
X X
C Service Water Discharge X
X X
X X
SW-108 Turbine Building Floor b
X X
Drain Sumps Liquid Radwaste Ef fluent Line, LW-220 X
X X
X X
X X
LW-ill e
X-Required a-Six monitors: 5S-122, S5-123, S5-124, SS-222, 55-223. 55-224 b-Whenever the secondary coolant activity exceeds 10 pc/ML the sump pumps shall be placed in manual operation and 5
samples shall be taken and analyzed prior to release.
c-Determined by monitoring pump run times.
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TABLE 2.2-3
- GAPP.A AtiD BETA COSE FACTCRS FOR NORTH ANttA PC'/IR STATI0ft, UttIT tt05. 1 At:0 2 X/0 = 1.3 x 10-6 sec/m at 1370 meters title direction 3
Dose Factors for Vent K,
89y M
N ttoble Gas 9
jy jy Radionuclide Total Body Skin Beta Air Gar =a Air rem /yr rem /yr rad /yr rad /yr C1/see C1/sec Ci/sec Ci/sec Kr-83m 6.4E-05 0
0.38 0.0034 I
i, Kr-8Em 0.75 1.9 02.6 0.78 l
Kr-85 0.0091 1.8 2.6 0.0097 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-133m 0.21 1.3 1.9 0.28 Xe-133 0.24 0.40 1.4 0.30
,Xe-135m 0.87 0.93 0.97 0.93 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 k
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I-2-9 9
w m
w
a.
(1) The release rate limit of noble gases frcm the site shall be such that 2.0[Q I 31I Tv v and 0.33[Q IC + I'IW )31I Tv v y
The release rate limit of all radiciodine and radioactive (2) materials in particulate form with half-lives greater than eight days, released to the environs as part of the gaseous wastes from the site, shall be such that 5
4.1[10 g 3ij y
b.
(1) The average release rate of noble gases from the sita during any calendar quarter shall be such that 13[QTv v 13I and 6.3[Q W 31I Tv y (2) The average release rate of noble gases from the site during any 12 consecutive months shall be 25[Q W 31I Tv y and 13EQTv v 13I (3) The average release rate per site of all radioiodines and radioactive materials in particulate form with half-lives greater than eight days during ar.y calendar quarter shall be such that 5
13[4.1 x 10 g gij The _. rage release rate per site of all radiotodines and (4) rad'a :tive materials in partculate form with half-lives gre.ser than eight days during any period of 12 consecutive months shall be such that 5
25[4.1 x 10 q 3ij (5) The amount of iodine-131 released during any calendar quarter shall not exceed 2 C1/ reactor.
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(6) The amount of iodine-131 released during any period of 12 consecutive months shall not exceed 4 Ci/rcactor, Should any of the conditions of 2.2.3.c(1), (2) or (3) listed c.
below exist, the liceosee 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 3
50[QTv v "I or 25[QTvv]'I (2)
If the average release rate per site of all radionuclides 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 ),)
y (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 ar.d 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 notific.ation shall be in accordance with Specifica-l tion 5.6.2.2.c(3).
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TABLE 2.2-4 f40RTH ANNA POWER STATION CASEOUS WASTE SYSTEM LOCATION OF PROCESS Ah0TFTTliENT~NONTTOR$7 tat'iAMntx3 uus;TRITBY7CitNICAL SPECIFICATIONS Release Point Continuous Monitoring Instrumentation Continuous Radiatinn Monitor Smapler Grab Plant Proc;ss Stream or Release Point Particulate Activity Radiation Auto Control to Oow Rate Sample Instrumentation Noble Gas Recorder Alans isolation Valve Indicator i
Particulate Station Activity I
Process Vent
- X X
X X
X
,X X
X rM-10l. Particu-late g
GW-102. Gaseous b
d I
Ventilation Vent A X
X X
X X
I X
VG-103. Particu-late g
VG-104. Gaseous d
I
- Ve tilation Vent B X
X
- X I
X X
X VG-112. Particu-C late VG-113,. Gaseous NL N lle'ctor Containment (During Purging)
A I
X X
HMS-159. 259 Particulate RMS-If D. 260 Gaseous Condenser Air Ejector X
X X
X X
sy-1?l. 221 Gross Activity Stian Generator Blowdown
. Tank Condenser Vent X'
X - Required a - Exhausts waste gas decay tank and waste evaporator condenser b - Exhausts Ausiliary Building Central and General Areas. Hot Laboratnry.
c - Exhausts Safeguards Areas. Decon Bldg.,Soltdtf tcation Bldg.,Peactor Containment and Fuel 01d.
9 d - Flow element and recnrder and integrator provided.
e - Radiolodine and Particulate samules shall be continuously collects 93 and analyzed daily whenever the secondary ruolarit activity exceeds 10~ oc/ mil.
f - These instruments are cowion to both Unit tios. I and 2.
9 O
Scecifications for Gaseous Waste Samolinc and Monitorinc 2.2.4 Station records shall be maintained and reports of the sampling and analyses results shall be submitted in accordance with a.
Estimates of the sampling Section 5.6 of these Specifications.
and analytical error, as described in Regulatory Guide 1.21 (Rev.
1), associated with each reported value should be included.
Gaseous releases to the environment, except from the turbin.e b.
building ventilation exhaust and as noted in Specification 2.2.4.c, shall be continuously monitored for gross radioactivity )
and the flow continuously measured (see footnote d in Table 2.2-4 Whenever these monitors are inoperable, grab and recorded.
samples shall be taken and analyzed daily for gross radioactivity.
If these monitors are inoperable for more than seven days, these releases shall ba terminated.
During the release of gaseous wastes from the primary system waste gas decay tank, the process vent monitor shall be operating.
c.
All
..te gas decay tank effluent monitors shall be calibrated at d.
All least quarterly by means of a known radioactive source.
laboratory analyses and other waste gas effluent monitors shall be calibrated at least every 18 months by means of a known The source used to calibrate the known radioactive source.
source shall
.e calibrated by a measurement system which is traceable to the National Bureau of Standards. Each monitor shall have a functional test at least monthly and instrument check at least daily.
Sampling and analysis of radioactive material in gaseous waste, e.
including particulate forms and radioiodines shall be performed, at least as frequently as required by Table 2.2-5.
During the release of gaseous wastes from the primary system f.
waste gas decay tank, the iodine collection device and particulate collection device shall be operating.
Bases The release of radioactive materials in gaseous waste effluents to unrestricted areas shall not exceed the concentration limits specified in 10 CFR Part 20 and should be as low as is reasonably achievable in These specifica-accordance with the requirements of 10 CFR Fart 50.34a.
tions provide reasonable assurance that the resulting annual air dose from the site due to gamma radiation will not exceed 10 mrad, and an annual air dose from the site due to beta radiation will not exceed 20 mrad from noble gases, that no individual in an unrestricted area will receive an annual dose to the total body greater than 5 mrem or an 7
I-2-13 i
4 TABLE 2.2-5 RADICACTIVE GASECUS WASTE SAMPLING AND ANALYSIS Gaseous Release Sampling Analysis Type of Detection Type Frequency Frequency Activity Analysis capabilities
(:Ci/ml)*
ncipal Gama 10~
ac.4 Tank Each Tank A.
Waste Gas Decay Grab Emitters 10-6 Tank Sample H-3 h,h. fr 10 c
B.
Containment Purge a
Eacn Purge 10-6 H-3 D
C.
Process Vent Monthly Principal Gam.a 10 C
c Grab Monthly Emitters Sample H-3 10 D
0.
Ventilation Monthly Principal Gama 10 C
c Vents A and B Grab Monthly Emitters 10~0 Sampl e H-3 E.
Process Vent and eekly
~12 d
Ventilation Vents Continuous Charcoal I-131 10 A and B Sample 1-133 10~
Weekly Continuous Particulate Principal Gama 10~))
d Samole Emitters, Gross 2 d
Continuous Quarterly
~3)
Particulate Sr-89, Sr-90 10 ihe nominal lower limit of detection is defined in HASL 300 (Rev. 8/74), pp. 0-C8-01, a
02, 03 at the 95" confidence level. The LLD levels are decay corrected to the end of the total sampling period. The LLD for radionuclides analyzed by gamma spectrcmetry will vary according to the number of radionuclides encountered in effluent samples.
These LLC levels should be used as minimum criteria for objectives for instrumentation and analytical procedure selection.
bFor certain mixtures qf gama emitters, it may not be possible to measure radienuclides at levels near their sensitivity limits when other nuclides are present in the sample at much higher levels. Under these circumstances, it will be more appropriate to cal-culate the levels of such radionuclides using obser.ed ratios with those radionuclides which are measurable.
Analyses shall also be performed weekly, for two weeks, for principal gama emitters, c
following each shutdcwn, startup, or similar operational occurrence which could alter the mixture of radionuclides.
d the sample volume to the sampled stream volume shall be known for The ratio of the sampling time period consistent with the analyses frequency.
' Prior to release.
I-2-14
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arnual skin dose greater than 15 mrem from fission product noble gases, and that the annual dose to any organ of an individual frcm radionuclides and radioactive material in particulate form with half-lives greater than eight days will not exceed 15 mrem per site.
At the same time these specifications permit the flexibility of cpera-tion, compatible with considerations of health and safety, to assure that the public is provided with a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels but still within the concentra-tion limits specified in 10 CFR Part 20.
Even with this operational flexibility under unusual operating condi-tions. if the licensee exerts every effort to keep levels of radio-active material in gaseous waste effluents as low as is reasonably achievable, the annual releases will not exceed a small fraction of the concentration limits specified in 10 CFR Part 20.
The design objectives have been developed based on operating experience taking into acccunt a combination of system variables including defec.
l tive fuel, primary system leakage, primary to secondary system leakage, steam generator blowdown and the performance of the various waste treatment systems.
Specification 2.2.3.a(1) limits the release rate of r. 51e gases from the site so that the corresponding annual gamma and br.4 dose rate above background to an individual in an unrestricted area will not exceed 500 mrem to the total body or 2000 mrem to the skin in co. pli-ance with the limits of 10 CFR Part 20.
For specification 2.2.3.a(1), gamma and beta dose factors for the individual noble gas radionuclides have been calculated for the plant gaseous release points and are provided in Table 2.2-3.
The expres-sions used to calculate these dose factors are based on dose ecdels derived in Section 7 of Meteorology and Atomic Energy-1968 and model techniques provided in Regulatory Guide 1.109.
00se calculations have been made to determine the site boundary location with the highest anticipated dose rate from noble gases using onsite meteorological d.ta and the dose expressions provided in Regulatory
)
4 Guide 1.109. The dose expression considers the release point location, building wake effects, and the physical characteristics of the radionuclides.
The offsite location with the highest anticipated annual dose from released noble gases is 1370 meters in the NNE direction.
I-2-15 l
.__o_
The release rate Specifications for a radioicdir.e and radioactive material in particulate form with half-lives greater than eight days are cependent on existing radionuclide pathways to man. The pathways
~
wnich were examined for these Specifications are:
- 1) individual inhalation of airborne radienuclides, 2) depcsition of radionuclides onto green leafy vegetation with subsequent c:nsumption by man, and 3) depositico onto grassy areas where milch ani. als graze with consump-tior, of the milk by man. Methods for estimating doses to the thyroid via these pathways are described in Regulatory Guide 1.109. The offsite location with the highest anticipated thyroid dose rate from radiciodines and radioactive material in particulate form with half-li"es greater than eight days was determined using onsite meteorologi-cal data and the expressions described in Regulatory Guide 1.109.
Specification 2.2.3.a(2) limits the release rate of radiciodines and radioactive material in particulate form with half-lives greater than eight days so that the corresponding annual thyroid dose via the most restrictive pathway is less than 1500 mrem.
For radioiodines and radioactive material in particulate form with half-lives greater than eight days, the most restrictive location is a dairy farm located 2990 meters in the east direction (vent X/Q - 3.19 3
x 10 7 sec/m ).
Specification 2.2.3.b establishes upper offsite levels for the releases of noble gases and radiciodines and radioactive material in particulate form with half-lives greater than eight days at twice the design object ve annual quantity during any calendar quarter, or four times i
the design objective annual quantity during any period of 12 consecu-tive months.
In addition to the limiting conditions fcr operation of Specifications 2.2.3.a and 2.2.3.b, the reporting recuirements of
~2.2.3.c provide that the cause shall be identified whenever the release of gaseous effluents exceeds one-half the design objective annual quantity during any calendar quarter and that the proposed program of action to reduce such release rates to the design objectives shall be described.
Specification 2.2.3.d requires that suitable equipment to monitor and control the radioactive gaseous releases are operating during any period these releases are taking place.
Specification 2.2.3.e limits the maximum quantity of radioactive gas that can be contained in a waste gas storage tank. The calculation of this quantity should assume instantaneous ground release, a X/Q based on 5 percent meteorology, the average gross energy is 0.19 Mev per disintegration (considering Xe-133 to be the principal emitter) and exposure occurring at the minimum site boundary radius using a semi-infinite cloud model. The calculated quantity will limit the offsite dose above background to 0.5 rem or less, censistent with Commission guidelines.
I-2-16 c
Specification 2.2.3.f provides for reporting 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 2.2.4 provide assurance that radioactive mat 1 rials released in gasecus waste effluents are prcperly controlled and monitcred in conformance with the requirements of Design Criteria 60 and 64. T.hese recuirerer,ts provide the data for the licensee and the Comiissicn to evaluate the plant's performance relative to radioactive waste effluents released to the environment. Reports on the quantities of radioactive materials released in gaseous effluents are furnished to the Commission on the basis of -Section 5.6.1 of these Technical Specifications. On the basis of such reports and any additional information the Commission
'may obtain from the licensee or others, the Commission may from time to time require the licensee to take such action as the Commission deems apppropriate.
Tne points of release.to the environment to be monitored in Section 2.2.4 include all the monitored release points as provided for in Table 2.2-4.
Specification 2.2.4.b excludes monitoring the turbine building ventila-tion exhaust since this release is expected to be a negligible release point. Many PWR reactors do not have turbine building enclosures. To be consistent in this requirement for all PWR reactors, the monitoring of ga eous releases from turbine buildings is not required.
2.2.5 Specifications for Solid Waste Handling and Dispcsal a.
Measurements shall be made to determine or estimate the total curie quantity of all radioactive solid waste shipped offsite.
b.
Estimates shall be made of the principal radionuclide composition of all radioactive solid waste shipped offsite.
c.
Reports of the radioactive solid waste shipments, volumes, principal radionuclides, and total curie quantity, shall be submitted in accordance with Section 5.6.1.
Bases The requiremente of solid radioactive waste handling and disposal given under' Specification 2.2.5 provide assurance that solid radio-active materials stored at the plant and shipped offsite are packaged in conformance with 10 CFR Part 20 and 10 CFR Part 71.
I-2-17
3.0 ENVIRONMENTAL SURVEILLANCE _
3.1 Nonradiological Surveillance 3.1.1 Abiotic - Aquatic None 3.1.2 Biotic Aquatic None 3.1. 3 Abiotic - Terrestrial Addressed in Part II, Section 4.2.
3.1.4 Onsite Meteorology Monitoring Objective The objective of onsite meteorological monitoring is to adequately measure and document meteorological conditions at the site, speci-fically at heights above ground that are representative of atmospheric conditions that exist at all effluent release points.
Specifications The onsite meteorological monitoring program, at the location (s) identified in the Environmental Report, shall conform to the recom-mendations and intent of Regulatory Guide 1.23, Onsite Meteorological Programs (February 1972), and include instruments to sense wind speed and direction at 10 meters and 49 meters, vertical temperature gradient between 10 meters and 49 meters, ambient temperature at 10 meters, and precipitation near the ground. Observations of cooling system impact on local meteorology (e.g., fogging, icing, precipitation, etc.) shall be made at appropriate locations, as identified in the Environmental Report, where this impact is attributable to plant operation.
Reporting Requirements Meteorological data shall be summarized and reported consistent with i
the recommendations of Regulatory Guide 1.21, Section C.1 (June 1974) and Regulatory Guide 1.23, February 17, 1972, and meteorological l
I-3-1 i
observations in a form consistent with National Weather Service proce-dures. Summaries of all data and observations shall be available to the NRC upon request.
If the outage of any meteorological instrument (s) r exceeds seven consecutive days, the total outage time, the dates of outage, the cause of the outage, and instrument (s) involved shall be reported within 30 days in accordance with Section 5.6.2.2.
Any modification to the onsite meteorological monitoring program as I
described above, or planned alterations of the area in the vicinity of the meteorological tower (s) that would interfere with the measurement of meteorological conditions representative of the site, will require sn itten approval in accordance with Section 5.6.3.
Bases The collection of meteorological data at the plant site will provide information which will be used to develop atmospheric diffusion para-meters to estimate potential radiation doses to the public resulting from actual routine or abnormal releases of radioactive materials to the atmosphere, and to assess the actual impact of the plant cooling A meteoro-system on the atmospheric environment of the site area.
logical data collection program as described above is necessary to meet the requirements of subparagraph 50.36(a)(2) of 10 CFR Part 50, Appendix E to 10 CFR Part 50, and 10 CFR Part 51.
3.2 Radiological Environmental Monitoring Objectives The overall objectives of the radiological environmental monitoring survey program are to identify changes in radioactivity in the vicinity of the station, and to provide information on the type and quantity of radiation in certain indicator organisms or critical pathways which can 1
be used as a basis for evaluating radiation exposures resulting from i
)
station operation.
Specifications Radiological environmental monitoring shall be performed according to Table 3.2-1.
The location of monitoring stations is presented in Fig. 3.2-1 and l
3.2-2.
i The sensitivities (L.L.D.) of the analyses of environmental samples are presented 'n Tables 3.2-2 and 3.2-3.
Deviations are permitted from the required sampling schedule if speci-mens are unobtainable due to hazardous conditions, seasonal unavaila-bility or malfunction of inplace equipment.
Deviations are permitted 1
I-3-2
~
TABLE 3.2-1 NORTil ANNA POWER STATION OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY SAMPLE LOCATION AND/OR SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE MAP NUMBER DESIGNATION COLLECTION FREQUENCY OF ANALYSIS AIRBORN$
Particulates Site or site boundary:
1,21, Continuous sampler Weekly gross beta on 22, 23 (2/3 running time each filter, q>arterly Communities:
3,5,7 cycle), changes gamma isotopic on each Control: 24 weekly location composite, Sr-89-90 on second 7*
oa Radioiodine 3.21,23,24 quarter composite, I-131 on radioiodine oa weekly.
Soil 1,3,4,5,6,7,21,22,23,24 Once per 3 years Gamma isotopic on each, Sr 89-90 on 1,21.22, 23, 24 (on collection)
DIRECT 1,3,4,5,6,7,21,22.23,24 Quarterly Gamma dose quarterly WATERBORNE Reservoir: 9 Monthly Gammajsotopicradio-Discharge: 8 iodine 11-3 quarterly composite. Sr 89-90 second quarter composi te North Anna River: ll Quarterly Ganna isotopic,11-3 on d
Ground (well): lA collection, Sr 89-90 second quarter sample l
TABLE 3.2-1 (Continued)
NORTil ANNA PDWER STATION OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY SAMPLE LOCATION AND/0R SAMPLING AND TYPE AND FREQUENCY AND/0R SAMPLE MAP NUMBER DESIGNATION COLLECTION FREQUENCY OF ANALYSIS AQUATIC,
Reservoir: 9 Semiannually Gamma isotopic on collection, Sr 89-90 Sedimend-Discharge: 8 North Anna River: 11 annually Shoreline Vicinity of: 9 INGESTION i*
milk Nearest Dairies: 12, 13, 14 Monthly
- Radiciodine#, Ganna isotopic monthly, Sr V8 89-90 quarterly Non-dairy activity Calculated dose Radiciodine"**, Gamma b
b h
b dependent i otopic Sr 89-90 Fish Reservoir: 9 Annually, near Gamma isotopic (Bass, or sunfish Discharge: 8 beginning of season or crappie and catfish)
Green Leafy 21, 23 Annually during Ganna isotopic on c
collection vegetation, harvest cultivated or weeds. Naturally occurring 4
TABLE 3.2-1 (Continued)
NORTH ANNA POWER STATION OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY SAMPLE LOCATION AND/0R SAMPLING AND TYPE AND FREQUENCY AN0/0R SAMPLE MAP NUMBER DESIGNATION COLLECTION FREQUENCY OF ANALYSIS 6,
a.
Once each month 1 and 2 mrem thyroid isodose lines will be calculated using the previous month's release data based on the cow-milk-child pathway. "hould a dairy be located within the 1 mrem isoduse line the sampling and analysis frequency for radio':2.ne will be modified to semimonthly for the month following the month.for which the calculation was made. A similar sampling program will be for the 2 mrem isodose line except on a weekly frequency.
ja 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. Shou!d the isodose line extend beyond the site La 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 from the owners of the animals will be put forth, if samples are obtainable, a sampling program similar to "a" above will be initiated. If samples are unobtainable, 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 maximum organ dose 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.
d.
Samples will be taken from the Environmental Laboratory well.
[
e.
Radioiodine analyses will be done by chemical separation.
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l TABLE 3.2-2 LOVER LIMITS OF DETECTION BY HIGH RESOLL' TION Ca(L1) GA>0dA SPECTROSCOPY ENVIRONMENTAL SA'.9LES Water (1 liter)
Soil & Vegetation Filters Nuclide pC1/1 (400 em) oC1/em pCi/ total filter Se 8EMI 2E-01 2E+01 K
2E+02 SE-01 SE+01 0
Cr$1 8EMI 2E-01 SE+01 8
2E-02 2
E Co 8
2E-02 2
8 Fe '
lE+01 4E-02 3
Co 8
2E-02 2
60 Zr 1E+01 4E-02 4
95 Ru 8
2E-02 2
Ru 8E+01 2E-01 8EMI I
10 3E-02 2
Cs 9
2E-02 2
134 Cs 9
2E-02 2
I3 Ba 3E+01 8E-02 6
l La 2E+01 4E-02 2EMI Ce '
2E+01 4E-02 3
Ce 8E+01 2E-01 2E+01 144 Ra 6E+01 1E-01 1E+01 Th 1E+01 2E-02 lE+01 I-3-8 e
a
o TABLE 3.2-3 LOWER LIMITS OF DETECTION L.L.D. &
Sampled Volume Samole Analysis Reporting Units Recuired 125 m3 1.
Airborne Particulate 3 ci/m3 Gross Alpha 2.5 x 10 p
Gross Beta 7.6 x 10 3 Ci/m3 p
Ge(L1) y-isotopic See Table 3.2-2 125 m3 2.
Airborne Iodine 3
Charcoal Cartridge I-131 2.4 x 10 2pC1/m 3.
Direct Radiation TLD Environmental Badge 2mR + 2mR 4 liter's 4.
Milk Sr-90 0.8 pCi/t 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 2 liters 5.
Well Water Gross Alpha
.5 pCi/t Gross Beta 0.5 pCi/t Tritium (gas count) 100 pCi/t Ge(Li) y-isotopic See Table 3.2-2 2 liters 6.
Surface Water Gross Beta 0.5 pCi/t Tritium (gas count) 100 pCi/t Ge(Li) y-isotopic See Table 3.2-2 7.
Fish: Flesh (2) 1 Kg 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*
Sr-90 0.5 pCi/gm*
I I-3-9
?
e 8
TABLE 3.2-3 (Continued)
LOWER LIMITS OF DETECTION L.L.0.
Saccisd 7 cit e Re ;irea Sa ole Analysis Recortina Units (2) 1 Kg 8.
Vegetation Samples A.
Corn See Table 3.2-2 l
Ge(Li),-isotopic 0.5 pCi/gm*
Sr-90 (2) 1 Kg B.
Leaf Vecetaticn Ge(L1) ~
See Table 3.2-2 Sr-39 0.8 pCi/sm*
Sr-90 0.5 pCi/gm a (2) 1 Kg C.
Food / Garden Crops (e.g. Lettuce)
Ge(li)
See Table 3.2-2 Sr-89 0.8 pCi/gm*
Sr-90 0.5 pCi/gm*
O.
Terrestrial Vegetation i Kg Ge(Li)
See Table 3.2-2 E.
Aquatic Vegetation Ge(Li) y-isotopic See Table 3.2-2 Sr-89 0.8 pct /gm*
e Sr-90 0.5 pCi/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 j
Sr-89 0.8 pCi/gm Sr-90 0.5 pCi/gm i
- 0etection in limits as stated are per gram of ashed material. The actual detection limits in pCi/gm (wet) will vary by a factor of 10-100, depending on the wet versus ash weight factor.
I 3-10 n -
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.O
on stated sensitivities and sample size up to a 25P. deviation.
All deviations from the sampling schedule shall be described in the annual report.
1 Reportino Reoufrement 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 environment 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.
i l
I-3-11 e
a
O 4.0 SPECIAL SURVEILLANCE AN6 STUDY ACTIVITIES None.
l l
l I-4-1
5.0 A_DMINISTRATIVE_ 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 requirements.
5.2 Organization The relationship between the Nuclear Operations Depqrtment and the Environmental Services Department is shown in Figure 5.2-1.
5.3 Review and Audit _
5.3.1 ptation Nuclear Safety and 0:erating Committee (SNSOC) 5.3.1.1 Function The SNSOC, as described in Section 6.5.1 of Appendix A cf this license, shall function to advise the Station Manager on natters related to the envircr.cental impact of the station.
'n' hen the SNSOC is exercising its responsibility for non-radiological aspects of the ETS, the Station Biologist or his alternate shall be consulted.
5$3.1.2 Responsibility.
The SNSOC shall be responsible for:
Coordination of the Envirencental Technical Specifications with a.
the Safety Technical Specifications (Appendix A) to avoid con-flicts and maintain consistency.
b.
Revicw of changes to the Environmental Tecnnical Specifications and the evaluation of the envirccmental i. pact of the chance.
e I-5-1
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Review of proposed written procedures r-e fred by Sections 5.5.2 and 5.5.3 below and changes thereto, whLn affect the environmental impact of the station.
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 formulation of recommendations 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 than that evaluated by the Commission.
5.3.1.3 Authority The SNSOC shall:
a.
Review the environmental evaluation of all changes described in Section 5.3.1.2 a, b and c, above. When the evaluation indicates that such activity may result in a significant adverse environ-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.
b.
If the SNSOC determines that unexpected harmful 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 problem and a plan of action to eliminate or significantly reduce the harmful effects or damage is submitted to the Commission 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 Chairmen of the System Nuclear Safety and OperatingCommittee(SyNSOC).
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l 5.3.2 Suoervisor, Quality Assurance, Ooerations and Maintenance 5.3.2.1 Function i
j The Supervisor, Quality Assurance, Operations and Maintenance shall perform independent audits of the implementa-icn of the Environmen al
[
Technical Specifications.
5.3.2.2 Audits The following audits shall be completed:
a.
The conformance 'of facility operation to provisions contained i'
within these Environmental Technical Specifications and applica-ble 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 these 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, i
5.3.2.3 Records Provide a written report of the results of the audits required by 5.3.2.2 above to the SNSOC, the SyNSCC and the Station Manager.
5.3.3 System Nuc' ear Safety and Operatina Committee (SyNSOC) 5.3.3.1 Function The SyNSOC as described in Section 6.5.2 of Appendix A of this license, shall function to provide independent review of designated activities a
related to the environmental impact of the station.
5.3.3.2 Review The SyNSOC shall review and, where necessary, comment on the results of the reviews conducted by the SNSOC and the independent audits conducted by the Supervisor, Quality. Assurance, Operations and Maintenance.
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5.3.3.3 Fes:cnsibility The SyNSCC has the responsibility for ensuring that the sta 'on is ocerated in accordance with the recuirements of this licarss and applicable NRC regulations.
5.3.3.4 Authori ty The SyNS0C shall report to and advise the Executive Manager-Licensing and Quality Assurance, who shall advise the Executive Vice President-Power on those areas relating to the environmental impact of the station.
5.3.3.5 Records 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 Permits and Certificat_es None 5.5 Procedures 5.5.1 Written Procedures Detailed written procedures, including applicable checklists and instructions, shall be prepared and folicwed for all accivities invcived in carrying out the Environmental Technical Specifications as defined in Sections 5.5.2, 5.5.3, and 5.5.4, belcw. Frocedures shall include sampling, data recording and storage, instrument calibration, measure-ments and analyses, and actions to be taken when limits are approached or exceeded. Testirg frequency of any alarm shall be included.
These frequencies shall be determined from experience with similar instru-ments in similar environments and from nanufacturer's technical renuals.
5.5.2 Doeratino Procedures Plant standard operating procedures shall include provisions, in addition'to the procedures specified in Section 5.5.1, to ensure that all p'. ant systems and components are operated in compliance with the Limiting Conditions of Operations established as part of the Environ-mental Technical Specifications.
W I-5-5 O
5.5.3 Procedures for Environmental Surveillance - Radiolooical Procedures to inplement the radiological environmental monitoring crogram shall be prepared and maintained in a manual for that purpose.
Securing samples, scheduling, transporting of samples, required anal-ysis and reporting will be included.
5.5.4 Procedures for Environmental Surveilla'ce - Nonradiological n
Not appitcable.
5.5.5 Ouality Assurance of Program 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 Changes in Frocedures, Statior Design or Ooeration Changes in procedures, station design or operation may be made subject to conditic.ns described below, provided such changes are approved tf the SNSOC (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-mental 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-l sion approval, unless the proposed change, test or experiment l
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; or (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.
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The licensee shall maintain records of chances in procedures and 4
c.
j in facility design or operation made pursuant to this Subsection, to the extent that such changes constitute changes in procedures as described in the document developed in accordance with Section 4
5.5 or in the FES, FES Addendua and ER.
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 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, or affect the requirements of Section 5.5.7 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 containina descriptions, analyses, interpretations, and evaluations of such changes, tests and experiments.
Changes in the procedures developed in accordance with Subsection 5.5 d.
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 impact of these changes, and the statement required under the t
provisions of Subsection 5.5.7.
5.5.7 Consistency with Initially Approved Programs Any modifications or changes of the procedures developed in accordance with Subsection 5.5 must be governed by the need to maintain consistency with previously used procedures so that 1
direct comparisons of data are technically valid.
Such modifications or changes must be justified and supported by adequate comparative sampling programs or studies demonstratino the comparability of results Or which provide a basis for making adjustments that would permit o!ract conparisons.
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 5.6.1 Routine Reports 5.6.1.1 Annual Environmental Operating Repor_t_
A report on the radiological environmental surveillance 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 The Reactor Regulation) as a separate document by April 1 of each year.
period of the first report shall begin with.the date of initial criti-cality of Unit No. 1.
The reports shall include summaries, interpre-
_ tations, and statistical evaluation of the results of the radiological I-5-7
environmental surveillance activities for the re; ort period, including a cccparison with preoperational studies, operational controis (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the alant opsettien on the environ 5ent. The reports shall also include the results of any land
(
use censuses required by Section 5.5.1.2.
If harmful ef fects or evidence of irreversible damage are detected by the monitoring, the licensee shall prov.ide an analysis of the problem and a proposed course of action to alleviate the problem.
Results of all radiological environmental sanples taken shall be summarized and tabulated on an annual basis.
In the event that some results are not available within the 90-day period, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supple-l mentary report.
5.6.1.2 Dadioactive Ef fluent Release Report A report on the radioactive discharges released frcm the site for _the previous semi-annual period (January-June and July-Cecember) sha.ll be submitted to the Director of the NRC Region II Office (with a copy to the Director, Office of Nuclear Reactor Regulation) by March 1 and September 1.of each year. The period of the first rc;crt shall begin with the date of the initial criticality of Unit 1.
The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the station as cutlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radio-activity in Solid Wastes and Releases of Radioactive "ateriais in 4
Liquid Gaseous Ef fluents from Light-Water-Cooled ;uclear Pa;er Fiants,"
with data sucmarized on a quarterly basis.
The necessary data and format are listed in Appendix B, Tables l A, IC, 2A, 23, and 3 of Regulatory Guide 1.21.
Table 4A shculd be duplicated for can:inuous and intermittant releases, so that the apcropriate ccrrelatian of effluents with metecrological data can be rade in the calculation of of fsite doses.
i 1
The report shall include a summary of the netese;;;;ical conditions concurrent wita the release of gaseous effluen?.: durin each quarter as outlined in Regulatory Guide *.21, with data sur.ari:e3 on a quarterly basis following the format of Appendix 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 period) to calculate and report the exposures to individuals and populations from t: e effluents.
In connection with this, the locations of the followin: critical receptors should be redetermined at the beginning of the gr:winc/ grazing season
_ in each sector (out to.five miles from Unit 1), tne nearest housino i
unit (including trailers and suncer-homes), gardsn, cow, and meatn animal (including chickens where they are used extensively for food).
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5.6.2 fionroutine Reports 5.6.2.1 fionroutine ffon-Radiological Environment _al Operating Report f(one.
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5.6.2.2 Nonroutine Radiological Environmental Operating Reports Anomalous Measurement Report.
If a confirmed measured level of a.
radioactivity 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.
Pathway Measurenent Recort.
If pathway samples collected over a b.
calendar quarter sr.ow average levels of radioactivity greater than j
10 times the. rend established by previcus monitoring, a written 5.6.1.2.
report shall be included ir. the report required by Section c.
Nonroutine Radioactive Effluent Reacets (1) PWR Liquid Radioactive Wastes Report.
If the cumulative releases of radioactive materials in liquid effluents, excluding tritium and dissolved gases, should exceed one-half the design objective annual quantity during any calendar quarter, the licensee shall make an investigation to identify the causes of 4
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 NRC within 30 days from the end of the quarter during which the release occurred.
(2) PNR Gaseous Radicactive Wastes Report.
See Section 2.2.3c.
A 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 if the earliest time consistent with the analysis, but in any case within 30 days, anomalous value is. confirmed, the report to the NRC shall be subt.itted.
I 5-10
1 (3)
PWR Unplanned cr Uncontrolled Release Rer;r.
Any und ; ned or uncontrolled offsite release of radicactive materials in excess of 0.5 Curie in liquid or in e cess of 150 Curies of noble gases or 0.05 Curie of radiciodices in gas =aus i: r.
requires notification.
This notification must be made by a written report within 30 days to tha NRC.
The report saall describe the event, identify the caures of the uno'cnted or uncontrolled release and repor,t actions taken to pre.'ect recurrence.
d.
Written 30-day reports will be submitted to the following Sddresses:
(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)
(4)
Director, Office of Nuclear Reactor Regulation, USNRC, Washington, D. C. (1 copy) 5.6.3 Changes in Environmental Technical Soecifications.
A report shall be nade to the NRC prior to implementation of a change in plant de ign, in plant operation, or in procedares described in Section 5.5 if the change would have a significant effect on the environment or involves an environmental matter or question not i
previously reviewed and evaluated 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 be submitted to the Director, Office of Nuclear Reactor Regulation, for review and authorization.
The request shall include an evaluation of the environmental impact of thc proposed changes and a supporting benefit-cost analysis.
5.6.4 Channes in Permits and Certifications None.
5.7 Records Retention Records and logs relative to the following areas shall be made and retained for the life of the station:
Records and drawings detailing plant design :hanges and modifica-a.
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 Environnental Technical Specifications.
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APPENDIX B TO FACILITY OPERATING LICENSE NO. NPF-7 NORTH ANNA POWER STATION i
UNIT 2 i
l' i
1 VIRGINIA ELECTRIC AND POWER COMPANY l
DOCKET NO. 50-339 i
A I
f-ENVIRONMENTAL' TECHNICAL SPECIFICATIONS i
PART II -~NON-RADIOLOGICAL i
i i
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NORTH ANNA POWER STATION UNIT 2 ENVIRONMENTAL TECHNICAL SPECIFICATIONS (NON-RADIOLOGICAL)
TABLE OF CONTENTS Section Page 1-1 1.
Definitions................................................
2.
Limiting Conditions for Operation..........................
2-1 3.
Environmental Monitoring...................................
3-1 4-1 4.
Special Studies and Requirements...........................
4-1 4.1 Exceptional Occurrences............................... 1 4.2 Special Studies.......................................
5.
Admi ni s tra ti ve Control s....................................
5-l' 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 i
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1.
DEFINITIONS 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 2 of the North Anna Power Station, as defined by its usage.
k 1
11-1-1
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2.
LIMITING CONDITIONS FOR OPERATION None required."
- In consideration of the provisions of the Clean Water Act (33 USC S 1251, 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 i
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.
The Nuclear Regulatory Commission will be relying on the NPDES permit limita-tions for protection of the aquatic environment from non-radiological effluents.
11-2-1
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3.
ENVIRONMENTAL MONITORING None required.*
1 l
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- ln consideration of the provisions of the Clean Water Act (33 USC S 1251, 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 No. VA0052451 issued by the' Commonwealth of Virginia to the Virginia Electric and Power Company (VEPCO).
This permit authorizes VEPC0 to discharge controlled 4
waste water from the North Anna Power Station into waters of Virginia.
The Nuclear Regulatory Commission will be relying on the NPDES permit limita-tions for protection of the aquatic environment from non-radiological. effluents.
1 11-3-1 E
i 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 mortality of any species protected by the Endangered Species Act of 1973; fish kills near the plant site; unanticipated or emergency dischargc.s 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 i
The licensee shall notify the NRC of occurrences in which the limits specified 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 of Subsections 5.4.2.b and 5.4.2.c or Subsection 5.4.2.d in the event that a limit specified 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 Ob_jective 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 Protection Agency and the Virginia Department of Agriculture.
The rates of II-4-l'
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), manner, and frequency of applica-tion will be included.
Field logs summarizing weather conditions, location of applications, and rates of application should 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 he'bicides will conform to various local and Federal regulations.
r This informtion will provide surveillance information to the staff to ensure that herbicide applications conform to current regulations and thereby minimize environmental impact due to right-of-way maintenance procedures.
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 daring 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 i
The Annual Environmental Operating Report (Section 5.4.1) will include a l
-summary of the field inspection programs.
Field logs summarizing locations of l
er'osion damage and appropriate actions taken to rectify erosion problem areas t
11-4-2
r-O should be kept and be available for a period of five years.
A summary of the inspection program and corrective actions taken will appear in the Annual 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 (1) density (2) productivity (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 growing seasons in 1979 and 1981.
This study will terminate after 1981.
If an ad.erse 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 environmental alterations due to the impoundment of Lake Anna and the Waste Heat Treatment Facility will 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.
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.
11-4-3 k._
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5.
ADMINISTRATIVE CONTROLS 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 services 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 environmental effects of the station, and any evaluation of the environ-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 implementation of these Environmental Technical Specifications.
5.3 Changes in Station Design or Operation CSanges in procedures, station design or operation may be made subject to ccnditions described below, provided such changes are approved by the SN50C (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 prior Commission approval, unless the proposed change, test, or experiment II J5-1
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involves a change in the objectives of the ETS, or an unreviewed environ-mental question of substantive impact.
1 A proposed change, test, or experiment shall be deemed to involve an B.
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 different type than any evaluated previously in the FES or FES Addendum may be created.
The licensee shall maintain records of changes in facility design or C.
operation made pursuant to this Subsection to the extent that such changes constitute changes in procedures as described in the FES, FES Addendum The licensee shall also maintain records of tests and experiments and ER.
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 substant.ive impact or constitute a The licensee shall furnish to the change in the objectives of these ETS.
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 experiment's.
Changes in the special studies, if required in Section 4.2, which affect D.
sampling frequency, location, gear, or replication shall be reported to the NRC within 30 days after their implementation.' These reports shall describe the changes made, the reasons for making the changes, and an evaluation of the enviror. mental 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 wgpid permit direct comparisons.
5.4 Station Reporting Requirements 5.4.1 Routine Reports Z
Annual Environmental Operating Report A report on the non radi'> logical 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 o ne of issuance of the operating license.
The report shall include summaries, analyses, interpretations, and statistical evaluation of the results of the environmental monitoring required by special studies and requirements (Section 4) for the report period, including a comparison with
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pre 6perational studies, operational controls (as appropriate), and previous g
non-radiological environmental monitoring reports, and an assessment of the If harmful observed impacts of the station operation on the environment.
effects or evidence of irreversible damage are suggested by the monitoring i
programs, the licensee shall provide a more detailed analysis of the data and I
a proposed course of action to alleviate.the problem.
II 5-2
i for those programs concerned with water quality or protection of aquatic 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 socn 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 nonroutine reports submitted per ETS Section 4.1.
5.
Changes in approved ETS.
5.4.2 Nonroutine Reports A report shall be submitted in the event that an " Unusual or Important Environ-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 with n 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 Subsect'.as 5.4.2.a, 5.4.2.b, and 5.4.2.c shall be satisfied by submitting, to the 4<, copies of reports as required by t e flPDES permit (or other regulations pu,suant to the Clean Water Act) and in accordance with the schedules and content requirements imposed thereby.
- 5. 5 Changes in Environmental Tech i Specifications and Permits 4
5.5.1 ChangesinEnvIronmentalTechnicalSpecifications Requests for changes in environmental technical specifications shall be submitted to the ilRC 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 thaa 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 a, ware of a request 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 permit 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
.ap' peal 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 Enviro.nmental Tech'nical 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), Statq, local, and regional authorities for the protection of the environment.
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(d) Routine reports submitted to the NRC.
- 5. 6. 2 Records of the 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.
Records associated with requirements of Federal (other than NRC),
5.6.3 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' O
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