Text

LaSalle County, Units 1 and 2 - 2016 Annual Radioactive Effluent Release Report, Part 9
	ML17117A586
Person / Time
Site:	LaSalle
Issue date:	04/27/2017
From:	; Exelon Generation Co
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML17117A559	List: ML17117A560; ML17117A562; ML17117A568; ML17117A570; ML17117A571; ML17117A574; ML17117A581; ML17117A582; ML17117A583; ML17117A584; ML17117A586; ML17117A588; ML17117A589; ML17117A592; ML17117A593; ML17117A594; ML17117A595; ML17117A597; RA17-040, 2016 Annual Radioactive Effluent Release Report, Part 17;
References
	RA17-040
	Download: ML17117A586 (60)
	v • d • e

NRG RA17-040 2016 Annual Radioactive Effluent Release Report Part 9 CY-LA-170-301 Revision 7 January 2016 Part II, Offsite Dose Calculation Manual 6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program for the environs around LaSalle Station is given in Table 6-1. Figure 6-1 through Figure 6-3 show sampling and monitoring locations.

11.6-1 LaSalle ODCM Part II Section 6 Exposure Pathway and/or Sample 1. Airborne a.Radioiodine and 1 ). Particulates

2. 3. CY-LA-170-301 Revision 7 January 2016 Part II, Offsite Dose Calculation Manual Table 6-1 (Page 1 of 8) Radiological Environmental Monitoring Program Sample or Monitoring Location Sampling or Collection Type and Frequency of Frequency Analysis Continuous sampler Radioiodine Canisters:

operation with particulate Indicators-Near Field sample collection weekly, 1-131 analysis weekly on or more frequently if near field and control L-01, Nearsite No. 1, 1.5 mi (2.4 km) NNW (N 41° 16.016', W 88° 40.920') required by dust loading, samples 1* L-03, Onsite No. 3, 1.0 mi (1.6 km) ENE (N 41° 15.145', W 88° 39.174') and radioiodine canister L-05, Onsite No. 5, 0.3 mi (0.5 km) ESE (N 41° 14.520', W 88° 39.355') collection weekly. Particulate Samgler: L-06, Nearsite No. 6, 0.4 mi (0.6 km) W (N 41° 14.602', W 88° 41.056') Gross beta analysis weekly filter change and gamma isotopic analysis 3 quarterly on composite filters by location on near field and control samples.1 Indicators-Far Field L-04, Rte 170, 3.2 mi (5.1 km) E (N 41° 15.243', W 88° 36.451 ') L-07, Seneca, 5.2 mi (8.4 km) NNE (N 41° 19.093', W 88° 36.473') L-08, Marseilles, 6.0 mi (9.7 km) NNW (N 41° 19.645', W 88° 42.925') L-11A, Ransom, 6.0 mi (9.7 km) S (N 41° 09.405', W 88° 39.565') Controls L-10, Streator, 13.5 mi (21.7 km) SW (N 41° 06.642', W 88° 49.481') 11.6-2 LaSalle ODCM Part II Section 6 Exposure Pathway and/or Sample 2. Direct Radiation

a. Field Dosimeter LaSalle ODCM Part II Section 6 Table 6-1 (Page 2 of 8) Radiological Environmental Monitoring Program CY-LA-170-301 Revision 7 January 2016 Part II, Offsite Dose Calculation Manual Sample or Monitoring Location Sampling or Collection Type and Frequency of Frequency Analysis 1) Indicators-Inner Ring Quarterly Gamma dose on each Field L-101-1, 0.5 mi (0.8 km) N (N 41° 15.084', W 88°40.087')

Dosimeter quarterly.

L-101-2, 0.5 mi (0.8 km) N (N 41° 15.084', W 88°40.087')

L-102-1, 0.6 mi (1.0 km) NNE (N 41° 15.226', W 88°39.915' L-102-2, 0.6 mi (1.0 km) NNE (N 41° 15.226', W 88°39.915' L-103-1, 0.7 mi (1.1 km) NE (N 41° 15.168', W 88°39.492')

L-103-2, 0.7 mi (1.1 km) NE (N 41° 15.168', W 88°39.492')

L-104-1, 0.8 mi (1.3 km) ENE (N 41° 15.138', W 88°39.185')

L-104-2, 0.8 mi (1.3 km) ENE (N 41° 15.138', W 88°39.185')

L-105-1, 0.7 mi (1.1 km) E (N 41° 14.724', W 88°39.425')

L-105-2, 0.7 mi (1.1 km) E (N 41° 14.724', W 88°39.425')

L-106-1, 1.4 mi (2.2 km) ESE (N 41° 14.328', W 88°38.751')

L-106-2, 1.4 mi (2.2 km) ESE (N 41° 14.328', W 88°38.751')

L-107-1, 0.8 mi (1.3 km) SE (N 41° 14.308', W 88°39.502')

L-107-2, 0.8 mi (1.3 km) SE (N 41° 14.308', W 88°39.502')

L-108-1, 0.5 mi (0.8 km) SSE (N 41° 14.305', W 88°39.825')

L-108-2, 0.5 mi (0.8 km) SSE (N 41° 14.305', W 88°39.825')

L-109-1, 0.6 mi (1.0 km) S (N 41° 14.299', W 88°40.106')

L-109-2, 0.6 mi (1.0 km) S (N 41° 14.299', W 88°40.106')

L-110-1, 0.6 mi (1.0 km) SSW (N 41° 14.290', W 88°40.388')

L-110-2, 0.6 mi (1.0 km) SSW (N 41°14.290', W 88°40.388')

L-111b-1, 0.8 mi (1.3 km) SW (N 41° 14.277', W 88°40.878')

L-111b-2, 0.8 mi (1.3 km) SW (N 41°14.277', W 88°40.878')

L-112-1, 0.9 mi (1.4 km) WSW (N 41° 14.403', W 88°41.050')

L-112-2, 0.9 mi (1.4 km) WSW (N 41°14.403', W 88°41.050')

L-113a-1, 0.8 mi (1.3 km) W (N 41° 14.658', W 88°41.055')

L-113a-2, 0.8 mi (1.3 km) W (N 41° 14.658', W 88°41.055')

L-114-1, 0.9 mi (1.4 km) WNW (N 41°14.991', W 88°41.070')

L-114-2, 0.9 mi (1.4 km) WNW (N 41°14.991', W 88°41.070')

L-115-1, 0.7 mi (1.1 km) NW (N 41° 15.054', W 88°40.529')

L-115-2, 0.7 mi (1.1 km) NW (N 41° 15.054', W 88°40.529')

L-116-1, 0.6 mi (1.0 km) NNW (N 41°15.210', W 88°40.366')

L-116-2, 0.6 mi (1.0 km) NNW (N 41° 15.210', W 88°40.366')

11.6-3 Exposure Pathway and/or Sample Table 6-1 (Page 3 of 8} Radiological Environmental Monitoring Program CY-LA-170-301 Revision 7 January 2016 Part II, Offsite Dose Calculation Manual Sample or Monitoring Location Sampling or Collection Type and Frequency of Frequency Analysis 2. Direct Radiation

2) Indicators-Outer Ring Quarterly Gamma dose on each Field (Cont'd) L-201-3, 4.0 mi (6.4 km) N (N 41° 18.205', W 88°40.162')

Dosimeter quarterly.

a. Field Dosimeter L-201-4, 4.0 mi (6.4 km) N (N 41° 18.205', W 88°40.162')

L-202-3, 3.6 mi (5.8 km) NNE (N 41° 17.793', W 88°38.287')

L-202-4, 3.6 mi (5.8 km) NNE (N 41° 17.793', W 88°38.287')

L-203-1, 4.0 mi (6.4 km) NE (N 41° 17.291', W 88°36.311')

L-203-2, 4.0 mi (6.4 km) NE (N 41° 17.291', W 88°36.311')

L-204-1, 3.2 mi (5.2 km) ENE (N 41° 15.346', W 88°36.442')

L-204-2, 3.2 mi (5.2 km) ENE (N 41° 15.346', W 88°36.442')

L-205-1, 3.2 mi (5.2 km) ESE (N 41° 14.144', W 88°36.410')

L-205-2, 3.2 mi (5.2 km) ESE (N 41° 14.144', W 88°36.410')

L-205-3, 5.1 mi (8.2 km) E (N 41° 14.774', W 88°34.209')

L-205-4, 5.1 mi (8.2 km) E (N 41° 14.774', W 88°34.209')

L-206-1, 4.3 mi (6.9 km) SE (N 41° 12.825', W 88°36.388')

L-206-2, 4.3 mi (6.9 km) SE (N 41° 12.825', W 88°36.388')

L-207-1, 4.5 mi (7.2 km) SSE (N 41° 11.476', W 88°37.546')

L-207-2, 4.5 mi (7.2 km) SSE (N 41° 11.476', W 88°37.546')

L-208-1, 4.5 mi (7.2 km) S (N 41° 10.818', W 88°39.432')

L-208-2, 4.5 mi (7.2 km) S (N 41° 10.818', W 88°39.432')

L-209-1, 4.0 mi (6.4 km) SSW (N 41° 11.662', W 88°41.173')

L-209-2, 4.0 mi (6.4 km) SSW (N 41° 11.662', W 88°41.173')

L-210-1, 3.3 mi (5.3 km) SW (N 41° 12.519', W 88°42.364')

L-210-2, 3.3 mi (5.3 km) SW (N 41° 12.519', W 88°42.364')

L-211-1, 4.5 mi (7.2 km) WSW (N 41° 12.557', W 88°44.489')

L-211-2, 4.5 mi (7.2 km) WSW (N 41° 12.557', W 88°44.489')

L-212-1, 4.0 mi (6.4 km) W(N 41° 14.095', W 88°44.508')

L-212-2, 4.0 mi (6.4 km) W (N 41° 14.095', W 88°44.508')

L-213-3, 4.9 mi (7.9 km) W (N 41° 14.402', W 88°45.674')

L-213-4, 4.9 mi (7.9 km) W (N 41° 14.402', W 88°45.674')

L-214-3, 5.1 mi (8.2 km) WNW (N 41° 16.028', W 88°45.708')

L-214-4, 5.1 mi (8.2 km) WNW (N 41° 16.028', W 88°45.708')

L-215-3, 5.0 mi (8.0 km) NW (N 41° 17.760', W 88°44.133')

L-215-4, 5.0 mi (8.0 km) NW (N 41° 17.760', W 88°44.133')

L-216-3, 5.0 mi (8.0 km) NNW (N 41° 18.823', W 88°42.087')

L-216-4, 5.0 mi (8.0 km)NNW (N 41° 18.823', W 88°42.087')

11.6-4 LaSalle ODCM Part II Section 6 Exposure Pathway and/or Sample 2. Direct Radiation (Cont'd) a. Field Dosimeter Table 6-1 (Page 4 of 8) Radiological Environmental Monitoring Program Sample or Monitoring Location Sampling or Collection Frequency

3) Indicators

-Other Quarterly One at each of the airborne location given in part 1.a.1 and 1.a.2 4 ). Controls One at each airborne control location given in part 1.a.3 11.6-5 LaSalle ODCM Part II Section 6 CY-LA-170-301 Revision 7 January 2016 Part II, Offsite Dose Calculation Manual Type and Frequency of Analysis Gamma dose on each Field Dosimeter quarterly.

Exposure Pathway and/or Sample 3. Waterborne

a. Ground/Well

b. Drinking Water c. Surface Water d. Sediments Table 6-1 (Page 5 of 8) Radiological Environmental Monitoring Program Sample or Monitoring Location Sampling or Collection Frequency

1) Indicators Quarterly L-27, LSCS Onsite Well at Station (N 41

14.665'. w as* 40.127') L-28 #6, Marseilles Well, 4.1 mi (11.3 km ) N (N 41* 1a.215', was* 39.430') 2) Control L-28 #4, Marseilles Well, 7.0 mi (10.9 km) NNW (N 41* 20.367', was* 42.054') L-28 #5, Marseilles Well, 6.7 mi (10.km) NNW (N 41

20.142'. w as* 42.563') There is no drinking water pathway within 6.2 mi (10 km) downstream of station. 1) Indicator L-40, Illinois River downstream, Weekly grab sample 5.2 mi (8.4 km) NNW (N 41

19.230', w as* 42.048') 2) Control L-21, Illinois River at Seneca, 4.0 mi (6.4 km) NE (N 41*11.a92*, was* 36.308') 1) Indicators L-40, Illinois River downstream, 5.2 mi (8.4 km) NNW (N 41

19.230*. w as* 42.048') L-41, Illinois River downstream 4.6 mi (7.4 km) N Semiannually (N 41

18.678'. was* 40.368') 2) Control L-21, Illinois River at Seneca 4.0 mi (6.4 km) NE (N 41* 17.892', was* 36.308') 11.6-6 LaSalle ODCM Part 11 Section 6 CY-LA-170-301 Revision 7 January 2016 Part II, Offsite Dose Calculation Manual Type and Frequency of Analysis Gamma isotopic 3 and tritium analysis quarterly.

Alternate based on availability Gross beta and isotopic analysis on monthly composite; tritium analysis on quarterly composite.

Gamma isotopic analysis 3 semiannually.

Exposure Pathway and/or Sample 4. Ingestion

a. Milk b. Fish c. Food Products 1) 2) 1) Table 6-1 (Page 6 of 8) Radiological Environmental Monitoring Program Sample or Monitoring Location Sampling or Collection Frequency Indicators At the time of this revision, there are no dairies within 6.2 Biweekly:

May through miles which consistently produce milk. October; monthly: November through April Controls L-42, Biros Dairy, 14.2 mi (22.9 km)E (N 41° 15.379' I w 88° 23.823') Indicator Two times annually L-35, Marseilles Pool of Illinois River, 6.5 mi (10.5 km)NNW (N 41° 19.386', W 88° 42.492') L-34, LaSalle Lake 2 mi (3.2 km) E 2) Control L-36, Illinois River upstream of discharge, 4.3 mi (6.9 km) NE (N 41

11 .892', w 88° 36.308') a. Indicators Annually Two samples from each of the four major quadrants within 6.2 miles (10 km) of the station, if available.

Sample locations for food products may vary based on availability and therefore are not required to be identified here but shall be taken. Refer to most recent Land Use Census for specific garden locations.

b. Controls Two samples within 9.3 to 18.6 miles (15 to 30 km) of the station, if available.

Refer to most recent Land Use Census for specific garden locations.

11.6-7 LaSalle ODCM Part II Section 6 CY-LA-170-301 Revision 7 January 2016 Part II, Offsite Dose Calculation Manual Type and Frequency of Analysis Gamma isotopic 3 and 1-131 analysis 4 biweekly May through October, monthly November through April. Gamma isotopic analysis 3 on edible portions of each Gamma isotopic analysis 3 and 1-131 analysis each sample.

Exposure Pathway and/or Sample 4. Ingestion (cont'd) d. Vegetation Table 6-1 (Page 7 of 8) Radiological Environmental Monitoring Program Sample or Monitoring Location Sampling or Collection Frequency

NOTE Monthly during the growing season (May These vegetation samples are only required if milk sampling through October) is not performed.

a. Indicator Samples of 3 different types of broadleaf vegetation within 10km (6.2 miles) at 2 different offsite locations in the highest D/Q sector of the station, if available Sample locations for vegetation may vary based on availability and therefore are not required to be identified here but shall be taken. Refer to most recent Land Use Census for specific vegetation locations.

b. Control Samples of 3 different types of broadleaf vegetation within 15 to 30km (9.3 to 18.6 miles) in the lowest D/Q sector of the station, if available.

Refer to most recent Land Use Census for specific vegetation loacations.

11.6-8 LaSalle ODCM Part 11 Section 6 CY-LA-170-301 Revision 7 January 2016 Part II, Offsite Dose Calculation Manual Type and Frequency of Analysis Gamma isotopic analysis 3 and 1-131 analysis on each sample.

2 3 4 Table 6-1 (Page 8 of 8) Radiological Environmental Monitoring Program CY-LA-170-301 Revision 7 January 2016 Part II, Offsite Dose Calculation Manual Far field samples are analyzed when near field results are inconsistent with previous measurements and radioactivity is confirmed as having its origin in airborne effluents released from the station, or at the discretion of the OOCM Specialist.

Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thorium daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples. Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station. 1-131 analysis means the analytical separation and counting procedure are specific for this radionuclide.

11.6-9 LaSalle ODCM Part II Section 6 Figure 6-1 CY-LA-170-301 Revision 7 January 2016 Part II, Offsite Dose Calculation Manual Fixed Air Sampling Sites and Outer Ring Field Dosimeter Locations 11.6-10 LaSalle ODCM Part II Section 6 Figure 6-2 Inner Ring Field Dosimeters Locations LaSalle ODCM Part 11 Section 6 11.6-11 CY-LA-170-301 Revision 7 January 2016 Part II, Offsite Dose Calculation Manual Figure 6-3 CY-LA-170-301 Revision 7 January 2016 Part II, Offsite Dose Calculation Manual Ingestion and Waterborne Exposure Pathway Sample Locations 11.6-12 LaSalle ODCM Part II Section 6 Appendix C Offsite Dose Calculation Manual Revision 8 ODCM Change Summary Matrix Determination identifier Editorial and grammatical

-Determination EG Paae 1 of 1 Description of change Enhancements due to removal of Plant trip vulnerabilities related to offgas valve 1 N62-F057 -Determination OG 1 All paqes All paqes EG Updated the ODCM revision effective date to the header on all pages for revision 8. 2 Title Paqe Title Paqe EG Updated the ODCM effective date for revision 8. 3 11.1-16 11.1-16 OG Added reference

112 per IA 2459034-02. 4 11.2-10 11.2-10 OG Added discussion to section 2.5.4 detailing the changes to U1 Offgas valve 1 N62-F057 based on EC #387161. Reference IA 2459034-02.

Appendix D Offsite Dose Calculation Manual Part I RECS Part II ODCM LaSalle Station Units 1 and 2 Revision 8 OFFSITE DOSE CALCULATION MANUAL PART I RECS PARTIIODCM LaSalle Station Units 1and2 Effective:

June 2016 CY-LA-170-301 Revision 8 June 2016 I ODCM TABLE OF CONTENTS PART I -RADIOLOGICAL EFFLUENT CONTROLS (RECS) CY-LA-170-301 Revision 8 June 2016 ODCM Parts I and II PAGE 1.0 USE AND APPLICATION

.......................................................................................

1-1.1-1 1.1 DEFINITIONS

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1-1.1-1 1.2 LOGICAL CONNECTORS

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1-1.2-1 1.3 COMPLETION TIMES ..................

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1-1.3-1 1.4 FREQUENCY

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1-1.4-1 1.5 REC & RSR IMPLEMENTATION

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1-1.5-1 2.0-11.0 NOT USED 12.0 ODCM RADIOLOGICAL EFFLUENT CONTROL (REC) APPLICABILITY

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1-12.0-1 12.0 ODCM RADIOLOGICAL EFFLUENT SURVEILLANCE REQUIREMENT (RSR) APPLICABILITY

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1-12.0-3 12.1 NOT USED 12.2 INSTRUMENTATION

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1-12.2.1-1 12.2.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

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1-12.2.1-1 12.2.2 Radioactive GASEOUS EFFLUENT MONITORING INSTRUMENTATION

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1-12.2.2-1 12.3 LIQUID EFFLUENTS

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1-12.3.1-1 12.3.1 Liquid Effluent Concentration

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1-12.3.1-1 12.3.2 Dose from Liquid Effluents

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1-12.3.2-1 12.3.3 Liquid Radwaste Treatment System .......................................................

1-12.3.3-1 Page 1 of 10 LaSalle ODCM Table of Contents ODCM TABLE OF CONTENTS PART I -RADIOLOGICAL EFFLUENT CONTROLS (RECS) CY-LA-170-301 Revision 8 June 2016 ODCM Parts I and II PAGE 12.4 GASEOUS EFFLUENTS AND TOTAL DOSE ...................................................

1-12.4.1-1 12.4.1 Gaseous Effluent Dose Rates .......................................................

..........

1-12.4.1-1 12.4.2 Dose from Noble Gases .........................................................................

1-12.4.2-1 12.4.3 Dose from lodine-131, lodine-133, Tritium and Radioactive Materials in Particulate Form ..............

.....................................

............

.......................

1-12.4.3-1 12.4.4 Gaseous Radwaste Treatment System ...................................................

1-12.4.4-1 12.4.5 Ventilation Exhaust Treatment System ...................................................

1-12.4.5-1 12.4.6 Mark II Containment

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1-12.4.6-1 12.4.7 Total Dose .......................

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1-12.4.7-1 12.4.8 Main Condenser

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1-12.4.8-1 12.4.9 Dose Limits For Members Of The Public ................................................

1-12.4.9-1 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM .....................

1-12.5.1-1 12.5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) ...............................................................................

1-12.5.1-1 12.5.2 LAND USE CENSUS ...................................

...........................................

1-12.5.2-1 12.5.3 lnterlaboratory COMPARISON PROGRAM ............................................

1-12.5.3-1 12.5.4 METEOROLOGICAL MONITORING PROGRAM ................................... 1-12.5.4-1 12.6 REPORTING REQUIREMENTS

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1-12.6.1-1 12.6.1 Annual Radiological Environmental Operating Report ..........................

1-12.6.1-1 12.6.2 Annual Radioactive Effluent Release Report ........................................

1-12.6.2-1 12.6.3 Off-site Dose Calculation Manual (ODCM) ...............................

............

1-12.6.3-1 12.6.4 Major Changes to Radioactive Waste Treatment Systems (Liquid and Gaseous) .......................................................................................

1-12.6.4-1 Page 2of10 LaSalle ODCM Table of Contents ODCM TABLE OF CONTENTS PART I -RADIOLOGICAL EFFLUENT CONTROLS (RECS) CY-LA-170-301 Revision 8 June 2016 ODCM Parts I and II B BASES ...............................................

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1-B-1 B.12.0 REC & RSR APPLICABILITY BASES ...................................................

l-B12.0-1 B.12.1 NOT USED B.12.2 INSTRUMENTATION

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l-B12.2.1-1 B.12.2.1 Radioactive Liquid Effluent Monitoring Instrumentation

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l-B12.2.1-1 B.12.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation

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l-B12.2.2-1 B12.3 LIQUID EFFLUENTS

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l-B12.3.1-1 B.12.3.1 Liquid Effluent Concentration

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l-B12.3.1-1 B.12.3.2 Dose from Liquid Effluents

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l-B12.3.2-1 B.12.3.3 Liquid Radwaste Treatment Systems .....................

......... l-B12.3.3-1 B.12.4 GASEOUS EFFLUENTS

& TOTAL DOSE .........................................

l-B12.4.1-1 B.12.4.1 Gaseous Effluent Dose Rates ...............................

........... l-B12.4.1-1 B.12.4.2 Dose From Noble Gases .................................................

l-B12.4.2-1 B.12.4.3 Dose From lodine-131, lodine-133Tritium And Radioactive Materials In Particulate Form .......................

l-B12.4.3-1 B.12.4.4 Gaseous Radwaste Treatment (Offgas) System ...............................................................

l-B12.4.4-1 B.12.4.5 Ventilation Exhaust Treatment System ............................

1-B 12.4.5-1 B.12.4.6 Mark II Containment

........................................................

1-B 12.4.6-1 B.12.4.7 Total Dose .......................................................................

l-B12.4.7-1 B.12.4.8 Main Condenser

.........................................

.....................

l-B12.4.8-1 B.12.4.9 Dose Limits for Members of the Public ............................

l-B12.4.9-1 B.12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ..... 1-812.5.1-1 8.12.5.1 REMP ..............................................................................

1-812.5.1-1 8.12.5.2 Land Use Census ............................................................

1-812.5.2-1 8.12.5.3 lnterlaboratory Comparison Program ...............................

1-812.5.3-1 B.12.5.4 Meteorological Monitoring Program .................................

1-812.5.4-1 Page 3 of 10 LaSalle ODCM Table of Contents TABLE OF CONTENTS PART 11-0DCM CY-LA-170-301 Revision 8 June 2016 ODCM Parts I and II PAGE

1.0 INTRODUCTION

-ODCM GENERAL INFORMATION

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11.1-1 1.1 STRUCTURE OF THE ODCM .......................................................................

11.1-1 1.2 REGULATIONS

.............................................................................................

11.1-2 1.2.1 Code of Federal Regulations

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11.1-2 1.2.2 Radiological Effluent Technical Specifications ....................................

11.1-4 1.2.3 Offsite Dose Calculation Manual .........................................................

11.1-5 1.2.4 Overlapping Requirements

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11.1-5 1.2.5 Dose Receiver Methodology

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11.1-6 1.3 OFFSITE DOSE CALCULATION PARAMETERS

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11.1-10

1.4 REFERENCES

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11.1-10 2.0 INSTRUMENTATION AND SYSTEMS .....................................................................

11.2-1 2.1 LIQUID RELEASES .......................................................................................

11.2-1 2.1.1 Radwaste Discharge tanks ...........................................................

11.2-1 2.1.2 Cooling Pond Slowdown ...............................................................

11.2-1 2.2 RADIATION MONITORS ...............................................................................

11.2-2 2.2.1 Liquid Radwaste Effluent Monitor .................................................

11.2-2 2.2.2 Service Water Effluent Monitor .....................................................

11.2-2 2.2.3 RHR Heat Exchange Cooling Water Effluent Monitors .................

11.2-2 2.3 LIQUID RADIATION EFFLUENT MONITORS ALARM AND TRIP SETPOINTS

..........................................................................................

11.2-2 2.3.1 Liquid Radwaste Effluent Monitor .................................................

11.2-2 2.3.2 Service Water Effluent Monitor .....................................................

11.2-3 2.3.3 RHR Heat Exchanger Cooling Water Effluent Monitors ................

11.2-3 2.3.4 Discharge Flow Rates ...................................................................

11.2-4 2.3.5 Allocation of Effluents from Common Release Points ...................

11.2-5 2.3.6 Projected Doses from Releases ....................................................

11.2-6 2.3.7 Solidification of Waste/Process Control Program ..........................

11.2-6 2.4 AIRBORNE RELEASES ................................................................................

11.2-6 2.4.1 Condenser Off gas Treatment System ...........................................

11.2-7 2.4.2 Ventilation Exhaust Treatment System .........................................

11.2-8 2.5 GASEOUS EFFLUENT RADIATION MONITORS .........................................

11.2-8 2.5.1 Station Vent Stack Effluent Monitor ..............................................

11.2-8 2.5.2 Standby Gas Treatment System Effluent Monitor .........................

11.2-8 2.5.3 Reactor Building Ventilation Monitors ...........................................

11.2-9 2.5.4 Condenser Air Ejector Monitors ....................................................

11.2-9 2.5.5 Turbine Building Trackway and North Service Building ..............

11.2-11 Page 4of10 LaSalle ODCM Table of Contents TABLE OF CONTENTS PART II -ODCM CY-LA-170-301 Revision 8 June 2016 ODCM Parts I and II PAGE 2.6 GASEOUS RADIATION EFFLUENT ALARM AND TRIP SETPOINTS.

11.2-11 2.6.1 Reactor Building Vent Effluent Monitor .......................................

11.2-11 2.6.2 Condenser Air Ejector Monitors ..................................................

11.2-11 2.6.3 Station Vent Stack Effluent Monitor ............................................

11.2-12 2.6.4 Standby Gas Treatment Stack Monitor .......................................

11.2-12 2.6.5 Release Limits ............................................................................

11.2-13 2.6.6 Release Mixture ..........................................................................

11.2-15 2.6.7 Conversion Factors .....................................................................

11.2-15 2.6.8 HVAC Flow Rates .......................................................................

11.2-15 2.6.9 Allocation of Effluents from Common Release Points .................

11.2-16 2.6.10 Dose Projections

.........................................................................

11.2-16 3.0 LIQUID EFFLUENTS

..........................................................................................

11.3-1 3.1 LIQUID EFFLUENT RELEASES-GENERAL INFORMATION

..............

11.3-1 3.2 LIQUID EFFLUENT CONCENTRATIONS

...............................................

11.3-2 3.3 LIQUID EFFLUENT DOSE CALCULATION REQUIREMENTS

..............

11.3-4 3.4 DOSE METHODOLOGY

.........................................................................

11.3-5 3.4.1 Liquid Effluent Dose Method: General ..........................................

11.3-5 3.4.2 Potable Water Pathway .................................................................

11.3-6 3.4.3 Fish Ingestion Pathway .................................................................

11.3-7 3.4.4 Offsite Doses ................................................................................

11.3-7 3.4.5 Drinking Water ..............................................................................

11.3-7 3.5 BIOACCUMULATION FACTORS ............................................................

11.3-7 4.0 GASEOUS EFFLUENTS

....................................................................................

11.4-1 4.1 GASEOUS EFFLUENTS

-GENERAL INFORMATION

..........................

11.4-1 4.2 GASEOUS EFFLUENTS

-DOSE AND DOSE RATE CALCULATION REQUIREMENTS

.........................................

...........................................

11.4-2 4.2.1 Instantaneous Dose Rates ............................................................

11.4-2 4.2.2 Time Averaged Dose from Noble Gas ..........................................

11.4-5 4.2.3 Time Averaged Dose from Non-Noble Gas Radionuclides

...........

11.4-9 Page 5 of 10 LaSalle ODCM Table of Contents TABLE OF CONTENTS PART II -ODCM CY-LA-170-301 Revision 8 June 2016 ODCM Parts I and II PAGE 5.0 TOTAL DOSE .....................................................................................................

11.5-1 5.1 TOTAL DOSE CALCULATION REQUIREMENTS

..................................

11.5-1 5.1.1 Total Effective Dose Equivalent Limits; 10CFR20 and 40CFR190 .....................................................................................

11.5-1 5.1.2 Total Dose Calculation Methodology

............................................

11.5-2 5.1.3 BWR Skyshine ..............................................................................

11.5-2 5.1.4 Independent Spent Fuel Storage Installation (ISFSI) ..........

........ 11.5-3 5.1.5 Non Fuel Waste (NFW) Storage ...................................................

11.5-3 5.2 BWR SKYSHINE CALCULATION

............................................................

11.5-4 5.3 ONSITE RADWASTE AND RAD MATERIAL STORAGE FACILITIES

..... 11.5-6 5.3.1 Process Waste Storage Facilities

................................................

11.5-6 5.3.2 DAW Storage Facilities

................................................................

11.5-6 5.3.3 ISFSI Facilities

............................................................................

11.5-6 5.4 METHODOLOGY

............................

..........................................................

11.5-6 5.5 TOTAL DOSE ...........................................................................................

11.5-7 5.6 COMPLIANCE TO TOTAL DOSE LIMITS ................................................

11.5-8 5.6.1 Total Effective Dose Equivalent Limit -1 OCFR20 Compliance

..... 11.5-8 5.6.2 Dose to a MEMBER OF THE PUBLIC in the Unrestricted Area ..............................................................................................

11.5-8 5.6.3 Dose to a MEMBER OF THE PUBLIC in the Restricted Area ....... 11.5-8 5.6.4 Total Dose Due to the Uranium Fuel Cycle (40CFR190)

.............. 11.5-9 5.7 WHEN COMPLIANCE ASSESSMENT IS REQUIRED ...........................

11.5-10 6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM .....................

11.6-1 Page 6of10 LaSalle ODCM Table of Contents ODCM TABLE OF CONTENTS LIST OF TABLES PART I -RADIOLOGICAL EFFLUENT CONTROLS (RECS) CY-LA-170-301 Revision 8 June 2016 ODCM Parts I and II PAGE Table 1-1 Compliance Matrix .............................................................................

1-1.1-6 Table R12.2.1-1 Radioactive Liquid Effluent Monitoring Instrumentation

................

1-12.2.1-5 Table R12.2.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation

...........

1-12.2.2-5 Table R12.2.2-2 Radioactive Gaseous Effluent Monitoring Instrumentation Applicability

...............................

.................................

..................

1-12.2.2-7 Table R12.3.1-1 Allowable Concentration of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Waste .................................................................................

1-12.3.1-3 Table R12.3.1-2 Radioactive Liquid Waste Sampling and Analysis Program .........

1-12.3.1-4 Table R12.4.1-1 Radioactive Gaseous Waste Sampling and Analysis Program .... 1-12.4.1-2 Table R12.5.1-1 Radiological Environmental Monitoring Program ..........................

1-12.5.1-6 Table R12.5.1-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples ..............................................................

1-12.5.1-12 Table R 12.5.1-3 Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection

.............................................................

1-12.5.1-13 PART II -ODCM Table 1-1 Regulatory Dose Limit Matrix .........................................................................

11.1-7 Table 1-2 Dose Assessment Receivers

.........................................................................

11.1-8 Table 1-3 Miscellaneous Dose Assessment Factors: Environmental Parameters

....... 11.1-17 Table 1-4 Stable Element Transfer Data ......................................................................

11.1-19 Table 2-1 Assumed Composition Of the LaSalle Station Noble Gas Effluent.

..............

11.2-17 Page 7of10 LaSalle ODCM Table of Contents ODCM TABLE OF CONTENTS LIST OF TABLES CY-LA-170-301 Revision 8 June 2016 ODCM Parts I and II PART II -ODCM PAGE Table 3-1 Bioaccumulation Factors (Bfi) to be Used in the Absence of Site-Specific Data ..................................................................................................

11.3-8 Table 4-1 Critical Ranges .............................................................................................

11.4-18 Table 4-2 Average Wind Speeds .................................................................................

11.4-19 Table 4-3 X/Q and D/Q Maxima at or Beyond the Unrestricted Area Boundary ...........

11.4-20 Table 4-4 X/Q and D/Q Maxima at or Beyond the Restricted Area Boundary ..............

11.4-21 Table 4-5 X/Q and D/Q at the Nearest Meat Animal Locations within 5 miles ..............

11.4-22 (Page 1) Table 4-5 X/Q and D/Q at the Nearest Milk Cow Locations within 5 miles ...................

11.4-23 (Page 2) Table 4-6 Maxium Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary For Various Nuclides ...................

11.4.24 Table 4-7 Deleted .........................................................................................................

11.4-39 Table 4-8 Parameters for Calculations of N-16 Skyshine Radiation From LaSalle .........................................................................................................

11.4-40 Table 4-9 Elevated Level Joint Frequency Distribution Table Summary ......................

11.4-41 Table 4-10 Mid Elevation Joint Frequency Distribution Table Summaries

......................

11.4-43 Table 4-11 Ground Level Joint Frequency Distribution Table Summary .........................

11.4-45 Table 4-12 Station Characteristics

......................................................................................

11.4-47 Table 4-13 Dose Factors for Noble Gases .....................................................................

11.4-48 Table 4-14 External Dose Factors for Standing on Contaminated Ground DFGii (mrem/hr per pCi/ m 2) ...................................................................................

11.4-49 Table 4-15 Maximum Bi and Vi at or Beyond the Unrestricted Area Boundary ..............

11.4-52 Table 4-16 Infant Drinking Water AiT ..............................................................................

11.4-67 Page 8of10 LaSalle ODCM Table of Contents CY-LA-170-301 Revision 8 June 2016 ODCM Parts I and II Table 4-17 Child Drinking Water Air ...............................................................................

11.4-71 Table 4-18 Teen Drinking Water Air ...............................................................................

11.4-75 Table 4-19 Adult Drinking Water Air ...............................................................................

11.4-79 Table 4-20 Infant Fish Air ............................................................................

...................

11.4-83 Table 4-21 Child Fish Air ................................................................................................

11.4-87 Table 4-22 Teen Fish Air ................................................................................................

11.4-91 Table 4-23 Adult Fish Air ................................................................................................

11.4-95 Table 4-24 Infant Inhalation Pj ...............

.........................................................................

11.4-99 Table 4-25 Child Inhalation Pi ......................................................................................

11.4-103 Table 4-26 Teen Inhalation Pi ......................................................................................

11.4-107 Table 4-27 Adult Inhalation Pi ......................................................................................

11.4-111 Table 4-28 All Age Groups Ground Plane Ri ................................................................

11.4-115 Table 4-29 Infant Inhalation Ri .........................................................

............................

11.4-119 Table 4-30 Child Inhalation Ri ......................................................................................

11.4-123 Table 4-31 Teen Inhalation Ri ......................................................................................

11.4-127 Table 4-32 Adult Inhalation Ri ....................................................

..................................

11.4-131 Table 4-33 Infant Vegetation Rj ....................................................................................

11.4-135 Table 4-34 Child Vegetation Rj .....................................................................................

11.4-139 Table 4-35 Teen Vegetation Ri .....................................................................................

11.4-143 Table 4-36 Adult Vegetation Ri .....................................................................................

11.4-147 Table 4-37 Infant Milk Ri ...............................................................................................

11.4-151 Table 4-38 Child Milk Ri ...............................................................................................

11.4-155 Table 4-39 Teen Milk Ri ...............................................................................................

11.4-159 Table 4-40 Adult Milk Ri ...............................................................................................

11.4-163 Table 4-41 Infant Meat Ri .......................................

......................................................

11.4-167 Table 4-42 Child Meat Ri ..............................................................................................

11.4-171 Table 4-43 Teen Meat Rj .........................................................

.....................................

11.4-175 Table 4-44 Adult Meat Ri ..............................................................................................

11.4-179 Table 6-1 Radiological Environmental Monitoring Program ...........................................

11.6-2 Page 9 of 10 LaSalle ODCM Table of Contents ODCM TABLE OF CONTENTS LIST OF FIGURES CY-LA-170-301 Revision 8 June 2016 ODCM Parts I and II PART I -RADIOLOGICAL EFFLUENT CONTROLS PAGE None PART II -ODCM Figure 1-1 Radiation Exposure Pathways to Humans ...............................................

11.1-9 Figure 1-2 Unrestricted Area Boundary ...................................................................

11.1-21 Figure 1-3 Restricted Area Boundary ......................................................................

11.1-22 Figure 2-1 Simplified Gaseous Radwaste and Gaseous Effluent Flow Diagram ..... 11.2-18 Figure 2-2 Simplified Liquid Radwaste Processing Diagram ................................... 11.2-20 Figure 2-3 Simplified Liquid Effluent Flow Diagram ................................................ 11.2-21 Figure 2-4 Simplified Solid Radwaste Processing Diagram .................................... 11.2-22 Figure 6-1 Fixed Air Sampling Sites and Outer Ring Field Dosimeter

....................

11.6-10 Figure 6-2 Inner Ring Field Dosimeter

.......................................

.............................

11.6-11 Figure 6-3 Ingestion and Waterborne Exposure Pathway Sample Locations

.........

11.6-12 Page10of10 LaSalle ODCM Table of Contents CY-LA-170-301 Revision 8 June 2016 I Part I, Radiological Effluent Controls RADIOLOGICAL EFFLUENT CONTROLS LASALLE STATION Units 1and2 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.0 USE AND APPLICATION

1.1 DEFINITIONS

The defined terms of this section appear in capitalized type and are applicable throughout these Offsite Dose Calculation Manual (ODCM) Controls and Bases. ACTION CHANNEL CALIBRATION CHANNEL CHECK CHANNEL FUNCTIONAL TEST Definition ACTION shall be that part of a control that prescribes remedial measures required under designated conditions.

A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors.

The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, display, and trip functions, and shall include the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an in-place qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is calibrated.

For specific calibration requirements refer to surveillance requirements section for the applicable instrumentation.

A CHANNEL CHECK shall be a qualitative assessment, by observation, of channel behavior during operation.

This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY, including required alarm, interlock, display, and trip functions, and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested. (continued)

Page 1-1.1-1 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.1 DEFINITIONS (continued)

CONTINUOUS SAMPLING DOSE EQUIVALENT 1-131 GASEOUS RADWASTE TREATMENT SYSTEM MEMBERS OF THE PUBLIC MODE OCCUPATIONAL DOSE Uninterrupted sampling with the exception of sampling interruptions of short duration for required surveillances.

That concentration of 1-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table Ill of TIO -14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites"; Table E-7 of Regulatory Guide 1.109, Rev. 1, NRC, 1977; or ICRP 30, Supplement to Part 1, pages 192-212, Table titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity." Any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

Any individual, except when that individual is receiving an occupational dose. A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Technical Specifications with fuel in the reactor vessel. The dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation and/or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include dose from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the public. (continued)

Page 1-1.1-2 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.1 DEFINITIONS (continued)

OFFSITE DOSE CALCULATION MANUAL (ODCM) OPERABILITY POSITION INDICATION VERIFICATION PROCESS CONTROL PROGRAM (PCP) PURGE -PURGING RATED THERMAL POWER (RTP) The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm!Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Program and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports. A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified function(s) are also capable of performing their related support function(s).

POSITION INDICATION VERIFICATION shall be the comparison of the physical position of the Slowdown Flow Control Valve (OWL005) actuator shaft in percent open to the remote WL002A) Slowdown Flow Control Valve position indication in percent open. The PCP shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes shall be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste. PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

The applicable unit's RTP shall be a total reactor core heat transfer rate to the reactor coolant as defined in Technical Specifications. (continued)

Page 1-1.1-3 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.1 DEFINITIONS (continued)

RADIOLOGICAL EFFLUENT CONTROL STANDARDS (RECS) SITE BOUNDARY SOLIDIFICATION SOURCE CHECK THERMAL POWER UNRESTRICTED AREA VENTILATION EXHAUST MENT SYSTEM A compilation of the various regulatory requirements, surveillance and bases, commitments and/or components of the radiological effluent and environmental monitoring programs for LaSalle Station. To assist in the understanding of the relationship between effluent regulations, ODCM equations, RECS and related Technical Specification requirements, Table 1-1 provides a matrix that relates these various components, as well as the Radiological Environmental Monitoring Program fundamental requirements.

That line beyond which the land is not owned, leased, or otherwise controlled by licensee as defined in ODCM Part II Figure 1-3. SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides standing).

A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source (This could be an external source or known radioactive process stream). THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. UNRESTRICTED AREA means an area, access to which is neither limited nor controlled by the licensee.

A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust system prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents).

Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components. (continued)

Page 1-1.1-4 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.1 DEFINITIONS (continued)

VENTING VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process. DEFINITIONS PECULIAR TO ESTIMATING DOSE TO MEMBERS OF THE PUBLIC USING THE ODCM COMPUTER PROGRAM: a. ACTUAL Refers to using known release data to project the dose to the public for the previous time period. These data are stored in the database and used to demonstrate compliance with the reporting requirements of RECS. b. PROJECTED Refers to using known release data from the previous time period or estimated release data to forecast a future dose to the public. This data is NOT incorporated into the database.

Page 1-1.1-5 Regulation 10 CFR 50 1. Appendix I 2. 3. 10 CFR 20 1. 40 CFR 190 1. (now by reference, 2. also part of 10 CFR 20) Technical

1. Specifications

2. 3. Table 1-1(Page1 of2) COMPLIANCE MATRIX Dose Component Limit Gamma air dose and beta air dose due to airborne radioactivity in effluent plume. a. Whole body and skin dose due to airborne radioactivity in effluent plume are reported only if certain gamma and beta air dose criteria are exceeded.

b Projected doses due to gaseous release, when averaged over 31 days, exceed 0.3 mrem to any organ. c Projected doses due to liquid release, when averaged over 31 days, exceed 0.06 mrem to the total body or 0.2 mrem to any organ. COE for all organs and all four age groups due to CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls ODCM Equation RECS Techn i cal Spec i fication 4-4 12.4.2 5.5.4.h 4-5 4-6 N/A N/A 4-7 N/A 12.4.5 5.5.4.f N/A 12.3.3 5.5.4.f 4-8 12.4.3 5.5.4.i iodines and particulates in effluent plume. All pathways are considered.

COE for all organs and all four age groups due to 3-3 12.3.2 5.5.4.d radioactivity in liquid effluents.

TEDE, totaling all deep dose equivalent components 5-3 12.4.9 5.5.4.c (direct, ground and plume shine) and COE (all pathways, both airborne and liquid-borne). COE evaluation is made for adult only using FGR 11 database. Whole body dose (DOE) due to direct dose, ground and 5-2 12.4.7 5.5.4.j plume shine from all sources at a station. Organ doses (COE) to an adult due to all pathways.

3-3 4-8 "Instantaneous" whole body (DOE), skin (SOE), and 4-1 12.4.1 5.5.4.g thyroid (COE) dose rates due to radioactivity in airborne 4-2 effluents. For the thyroid dose, only inhalation is 4-3 considered. "Instantaneous" concentration limits for liquid effluents.

3-1 12.3.1 5.5.4.b Radioactive Effluent Release Report NIA 12.6.2 5.6.3 (continued)

Page 1-1.1-6 Regulation 10CFR50 Appendix I Section IV. B.2 10CFR50 Appendix I Section IV.B.3 10CFR50 Appendix I Section IV. B.2 10CFR50 Appendix I Section IV. B.2 and Technical Specifications

1. 1. 1. 1. Table 1-1 (Page 2 of 2) COMPLIANCE MATRIX Dose Component Limit Implement environmental monitoring program. Land Use Census lnterlaboratory Comparison Program Annual Radiological Environmental Operating Report Page 1-1.1-7 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls ODCM RECS Technical Equation Specification N/A 12.5.1 N/A N/A 12.5.2 N/A NIA 12.5.3 N/A NIA 12.6.1 5.6.2 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.0 USE AND APPLICATION

1.2 Logical

Connectors PURPOSE BACKGROUND EXAMPLES The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in ODCM to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies.

The only logical connectors that appear in ODCM are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings. Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action). The successive levels of logic are identified by additional digits of the Required Action number and by successive indentations of the logical connectors.

When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency.

The following examples illustrate the use of logical connectors. (continued)

Page 1-1.2-1 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.2 Logical Connectors EXAMPLES (continued)

EXAMPLE 1.2-1 ACTIONS CONDITION A. Control not met. REQUIRED ACTION A.1 Verify ... A.2 Restore ... COMPLETION TIME In this example, the logical connector AND is used to indicate that, when in Condition A, both Required Actions A.1 and A.2 must be completed. (continued)

Page 1-1.2-2 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.2 Logical Connectors EXAMPLES (continued)

EXAMPLE 1.2-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Control not met. A.1 Trip ... OR A.2.1 Verify ... AND A.2.2.1 Reduce ... OR A.2.2.2 Perform ... OR A.3 Align This example represents a more complicated use of logical connectors.

Required Actions A.1, A.2 and A.3 are alternate choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement.

Any one of these three Action may be chosen. If A.2 is chose, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND. Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.

Page 1-1.2-3 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.0 USE AND APPLICATION

1.3 Completion

Times PURPOSE BACKGROUND DESCRIPTION The purpose of this section is to establish the Completion Time convention and to provide guidance for its use. ODCM Radiological Effluent Controls (RECs) specify minimum requirements for ensuring safe operation of the unit. The ACTIONS associated with a REC state Conditions that typically describe the ways in which the requirements of the REC can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Times. The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the REC. Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the unit is not within the REC Applicability.

If situations are discovered that require entry into more than one Condition at a time within a single REC (multiple Conditions), the Required Actions for each Condition must be performed within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the time of discovery of the situation that required entry into the Condition.

Once a Condition has been entered, subsequent divisions, subsystem, components or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition. (continued)

Page 1-1.3-1 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.3 Completion Times DESCRIPTION (continued)

EXAMPLES However, when a subsequent division, subsystem, component, or variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended.

To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:

a. Must exist concurrent with the first inoperability; and b. Must remain inoperable or not within limits after the first inoperability is resolved.

The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either: a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or b. The stated Completion Time as measured from discovery of the subsequent inoperability. The above Completion Time extension does not apply to those RECs that have exceptions that allow completely separate re-entry into the Condition (for each division, subsystem, component, or variable expressed in the Condition) and separate tracking of Completion Times based on this entry. These exceptions are stated in individual RECs. The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery

... " Example 1.3-3 illustrates one use of this type of Completion Time. The 10 day Completion Time specified for Condition A and Bin Example 1.3-3 may not be extended.

The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions. (continued)

Page 1-1.3-2 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION B. Required Action and B.1 Be in MODE 3. associated Completion Time not met. B.2 Be in MODE 4. COMPLETION TIME 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered. The Required Actions of Condition B are in to be in MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND in MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A total of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is allowed for reaching MODE 3 and a total of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (not 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ) is allowed for reaching MODE 4 from the time that Condition B was entered. If MODE 3 is reached within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , the time allowed for reaching MODE 4 is the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months because the total time allowed for reaching Mode 4 is 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . If Condition B is entered while in MODE 3, the time allowed for reaching MODE 4 is the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . (continued)

Page 1-1.3-3 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One monitor A.1 Restore monitor to 7 days inoperable. OPERABLE status. B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months When a monitor is declared inoperable, Condition A is entered. If the monitor is not restored to OPERABLE status within 7 days, Condition B is also entered and the Completion Time clocks for Required Action B.1 and B.2 start. If the inoperable monitor is restored to OPERABLE status after Condition B is entered, Condition A and Bare exited, and therefore, the Required Actions of Condition B may be terminated.

When a monitor pump is declared inoperable while the first monitor is still inoperable, Condition A is not re-entered for the second monitor. REC 12.0.3 is entered, since the ACTIONS do not include a Condition from more than one inoperable monitor. The Completion Time clock for Condition A does not stop after REC 12.0.3 is entered, but continues to be tracked from the time Condition A was initially entered. While in REC 12.0.3, if one of the inoperable monitors is restored to OPERABLE status and the Completion Time for Condition A has not expired, REC 12.0.3 may be exited and operation continued in accordance with Condition A. (continued)

Page 1-1.3-4 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

While in REC 12.0.3, if one of the inoperable monitors is restored to OPERABLE status and the Completion Time for Condition A has expired, REC 12.0.3 may be exited and operation continued in accordance with Condition B. The Completion Time for Condition B is tracked from the time the Condition A Completion Time expired. On restoring one of the monitors to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first monitor was declared inoperable.

This Completion Time may be extended if the monitor restored to OPERABLE status was the first inoperable monitor. A 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months extension to the stated 7 days is allowed, provided this does not result in the second monitor being inoperable for > 7 days. (continued)

Page 1-1.3-5

1.3 Completion

Times EXAMPLES (continued)

EXAMPLE 1.3-3 ACTIONS CONDITION A. One Function X subsystem inoperable.

B. One Function Y subsystem inoperable.

C. One Function X subsystem inoperable.

AND One Function Y subsystem inoperable.

A.1 B.1 C.1 OR C.2 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls REQUIRED ACTION COMPLETION TIME Restore Function X 7 days subsystem to OPERABLE status. AND 10 days from discovery of failure to meet the Control Restore Function Y 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem to OPERABLE status. AND 10 days from discovery to meet Control Restore Function X 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem to OPERABLE status. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Restore Function Y subsystem to OPERABLE status. (continued)

Page 1-1.3-6 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

When one Function X subsystem and one Function Y subsystem are inoperable, Condition A and Condition B are concurrently applicable.

The Completion Times for Condition A and Condition B are tracked separately for each subsystem, starting from the time each subsystem was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second subsystem was declared inoperable (i.e., the time the situation described in Condition C was discovered).

If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected subsystem was declared inoperable (i.e., initial entry into Condition A). The Completion Times of Conditions A and B are modified by a logical connector, with a separate 10 day Completion Time measured from the time it was discovered the REC was not met. In this example, without the separate Completion Time, it would be possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the REC. The separate Completion Time modified by the phrase "from discovery of failure to meet the Control" is designed to prevent indefinite continued operation while not meeting the REC. This Completion Time allows for an exception to the normal "time zero" for beginning the Completion Time "clock." In this instance, the Completion Time "time zero" is specified as commencing at the time the associated Condition was entered. (continued)

Page 1-1.3-7 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months instruments inoperable.

instruments(s) to OPERABLE status. B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months B.2 Be in MODE 4. A single Completion Time is used for any number of instruments inoperable at the same time. The Completion Time *associated with Condition A is based on the initial entry into Condition A and is not tracked on a per instrument basis. Declaring subsequent instruments inoperable, while Condition A is still in effect, does not trigger the tracking of separate Completion Times. Once one of the instruments has been restored to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first instrument was declared inoperable.

The Completion Time may be extended if the instrument restored to OPERABLE status was the first inoperable instrument.

The Condition A Completion Time may be extended for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months provided this does not result in any subsequent instrument being inoperable for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . If the Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (plus the extension) expires while one or more instruments are still inoperable, Condition B is entered. (continued)

Page 1-1.3-8 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-5 ACTIONS Separate Condition entry is allowed for each inoperable instrument.

CONDITl()N REQUIRED ACTl()N C()MPLETl()N TIME A. One or more instruments A.1 Restore 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable. instrument(s) to OPERABLE status. B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months B.2 Be in MODE 4. The Note above the ACTl()NS Table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table. The Note allows Condition A to be entered separately for each inoperable instrument, and Completion Times tracked on a per instrument basis. When an instrument is declared inoperable, Condition A is entered and its Completion Time starts. If subsequent instruments are declared inoperable, Condition A is entered for each instrument and separate Completion Times start and are tracked for each instrument.

If the Completion Time associated with an instrument in Condition A expires, Condition B is entered for that instrument.

If the Completion Times associated with subsequent instruments in Condition A expire, Condition B is entered separately for each instrument and separate Completion Times start and are tracked for each instrument.

If a instrument that caused entry into Condition B is restored to OPERABLE status, Condition B is exited for that instrument.

Since the Note in this example allows multiple Condition entry and tracking of separate Completion Times, Completion Time extensions do not apply. (continued)

Page 1-1.3-9 CY-LA-170-301 Revision 8 June 2016 Part I , Rad i ological Effluent Controls 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel Perform RSR 12.x.x.x.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable.

OR Reduce THERMAL POWER to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 50% RTP. B. Required Action and 8.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. Entry into Condition A offers a choice between Required Action A.1 or A.2. Required Action A.1 has a "once per" Completion Time, which qualifies for the 25% extension, per RSR 12.0.2 to each performance after the initial performance.

The initial 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval of Required Action A.1 begins when Condition A is entered and the initial performance of Required Action A.1 must be completed within the first 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval.

If Required Action A.1 is followed and the Required Action is not met within the Completion Time (plus the extension allowed by RSR 12.0.2), Condition Bis entered. If Required Action A.2 is followed and the Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is not met, Condition B is entered. If after entry into Condition B, Required Action A.1 or A.2 is met, Condition B is exited and operation may then continue in Condition A (continued)

Page 1-1.3-10 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.3 Completion Times EXAMPLES (continued)

IMMEDIATE COMPLETION TIME EXAMPLE 1.3-7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One subsystem A.1 Verify affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable.

subsystem isolated.

AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Restore subsystem to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status. B. Required Action and 8.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Required Action A.1 has two Completion Times. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time begins at the time the Condition is entered and each "Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter" interval begins upon performance of Required Action A.1. If after Condition A is entered, Required Action A.1 is not met within either the initial 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or any subsequent 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval from the previous performance (plus the extension allowed by RSR 12.0.2), Condition B is entered. The Completion Time clock for Condition A does not stop after Condition Bis entered, but continues from the time Condition A was initially entered. If Required Action A.1 is met after Condition B is entered, Condition 8 is exited and operation may continue in accordance with Condition A, provided the Completion Time for Required Action A.2 has not expired. When "Immediately" is used as a Completion Time, the Required Action should be pursued without delay and in a controlled manner. Page 1-1.3-11 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.0 USE AND APPLICATION

1.4 Frequency

PURPOSE DESCRIPTION The purpose of this section is to define the proper use and application of Frequency requirements.

Each ODCM Radiological Effluent Surveillance Requirement (RSR) has a specified Frequency in which the Surveillance must be met in order to meet the associated ODCM REC. An understanding of the correct application of the specified Frequency is necessary for compliance with the RSR. The "specified Frequency" is referred to throughout this section and each of the Requirements of Section 12.0, ODCM Surveillance Requirement (RSR) Applicability.

The "specified Frequency" consists of the requirements of the Frequency column of each RSR, as well as certain Notes in the Surveillance column that modify performance requirements.

Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are "otherwise stated" conditions allowed by RSR 12.0.1. They may be stated as clarifying Notes in the Surveillance, as part of the Surveillance, or both. Example 1.4-4 discusses these special situations.

Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated REC is within its Applicability, represent potential RSR 12.0.4 conflicts.

To avoid these conflicts, the RSR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed.

With a RSR satisfied, RSR 12.0.4 imposes no restriction.

The use of "met" or "performed" in these instances conveys specified meanings.

A Surveillance is "met" only when the acceptance criteria are satisfied.

Known failure of the requirements of a Surveillance, even without a Surveillance specifically being "performed," constitutes a Surveillance not "met." "Performance" refers only to the requirement to (continued)

Page 1-1.4-1 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.0 USE AND APPLICATION

1.4 Frequency

DESCRIPTION (continued)

EXAMPLES specifically determine the ability to meet the acceptance criteria.

RSR 12.0.4 restrictions would not apply if both the following conditions are satisfied:

a. The Surveillance is not required to be performed; and b. The Surveillance is not required to be met or, even if required to be met, is not known to be failed. The following examples illustrate the various ways that Frequencies are specified.

In these examples, the Applicability of the REC (REC not shown) is MODES 1, 2, and 3. EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 1.4-1 contains the type of RSR most often encountered in the ODCM. The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval.

Although the Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed by RSR 12.0.2 for operational flexibility. The measurement of this interval continues at all times, event when the RSR is not required to be met per RSR 12.0.1 (such as when the equipment is inoperable, a variable is outside specified limits, or the unit is outside the Applicability of the REC). If the interval specified by RSR 12.0.2 is exceeded while the unit is in a MODE or other specified condition in the Applicability of the REC, (continued)

Page 1-1.4-2 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.0 USE AND APPLICATION

1.4 Frequency

EXAMPLES EXAMPLE 1.4-1 (continued) and the performance of the Surveillance is not otherwise modified (refer to Examples 1.4-3 and 1.4-4), then RSR 12.0.3 becomes applicable.

If the interval as specified by RSR 12.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the REC for which performance of the RSR is required, the Surveillance must be performed within the Frequency requirements of RSR 12.0.2 prior to entry into the MODE or other specified condition.

Failure to do so would result in a violation of RSR 12.0.4. EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE Verify flow is within limits. FREQUENCY Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after.::.

25% RTP 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 1.4-2 has two Frequencies.

The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector "AND" indicates that both Frequency requirements must be met. Each time reactor power is increased from a power level < 25% RTP to .::. 25% RTP, the Surveillance must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . (continued)

Page 1-1.4-3 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.0 USE AND APPLICATION

1.4 Frequency

EXAMPLES EXAMPLE 1.4-2 (continued)

The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND"). This type of Frequency does not qualify for the extension allowed by RSR 12.0.2. "Thereafter" indicates future performances must be established per RSR 12.0.2, but only after a specified condition is first met (i.e., the "once" performance in this example).

If reactor power decreases to< 25% RTP, the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP. EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 25% RTP. Perform channel adjustment.

FREQUENCY 7 days The interval continues whether or not the unit operation is < 25% RTP between performances.

As the Note modifies the required performance of the Surveillance, it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is< 25% RTP, this Note allows 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after power reaches 25% RTP to perform the Surveillance.

The Surveillance is still considered to be within the "specified Frequency." Therefore, if the Surveillance were not performed within the 7 day interval (plus the extension allowed by RSR 12.0.2), but operation was < 25% RTP, (continued)

Page 1-1.4-4 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 1.0 USE AND APPLICATION

1.4 Frequency

EXAMPLES EXAMPLE 1.4-3 (continued) it would not constitute a failure of the RSR or failure to meet the REC. Also, no violation of RSR 12.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with power _:::25% RTP. Once the unit reaches 25% RTP, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months would be allowed for completing the Surveillance.

If the Surveillance were not performed within this 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of RSR 12.0.3 would apply. EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Only required to be met in MODE 1. Verify leakage rates are within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 1.4-4 specifies that the requirements of this Surveillance do not have to be met until the unit is in MODE 1. The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance.

Therefore, if the Surveillance were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval (plus the extension allowed by RSR 12.0.2), but the unit was not in MODE 1, there would be no failure of the RSR nor failure to meet the REC. Therefore, no violation of RSR 12.0.4 occurs when changing MODES, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change was not made into MODE 1. Prior to entering MODE 1 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met), RSR 12.0.4 would require satisfying the RSR. Page 1-1.4-5 1.0 USE AND APPLICATION 1.5 REC and RSR Implementation CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls The ODCM provides those limitations upon plant operations which are part of the licensing basis for the station but do not meet the criteria for continued inclusion in the Technical Specifications. It also provides information which supplements the Technical Specifications by implementing the requirements of Technical Specification Sections 5.5.1, 5.5.4, 5.6.2, and 5.6.3. RECs and RSRs are implemented the same as Technical Specifications (see 12.0 Applicability).

However, RECs and RSRs are treated as plant procedures and are not part of the Technical Specifications.

Therefore the following exceptions apply: a. Violations of the Action or Surveillance requirements in a REC are not reportable as conditions prohibited by, or deviations from, the Technical Specifications per 10 CFR 50.72or10 CFR 50.73. b. Power reduction or plant shutdowns required to comply with the Actions of a REC are not reportable per 10 CFR 50. 72 or 1 O CFR 50. 73. Page 1-1.5-1

2.0 through

11.0 NOT USED CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls INTENTIONALLY BLANK Sections 2.0 through 11.0 are not used in the ODCM in order to maintain the Original ODCM numbering convention Page 1-2.0-1 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 12.0 ODCM RADIOLOGICAL EFFLUENT CONTROL (REC) APPLICABILITY REC 12.0.1 REC 12.0.2 REC 12.0.3 REC 12.0.4 RECs shall be met during the MODES or other specified conditions in the Applicability, except as provided in REC 12.0.2. Upon discovery of a failure to meet a REC, the Required Actions of the associated Conditions shall be met, except as provided in REC 12.0.5. If the REC is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated. When a REC is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to: a. Implement appropriate compensatory actions as needed; b. Verify that the plant is not in an unanalyzed condition or that a required safety function is not compromised by the inoperabilities; and c. Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , obtain Shift Operations Superintendent or designee approval of the compensatory actions and the plan for exiting REC 12.0.3. Exceptions to this REC are stated in the individual RECs. Where corrective measures are completed that permit operation in accordance with the REC or ACTIONS, completion of the actions required by REC 12.0.3 is not required.

REC 12.0.3 is only applicable in MODES 1, 2, and 3. When a REC is not met, entry into a MODE or other specified condition in the Applicability shall not be made except when the associated ACTIONS to be entered permit continued operation in the MODE or other specified (continued)

Page 1-12.0-1 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 12.0 REC APPLICABILITY REC 12.0.4 (continued)

REC 12.0.5 REC 12.0.6 condition in the Applicability for an unlimited period of time. This REC shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit. Exceptions to this REC are stated in the individual RECs. REC 12.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2, and 3. Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment.

This is an exception to REC 12.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

RECs, including associated ACTIONS, shall apply to each unit individually, unless otherwise indicated.

Whenever the REC refers to a system or component that is shared by both units, the ACTIONS will apply to both units simultaneously.

Page 1-12.0-2 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 12.0 ODCM RADIOLOGICAL EFFLUENT SURVEILLANCE REQUIREMENT (RSR) APPLICABILITY RSR 12.0.1 RSR 12.0.2 RSR 12.0.3 RSRs shall be met during the MODES or other specified conditions in the Applicability for individual RECs, unless otherwise stated in the RSR. Failure to meet a RSR, whether such failure is experienced during the performance of the RSR or between performances of the RSR, shall be failure to meet the REC. Failure to perform a RSR within the specified Frequency shall be failure to meet the REC except as provided in RSR 12.0.3. RSRs do not have to be performed on inoperable equipment or variables outside specified limits. The specified Frequency for each RSR is met if the RSR 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. For Frequencies specified as "once," the above interval extension does not apply. If a Completion Time requires periodic performance on a "once per ... " basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this RSR are stated in the individual RSRs. If it is discovered that a RSR was not performed within its specified Frequency, then compliance with the requirement to declare the REC not met may 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 greater. This delay period is permitted to allow performance of the RSR. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the risk impact shall be managed. If the RSR is not performed within the delay period, the REC must immediately be declared not met, and the applicable Condition(s) must be entered. When the RSR is performed within the delay period and the RSR is not met, the REC must immediately be declared not met, and the applicable Condition(s) must be entered. (continued)

Page 1-12.0-3 CY-LA-170-301 Revision 8 June 2016 Part I, Radiological Effluent Controls 12.0 RSR APPLICABILITY (continued)

RSR 12.0.4 RSR 12.0.5 Entry into a MODE or other specified condition in the Applicability of a REC shall not be made unless the REC's RSRs have been met within their specified Frequency.

This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit. RSR 12.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2, and 3. RSRs shall apply to each unit individually, unless otherwise indicated.

Page 1-12.0-4

ML17117A586

Text

1.0 INTRODUCTION

1.4 REFERENCES

1.1 DEFINITIONS

1.2 Logical

1.3 Completion

1.3 Completion

1.4 Frequency

1.4 Frequency

1.4 Frequency

1.4 Frequency

1.4 Frequency

2.0 through

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