Text

2018 Radioactive Effluent Release Report, Volume 2
	ML19122A385
Person / Time
Site:	Millstone
Issue date:	04/28/2019
From:	; Dominion Energy Nuclear Connecticut
To:	; Office of Nuclear Reactor Regulation
References
	19-163 MP-22-REC-BAP01, Rev 030
	Download: ML19122A385 (139)
	v • d • e

Serial No.19-163 Docket Nos. 50-245 50-336 50-423 License Nos. DPR-21 DPR-65 NPF-49 ATTACHMENT 2 2018 RADIOACTIVE EFFLUENT RELEASE REPORT VOLUME 2 MILLSTONE POWER STATION UNITS 1, 2, AND 3 DOMINION ENERGY NUCLEAR CONNECTICUT, INC. {DENC)

MILLSTONE POWER STATION STATION PROCEDURE

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Radiological Effluent MonitQring and Offsite Dose CaJ~ulation Manual (REMODCM)

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MP-22-REC-BAPOl Rev. 030 Approval Date: 09/13/18 Effective Date: 09/19/18

Millstone All Units Station Procedure Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM)

TABLE OF CONTENTS I. Radiological Effluent Monitoring Manual (REMM) . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 I.A. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 LB. Responsibilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 LC. Liquid Effluents .............................................. ....... 7

1. Liquid Effluent Sampling and Analysis Program . . . . . . . . . . . . . . . . . . . . . . 7

2. Liquid Radioactive Waste Treatment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 I.D. Gaseous Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23

1. Gaseous Effluent Sampling and Analysis Program . . . . . . . . . . . . . . . . . . . 23

2. Gaseous Radioactive Waste Treatment ............................ 31 I.E. Radiological Environmental Monitoring . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36

1. Sampling and Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36

2. Land Use Census . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46

3. Interlaboratory Comparison Program ............................. 46 I.F. Report Content .............................................. ....... 47

1. Annual Radiological Environmental Operating Report ............... 47

2. Radioactive Effluent Release Report . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 48 II Off-Site Dose Calculation Manual (ODCM) ................................. 51 II.A. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 II.B. Responsibilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 II.C. Liquid Dose Calculations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52

1. Monthly, Quarterly, and Annual Dose Calculation (Applicable to All Units) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52

2. Monthly Dose Projections ....................................... 52 II.D. Gaseous Dose Calculations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55

1. Site Release Rate Limits ("Instantaneous") . . . . . . . . . . . . . . . . . . . . . . . . 55

2. 10 CFR50 Appendix I - Noble Gas Limits . . . . . . . . . . . . . . . . . . . . . . . . . 57

3. 10 CFR50 Appendix I - Iodine, Tritium and Particulate Doses . . . . . . . . 59

4. Gaseous Effluent Monthly Dose Projections . . . . . . . . . . . . . . . . . . . . . . . . *60

5. Compliance with 40CFR190 ..................................... 63 II.E. Liquid Discharge Flow Rates And Monitor Setpoints . . . . . . . . . . . . . . . . . . . . . 64

1. Unit 1 Liquid Waste Effluent Discharge (RE-M6-110) . . . . . . . . . . . . . 64 I

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2. Reserved . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 65

3. Unit 2 Clean Liquid Radwaste Effluent Line - RM9049 and Aerated Liquid Radwaste Effluent Line - RM9116 ......................... 65

4. Condensate Polishing Facility Waste Neutralization Sump Effluent Line - CND245 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 68

5. Unit 2 Steam Generator Blowdown - RM4262 and Unit 2 Steam Generator Blowdown Effluent Concentration Limitation . . . . . . . . . . . . . . . . . . . . . . . 69

6. Unit 2 Condenser Air Ejector - RM5099 . . . . . . . . . . . . . . . . . . . . . . . . . . 69

7. Unit 2 Reactor Building Closed Cooling Water RM6038 and Unit 2 Service Water, and RBCCW Sump and Turbine Building Sump Effluent Concentration Limitation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 69

8. Unit 3 Liquid Waste Monitor - LWS-RE70 ....................... 71

9. Unit 3 Regenerant Evaporator Effluent Line - LWC-RE65 ......... 73

10. Unit 3 Waste Neutralization Sump Effluent Line - CND-RE07 ...... 73

11. Unit 3 Steam Generator Blowdown - SSR-RE08 and Unit 3 Steam Generator Blowdown Effluent Concentration Limitation . . . . . . . . . . . . . 73

12. Unit 3 Turbine Building Floor Drains Effluent Line - DAS-RE50 and Unit 3 Service Water and Turbine Building Sump Effluent Concentration Limitation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 75 II.F. Gaseous Monitor Setpoints . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 76

1. Unit 1 Spent Fuel Pool Island Monitor - RM-SFPI-02 ............. 76

2. Unit 2 Wide Range Gas Monitor (WRGM) - RM8169 . . . . . . . . . . . . . . 76

3. Reserved . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 76

4. Unit 3 SLCRS - HVR-RE19B .................................. 77

5. Unit 2 Vent - Noble Gas Monitor - RM8132B .................... 77

6. Unit 2 Waste Gas Decay Tank Monitor RM9095 .................... 77

7. Unit 3 Vent Noble Gas Monitor - HVR-RElOB ................... 78

8. Unit 3 Engineering Safeguards Building Monitor - HVQ-RE49 ...... 78 III REMODCM Unit One Controls . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 82 III.A. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 82 III.B. Definitions and Surveillance Requirement (SR) Applicability . . . . . . . . . . . . . . 82 III.C. Radioactive Effluent Monitoring Instrumentation . . . . . . . . . . . . . . . . . . . . . . . . 85

1. Radioactive Liquid Effluent Monitoring Instrumentation . . . . . . . . . . . . . 85

2. Radioactive Gaseous Effluent Monitoring Instrumentation . . . . . . . . . . . 88 III.D. Radioactive Effluents Concentrations And Dose Limitations . . . . . . . . . . . . . . . 91

1. Radioactive Liquid Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 91

2. Radioactive Gaseous Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 93 III.E. Total Radiological Dose From Station Operations Controls . . . . . . . . . . . . . . . . 97 IV REMODCM Unit Two Controls . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 99 IV.A. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 99

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IY.B. Definitions, Applicability and Surveillance Requirements . . . . . . . . . . . . . . . . . 99 IV.C. Radioactive Effluent Monitoring Instrumentation . . . . . . . . . . . . . . . . . . . . . . . 103

1. Radioactive Liquid Effluent Monitoring Instrumentation . . . . . . . . . . . . 103

2. Radioactive Gaseous Effluent Monitoring Instrumentation . . . . . . . . . . 107 IY.D. Radioactive Effluents Concentrations And Dose Limitations.............. 111

1. Radioactive Liquid Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 111

2. Radioactive Gaseous Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 113 IY.E. Total Radiological Dose From Station Operation . . . . . . . . . . . . . . . . . . . . . . . 117 V REMODCM Unit Three Controls . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 119 V.A. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 119 V.B. Definitions and Applicability and Surveillance Requirements . . . . . . . . . . . . . 119 V.C. Radioactive Effluent Monitoring Instrumentation . . . . . . . . . . . . . . . . . . . . . . . 122

1. Radioactive Liquid Effluent Monitoring Instrumentation . . . . . . . . . . . . 122

2. Radioactive Gaseous Effluent Monitoring Instrumentation . . . . . . . . . . 126 V.D. Radioactive Effluents Concentrations And Dose Limitations . . . . . . . . . . . . . . 131

1. Radioactive Liquid Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 131

2. Radioactive Gaseous Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 133 V.E. Total Radiological Dose From Station Operations . . . . . . . . . . . . . . . . . . . . . . . 137 0

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TABLES AND FIGURES TABLES Table I.C.-1, "Millstone Unit 1 Radioactive Liquid Waste Sampling and Analysis Program" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 Table I.C.-2, "Millstone Unit 2 Radioactive Liquid Waste Sampling and Analysis Program" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 Table I.C.-3, "Millstone Unit 3 Radioactive Liquid Waste Sampling and Analysis Program" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 Table I.D. -1, "Millstone Unit 1 Radioactive Gaseous Waste Sampling and Analysis Program" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23 Table I.D.-2, "Millstone Unit 2 Radioactive Gaseous Waste Sampling and Analysis Program" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 Table I.D;-3, "Millstone Unit 3 Radioactive Gaseous Waste Sampling and Analysis Program" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28 Table I.E. -1, "Millstone Radiological Environmental Monitoring Program" . . . 38 Table I.E.-2, "Environmental Monitoring Program Sampling Locations" . . . . . . 39 Table tE.-3, Reporting Levels For Radioactivity Concentrations In Environmental Samples ............... ............... ............... .......... 43 Table I.E.-4, Maximum Values For Lower Limits Of Detection (LLD) . . . . . . . 44 Table App. II.A.-1, "Millstone Effluent Requirements and Methodology Cross Reference" ............... ............... ............... ........ .

Table III.C.-1, "Radioactive Liquid Effluent Monitoring Instrumentation" . . . . 86 Table III.C.-2, "Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 87 Table III.C.-3, "Radioactive Gaseous Effluent Monitoring Instrumentation" . . 89 Table III.C.-4, "Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 90 Table IV.C.-1, "Radioactive Liquid Effluent Monitoring Instrumentation" . . . 104 Table IV.C.-2, "Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 106 Table IV.C.-3, "Radioactive Gaseous Effluent Instrumentation" . . . . . . . . . . . 108 Table IV.C.-4, "Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 110 Table V.C.-1, "Radioactive Liquid Effluent Monitoring Instrumentation" .... 123 Table V.C.-2, "Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 125 Table V.C.-3, "Radioactive Gaseous Effluent Monitoring Instrumentation" . . 127 Table V.C.-4, "Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 129

FIGURES Figure I.C.-1, "Reserved" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 Figure I.C.-2, "Simplified Liquid Effluent Flow Diagram Millstone Unit 2 21 Figure I.C.-3, "Simplified Liquid Effluent Flow Diagram Millstone Unit 3 . . . . 22 Figure I.D. -1, "Simplified Gaseous Effluent Flow Diagram Millstone Unit One" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 33 Figure I.D.-2, "Simplified Gaseous Effluent Flow Diagram Millstone Unit Two" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34 Figure I.D.-3, "Simplified Gaseous Effluent Flow Diagram Millstone Unit Three" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 35 Figure I.E.-1, "Inner TLD, Air, Grass, Soil, and Aquatic Locations" . . . . . . . . . 41 Figure I.E.-2, "Outer TLD and Aquatic Locations ....................... . 42 Figure III.D. -1, "Site Boundary for Liquid and Gaseous Effluents" . . . . . . . . . . 96 Figure IY.D. -1, "Site Boundary for Liquid and Gaseous Effluents" . . . . . . . . . . 116 Figure VD. -1, "Site Boundary for Liquid and Gaseous Effluents" . . . . . . . . . . 136

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SECTION I.

Radiological Effluent Monitoring Manual (REMM)

For the Millstone Nuclear Power Station Nos. 1, 2, & 3 Docket Nos. 50-245, 50-336, 50-423 1\ 1\ '\

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SECTION I. RADIOLOGICAL EFFLUENT MONITORING MANUAL (REMM)

I.A. Introduction The purpose of Section I of this manual is to provide the sampling and analysis programs which provide input to Section II 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 (ALARA).

The Radiological Environmental Monitoring Program outlined within this manual provides confirmation that the measurable concentrations of radioactive material in the environment 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 NRC in both the Annual Radiological Environmental Operating Report and the Radioactive Effluent Release Report.

MP-22-REC-REF03, "REMODCM Technical Information Document (TID)," has additional bases and technical infonnation. It also contains a list of exceptions to Regulatory Guide 1.21 (see Section 2 of the TID).

I.B. Responsibilities All changes to the Radiological Effluent Monitoring Manual (REMM) shall be reviewed and approved by the Facility Safety Review Committee prior to implementation.

All changes and their rationale shall be documented in the Radioactive Effluent Release Report.

It shall be the responsibility of the Site Vice President Millstone to ensure that this manual is used as required by the administrative controls of the Technical Specifications. The delegation of implementation responsibilities is delineated in MP-22-REC-PRG, "Radiological Effluent Program."

LC. Liquid Effluents

1. Liquid Effluent Sampling and Analysis Program Radioactive liquid wastes shall be sampled and analyzed in accordance with the program specified in Table I.C.-1 for Millstone Unit No. 1, Table I.C.-2 for Millstone Unit No. 2, and Table I.C.-3 for Millstone Unit No. 3. The results of the radioactive analyses shall be input to the methodology of Section II to assure that the concentrations at the point of release are maintained within the limits of Radiological Effluent Controls (Section III.D.l.a. for Millstone Unit No. 1, Section IVD.l.a. for Millstone Unit No.

2, and Section VD.La. for Millstone Unit No. 3).

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Table I.C.-1 Millstone Unit 1 Radioactive Liquid Waste Sampling and Analysis Program Liquid Release Sample 'fype and Minimum Analysis 'fype of Lower Limit Source Frequency Frequency Radioactivity of Detection Analysis (LLD)A

(µCi/ml)

Any Batch Grab sample prior to Prior to each batch Principal Gamma 5 X 10- 7 Release from any each batch releaseB release Emitters source Kr-85 1 X 10-S H-3 1 X 10- 5 Grab sample prior to Prior to initial batch re- Gross alpha 1 X 10- 7 initial batch release lease from each source.

from any one source Quarterly for each Sr-90 5 X 10-S and quarterly compos- source. 0 ite thereafterC Fe-55 1 X 10- 6 Table I.C.-1 TABLE NOTATIONS 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 "real" signal.

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

LLD= 4.66 Sb (E)(V)(2.22xl06)(Ye -ALI 1)

Where:

LLD is the lower limit of detection as defined above (as µCi 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 1os is the number of transformations per minute per µCi

Y is the fractional radiochemical yield (when applicable)

1w is the radioactive 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 posteriori (after the fact) limit for a particular measurement.

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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 recorded on the analysis sheet for the particular sample.

B. Prior to the sampling, each batch shall be isolated and at least two tank/sump volumes shall be recirculated or equivalent mixing provided.

C. 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. 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.

D. For sources with no release during previous quarter, a quarterly sample is not required.

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Table I.C.-2 Millstone Unit 2 Radioactive Liquid Waste Sampling and Analysis Program Liquid Release Sample 'Iype and Minimum Analysis 'Iype of Lower Limit Source Frequency Frequency Radioactivity of Detection Analysis (LLD)A

(µCi/ml)

A.Batch ReleaseB.

l.Clean Waste Moni- Grab sample prior to Prior to each batch Principal Gamma 5 X 10- 7 tor Tank. each batch release release EmittersC.

2.Aerated Waste 1-131 1 X 10- 6 Monitor Tank.

3.Steam Generator Ce-144 5 X 10- 6

BulkD* Dissolved & 1 X lQ-S Entrained GasesK.

4.Condensate H-3 1 X lQ-S Polishing Facility

- Waste Quarterly Gross alpha 1 X 10- 7 Neutralization CompositeE,G.

Sr-89, Sr-90 5 X 10- 8 SumpE*

Fe-55 1 X 10-~

B.Continuous Release l.Steam Generator Daily Grab Sample!.& Weekly Principal Gamma 5 X 10- 7 BlowdownH. prior to aligning to CompositeE,G. EmittersC.

Long Island Sound for 2.Service Water RBCCWsump 1-131 1 X 10- 6 Effluent1*

Ce-144 5 X 10- 6 3.Turbine SumpsL Monthly Grab Monthly Dissolved & 1 X 10-S Sample Entrained GasesK.

4.RBCCW SumpM* Weekly Grab or Com- Monthly H-3N. 1 X 10-S posite CompositeE,G.

Weekly Composite Quarterly Gross alpha 1 X lQ- 7 CompositeE,G.

Sr-89, Sr-90 5 X lQ- 8 Fe-55 1 X 10- 6 TABLE I.C.-2 TABLE NOTATIONS 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 "real" signal.

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

LLD= 4.66 Sb (E)(V)(2.22xl06)(Ye-MI)

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Where:

LLD is the lower limit of detection as defined above (as µCi 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 is the number of transformations per minute per µCi

Y is the fractional radiochemical yield (when applicable)

l is the radioactive 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 posteriori (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 recorded on the analysis sheet for the particular sample.

B. A batch release is the discharge of liquid wastes of a discrete volume from the tanks listed in this table. Prior to the sampling, each batch shall be isolated and at least two tank/sump volumes shall be recirculated or equivalent mixing provided. If the steam generator bulk can not .be recirculated prior to batch discharge, a sample will be obtained by representative compositing during discharge.

C. The LLD will be 5 x 1o- 7 µCi/ml. The principal gamma emitters for which this LLD applies are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141. Ce-144 shall also be measured, but with an LLD of 5 x 10- 6

µCi/ml. 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 LLDs higher than required, the reasons shall be documented in the Radioactive Effluent Release

. Report.

D. For the Steam Generator Bulk:

lE. the applicable batch gamma radioactivity is not greater than 5 x 1o- 7 µCi/ml, THEN the sampling and analysis schedule for gross alpha, Sr-89, Sr-90, Fe-55 are not required.

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E. For the Condensate Polishing Facility (CPF} waste neutralization sump:

IF there is no detectable tritium in the steam generators, THEN tritium sampling and analyses is not required.

IF the gross gamma radioactivity in the grab sample taken prior to release does not exceed 5 x 1o- 7 µCi/ml, THEN the sampling and analysis schedule for gross alpha, Sr-89, Sr-90 and Fe-55 are not required.

F. For Batch Releases and Steam Generator Slowdown only, 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.

H. For the Steam Generator Slowdown:

IF the steam generator gross gamma radioactivity does not exceed 5 x 10- 7 µCi/ml, THEN the sampling and analysis schedule for all principal gamma, 1-131, Ce-144, noble gases, gross alpha, Sr-89, Sr-90 and Fe-55 are not required. For the purposes of this footnote, if steam generator samples are not available, condensate water gamma radioactivity may be used during times of blowdown.

I. Daily grab samples shall be taken at least five days per week. For service water, daily grabs shall include each train that is in-service. For steam generator blowdown, condensate may be sampled during blowdown if steam generator sample is not available.

J. For the Service Water:

IF a weekly gamma analysis does not indicate a gamma radioactivity greater than 5 x10- 7

µCi/ml, THEN the sampling and analysis schedule for gross alpha, Sr-89, Sr-90, Fe-55 are not required.

K. LLD applies exclusively to the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138. 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 LLDs higher than required, the reasons shall be documented in the "Radioactive Effluent Release Report."

L. For the Turbine Building Sump:

IF there is no detectable tritium in the secondary side before an outage, THEN tritium sampling and analyses is not required during an outage.

IF the steam generator gross gamma radioactivity does not exceed 5 x 1o- 7 µCi/ml, OR sump is directed to radwaste treatment, THEN the sampling and analysis schedule for all principal gamma, 1-131, Ce-144, noble gases, gross alpha, Sr-89, Sr-90 and Fe-55 are not required.

IF the release pathway is directed to yard drains, THEN the LLD for 1-131 shall be 1.5 x 10- 7

µCi/ml and for gross alpha 1 x 1o- 8 µCi/ml.

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M. For the RBCCW Sump:

IE the RBCCW Sump is directed to radwaste treatment or is not aligned to Long Island Sound, THEN sampling is not required.

IF the applicable batch gamma radioactivity is not greater than 5 x 1o- 7 µCi/ml, THEN sampling and analysis schedule for gross alpha, Sr-89, Sr-90, Fe-55 are not required.

N. Detectable tritium shall be used to estimate tritium releases to the atmosphere via the blowdown tank vent.

Table J.C. -3 Millstone Unit 3 Radioactive Liquid Waste Sampling and Analysis Program Liquid Release Sample 'fype and Minimum Analysis 'fype of Lower Limit Source Frequency Frequency Radioactivity of Detection Analysis (LLD)A

(µCi/ml)

A.Batch ReleaseB*

I.Condensate Polish- Grab sample prior Prior to each batch Principal Gamma 5 X lQ- 7 ing Facility Waste to each batch release release EmittersC.

Neutralization SumpE* I-131 1 X lQ- 6

2. Waste Test Tanks Ce-144 5 X lQ- 6 3.Low Level Waste 1 X lQ-S Tank Dissolved &

Entrained GasesK.

4.Boron Test Tanks H-3 1 X lQ-S 5.Steam Generator BulkD* Quarterly Gross alpha 1 X 10- 7 CompositeE,G.

Sr-89, Sr-90 5 X 10- 8 Fe-55 1 X lQ- 6 B.Continuous Release I.Steam Generator Daily Grab Sampler. Weekly Principal Gamma 5 X 10- 7 BlowdownH* CompositeE,G. EmittersC.

2.Service Water Ef- I-131 1 X lQ- 6 fluent1*

Ce-144 5 X lQ- 6 3.Turbine Building Monthly Grab Monthly Dissolved & 1 X lQ-S SumpsL Sample Entrained GasesK.

Weekly Grab or Com- Monthly H-3M. 1 X lQ-S posite CompositeE,G.

Weekly Composite Quarterly Gross alpha 1 X lQ- 7 CompositeE,G.

Sr-89, Sr-90 5 X lQ- 8 Fe-55 1 X lQ- 6 TABLE I.C.-3 TABLE NOTATIONS 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 "real" signal.

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

LLD= 4.66 Sb (E)(V)(2.22xl06)(Ye-MI)

Where:

LLD is the lower limit of detection as defined above (as µCi 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 is the number of transformations per minute per µCi

Y is the fractional radiochemical yield (when applicable)

,. is the radioactive 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 posteriori (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 recorded on the analysis sheet for the particular sample.

B. A batch release is the discharge of liquid wastes of a discrete volume from the tanks listed in this table. Prior to the sampling, each batch shall be isolated and at least two tank/sump volumes shall be recirculated or equivalent mixing provided. If the steam generator bulk can not be recirculated prior to batch discharge, a sample will be obtained by representative compositing during discharge.

C. The LLD will be 5 x 1o- 7 µCi/ml. The principal gamma emitters for which this LLD applies are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141. Ce-144 shall also be measured, but with an LLD of 5 x 10- 6

µCi/ml. 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 LLDs higher than required, the reasons shall be documented in the Radioactive Effluent Release Report.

D. For the Steam Generator Bulk:

IF the applicable batch gamma radioactivity is not greater than 5 x 1o- 7 µCi/ml, THEN the sampling and analysis schedule for gross alpha, Sr-89, Sr-90, Fe-55 are not required .

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E. For the Condensate Polishing Facility (CPF) waste neutralization sump:

IF there is no detectable tritium in the steam generators, THEN tritium sampling and analyses is not required.

IF the gross gamma radioactivity in the grab sample taken prior to release does not exceed 5 x 1o- 7 µCi/ml, THEN the sampling and analysis schedule for gross alpha, Sr-89, Sr-90 and Fe-55 are not required.

F. For Batch Releases and Steam Generator Slowdown only, 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.

H. For the Steam Generator Slowdown:

IF the steam generator gross gamma radioactivity does not exceed 5 x 1o- 7 µCi/ml, THEN the sampling and analysis schedule for all principal gamma, 1-131, Ce-144, noble gases, gross alpha, Sr-89, Sr-90 and Fe-55 are not required.

Steam Generator Slowdown samples are not required when blowdown is being recovered.

I. Daily grab samples shall be taken at least five days per week. For service water, daily grabs shall include each train that is in-service.

J. For the Service Water:

IF a weekly gamma analysis does not indicate a gamma radioactivity greater than 5 x1 o- 7

µCi/ml, THEN the sampling and analysis schedule for gross alpha, Sr-89, Sr-90, Fe-55 are not required.

K. LLD applies exclusively to the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138. 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 LLDs higher than required, the reasons shall be documented in the "Radioactive Effluent Release Report."

L. For the Turbine Building Sump:

IF the steam generator*gross gamma radioactivity does not exceed 5 x 1o- 7 µCi/ml, OR sunip is directed to radwaste treatment, THEN the sampling and analysis schedule for all principal gamma, 1-131, Ce-144, noble gases, gross alpha, Sr-89, Sr-90 and Fe-55 are not required.

IF the release pathway is directed to yard drains, THEN the LLD for 1-131 shall be 1.5 x 10- 7

µCi/ml and for gross alpha 1 x 1o-s µCi/ml.

M. Detectable tritium shall be used to estimate tritium releases to the atmosphere via the blowdown tank vent.

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2. Liquid Radioactive Waste Treatment

a. Dose Criteria for Equipment Functionality Applicable to All Millstone Units The following dose criteria shall be applied separately to each Millstone unit.

1) IF the radioactivity concentration criteria for the Unit 3 steam generator blowdown is exceeded with blowdown recovery not available to maintain releases to as low as reasonably achievable; or, IF any of the other radioactive waste processing equipment listed in Section b. are not functional, THEN doses due to liquid effluents from the applicable waste stream to unrestricted areas shall be projected at least once per 31 days in accordance with the methodology and parameters in Section II.C.2.

2) IF any of these dose projections exceeds 0.006 mrem to the total body or 0.02 mrem to any organ, THEN best efforts shall be made to return the processing equipment to service, or to limit discharges via the applicable waste stream.

3) IF an actual dose due to liquid effluents exceeds 0.06 mrem to the total body or 0.2 mrem to any organ AND the dose from the waste stream with processing equipment not functional exceeds 10% of one of these limits, THEN prepare and submit to the Commission a Special Report within 30 days as specified in Section 2.c.

b. Required Equipment for Each Millstone Unit Best efforts shall be made to return the applicable liquid radioactive waste treatment system equipment specified below for each unit to service or to limit discharge via the applicable waste stream if the projected doses exceed any of the doses specified above.

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1. Millstone Unit No. 1 Waste Stream Processing Equipment Spent Fuel Pool water One filter and one demineralizer

2. Millstone Unit No. 2 Waste Stream Processing Equipment Clean liquid Deborating ion exchanger (T11) OR Purification ion exchanger (TlOA or TlOB) OR Equivalent ion exchanger Primary demineralizer (T22 A or B) OR Equivalent demineralizer ALPS/AIM processing OR Secondary demineralizer (T23 A or B) OR Equivalent demineralizer Aerated liquid ALPS/AIM processing OR Demineralizer (T24) OR Equivalent demineralizer

3. Millstone Unit No. 3 Waste Stream Processing Equipment or Radioactivity Concentration High level ALPS processing (3LWS-SKD1) OR Demineralizer (3LWS-DEMN2) and Demineralizer filter (3LWS-FLT3) OR Demineralizer (LWS-DEMNl) and Demineralizer filter (LWS-FLTl)

Boron recovery Cesium ion exchanger (3BRS-DEMN1A or B)

Boron evaporator (3BRS-EV1)

Low level High level processing equipment Steam generator

Blowdown recovery when total gamma radioactivity exceeds SE- 7 blowdown µCi/ml or tritium exceeds 0.02 µCi/ml.

NOTE: The qualifier OR indicates that any of the equipment list_ed within the block would satisfy the processing requirement if functional.

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c. Report Requirement For All Three Millstone Units If required by Section 2.a.3), prepare and submit to the Commission a Special Report within 30 days with the following content:

Explanation of why liquid radwaste was being discharged without treatment, identification of any equipment not in service, and the reason for the equipment being out of service,

Action( s) taken to restore the equipment to service, and

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

I,

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Figure I.C. -1, "Reserved 1\

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Coiltainine:ntLeakoff Primary Drains Tank (Ti7) ,-*------

IonExchanger1 Coolant Waste.

I*******.*** I

. 1 lon~changer Coolant Waste

]Mixed Bed 4 1

.. -*- --~ *-

Receiver I Mixe~Bed I I (T22AJB) I Tanks (T14A/B) .. _ (J.2J1fll) _ .;.1 RCPs Bleedoff Equipment Aux Bldg&

Enclosure Bldg.

DrainSump Tank (175) **------*

1 Equipment Leako - - -.....~

._ . .--*r-*

ALPS/AlM :------------

C!eanliqui Radl\llonito (RM9049)

ToCoolantWaste

~ io;;'B{~;r- -----M ~

Samp!ing'.Drains. Receiver Tank (T14A!B)

Piping*& Aerated Waste 1 Aerated Waste E

ment Drains Drains Tanks 1------'---L. * (124)

_ *

_ .. J I Monitor

(")"20NB) Tank (T21)

Decontamination**

J Aerated. Liquid I* * ** * * .*.* *

Rad'Monitor (RM9116)

I Di:borating I

.Primary Coolant Letdown

.1 Ion ~1~)ger 1 2Purification 1

-=----~~I 7 Volume Control Tank (T5)

To* Primary Coolant Loop Condensate

.Polishing Facility Waste Neut: Sump

& R I

I IonExchangers (TlOA/B) I Rad Monitor S/ G Blowdown . (CND245)

.,;S;t;::e,:am~G::.*e:::ne:::::,ra::;t:;;:o,:.r_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~,,~I or Quench Tonk Blowdo.wn Turbine Bldg. FloorDrains*

Niantic Bay

~

(T45) 11 SIG Blowi:lown Rad Monitor, (RM4262)

~ - - - t o l Quarry

Turbine Bldg floor drains normally to stomidrains.

..........:=

Compone%lt included* in*ramvaste treatment*

Drains may be diverted to theTadwaste treatment system. ~ ........ ! equipment .requirement

- HP de con facility sump is.coll'ectedin°totes and shipped offsite.

Filter ---------,I Containment Bldg Sump*!** r--i---, ---------

Aux Bldg Sump* High Level Waste Drain 1 Filter I :

-~(LWS-FLT3)~-~ (LWS-DEMN2)~

Demin :

Waste Test Demin Filter l------~

I ---------------- --------- I I I Reactor Pl ant Sample Sinks Tank

-1 Tank (LWS DEMNl)M (LWS-FLT!) I (LWS-TKl A/B) 1 ALPS processing (LWS-SKDl) I LWS-TK3A/B [___ -____ . *-------2 Lab Wastes* I I

--1 MiscHigh-Level Waste To Primary

ViaReactor Plant Aerated Drain System Volume Grade Water

'\

. ,. (J) I Letdown Demin Control Tank B oron Recovery

-+'------ Boron Boron (DEMNIA/B) Tank Test Tank 0 -----~ Degassilier Dem ineralizer

., --~-"1? i (BRS-TKJA/B) (BRS-TK 2A/B) RS-DEMN2A/B)

\I (GWS-GRU!)

Demin

/] (DEMIN2 A/B)

I r----------,

'-i' Cesium : Boron Filter

) ~----->

/ z (.'-- Ion Exchanger I

I : Evaporator 1

1---- (BRS-FLT3)

I

.::---~ I Reactor Plant Gaseous Drains (BRS-DEMNl A/B) 1 ~- - - (EV!) ___ :

,; Filter (FLT 4A/B)

. . ;, L~-...

/ 0 ----- Low-Level

~/~,.~-~ j

\I Waste Drain

Miscellaneous Low-Level Waste Tank (LWS-TK4A/B) 3LWS-RE70)

Niantic Bay

_T_u_rb_in_e_P_l_an_t_L_e_ak_ag_e_to_s_u_m_P_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ viaDSN 006 3PAS-EE50

Service Water Discharge CPF Waste Neut Sump (TklO&l l) 3CND-RE07 3SSR-RE08 Steam Generator Blowdown (Open Cycle)

Component included in (11111*-*-

Quany

____ i = radwaste treatment equipment requirement

I.D. Gaseous Effluents

1. Gaseous Effluent Sampling and Analysis Program Radioactive gaseous wastes shall be sampled and analyzed in accordance with the program specified in Table I.D. -1 for Millstone Unit No. 1, Table I.D.-2 for Millstone Unit No. 2, and Table I.D.-3 for Millstone Unit No. 3.

The results of the radioactive analyses shall be input to the methodology of Section II to assure that offsite doses are maintained within the limits of Radiological Effluent Controls (Section III.D.2. for Millstone Unit No. 1,Section IV.D.2. for Millstone Unit No. 2, and Section V.D.2. for Millstone Unit No. 3).

Table I.D. -1 Millstone Unit 1 Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Release Sample 'Iype and Minimum 'Iype of Radioactivity Lower Limit Point or Source Frequency8 Analysis Analysis of Detection Frequency (LLD)A

(µCi/ml)

A.Spent Fuel Pool MonthlyD,F - Gaseous Monthly Kr-85 1 X lQ- 4 Island Vent Grab Sample H-3G 1 X 10- 6 Twice per month Principal Gamma 1 X lQ-ll ContinuousE. EmittersC. - (with half Particulate Sample lives greater than 8 days)

ContinuousE. Quarterly Sr-90, Gross alpha 1 X lQ-ll Particulate Sample Composite ContinuousE. Continuous Kr-85 1 X lQ- 6 Noble Gas Monitor B.Balance of Twice per month Principal Gamma 1 X 10-ll Plant Vent EmittersC. - (with half ContinuousE. lives greater than 8 Particulate Sample days)

Quarterly Sr-90, Gross alpha 1 X 10-ll Composite Grab sample of Reactor Prior to processing H-3 1 X 10-S Bldg evaporator staging of each batch tank prior to processing Table I.D.-1 TABLE NOTATIONS A. The lower limit of detection (LLD) is defined in Table Notations, Item a, of Tables I.C.-1, I.C.-2, or I.C.-3.

B. Samples not required when Release Point is not in use.

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C. For particulate samples, the LLD will be 1 x 1o- 11 µCi/cc. The principal gamma emitters for which this LLD applies are exclusively the following radionuclides: Mn-54, Co-60, Zn-65, Cs-134, Cs-137, and Ce-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 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 LLDs higher than required, the reasons shall be documented in the Radioactive Effluent Release Report.

D. IF there is an unexplained increase of the SFPI Vent noble gas monitor of greater than a factor of ten, OR the monitor reads 8.SE-5 µCi/cc or greater, THEN sampling and analysis shall also be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

E. Continuous when exhaust fans are in operation.

F. When Spent Fuel Pool Island ventilation is shutdown and ventilation of Spent Fuel Poo.1 Island is exhausted to Balance of Plant Vent, the monthly gaseous grab sample shall be obtained from the Balance of Plant Vent.

G. Tritium analysis of vent grab sample may be replaced by a calculation of tritium released from the spent fuel pool.

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Table I.D.-2 Millstone Unit 2 Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Sample 'Iype and Minimum 'Iype of Lower Limit Release Point Frequency Analysis Radioactivity of Detection or Source Frequency Analysis (LLD)A (µCi/ml)

A.Batch Release Principal Gamma 1 X lQ- 4 I.Waste Gas Stor- Gaseous Grab Prior to each Each Tank Discharge EmittersB age TankH Waste Gas Tank Discharge H-3 1 X 10-o B.Containment&Aux Building Releases

1. Containment Gaseous Grab of purges 1. Prior to Each Principal Gamma 1 X lQ- 4 and vents Purge EmittersB

1. Prior to Each Purge1 2. Every two weeks

2. Every two weeks for for Venting Venting1 Monthly H-3 1 X lQ-O Continuous Particulate for Weekly Gamma emitters NA Open Containment Equip- for 1/2 hr count ment Hatch during Outage (I-131, others with half-life greater than 8 days)

Continuous Charcoal for Weekly I-131 andl-133 for NA Open Containment Equip- one hour count ment Hatch during Outage C.Continuous Release 1.Vent Monthly - Gaseous Grab Monthly'---, u. Principal Gamma 1 X lQ- 4 (RM8132B) SampleC.,G. EmittersB H-3v 1 X lQ-O 2.Millstone Continuous Charcoal Sam- Weekly I-131 1 X lQ-lL Stack pleD.,F. I-133 1 X lQ-lO (RM8169-1) Continuous Particulate Weekly Principal Gamma 1 X lQ-ll SampleD.,F. EmittersB -

(I-131, others with half lives greater than 8 days)

Continuous Particulate Quarterly Composite Sr-89, Sr 1 X lQ-ll Sample0

Gross alpha 1 X lQ-ll Continuous Noble Gasu. Continuous Monitor Noble Gases - 1 X lQ-O Gross Radioactivity TABLE I.D.-2 TABLE NOTATIONS A. The lower limit of detection (LLD) is defined in Table Notations, Item a, of Tables I.C.-1, I.C.-2, or I.C.-3.

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B. For gaseous samples, the LLD will be 1 x 1o- 4 µCi/cc and for particulate samples, the LLD will be 1 x 10-11 µCi/cc. The principal gamma emitters for which these LLDs 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, Fe-59, Co-58, Co-60, Zn-65, Mo-99, 1-131, 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 LLDs higher than required, the reasons shall be documented in the "Radioactive Effluent Release Report."

C. IF there is an unexplained increase of the Millstone Stack or Unit 2 Vent noble gas monitor of greater than 50%, THEN sampling and analysis for principal gamma emitters shall be

performed within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Sampling and analysis is not required if the monitor reading has returned to within 20% of the average reading prior to the increase.

IF the Millstone Stack or Unit 2 Vent noble gas monitor increased greater than 50% and then has decreased to within 20% of the average reading prior to collecting a sample representative of the elevated reading, THEN an estimate of radioactivity released during the period of elevated reading shall be made.

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

E. RESERVED F. Samples shall be changed at least once per seven days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing.

For Unit 2 vent only The sampling frequency shall be increased to daily following each reactor shutdown, reactor criticality after shutdown, or thermal power change exceeding 15% of rated thermal power as defined in Technical Specification within a one hour period, if one or both of the following has occurred:

1) The Dose Equivalent 1-131 concentration in the reactor coolant has increased by more than a factor of three above the concentration that existed during steady state, full power operation prior to the power transient.

2) The noble gas monitor, RMS 1328, has increased more than a factor of three relative to the radiation monitor reading that existed during steady state, full power operation prior to the power transient.

Analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. For daily samples, the LLDs may be*

increased by a factor of 10.

Daily sampling shall be maintained for seven days or until such time when both conditions (1) and (2) are not satisfied, whichever is shorter.

G. IF the refueling cavity is flooded, THEN grab samples for tritium shall be taken weekly. The grab sample shall be taken from the Millstone Stack or vent where the containment ventilation is being discharged at the time of sampling.

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H. Waste Gas Storage Tanks are normally released on a batch basis via the Millstone Stack.

However, for the purpose of tank maintenance, inspection, or reduction of oxygen concentration, a waste gas tank may be vented or purged with nitrogen and released to the environment via the normal or alternate pathway using one of the following methods:

Method A: Without a permit provided the following conditions are met:

(1) The tank has been previously discharged with a permit.

(2) The current tank pressure is less than 5 PSIG.

(3) No radioactive gases have been added to the tank since the previous discharge from the tank.

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

(5) Prior to initiation of the vent or purge, a sample of the gas in the tank will be taken and analyzed for any residual gamma emitters and tritium. The tank may be released if:

a) Tank radioactivity is less than 1% of the radioactivity released in the previous batch release from the tank, or less than 1% of the radioactivity released to date for the calendar year, and b) the radioactivity of Kr-85 and Xe-133 is less than 0.01 Ci and the radioactivity of all other gases is less than 0.001 Ci.

Method B: With a permit provided valve lineups are verified to ensure that no radioactive waste gases will be added to the tank.

I. 1E compared to the radioactivity at the time of the air sample, a Radiation Monitor RM8123 or RM8262 gas channel increases by a factor of two, THEN a new containment air sample shall be taken.

1E containment noble gas radioactivity exceeds 1E-6 µCi/cc as indicated by the last grab sample, THEN sampling frequency shall be increased to weekly until such time that the radioactivity is less than 1E-6 µCi/cc.

J. During an outage a sample is only required prior to the initial purge.

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Table I.D. -3 Millstone Unit 3 Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Sample 'fype and Minimum 'fype of Radioactivity Lower Limit Release Point Frequency Analysis Analysis of Detection or Source Frequency (LLD)A. (µCi/ml)

A. Containment Release I.Containment Gaseous, particulate and Same as sample fre- Principal gamma 1 X 10- 4 charcoal grab prior to quency. emittersB*

each drawdown (via air ejector)

Gaseous grab prior to Same as sample fre- On charcoal sample: 1 X lQ-lk each purgeH. quency. I-131 1 X lQ-10 I-133 Gaseous Grab every two On particulate sample: 1 X lQ-ll weeks for vents (i.e., re- Principal gamma leases to maintain emittersB* - (I-131, oth-sub-atmospher ic ers with half lives greater pressure via containment than 8 days) vacuum pump)1-Monthly for purge, H-3 1 X lQ-O vents, and drawdowns Continuous particulate Weekly Gamma emitters for 1/2 NA for open containment hour count (I-131, others equipment hatch during with half-life greater than 8 outages. days)

Continuous i;:harcoal for Weekly I-131 and I-133 for one NA open containment , hour count equipment hatch during outages.

B.Continuous Release I.Unit 3 Ventila- Monthly - Gaseous MonthlyL-., u. Principal gamma 1 X 10- 4 tion Vent Grab SampleC., G. emittersB *

(HVR-RElOB) H-31.J 1 X 10-o 2.Engineered Continuous charcoal Weekly I-131 1 X lQ-1.t Safeguards sampleD.,F. I-133 1 X lQ-10 Building Continuous particulate (HVQ-RE49) sampleD.,F.

Weekly Principal gamma 1 X lQ-ll emittersB* - (I-131, others 3 .Millstone with half lives greater than 8 Stack via days)

SLCRS Continuous particulate Quarterly composite Sr-89, Sr-90 1 X lQ-ll (HVR- sampleD* Gross alpha 1 X 10-ll RE19B)

Continuous noble gasu. Continuous Noble gases - gross 1 X 10-o monitor radioactivity TABLE I.D.-3 TABLE NOTATIONS A. The lower limit of detection (LLD) is defined in Table Notations, Item a, of Tables I.C. -1, I.C. -2, or I.C.-3.

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B. For gaseous samples, the LLD will be 1 x 1o-4 µCi/cc and for particulate samples, the LLD will be 1 x 10-11 µCi/cc. The principal gamma emitters for which these LLDs 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, Fe-59, Co-58, Co-60, Zn-65, Mo-99, 1-131, 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 LLDs higher than required, the reasons shall be documented in the Radioactive Effluent Release Report.

C. IF there is an unexplained increase of the Unit 3 ventilation vent or SLCRS noble gas monitor of greater than 50%, THEN sampling and analysis for principal gamma emitters shall be performed within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Sampling and analysis is not required if the monitor reading has returned to within 20% of the average reading prior to the increase.

IF the SLCRS or Unit 3 Vent noble gas monitor increased greater than 50% and then has decreased to within 20% of the reading prior to collecting a sample representative of the elevated reading, THEN an estimate of radioactivity released during the period of elevated reading shall be made.

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

E. RESERVED F. Samples shall be changed at least once per seven days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing.

For Unit 3 Vent only:

The sampling frequency shall be increased to daily following each reactor shutdown, reactor criticality after shutdown, or thermal power change exceeding 15% of rated thermal power as defined in Technical Specification within a one hour period, if one or both of the following has occurred:

1) The Dose Equivalent 1-131 concentration in the reactor coolant has increased by more than a factor of three above the concentration that existed during steady state, full power operation prior to the power transient.

2) The noble gas monitor, HVR-RE1 OB, has increased more than a factor of three relative to the radiation monitor reading that existed during steady state, full power operation prior to the power transient.

Analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. For daily samples, the LLDs may be increased by a factor of 10.

Daily sampling shall be maintained for seven days or until such time when both conditions (1) and (2) are not satisfied, whichever is shorter.

G. IF the refueling cavity is flooded, THEN grab samples for tritium shall be taken weekly from the ventilation vent.

I. 1E, compared to the radioactivity at the time of the air sample, Radiation Monitor CMS22 gas channel increases by a factor of two, THEN a new containment air sample shall be taken.

!E containment noble gas radioactivity exceeds 1E-6 µCi/cc as indicated by the last grab sample, THEN sampling frequency shall be increased to weekly until such time that the radioactivity is less than 1E-6 µCi/cc.

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2. Gaseous Radioactive Waste Treatment

a. Dose Criteria for Equipment Functionality Applicable to All Millstone Units The following dose criteria shall be applied separately to each Millstone unit.

1) IF any of the radioactive waste processing equipment listed in Section 2.b. are not functional or are being bypassed, THEN doses due to gaseous effluents from the untreated waste stream to unrestricted areas shall be projected at least once per 31 days in accordance with the methodology and parameters in Section II.D.4.

For each waste stream, only those doses specified in Section II.D.4.

need to be determined for compliance with this section.

2) IF any of these dose projections exceed 0.02 mrad for gamma radiation, 0.04 mrad for beta radiation or 0.03 mrem to any organ due to gaseous effluents, THEN best efforts shall be made to return the processing equipment to service.

3) IF actual doses exceed 0.2 mrad for gamma radiation, 0.4 mrad for beta radiation or 0.3 mrem to any organ AND the dose from a waste stream with equipment not functional exceed 10% any of these limits, THEN prepare and submit to the Commission a report as specified in Section I.D.2.c.

b. Required Equipment for Each Millstone Unit Best efforts shall be made to return the gaseous radioactive waste treatment system equipment specified below for each unit to service if the projected doses exceed any of doses specified above. For the Unit 2 gas decay tanks, the tanks shall be operated to allow enough decay time of radioactive gases to ensure that the Radiological Effluent Control dose limits are not exceeded.

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1. Millstone Unit No. 1 Waste Stream Processing Equipment None Specified None required

2. Millstone Unit No. 2 Waste Stream Processing Equipment Gaseous Radwaste Five (5) gas decay tanks Treatment System One waste gas compressor Ventilation Exhaust Auxiliary building ventilation HEPA filter (L26 or L27)

Treatment System Containment purge HEPA filter (L25)

Containment vent HEPNcharcoal filter (L29 A or B)

3. Millstone Unit No. 3 Waste Stream Processing Equipment or Radioactivity Concentration Gaseous Radwaste Charcoal bed adsorbers Treatment System One HEPA filter

c. Report Requirement For All Three Millstone Units If required by Section I.D.2.a.3), prepare and submit to the Commission a Special Report within 30 days with the following content:

Explanation of why gaseous radwaste was being discharged without treatment, identification of any equipment out of service, and the reason for being out of service,

Actions taken to restore the nonfunctional equipment to service, and

Summary description of actions taken to prevent a recurrence.

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Figure I.D.-1, "Simplified Gaseous Effluent Flow Diagram Millstone Unit One"

-c-- * * ***** ** ****** .... = generalized air flow Spent Fuel Pool SFPI - - - ~

Vent Island (SFPI)

RM-SFPl-02 Reactor Balance of Plant Vent Building S = particulate .__ ______ Evaporator sampler

Vent plenum :

'--~-----~----

Turbine Building

-C******** ............ . Radwaste Building

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Figure I.D.-2, "Simplified Gaseous Effluent Flow Diagram Millstone Unit 1\vo" Main i-----iM.Air ~jector Unit2 Condenser Enclosure Building loofVen Millstone Stack

~-----, ~------,

I I I

\Vaste Gas 1 1 1 Decay I Tanks Proce~ing 1I Waste Gas: 1 T*IBPA Svstem ICompre~or~ (TJ 9 ,vni \Lli)

' __:__,,,,, ~----..--. CID/Elf)_

,.-. (F-lA/B) I 1 1

I I I I I I WRGM

';_ _____ * ~------..! R.M-8169 Waste Gas Containmen l .- -- - - --- - - - - ~ Rad Monitor Vent HEPA/Charcoal ...

_ _ _ _,..

Adsorber Unit (L29AIB):

I I A _A _______ ..I Enclosure Building/ I1 II;;: I- - - - - -I Containment Purge 'i 1* I I

' I HEPA I I II (L25) I, - - - - - - - - - - - - - - - ,

I I I

- I Stearn Generator Fuel : i-----1 Blowdown Quench Building I I I (Aux 1 Tank Vent ____*_ _ _...,* HEPA ~- - - - - - - - - ~

Building I (127) 38'6) I I

-----l Steam Generator Blowdo'N"Il Tank Vent

- - - - - - - - - - - - - - - - - - - + Enclosure 13ldg RoofVent r-----1 I I Aux Bldg I I

- - - - - - - - - - - - - - - - -

HEPA * - - - - - - - - - - - - - - - ' Vent (L26) : Rad Monitor I (RM8132A/B)

L-----*

Turbine Bldg

- - - - - - - - - - - - - - - - - - - - - - - - - - - -

TurbincBldgRoofVenl

These flow palhs used during an accident.

I I 1

I 1

I

= Component included in treatment equipment requirement I I

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Figure I.D.-3, "Simplified Gaseous Effluent Flow Diagram Millstone Unit Three" Atmosphere Reactor Plant Ventillalion Vent Service Building 1 - - - - - - - - - - - - - - -.. . . . ._

< /

R Ventilation Vent Rad Monitor (3HVR*RE10B)

J HEPA/Charcoal (3HVR"FLT2A/B)

Fuel Building RCS Millstone Letdown Stack Auxiliary Building Gaseous Waste HEPA/Charcoal System (3HVR*FLT1A/B)

I I Waste Disposal : Charcoal Beds :

Building : (3GWS'ADS1NB) :

I

~-------------l I I GWSRad

', : HEPA :

Monitor

(3GWS*FLT1A/B):

w Containment 3GWS-RE48 SLCRS Rad L-------------t Structure Monitor (3HVR*RE19B)

Secondary Containments

HEPA & Charcoal I (SLCRS} ____. (3HVR"FLT3A/B) 1------------------~

Containment Vacuum System Drawdown L....----*- Atmosphere Main Condenser Air Ejector ESF Building ESF Building Exhaust en om or R (3HVQ-RE49)

Turbine Building I Atmosphere SG Blowdown I -

Tank (3BDG-TK1)

-- Turbine Building Roof Exhausters CPF Turbine Gland Seal Stearn

~----1 Cond Exhaust I I I Component included in treatment equipment requirement I

~----'

These flow paths used during an accident ** Releases from Mechanical Rooms A-D not monitored

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I.E. Radiological Environmental Monitoring

1. Sampling 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 I.E. -1 for the locations shown Table I.E.-2. 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 I.El. It is recognized that, at times, it may not be possible or practicable to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. 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.

If the level of radioactivity in an environmental sampling medium at one or more of the locations specified in Table I.E. -2 exceeds the report leveis of Table I.E. -3 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from receipt of sample results, a Special Report which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of Table I.E. -3 to be exceeded. When more than one of the radionuclides in Table I.E.-3 are detected in the sampling medium, this report shall be submitted if:

concentration (1) concentration (2)

~---'-- + + ... ~ 1.0 reporting level (l) reporting level (2)

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When radionuclides other than those in Table I.E.-3 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 Radiological Effluent Controls (Sections III.D.l.b.,

III.D.2.b., or III.D.2.c. for Unit 1; Sections IV.D.l.b., IV.D.2.b., or IV.D.2.c.

for Unit 2; and Sections V.D.l.b., V.D.2.b., or V.D.2.c. for Unit 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 Annual Radiological Environmental Operating Report.

The detection capabilities required by Table I.E.-4 are state-of-the-art for routine environmental measurements in industrial laboratories. 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 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.

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Table I.E. -1 Millstone Radiological Environmental Monitoring Program Exposure Pathway and/or No. of Sampling and Collection 'fype and Frequency of Sample Locations Frequency Analysis l.Gamma Dose - 39(a) Quarterly Gamma Dose - Quarterly Environmental TLD 2.Airbome Particulate 8 Continuous sampler - filter Gross Beta - Every two weeks change every two weeks Gamma Spectrum - Quarterly on composite (by location), and on indi-victual sample if gross beta is greater than lOx the mean of the control sta-tion's gross beta results 3.Airborne Iodine 8 Continuous sampler - I-131 - Every two weeks canister change every two weeks 4.Vegetation 5 One sample near middle and Gamma Isotopic on each sample one near end of growing season 5.Reserved 6.Sea Water 2 Continuous sampler with a Gamma Isotopic & Tritium on each monthly collection at indica- sample tor location. Quarterly at control location - Compos-

ite of 6 weekly grab samples 7.Well Water 6 Semiannual Gamma Isotopic & Tritium on each sample 8.Bottom Sediment 5 Semiannual Gamma Isotopic on each sample 9.Soil 3 Annually Gamma Isotopic on each sample 10.Fin Fish-( edible portion) 2 Semi- annual Gamma Isotopic on each sample 11.Aquatic flora 4 Quarterly Gamma Isotopic on each sample 13.Clams (edible portion) 2 Semi- annual Gamma Isotopic on each sample 14.Lobsters (edible portion) 2 Semi- annual Gamma Isotopic on each sample (a) Two or more TLDs or TLD with two or more elements per location.

(b) Not required during 1st quarter.

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Table I.E. -2 Environmental Monitoring Program Sampling Locations The following lists the environmental sampling locations and the types of samples obtained at each location. Sampling locations are also shown on Figures I.E.-1 and I.E.-2:

Location Direction & Dis- Sample Types tance from Re-No* Name lease Point**

1-I Onsite - NAP Parking Lot North 0.6Mi,NNW TLD, Air Particulate, Iodine, Vegetation 2-I Onsite - Weather Shack 0.3 Mi, S TLD, Air Particulate, Iodine 3-I Onsite - Bird Sanctuary 0.3 Mi, NE TLD, Air Particulate, Iodine, Soil 4-I Onsite - Albacore Drive 1.0 Mi, N TLD, Air Particulate, Iodine, Soil 5-I Onsite - Quarry East 0.1 Mi, SSE TLD 6-I Onsite - Quarry Discharge 0.3 Mi, SSE TLD 7-I Onsite - Environmental Lab Dock 0.3 Mi, SE TLD 8-I Onsite - Environmental Lab 0.3 Mi, SE TLD 9-I Onsite - Bay Point Beach 0.4 Mi, W TLD 10-I Waterford-Goshen Fire Dept. 1.2 Mi, E TLD, Air Particulate, Iodine, Vegetation 11-I Great Neck Country Club 1.6 Mi, ENE TLD, Air Particulate, Iodine 13-C Mystic, CT 11.5Mi,ENE TLD 14-C Ledyard, CT 12.0 Mi, NE TLD, Soil 15-C Norwich, CT 14.0 Mi, N TLD, Air Particulate, Iodine 16-C Old Lyme, Halls Rd. 8.8 Mi, W TLD 17-I Site Boundary 0.5Mi, NE Vegetation 25-I Fruits & Vegetables Within 10 Miles Vegetation 26-C Fruits & Vegetables Beyond 10 Mi Vegetation 27-I East Lyme - Police Station l.7Mi, WNW TLD, Air Particulate, Iodine 28-I Two Tree Island 0.8 Mi, SSE Fish 1 29-I West Jordan Cove :;::;0.5 Mi, ENE to Clams, Fish 1 , Aquatic Flora ESE 31-I Niantic Shoals 1.8 Mi, NW Bottom Sediment, Clams 32-I Vicinity of Dischargez Bottom Sediment, Fish1, Seawater, Aquatic Flora 33-I Seaside Point 1.8 Mi, ESE Bottom Sediment 34-I Thames River Yacht Club 4.0Mi,ENE Bottom Sediment 35-I Niantic Bay :;::; 0.5 Mi, SSW to Lobster, Fish, Aquatic Flora w

36-C Black Point 2.7Mi, SW Aquatic Flora 37-C Giant's Neck 3.5Mi, WSW Bottom Sediment, Seawater 41-I Waterford - Myrock Avenue 3.2Mi, ENE TLD 42-I East Lyme - Billow Road 2.4Mi, WSW TLD

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Table I.E. -2, Cont.

Location Direction & Dis- Sample Types tance from Re-No* Name lease Point**

43-I East Lyme - Old Black Point Rd. 2.6Mi, SW TLD 44-I Onsite - Schoolhouse O.lMi,NNE TLD 45-I Onsite Access Road #1 0.5Mi,NNW TLD 46-I Old Lyme - Hillcrest Rd. 4.6Mi, WSW TLD 47-I East Lyme - W. Main St. 4.5Mi, W TLD 48-I East Lyme - Corey & Roxbury Rd. 3.4Mi, WNW TLD 49-I East Lyme - Society Rd. 3.6Mi,NW TLD 50-I East Lyme - Manwaring Rd & 2.1 Mi, W TLD Terrace Ave.

51-I East Lyme - Smith Ave. l.5Mi, NW TLD 52-I Waterford - River Rd. l.lMi, NNW TLD 53-I Waterford - Gardiners Wood Rd. 1.4 Mi, NNE TLD 55-I Waterford - Magonk Point 1.8 Mi, ESE TLD 56-I New London - Ocean & Mott Ave. 3.7 Mi, E TLD 57-I New London - Ocean Ave. 3.6 Mi, ENE TLD 59-I Waterford - Miner Ave. 3.4 Mi, NNE TLD 60-I Waterford - Parkway South & 4.0Mi, N TLD Cross Rd.

61-I Waterford - Oil Mill & Boston Post 4.3Mi,NNW TLD Rd.

62-I East Lyme - Columbus Ave. l.9Mi, WNW TLD 63-I Waterford - Gradiners Wood & 0.8 Mi, NE TLD Jordon Cove Rd.

64-I Waterford - Shore Rd. 1.1 Mi,ENE TLD 65-I Waterford - Boston Post Rd. 3.2Mi,NE TLD 71-I Onsite well Onsite Well water 72-I Onsite well Onsite

Well water 79-I Onsite well Onsite Well water 80-I Onsite well Onsite Well water 81-I Onsite well Onsite Well water 82-I Onsite well Onsite Well water 89-C Aquatic Background Beyond 4 Mi. Of Lobster discharge 1Fish to be sampled from one of three locations -28, 29, or 32.

2 Vicinity of discharge includes the Quarry and shoreline area from Fox Island to western point of Red Barn Recreation Area and offshore out to 500 feet.

I = Indicator; C = Control.

- = The release points are the Millstone Stack for terrestrial locations and the end of the quarry for aquatic location.

NOTE: Environmental TLDs also function as accident TLDs in support of the Millstone Emergency Plan.

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Table I.E. -3 Reporting Levels For Radioactivity Concentrations In Environmental Samples Analysis Water Airborne Fish Shellfishc. Milk Vegetables (pCi/1) Particulate (pCi/g, wet) (pCi/g, wet) (pCi/1) (pCi/g, wet) or Gases (pCi/m3)

H-3 20 oooA Mn-54 1,000 30 140 Fe-59 400 10 60 Co-58 1,000 30 130 Co-60 300 10 50 Zn-65 300 20 80 Zr-95 400 Nb-95 400 Ag-llOm 8 30 1-131 20B. 0.9 0.2 1 3 0.1 Cs-134 30 10 1 5 60 1 Cs-137 50 20 2 8 70 2 Ba-140 200 300 La-140 200 300 A. 20,000 pCi/1 for drinking water samples. (This is 40 CFR Part 141 value.) For non-drinking water pathways, a value of 30,000 pCi/1 may be used.

B. Reporting level for 1-131 applies to non-drinking water pathways (i.e., seawater). If drinking water pathways are sampled, a value of 2 pCi/1 is used.

C. For on-site samples, these values can be multiplied by 3 to account for the near field dilution factor

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Table I.E.-4 Maximum Values For Lower Limits Of Detection (LLD)A*

Analysis Water Airborne Fish Milk Food Sediment (pCi/1) Particulate Shellfish (pCi/1) Products and Soil or Gases (pCi/g, wet) and Vegeta- (pCi/g, dry)

(pCi/m3 ) tion (pCi/g, wet) gross beta 1 X 10-z H-3 2000D*

Mn-54 15 0.130 Fe-59 30 0.260 Co-58, 60 15 0.130 Zn-65 30 0.260 Zr-95 30 Nb-95 15 I-131 15c. 7 X 10- 2 0.093 1 0.06B.

Cs-134 15 5 X 10- 2 0.130 15 0.060 0.150 Cs-137 18 6 X lQ- 2 0.150 18 0.080 0.180 Ba-140 60C. 70 La-140 15c. 25 TABLE NOTATIONS Table I.E. -4 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 "real" signal.

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

LLD= 4.66 Sb (E)(V)(2.22)(YcicLl1)

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 is the number of transformations per minute per pCi

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Y is the fractional radiochemical yield (when applicable)

i is the radioactive decay constant for the particular radionuclide

At is the elapsed time between midpoint of sample collection and midpoint of counting time (or end of the sample collection period) and time of counting.

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.

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 in the Annual Radiological Environmental Operating Report.

B. LLD for leafy vegetables.

C. From end of sample period.

D. If no drinking water pathway exists (i.e., seawater), a value of 3,000 pCi/1 may be used.

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2. Land Use Census A land use census shall be conducted annually during the growing season to identify; (1) changes in the use of unrestricted areas, (2) receptor locations, and (3) new exposure pathways to permit modifications in monitoring programs for evaluating doses to individuals from principal pathways of exposure. The land use census shall identify the location of the nearest resident, nearest garden, and any other land-based food sources in each of the meteorological land sectors within a distance of five miles. Sectors SE, SSE, S, and SSW, are not land sectors because they are over water.

When a land use census identifies a food source location other than the nearest garden in a sector which yields a calculated dose greater than the dose currently being calculated in the off-site dose models, make the appropriate changes in the sample location used.

For each type of food source (milk, fruits, etc.) other than the nearest garden in a sector, when a land use census identifies a location which has a D/Q 20%

or greater than the D/Q for a current indicator location begin sampling from the new location within 30 days.

Sample location changes for food sources other than nearest garden shall be noted in the Annual Radiological Environmental Operating Report.

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

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.

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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I.F. Report Content

1. Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report shall include 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 radioactivity from plant operation in the environment. Any radioactivity from plant operation detected in the environment shall be compared to levels of radioactivity expected based on the effluent monitoring program and modelling of environment exposure pathways for the purpose of verifying the accuracy of the program and modelling. If levels of radioactivity are detected that result in calculated dos~s greater than 10CFR.50 Appendix I Guidelines, the report shall provide an analysis of the cause and a planned course of action to alleviate the cause.

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 control locations.

3) Lower li;rnit of detection (LLD).

4) Mean and range of all indicator locations together.

5) Mean and range of all control locations 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 non -routine 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 Interlaboratory Comparison Data required by Section I.E.3. of this manual.

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The report shall include the results of the land use census required by Section I.E.2. of this manual.

2. Radioactive Effluent Release Report The Radioactive Effluent Release Report (RERR) shall include quarterly quantities of and an annual summary of radioactive liquid and gaseous effluents released from the unit in the Regulatory Guide 1.21 (Rev. 1, June 1974) format. Radiation dose assessments for these effluents shall be provided in accordance with 10 CPR 50.36a and the Radiological Effluent Controls. An annual assessment of the radiation doses from the site to the most likely exposed REAL MEMBER OF JHE PUBLIC shall be included to demonstrate conformance with 40 CPR 190. Gaseous pathway doses shall use meteorological conditions concurrent with the quarter of radioactive gaseous effluent releases. Doses shall be calculated in accordance with the Offsite Dose Calculation Manual. The licensee shall maintain an annual of the hourly meteorological data (i.e., wind speed, wind direction and atmospheric stability) either in the form of a listing or in the form of a joint frequency distribution. The licensee has the option of submitting this annual meteorological summary with the RERR or retaining it and providing it to the NRC upon request. The RERR shall be submitted prior to May 1 of each year for the period covering the previous calendar year.

The RERR shall include 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:

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

solidification agent (e.g., cement)

total curies

total volume and typical container volumes

principal radionuclides (those greater than 10% of total radioactivity)

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

The RERR shall include a list of all abnormal releases of radioactive gaseous and liquid effluents (i.e., all unplanned or uncontrolled radioactivity releases, including reportable quantities) from the site to unrestricted areas.

Refer To MP-22-REC-REF03, "REMODCM Technical Information Document (TID)," for guidance on classifying releases as normal or

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abnormal. The following information shall be included for each abnormal release:

total number of and curie content of releases (liquid and gas)

a description of the event and equipment involved

cause( s) for the abnormal release

actions taken to prevent recurrence

consequences of the abnormal release Changes to the MP REC-BAPOl, "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 RERR for the period in which the changes were made.

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SECTION II.

Offsite Dose Calculation Manual (ODCM)

For the Millstone Nuclear Power Station Nos. 1, 2, & 3 Docket Nos. 50-245, 50-336, 50-423

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SECTION II. OFFSITE DOSE CALCULATION MANUAL (ODCM)

II.A. Introduction The purpose of the Offsite Dose Calculation Manual (Section II of the REMODCM) is to provide the parameters and methods to be used in calculating offsite doses and effluent monitor setpoints at the Millstone Nuclear Power Station. Included are methods for determining maximum individual whole body and organ doses due to liquid and gaseous effluents to assure compliance with the regulatory dose limitations in 10 CFR 50, Appendix I. Also included are methods for performing dose projections to assure compliance with the liquid and gaseous treatment system functionality sections of the Radiological Effluent Monitoring Manual (REMM - Section I of the REMODCM). The manual also includes the methods used for determining quarterly and annual doses for inclusion in the Radioactive Effluent Release Report.

The bases for selected site-specific factors used in the dose calculation methodology are provided in MP-22-REC-REF03, "REMODCM Technical Information."

Another section of this manual discusses the methods to be used in determining effluent monitor alarm/trip setpoints to be used to ensure compliance with the instantaneous release rate limits in Sections III.D.2.a., IV.D.2.a., and V.D.2.a.

This manual includes the methods to be used in performance of the surveillance requirements in the Radiological Effluent Controls of Sections III, rv, and V.

Appendix A, Tables App.A-1 provide a cross-reference of effluent requirements and applicable methodologies contained in the REMODCM.

II.B. Responsibilities All changes to the Offsite Dose Calculation Manual (ODCM) shall be reviewed and approved by the Facilities Safety Review Committee prior to implementation.

All changes and their rationale shall be documented in the Radioactive Effluent Release Report.

It shall be the responsibility of the Site Vice President Millstone to ensure that this manual is used as required by the administrative controls of the Technical Specifications. The delegation of implementation responsibilities is delineated in the MP-22-REC-PRG, "Radiological Effluent Control."

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II.C. Liquid Dose Calculations Radiological Effluent Controls (Sections III, IV, and V) limit whole body and maximum organ doses to an individual member of the public to 1.5 mrem whole body and 5 mrem maximum organ per calendar quarter and 3 mrem whole body and 10 mrem maximum organ per year from liquid effluents released from each unit. (See Appendix A, Table App.A-1 for cross-reference effluent control requirements and applicable sections in the REMODCM which are used to determine compliance). In addition, installed portions of liquid radwaste treatment system are required to be operated to reduce radioactive materials in liquid effluents when the projected dose over 31 days from applicable waste streams exceeds 0.006 mrem whole body or 0.02 mrem maximum organ. This part of the REMO DCM provides the calculation methodology for determining the doses from radioactive materials released into liquid pathways of exposure associated with routine discharges.

1. Monthly, Quarterly, and Annual Dose Calculation (Applicable to All Units)

For each Unit, whole body and maximum organ doses from liquid effluents shall be calculated at least once per 31 days ( or monthly) using the methodology of Regulatory Guide 1.109, Rev. 1. The calculation shall include contributions from all analyses required by Table I.C-1 for Unit 1, Table I.C-2 for Unit 2, and Table I.C-3 for Unit 3 recorded to date. If any required analyses have not yet been completed for the dose period, an estimate of dose from unanalyzed isotopes shall be included in the dose total.

Results of these dose calculations shall be summed to determine compliance with quarterly and annual dose limits for each Unit.

2. Monthly Dose ProjectionsSection I.C.2.a. of the REMM requires that certain portions of the liquid radwaste treatment equipment be used to reduce radioactive liquid effluents when the projected doses for each Unit (made at least once per 31 days) exceeds 0.006 mrem whole body or 0.02 mrem to any organ. The following methods are applied in the estimation of monthly dose projections:

a. Whole Body and Maximum Organ when Steam Generator Total Gamma Radioactivity is less than 5E- 7 µCi/ml and Steam Generator Tritium is less than 0.02 µCi/ml (Applicable to Units 2 and 3)

The projected monthly whole body dose (Units 2 or 3) is determined from:

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The monthly projected maximum organ dose (Units 2 or 3) is determined from:

Where:

DMw =the whole body dose from the last typical previously completed month as calculated per the methods in Section IL C. l.

DMo = the maximum organ dose from the last typical previously completed month as calculated per the methods in Section IL C. l.

R1 = the ratio of the total estimated volume of liquid batches to be released in the present month to the volume released in the past month.

R4 = the ratio of estimated primary coolant radioactivity for the present month to that for the past month.

F2 = the factor to be applied to the estimated ratio of final curies released if there are expected differences in treatment of liquid waste for the present month as opposed to the past month (e.g., bypass of filters or demineralizers).

NUREG-0017 or past experience shall be used to determine the effect of each form of treatment which will vary. F2 = 1 if there are no expected differences.

The last month should be typical without significant operational differences from the projected month. If there were no releases during last month, do not use that month as the base month if it is estimated that there will be releases for the coming month.

b. Whole Body and Maximum Organ when Steam Generator Total Gamma radioactivity Exceeds 5E-7 µCi/ml or Steam Generator Tritium Exceeds 0.02 µCi/ml (Applicable to Units 2 and 3)

The projected monthly whole body dose (Units 2 or 3) is determined from:

The monthly projected maximum organ dose (Units 2 or 3) is

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determined from:

Where:

DMw=the whole body dose from the last typical previously completed month as calculated per the methods in Section IL C. l.

DMo=the maximum organ dose from the last typical previously completed month as calculated per the methods in Section II.C.l.

R1 = the ratio of the total estimated volume of liquid batches to be released in the present month to the volume released in the past month.

R2 = the ratio of estimated volume of steam generator blowdown to be released in present month to the volume released in the past month.

F1 = the fraction of curies released last month coming from steam generator blowdown calculated as:

curies from blowdown curies from blowdown + curies from batch tanks R3 = the ratio of estimated secondary coolant radioactivity for the present month to that for the past month.

R4 = the ratio of estimated primary coolant radioactivity for the present month to that for the past month.

F2 = the factor to be applied to the estimated ratio of final curies released if there are expected differences in treatment of liquid waste for the present morith as opposed to the past month (e.g., bypass of filters or demineralizers).

NUREG-0017 or past experience shall be used to determine the effect of each form of treatment which will vary. F2 = 1 if there are no expected differences.

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II.D. Gaseous Dose Calculations

1. Site Release Rate Limits ("Instantaneous")

Radiological Effluent Controls (Sections III.D.2.a, IY.D.2.a, and V.D.2.a) for each unit require that the instantaneous off-site dose rates from noble gases released to the atmosphere be limited such that they do not exceed 500 mrem/year at any time to the whole body or 3000 mrem/year to the skin at any time. For iodine-131, 133, tritium, and particulates (half-lives > 8 days), the dose rate from all units shall not exceed 1500 mrem/year at any time to any organ. These limits apply to the combination of releases from all three Units on the site, and*are directly related to the radioactivity release rates measured for each Unit.

a. Method 1 for Noble Gas Release Rate Limits Instantaneous noble gas release rate for the site:

01v /90,000 +Ozs/560,000 + 02v/290,000 + Q3s/560,000 + 0 3v/290,000 _:s.1 Where:

01v = Noble gas release rate from Spent Fuel Pool Island Vent

(µCi/sec) 02s = Noble gas release rate from MP2 to Millstone Stack (µCi/sec) 02v = Noble gas release rate from MP2 Vent (µCi/sec)

Q3y = Noble gas release rate from MP3 Vent (µCi/sec)

Q3s = Noble gas release rate from MP3 to Millstone Stack (µCi/sec)

As long as the above is less than or equal to 1, the doses will be less than or equal to 500 mrem to the total body and less than 3000 mrem to the skin. The limiting factor for the Unit 1 SFPI vent of 90,000 is based on the skin dose limit of 3,000 mrem/year, while all the other factors are based on the whole body dose limit of 500 mrem/year.

b. Method 1 Release Rate Limit - I-131, I-133, H-3 and Particulates Half Lives Greater Than 8 Days With releases satisfying the following limit conditions, the dose rate to the maximum organ will be less than 1500 mrem/year from the inhalation pathway:

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1) Site release rate ofl-131, I-133, and tritium (where the thyroid is the critical organ for these radionuclides):

DRthyl + DRthy2 + DRthy3 ::s; 1 Where the contribution from each Unit is calculated from:

Unit 1: DRthyl = 2.78E-5 QHlV Unit 2: DRthy2 = 8.80E-2131Q12v + 9.67E-3 131Qr2s +

2.08E-2133Qr2v+2.29E-3 133Qr2s +

6.87E-6 QH2v+ 7.53E- 7 QH2S Unit 3: DRthy3 = 8.80E-2131Q13y + 9.67E-3 131Q13s +

2.08E-2133Q13y +2.29E-3133Q13s +

6.87E-6 QH3V + 7.53E-7 QH3S

2) Site release rate of particulates with half-lives greater than 8 days and tritium (where the critical organ is a composite of target organs for a mix of radionuclides):

DRorgl + DRorg2 + DRorg3 :51 Where the contribution from each Unit is calculated from:

Unit 1:DRorgl = 3.52E-1 [Qp1v + Qprn ]+2.78E-5 QHlV Unit 2:DRorg2 = 9.53E-3 QP2s + 8.67E-2 QP2v +

7.53E-7 QH2S + 6.87E-6 QH2V Unit 3:DRorg3 = 9.53E-3 Qp3s + 8.67E-2 Qp3y +

7.53E-7 QH3S + 6.87E-6 QH3V Each of the release rate quantities in the above equations are defined as:

131Qr2v =Release rate ofl-131 from MP2 Vent (µCi/sec)*

1310r2s = Release rate ofl-131 from MP2 to Millstone Stack

(µCi/sec) 133Qr2v =Release rate ofl-133 from MP2 Vent (µCi/sec)*

133Qr2s = Release rate of I-133 from MP2 to Millstone Stack

(µCi/sec) 131Q13y =Release rate ofl-131 from MP3 Vents (Normal and ESF)

(µCi/sec)*

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131Q13s = Release rate of 1-131 from MP3 to Millstone Stack

(µCi/sec) 133Q13y =Release rate of 1-133 from MP3 Vents (Normal and ESF)

(µCi/sec)*

133 Q13s = Release rate of 1-133 from MP3 to Millstone Stack

(µCi/sec)

OH1V = Release rate of tritium from the Spent Fuel Pool Island and Balance of Plant Vents (µCi/sec)

OH2v = Release rate of tritium from MP2 Vent*(µCi/sec)*

QH2S = Release rate of tritium from MP2 to Millstone Stack

(µCi/sec)

QH3V = Release rate of tritium from MP3 Vents (Normal and ESF)

(µCi/sec)*

QH3S = Release rate of tritium from MP3 to Millstone Stack

(µCi/sec)

Qp1v = Release rate of total particulates with half-lives greater than 8 days from the Spent Fuel Pool Island Vent (µCi/sec)

Qprn = Release rate of total particulates with half-lives greater than 8 days from the Balance of Plant Vent (µCi/sec)

OP2v = Release rate of total particulates with half-lives greater than 8 days from the MP2 Vent (µCi/sec)

OP2s = Release rate of total particulates with half-lives greater than 8 days from MP2 to Millstone Stack (µCi/sec)

Qp3y = Release rate of total particulates with half-lives greater than 8 days from MP3 Vents (Normal and ESF) (µCi/sec)

Qp3s = Release rate of total particulates with half-lives greater than 8 days from MP3 to Millstone Stack (µCi/sec)

includes releases via the steam generator blowdown tank vent.

c. Method 2 The above Method 1 equations assume a conservative nuclide mix. If necessary, use the methodology given in Regulatory Guide 1.109 to estimate the dose rate from either noble gases or iodines, tritium, and particulates with half-lives greater than 8 days.

2. 10 CFR50 Appendix I - Noble Gas Limits Use the methodology of Regulatory Guide 1.109 Rev.1, to calculate the critical site boundary gamma air and beta air doses at least once per 31 days (monthly).

For calculations performed once every 31 days, enter the following meteorology:

Release Point x)Q D/Q Site Stack 8.92E-7 8.84E-9 Mixed-mode or rooftop (e.g., vents) 8.lE-6 l.5E-7 Ground 3.28E-5 l.68E-7 If the calculated air dose exceeds one half the quarterly Radiological Effluent Control limit, use meteorology concurrent with quarter of release.

Results of these dose calculations shall be summed to determine compliance with quarterly and annual dose limits for each Unit.

For calculations of quarterly doses for the Radioactive Effluent Release Report, use average quarterly or real- time meteorology.

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3. 10 CFR50 Appendix I - Iodine, Tritium, C-14, and Particulate Doses For each Unit, whole body and maximum organ doses from I-131, I-133, tritium, C-14 and particulates with half-lives greater than 8 days in gaseous effluents shall be calculated at least once per 31 days (or monthly) using the methodology of Regulatory Guide 1.109, Rev.l.

For calculations performed once every 31 days, enter the following meteorology:

Release Point 't)Q D/Q Site Stack 8.92E-7 8.84E-9 Mixed-mode or rooftop (e.g., vents) 8.lE-6 l.5E-7 Ground 3.28E-5 l.68E-7 The calculation shall include contributions from all analyses required by Table I.D-1 for Unit 1, Table I.D-2 for Unit 2, and Table I.D-3 for Unit 3 recorded to date. If any required analyses have not yet been completed for the dose period, an estimate of dose from unanalyzed isotopes shall be included in the dose total. If the calculated dose exceeds one-half the quarterly Radiological Effluent Control limit, use meteorology concurrent with the dose period.

Results of these dose calculations shall be summed to determine compliance with quarterly and annual dose limits for each Unit.

For calculations of quarterly doses for the Radioactive Effluent Release Report, use average quarterly or real- time meteorology.

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4. Gaseous Effluent Monthly Dose ProjectionsSection I.D.2.a. of the REMM requires that certain portions of the gaseous radwaste treatment equipment be returned to service to reduce radioactive gaseous effluents when the projected doses for each Unit (made at least once per 31 days) exceed 0.02 mrad gamma air, 0.04 mrad beta air, or 0.03 mrem to any organ from gaseous effluents. The following methods are applied in the estimation of monthly dose projections.

a. Unit 1 Projection Method None required.

b. Unit 2 Projection Method

1) Due to Gaseous Radwaste Treatment System (Unit 2)

Determine the beta and gamma monthly air dose projection from noble gases from the following:

DEMG (mrad) = 5E-4 CEN DEMB (mrad) = 3E-4 CEN DEMO (mrem) = 3E-4 CEN Where:

cEN = the number of curies of noble gas estimated to be released from the waste gas storage tanks during the next month.

DEMG = the estimated monthly gamma air dose.

DEMB= the estimated monthly beta air dose.

DEMo= the estimated monthly organ dose.

2) (Reserved)

3) Due to Ventilation Releases (Unit 2)

If portions of the ventilation treatment system are expected to be out of service during the month, determine the monthly maximum organ dose projection (DEMO ) from the following:

1. Method 1 Determine DEMO which is the estimated monthly dose to the maximum organ from the following:

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DEMO= 1/3 R1 (1.01- R2) (R3+ 0.01) Do For the last quarter of operation, determine Do as determined per Section II.D.3.

R1 = the expected reduction factor for the HEPA filter.

Typically this should be 100 (see NUREG-0016 or 0017 for additional guidance).

R2 = the fraction of the time which the equipment was nonfunctional during the last quarter.

R3 = the fraction of the time which the equipment is expected to be nonfunctional during the next month.

Do= maximum organ dose from the previous month.

11. Method 2 If necessary, estimate the curies expected to be released for the next month and applicable method for dose calculation from Section II.D.3.

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c. Unit 3 Projection Method

1) Due to Radioactive Gaseous Waste System (Unit 3)

Determine the beta and gamma monthly air dose projection from noble gases from the following:

DEMG (mrad) = 5E-4 cEN DEMB (mrad) = 3E-4 CEN DEMO (mrem) = 3E-4 CEN Where:

cEN = the number of additional curies of noble gas estimated to be released from Unit 3 during the next month due to the nonfunctional processing equipment.

DEMG =the estimated monthly gamma air dose.

DEMB = the estimated monthly beta air dose.

DEMO = the estimated monthly organ dose .

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5. Compliance with 40CFR190 The following sources shall be considered in determining the total dose to any real member of the public, at or beyond the site boundary, from uranium fuel cycle sources:

a. Gaseous Releases from Units 1, 2, and 3.

b. Liquid Releases from Units 1, 2, and 3.

c. Direct and Scattered Radiation from Radioactive Material on Site.

d. Direct and Scattered Radiation from the Independent Spent Fuel Storage Installation (ISFSI). I Doses shall be obtained per the requirements of Section II.C.l'for liquid releases and Section II.D.2 and II.D.3 for gaseous releases.

Direct and scattered radiation doses shall be calculated. Doses from all sources shall be added to determine compliance with 40CFR190.

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II.E. Liquid Discharge Flow Rates And Monitor Setpoints

1. Unit 1 Liquid Waste Effluent Discharge (RE-M6-110) I The limit on discharge flow rate and setpoint on the Unit 1 liquid waste monitor depend on dilution water flow, radwaste discharge flow, the isotopic composition of the liquid, the background count rate of the monitor and the efficiency of the monitor. Due to the variability of these parameters, the alert and alarm setpoints will be determined prior to the release of each batch. The following method will be used:

STEP 1:

From the isotopic analysis and the Effluent Concentration (EC) values for each identified nuclide determine the required reduction factor, i.e.:

1 R = Requi7:ed Reduction Factor = µc; ,f' z*d .

~ --;;J" oJ nucz e z L 10 x EC of nuclide i STEP 2:

Determine the allowable discharge flow (F)

F = O.lxRxD Where:

D = The existing dilution flow which is the any dilution flow from Millstone Unit 2 and/or Unit 3 not being credited for any other radioactivity discharge during discharge of Unit 1 water.

0.1 = safety factor to limit discharge concentration to 10% of the Radiological Effluent Control Limit.

STEP 3:

Calculate the monitor setpoint as follows:

Rset = 2 x AC x RCF + Background Where:

Rset = The setpoint of the monitor.

AC = The total radwaste effluent concentration (µCi/ml ) in the tank.

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RCF = The response correction factor for the effluent line monitor using the current calibration factor or isotopic-specific responses.

2 = Tolerance limit which brings the setpoint at twice the expected response of the monitor based on sample analysis. With the safety factor of 0.1 the setpoint would be at 20% of the Radiological Effluent Control Limit.

Option setpoint:

A setpoint based upon worst case conditions may be used. Assume the maximum possible discharge flow, a minimum dilution flow not to exceed 100,000 gpm, and a limit of 1 x 10-7 µCi/ml which is lower than any 10CFR20 EC limit except for transuranics. This will assure that low level releases are not terminated due to small fluctuations in radioactivity. When using this option setpoint independent verification of discharge lineup shall be performed. The optional setpoint may be adjusted (increased or decreased) by factors to account for the actual discharge flow and actual dilution flow; however, controls shall be established to ensure that the allowable discharge flow is not exceeded and the dilution flow is maintained.

2. Reserved

3. Unit 2 Clean Liquid Radwaste Effluent Line - RM9049 and Aerated Liquid Radwaste Effluent Line - RM9116 The setpoint on the Unit 2 clean and aerated liquid waste effluent lines depend on dilution water flow, radwaste discharge flow, the isotopic composition of the liquid, the background count rate of the monitor and the efficiency of the monitor. Due to the variability of these parameters, an alarm/trip setpoint will be determined prior to the release of each batch.

The following method will be used:

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STEP 1:

From the tank isotopic analysis and the Effluent Concentrations (EC) in 10CFR20, App. B, Table 2, Col. 2 for each identified nuclide determine the required reduction factor, i.e.:

For Nuclides Other Than Noble Gases:

R1 = Required Reduction Factor = c 1

"'"' 1;;f of nuclide i L 10 x EC of nuclide i For Noble Gases: If the noble gas concentration is less than 1.1 x 10- 2 µCi/ml or the calculated diluted concentration is less than 2 x 10-5 µCi/ml, the reduction factor need not be determined. The concentration of 1.1 x 10- 2 µCi/ml is based on 175 gpm discharge flow, 100,000 gpm dilution flow, and a safety factor of 0.1 (See Note below.) If dilution flow is less than 100,000 gpm, the noble gas concentration limit shall be decreased by the ratio of actual dilution flow to 100,000gpm. For example, if dilution flow is 50,000 gpm, the limit would be reduced by a factor of 0.5 (50,000/100,000).

2 X 10-4µCi R2 = Required Reduction Factor = ____l _ __ ml

"'"' ~ of noble gases "'"' µm/

L C noble gases L 2 X 10-4/'Ci ml R = the smaller of R1 or R2 STEP 2:

Determine the allowable discharge flow (F) in gpm:

F = O.lxRxD Where:

D = the existing dilution flow (D) from circulating and service water pumps. It may include any Unit 3 flow, or portion of Unit 3 flow, not being credited for dilution of a Unit 3 radioactivity discharge during the time of the Unit 2 discharge.

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NOTE Note that discharging at this flow rate would yield a discharge concentration corresponding to 10% of the Radiological Effluent Control Limit due to the safety factor of 0.1.

With this condition on discharge flow rate met, the monitor setpoint can be calculated:

Rset = 2 x AC x RF (See Note 1 below.)

Where:

Rset = the setpoint of the monitor (cpm).

AC = the total radwaste effluent concentration (µCi/ml) in the tank.

RF = the response factor for the effluent line monitor using the current calibration factor or isotopic-specific responses.

2 = the multiple of expected count rate on the monitor based on the radioactivity concentration in the tank.

This value or that corresponding to 5.6 x 10-5 µCi/ml (Note 2 below),

whichever is greater, plus background is the trip setpoint. For the latter setpoint, independent valve verification shall be performed and minimum dilution flow in Note 2 shall be verified and if necessary, appropriately adjusted.

Note 1: If discharging at the allowable discharge rate (F) as determined in above, this setpoint would correspond to 20% of the Radiological Effluent Control limit.

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Note 2: This value is based upon assuming maximum discharge flow (175 gpm), dilution water flow of 100,000 gpm and a limit of 1 x 10-7 which is lower than any Technical Specification limit (ten times 10CFR20 EC values) except for transuranics. This will assure that low level releases are not terminated due to small fluctuations in radioactivity activity. However, to verify that the correct tank is being discharged when using this value, independent valve verification shall be performed. This value may be adjusted (increased or decreased) by factors to account for the actual discharge flow and actual dilution flow; however, controls shall be established to ensure that the allowable discharge flow is not exceeded and the dilution flow is maintained. Dilution flow may include any Unit 3 flow, or a portion of Unit 3 flow, not being credited for dilution of a Unit 3 radioactive discharge during the time of the Unit 2 discharge.

4. Condensate Polishing Facility Waste Neutralization Sump Effluent Line -

CND245 The setpoint shall be determined as for the Clean and Aerated Liquid Monitors in Section II.E.3.

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5. Unit 2 Steam Generator Blowdown - RM4262 and Unit 2 Steam Generator Blowdown Effluent Concentration Limitation 5a. Unit 2 Steam Generator Blowdown - RM4262 Alarm :;:; 800 CPM + background This setpoint may be adjusted (increased or decreased) through proper administrative controls.

circulating & service water flow (gpm)

Adjusted alarm ::5 6 C'P'M X + Background total SG blowdown (gpm)

When using the adjusted alarm, ensure that any other simultaneous discharge does not cause an exceedance of regulatory limits.

5b. Unit 2 Steam Generator Blowdown Effluent Concentration Limitation The results of analysis of blowdown samples required by Table I. C. -2 of Section I of the REMO DCM shall be used to ensure that blowdown effluent releases do not exceed ten times the concentration limits in 10CFR20, Appendix B.

6. Unit 2 Condenser Air Ejector - RM5099 NIA since this monitor is no longer a final liquid effluent monitor.

7. Unit 2 Reactor Building Closed Cooling Water RM6038 and Unit 2 Service Water, and RBCCW Sump and Turbine Building Sump Effluent Concentration Limitation 7a. Unit 2 Reactor Building Closed Cooling Water RM6038 The purpose of the Reactor Building Closed Cooling Water (RBCCW) radiation monitor is to give warning of abnormal radioactivity in the RBCCW system and to prevent releases to the Service Water system which, upon release to the environment, would exceed ten times the concentration values in 10CFR20. According to Calculation RERM-02665-R2, radioactivity in RBCCW water which causes a monitor response of greater than the setpoint prescribed below could exceed ten times the10CFR20 concentrations upon release to the Service Water system.

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SETPOINT DURING POWER OPERATIONS:

To give adequate warning of abnormal radioactivity, the setpoint shall be two times the radiation monitor background reading, provided that the background reading does not exceed 2,000 cpm. The monitor background reading shall be the normal monitor reading. If the monitor background reading exceeds 2,000 cpm, the setpoint shall be set at the background reading plus 2,000 cpm and provisions shall be made to adjust the setpoint if the background decreases.

SETPOINT DURING SHUTDOWN:

1) During outages not exceeding three months the setpoint shall be two times the radiation monitor background reading, provided that the background reading does not exceed 415 cpm. If the monitor background reading exceeds 415 cpm, the setpoint shall be set at the background reading plus 415 cpm and provisions shall be made to adjust the setpoint if the background decreases.

2) During extended outages exceeding three months, but not exceeding three years, the setpoint shall be two times the radiation monitor background reading, provided that the background reading does not exceed 80 cpm. If the monitor background reading exceeds 80 cpm, the setpoint shall be set at the background reading plus 80 cpm and provisions shall be made to adjust the setpoint if the background decreases.

PROVISIONS FOR ALTERNATE DILUTION FLOWS:

These setpoints are based on a dilution flow of 4,000 gpm from one service water train. If additional dilution flow is credited, the setpoint may be adjusted proportionately. For example, the addition of a circulating water pump dilution flow of 100,000 gpm would allow the setpoint to be increased by a factor of 25.

7b. Unit 2 Service Water, and RBCCW Sump and Turbine Building Sump Effluent Concentration Limitation Results of analyses of service water, RBCCW sump and turbine building sump samples taken in accordance with Table I. C.-2 of Section I of the REMODCM shall be used to limit radioactivity concentrations in the service water, RBCCW sump and turbine building sump effluents to less than ten times the limits in 10CFR20, Appendix B.

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8. Unit 3 Liquid Waste Monitor - LWS-RE70 The setpoints on the Unit 3 liquid waste monitor depend on dilution water flow, radwaste discharge flow, the isotopic composition of the liquid, the background count rate of the monitor and the efficiency of the monitor. Due to the variability of these parameters, the alert and alarm setpoints will be determined prior to the release of each batch. The following method will be used:

Step 1:

From the tank isotopic analysis and the Effluent Concentration. (EC) values for each identified nuclide determine the required reduction factor, i.e.:

For Nuclides Other Than Noble Gases:

R1 = Required Reduction Factor = c* l

, l!,;f- of nuclide i

_ L 10 x EC of nuclide i For Noble Gases: If the noble gas concentration is less than 0.013 µCi/ml or the calculated diluted concentration is less than 2 x 10-5 µCi/ml, the reduction factor need not be determined. The concentration of 0.013 µCi/ml is based on 100,00 gpm dilution flow and a safety factor of 0.1 (See Note Below.) If dilution flow is less than 100,000 gpm, the noble gas concentration limit shall be decreased by the ratio of actual dilution flow to 100,000gpm.

For example, if dilution flow is 50,000 gpm, the limit would be reduced by a factor of 0.5 (50,000/100,000).

2 X 10-4µCi R2 = Required Reduction Factor= ---"""'"1- - - , c*

ml

, !!!j/- of noble gases L µm/ noble gases L 2 x 10-4'~:

R = the smaller of Rl or R2 Step 2:

Determine the allowable discharge flow (F)

F = O.lxRxD Where:

D = The existing dilution flow (D) from circulating and service water pumps.

It may include any Unit 2 flow, or portion of Unit 2 flow, not being credited for dilution of a Unit 2 radioactivity discharge during the time of the Unit 3 discharge.

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NOTE Note that discharging at this flow rate would yield a discharge concentration corresponding to 10% of the Radiological Effluent Control Limit due to the safety factor of 0.1.

With this condition on discharge flow rate met, the monitor setpoint can be calculated:

Rset = 2 x AC x RCF (see Note 1)

Where:

Rset= The setpoint of the monitor.

AC= The total radwaste effluent concentration (µCi/ml ) in the tank.

RCF= The response correction factor for the effluent line monitor using the current calibration factor or isotopic-specific responses.

2 = The multiple of expected count rate on the monitor based on the radioactivity concentration in the tank.

This value, or that corresponding to 6.6 x 10-5 µCi/ml (Note 2 below),

whichever is greater, plus background is the trip setpoint. For the latter setpoint, independent valve verification shall be performed and minimum dilution flow in Note 2 shall be verified and if necessary, appropriately adjusted.

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NOTE

1. If discharging at the allowable discharge rate (F) as determined above, this Alarm setpoint would yield a discharge concentration corresponding to 20% of the Radiological Effluent Control limit.

2. This value is based upon assuming maximum discharge flow (150 gpm), dilution water flow of 100,000 gpm, and a limit of 1 x 10-7 µCi/ml which is lower than any Technical Specification limit (ten times 10CFR20 EC values) except for transuranics. This will assure that low level releases are not terminated due to small fluctuations in radioactivity. However, to verify that the correct tank is being discharged when using this value, independent valve verification shall be performed. This value may be adjusted (increased or decreased) by factors to account for the actual discharge flow and actual dilution flow; however, controls shall be established to ensure that the allowable discharge flow is not exceeded and the dilution flow is maintained. Dilution flow may include Unit 2 flow, or portion of Unit 2 flow, not being credited for dilution of a Unit 2 discharge during the time of the Unit 3 discharge. *

9. Unit 3 Regenerant Evaporator Effluent Line - LWC-RE65 The MP3 Regenerant Evaporator has been removed from service with DCR M3-97-041. Therefore a radiation monitor alarm is not needed.

10. Unit 3 Waste Neutralization Sump Effluent Line - CND-RE07 Same asSection II.E.8.

11. Unit 3 Steam Generator Blowdown - SSR-RE08 and Unit 3 Steam Generator Blowdown Effluent Concentration Limitation lla. Unit 3 Steam Generator Blowdown - SSR-RE08 The alarm setpoint for this monitor assumes:

a. Steam generator blowdown rate of 400 gpm (maximum blowdown total including weekly cleaning of generators - per ERC 25212-ER-99-0133).

b. The release rate limit is conservatively set at 3 x 10-8 µCi/ml which is well below any 10CFR20 Effluent Concentration except for transuranics*.

c. Circulating and service water dilution flow during periods of blowdown = 100,000 gpm.

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d. Background can be added after above calculations are performed.

Therefore, the alarm setpoint corresponds to a concentration of:

Alarm (µCi/ml) = 10~0~00 x 3xl0-8 + background = 7.Sxl0-6 µCi/ml + background This setpoint may be increased through proper administrative controls if the steam generator blowdown rate is maintained less than 400 gpm and/or more than 100,000 gpm dilution flow are available. The amount of the increase would correspond to the ratio of flows to those assumed above or:

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I-131, I-133 & tritium*
III.D.2.b II.D.2. 5 5 mrad gamma air Calendar Quar- 30-day report if exceeded IV/Y.D.2.bDose Noble 5 10 mrad beta air ter**
Gases 510 mrad gamma air Calendar Year 5 20 mrad beta air III.D.2.c II.D.3. 5 7.5 mrem organ Calendar Quar- 30-day report if exceeded. Relative IV/Y.D.2.c ter** accuracy or conservatism of the cal-Dose I-131, I-133, Par- culations shall be confirmed by per-ticulates, H-3 515 mrem organ Calendar Year formance of the REMP in Section I.
T.S. 5.6.4 (Unit 1) II.D.2. > 0.02 mrad gamma air Projected for 31 Return to operation Gaseous Rad-T.S. 6.14 (Unit 2) II.D.4. > 0.04 mrad beta air Days (if system waste 'Ireatment System T.S 6.14 & T.S 6.15 (U3) > 0.03 mrem organ not in use)
Gaseous Radwaste Treatment ILE II.D.5. 525 mrem T.B.* 12 Consecutive 30-day report if Unit 1 Effluent IVI/Y.F 5 25 mrem organ* Months** Control III.D.1.2, III.D.2.2, or Total Dose 5 75 mrem thyroid* III.D.2.3 or Units 2/3 Effluent Con-trol IV/Y.E.1.2, IV/Y.E.2.2, or IV/
V.E.2.3 are exceeded by a factor of
2. Restore dose to public to within the applicable EPA limit(s) or ob-tain a variance NOTE: T.B. means total or whole body.
Applies to the entire site (Units 1, 2, and 3) discharges combined.
Cumulative dose contributions calculated once per 31 days.
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SECTION III.
Millstone Unit 1 Radiological Effluent Controls Docket Nos. 50-245
SECTION III. REMO DCM UNIT ONE CONTROLS III.A Introduction The purpose of this section is to provide the following for Millstone Unit One:
a. the effluent radiation monitor controls and surveillance requirements,
b. the effluent radioactivity concentration and dose controls and surveillance requirements, and
c. the bases for the controls and surveillance requirements.
Definitions of certain terms are provided as an aid for implementation of the controls and requirements.
Some surveillance requirements refer to specific sub-sections in Sections I and II as part of their required actions 111.B. Definitions and Surveillance Requirement (SR) Applicability 111.B.1 - Definitions The defined terms of this sub-section appear in capitalized type and are applicable throughout Section III.
1. ACTION - that part of a Control that prescribes remedial measures required under designated conditions.
2. INSTRUMENT CALIBRATION - the adjustment, as necessary, of the instrument output such that it responds within the necessary range and accuracy to know values of the parameter that the instrument monitors. The INSTRUMENT CALIBRATION shall encompass those components, such as sensors, displays, and trip functions, required to perform the specified safety function(s). The INSTRUMENT CALIBRATION shall include the INSTRUMENT FUNCTIONAL TEST and may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is calibrated.
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3. INSTRUMENT FUNCTIONAL TEST - the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify that the instrument is FUNCTIONAL, including all components in the channel, such as alarms, interlocks, displays, and trip functions, required to perform the specified safety function(s). For digital instruments, the computer database may be manipulated, in lieu of a signal injection, to verify operability of alarm and/or trip functions. The INSTRUMENT FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested.
4. CHANNEL CHECK - the qualitative determination of functionality by observation of behavior during operation. This determination shall include, where possible, comparison of the instrument with other independent instruments measuring the same variable.
5. FUNCTIONAL - An instrument shall be FUNCTIONAL when it is capable of performing its specified functions(s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the instrument to perform its functions(s) are also capable of performing their related support function(s).
6. REAL MEMBER OF THE PUBLIC - an individual, not occupationally associated with the Millstone site, who is exposed to existing dose pathways at one particular location. This does not include employees of the utility or utilities which own a Millstone plant and utility contractors and vendors.
Also excluded are persons who enter the Millstone site to service equipment or to make deliveries. This does include persons who use portions of the Millstone site for recreational, occupational, or other purposes not associated with any of the Millstone plants.
7. SITE BOUNDARY - that line beyond which the land is not owned, leased, or otherwise controlled by the licensee.
8. SOURCE CHECK - the qualitative assessment of channel response when the channel is exposed to radiation.
9. RADIOACTIVE WASTE TREATMENT SYSTEMS - Radioactive Waste Treatment Systems are those liquid, gaseous, and solid waste systems which are required to maintain control over radioactive materials in order to meet the controls set forth in this section.
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111.B.2 - Surveillance Requirement (SR) Applicability
1. SRs shall be met during specific conditions in the Applicability for individual LCOs unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in III.B.2 3.
Surveillances do not have to be performed on nonfunctional equipment or variables outside specified limits.
2. The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the frequency is met.
3. If it is discovered that a Surveillance was not performed within its specified frequency, then compliance with the requirement to declare the LCO not met inay be delayed from the time of discovery up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified frequency, whichever is less. This delay period is -
permitted to allow performance of the surveillance. If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met and the applicable Condition(s) must be entered. The Completion Times of the Required Actions begin immediately upon expiration of the delay period. When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met and the applicable Condition(s) must be entered. The Completion Times of the Required Actions begin immediately upon failure to meet the Surveillance. *
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III.C. Radioactive Effluent Monitoring Instrumentation
1. Radioactive Liquid Effluent Monitoring Instrumentation CONTROLS The radioactive liquid effluent monitoring instrumentation channels shown in Table III.C.-1 shall be FUNCTIONAL with applicable alarm/trip setpoints set to ensure that the limits of Specification III.D.l.a. are not exceeded. The setpoints shall be determined in accordance with methods and parameters described in Section II.
APPLICABILITY: As shown in Table III.C.-1 ACTION:
a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel nonfunctional, or change the setpoint so it is acceptably conservative.
b. With the number of channels less than the minimum channels FUNCTIONAL requirement, take the action shown in Table III.C.-1.
Exert best efforts to restore the nonfunctional monitor to FUNCTIONAL status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the nonfunctionality was not corrected in a timely manner. Releases need not be terminated after 30 days provided the specified actions are continued.
SURVEILLANCE REQUIREMENTS Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table III.C.-2.
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TABLE III.C. -1 Radioactive Liquid Effluent Monitoring Instrumentation Instrument Action when not functional Notes
1. Liquid Waste Effluent Monitor (RE-M6-110) A 1,2 I
1. Whenever the pathway is being used except that outages are permitted, for a maximum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , for the purpose of maintenance and performance of required test, checks, calibrations, or sampling.
2. Alarm setpoint required.
Action A With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirements, effluent releases may continue provided that best efforts are made to repair the instrument and that prior to initiating a release:
(1) At least two independent samples are analyzed for gamma radioactivity as specified in Table I.C-1 and; (2) The original release rate calculations and discharge valving are independently verified by a second individual.
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TABLE 111.C.-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Instrument Channel Source Channel Channel Check Check Calibration Functional Test
1. Liquid Waste Effluent Monitor (RE-M6-110) D* p T(l) Q I
D Daily P = Prior to each batch release T = Once every two years Q Once every 3 months
During releases via this pathway and when the monitor is required FUNCTIONAL per Table 111.C.-1. The CHANNEL CHECK should be done when the discharge is in progress.
(1) Calibration shall include the use of a radioactive liquid or solid source which is traceable to an NIST source.
2. Radioactive Gaseous Effluent Monitoring Instrumentation CONTROLS The radioactive gaseous effluent monitoring instrumentation channels shown in Table III.C.-3 shall be FUNCTIONAL with applicable alarm setpoints set to ensure that the limits of Control III.D.2.a. are not exceeded. The setpoints shall be determined in accordance with methods and parameters described in Section II.El.
APPLICABILITY: As shown in Table III.C.-3 ACTION:
a. With a radioactive gaseous effluent monitoring instrumentation channel alarm setpoint less conservative than required by the above Control, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel nonfunctional, or change the setpoint so it is acceptably conservative.
b. With the number of channels less than the minimum channels functional requirements, take the action shown in Table III.C.-3. Exert best efforts to restore the nonfunctional monitor to FUNCTIONAL status within 30 days and, if unsuccessful, explain in the next Radiological Effluent Release Report why the nonfunctionality was not corrected in a timely manner. Release need not be terminated after 30 days provided the specified actions are continued.
SURVEILLANCE REQUIREMENT Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the INSTRUMENT CHECK, INSTRUMENT CALIBRATION, INSTRUMENT FUNCTIONAL TEST, and SOURCE CHECK operations at the frequencies shown in Table III.C.-4.
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TABLE 111.C. -3 Radioactive Gaseous Effluent Monitoring Instrumentation Instrument Action when not functional Notes l.Spent Fuel Pool Island Vent (a) Noble Gas Radioactivity Monitor A 1, 2 (b) Particulate Sampler B 1 (c) Vent Flow Rate Monitor C 1 (d) Sampler Flow Rate Monitor D 1,2 2.Balance of Plant Vent (a) Particulate Sampler B 1 (b) Sampler Flow Monitor D 1
1. Channels are FUNCTIONAL and in service on a continuous, uninterrupted basis when exhaust fans are operating, except that outages are permitted, for a maximum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , for the purpose of maintenance and performance of required tests, checks, calibrations, and sampling associated with the instrument or any system or component which affects functioning of the instrument.
2. Alarm setpoint required. I ACTION STATEMENTS Action A With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that grab samples are taken daily when fuel is being moved, or during any evolution or event which would threaten fuel integrity, and these samples are analyzed for gamma radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
Action B With the number of samplers FUNCTIONAL less than required by the Minimum number FUNCTIONAL requirement, effluent releases via this pathway may continue provided that the best efforts are made to repair the instrument and that a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months duration sample is collected with auxiliary sampling equipment once every seven (7) days, or anytime significant generation of airborne radioactivity is expected, and analyzed for principal gamma emitters with half lives greater than 8 days within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after the end of the sampling period.
Operation of the auxiliary sampling equipment shall be verified every twelve (12) hours.
Action C With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument.
Action D With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that the flow rate is estimated once during the Chemistry compensatory sampling time period as specified in Action A or Action B. Sample flow rate need not be estimated if the auxiliary sampling equipment of Action B is in use.
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TABLE 111.C.-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Instrument Channel Instrument Functional Source Check Calibration Test Check l.Spent Fuel Pool Island Vent (a) Noble Gas Radioactivity Monitor D(3) T(6) Q(7) M (b) Particulate Sampler TM NA NA NA (c) Vent Flow Rate Monitor D T NA NA (d) Sampler Flow Rate Monitor D T NA NA 2.Balance of Plant Vent (a) Particulate Sampler TM NA NA NA (b) Sampler Flow Monitor D T NA NA D = Daily W = Weekly TM = Twice per month M = Monthly Q = Once every 3 months T = Once every two years NA = Not Applicable Table 111.C.-4 TABLE NOTATION (1) RESERVED (2) RESERVED (3) Instrument check daily only when there exist releases via this pathway.
(4) RESERVED (5) RESERVED (6) Calibration shall include the use of a known source whose strength is determined by a detector which has been calibrated to a source which is traceable to the NIST. These sources shall be in a known reproducible geometry.
(7) The INSTRUMENT FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:
1. Instrument indicates measured levels above the alarm/trip setpoint.
2. Instrument indicates a downscale failure.
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III.D. Radioactive Effluents Concentrations And Dose Limitations
1. Radioactive Liquid Effluents
a. Radioactive Liquid Effluents Concentrations LIMITING CONDITIONS OF OPERATIONS The concentration of radioactive material released from the site (see Figure III.D.-1) shall not exceed ten times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall not exceed 2 x 10-4 µCi/ml total radioactivity.
APPLICABILITY: At all times.
ACTION:
With the concentration of radioactive material released from the site exceeding the above limits, restore the concentration to within the above limits within 15 minutes.
SURVEILLANCE REQUIREMENT Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program specified in Section I.
The results of the radioactive analysis shall be used in accordance with the methods of Section II.E to assure that the concentrations at the point of release are maintained within the limits of Specification III.D.l.a.
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b. Radioactive Liquid Effluents Doses LIMITING CONDITIONS OF OPERATIONS The dose or dose commitment to any REAL MEMBER OF THE PUBLIC from radioactive materials in liquid effluents from Unit 1 released from the site (see Figure III.D.-1) shall be limited:
a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ; and,
b. During any calendar year to less thaff or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
APPLICABILITY: At all times ACTION:
a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits prepare and submit to the Commission within 30 days a Special Report which identifies the cause( s) for exceeding the limit( s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents and the proposed corrective actions to be taken to assure that subsequent rele~ses will be in compliance with the above limits.
SURVEILLANCE REQUIREMENTS
1) Dose Calculations - Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section II once every 31 days.
2) Relative accuracy or conservatism of the calculations shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in Section I.
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2. Radioactive Gaseous Effluents
a. Radioactive Gaseous Effluents Dose Rate CONTROLS The dose rate, at any time, offsite (See Figure III.D.-1) due to radioactivity released in gaseous effluents from the site shall be limited to the following values:
a. The dose rate limit for noble gases shall be less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin; and,
b. The dose rate limit for Tritium and for all radioactive materials in particulate form with half lives greater than 8 days shall be less than or equal to 1500 mrem/yr to any organ.
APPLICABILITY: At all times.
ACTION:
With the dose rate(s) exceeding the above limits, decrease the release rate to comply with the limit(s) given in Control III.D.2.a. within 15 minutes.
SURVEILLANCE REQUIREMENT
1) The release rate, at any time, corresponding to the above dose rates shall be determined in accordance with the methodology of Section IL
2) The release rate, at any time shall be monitored in accordance with the requirements of Section III.C.2.
3) Sampling and analysis shall be performed in accordance with Section I to assure that the limits of Control III.D.2.a. are met.
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b. Radioactive Gaseous Effluents Noble Gas Dose CONTROLS The air dose offsite (see Figure III.D. -1) due to noble gases released in gaseous effluents from Unit 1 shall be limited to the following:
a. During any calendar quarter, to less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation;
b. During any calendar year to less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
APPLICABILITY: At all times.
ACTION:
With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits prepare and submit to the Commission within 30 days a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
SURVEILLANCE REQUIREMENTS
1) Dose Calculations - Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in*
accordance with Section II once every 31 days.
2) Relative accuracy or conservatism of the calculations shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in Section I.
c. Gaseous Effluents - Dose from Radionuclides Other than Noble Gas CONTROLS The dose to any REAL MEMBER OF THE PUBLIC from Tritium and radioactive materials in particulate form with half lives greater than 8 days in gaseous effluents released offsite from Unit 1 (see Figure III.D. -1) shall be limited to the following:
a. During any calendar quarter to less than or equal to 7.5 mrem to any organ;
b. During any calendar year to less than or equal to 15 mrem to any organ.
APPLICABILITY: At all times.
ACTION:
With the calculated dose from the release of Tritium and radioactive materials in particulate form exceeding any of the above limits prepare and submit to the Commission within 30 days a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases of radioactive materials in gaseous effluents and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
SURVEILLANCE REQUIREMENTS
1) Dose Calculations - Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section II once every 31 days.
2) Relative accuracy or conservatism of the calculations shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in Section I.
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Figure 111.D. -1, "Site Boundary for Liquid and Gaseous Effluents"
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III.E. Total Radiological Dose From Station Operations Controls CONTROLS The annual dose or dose commitment to any REAL MEMBER OF THE PUBLIC, beyond the site boundary, from the Millstone Site is limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which is limited to less than or equal to 75 mrem).
APPLICABILITY: At all times.
ACTION:
With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls III.D.l.b., III.D.2.b. or III.D.2.c. prepare and submit a Special Report to the Commission within 30 days and limit the subsequent releases such that the dose commitment from the site to any REAL MEMBER OF THE PUBLIC from the Millstone Site is limited to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months.
This Special Report shall include an analysis which demonstrates that radiation exposures from the site to any REAL MEMBER OF THE PUBLIC from the Millstone Site (including all effluent pathways and direct radiation) are less than the 40 CFR 190 Standard.
If the estimated doses exceed the above limits, the Speci_al Report shall include a request for a variance in accordance with the provisions of 40 CFR 190.
Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
SURVEILLANCE REQUIREMENTS Cumulative dose contributions from liquid and gaseous effluents and direct radiation from the Millstone Site shall be determined in accordance with Section II once per 31 days.
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SECTION IV.
Millstone Unit 2 Radiological Effluent Controls Docket Nos. 50-336 I\ ,\
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SECTION IY. REMO DCM UNIT TWO CONTROLS IV.A. Introduction The purpose of this section is to provide the following for Millstone Unit Two:
a. the effluent radiation monitor controls and surveillance requirements,
b. the effluent radioactivity concentration and dose controls and surveillance requirements, and
c. the bases for the controls and surveillance requirements.
Definitions of certain terms are provided as an aid for implementation of the controls and requirements.
Some surveillance requirements refer to specific sub-sections in Sections I and II as part of their required actions.
IV.B. Definitions, Applicability and Surveillance Requirements IV.B.l - Definitions The defined terms of this sub-section appear in capitalized type and are applicable throughout Section rv.
1. ACTION - Those additional requirements specified as corollary statements to each principal control and shall be part of the control.
2. FUNCTIONAL I FUNCTIONALITY - An instrument shall be FUNCTIONAL or have FUNCTIONALITY when it is capable of performing its specified functions(s) and when all necessary attendant instrumentation, controls, normal and emergency electrical power sources, or other auxiliary equipment that are required for the instrument to perform its functions are also capable of performing their related support functions.
3. CHANNEL CALIBRATION - A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to know values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.
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4. CHANNEL CHECK - A CHANNEL 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 instrument channels measuring the same parameter.
5. CHANNEL FUNCTIONAL TEST - A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify FUNCTIONALITY including alarm and/or trip functions. For digital instruments, the computer database may be manipulated, in lieu of a signal injection, to verify functionality of alarm
. and/or trip functions.
6. SOURCE CHECK - A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to radiation.
7. MEMBER(S) OF THE PUBLIC -*MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant.
This category does not include employees of the utility, its contractors or its vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.
The term "REAL MEMBER OF THE PUBLIC" means an individual who is exposed to existing dose pathways at one particular location.
8. MODE - Refers to Mode of Operation as defined in Safety Technical Specifications.
9. SITE BOUNDARY - The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee.
10. UNRESTRICTED AREA - Any area at or beyond the site boundary to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the site boundary used for residential quarters or industrial, commercial, institutional and/or recreational purposes.
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11. DOSE EQUIVALENT I-131 - DOSE EQUIVALENT I-131 shall be that concentration of I-131 (µCi/gram) which alone would produce the same CDE-thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed under Inhalation in Federal Guidance Report No. 11 (FGR 11), "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion and Ingestion."
IY.B.2 - Applicability IV.B.2a - LIMITING CONDITIONS FOR OPERATION
1. Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.
2. Noncompliance with a specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals, except as provided in Condition IY.B.2.a(6). If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.
3. NOTUSED.
4. NOTUSED.
5. When a system, subsystem, train, component or device is determined to be nonfunctional solely because its emergency power source is nonfunctional, or solely because its normal power source is nonfunctional, it may be considered FUNCTIONAL for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (1) its corresponding normal or emergency power source is FUNCTIONAL; and (2) all of its redundant system(s), subsystem(s), train(s), component(s) and device( s) are FUNCTIONAL, or likewise satisfy the requirements of this specification.
6. Equipment removed from service or declared nonfunctional to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its FUNCTIONALITY or the FUNCTIONALITY of other equipment. This is an exception to Condition IY.B.2.a(2) for the system returned to service under administrative control to perform the testing required to demonstrate FUNCTIONALITY.
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IV.B2.b - SURVEILLANCE REQUIREMENTS
1. Surveillance Requirements shall be applicable during any condition specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.
2. Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance time interval.
3. Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Condition IV.B2.b(2), shall constitute a failure to meet the FUNCTIONALITY requirements for a Limiting Condition for Operation. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
Surveillance Requirements do not have to be performed on nonfunctional equipment.
4. Entry into any specified condition shall not be made unless the Surveillance Requirement(s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.
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IV.C. Radioactive Effluent Monitoring Instrumentation
1. Radioactive Liquid Effluent Monitoring Instrumentation LIMITING CONDITIONS OF OPERATIONS The radioactive liquid effluent monitoring instrumentation channels shown in Table IV. C.-1 shall be FUNCTIONAL with applicable alarm/trip setpoints set to ensure that the limits of Specification IV.D.l.a. are not exceeded. The setpoints shall be determined in accordance with methods and parameters described in Section II.
APPLICABILITY: As shown in Table IV.C.-1 ACTION:
a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel nonfunctional, or change the setpoint so it is acceptably conservative.
b. With the number of channels less than the minimum channels FUNCTIONAL requirement, take the action shown in Table IV.C.-1.
Exert best efforts to restore the nonfunctional monitor to FUNCTIONAL status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the nonfunctionality was not corrected in a timely manner. Releases need not be terminated after 30 days provided the specified actions are continued.
SURVEILLANCE REQUIREMENTS Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table IV.C.-2.
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TABLE N.C.-1 Radioactive Liquid Effluent Monitoring Instrumentation Action when not Instrument Notes functional I.Gross Radioactivity Monitors Providing Alarm and Automatic Termination Of Release (a) Clean Liquid Radwaste Effluent Line A 1 (b )Aerated Liquid Radwaste Effluent Line A 2 (c) Steam Generator Blowdown Monitor B 2 (d)Condensate Polishing Facility Waste Neut Sump E 2 2.Gross Radioactivity Monitors Providing Alarm and Not Providing Automatic Termination Of Release (a)Reactor Building Closed Cooling Water Monitor C 1 3.Flow Rate Measurements - No Alarm Setpoint Requirements (a) Clean Liquid Radwaste Effluent Line D 1 (b )Aerated Liquid Radwaste Effluent Line D 1 (c) Condensate Polishing Facility D 1
1. Required to be functional at all times - which means that channels shall be FUNCTIONAL and in service on a continuous, uninterrupted basis, except that outages are permitted, for a maximum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , for the purpose of maintenance and performance of required test, checks, calibrations, or sampling associated with the instrument or any system or component which affects functioning of the instrument.
2. Required to be functional whenever the discharge pathway is being used except that outages are permitted, for a maximum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , for the purpose of maintenance and performance of required test, checks, calibrations, or sampling associated with the instrument or any system or component which affects functioning of the instrument.
ACTION STATEMENTS Action A With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirements, effluent releases may continue provided that best efforts are made to repair the instrument and that prior to initiating a release:
. (1) At least two independent samples are analyzed for gamma radioactivity as specified in Table I.C.-2, and; (2) The original release rate calculations and discharge valving are independently verified by a second individual.
Action B With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, either:
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(1) Suspend all effluent releases via this pathway, or (2) Make best efforts to repair the instrument and obtain grab samples and analyze for gamma radioactivity as specified in Table I.C.-2; a) Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01 µCi/gm DOSE EQUIVALENT 1-131.
b) Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 µCi/gm DOSE EQUIVALENT 1-131.
Action C With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months grab samples of the seNice water effluent are collected and analyzed for gamma radioactivity at LLD as specified in Table I.C.-2; Action D With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that the flow rate is estimated once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves may be used to estimate flow.
Action E With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirements, effluent releases may continue provided that best efforts are made to repair the instrument and that prior to initiating a release:
(1) At least two independent samples are analyzed for gamma radioactivity as specified in Table I.C.-2, and; (2) If one of the samples has gamma radioactivity greater than any of the LLDs in Table I.C. -2, the original release rate calculations and discharge valving are independently verified by a second individual.
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TABLE Iv.C.-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Instrument Channel Source Channel Channel Check Check Calibration Functional Test I.Gross Radioactivity Monitors Providing Alarm and Automatic Termination Of Release
a. Clean Liquid Radwaste Effluent Line D* p R(l) Q(2)
b. Aerated Liquid Radwaste Effluent D* p R(l) Q(2)
Line
c. Steam Generator Blowdown Monitor D* M R(l) Q(2) d.Condensate Polishing Facility Waste D* p R(l) Q(2)
Neut Sump 2.Gross Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination Of Release
a. Reactor Building Closed Cooling D* M R(l) Q(2)
Water Monitor 3.Flow Rate Measurements
a. Clean Liquid Radwaste Effluent Line '
D* NIA R Q
b. Aerated Liquid Radwaste Effluent D* NIA R Q Line
c. Condensate Polishing Facility Waste D* NIA R Q Neut Sump D = Daily R = Once every 18 months M Monthly Q = Once every 3 months P = Prior to each batch release N/A= Not Applicable TABLE Iv.C.-2 TABLE NOTATION
During releases via this pathway and when the monitor is required FUNCTIONAL per Table IV.C.-1. The CHANNEL CHECK should be done when the discharge is in progress ..
(1) Calibration shall include the use of a radioactive liquid or solid source which is traceable to an NIST source.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:
a) Instrument indicates measured levels above the alarm/trip setpoint.
b) Instrument indicates a downscale or circuit failure.
- Automatic isolation of the discharge stream shall also be demonstrated for this case for each monitor except the reactor building closed cooling water monitor.
2. Radioactive Gaseous Effluent Monitoring Instrumentation LIMITING CONDITIONS OF OPERATIONS The radioactive gaseous effluent monitoring instrumentation channels shown in Table IVC.-3 shall be FUNCTIONAL with applicable alarm setpoints set to ensure that the limits of Specifications IVD.2.a. are not exceeded. The setpoints shall be determined in accordance with methods and parameters described in Section II.
APPLICABILITY: As shown in Table IVC.-3 ACTION:
a. With a radioactive gaseous effluent monitoring instrumentation channel alarm setpoint less conservative than required by the above specification, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel nonfunctional, or change the setpoint so it is acceptably conservative.
b. With the number of channels less than the minimum channels FUNCTIONAL requirement, take the action shown in Table IVC.-3.
Exert best efforts to restore the nonfunctional monitor to FUNCTIONAL status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the nonfunctionality was not corrected in a timely manner. Release need not be terminated after 30 days provided the specified actions are continued.
SURVEILLANCE REQUIREMENTS Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table IVC.-4.
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TABLE J:v.C.-3 Radioactive Gaseous Effluent Monitoring Instrumentation Action when not Instrument Notes functional l.MP2 Vent (normal range, RM-8132 only; high range monitor, RM-8168, requirements are in the TS)
a. Noble Gas Radioactivity Monitor A 1, 3
b. Iodine Sampler B 1 C. Particulate Sampler B 1
d. Vent Flow Rate Monitor C 1
e. Sampler Flow Rate Monitor C 1 2.Millstone Stack - applicable to the WRGM (RM-8169, normal range, channel 1, only; mid range channel 2 and high range channel 3 requirements are contained in TRM LCO 3.3.3.8)
a. Noble Gas Radioactivity Monitor E 1, 3
b. Iodine Sampler B 1 C. Particulate Sampler B 1
d. Stack Flow Rate Monitor C 1
e. Sampler Flow Rate Monitor C 1 3.Waste Gas Holdup System
a. Noble Gas Monitor Providing Automatic Termination of D 2,4 Release 1 Required to be functional at all times when air is being released to the environment by the pathway being monitored. The channel shall be FUNCTIONAL and in service on a continuous, uninterrupted basis. Outages are permitted for a maximum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for the purpose of maintenance and performance of required tests, checks, calibrations, or sampling associated with the instrument or any system or component which affects functioning of the instrument.
2 Required to be functional during waste gas holdup system discharge.
3 Alarm setpoint with required. Automatic isolation feature is not required.
4 Alarm setpoint required. Automatic isolation feature is required.
ACTION STATEMENTS Action A With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that grab samples are taken once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gamma radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . If the monitor flow and readout are not adversely affected by the loss of functionality, the daily CHANNEL CHECK may be performed in lieu of the grab sample.
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Action B With the number of samplers FUNCTIONAL less than required by the Minimum number FUNCTIONAL requirement, effluent releases via this pathway may continue provided that the best efforts are made to repair the instrument and that effluent is continuously sampled with auxiliary sampling equipment and collected at least once per seven (7) days and analyzed for principal gamma emitters with half lives greater than 8 days within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after the end of the sampling period. Auxiliary sampling must be initiated within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of initiation of this action statement. Operation of the auxiliary sampling equipment shall be verified every twelve (12) hours. Auxiliary sampling outages are permitted for a maximum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for the purpose of maintenance and performance of required tests, checks, calibrations, or sampling.
Action C With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that the flow rate is estimated once per 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .
Sample flow rate need not be estimated if the auxiliary sampling equipment of Action B is in use.
Action D With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement:
Releases from the Millstone Unit 2 waste gas system may continue provided that best efforts are made to repair the instrument and that prior to initiating the release:
a) At least two independent samples of the tank's contents are analyzed; and b) The original release rate cal.culations and discharge valve lineups are independently verified by a second individual. Otherwise, suspend releases from the waste gas holdup system.
Action E With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, Millstone Unit 2 releases via the Millstone Stack may continue provided that best efforts are made to repair the instrument and that grab samples are taken once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gamma radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . If the monitor flow and readout are not adversely affected by the loss of functionality, th.e daily CHANNEL CHECK may be performed in lieu of the grab sample.
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TABLE IY.C.-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Channel Channel Source Channel Instrument Functional Check Check Calibration Test l.MP2 Vent (normal range, RM-8132 only; high range monitor, RM-8168, requirements are in the TS)
a. Noble Gas Radioactivity Monitor D M R(l) Q(2)
b. Iodine Sampler w NA NA NA
c. Particulate Sampler w NA NA NA
d. Vent Flow Rate Monitor D NA R Q
e. Sampler Flow Rate Monitor D NA R NA 2.Millstone Stack - applicable to the WRGM (RM-8169, normal range, channel 1, only; mid range channel 2 and high range channel 3 requirements are contained in TRM LCO 3.3.3.8)
a. Noble Gas Radioactivity Monitor D M R(l) Q(2)
b. Iodine Sampler w NA NA NA C. Particulate Sampler w NA NA NA
d. Stack Flow Rate Monitor D NA R Q
e. Sampler Flow Rate Monitor D NA R NA 3.Waste Gas Holdup System
a. Noble Gas Monitor D* p R(l) Q(:l)
During releases via this pathway and when the monitor is required FUNCTIONAL per Table IV.C.-3. The CHANNEL CHECK should be performed when the discharge is in progress.
P = Prior to discharge R = Once every 18 months D = Daily Q = Once every 3 months W = Weekly NA= Not Applicable M = Monthly TABLE IY.C.-4 TABLE NOTATION (1) Calibration shall include the use of a known source whose strength is determined by a detector which has been calibrated to a source which is traceable to the NIST. These sources shall* be in a known, reproducible geometry..
(2) The CHANNEL FUNCTION.AL TEST shall also demonstrate that control room alarm annunciation* occurs if any of the following conditions exist:
a) Instrument indicates measured levels above the alarm/trip setpoint.
b) Instrument indicates a downscale failure.
- Also demonstrate automatic isolation for the waste gas system noble gas monitor.
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IV.D. Radioactive Effluents Concentrations And Dose Limitations
1. Radioactive Liquid Effluents
a. Radioactive Liquid Effluents Concentrations LIMITING CONDITIONS OF OPERATIONS The concentration of radioactive material released from the site (see Figure IY.D.-1) shall not exceed ten times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall not exceed 2 x 10-4 µCi/ml total radioactivity.
APPLICABILITY: At all times.
ACTION:
With the concentration of radioactive material released from the site exceeding the above limits, restore the concentration to within the above limits within 15 minutes.
SURVEILLANCE REQUIREMENTS
1) Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program specified in Section I.
2) The results of the radioactive analysis shall be used in accordance with the methods of Section ILE to assure that the concentrations at the point of release are maintained within the limits of Specification IV.D.l.a.
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b. Radioactive Liquid Effluents Doses LIMITING CONDITIONS OF OPERATIONS The dose or dose commitment to any REAL MEMBER OF THE PUBLIC from radioactive materials in liquid effluents from Unit 2 released from the site (see Figure IV.D.-1) shall be limited:
a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ; and,
b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
APPLICABILITY: At all times.
ACTION:
a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits prepare and submit to the Commission within 30 days a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limit.
SURVEILLANCE REQUIREMENTS
1) Dose Calculations. Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in Section II at least once per 31 days.
2) Relative accuracy or conservatism of the calculations shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in Section I.
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2. Radioactive Gaseous Effluents
a. Radioactive Gaseous Effluents Dose Rate LIMITING CONDITIONS OF OPERATIONS The dose rate, at any time, offsite (see Figure IV.D.-1) due to radioactivity released in gaseous effluents from the site shall be limited to the following values:
a. The dose rate limit for noble gases shall be less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin; and,
b. The dose rate limit for Iodine-131, Iodine-133, Tritium, and for all radioactive materials in particulate form with half lives greater than 8 days shall be less than or equal to 1500 mrem/yr to any organ.
APPLICABILITY: At all times.
ACTION:
With the dose rate(s) exceeding the above limits, decrease the release rate to comply with the limit(s) given in Specification IV.D.2.a. within 15 minutes.
SURVEILLANCE REQUIREMENTS
1) The release rate, at any time, of noble gases in gaseous effluents shall be controlled by the offsite dose rate as established above in Specification IV.D.2.a. The corresponding release rate shall be determined in accordance with the methodology of Section II.
2) The noble gas effluent monitors of Table IY.C.-3 shall be used to control release rates to limit offsite doses within the values established in Specification IV.D.2.a.
3) The release rate of Iodine-131, Iodine-133, tritium and for all radioactive materials in particulate form with half lives greater than 8 days in gaseous effluents shall be determined by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Section I. The corresponding dose rate shall be determined using the methodology given in Section II.
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b. Radioactive Gaseous Effluents Noble Gas Dose LIMITING CONDITIONS OF OPERATIONS The air dose offsite (see Figure IY.D. -1) due to noble gases released in gaseous effluents from Unit 2 shall be limited to the following:
a. During any calendar quarter, to less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation;
b. During any calendar year to less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
APPLICABILITY: At all times.
ACTION:
a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits prepare and submit to the Commission within 30 days a Special Report which identifies the cause( s) for exceeding the limit( s) and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limit.
SURVEILLANCE REQUIREMENTS
1) Dose Calculations - Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section II once every 31 days.
2) Relative accuracy or conservatism of the calculations shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in S_ection I.
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c. Gaseous Effluents - Doses from Radionuclides Other than Noble Gas LIMITING CONDITIONS OF OPERATIONS The dose to any REAL MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, Tritium, C-14, and radioactive materials in particulate form with half lives greater than 8 days in gaseous effluents released offsite from Unit 2 (see Figure IY.D.-1) shall be limited to the following:
a. During any calendar quarter to less than or equal to 7.5 mrem to any organ;
b. During any calendar year to less than or equal to 15 mrem to any organ.
APPLICABILITY: At all times.
ACTION:
a. With the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding any of the above limits prepare and submit to the Commission within 30 days a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limit.
SURVEILLANCE REQUIREMENTS
1) Dose Calculations - Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section II once every 31 days.
2) Relative accuracy or conservatism of the calculations shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in Section I.
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Figure IY.D.-1, "Site Boundary for Liquid and Gaseous Effluents" JORDAN ~ov~
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IV.E. Total Radiological Dose From Station Operation CONTROLS The annual dose or dose commitment to any REAL MEMBER OF THE PUBLIC, beyond the site boundary, from the Millstone Site is limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which is limited to less than or equal to 75 mrem).
APPLICABILITY: At all times.
ACTION:
With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls IV.D.2.a., IV.D.l.b., or IV.D.2.c. prepare and submit a Special Report to the Commission within 30 days and limit the subsequent releases such that the dose commitment from the site to any REAL MEMBER OF THE PUBLIC from the Millstone Site is limited to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months.
This Special Report shall include an analysis which demonstrates that radiation exposures from the site to any REAL MEMBER OF THE PUBLIC from the Millstone Site (including all effluent pathways and direct radiation) are less than the 40 CFR 190.
If the estimated doses exceed the above limits, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190.
Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
SURVEILLANCE REQUIREMENTS Cumulative dose contributions from liquid and gaseous effluents and direct radiation from the Millstone Site shall be determined in accordance with Section II once per 31 days.
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SECTIONV.
Millstone Unit 3 Radiological Effluent Controls Docket Nos. 50-423 1
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SECTION V. REMO DCM UNIT THREE CONTROLS V.A. Introduction The purpose of this section is to provide the following for Millstone Unit Three:
a. the effluent radiation monitor controls and surveillance requirements,
b. the effluent radioactivity concentration and dose controls and surveillance requirements, and
c. the bases for the controls and surveillance requirements.
Definitions of certain terms are provided as an aid for implementation of the controls and requirements.
Some surveillance requirements refer to specific sub- sections in Sections I and II as part of their required actions.
V.B. Definitions and Applicability and Surveillance Requirements V.B.1 - Definitions The defined terms of this sub-section appear in capitalized type and are applicable throughout Section V.
1. ACTION - ACTION shall be that part of the control which prescribes remedial measures required under designated conditions.
2. CHANNEL FUNCTIONAL TEST - A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify FUNCTIONALITY of alarm, interlock and/or trip functions. For digital instruments, the computer database may be manipulated, in lieu of a signal injection, to verify functionality of alarm and/or trip functions.
The CHANNEL FUNCTIONAL TEST shall include adjustments, as necessary, of the alarm, interlock and/or trip setpoints such that the setpoints are within the required range and accuracy.
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3. CHANNEL CALIBRATION - A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip functions and may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.
4. CHANNEL CHECK - A CHANNEL 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 instrument channels measuring the same parameter.
5. DOSE EQUIVALENT I-131 - DOSE EQUIVALENT I-131 shall be that concentration of I-131 (µCi/gram) which alone would produce the same CDE-thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed under Inhalation in Federal Guidance Report No. 11 (FGR 11 ), "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion and Ingestion."
6. MEMBER(S) OF THE PUBLIC - MEMBER(S) OF. THE PUBLIC shall include all persons who are not occupationally associated with the plant.
This category does not include employees of the licensee, its contractors or its vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.
The term "REAL MEMBER OF THE PUBLIC" means an individual who is exposed to existing dose pathways at one particular location.
7. MODE - Refers to Mode of Operation as defined in Safety Technical Specifications.
8. FUNCTIONAL - FUNCTIONALITY - An instrument shall be FUNCTIONAL or have FUNCTIONALITY when it is capable of performing its specified functions(s) and when all necessary attendant instrumentation, controls, electrical power, or other auxiliary equipment that are required for the instrument to perform its functions(s) are also capable of performing their related support function(s).
9. SITE BOUNDARY - The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee.
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10. SOURCE CHECK - A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to radiation.
11. UNRESTRICTED AREA - Any area at or beyond the SITE BOUNDARY to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the SITE BOUNDARY used for residential quarters or industrial, commercial, institutional and/or recreational purposes.
V.B.2 - Applicability V.B.2.a - LIMITING CONDITIONS FOR OPERATION
1. Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.
2. Noncompliance with a specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals. If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.
V.B.2.b - SURVEILLANCE REQUIREMENTS
1. Surveillance Requirements shall be applicable during any condition specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.
2. Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance time interval.
3. Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Condition V.B.2.b(2), shall constitute a failure to meet the FUNCTIONALITY requirements for a Limiting Condition for Operation. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
Surveillance Requirements do not have to be performed on nonfunctional equipment.
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4. Entry into any specified condition shall not be made unless the Surveillance Requirement(s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.
V.C. Radioactive Effluent Monitoring Instrumentation
1. Radioactive Liquid Effluent Monitoring Instrumentation LIMITING CONDITIONS OF OPERATION The radioactive liquid effluent monitoring instrumentation channels shown in Table V.C.-1 shall be FUNCTIONAL with their Alarm/Trip setpoints set to ensure that the limits of Specification V.D.l.a are not exceeded. The alarm/trip setpoints shall be determined in accordance with methodology and parameters as described in Section IL APPLICABILITY: As shown in Table V.C.-1 ACTION:
a. With a radioactive liquid effluent monitoring instrumentation channel Alarm/Trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel nonfunctional, or change the setpoint so it is acceptably conservative.
b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels FUNCTIONAL, take the action shown in Table V.C.-1. Exert best efforts to restore the nonfunctional instrumentation to FUNCTIONAL status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the nonfunctionality was not corrected in a timely manner. Releases need not be terminated after 30 days provided the specified actions are continued.
SURVEILLANCE REQUIREMENTS Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL OPERATIONAL TEST at the frequencies shown in Table V.C.-2.
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TABLE V.C.-1 Radioactive Liquid Effluent Monitoring Instrumentation Action when Instrument Notes not functional l.Radioactivity Monitors Providing Alarm and Automatic Termination Of Release
a. Waste Neutralization Sump Monitor Condensate Polishing Facility D 2
b. Turbine Building Floor Drains B 1 C. Liquid Waste Monitor A 1
d. RESERVED
e. Steam Generator Blowdown Monitor B 3 2.Flow Rate Measurement Devices - No Alarm Setpoint Requirements
a. Waste Neutralization Sump Effluents C 1
b. RESERVED C. Liquid Waste Effluent Line C 1
d. RESERVED
e. Steam Generator Blowdown Effluent Line C 3 1 Required to be functional at all times - which means that channels shall be FUNCTIONAL and in service on a continuous, uninterrupted basis, except that outages are permitted, for a maximum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , for the purpose of maintenance and performance of required test, checks, calibrations, or sampling associated with the instrument or any system or component which affects functioning of the instrument.
2 Required to be functional in MODEs 1-5, and MODE 6 when discharge pathway is being used, except that outages are permitted, for a maximum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , for the purpose of maintenance and performance of required test, checks, calibrations, or sampling associated with the instrument or any system or component which affects functioning of the instrument.
The monitor must be on-line with no unexpected alarms.
3 Required to be functional whenever the discharge pathway is being used, except that outages are permitted, for a maximum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , for the purpose of maintenance and performance of required test, checks, calibrations, or sampling associated with the instrument or any system or component which affects functioning of the instrument. The monitor must be on-line with no unexpected alarms.
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TABLE V.C.-1 ACTION STATEMENTS Action A With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirements, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that prior to initiating a release:
1. At least two independent samples are analyzed for gamma radioactivity as specified in Table I.C-3, and;
2. The original release rate calculations and discharge line valving are independently verified by a second individual.
Action B With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided best efforts are made to repair the instrument and that grab samples are analyzed for gamma radioactivity specified in Table I.C. -3:
1. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01 µCi/gram DOSE EQUIVALENT 1-131, or
2. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 µCi/gram DOSE EQUIVALENT 1-131.
Action C With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves may be used to estimate flow.
Action D With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirements, effluent releases may continue provided that best efforts are made to repair the instrument and that prior to initiating a release:
1. At least two independent samples are analyzed for gamma radioactivity as specified in Table I.C-3, and;
2. If one of the samples has gamma radioactivity greater than any of the lower limits of detection specified in Table I.C.-3, the original release rate calculations and discharge valving are independently verified by a second individual.
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TABLE V.C.-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Instrument Channel Source Channel Channel Check Check Calibration Functional Test l.Radioactivity Monitors Providing Alarm and Automatic Termination Of Release
a. Waste Neutralization Sump Monitor D p R(2) Q(l)
Condensate Polishing Facility
b. Turbine Building Floor Drains D M R(2) Q(l)
C. Liquid Waste Monitor D p R(2) Q(l)
d. Deleted
e. Steam Generator Blowdown Monitor D M R(2) Q(l) 2.Flow Rate Measurements
a. Waste Neutralization Sump Effluents D(3) NA R Q
b. RESERVED
c. Liquid Waste Effluent Line D(3) NIA R Q
d. Deleted
e. Steam Generator Blowdown Effluent D(3) NIA R Q Line D Daily R = Once every 18 months M Monthly Q = Once every 3 months P = Prior to each batch release N/A= Not Applicable TABLE V.C.-2 TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:
a) Instrument indicates measured levels above the alarm/trip setpoint, or b) Circuit failure (Alarm only), or Instrument indicates a downscale failure (Alarm only).
(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities of NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made.
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2. Radioactive Gaseous Effluent Monitoring Instrumentation LIMITING CONDITIONS OF OPERATION The radioactive gaseous effluent monitori:µg instrumentation channels shown.
in Table V.C.-3 shall be FUNCTIONAL with their Alarm Setpoints set to ensure that the limits of Specification V.D.2.a. are not exceeded. The Alarm Setpoints of these channels shall be determined in accordance with the methodology and parameters in Section II.
APPLICABILITY: As shown in Table V.C.-3.
ACTION:
a. With a radioactive gaseous effluent monitoring instrumentation channel Alarm Setpoint less conservative than required by the above specification, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel nonfunctional, or change the setpoint so it is acceptably conservative.
b. With the number of FUNCTIONAL radioactive gaseous effluent monitoring instrumentation channels less than the Minimum Channels FUNCTIONAL, take the ACTION shown in Table V.C.-3. Exert best efforts to restore the nonfunctional instrumentation to FUNCTIONAL status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the nonfunctionality was not corrected in a timely manner. Release need not be terminated after 30 days provided the specified actions are continued. .
SURVEILLANCE REQUIREMENT Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table V.C.-4 .
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TABLE V.C.-3 Radioactive Gaseous Effluent Monitoring Instrumentation Instrument Action when Notes not functional I.Millstone Unit 3 Ventilation Vent (Turbine Building - HVR-RElOB, normal range only; high range monitor, HVR-RElOA, requirements are in the TRM)
a. Noble Gas Radioactivity Monitor Providing Alarm A 1,2
b. Iodine Sampler B 1,2 C. Particulate Sa:i;npler B 1,2
d. Vent Flow Rate Monitor C 1, 2
e. Sampler Flow Rate Monitor C 1 2.Millstone Stack - applicable to SLCRS (HVR-RE19B, normal range only; high range monitor, HVR-RE19A, requirements are in the TRM)
a. Noble Gas Radioactivity Monitor Providing Alarm A 1, 2
b. Iodine Sampler B 1, 2 C. Particulate Sampler B 1, 2
d. Process Flow Rate Monitor C 1,2
e. Sampler Flow Rate Monitor C 1 3.Engineered Safeguards Building Monitor (HVQ-RE49)
a. Noble Gas Radioactivity Monitor D 1
b. Iodine Sampler B 1 C. Particulate Sampler B 1
d. Discharge Flow Rate Monitor E 1
e. Sampler Flow Rate Monitor C 1 TABLE V.C. -3 Table Notations 1 Instrument required to be functional whenever the release path is in service. Outages are permitted for a maximum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for the purpose of maintenance and performance of required tests, checks, calibrations, or sampling associated with the instrument or any system or component which affects functioning of the instrument.
2 When the Ventilation Vent Flow Rate Monitor or Millstone Stack Process Flow Rate Monitor is nonfunctional because of degraded flow indication, the Noble Gas Monitor and Iodine and Particulate Samplers for the affected pathway (Ventilation Vent or Millstone Stack) remain functional as long as there is a minimum indicated process flow.
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TABLE V.C.-3 ACTION STATEMENTS Action A With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided that a) best efforts are made to repair the instrument and that grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gamma radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , OR b) if the cause of the nonfunctionality is solely due to a loss of annunciation in the control room and the Remote Indicating Controller (RIC) remains FUNCTIONAL, perform a channel check at the RIC at least once per twelve hours and verify the indication has not alarmed.
Action B With the number of samplers FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided that the best efforts are made to repair the instrument and that effluent is continuously sampled with auxiliary sampling equipment at least once per seven (7) days and analyzed for principal gamma emitters with half lives greater than 8 days within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after the end of the sampling period. Auxiliary sampling must be initiated within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after initiation of this ACTION statement. Operation of the auxiliary sampling equipment shall be verified every twelve (12) hours. Auxiliary sampling outages are permitted for a maximum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for the purpose of maintenance and performance of required tests, checks, calibrations, or sampling.
Action C With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that the flow rate is estimated at least once per 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . Sample flow rate need not be estimated if the auxiliary sampling equipment of Action B is in use.
Action D With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gamma radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
Action E With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument.
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TABLE V.C.-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Instrument Channel Source- Channel Channel When Check Check Calibra- Functional Surveil-tion Check lance is Required l.Millstone Unit 3 Ventilation Vent (Turbine Building - HVR-RElOB, normal range only; high range monitor, HVR-RElOA, requirements are in the TRM)
a. Noble Gas Radioactivity Monitor D M R(l) Q(2)
Providing Alarm
b. Iodine Sampler w NA NA NA *
c. Particulate Sampler w NA NA NA *
d. Vent Flow Rate Monitor D NA R Q *
e. Sampler Flow Rate Monitor D NA R Q
2.Millstone Stack - applicable to SLCRS (HVR-RE19B, normal range only; high range monitor, HVR-RE19A, requirements are in the TRM)
a. Noble Gas Radioactivity Monitor D M R(3) Q(2)
Providing Alarm
b. Iodine Sampler w NA NA NA *
c. Particulate Sampler w NA NA NA *
d. Process Flow Rate Monitor D NA R Q *
e. Sampler Flow Rate Monitor D NA R Q **
3.Engineered Safeguards Building Monitor (HVQ-RE49)
a. Noble Gas Radioactivity Monitor D M R(l) Q(2)
Providing Alarm
b. Iodine Sampler w NA NA NA
C. Particulate Sampler w NA NA NA *
d. Discharge Flow Rate Monitor D NA R Q *
e. Sampler Flow Rate Monitor D NA R Q *
At all times except when the vent path is isolated.
D = Daily R = Once every 18 months W = Weekly Q = Once every 3 months M Monthly N/A= Not Applicable 1\ A I>
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TABLE V.C.-4 Table Notations
("1) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities of NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
{2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:
a) Instrument indicates measured levels above the Alarm Setpoint, or b) Circuit failure, or c) Instrument indicates a downscale failure.
{3) The CHANNEL CALIBRATION shall include the use of a known source whose strength is determined by a detector which has been calibrated to an NIST source. These sources shall be in know, reproducible geometry.
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V.D. Radioactive Effluents Concentrations And Dose Limitations
1. Radioactive Liquid Effluents
a. Radioactive Liquid Effluents Concentrations LIMITING CONDITIONS OF OPERATION The concentration of radioactive material released from the site (see Figure V.D. -1) shall be limited to ten times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall not exceed 2 x 10-4 µCi/ml total radioactivity.
APPLICABILITY: At all times.
ACTION:
With the concentration of radioactive material released from the site exceeding the above limits, restore the concentration to within the above limits within 15 minutes.
SURVEILLANCE REQUIREMENTS
1) Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program specified in Section I.
2) The results of the radioactive analysis shall be used in accordance with the methods of Section ILE to assure that the concentrations at the point of release are maintained within the limits of Specification V.D.l.a.
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b. Radioactive Liquid Effluents Doses LIMITING CONDITIONS OF OPERATION The dose or dose commitment to any REAL MEMBER OF THE PUBLIC from radioactive materials in liquid effluents from Unit 3 released from the site (see Figure V.D.-1) shall be limited:
a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ; and,
b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
APPLICABILITY: At all times.
ACTION:
a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits prepare and submit to the Commission within 30 days a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limit.
SURVEILLANCE REQUIREMENTS
1) Dose Calculations. Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in Section II at least once per 31 days.
2) Relative accuracy or conservatism of the calculations shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in Section I.
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2. Radioactive Gaseous Effluents
a. Radioactive Gaseous Effluents Dose Rate LIMITING CONDITIONS OF OPERATION The dose rate, at any time, offsite (see Figure V.D.-1) due to radioactivity released in gaseous effluents from the site shall be limited to the following values:
a. The dose rate limit for noble gases shall be less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin; and,
b. The dose rate limit due to inhalation for Iodine-131, Iodine-133, Tritium, and for all radioactive materials in particulate form with half lives greater than 8 days shall be less than or equal to 1500 mrem/yr to any organ.
APPLICABILITY: At all times.
ACTION:
With the dose rate(s) exceeding the above limits, decrease the release rate to comply with the limit(s) given in Specification V.D.2.a. within 15 minutes.
SURVEILLANCE REQUIREMENTS
1) The release rate, at any time, of noble gases in gaseous effluents shall be controlled by the offsite dose rate as established in Specification V.D.2.a. The corresponding release rate shall be determined in accordance with the methodology of Section II.
2) The noble gas effluent monitors of TableV.C.-3 shall be used to control release rates to limit offsite doses within the values established in Specification V.D.2.a.
3) The release rate of Iodine-131, Iodine-133, tritium, and for all radioactive materials in particulate form with half lives greater than 8 days in gaseous effluents shall be determined by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Section I. The corresponding dose rate shall be determined using the methodology given in Section II.
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b. Radioactive Gaseous Effluents Noble Gas Dose LIMITING CONDITIONS OF OPERATION The air dose offsite (see Figure V.D. -1) due to noble gases released from Unit 3 in gaseous effluents shall be limited to the following:
a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and
b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
APPLICABILITY: At all times.
ACTION:
a. With the calculated air dose froni radioactive noble gases in gaseous effluents exceeding any of the above limits prepare and submit to the Commission within 30 days a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limit.
SURVEILLANCE REQUIREMENTS
1) Dose Calculations - Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section II once every 31 days.
2) Relative accuracy or conservatism of the calculations shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in Section I.
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c. Gaseous Effluents - Doses from Radionuclides Other than Noble Gas LIMITING CONDITIONS OF OPERATION The dose to any REAL MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, Tritium, C-14, and radioactive materials in particulate form with half lives greater than 8 days in gaseous effluents released offsite from Unit 3 released offsite (see Figure V.D.-1) shall be limited to the following:
a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and,
b. During any calendar year: Less than or equal to 15 mrem to any organ.
APPLICABILITY: At all times.
ACTION:
c. With the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding any of the above limits prepare and submit to the Commission within 30 days a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limit.
SURVEILLANCE REQUIREMENTS
1) Dose Calculations - Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section II once every 31 days.
2) Relative accuracy or conservatism of the calculations shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in Section I.
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Figure V.D. -1, "Site Boundary for Liquid and Gaseous Effluents"
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V.E. Total Radiological Dose From Station Operations CONTROLS The annual dose or dose commitment to any REAL MEMBER OF THE PUBLIC, beyond the site boundary, from the Millstone Site is limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which is limited to less than or equal to 75 mrem).
APPLICABILITY: At all times.
ACTION:
With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls V.D.l.b., V.D.2.b., or V.D.2.c. prepare and submit a Special Report to the Commission within 30 days and limit the subsequent releases such that the dose commitment from the site to any REAL MEMBER OF THE PUBLIC from the Millstone Site is limited to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months.
This Special Report shall include an analysis which demonstrates that radiation exposures from the site to any REAL MEMBER OF THE PUBLIC from the Millstone Site (including all effluent pathways and direct radiation) are less than the 40 CFR 190 Standard.
If the estimated doses exceed the above limits, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190.
Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
SURVEILLANCE REQUIREMENTS Cumulative dose contributions from liquid and gaseous effluents and direct radiation from the Millstone Site shall be determined in accordance with Section II once per 31 days.
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ML19122A385

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