ML20196F281

Rev 1 to, Radiological Effluent Monitoring & Offsite Dose Calculation Manual & Process Control Program

ML20196F281
Person / Time
Site:	Millstone
Issue date:	01/31/1989
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20196F178	List: B13081, Forwards Rev 1 to Radiological Effluent Monitoring & Offsite Dose Calculation Manual & Process Control Program. Attachment 1 Provides Detailed List of Proposed Changes for NRC Approval.Fee Paid ML20196F281
References
PROC-890131, NUDOCS 8812120250
Download: ML20196F281 (37)

Text

___ _ _ _ _ _

v Docket Nos. 50 245 50 336 50 423 License Nos DPR 21 DPR 65 NPF.44 R_A_DIOLOGICAL EFFLUENT

_ MONITORING AND OFFSITE DOSE CALCULATION MANUAL AND PROCESS CONTROL PROGRAM MILLSTONE UNIT NOS.1,2, & 3 Northeast Nuclear Energy Company

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P Jg 989

v LECTION I RADIOLOGICAL EFFLUENT MONITORING MANUAL FORTHE MILLSTONE NUCLE AR POWER STATION UNIT NOS.1,2, & 3 DOCKET NO. 50 245 50 336 50 423 January 1989 Revision i

v 1/1/89 Ree.1 4

RADIOLOGICAL EFFLUENTMONITORING MANUAL TABLE OF CONTENTS SECTION PAGE NO.

R EV. NO.

A.

INTRODUCTION A1 1

B.

RESPONSIBILITIES B1 1

C.

LIQUID EFFLUENTS 1.

LIQUID EFFLUENTS SAMPLING C1 1

AND ANALYSIS PROGRAM 2.

LIQUID WASTE TRE ATMENT C 11 1

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i D.

GASEOUS EFFLUENTS 1.

G ASEOUS EFFLUENTS SAMPLING D1 1

i AND ANALYSIS PROGRAM

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2.

G ASEOUS WASTE TRE ATMENT D9 1

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E.

RADIOLOGICAL ENVIRONMENTAL I

MONITORING 1.

SAMPLING AND ANALY5ts E1 1

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LAND USE CENSUS E3 1

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INTERLABORATORY COMPARISON PROGRAY E4 1

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REPORT CONTENT

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1.

ANNUAL RADIOLOGICAL l

ENVIRONMENTAL OPER ATING REPORT F1 1

2.

SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT F2 1

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1/1/89 Rev 1 A.

INTRODUCTION The purpose of this manualis to provide the sampling and analysis programs which provide input to the ODCM for calculating liquid and gaseous effluent t

concentrations and offsite doses. Guidelines are provided for operating radioactive waste treatment systems in order that offsite doses are kept As Low As Reasonably-l Achievable (ALAR A).

l The Radoological Environmental Monitoring Program outlined within this manual provides confirmation that the measurable concentrations of radioactive material released as a result of operations at the Millstone Site are not higher than expected in addition, this manual outlines the information required to be submitted to the f

NRC in both the Annual Radiological Environmental Operating Report and the SemiannualRadooactive EHluent Release Report.

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1/1/89 Rev.1 r

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RESPO_N5tBILITIE S All changes to this manual shalt be reviewed and approved by the Station Operations Review Committee and the Nuclear Regulatory Commission prior to implementation.

All changes and their rationate shat! be documented in the SemiannualRadioactsve

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Effluent Release Report.

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l It shall be the responsibility of the Station Superintendent to ensure that this manual is used in performance of the surveillance requirements and administrative controls i

of the TechnicalSpecifications.

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LIQUID EFFLUENTS C.1 Liouid Effluent Samphand Analysis procram f

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l Radioactive liquid wastes shall be sampled and anatyred in accordance with the

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j program specified in Table C f for Millstone Unit No.1 Table C 2 for Millstone j

Unit No. 2, and Table C 3 for Millstone Unit No. 3. The results of the radioactive analyses shall be input to the methodology of the ODCM to assure that the l

i concentrations at the point of release are maintained within the limits of the 3

TechnicalSpecification 3.8 C.f for Millstone Unit No.1 and within the limits cf Technica/ Specification 3.f f.f for Millstone Unit Nos. 2 and 3.

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Table C 1 MILi. PONE 1 RADIOA CTIVE LIQUID WAS TE 5 AMPLING 5.ND ANAL YSl$ PROGRAM Lower Limit Minimum of Detection Sampling Analysis Type of Activity (LLD)a

(

Liquid Release Type Frequency Frequency Analysis (pCi'ml)

A. Batch Releasef

1. Waste Sample Prior to Prior to Principal Gamma 5 x 10 7 Tanks Each Batch Each Batch Emittersb l 131 Mo 99 1 x 10 6 1

Ce 141 Ce 144 5 x 10 6 t"

2 Floor Drain Sample Tank One Batch Monthly Other Dissolved 1 x 10 5 per Yonth and Entrained Gases j

3 Decontamina-Prior to Monthly H3 1 x 10 5 l

tion Solution Each Batch Composite Gross alpha 1 x 10 7 Tank l Ovarteth i

l Prior to St 89, Sr 90

,. 18 Each Batch l Composite Fe 55 1,

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B. Continuous l

Release Daily iWeekly Principal Gamma Grab i Compositec Emittersb 5 x 10 7 i

Sampleo t

1 131, Mo.99 1 x 10 6 Ce 141, Ce 144 5 x 10 6 Reactor Building Service Water Monthi) Grab Monthly Dissolved and 1 x 10 5 Sample Entrained Gases Weekly Grab Monthly H 3e 1 x 10 5 1

Simple Compoutec l

Gross alphae 1 x 10 7 l

I Weekly Grab Quarterly Sr 89e, Sr 90e 5 x 10 8 l

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. Sa mple I Compositec

_ Fe 55e 1 x 10 6 j

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o s

1/1/89 Rev.*

TABLE C 1 (Cont'd.)

TABLE NOTA TIONS The LLD is the sma'lest concentration of radioactive materialin a Sample that will be a.

detected with 958: probability with 58: probability of falsely concluding that a blank observation represents a real" signal.

For a panicular measurement system (which may include radiochemical 5Jparation) 4.60 S, LLD a hV 2 22 s 16'. Y. cap t- \\ h r s where:

LLD is the lower hmit of dstection as defined above (as pC per unit mass or volume)

Se 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)

Vis the < ample size (in units of mass or volume) 2.22 a 106 is the number o4 trans'ormat ons per minute r:er microcurie l

Y is the f ractiona, rad,iochemical yield (w hen applicable)

A is the radioactive decay constant f or the particular radionuchde l

.it is the elapsed time between midpoint of sample collection and midpoint o' counting time It should be recognized that the LLD is defined as an a prjoy (before the fact) hm>t rep'esentirg the c3pability of a measurement system ano not as an aposterio'i(a+1e' the fact) hmit for a particular measurement.

Analyses shall be performed in such a manner that the stated LLD's will be achieved l

under routine conditions Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuchdes, or other uncontrollable circumstances may render these LLD's ungchievable. In such cases, the contributing factors will be identified and recorded on the analysis 5 seet for the particular sample.

b The LLD will be 5 a 10 7 pCi ml The principal gamma emitters for which this LLD applies are eaclusively the following radionuclides Mn 54, Fe 59, Co 58. Co 60.

2n 65, C5134, and C5-137 This hst does not mean that only these nuchdes are w be detected and reponed Other peaks which are measurable and identifiable, together with the above nuchdes, sha!! also be identified and reponec Nuchdes which are below the LLD for the analyses shou!d not be reponed as being present at the LLD level When unusual circumstances result in a prtofi LLD's highe' than required, the reasons shall be documented in the SemiannuaTRacioactn e EH! vent Re: ease Repon U

1.hh Reu.1 c

A compos'te sampf e 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 empic,)ed results in a specimen which is representative of the liquids released l

Prior to analysis, at! samples taken for the composite shall be thoroughly mixed in order for the composite sampfe to be representative of the effluents released l

d Dai!y grab samptes for service water taken at least five days per week l

e These ana' pes are required on!) if weekly gamma analysis indicates a gamma activity greater than 5 m 10 7 pCumi f.

A batch release is the discharge of hquid wastes of a discrete volume Prior to l

Samphng, each batch sha!! be itof ated and at least two tantsump volumes shall be recirculated or equivalent mixing proviced

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i 9/1/89 Retr 9 Table C 2 MILLSTONE 2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANAlyS]$ PMOGRAM j

Lower Limit Minimum of Detection Sampling Analysis Type of Activity (LLD):

f Liquid Release Type Frequency Frequency Analysis (uCi ml) t A. Batch Releaseb

1. Coolant Waste Prior to Prior to Principal Gamma 5 x 10 7 i

Monitor Ta nk Each Batch Each Batch Emitters (

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l 131, Mo 99 1 a 10 6

2. Aerated Waste Ce 141 Ce 144 5 x 10 6 i

Samr'e Tank One Batch Monthly Dissolved and 1 a 10 5

3. Condensate per Month Entrained Gasesd Polishing Facility Waste r

1 Neutralization Prior to Monthly H 3d 1 a 10 5 l

1 Sumpe Each Batch Compositet.9 Gross alphad 1 m 10 7 i

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Prior to Quarterly

$r 89d,Sr 90d 5 a 10 8

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Each Batch Compositet.9 Fe 55d 1 x 10 6 6.

Continuous l

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Release l

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1. 5 team Generator Daily Grab Weekly Principal Gamma 5 x 10 7

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Blowdown

• Samplei Composites Emitterst l 131. Mo 99 1 a 10 6 Ce 141, Ce 144 5 x 10 6 2.5er ice Water i

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Effluenth

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i Monthly Grab Monthly Dissolved and 1 a 10 5 i

Sample Entramed Gasesi Weekly Grab Monthly H 31 1 z 10 5 l

Sample Composites

' Gross af phai 1 m 101 i

3. Turbine Building L

j Sumpsh j

Weekly Grab Ovaneri>

Sr 89). $r 90).

5 m 10 s I

Sample Composites Fe 551 1 x 10 6 I

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" /89 Rev.1 TMQ (Cont'd.)

TABLE NOTA TIONS a.

The LLD is the sr.

?ntration of radioactive materialin o sample that will be detected with i

.lity with 5% probabihty of falsely concluding that a blank ooservation ter real" signal.

For a particslar mew;rement system (which may include radiochemical separation):

4.66 S, LLD =

6 E V 2 22 2 10 Y crp (- A a r 1

-yhcre:

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

Se 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 106 s the number of transformations per minute per microcurie i

Y is the fractional radiochemical yield (when applicable)

A is the radioactive decay cons ant for the particular radionuclide at is the elapsed time between midpoint of sample collection and midpoint o' counting time it should be recognized that the LLD is defined as an a_ priori (before the fact) limit representing the caoability of a measurement system and not as an aposterio_ri(after the fact) limit for a panicular measuremeilt.

Analyses shall be performed in such a manner that the stated LLD's will be achieved I

under routine conditions. Occasionally backgro.:nd, fluctuations, unavoidably small sample sizes, the presence of interfering nucodes, or other uncontrollable circumstances may render these LLD's unachievab:e. In such cases, the contributinc l

factors will be identified and recorded on the ana:ysis sheet for the particulai sample.

b.

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

The LLD will be 5 x 10 7 pCi/ml. The principal gamma emitters for which this LLD applies are exclusively the following radionuchdes:

Mn 54, Fe 59, Co 58, Co 60.

2n 65, Cs 134, and Cs 137.

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i 1/1/89 Rev.1 Table C 2 (Cont'd.)

TABLE NOTATIONS 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 also 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 a_ priori LLD's higher than required, the reasons shall be l

documented in the SemiinnualRadioactive Efiluent Release Report.

d.

For the Condensate Polishing Facility (CPF)

Waste Neutralization Sump, these analyses are only required if the gamma analysis of the CPF Waste Neutralization Sump indicates a gamma activity greater than 5 x 10 7 pCi/ml.

e.

For the Condensate Polishing Facility Waste Neutralization Sump,these analyses are only required when the stes n generator gross activity (sampled ard analyzed 3 times per week as per Table 4.7 2 of the Safety Technical Specifications) exceeds 1 x 10-l 5 pCi/ml.

f.

A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharge: and in which the method of sampling employed results in a specimen which is representative cf the liquids released.

9 Prior to analysis, all samples taken for the composite shall be thoroughir mixed in order for the composite sample to be representative of the effluents,elea. d.

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For the Steam Generator Blowdown and the Turbine Building Sump, these analyses are only required when the steam generator gross activity (sampled and analyzed 3 times per week as per Table 4.7 2 of the Safety Techroical Specifications) exceeds l

5 x 10 7 pCi/m!.

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Daily grab samples shall be taken at least 5 days per week.

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For the Service Water, these analyses are only required if a weekly gamma ana'ysis l

indicates a gamma activity greater than 5 x 10 7 pCi/ml.

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The daily and weekly 3 sample frequencies for Service Water can be reduced to monthlyif: f), the reacwr building closed cooling water is sampled weekly and these samples indicate gamma activity less than 2 x 10 6 pCi/ml and 2), the leakage from the reactor building closed cooling water is less than 350 gallons per minute.

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1/1/89 Rev.1 T_able C-3 MILLSTONE 3 RADIOACTIVE LIQUID WASTE SAMPLING AND ANAL YSIS PROGRAM l

Lower Limit of Detection Sampling Analysis Type of Activity (LLD)a Liquid Release iype Frequency Frequency Analysis (pCi/ml)

• Batch Releaseb

1. Condensaw Polishing Facility Waste Prior to Prior to Principal Gamma 5 x 10 7 Nestralization Each Batch Each Batch Emitters (

l Sumpe 1131, Mo 99 1 x 10 6 Ce 141, Ce 144 5 x 10 6

2. Waste Test Tan ks One Batch Monthly Di%olved and 1 x 10 5

3. Condensate per Month Entrained Gasesd Polishing Facility -

Regenerate Prior to Monthly H 3d 1 x 10 5 Distillate Tank Each Batch Compositetg Gross alphed 1 x 10 7

4. Low Level Waste Drain Tank Pr;or to Qua rterly Sr 89d, Sr 90d 5 x 10 8 Each Batch Compositetg Fe 55d 1 x 10 6

5. Boron Test Tanks B.

Continuous Release Daily Grab Weekly Principal Gamma 5 x 10 7 1 Steam Generator Samplei Composite 9 Emitterst Blowdownh I 131, Mo 99 1 x 10 6 Ce 141, Ce 144 5 x 10 6 2 Service Water

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s Efiluenth Monthly Grab Monthly Dissolved and 1 x 10 5 Sample Entrained G,eJ l

Weekly Grab Monthly H 3i 1 x 10 5

3. Turbine Building Sample Compositeg Gross alphai 1 x 10 7 Sumpsh l

I Weekly Grab Quarterly Sr 891, Sr 90),

5 x 10 8

, Sample Compositeg Fe 55i 1 x 10 6 1

CB

1/1/89 Rev.1 Table C 3 (Cont'd.)

TABLE NOTATIONS The Lt.D 6 the smallest concentration of radioactive materialin a sample that will be a.

deteced with 95c4 probability with 504 probability of falsely concluding that a blank observation represents a real" signal.

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

4.66 S 6 LLD =

6 E V 2 22 10. Y czp (- A.1 t l where:

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

Sb 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 106 s the number of transformations per minute per microcurie i

Y is the iractional radiochemical yield (when app!! cable)

A is the radioactive decay constant for the particular radionuclide

.it 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 anc not as an aposteriori(after the fact) limit for a particular measurement.

Analyses shall be performed in such a manner that the stated LLD's will be achieved l

under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLD's unachievable. In st,ch cases, the contributing l

factors will be identified and recorded on th( analysis sheet for the particular sample.

b.

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

The LLD will be 5 x 10 7 pCi/m!. The principal gamma emitters for which this LLD c.

applies are exclusively the following radionuclides:

Mn 54, Fe 59, Co 58, Co 60, 2n 65, Cs 134, and C5-137.

1 C 9

e' 1/1/89 Rev.1 Table C 3 (Cont'd.)

TABLE NOTATIONS 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 also be identified and reported. Nuclides which are below the LLD for the analyses should not be repo' ed as being present at the LLD level. When unaval circumstances result in a prior..LD's higher than required, the reasons shaf t be l

documented in the Semiannual Radioactive Effluent Release Report.

d.

For the Condensate Polishing Facility (CPF) - Waste Neutralization Sump, these analyses are only required if the gamma analysis of the CPF Waste Neutralization Sump indicates a gamma activity greater than 5 x 10 7 pCi/ml.

e.

Fnr the Condensate Polishing Facility Waste Neutralization Sump, these analyses are only required when the steam generator gross activity (sampled and analyzed 3 times per week as per Table 4.71 of the Safety Technical Specifications) exceeds l

1 x 10 5 pCi/ml.

f.

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 liquids released.

g.

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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For the Steam Generator Blowdown and the Turbine Buildinn Sump, these analyses are only required when the steam generator gross activity (sampled and anal zed 3 y

times per week as per Table 4.71 of the Safety TechnicalSpecifications) exceecs l

5 x 10 7 pCi/ml.

Daily grab samples shall be taken at least 5 days per week.

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For the Service Water, these analyses are only required if a weekly gamma analysis l

indicates a gamma activity greater than 5 x 10 7 pCi/ml.

k.

The daily and weekly grab sample frequencies for Service Water can be reduced to monthly if: f), the reactor plant closed cooling water is sampled weekly and these samples indicate gamma activity less than 2 x 10 6 pCi/mi and 2), the leakage from the reactor plant component cooling water system is less than 100 gallons per minute.

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.9 Rev.1 C.2 Liouid Radioactive Waste Treatment All apphcable 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 respontible for greater than ten percent (10'd) of the total projected dose. The liquid radioactive waste treatment system equipment is specified below for each unit.

l Millstone Unit No.1 Filtration and ion exchange system and waste demineralizer A or B.

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Millstone Uni _t No. 2

1. Degasifier, clean liquid primary demineralizer, boric acid evaporator, clean liquid secondary demineralizer and filter.

2. The aerated waste demineralizer and filter.

Millstone Unit No. 3

1. Degasifier, ion exchanger, boron evaporator, boron demineralizer, and boron deminerahzer filter.

2. High level waste demineralizer or waste evaporator, waste demineralizer and waste demineralizer filter.

3. Regenerant evaporator, regenerant demineralizer, and regenerant deminerahzer filter.

4 Condensate polishing filter system.

With radioactive liquid waste being discharged withcut treatment and in excess of the above limits, prepare and submit to the Commission a report that includes 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,

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 ARE AS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.

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- o' 1/1/89 Ree.1 D.

GASEOUS EFFLUENTS D.1 Gaseous Efiluents Samplina and Analysis Proaram Radioactive gaseous wastes shall be sampled and analyzed in accordance with the program specified in Table D 1 for Millstone Unit No.1, Table D 2 for Millstone Unit No. 2, and Table D-3 for Millstone Unit No. 3. 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 Specifications 3.8.D.1 for Unit No.1 and within the Specifications of 3.11.2.1 for Unit Nos. 2 and 3.

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h 1/1/89 Rev.1 TA__BLE D-1 MILLSTONE 1 RADIOACTIVE GASEOUS WASTE SAMPLING AND MALYSIS PROGRAM Lower Limit Minimum of Detection Sampling Analysis Type of Activity (LLD)a Gaseous Release Type - Frequency Frequency Analysis (pCi-cc)

A. Steam Jet Air Monthly -

Monthlyc Principal Gaseous 1 x 10 4 Ejector Discharge Gaseous Gamma Emittersb Grab Samplec B. Main Stack Monthly -

Monthly Principal Gaseous 1 x 10 4 Gaseous Gamma Emittersb Grab Sample H3 1 x 10 6 Continuousd Weekly 1-131 1 x 1012 Charcoal Samplef I133e 1 x 1010 Continuousd Weeklyf Principal Particulate 1 x 1011 Particulate Gamma Emitters -

Sample Half Lives Greater Than 8 Daysb

=

Continuousd Monthly Gross Alpha 1 x 1011 Composite Particulate Sample Continuousd Quarterly Sr 89, Sr 90 1 x 1011 Composite Particulate Sample Continuousd Noble Gas Noble Gases -

1 x 10 6 Monitor Gross Activity D2

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1/1/89 Rev.1 TABLE D 1 (Cont'd.)

TABLE NOTATIONS a.

The lower limit of detection (LLD)is defined in Table Notations, item a, of Tables C 1, l

C 2, or C 3 b.

For gaseous samples, the LLD will be 1 x 10 4 pCi/cc and for particulate samples, the LLD will be 1 x 1011 pCi/cc. The principal gamma emitters for which these LLD's apply l

are exclusively the following radionuclides: Kr 87, Kr 88, Xe 133, Xe 133m, Xe 135 and Xe 138 for gaseous emission and Mn 54, Fe 59, Co-58, Co 60,2n 65, Mo 99, Cs 134, Cs 137, Ce-141, and Ce 144 for particulate emissions. 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 also 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 a priori LLD's higher than required, the reasons shall be l

documented in the SemiannualRadioactive Effluent Release Report.

c.

Sempling and analysis shall also be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following an increase, l

as indicated by the steam jet air ejector off gas monitor, of greater than 50'd, after factoring out increases due to changes in THERMAL POWER level.

d.

The ratio of the sample flow rate to the sampled stream fl'sw rate shall be known, e.

Analyses for I 133 will not be performed on each chartoal sample. Instead, at least once per month, the ratio of I 133 to I 131 will be determined from a charcoal sample changed after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of sampling. This ratio, along with the routine 1131 activity determination will be used to determine the release rate of I 133.

f.

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. hall also be performed whenever subsequent reactor coolant 1 131 samples 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 1131 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 LLD's may be increased by a factor of 10 for these samples.

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a 1/1/89 Rev.1 TABLE D 2 MILLSTONE 2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Sampling Analysis Type of Activity (LLD)a Gaseous Release Type Frequency Frequency Analysis (pCi/cc) l A. Batch Release

1. Waste Gas Prior to Each Tank Principal Gamma 1 x 10 4 Storage Tankh Each Tank Discharge Emittersb Discharge

2. Containment H3 1 x 10 6 Purge B. Continuous Release Monthly -

Monthlyc Principal Gamma 1 x 10 4 Gaseous Emittersb Grab Sample (

H 39 1 x 10 6 Continuousd Weeklyf I131 1 x 1012 Charcoal Sample I133e 1 x 1010 Vent Continuousd Weeklyf Principal Gamma 1 x 1011 Particulate Emittersb Sample (1 131, others with i

Half lives > 8 days)

Continuousd Monthly Gross Alpha 1 x 1011 Composite Particulate Samples Continuousd Quarterly St 89, Sr 90 1 x 1011 Composite Particulate l

Samples Continuousd Noble Gas Noble Gases -

1 10 6

. Mon!o'

- Gross Activity t

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1/1/89 Rev.1

)

TABLE D 2 (Cont'd.)

TABLE NOTATIONS The lower hmit of detection (LLD)is defined in Table Notations, Item a, of Tables C 1, a.

C 2, or C 3.

S.

For gaseous samples, the LLO will be 1 x 10 8 pCi/cc and for particulate samples, the LLD will ne 1 x 1011 pCi/cc. The principal gamma emitters for which these ! '.O's apply are exclusively the following radionuclides: Kr 87, Kr 88, Xe-133, Xe 133m, Xe 135 and Xe 138 for gaseous emission and Mn 54, Fa 59, Co 58, Co 60,2n 65, Mo 99, "s 134. Cs 137, Ce 141, and Ce 144 for particulate eminions. The list dces not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and idc.ntifiable, together with the above nuclides, shall also 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 a _ priori LLD's higher than required, the reasons shall be l

docu mented in the Semiannut! Radioactive Effluen t Release Report.

Sampling and analysis shall also be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following an t

unexplained increase, as indicated by the Unit 2 stack noble gas monitor, of greater than 50%, after factoring out increases due to changes in THERMAL POWER levels, containment purges, or other explainable increases.

d.

The ratio of the sample flow rate to the sampled stream flow rate shall be known.

e.

Analyses for I 133 will not be performed on each charcoal sample. Instead, at least once per month, the ratio of I 133 to 1131 will be determined from a charcoal sample changed after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of sampling. This ratio, along with the routine I 131 activity determination will be used to determine the release rate ofI 133.

f.

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 1131 samples, which are taken 2 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 I 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 LLD's may be increased by a factor cif 10 for these samples g.

Grab samples for tritium shall be taken weekly whenever the refueling cavity is flooded and there is fuelin the cavity. The grab sample shall be taken from the stack (Unit 1 and 2) where the containment ventilation is being discharged at the time of sampling.

h.

Waste Gas Storage Tanks are normally released on a batch basis. However, for the purpose of tank maintenance, inspection, or reduction of oxygen concentration, a waste gas tank may be continuously purged with nitrogen provided the following conditions are met:

(1) The previous batch of radioactive waste gas has been discharged to a fmal tank pressure of less than 5 P5tG.

D5 i

e' 1/1/89 Ree.1 TABLE D 2 (Cont'd.)

TABLE NOTATIONS (2) No radioactive waste gases have been added to the tank since the previous discharge.

(3) Valve lineups are verified to ensure that no radioactive waste gases will be added to the tank.

(4) After pressurizing the tank with nitrogen, a sample of the gas in the tank will be taken and analyzed for any residual gamma emitters and tritium prior to initiation of the nitrogen purge. The measured activity will be used to calculate the amount of activity released during the purge.

L

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D6

9/1/89 Rev.1 T_A_B_LE D 3 MILLSTONE 3 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection

{

Sampling Analysis Type of Activity (LLD)a Gaseous Release Type Frequency Frequency Analysis (pCi cc)

A Batch Release Containment Prior to Each Purge or Principal Gamma 1 x 10 4 Purge or Drawdown Each Purge or Drawdown Emittersb Drawdownh H3 1 x 10 6 B. Continuous Release

1. Unit 3 Monthly (

Monthlyc Principal Gamma 1 x 10 4 Ventilation Vent Gaseous Emittersb Grab Sample H 39 1 x 10 6

2. Engineered Continuousd Weekly 1131 1 x 1012 Safeguards Charcoal Building Samplef I133e 1 x 1010 Continuousd Weekly Principal Gamma 1 x 1011 Particulate Emittersb i

Samplef (1 131, others with Half lives >8 days)

Continuousd Monthly Gross Alpha 1 x 1011 Composite Particulate Samples Continuousd Quarterly Sr 89, Sr 90 1 x 1011 Composite Particulate Samples Continuousd Noble Gas Noble Gases.

1 x 10 6 Monitor Gross ActLvity D7

1/1/89 Rev.1 TABLE D.3 (Cont'd.)

TABLE NOTATIONS a.

The lower limit of detection (LLD)is defined in Table Notations, frem a, of Tables C 1, l

C 2, or C 3.

b.

For gaseous samples, the LLD will be 1 x 10 4 pCi/cc and for particulate samples, the LLD will be 1 x 1011 pCi/cc. The principal gamma emitters for which these LLD's apply l

are exclusively the following radionuclides: Kr 87, Kr 88, Xe 133, Xe 133m, Xe 135 and Xe 138 for gaseous emission and Mn 54, Fe 59, co 58, Co 60,2n 65, Mo 99, Cs 134, Cs 137, Ce 141, and Ce 144 for particulate emissions. 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 also 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 a priori LLD's higher than required, the reasons shall be l

documented in the Semiannual Radioactive Efiluent Release Report.

c.

Sampling and analysis shall also be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following an l

unexplained increase, as indicated by the Unit 3 vent noble gas monitor, of greater than 50'o, after factoring out increases due to changes in THERMAL POWER levels, containment purges, or other explainable increases.

d.

The ratio of the sample flow rate to the se,mpled stream flow rate shall be known.

e.

Analyses for 1133 will not be performed on each charcoal sample. Instead, at least once per month, the ratio of I 133 to I 131 will be determined from a charcoal sample changed after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of sampling. This ratio, along with the routine I 131 activity determination will be used to determine the release rate of I 133.

f.

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 anc particulate filters shall also be performed whenever reactor coolant 1131 samples (which are taken 2 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one hour per Table 4.4 4 of the Safeh Technica/ Specifications) 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 1131 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 LLD's may be increased by a factor of 10 for these samples.

g.

Grab samples for tritium shall be taken weekly from the ventilation vent whenever l

the refueling cavity is flooded and there is fuelin the cavity.

h.

Subsequent to medical emergencies, for initial determination of isotopic content of the containment air, a Health Physics sample may be used in place of the norma!

chemistry sample.

D8

1/1/89 Rev.1 D.2 Gaseous Radioactive Waste Treatment All applicable gaseous radioactive waste treatment systems shall be operated when the projected dose due to gaseous effluents averaged over 31 days exceeds 0.2 mrad for gamma radiation, OA 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 (10c ) of the total projected dose. The gaseous radioactive waste c

treatment system equipment is specified below for each Unit.

Millstone Unit No.1 Offgas System Recombiner Train A or B Charcoal Bed Train A or B and the HEPA filter Radwaste Ventilation Exhaust Treatment System Radwaste ventilation HEPA filters Millstone Unit No. 2 Gaseous Radwaste Treatment System at least two (2) gas decay tanks, the waste gas fater and one waste gas compressor.

Ventilation Exhaust Treatment System - Auxiliary building ventilation HEPA filter (L26), containment purge HEPA filter (L25).

Millstone Unit No. 3 Gaseous Radwaste Treatment System. charcoal bed adsorbers, one HEDA filte',

and one process gas compressor.

Building Ventilation Auxiliary building ventilation filter, fuel bu;lding ventilation filter SLCRS filter.

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

1. Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,

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 D9

O*~

e*

n/89 Rev.1 E.

RADIOLOGICAL ENVIRONMENTAL MONITORING E.1 Samphno and Ana!vsis 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 l

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 Radiological Environmental 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 at the most desired location or time. In these instances suitable afternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the r' diological environmental monitoring program. In these instances, identify the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining replacement samples in the next Semiannual Rad,oactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).

If milk sampfes are unavailable from any one or more of the milk sample locations required by Table E 1, a grass sample shall be substituted until a suitable milk location is evaluated as a replacement or until milk is available from the original location. Such an occurrence will be documented in the A nn ual Radoological En vironm en tal Op era tung Report.

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 averaged over any calendar quarter, prepare 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 radionuclidesin Table E 2 are detected in the sampling medium, this report shall be submitted if:

n ncentrurum ti i n mr.n reu rio n (2 i o

+-

frportiRC $4vf!i) i ftpOMng Ett'tll2 i E1

a' 1/1/89 Ree.1 When radionuclides other than those in Table E 2 are detected and are the result of plant effluents, this Special 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 l

Technical Specifications 3.8.C.2.1, 3.8.D.2.1 or 3.8.D.3.1 for Millstone Unit No.1 or 3.71.1.2, 3.11.2.2 or 3.7 f.2.3 for Millstone Unit Nos. 2 and 3.

This report is not required if the measured level of radioactivity was not the result of plant effluents, however, in such an event, the condition shall be reported and described in the A n n ua l Ra diological En viron m en ta l Op era ting Repo rt.

The detection capabilities required by Table F 3 are state of the art for routine environmental measurements in industriallaboratories. 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_posteriori(after the fact) limit for a particular measurement. All analyses shall be performed in such a manner that the stated LLD's l

will be achieved under routine conditions. Occasionally background fluctuations, l

unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLD's unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.

l l

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1 l

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t E2

o' 1/1/89 Rev.1

\\

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 Sectron IV.B.3 of Appendu I to 10 CFR Part 50. The land use census shall be maintained and shat! identify 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 12 months by either a door to door survey, aerial survey, consulting local agr# culture authorities, or any combination of these methods.*

With a land use census ictentifying a location (s) which yields a calculated dose or dose commitment greater than the doses currently being calculated in the ODCM, make the appro sriate changesin the sample locations of Table E 2.

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

(1)If the D/O is at least 209o greater than the previously highest D/0, replace one of the present sample locations with the new one within 30 days if milk is available.

(2)If the D/O is not 20?c greater than the previously highest D/0, consider l

direction, distance, availability of milk, and D/O in deciding whether to replace one of the existing sample locations. If applicable, replacement shciutd be within 30 days. If no rep:acement is made, sufficient justification should be given in the annual repoa Sample location changes shall be noted in the Annual Radiological En vironmen tal Opera ting Report.

i 1

i

• Broad leaf vegetation (a composite of at least 3 different kinds of vegetation) l 15 sampled at the site boundary in each of 2 different direction sectors with the

[

highest D/O in lieu of a garden census E3

m 1/1/89 Rev.1 E.3 Inter!aboratory Comparison ProQram The interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materialin environmental sample matrices are performed as part of a quahty assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

Analyses shall be performed on 'adioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Ra diological En vironm en tal Opera tung Report.

With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commissior in the Annual Radoological En vironm en tal Opera ting Report.

t t

L e

E4

.o 1/1/89 Rev.1 TABLE E 1 MILLSTONE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sampling and Exposure Pathway Number of Collection and/or Sample Locations Frequency Type and Frequency of Analysis 1.a. Gamma Dose -

Environmental TLD 17 Monthly Gamma Dose Monthly 1.b. Gamma Dose -

Accident TLD 22 Quarterly (a)

N/A(a) 2.

Airborne Particulate 8

Continuous Gross Beta Weekly sampler -

Gamma Spectrum - Quarterly on weekly filter composite (by location), and on change individual sample if gross beta is greater than 10 times the mean of the weekly control station's gross beta results.

3.

Airborne lodine 8

Continuous 1131 Weekly sampler weekly canister change 4.

Vegetation 5

One sample Gamma Isotopic on each sample near middle and one near end of grow.

ing season 5.

Milk 6

Monthly for Gamma !sotopic and ! 131 on each all animals sample i

except semi-monthly for Sr 89 and Sr 90 on monthly goats when on composite pasture 6.

Sea Water 2

Qua rterly -

Quarterly Fractional Beta, Composite of Gamma Isotopic, and Tritium 6 weekly grab on each composite samples 7.

Bottom Sediment 5

Semiannual Gamma Isotopic on each sample E5

1/1/89 Rev.1 T_ABLE E 1 (Cont'd.)

MILLSTONE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sampling and Exposure Pathway Number of Collection and'or Sample locations Fre qu ency Type and Frequency of Analysis 8.

Fin Fish Flounder 2

Quarterly Gamma Isotopic on each sampfe and one other type of edible fin fish 9.

Mussels l

2 l

Quarterly l Gamma Isotopic on each sample l

Quarterly l Gamma Isotopic on each sample

10. Oysters l

4

11. Clams l

2 l

Quarterly l Gamma Isotopic on each sample l

Quarterly Gamma Isotopic on each sample

12. Lobsters l

2 (a)

Accident monitoring TLD's to be dedosed at least quarterly.

l l

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/

1/1/89 Rev.1 TABLE E 2 R_EPOR TING L E VEL S FOR RA DIOA CTIVITY CONCENTRA TIONS IN ENVIRONMENTA L SAMPL ES Reporting Levels Airborne Particulate or Fish Milk Vegetables 3

Analysis Water (pCi l) Gases (pCi'm ) (pCi/ka, wet)

(pCill)

(pCrk a, wet)

H3 2 x 104(a)

Mn 54 1x103 3xit)d Fe 59 4 x 102 4

1 x 10 Co 58 1 x 103 3 x 104 Co 60 3 x 102 4

1 x 10 2n 65 3 m 102 2 x 108 2r 95 4 x102 Nb 95 4 x 102 1131 (b) 09 3

1 x 102 C5134 30 10 1 x 103 60 1 x 103 C5137 50 20 2 x 103 70 2 x 103 Ba 140 2 x 102 3 x 102 La 140 2 x 102 3 x 102 (a)

For drinking water sampfes. This is 40 CFR Part 141 value.

(b)

Level for I 131 not included since no radioactivity discharged to any drinking water pathways; other reporting levels are included for trending of long hved isotopes only.

E7

in,ev p

Rev.1 TABLE E 3 MAXIMUM VAL UES FOR LOWER LIMITS OF DETECTION (LLD)*

Airborne Particulate Food Sediment Water or Gas Fish, Shellfish Milk Products (pCi'kg.

Analvsis (pCi l}

(pCi/ml)

(pCi/k a, wet)

(pCi/l)

(pCi,'k a, we t) dj Gross beta 1 x 10 2 l

Fractional beta 4

H3 2000 Mn 54 30(

130 Fe 59 60c 260 Co 58,60 30(

130 2n 65 60(

260 2r 95 60(

Nb 95 30c l131 d

7 x 10 2 1

60b i

Cs134 30(

5 x 10 2 130 15 60 150 Cs137 40(

6 x 10 2 150 18 80 180 Ba 140 120(.e 70 La 140 30(.e 25 l

I I

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E8

111/8 9 Rev.1 TABLE E-3 (Cont'd.)

TABLE NOTATIONS a.

The LLD is the smallest concentration of radioactive materialin a sample that will be detected with 9584 probability with 5'd probability of falsely concluding that a blank observation represents a "reaf" signal.

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

4.66 S 3 LLD = E V 2.22. Y ap (- X.% t )

where:

i t

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

$b s the standard deviation of the background counting rate or of the counting i

rate of a blank sample as appropriate (as counts per minute)

E is the countino efficiency (as counts per transGrmation)

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

A is the radioactive decay constant for the particular radionuclide At is the elapsed time between midpoint of sampla collection (or end of the sample collection period) and time of counting It should be recognized that the LLD is defined as an a ariori(before the fact) limit representing the capability of a measurement system anc not as an aposteriori(after the fact) limit for a particular measurement.

Analyses shall be performed in such a manner that the stated LLD's will be achieved l

under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLD's unachievable. In such cases, the contributing l

factors will be identified and described in the Annual Radiological Environmental Operating Report, b.

LLD for leafy vegetables.

c.

To be reduced by a factor of two if the fractional beta for the sample exceeds 15 pCi/l.

d.

Level for 1131 not included since no radioactivity discharged to any drinking water pathway.

e.

From end of sample period-E9

1/1/89

.I Rov.1 F.

REPORT CONTENT F.1 Annual Radiolooical Environmental Operatino Report The Annual Radoological Environmental Operating Report shall include l

summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, i

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 l

required by Section E.2 of this manual. If harmful effects are detected by the f

monitoring, the repart shall provide an analysis of the problem and a planned course of action to alleviate the problem.

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

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

(2) Total number of analyses performed at controllocations.

(3) Lower limit of detection (LLD).

(4) Mean and range of allindicator lo:ations together.

(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 r

specifications.

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

l 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 Interlaboratory Comparison Data required by Section E.3 of this manual.

4 F.1 i

I

J' 1/1'89 Rev 1 F.2 Semiannual Radioactive Effluent Release Report The SemiannualRadioactive EHluent Release Report shallinclude a summary of the quantities of radioactive iiquid and gaseous effluents released from the unit as outhned in Regulatory Guide 1.21, Revision f June 1974, with data summarized on a quarterly basis following the format of Appendix 8 thereof.

In addition, a report to be submitted 90 days after January 1 of each year, shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour by-hour listing on magnetic tape of wind speed, wind direction, and atmospheric stability, or in the form of joint frequency distributions of wind speed, wind directon, and atmospheric stabihty." This same report shall include an assessment of the radiation doses due te the radioactive hquid and gaseous effluents released from the site durir e the previous calendar year. The 4

meteorological conditions concurrent with the time of release of radioactive material in gaseous effluents shall be used for determining the giseous pathway doses Dose calculations shall be performed in accordance with the OHsite Dose Calculation Manual.

In addition, the report to be submitted 90 days after Januar 1 of each year shall include att assessment of radiation doses to the most li ely exposed REAL l

MEMBER OF THE PUBLIC from the site for the previous 12 consecutive rnenths to show conformance with 40 CFR 190. Doses shall be calculated in accordance with the OHsite Dose Csiculation Manual.

The semiannual effluent report shall also include a summary of each type of sohd radioactive waste shipped offsite for burial or final disposal during the report period. This summary shall include the following information for each type of waste:

a.

Type of waste (e g., spent resin, compacted dry waste, irradiated l

components, etc.).

b Sohdification agent (e g, cement).

c Total curies.

i d.

Total volume and typical container volumes.

e.

Princig,al radionuchdes (those greater than 10% of total activity).

f.

Types of :ontainers used (e.g, LSA, Type A, etc.).

The semiannual effluent report shallinclude the followinn information for all unplanned releases from the site to unrestricted areas of radioactive materia!s in gaseous and liquid effluents:

a A description of the event and equipment involved.

b Cause(s) for the unplanned release.

c Actions taken to prevent r?currence.

F2

~_

r# 'r 1 1/89 Rev.1 d-Consequences of the unplanned release.

Any changes to the RADIOLOGICAL EFFLUENT and OFFSITE DOSE CALCULA TION MANUAL and Process Control Program shall be sutomitted in the Semiannual i

Radioactive Effivent Release Report.

i

• • In lieu of submission with the Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data or I

site in a file that shall be provided to the NRC upon request.

J I

a n

F3

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