ML20206D103

Rev 10 to Radioactive Effluent Monitoring Manual

ML20206D103
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	05/31/1997
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20206D089	List: CY-99-057, Forwards 1998 Annual Radioactive Effluent Rept for HNP, & Rev 10 to Remodcm. with Summary of Quantities of Solid Radwaste & Liquid & Gaseous Effluents,As Well as Summary of Assessment of Max Individual Dose ML20206D090 ML20206D103 ML20206D107
References
PROC-970531, NUDOCS 9905030300
Download: ML20206D103 (76)

Text

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Northeast Utilities ,.

RADIOLOGICAL EFFLUENT MONITORING 1

OFFSITE DOSE CALCULATION MANUAL REMODCM CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT .'

Haddam, C=eicut DOCKET NO.50-213 I ,. LICENSE NO.DPR 61 PDR DO 0500 213 R PDR

5/30/97 Revision 10

(- HADDAM NECK PLANT RADIOLOGICAL EFFLUENT MONITORING MANUAL TABLE OF CONTENTS SECTION PAGE NO. REV.NO. DAIR A. INTRODUCTION A1 3 12/31/94 B. RESPONSIBILITIES B-1 3 12/31/94 I

C. LIQUID EFFLUENTS C.1 LIQUID EFFLUENTS SAMPLING AND ANALYSIS PROGRAM C-1 4 2/1/93 C-2 4 2/1/93 C-3 4 2/1/93 C-4 4 2/1/93 C.2 LIQUID RADIOACTIVE WASTE TREATMENT C-5 4 2/1/93 D. GASEOUS EFFLUENTS D.1 GASEOUS EFFLUENTS SAMPLING AND ANALYSIS PROGRAM D-1 4 12/31/94 D-2 4 12/31/94 D3 4 12/31/94 D.2 GASEOUS RADIOACTIVE WASTE TREATMENT D4 3 2/1/92 E. RADIOLOGICAL ENVIRONMENTAL MONITORING E.1 SAMPLING AND ANALYSIS E1 6 5/30/97 j E2 5 5/30/97 E-3 6 2/28/97 E-4 4 8/31/94 E-5 4 8/31/94 E6 4 8/31/94 E.2 LAND USE CENSUS E-7 5 2/28/97 E.3 INTERLABORATORY COMPARISON PROGRAM E-8 5 5/30/97 l F. REPORT CONTENT I

F.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL

OPERATING REPORT F-1 3 10/15/95 j F.2 ANNUAL RADIOACTIVE EFFLUENT REPORT F-2 3 8/31/94 omaxwmi

s I manu RADIOLOGICAL EFFLUENT MONITORING MANUAL FOR THE HADDAM NECK PLANT DOCKET NO. 50 213 i

4 May 1997 Revision 10 De82XW.001. DOC

12/31/94 Revision 3 A. lNTRODUCTION

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The purpose of this manual ik to provide the sampling and analysis programs which provide input to the ODCM for calculating liquid and gaseous effluent concentrations and offsite doses. Guidelines are provided for operating radioactive waste treatment systems in order that offsite doses are kept As-Low-As-Reasonably Achievable (Al. ARA).

The Radiological EnvironmentalMonitoring Program outlined within this manual provides confirmation that the measurable concentrations of radioactive material released as a I result of operations at the Haddam Neck Plant are not higher than expected.

i in addition, this manual outlines the information required to be submitted to the NRC in both the Annual Radiological Environmental Operating Report and the Annual l ;

Radioactive Effluent Report. I 4

0482XW 091 A1

i 12/31/94 Revision 3 B. RESPONSIBILITIES l- All changes to this manual shall be reviewed by the Plant Operations Review Committee prior to implementation.

All changes and their rationale shall be documented in the Annual Radioactive EMuent Report. [

it shall be the responsibility of the Station Vice President to ensure that this manual is used in performance of the surveillance requirements and administrative controls of the Technical SpeciMcations.

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4 02/1/93 Revisi:n 4 C. LIQUID EFFLUENTS C.1 Llauld Effluent Samolina and Analysis Prooram Radioactive liquid wastes shall be sampled and analyzed in accordance with the program specified in Table C-f for the Haddam Neck Plant. The results of the i radioactive analyses shall be input to the methodology of the ODCM to assure that the concentrations at the point of release are maintained within the limits of the TechnicalSpecifi:.ation.

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02/1/93 R:visi:n 4 Table C-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit of Minimum Detection Sampling Analysis Type of Activity (LLD)*

Liquid Release Type hequency Frequency Analysis (pCl/ml)

A. Batch Release" Prior to Prior to Principal Gamma 5 x 10 )

Each Batch Each Batch Emitters *

1. Waste Test 1131, Mo-99, 1 x 10 4 j Tanks and Zn-65, Cr 51, l Recycle Test Ru 106 I Tanks Co-141, Co 144 5 x 10 4 Kr 85 1 x 10" l One Batch Monthly 4 Other Dissolved 1 x 10 per Month

• and Entrained Gases

2. Waste Prior to Monthly H 3' 1 x 10 4 Neutralization Each Batch Composite *'

Tank" and Gross alpha' 1 x 10 )

i NPDES Turbine Building Sump" Sr-891, Sr 90' 5 x 10 4 Prior to Quarterly Fe-55' 1 x 104 Each Batch Composite **

8. Continuous Daily' Grab Weekly Principal Gamma 5 x 10

Release Sample Composite

• Emitters

• l 131, Mo-99, 1 x 10 4 Zn-65, CR-51, Ru-106

1. Steam Co-141, Co-144 5 x 10 4 Generator Blowdown d

Monthly Monthly Kr 85 1 x 10 Grab Other Dissolved Sample and Entralned Gases 1 x 10 4

2. Service Water Weekly Monthly H3 1 x 10 4 i Effluent Grab Composite

• l Sample Gross alpha' 1 x 10

Weekly Quarterly Sr 898, Sr-90' 5 x 104

- Grab Composite

• Fe 55 1x10* ,

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02/1/93 Revbisn 4 TABLE NOTATIONS

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a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a areal" signal.

For a particular measurement system (which may include radiochemical separation):

g, 4.66s, E V 2.22 x 10* y exp(-Aat) where:

LLD is the lower limit of detection as defined above (as pCl per unit mass or volume)

S is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

E is the counting efficiency (as counts per transformation)

V is the sample size (in units of mass or volume) 2.22 x 10' is the number of transformations per minute per microcurie g Y is the fractional radiochemical yield (when applicable)

A is the radioactivity decay constant for the particular radionuclide at is the elapsed time between midpoint of sample collection and midpoint of counting time.

It should be recognized that the LLD is defined as an a priori (before the fact) limit  ;

representing the capability of a measurement system and not as an a costeriori (after the fact) limit for a particular measurement.

Analyses shall be performed in such a mar.ner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoldably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be '

identified and recorded on the analysis sheet for that particular sample,

b. A 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 liquid released.

c. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluents released.

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d. One batch per month means one batch from a waste test tank and one from a recycle test tank if they are discharged that month.

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e. The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co 60, Cs-134, and Cs 137. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level. When unusual circumstances result in ,

igrigd LLDs higher than required, the reasons shall be documented in the Annual l Radioactive Effluent Report.

f. At least 5 days per week.

g.

For Service Water, these analyses are only required if a weekly gamma analysis indicates a gamma activity greater than 5 x 10' pCi/ml.

h. Each batch should be sampled and analyzed for principal gamma emitters only if the steam generator gamma activity is greater than 5 x 104 Ci/ml.

1. Not required for NPDES turbine building sump and waste neutralization tank.

J. Only required for the turbine building sumps and waste neutralization tank if the gamma activity of the batch is greater than 5 x 10 4 Ci/ml.

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k. A batch release is the discharge of liquid waste of a discrete volume. Prior to sampling, each batch shall be isolated and at least two tank / sump volumes shall be recirculated or equivalent mixing provided.

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02/1/93 R0 vision 4 C.2 Llauld Radioactive Waste Treatment All applicable liquid radioactive waste treatment systems will be operated when the projected dose due to liquid effluents averaged over 31 days exceeds 0.06 mrem to the total body or 0.2 mrem to any organ.

The term all applicable liquid radioactive waste treatment" is defined as that equipment applicable to a waste stream responsible for greater than ten percent (10%) of the total projected dose. The liquid radioactive waste treatment system equipment at the Haddam Neck Plant consists of the following:

portable mixed bed domineralizer and either evaporator or mixed bed polishing domineralizer;

• degasifier; and letdown system mixed bed demineralizer and either evaporator or boron recovery mixed bed polishing domineralizer.

With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission a report that included the following information:

1. explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability; j

2. action (s) taken to restore the inoperable equipment to OPERABLE status; and

3. summary description of action (s) taken to prevent a recurrence.

If the above treatment systems are not routinely operating, doses due to liquid effluents to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.

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12/31/94 Revision 4 D. GASEOUS EFFLUENTS I-N.

D.1 Gaseous Effluents Samolina and Analysis Proaram Radioactive gaseous wastes shall be sampled and analyzed in accordance with the piogram specified in Table D-1 for the Haddam Neck Plant. The results of the radioactive analyses shall be input to the methodology of the ODCM to assure that the offsite dose rates are maintained within the limits of the Technical Speci.

Ilcation.

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12/31/94 Revision 4

.TABLEIh1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit  !

Minimum of Detection Sampling Analysis Type of Activity Gaseous Release Type (LLD)*

Frequency Frequency Analysis (uCilcc)

A. Waste Gas Decay Grab Sample Prior to Principal Gamma d 1 x 10 Tank Prior to Each Tank Emitters

• i Each Tank H-3 1x 10 4

Discharge Xe-138 d l 3 x 10 i B. Containment Purge Grab Sample Prior to Principal Gamma 1 x 10*

Prior to Each Purge Emittars' Each Purge H-3' 1 x 10 4

Xe-138 3 x 10" Monthly

• Monthly

• Principal Gamma 1 x 10

Gaseous Emitters' Grab Samples H-3 1 x 10*

Xe-138 3 x 10" Continuous

• Weekly" 1-131 1 x 10"2 Charcoal Sample 1-133 1 x 10""

Continuous' Week ly" Principal Particu- 1 x 10'"

Particulate late Gamma Sample Emitters' (1-131, others with half lives > 8 days)

C. Main Stack Continuous' Monthly Gross Alpha 1 x 10'"

Composite Particulate  ;

Sample l 1

Continuous' Quarterly Sr-89, Sr-90 1 x 10'" l Composite Particulate Sample Continuous

• Noble Gas Noble Gases 1 x 10 4

Monitor Gross Activity 1

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.TABLEJht(cont'd.)

(_ TABLE NOTATIONS a.

The lower limit of detection (LLD) is defined in Table Notations of Table C-1.

b. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing. Special sampling and analysis of iodine and particulate filters shall also be performed whenever reactor coolant 1-131 samples taken 2-6 hours following a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one hour show an increase of greater than a factor of 5. These filters shall be changed following such a five-fold increase in coolant activity and every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter until the reactor coolant 1-131 levels are less than a factor of 5 greater than the original coolant levels or until seven days have passed, whichever is shorter.

Sample analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. The LLDs may be increased by a factor of 10 for these samples.

c. Sampling and analysis of principal gamma emitters shall also be performed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour unless (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the primary coolant has not increased more than a factor of 3 and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.

d. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the i time period covered by each dose or dose rate calculation made in accordance with TechnicalSpeciRcations.

e.

The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr 88, Xe-133, Xe-133m, and Xe-135. The list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in LLDs higher than required, the reasons shall be documented in the Annual Radioactive Ettluent Report.

f. When the refueling cavity is flooded and purging is in progress, samples shall be taken at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the charging floor (refueling floor) and analyzed for tritium. The results shall be used along with containment purge flow rates to determine tritium releases.

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The principal gamma emitters for which the LLD specification will apply are exclusively j the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo 99, Cs-134,

- Cs-137, Co-141, and Co 144. The list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in LLDs higher than required, the reasons

(- shall be documented in the Annual Radioactive Etnuent Report. l D-3 oearxw.oei i

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(--- D.2 Gaseous Radioactive Waste Treatment All applicable when the proj, gaseous radioactive waste treatment systems shall b exceeds 0.2 mrad for gamma radiation,0.4 mrad for beta radiation or 0.3 mrem to any organ due to gaseous particulate effluents.

The term all applicable gaseous radioactive treatment is defined as that equipment applicable to a waste stream responsible for greater than ten percent (10%) of the total projected dose. The gaseous radioactive waste treatment systems equipment at the Haddam Neck Plant consists of the following:

e Waste Gas Surge Tank, Waste Gas Compressor A or B and at least one Waste Gas DecayTank e Ventilation System HEPA Filter and Charcoal Filter With gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission a report that includes the  :

following information: 1

1. Explanation of why gaseous radwaste was being discharged without treatment, identificat,on i of any inoperable equipment or subsystems, and the reasons for the inoperability, i 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action (s) taken to prevent a recurrence.

if the above treatment systems are not routinely operating, doses due to gaseous effluents to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.

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5/30/g7 Revision 6 E. RADIOLOGICAL ENVIRONMENTAL MONITORING E.1 Samolina and Analysis The radiological sampling and analyses provide measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from plant operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Program changes may be made based on operational experience.

The sampling and analyses shall be conducted as specified in Table E-1 for the locations shown in Appendix G of the ODCM. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment or other legitimate reasons, if specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period.

All deviations from the sampling schedule shall be documented in the Annual RadiologicalEnvironmental Operating Report pursuant to Section F.1. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice (excluding milk) at the most desired location l

or time. In these instances suitable altemative media and locations may be chosen for the particular pathways in questions and appropriate substitutions made within 30 days in the radiological environmental monitoring program.

If milk samples are temporarily unavailable from any one or more of the milk sample locations required by Table E-1, a grass sample shall be substituted during the growing season (Apr. - Dec.) and analyzed for gamma isotopes until milk is again available. Upon notification that milk samples will be unavailable for a prolonged period (>g months) from any one or more of the milk sample locations required by Table E-1, a suitable replacement milk location shall be evaluated and appropriate changes made in the radiological environmental monitoring program.

Reasonable attempts shall be made to sample the replacement milk location prior to the end of the next sampling period. Any of the above occurrences shall be documented in the Annual Radiological Environmental Operating Report which is submitted to the U.S. Nuclear Regulatory Commission prior to May 1 of each year.

Changes to sampling locations shall be identified in a revised table and figure (s) in Appendix G of the ODCM.

If the level of radioactivity in an environmental sampling medium at one or more of the locations specified in Table E-1 exceeds the report levels of Table E-2 when o.saxw-tooc E-1

5/30/97 Revision 5

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averaged over any calendar quarter, prepara and submit to the Commission within 30 days from the end of the affected calendar quarter, a Special Report which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of Table E 2 to be exceeded. When more than one of the radionuclides in Table E 2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) concentration (2) reportinglevel(1) reporting level (2)

When radionuclides other than those in Table E-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the appropriate calendar year limit of the TechnicalSpec/Scation. This report is not required if the measured level of condition shall be reported and described in the Annual Radiological Environmental Operating Report.

The detection capabilities required by Table E 3 are state-of the-art for routine environmental measurements in industriallaboratories. It should be recognized that the LLD is defined as an a orlori(before the fact) limit representing the capability of a measurement system and not as an a costerior (after the fact) limit for a particular measurement. All analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.

Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the

, Annual Radiological Environmental Operating Report I

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2/28/97 Revision 6

(_. nauuu HADDAM NECK RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Sampling and Type and Frequency of and/or Sample Locations Collection Frequency Analysis 1a. Gamma Dose - 14 Monthly Gamma Dose - Monthly Environmental TLD 1b. Gamma Dose - 27 Quarterty" N/AW Accident TLD

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2. Airbome 7 Continuous sampler- Gross Beta - Weekly

. Particulate weekly filter change Gamma Spectrum - Quarterly on composite (by location),

and on indiv! dual sample if gross beta is greater than 10 times the mean of the weekly control station's gross beta results

3. Vegetation 4 One sample near middle G1mma Isotopic on each and one near end of- sample growing season

4. Milk 6 Monthly Gamma isotopic on each sample - Monthly t Sr-89 and Sr 90 - Quarterly 4a. Pasture Grass 6 Sample as necessary to Gamma Isotopic substitute for unavailable milk

5. Well Water 2 Quarterly Gamma isotopic, and Tritium on each composite

6. Bottom Sediment 3 Semlannual Gamma Isotopic

7. River Water 2 Quarteny Sample - . Quarterly- Gamma isotopic indicator is continuous and Tritium Compos 4e; Background is Composite of Six Weekly Gram Samples

8. Fish - bullheads 3 Quarterly Gamma isotopic- Quarterly and,when available, Perch or other edible fish

9. Shellfish 2 Quartedy Gamma isotopic- Quarterly (a) Accident monitoring TLDs to be dedosed at least quarterly.

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08/31/94 Ravision 4 TABLE E 2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels Alttporne Particulate Fish Vegetables Shellfish Water or Gases (pCi/kg, Milk (pCl/kg, (pCl/kg, Analysis (PCl/l) (pCl/m') wet) (pCl/l) wet) wet)

H-3 2 x 10' Mn-54 1 x 10' 3 x 10' 1.4 x 10' Fe-59 4 x 10' 1 x 10' 6.0 x 10' Co-58 1 x 10' 3 x 10' 1.3 x 105 Co-60 3 x 10' 1 x 10' 5.0 x 10' Zn-65 3 x 10" 2 x 10' 8.0 x 10' Zr-95 4 x 10' Nb-95 4 x 10" l131 (a) 0.9 2 x 10" 3 1 x 10 8 1 x 10 2 Cs 134 30 10 1 x 10 8 60 1 x 10' 5 x 10' I Cs 137 50 20 2 x 10 5 70 2 x 10 5 8 x 10' Ba-140 2 x 10" 3 x 10" La-140 2 x 10' 3 x 10 3 (a) Level for 1-131 not included since no radioactivity discharged to any drinking water pathways; other reporting levels are included for trending of long-lived isotopes only.

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08/31/94 Revision 4 TABLE E 3

(' ___ MAXIMUM VALUES FOR LOWER LIMITS OF DETECTION (LLDt Airborne Food Particulate Fish Products Sediment Water or Gas (pC1/kg, Milk (pCl/kg, (pCl/kg, Analysis (pCl/l) (pCl/m') wet) (pCl/l) wet) dry) gross beta 1 x 10'8 H3 2000 Mn-54 15 130 Fe-59 30 260 Co 58,60 15 130 Zn-65 30 260 Zr 95 30 Nb-95 15 l131 c 7 x 10~8 1 60*

Cs 134 15 5 x 10~8 130 15 60 150 Cs 137 18 6 x 10'8 150 18 80 180 l t Ba 140 60 70 La 140 15 25

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l 08/31/94 Revision 4 TABLE E 3 (Cont'd)

TABLE NOTATIONS

a. The LLD is the smallest concentration of radioactive materialin a sample that will be <

1 detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66s, LLD =

E V 2.22 Y exp(-Aat) where:

LLD is the lower limit of detection as defined above (as pCi per unit mass or volume) l S is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute) l 1

E is the counting efficiency (as counts per transformation)

V is the sample size (in units of mass or volume) 2.22 is the number of transformations per minute per picoeurie  ;

Y is the fractional radiochemical yield (when applicable)

A is the radioactivity decay constant for the particular radionuclide At is the elapsed time between midpoint of sample collection and midpoint of q counting time.

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lt should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a costeriori (after the fact) limit for a particular measurement.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radio logical Environmental Operating Report.

b. LLD for leafy vegetablos.

c. Background and onsite well water will not contain the short-lived 1-131 Isotope. River water is not used as offsite potable water supply and need not be analyzed for 1-131.

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2/28/97 Revision 5

( -- E.2 Land Use Census The land use census ensures that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required '

by the results of this census. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR Part 50. The land use census shall be maintained and shallidentify the location of the milk animals in each of the 16 meteorological sectors within a distance of five miles.'

The validity of the land use census shall be verified at least once per calendar year by either a door-to-door survey, serial survey, consulting local agriculture l

authorities, or any combination of these methods.*

With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the doses currently being calculated in the off-site dose models, make the appropriate changes in the sample locations used.

With a land use census identifying a location (s) which has a higher D/Q than a current indicator location the following shall apply:

(1) If the D/Q is at least 20% greater than the previously highest D/Q, replace one of the present sample locations with the new one within 30 days if milk is available.

( (2) If the D/Q is not 20% greater than the previously highest D/Q, consider direction, distance, availability of milk, and D/Q in deciding whether to l replace one of the existing sample locations. If applicable, replacement should be within 30 days. If no replacement is made, sufficient justification should be given in the annual report.

Sample location changes shall be noted in the EnnualRadiologicalEnvironmental Operating Report.

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• Broad leaf vegetation (a composite of at least 3 different kinds of vegetation) may be sampled at the site boundary in each of 2 different direction sectors with high D/Q in lieu of a garden census.

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5/30/97 Revision 5

(- E.3 Interfaboratory Comnarison Prooram -

The Interlsboratory Comparison Program is provided to ensure that independent checks t on the precision and accuracy of the measurements of radioactive materialin 4 environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably l valid.

{1 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program. A summary of the results obtained as part of the above required interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report.

1 With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

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10/15/g5 R0 vision 3 F. PtEPORT CONTENT .

(-- F.1 Annual Radioloalcal Environmental Ooeratina Report The AnnualRadiologicalEnvironmental Operating Report shallinclude summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The report shall also include the results of the land use census required by Section E.2 of this manual. If levels of radioactivity are detected that result in calculated doses greater than 10 CFR 50 Appendix l Guidelines, the report shall provide an analysis of the cause and a planned course to action of alleviate the cause.

The report shallinclude a summary table of all radiological environmental samples which shallinclude the following information for each pathway sampled and each type of analysis: j I

(1) Total number of analyses performed at indicator locations.

(2) Total number of analyses performed at controllocations.

(3) Lowerlimit of detection (LLD).

(4) Mean and range of allindicatorlocations together.

i (5) Mean and range of all controllocations together.

(6) Name, distance, and direction from discharge, mean and range for the location with the highest annual mean (indicator or control).

(7) Number of nonroutine reported measurements as defined in these specifications.

In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in the next annual report, '

The report shall also include a map of sampling locations keyed to a table giving distances and directions from the discharge; the report shall also include a summary of the Intertaboratory Comparison Data required by Section E.3 of this manual.

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F-1 Dd81XW.091

08/31/94 Rivisitn 3 F.2 Annual Radioactive Effluent Rooort The AnnualRadioactive Emuent Report (ARER) shall include quarterly quantities of and an annual summary of radioactive liquid and gaseous affluents released from the unit in the Regulatory Gude 1.21 (Rev.1, 06f74) format. Radiation dose assessments for these affluents shall be provided in accordance with 10CFR 50.36a and the Radiological EMuent TechnicalSpec/fications. An annual assessment of the radiation doses from the site to the most likely exposed REAL MEMBER OF THE PUBLIC shall be included to demonstrate conformance with 40 CFR 190. Gaseous pathway doses shall use meteorological conditions concurrent with the time of radioactive gaseous effluent.

releases. Doses shall be calculated in accordance with the Offs /te Dose Calculation Manual. The licensee shall maintain an annual summary of the hourly meteorological data (i.e., wind speed, wind direction, and atmospheric stability) either in the form of an hour-by-hour listing on a magnetic medium or in the form of a joint frequency distribu-tion. The licensee has the option of submitting this annual meteorological summary with the ARER, or retaining it and providing it to the NRC upon request. The ARER shall be submitted by May 1 of each year for the period covering the previous calendar year.

The ARER shallinclude a summary of each type of solid radioactive waste shipped offsite for burial or final disposal during the report period and shall include the following information for each type:

a. type of waste (e.g., spent resin, compacted dry waste, irradiated components, etc.);

b. solidification agent (e.g., cement);

c. total curies;

d. total volume and typical container volumes;

e. principal radionuclides (those greater than 10% of total activity); and

f. types of containers used (e.g., LSA, Type A, etc.).

The ARER shall include the following information for all abnormal releases of radioactive gaseous and liquid effluents (i.e., exceeding TechnicalSpecification instantaneous release limits) from the site to unrestricted areas:

a. a description of the event and equipment involved;

b. cause(s) for the abnormal release;

c. actions taken to prevent recurrence; and

d. consequences of the abnormal release.

Changes to the RADIOLOGICAL EFFLUENT MONITORING and OFFSITE DOSE CALCULATION MANUAL (REMODCM) shall be submitted to the NRC as appropriate, as a part of or concurrent with the ARER for the period in which the changes were made.

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