ML20198M262

Revs to Offsite Dose Calculation Manual,Consisting of Rev 1.5 to Chapter 11 & Rev 1.5 to Chapter 12

ML20198M262
Person / Time
Site:	Byron
Issue date:	10/31/1997
From:	COMMONWEALTH EDISON CO.
To:	NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
PROC-971031, NUDOCS 9801200052
Download: ML20198M262 (85)

Text

{{#Wiki_filter:. _ .-t ( L-X244 Alj.,. _. [4-5. Document Centrol Desk 1 1 K Dweeter of Nm: lear Reactor Regulabon ' U.S. Nuclear Regulator /O-Mail Station Pl-137 Waalungeon,DC 20555 Dooomber 17,1997

Attached is a revision to the Offsite Dose Calculation Manual, Byron Annex, Chaptersil and 12.

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Please update your manual as follows:

h: Byron Chapter 11, Resision 1.4' ' Byron Chapter 12, Revision 1.4 Insert:

Byron Chapter 11, Revision 1.5 :

Byron Chapter 12, Revision 1.5 Please sign below indicating your manual has been updated and that your controlled copy number . is correct. .Name Date . Return to ; ..ComFE Central Files 1400 Opus Place,4th Floor Downers Grove,IL 60515 .-4 I .. - or - ' - Central Files N ' [J _ L4th Floor - - 1 ,yggn: 1 1 E. M..E.R. t,$ . hwiemut,iai.t.ono: 1 , m, o.m.. o

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~ p f 1 i Byron Station) Chapter 11 Change Summary ~ - ODCM Revision 1.5, October 1997-- i P.., ch.. Daenintion - . 1 Updated revision number < 11-2 through 11 7.-- Updated the distances for the sampling and monitoring locations listed in Table I l-1 based on the results of a verification survey performed in August,1997 The survey was performed using a Global Positioning - System (GPS) identifying the latitude, longitude and distance from the Station Vent Stack for each location. Il 3-Corrected the sector designator and direction for airborne control sample ' ' BY-8. The sample location is very close to the edge of sectors P'and Q, however, the August,1997 GPS survey identified the proper sector as P. 1 ~ l1-5 Corrected the sector directions for TLD monitoring locations BY-211-1, 211-4, and 212-1 The sector designators listed in Table 11-1 were correct, however, the directions given for those sectors were wrong. ? t A)*-. 1 ) s 1 5 s .s. d;_ 4 ur a.a me r19--1 ,wi g-v-w y--+'W-W-fp e v-d w-M w-

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1 I BYRON Revision 1.5 October 1997 CHAPTER 11 I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TAELE OF CONTENTS PAGE 11.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 11-1 O i O h:\\worddata\\odem\\by11r1-5. doc 11-li 1

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DYRON- - Revision 1.5 i '4= October 1997 l i CHAPTER 11 LIST OF TABLES I NUMBER TITLE PAGE 4 i 11-1 Radelogical Environmental Monitoring Pingram 11-2 3 4 2 Y t i. f 1 1 i - t. t i. 6 f 1 t. 1 I e i i l h:\\worddatabdcmby11ri-5. doc p 11 iii 1u. -.

BYRON Revision 1.5 October 1997 CHAPTER 11 LIST OF FIGURES NUMBER TITLE PAGE 11-1 Onsite Air Sampling Locations 11-10 11-2 Offsite Air Sampling Locations 11-11 11-3 inner Ring and Outer Ring TLD Locations 11-12 11-4 Ingestion and Waterbome Exposure Pathway Sample Locations 11-13 O O h:\\worddata\\odem\\by11r1-5. doc 11-iv

'i BYRON R'4 l-ion 1.5 C tober 1997 CHAPTER 11 j - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The radiological environrnental rnonitoring program for the environs around Byron Staten is given in Table 11 1.- Figures 11-1 through 11-4 show sampling and monitonng locations. i-O i I l h:\\worddata\\cdem\\by11r1-5. doc l' l' 11-1 I-4 m ,,yr-

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BYROM Revson 1.5 October 1997 Table 11-1 Radiological Environmental Munitoring Program Exposure Pathway Sampling or Type of Frequency and/or Sample Sa.molino or Monitorino Locations Collection Frecuency of Ana!vsis

1. Airbome Radiciodine and

a. Indicators-Near Field Continuous sampler operation Radiciodine Canister-Particulates with particulate sample I-131 analysis biweekly BY-21, Byron Nearsite N, collection weekly, or more on near field and control 0.3 mi N (0.5 km A) frequently if required by dust samples.'

BY-22, Byron Nearsite ESE, loading, and radiciodine canister 0.4 mi ESE (0.6 km F) cothion biweekly. Particulate Samoler BY-23. Byron Nearsite S, 0.6 mi S (1.0 km J) Gross beta analysis BY-24, Byren Nearsite SW, following weekly filter 0.6 mi SW(1.0 km L) change and gamma iso *.opic analysis' quarterly on composite filters by location on l near field and control samples.

b. Indicators-Far Field BY-1, Byron,3.0 mi N (4.8 km A)

BY-4, Paynes Pt., 5.0 mi SE (8.0 km G) BY-6, Oregon,4.7 mi SSW (7.5 km K) h:\\worddata\\odem\\by11rl-5. doc e d' e

ON R October 1997 Table 11-1 (Cont.) Radiological Environmental udlonitoring P"qram Exposure Pathway Sampling or Type of Frequency and/or Samole Samoling or Monitoring Locations Collection Frecuency of Analysis

1. Airbome (Consd)

c. Controts BY-8, Leaf River. 6.8 mi WNW(10.9 km P)

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2. Direct Radiation a.

lodgaf0fS-Inner Ring Quarterfy Gamma dose quarterfy BY-101-1,0.3 mi N (0.5 km A) BY-101-2,0.3 mi N (0.5 km A) BY-102-1,0.9 mi NNE (1.5 km B) BY-102-2,1.0 mi NNE (1.5 km B) BY-103-1,1.7 mi NE (2.8 km C) BY-103-2,1.7 mi NE (2.7 km C) BY-104-1,1.5 mi ENE (2.4 km D) BY-104-2,1.5 mi ENE (2.4 km D) i BY-105-1,1.3 mi E (2.1 km E) BY-105-2,1.3 mi E (2.1 km E) BY-106-1,1.4 mi ESE (2.3 km F) BY-106-2,1.4 mi ESE (2.3 km F) BY-107-1,1.4 mi SE (2.2 km G) BY-107-2,1,4 mi SE (2.2 km G) BY-108-1,0.7 mi SSE (1.1 km H) l BY-108-2,0.6 mi SSE (1.0 km H) BY-109-1,0.6 mi S (1.0 km J) BY-109-2, 0.6 mi S (1.0 km J) BY-110-1,0.6 mi SSW (1.0 km K) BY-110-2,0.6 mi SSW (1.0 km K) BY-111-3,0.7 mi SW (1.1 km L) BY-111-4,0.8 mi SW (1.3 km L) BY-112-3,0.8 mi WSW (1.2 km M) BY-112-4,0.8 mi WSW (1.2 km M) h:\\worddata\\odem\\by11rl-5. doc 11-3

BYRON Revision 1.5 October 1997 Table 11-1 (Cont.) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Samole Sampling or Monitorina Locations Collection Frecuency of Analysis 2.- Direct Radiation BY-113-1,0.7 mi W (1.1 km N) (Cont'd) BY-113-2,0.7 mi W (1.1 km N) BY-114-1,0 8 mi WNW(1.2 km P) l BY-114-2,0.8 mi WNW (1.3 km P) BY-115-1,1.0 mi NW (1.6 km O) BY-115-2,1.0 mi NW (1.7 km Q) BY-116-1,1.4 mi f"NW(2.3 km R) BY-116-2,1.4 mi NNW(2.3 km R)

b. Indicators-Outer Ring BY-201-3,4.5 mi N (7.1 km A) l BY-201-4,4.4 mi N (7.1 km A) l BY-202-1,4.3 mi NNE (6.9 km B)

BY-202-2,4.8 mi NNE (7.6 km B) BY-203-1,4.8 mi NE (7.7 km C) BY-203-2,4.7 mi NE (7.5 km C) BY-204-1,4.2 mi ENE (6.6 km D) BY-204-2,4.1 mi ENE (6.5 km D) BY-205-1,3.8 mi E (6.2 km E) i BY-205-2,3.8 mi E (6.2 km E) BY-206-1,4.1 mi ESE (6.5 km F) BY-206-2,4.4 mi ESE (7.0 km F) BY-207-1,4.2 mi SE (6.7 km G) BY-207-2,3.6 mi SE (5.8 km G) i h:\\worddata\\odem\\byllrl-5. doc 11-4 l O O O

.i Revoon October 1997 Table 11-1 (Cont.) Radiological Environmental Monitoring Program Exposure Pathway Sampling or - Type of Frequency and/or Sample Samohno or Monitorino L. *-ns Collechon Freauencv of Analysis.

2. Direct Radsabon BY-208-1,4.0 mi SSE (6.4 km H)

(Cont'd). BY-208-2, 3.7 mi SSE (5.9 km H) BY-209-1,3.7 mi S (5.9 km J) BY-20",4,3.7 mi S ' (5.9 km J) BY-210-3,3.9 mi SSW(6.2 km K) BY-210-4, 3.9 mi SSW (6.2 km K) BY-211-1,4.9 mi SW (7.9 km L) BY-211-4,4.9 mi SW(7.8 km L) BY-212-1,4.7 mi WSW (7.4 km M) BY-212-4. 4.7 mi WSW (7.4 km M) BY-213-1,4.7 mi W (7.5 km v4) ' BY-213-4,4.6 mi W : (7.4 km N) BY-214-1,4.6 miWNW(7.4 km P) BY-214-4, 4.9 mi WNW (7.8 km P) BY-215-1, 5.3 mi NW (8.4 km O) BY-215-4,6.2 mi NW (8.3 km Q) BY-216-1,4.6 mi NNW (7.3 km R) BY-2.16-2,4.8 mi NNW(7.6 km R)

c. Other

'InCcators i One at each airborne location given in part 1.a and 1.b.

d. Control One at each airbome control locaten given in part 1.c.

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BYRON Revision 1.5 October 1997 Table 11 1 (Cont.) Radiological Environmental Monitoring Program Exposu;e Pathway Sampling or Type of Frequency and/or Samole Samoling or Monitorino Locations Collection Freauency of Analysis

3. Waterbome

a. Ground /Well sit Indicators Quarterfy Gamma isotopic' and tritium analysis BY-14, Comed Offsite Well quarterly 0.5 mi ESE (0.7 km F)

BY-18, McCoy Farmstead 03 mi SW (1.2 km L) BY-32, Wolford Well 1.8 mi W(2.9 km N)

b. Drinking There is no drinking water pathway within 6.2 mi downstream of the station.

c. Surface BY-12 Oregon Pool of Rock River, Weekly grab samples.

Gross beta and gamma Downstream of Discharge, isotopic analysis on 4.5 mi SSW(7.3 km K) monthly composite; tritium analysis on quarterly cowposite.

d. Controj BY-29, Byron, Upstream of Intake Weekly grab samples.

Gross beta and gamma 3.0 mi N (4.8 km A) isotopicanalysis on monthly composite; tritium analysis on quarterly composite.

e. Sediment BY-12 Oregon Pool of Rock River, Semiannually Gamma isotopic

• Downstrearn of Discharge, analysis semaannually.

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.-. = -. Ot So- - R4 1 ~ e October 1997 L.! Tatste 11-1 (Cont.) '~ Radiological Environmental RAonitoring Program Expose e Pathway Sampling or-L Type of Frequency anc'aor Samnie Sampieng or Monstonng Locahons CoRachon Frequency of Analvam

4. Ingenbon

_. a. Milk

a. IfEbcators

.C;x'4: May through Gammaisotopec and 8 October, nu. y. 1-131 analytis* on each l-BY-20, K. Reeverts Dairy Farm. November through April.' sample. 2.0 mi NE (3.2 km C). BY-27, Kenneth Druten Dairy Farm,

i

5.7 mi WSW (9.2 km M)

'i [ BY-30 Don Roos Dairy, 5.3 mi SE (8.4 km G)

b. Controls

.BY-26. Glen Gazzard's Dairy, 12.0 mi N (19.2 km A)

b. Fish

a. Indscator BY-31,.. ek River in vicinity of Discharge, Two hmes annually Gamme isotopic

• 2.2 mi WNW (3.5 km P) 1 analysis on edible

'1 1 portions

b. Control

'i -i BY-29, Byron, Upstream of Intake 3.0 mi N (4.8 km A) j

c. Food Products

a. Indscators Annually Gamma isotopsc ~

-l 8 l analysis on each Two samples from each of the four sample maior quadrants within 6.2 miles of the station. 'h:\\worddata\\odem\\by11rl-5. doc t 11-7'

BYRON Revision 1.5 October 1997 Table 11-1 (Cont.) Radiological Environmantal Monitoring Program Exposure Pathway Sampsng or Type of Frequency and/or Samole Scmoling or Monitoring Locations Collection Freauency of Analysis Sample locations for food products may vary based on availability and therefore are not required to be identified here but shall be taken.

b. Control Two samples within 9.3 to 18.6 miles of the station.

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) October 1997 TABLE 11-1 (Cont'd) Radiological Environmental RAonitoring Program ' 'Far field samples are analyzed when the respective near field sample results are inconsistent with previous measurements and radioactivity is - confirmed as having its origin in airborne effluents from the staten, or at the descrecon of the Radiation Picieca06 Director. ' Airborne partculate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air partculate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples ' Gamma esotope analysis means the identification and quantifcaten of gamma-emitting radionuclides that may be attnbutable to the effluens from the station. 'l-131 analysis means the analytical separation and counting procedure are specific for this radionuclide. l I h:\\worddata\\odem\\by11rl-5. doc 9

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Byron Station ODCM Chaner Summary Chapter 12, Resision 1,5, October 1997 - - Pane - Change Dcheristion 12-i. Updated revision number.- 124ii - Updated page numbers in Table esf Contents. 12-iv Updated page numbers in List cf Tabics. 12 18,25,27 Corrected typographical errors in section numbers. i 12 34 Corrected typographical error in titic.

12 36,38

- Corrected typographical erre: in section numbers. 124 8,39,40 Added surveillance requirereents ami bases statements for use and monitoring of the Old Steam Gaerator St.srage Facility (OSGSF). i 12-49 ' Corrected Table number in Notation (1) from 1.1 1 to 11 1. 12 5: Changed the LLD for tritiam from 200 pCi/l to 2,000 pCi/l to maintain comistency with the NRC is..cr.dritions in Generic Letter 89-01. 12 53 Added a footnote to the table to identify that the resised LLD wr tritium is the minimum acceptable LLD authorized. Vendors performing environmental sampic analyses off-site would still be required to use 200 pCi/l as the LLD. 12 56 Deleted the reference to use of preoperational studies in the Annual Emironmental Operating Report. His data is not required to be included and has not been in previous rgarts. j 12 59 Corrected a typographical enor that referred to a section number in the old 10 CFR Part 20. 9 !'i T u N, W Idwordataibyl2cl-5. doc 6 g pgr 3 ,n,ag-er-g-rs. g. Wi W r+mw-y4-p.5.- qp q p ggy _- g -y y iW., e ,.p. _g--- e,_. --= p p-m- +-4gi ee -y*-n-

f BYRON Revision 1.5 October 1997 f + t'( CHAPTER 12.0 SPECIAL NOTE The transfer of the Byron Radiological Emuent Technical SpecircMions to the ODCM was approved by the Nucieer Regulatory Commission in Techreical Specification Amendment 46, dated April 13,1992. i i 1 I l l b i Lv l g WnbdomWmex%ronW12ri 5 doc 12-1

BYRON Revision 1.5

• l October 1997 BYRON ANNEX INDEX CHAPTER 12 Revision 1.5 1

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BYRON Rcvision 1.5 October 1997 CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS) TABLE OF CONTENTS PAGE 12.1 DEFINITIONS 12 2 12.2 INSTRUMENTATION 12-6 1. Radioactive Liquid Emuent Monitonng Instrumentation 12-6 2. Radcactive Gaseous Emuent Monitoring instrumentation 12 11 12.3 LIQUID EFFLUENT 8 12 18 1. Concentration 12 18 2. Dose 12 23 3. Liquid Radwaste Treatment System 12 25 12.4 GA8EOUS EFFLUENTS 12 27 t. 1. Dose Rate 12 27 (b 2. Dose - Noble Gases 12 32 l 3. Dose lodine 131, lodine-133, Tntium, and Radioactive Material in Partculate Form 12 34 4. Gaseous Raowaste Treatment System 12-36 5. Total Dose 12 38 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12-41 1. Monitoring Program 12 41 2. Land Use Census 12 54 3. Intertaboratory Comparison Program 12 55 12.8 REPORTING REQUIREMENTS 12 56 1. Anr.ual Radiological Environmental Operating Report 12 56 2. Annual Radioactive Emuent Release Report 12-58 3. O# site Dose Calculation Manual (ODCM) 12 59 4. Major Changes to Liquid and Gaseous Radwaste Treatment Systems 12-60 V g wnweemwventyronty12ri 5 doc l 12-1i1

BYRON Revision 1.5 October 1997 ) CHAPTER 12 RADIOACTIVE EFFLUEkT TECHNICAL STANDARDS (RETS) LIST OF TABLES TABLE TITLE

PAGE, 12.01 Compliance Matrix 12 1 12.1 1 Frequency Notations 12-5 12.2 1 Radioactive LiquW Emuent Monitoring Instrumentation 12-7 12.2 2 Radioactive Liquid Emuent Monitoring instrumentation Surveillance Requirements 12 9 12.2 3 Radioactive Gaseous Emuent Monitoring instrumentation 12-12 12.2 4 Radioactive Gaseous Emuent Monitoring Instrumentation Surveillance Requirements 12 15 12.3 1 Radioactive Liquid Waste Sampling and Analysis Program 12 19 0

12,4 1 Radioactive Gaseous Waste Sampling and Analysis Program 12 29 12.5-1 Radiological Environmental Monitoring Program 12-44 12.5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 12 50 12.5-3 Detection Capabilities for Environmental Sample l Analysis 12-51 l s _ _ _,,,., _ 12-iv

BYRON Revtion 1.5 October 1997 - BYRON STATN)N Table 12.0-1 COMPLIANCE MATRIX Regulat6on Dose Component L6rait ODCM RET $ Techn6 cal Equation Specifica-4 tion 10 CFR 50

1. Gamma air dose and beta sir dose due to A1 12.4.2 6.8.4.e.8 Appendix l sirbome radioactivity in effluent plume.

A2

a. Whole body and skin dose due to airbome A-6 N/A N/A radion:tivity in effluent plume are reported A7 only if certain gamma and beta air dose criteria are exceeded A 13 12.4.3 6.8.4.e.9

2. CDE for all organs and all four age groups due to

) lodinou and particulates in effluent plume. All A-29 12.3.2 6.8.4.e4 pathways are considered.

3. CDE for all organs and all four age groups due to radioactivity in liquid effluents.

i 10 CFR 20

1. TEDE, totahng all deep dose equivalent A 38 6.8.4.e.3 l

components (direct, ground and plume shine) and committed effective dose equivalents (all { } pathways, both airbome and liquid-bome). CDE evaluation is made for adult only using FGR 1.1 l data base. 40 CFR 190

1. Whole body dose (DDE) due to derect dose,

' A 35 12.4.5 6.8.4.e.10 (now by ground and plume shine from all sources at a t'forence, also

station, part of A-13 10 CFR 20)

2. Organ doses (CDE) to an adult due to all pathways.

Technmal 1 " Instantaneous" whole body (DDE), skin (SDE), A-8 12.4.1 6.8.4.e.7 Specifications and organ (CDE) dose rates to an adult due to A9 radioactivity in airbome effluents. For the organ A-28 dose, only inhalation is considered. A-32 12.3.1 6.8.4.e.2

2. " Instantaneous" concentration limits for liquid effluents.

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BYRON Revision 1.5 October 1997 12.1 DEFINITIONS 12.1.1 ACTION shall be that which prescaibes remedial measures required under designated cond:tions. - 2.1.2 ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY of alarm, interlock and/or trip functions. The ANALOG CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the starm interlock and/or Trip Setpoints such that the Setpoints are within the required range and accuracy. 12.1.3 CHANNEL CAllBRATION shall be the adjustrnent, as necessary, of the channel such that it responds within the required range and accuracy to known values of input. The CHANNEL CAllBRATION 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. 12.1.4 CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shallinclude, 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. 12.1.5 DIGITAL CHANNEL OPERATIONAL TEST shall consist of exercising the digital computer hardware using data base manipulation and injecting simulated process data to verify OPERABILITY of alarm and/or trip functions. 12.1.6 DOSE EQUIVALENT l-131 shall be that connection of I-131 (microcurie / gram) which alone would produce the same thyroid dose ah, the quantity and isotopic mixture of I 131,1132,1-133,1-134, and 1335 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table ill of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites". 12.1.7 FREQUENCY - Table 12.1-1 provides the definitions of various frequencies for which surveillances, sampling, etc., are performed unless defined otherwise The 25% variance shall not be applied to Operabihty Action statements. The bases to Technical Specification 4.0.2 provide clarifications to this requirement. 12.1.8 MEMBER (S) OF THE PUBLIC means any individual except when that indivMualis receiving an occupational dose. 12.1.9 OCCUPATIONAL DOSE means the dase 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 pubkc. O g embdcrn\\annexbyronty12r1-5 doc 12 2

BYRON Revision 1.5 October 1997 12.1,10 OPERABLE / OPERABILITY a system, subsystem, train, component or device shall be - v) OPERABLE or have OPERABILITY when it is capable of performing its specified funcbon(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s). 12.1.11 OPERATIONAL MODE (i.e. Mode) shall correspond to any one inclusive combination i of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2 of the Technical Specifications. 12.1.12 PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, ana!yses, tests, 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 will be accomplished in such a way as to assure compliance with 10 CFR Parts 20,61. 71 and State regulations, burial ground requirements, and other requiremen'.s goveming the disposal of radioactive wastes. 12.1.13 PURGE / PURGING 6 hall be any controkd process of discharging air or gas from a confirement to mr ntain terrperature, pressure, humidity, concentration or other e operating condition, in such a manner that replacement air or gas is required to purify sne confinement. 12.1.14 RATED THERMAL POWER shall be a total core heat transfer rate to the reactor coolant of 3411 MWm. Q 12.1.15 SITE BOUNDARY shall be that line beyond which the land or property is not owned, Q leased, or otherwise controlled by the licensee. 12.1 10 SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements. 12,1,17 SOURCE CHECK shall be the qualitative assessment of channel response when the enannel sensor is exposed to a source of increased radioactivity. 12.1.18 THERMAL POWER shall be the total core heat transfer rate to the reactor coolant. 12.1.19 UNRESTRICTED AREA means an area, access to which is neither limited nor controlled by the licensee. 12.1.20 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 exbnust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST . TREATMENT SYSTEM components. {\\ g Wmbdcmunne4byronty12r15 doc 12-3

BYRON L'evision 1.5 Oc W r1997 12.1.21 VENTING snall be any 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 replacemerit air or gas is not provided or required during VENTING. Vent, used in system names, does nut imply a VENTING process. 12.1.22 WASTE GAS HOLDUP SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System off-gases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. 12.1.23 Def)nitions Peculiar to Estimating Dose to Members of the Public using the ODCM Computer Program. a. ACTUAL - ACTUAL refers to using known release data to project the dose to members cf the public for the previous time period. This data is stored in the database and used to demonstrate compliance with the reporting requiremer'ts of Chapter 12. b. PROJECTED - PROJECTED refers to using known release data from the previous time period or estimated release data to forecast a future dose to members of the public. This data is not incorporated into the database. O O 9 kmbdcmWnnextyronty12ri-5 doc 12-4

= BYRON Revision 1.5 October 1997 O-I TABLE 12.1 1 ) FREQUENCY NOTATidNS* Notatior) - Freauency i S Shiftly At least once per 12 hours D Daily Atleast once per 24 hours W-Weekly At least once per 7 days M Monthly At least once per 31 days Q. Quarterly At least once per 92 days SA. Semiannually At least once per 184 days - A Annually At least once per 366 days R - Refuel Cycle At least once per 18 months S/U Startup Prior to each reactor startup N.A. Not applicable P Prior Prior to each radioactive release

• Each frequency requirement shall be performed within the specified time interval with the rnaximum allowable extension not to exceed 25% of tr.4 frequency interval. The 25% variance shall not be applied to Operability Action statements. The bases to Technical Spacification 4.0.2 provide clanfications to this requirement. These frequency notations do not apply to the Radiological Environmental Monitoring Program as described in Sectbn 12.5.

a ' O. U . g twsusamanne@ytomy12r1-5 doc 12 5

BYRON Revision 1.5 October 1997 O 12.2 INSTRUMENTATION j 12.2.1 Radioactive Liquid Effluent Monitoring instrumentation Ooerabilttv Reauirements 12.2.1.A The ladioactive liquid effluent monitoring instrumentation channels shown in Table 12.2-1 shall be OPER ABLE with their Alarm / Trip Setpoints set to ensure that the limits of 12.3.1.A are not exceeded. The Alarm / Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM. Aeolicabilite: At all times ACh0D 1. With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channelinoperable. 2. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 12.2-1. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Radioactive Effluent Release Report pursuant to Section 12.6 why this inoperability was not corrected within the time specified. Surveillance Reauirements 12.2.1.B Each radioactive liquid effluent monitoring instrumentation channel shall be demor% rated OPERABLE by performance of be CHANNEL CPECK, SOURCE CHECK, CHANNEL CAllBRATION and DIGITAL and ANALOG CHANNEL OPERATIONAL TEST at the freq.sencies shown in Table 12.2 2. Bases 12.2.1.C The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The Alarm / Trip Setpoints for these instruments sheii be calculated and adjusted in accordance with the methodology and parameters in t':s ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of RETS. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Cnteria 60,63, and 64 of Appendix A to 10 CFR Part 50. O g umbdcmunnextyroney12ri 5 doc 12-6

k' October 7 TABLE 122-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION 1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release a. Liquid Radwaste Emuent Line (ORE-PR001) 1 31 b. Fire and Oil Sump (ORE-PR005) 1 34 c. Condensate Polisher Sump Discharge (ORE-PR041) 1 34 2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release a. Essential Service Water 1) Unit 1 a) RCFC 1A and 1C Outlet (1RE-PR002) 1 32 b) RCFC 18 and 1D Outlet (1RE-PR003) 1 32 2j Unit 2 a) RCFC 2A and 2C Outlet (2RE-PR002) 1 32 b) RCFC 28 and 2D Outlet (2RE-PR003) 1 32 b. Station Blowdown Line (ORE-PRO 10) 1 32 3. Flow Rate Measurement Devices a. Liquid Radwaste Emuent Line (Loop-WX001) 1 33 b. Liquid Radwaste Emuent Low Flow Line (Loop-WX630) 33 c. Statior' Blowdown Line (Loop-CWO32) 1 33 g bmbdcrrnannextyron'by12ri-5 doc 12-7

BYRON Revision 1.5 October 1997 TABLE 12.2-1 (Continued) RADIOACTIVE LIQUJD EFFLUENT MONITORING INSTRUMENTATION ACTION STATEMENTS ACTION 31 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 14 days provided that prior to initiating a release: a. At least two independent samples are analyzed in accordance with Section 12.3 and b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving. Otherwise, suspend release of radioactive effluents via this pathway. ACTION 32 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 12 hours, grab samples are collected and analyzed for radioactivity at a lower limit of detection as specified in Table 12.3-1. ACTION 33 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours during actual releases. Pump performance curves generated in place may be used to estir.iate flow. ACTION 34 - With the number of channels OPERABLE less than required by the Minimum Channels OPERA 9tE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for radioactivity at a lower limit of detection as specified in Table 1? 31: At least once per 12 hours when the specific activity of the secondary coolant is a. greater than 0.01 microcurie / gram DOSE EQUIVALENT l 131, or b. At least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT l-131. O g kmbdemwrw:satyronby12ri 5. doc 12-8

o o e ~: BYRON Revisen 1.5 October 1997 TABLE 12.2-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVFil I ANCE REQUIRFtFNTS DIGITAL ANALOG CHANNEL CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL i ~ INSTRUMENT CHECK CHECK CALIBRATION TEST TEST 1.- Radcactrvity Monitors Prov* ding Alarm and Automabc Termmahon of Release

a. Liqued Radweste Effluent Line (ORE-PR001)

D P R(3) O(1) NA

b. Fire and Oil Sump Descharge (ORE-PR005)

D M R(3) Q(1) NA

c. Condensate Polisher Sump Discharge (ORE-PR041)

D M R(3) O(1) NA 2. Radcachwity Monitors Providing Alarm But Not Provdng Automabc Terminabon of Release a. Essenbal Service Water 1) Unit I a) RCFC 1A and 1C Outlet (1RE-PR002) D M R(3) Q(2) NA b) RCFC 18 and 1D Outlet (1RE-PR003) D M Rg3) Q(2) NA i 2) Unit 2 a) RCFC 2A and 2C Outlet (2RE-PR002) D M R(3) O(2) NA b) RCFC 28 and 2D Outlet (2RE-PR003) D M R(3) O(2) NA l b. Sth Blowdown Line (ORE-PRO 10) D M R(3) O(2) NA 3. Flow Rate Measurement Devmes a. Liqued Radwaste Effluent Line (Loop-WX001) D(4) NA R NA' Q b. Liquid Radweste E* fluent Low Flow Line D(4) NA R NA Q (Loop-WX630) c. Stabon Blowdown Line (Loop-CWO32) D(4) NA R NA' Q g wnetyroney12r1-5 doc 12, 4 i

BYRON Revision 1.5 October 1997 TABLE 12.2-2 (Continued) RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIONS (1) The DIGITAL CHANNc.L OPERATIONAL 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 (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or c. Detector check source test failure, or d. Detector channel out-of-service, or e. Monitor loss of sample flow. (2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists: a. Instrument indicates measured levels above the Alarm Setpoint, or e b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or mon!'or loss of power), or c. Detedor check source test failure, or d. Detector channel out-of-service, or e. Monitor loss of sample flow. (3) The initial CHANNEL CAllBRATION shall be performed using one or more of the reference standards certified by the Nationalinstitute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of cnergy and measurement range. For subsequent CHANNEL CAllBRATION, sources that have been related to the l initial calibration shall be used. (4) CH/,NNEL CHECK shall consist of venfying indication of flow during periods of release. CHANNEL CHE:CK shall be made at least once per 24 hours on days on which continuous, periodic, or batch releases are made. l l 9 g wmbocmunnextyronty12ri 5 doc 12-10

BYRON R:vtion 1.5 October 1997 O V 12.2.2 Radioactwe Gaseous Effluent Monitorina Instrumentation Ooerabiktv Reauirements 12.2.2.A The radioactive gaseous effluent monitoring instrumentation channels shown in Table 12 2 3 shall be OPERABLE with their Alarm / Trip Setpoints sei s ensure that the limits of Section 12.4 are not exceeded. The Alarm / Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM. 6pokcabihtv: As shown in Table 12.2 3 Actiorl 1. With a radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channelinoperable. 2. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, taKe the ACTION shown in Table 12.2 3. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Radioactive Effluent Rr lase !O Report pursuant to Section 12.6 why this inoperability was ni ; corrected within the l V time specified. Surveillance Reauirements. 12.2.2.B Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION and DIGITAL and CHANNEL OPERATIONAL TEST at the frequencies shown in Table 12.2-4. Bases 12.2.2.C The radioactrve gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actua! or potential releases of gaseous effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm /tnp will occur prior to exceeding the hmits of RETS. The instrumentation also includes provisions for monitoring (and controlhng) the concentrations of potentially explosive gas mixtures in the WASTE GAS HOLDUP SYSTEM. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63, and 64 of Appendix A to RETS. The sensitivity of any noble gas activity monitor used to show compliance with the gaseous effluent release requirements of Section 12.4 shall be such that concentrations as low as 4 1x10 uCi/cc are measurable. (D -( l g%mbdenMnnextyronty12ri 5 doc 12 11 l l

BYRON Revision 1.5 October 1997 TABLE 12.2-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTAllON M!N MUM CHANNELS INSTRUMENT OPERABLE APPLICAB!LlTY ACTION 1. Plant Vent Monitoring System - Unit 1 a. Noble Gas Actmty Monitor-Providing Alarm

1) High Range (1RE-PR028D) 1 39

2) Low Range (1RE-PR028B) 1 39 b.

lodine Sampler (1RE-PR026C) 1 40 c. Particulate Sampler (1RE-PR028A) 1 40 d. Emuent System Flow Rate Measuring Device (LOOP-VA019) 1 36 e. Sampler Flow Rate Measuring Device (1FT-PR165) 1 36 2. Plant Vent Monitonng System - Unit 2 a. Noble Gas Activity Monitor-Providing Alarm

1) High Range (2RE-PR028DJ 1

39

2) Low Range (2RE-PR0288) 1 39 b.

lodine Sampler (2RE-PR028C) 1 40 c. Particulate Sampler (2RE-PR028A) 1 40 d. Emuent System Flow Rate Measuring Device (LOOP-VA020) 1 36 e. Samp:er Flow Rate Measuring Device (2FT-PR165) 1 3G g wmbdcrmannexeyroney12rt-5 doc e 6 e

o-qRON o ~ Revisson 1.5 ,i October 1997 TABLE 12_2-3 iConW) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTROnsNTATION (CONT *D) MINIMUM CHANNELS INSTRUMENY OPER/BLE APPLICABILITY ACTION 3. Not Used. r. '4. Gas Decay Tank System a. Noble Gas Activity Monitor-Providing Alarm and Au*tr.:stic Tenmnabon of Release (ORE-PR002A and 28) 2 35 5. Containment Purge System 4 a. Noble Gas Activity Monitor-Providing Alarm (RE-PR001B) 1 37 b. lodine Sampler (RE-PR001C) 1 40 L ~ c. Partf'Me Sampler (RE-PR001A) 1 40 . 6. Radeactivity Monitors Providing Alarm and Automate Closure of Surge Tank Vent-Component Cooling Water Line d (ORE-PR009 and RE-PR009) 2 41- ? { l g WrnodernWmembron%12rt-5. doc 4 12-13

BYRON Revision 1.5 October 1997 TABLE 172-1] Continued) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (CONTD) TABLE NOTATIQHS

• At all times.

ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 14 days provided that prior to initiatmg the release: a. At least two independent samples of the tank's contents are analyzed, and b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup. Otherwise. suspend release of radioactive effluents via this pathway. ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours. ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERACLE requirement, immediately suspend PURGING of radioactive effluents via this pathway. Releases may continue via this pathway for up to 7 days provided real time monitoring of radioactive effluents released via this pathway is established. ACllON 38 - Not used. ACTION 39 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 12 hours and these samples are analyzed for principle gamma emitters at an LLD as specified in Table 12.41. ACTION 40 - With the numbe of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases vic the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required in Table 12.41. ACTION 41 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 12 hours, gaseous grab samples are collected and analyzed for radioactivity at a lower limit of detection as specified in Table 12.4-1. O g Wmbdcm\\annextyrontyt?rt.5. doc 12 14 .y

,m OL O O m BYRON Reymon 1.5 Octooer 1997 TABLE 12.2-4 I RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRe_h3dTATION SURVFil i ANCE REQUUtFMFMTS DKMTAL. CHANNEL., MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE FUhCTIONAL UNIT CHECK CHECK CALIBRATION TEST . IS REQUIRED 1. PlantVent Monstonng System-Unit 1 .a. Nx4 Gas Actmty Monitor-Provdng Alarm .1) High Range (1REN80) D M R(3) Q(2)

2) Low Range (1RE-PR0288)

D M R(3) Q(2) b; lo6ne Sampler (1RE-PR028C) D M R(3) O(2) cc. Parbculate Sampier (1RE-PR028A) D M R(3) Q(2) d. Effluent System Flow Rate Measunng D NA R Q Dmnce (LOOP-VA019) \\ e. Sampler Flow Rate Measunng Devce D NA R Q i (1FT-PR165) N . 2. Plant Vent Mendonng System - Unit 2 - a. Noble Gas Activity Morntor-Provdng i

1) High Range (2RE-PR028D)

D M R(3) Q(2)

2) Low Range (2RE-PR02SB)

D M R(3) Q(2) i b. lo&ne Sampler (2RE-PR028C) D M R(3) Q(2) - g ' ii uuun ..dL,iunw,12rt-5 che. r 12-15 I

BYRON Revision 1.5 October 1997 TABLE 12.2-4 (Continued) BADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DIGITAL CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CHECK CALIBRATION TEST IS REQUIRED 2. Plant Vent Monitoring System - Unit Two (Continued) c. Particulate Sampler (2RE-PR028C) D M R(3) O(2) d. Emuent System Flow Rate Measuring D NA R Q Device (LOOP-VA020) e. Sampfer Flow Rate Measuring Device D NA R Q (2FT-PR165)

3. Not Used

4. Gas Decay Tank System a.

Noble Gas Activity Monitor P P R(3) Q(1) Providing Alarm and Automatic Termination of Release (ORE-PR002A and 28)

5. Containment Purge Systern a.

Noble Gas Activity Monitor-Providing Alarm (RE-PR0018) D P R(3) Q(2) b. todine Samt. (RE-PR001C) P P R(3) NA c. Particulate Sampler (RE-PR001A) P P R(3) NA

6. Radioactivity Monitors Providing Alarm and Automatic Closure of Surge Tank Vent-Component Cooling Water Line (ORE-PR009 and RE-PR009)

D M R(3) Q(1) h E

BYRON Revision 1.5 October 1997 [ TABLE 12.2-4 fContinued) k RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIONS

• At all times.

(1) The DIGITAL CHANNEL OPERATIONAL 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 at Ove the AlarmfTrip Setpoint, or b. Circuit failure (monitor loss of et.munica' ons - alarm only, detector loss of counts, or monitor loss of power), or c. Detector check source test failure, c, d. Detector channel out-of-service, or e. Monitor loss of sample flow. (2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists: O V a. Instrument indicales measured levels above the Alarm Setpoint, or b. Circuit failure (monitor loss of communications alarm only, detector loss of counts, or monitor loss of power), or c. Detector check source test failure, or d. Detector channel out-of-service, or e. Monitor loss of sample flow, (3) The initial CHANNEL CAllBRATION 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 with 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. (~) U g Wnbdemwnnextyronty12r1-5. doc 12-17

BYRON Revision 1.5 October 1997 12.3 LIQUID EFFLUENTS 12.3.1 Concentration Doerabiftty Recuirements 12.3.1. A The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Byron Station ODCM Annex, Appendix F, Figure F-1) conforming to 10 times the concentration values in Appendix B, Table 2. Column 2 to 10CFR20.1001-20.2402. For dissolved or entrained noble gases, the concentration shall be limited to d 2x10 microcurie /mitotalactivity. AR2hCabihty: At all times 6CliOE 1. With the concentration of radioact9e material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits. Surveillance Reauirements 12.3.1.B.1 Radioactive liquid wastes shat be sampled and analyzed according to the sampling and 'l analysis program of Table 12.3-1. lO 12.3.1.B.2 The results of the radiorctivity analysis shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are m&intained with the Smits of 12.3.1.A. Bases 12.3.1.C This roecification is provided to ensure that the concentration of radioactive materials releastM h 11uid waste effluents to UNRESTRICTED AREAS will be less than 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR Part 20.1001 l 20.24C2. This limitation provides additional assurance that the levels of radioactive matorials in bodies of water in UNRESTRICTED AREAS will result in exposures within: (1) the Section ll.A design objectives of Append!x 1,10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.1301 to the population. This specification applies to the release of radioactive materials in liquid effluents from all l units at the site. The required detection capabilrties for radioactive, materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., " Limits for Quatriative Detection and Quantitative Determination - l Application to Radiochemistry," Anal. Chem. 40. 586-93 (1968), and Hartwell, J.K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975). O l l-g wmedemwnnexwymneyuri.5 doc 12 18 i l l

BYRON Revtion 1.5 October 1997 j TABLE 12.31 RADIOACTIVE LlOUlD WASTE SAMPLING AND ANALYSTS PROGRAM i l LOWER LIMIT MINIMUM OF DETECTION LlOUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)"' TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/ml)

1. Batch P

P Pnncipal Gamma 5x10 Release Each Batch Each Batch Emitters

• Tanks
• l131 1x10' P

M Dissolved and 1x10' One Batch /M Entrained Gases 1 Gamma Emitters) P M H3 1x10~" Each Batch Composite

• Gross Alpha 1x10

P Q Sr 89, Sr 90 5x10* Each Batch Composite

• Fe-55 1x10'

2. Continuous Continuous

W Pnnespal Gamma 5x10 Rel6. es

• Composite
• Emitters
• l I

l131 1x10'

a. Circulating M

M Dissolved and 1 x10 Water Grab Sample Entrained Gases Blowdown (Gamma Emitters)

b. Waste Water Continuous""

M H-3 1x10* Treatment Composite

• Discharge to Circulating

. Water Discharge Gross Alpha 1 x10

c. Condensate Continuous""

Q Sr-89, Sr 90 5x104 Polisher Sump Composite

• Discharge Fe-55 1x10' g wcwoocmwnnestyronwy12rt 5 doc 12 19

BYRON Revision 1.5 October 1997 TABLE 12.31 (Continued) RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER 8.lMIT MINIMUM OF DETECTION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTMTY (LLD)"3 TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/ml)

3. Continuous W

W Principal Gamma 5x10' A Release *' Emitters") Grab Sample Essential Service Water, Reactor Containment Fan Cooler (RCFC) Outlet Line 1-13' 1x10' Dissolved and Entrained Gases (Gamma Emitters) 1x10'S H-3 1x10* O O g hvxtanunnextyronty12ri 5. doc 12-20

. - _ ~ BYRON Revtion 1.5 October 1997 IABLE 12 3-1 (Continued) RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGR6M TABLE NOTATIONS (1) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probabilrty with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation: LLD = 4fA s. E

• V
• 2.22 x 10. Y
• exp ( AAt)

Where: LLD = the lower limit of detection (microCuries per unit mass or volume),

s. =

the standard deviation of the backgrour,d counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E= the counting efficiency (counts per disintegration), l V= the sample size (units of mass or volume), 2.22 x 10' = the number of disintegrations per minute per microcurie, Y= the fractional radiochemical yield, when applicable, A= the radioactive decay constant for the particular radionuclide (sec "), and at = the elapsed time between the midpoint of sample collection and the time of counting (sec). Typical values of E, V, Y, at and should be used in the calculation. i lt should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement. (2) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling. (3) The principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54 Fe-59, Co-58, Co-60,2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to Section 12.6.2 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1 June 1974. AV g wmboomurmentyronty12r1-$. ooc 12-21 =.

BYRON Revrion 1.5 October 1997 TABLE 12.3-1 (Continued) RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS (4) 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 that is representative of the liquids released. (5) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e g., from a volume of a system that has an input flow during the continuous release. (6) To be representative of the quantities and concentrations of radioactive materials in ligt.u effluents, samples shall be collected continuously in proportion to the rate of flow of the edioent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release. (7) Not required unless the Essential Service Water RCFC Outlet Radiation Monitors RE-PR002 and 4 RE-PR003 indicates measured levels greater than 1x10 pCi/ml above background at any time during the week. O O g Wmbdcmbreextyroney12ri-5 doc 12-22

= ~ = -. _ BYRON Revision 1.5 October 1997 12.3.2 QQat pb Crsdh Reauirements 12.3.2.A The dose or dose commit'nent to a MEMBER OF THE PUBUC from radcactive materials in ' quid effluents released, from o'ach unit, to UNRESTRICTED AREAS (see Byron Staton ODCM Annex, Appendix F, Figure F 1) shall b limited: 1. During any calendar quarter to less than or equal to 1.5 mrems to the v. hole body and to less than or equal to 5 mrems to any organ, and 2. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ. 6polacability At all times. Action 1. With the calculated dose from the release of radioactive materials in liquid J effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the correct ye actions that have been taken to reduce the releases and the proposed correcove actions to be taken to assure that subsequent releases will *;9 in compliance with the above limits. Surveillance Raouirements 12.3.2.B 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 the ODCM at least once per 31 days. Bases 12.3.2.C This section is provideo to implement the requirements of Sections ll.A. Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Operability Requirements implement the guides set forth in Section ll.A of Appendix 1. The ACTION statements provide the required operating flexibility and at the same '.ime implement the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS ull be kept "as low as is reasonably achievable." The dose calculaton methodology end parameters in the ODCM ;mplement the requirements in Secton Ill.A of Appendix 1 that xGrmance with the guides of Appendix 1 be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBUC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquKI effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man From Routine Releases of Ructor Effluents For the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I" Revision 1, October 1977 and Regulatory Guide 1.113. " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendix 1," April 1977. bv g mmwww12 rim 12 23 II

BYRON R:; vision 1.5 October 1997 12.3.2 DQ12(Continued) Bases This section applies to the release of radioactive materials in hquid effluents from each resctor at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluei.t releases cannot accurately be ascribed to a s).ecific unit. An estimate should be made of the contributions frorr each unit based on input conditions, e.g., flow rates and radio 3ctivity concentrations, or, if not practia,able, the treated effluent releases may be allocated equally to each of the radioactive waste producirq) units s% ring the Radwas,te Tmatment System. For determining conformar,ce to Oportability Requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit. O I e g Wm'eccmunnextyronty12r1-5. doc 12-24

. _. ~. _. ___ __.,, _. _ _. _ _ _ __.. BYRON R: vision 1.5 ' October 1997 12.3.3 Liquid Radwasta Treatment Walam Oner=hihev p==%ments 12.3 3.A - The Liquid Radweste Treatment System shall be OPERABLE and appropnate portions of the system shall be used to reduce releases of redcactwity when the projected doses due to the liquid emuent, from each unit, to UNRESTRICTED AREAS (see Byron Station ODCM Annex, Appendix F, Figure F-1) would exceed 0.06 mrom to the whole body or 0.2 mrom to any organ in a 31-day penod Appicabihty - At all times. AGh00 4 1. With radioachve liquid waste tseing discharged without treatment and in excess of the above limits and any porten of the Liquid Raduaste Treatment System not in operaton, prepare and submit to the Commission within 30 days, pursuant to - ^ Technical Specification 6.9.2, a Special Report that includes the following information: a. Explanation of why liquid radweste was being discharged without treatment, identifcation of any inoperable equipment or subsystems, and the reason for the inoperability, 4 b. Action (s) taken to restore the inoperable equipment to OPERABLE stat.", and c. Summary description of action (s) taken to prevent a recurrence.- 4 Surveillance Rannirements 12.3.3.B.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be l projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when the Liquid Radweste Treatment System is not being fully utilized. - 12.3.3.B.2 The installed Liquid Radwaste Treatment System shall be considered OPERABLE by l meeting Sections 12.3.1.A and 12.3.2.A. I Ramme 12.3.3.C The OPERABILITY of the Liquid Radwaste Treatment S" stem ensures that this system l 1 will be available for ute wi snever liquid emuents require treatment prior to release to the enviro'mant The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in hquid effluents will be kept "as low as is reasonably achievable". This secten implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section ILD of Appendix l to 10 CFR Part 50. i g wmedemwwm%mney12rt-5 doc 12 4 m --<r-- vv---r w-w-w w -u,am e- ,r --N,+,~ v-a- -r---ve-wm-- rc w +w-e ew- --v.,--w-m~-, wren-,

BYRON R2vton1.5 October 1997 4 I I 12.3.3 Liouid Radwaste Treatment System (Continued) Baits The specified limits goveming the use of appropriate portions of the Liquid Radwaste Treatment System we:e specified as a suitable fraction of the dose design objectives set forth in Section ll.A of Appendix 1,10 CFR Part 50, for liquid efflue.its. This section app %s to the release of radioactwe materials in liquid effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicsble, the treated effluent releases may be allocated equally to each of the radioz~'Me waste producing units sharing the Radwaste Treatment System. For determining conformance to Operability Requirements, these allocotions from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit. O t s 1 O g Wn\\odt:rn\\annextyronty12ri 5. doc 12-26 j

l !m BYRON-Revtion 1.5 L October 1997 - 12.4 GASEOUS EFFLUENTS _12.4.1 -- Dona Raia nn r.hmsp.a.,% manen 12.4,1.A The does rate due to radioactwo materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Byron Stahon ODCM Annex, Appendix F, Figure F 1) shall be hmited to the following 1. For noble gases less than or equal to a dose rate of 500 mrom/yr to the whole body and less than or equal to a dose rate of 3000 mrom/yr to the skin, and 2. For iodine 131, lodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: less than or soual to a dose rate of 1500 mrom/yr to any organ. Anphcabeldy At all times. MiGD 1. With die dose rate (s) exceeding the above limits, immediately restore the release rate to within the above limit (s). Survedlanca Recairements 12.4.1.B 1 .Th dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM. 3 12.4.1.B.2 The dose rate due to lodine-131, lodine-133, tritium, and all radionuclides in particulate l form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program speedied in Table 12.4-1. Baema - 12.4.1.C This sechon is provided to ensure that the dose at any time at and beyonet the SITE - BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of RETS. - These limits provide reasonable assurance that radioachve matenal - discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outs % the SITE BOUNDARY specified in 10 CFR 20.1301. If 9'h%mney12rt.s. doc 12 27 d- _______.-._L__L.-

BYRON R;v'" ion 1.5 October 1997 12.4 GASEOUS EFFLUENTS Bases For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be suff;ciently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the wrresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond tis SITE BOUNDARY to less than or equal to a dose rate of 500 mrem / year to the whole body or to less than or equal to a dor,e rate of 3000 mrem / year to the skin. These release rate limits also restrict, at all times the corresponding thyroid dose rate above background via the inhalation pathway to less than or equal to a dose rate of 1500 mrems/ year. This section applies to the release of radioactive materials in gaseous effluents from all units at the site. The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., " Limits for Qua!itative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40. 586-93 (1968), and Hartwell, J.K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975). O Intercretations 12 4.1.D This Technical Standard requires sampling and analysis following a power change exceeding 15% of Rated Thermal Power within a 1 - hour period. The interpretation of this requirement for power etwiges is as follows: a) Samples are required to be pulled within 24 hours of the power transient b) If there are several power transients that exceed 15% RATED THERMAL POWER per hour, sampling aced only be performed after the last transient but within 24 hours of the first transient that exceed 15% of RATED THERMAL POWER. In all cases, sample analysis shall be completed within 48 hours of the start of the initial transient. O g wmbocmunnextyronty12ri 5 doc 12-28

^\\ - Revision 1.5 - ~$ October 1997 TABLE 12.4-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM TYPE OF LOWER LIMIT OF ' l SAMPLING ANALYSIS ACTIVITY ANALYSIS DETECTION (LLD)"' l. GASEOUS RELEASE TYPE FREQUENCY FREQUENCY (pCi/cc) l P P l

1. Waste Gas Decay Each Tank Each Tank Principal Gamma Erntters" 1x10*

l Tank Grab Sample

2. Containment Purge P

P Each Purge

• Each Purge
• Princtoal Gamma Erntters*

1x10d Grab Sample H-3 1x10

3. AuxiE'ry Bkig.

M*' M Principal Gamma Erntters"3 1x10* - Vent Stack. Grab Sample - (Unit 1 and 2) H-3 1x10 Continuous" W f-131 1x10* Charcoal Sample 1-133

C*

Continuous

• W

Principal Gamma Ernitters"' Particulate Sample 1x10'" Continuous" O Gross Alpha Composite 1x10'" Particulate Sample Continuous

• Q Sr-89, Sr-90 Composite 1x10-"

Particulate Sample Continuous N.A. Noble Gases: Gross Beta or Noble Gas Monitor Gamma 1x10* g Wmbdcmwmextyronty12ri-5. doc 12-29 a. ^

BYRON Revtion 1.5 October 1997 TABLE 12.4-1 (Continued) RADIOACTIVE GASEOUS WASTE SAMPLING ANDANALYSIS PROGRAM TABLE NOTATIONS (1) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive rraterial in a sample that w?! yield a net count, above system background, that will be detected with 95% probability with only 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 s. ~ E V 2.22 x 10' Y exp (-Aat) Where: LLD = the lower limit of detection (microCuries per unit mass or volume), s, = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E= the counting efficiency (counts per disintegration), T V= the sample size (units of mass or volume), 2.22 x 10' = the number of disintegrations per minute per microcurie, Y= the fractional radiochemical yield, when applicable, A= the radioactive decay constant for the particular radionuclide (sec "), and at = the elapsed time between the midpoint of sample collection and the time of counting (sec). Typical va'oes of E, V, Y, and at should be used in the calculation. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement. (2) The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-8L, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases aild Mn-54, Fe-59, Co-58, Co-60, Zn45, Mo-99,1-131, Cs-134, C3-137, Ce-141, and Ce-144 in iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Repoit pursuant to Section 12.6.2, in j the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974. O g%mbdcmunnext fron\\by12rl-5. doc j 12-30

BYRON Revision 1.5 - October 1997 TARI F 12.41 (ContiruM RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS (3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour penod (4) Tritium grab samples shall be taken at least once per 24 hours when the refueling canal is flooded (5) Tritium grab samples shall be taken at least once per 7 days from the spent feel pool area, whenever spent fuel is in the spen'. fuel pooi. (6) The ratio of the semple flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Sectons 12.4.1.A.- 12.4.2.A and 12.4.3.A. (7)' Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing, or after rstaoval from sampler. Sampling shall also be performed at least once per 24 hours for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours of changing. When samples collN:ted for 24 hours are ainlyzed, the corresponding LLDs may be increased by a factor of 10. This requirament does not apply if-(1) analysis shows that the DOSE EQUIVALENT l 131 concentrabon in the reactor coolant has not.ncrease more than a factor of 3, and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3. q g wmedcmwwwxtyroney12r1-5 ooc 12 31

} i BYRON Revrion 1.5

• l Oc'ober 1997 12.4.2 Dose Noble Gases l

Ooerabilrty Rg2uirements 12.4.2.A The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond me SITE BOUNDARY (see Byron Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the following: 1. During any calendar quarter: Less than or equa' to 5 mrads for gamma radiation and less than o equal to 10 mrads for beta radiation, and 2. During any calendar year: Less than or equal to 10 mrads for gamme radiation and less than or equal to 20 mrads for beta radiation. golicability: At all times. Action: 1. With the calculated air dose from radioactive nobic gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the reletses and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. Surveillance Re2uirements 12.4.2.B Cumulative dose contributions for the current calendar quarter and the current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days. Bases 12 4.2.C This section is provided to implement the requirements of Sections 11.B, ;ll.A and IV.A of Appendix 1,10 CFR Part 50. The Operability Requirements implement the guides set forth in Section 11.8 of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix l to assure that the releases of radioactive material in gaseous effluents at or beyond the Site Boundary will be kept "?.s low as is reasonable achievable " The Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix i be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. O g Wm2demunnextymtmy12ri-5 doc 12-32 1

BYRON Revtion 1.5 Octobe r 1997 12A.2 Dose - Noble na*** (Continued) s s Raame The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactwe materials in gaseous emuents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents For the Purpose of Evatusting Compliance with 10 CFR Part 50, Appendix I" Revision 1, October 1977 and Regulatory Guide 1.111 " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Wa'.er Cooled Reactors, Revision 1," July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average r.*mospheric condrtions. This secten applies to the release of radioactive matenals in gaseous effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than ona unit on a site, the wastes from all units are mixed for shared treatment, by such tr' the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practbabie, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit. O ) g Wmbdcmunnextyronty12ri-5. doc 12-33

BYRON Revrion 1.5 October 1997 12.4.3 Dose -lodine-131. lodine-133. Tritium. and Radioactive Material in Particulate Form Ooerability Reauirements 12.4.3.A The dose to a MEMBER OF THE PUBLIC from lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to artsas at and beyond the SITE BOUNDARY (see Byron Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the following: 1. During any calendar quarter Less than or equal to 7.5 mrems to any organ, and 2. During any calendar year Less than or equci to 15 mrems to any organ. Aeolicabilitv: At all times. Action 1. With the calculated dose from the release of lodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases end the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. Surveillance Recuirements 12.4.3.B Cumulative dose contributions for the current calendar quarter and the current calendar year for lodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days. Bases 12.4.3.C This section is provided to implement the requirements of Sections ll.C Ili.A and IV.A of Appendix 1,10 CFR Part 50. The Operability Requirements are the guides set forth in Section ll.C of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix i to assure that the releases of radioactive material in gaseous effluents at or beyond the Site Boundary will be kept "as low as is reasonable achievable." The ODCM calculational methods specified in the Surveillance Requirements implernent the requirements in Section lil.A of Appendix i that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure cif a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. O g%mbdot9annextyronty12r1-5. doc 12-34

= BYRON Revision 1.5 October 1997 12.4.3 QQas (Continued) n. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject malerials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents For the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I" Revision 1, October 1977 and Regulatory Guide 1,11_1, " Methods ft,r Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Watsr-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for todine-131, lodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon tt:e existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY, The pathways that were examined in the development of these calculations were: (1) individual inhalation of airbome radionuclides, (2) deposition of radionuclMes onto green leafy vegetation with subsequent consumption by man, (3) ' deposition onto grassy areas where milk animals and meat producing animars gran with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure to man. Thb section applies to the release of radiocctive materists in gaseous effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates (3 and radioactiviiy concentrations, or, if not practicable, the treated effluent releases may be \\ a! located equally to aach of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to Oper,bility Requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit. r\\ '\\ ) V g WrmodcrMannexWyronWy12rt-5 doc 12-35

BYRON Revision 9.5 October 1997 12.4.4 Gaseous Radwaste Trea' ment System Ooerability Reauirements 12A4.A The VENTILATION EXHAUST TREATMENT SYSTh.. and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous affluent releases, from each unit, to areas at and beyond the SITE BOUNDARY (see myron Station ODCM Annex, Apoendix F, Figure F-1)would exceed: 1. 0.2 mrad to air from gamma radiation, or 2. 0.4 mrad to air from tm;m radiation, or 3. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC. Acolicability: At all times. Action 1. With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that includes the following information: I a. Mentification of any inoperable equipment or subsystems, and the reason i for the inoperability, b. Action (s) taken to restore the inoperable equipment to OPERABLE status, and c. Summary description of action (s) taken to prevent a recurrence. Surveillance Reauirements 12.4.4.B.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at east once per 31 days in accordance with the methodology and parameters in the ODCM when Gaseous Radwaste Treatment Systems are not being fully utilized. 12.4.4.B.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS l HOLDUP SYSTEM shall be considered OPERABLE by meeting Section 12.4.1 and 12 4.2 or 12.4.3. Bases 12.4.4.C The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment p*ior to release to the environment. O g %mbdo19.armextyronty12r1-5 doc 12-36

... -. ~ -. 'C BYRON' Revnion 1.5 - ~ October 1997 123.4" Gaseous Radwaste Treatment System (Continued) -N - The requirement that the appropnate portons of this system be used when specified ' provides reasonable assurance that % releases of radioactwo materials in gaseous emuents will be kept "as low as is reasonably achievable". This secten implements the. requirements of 10 CFR 50.36a, General Design Criterion 60 bf Appendix A to 10 CFR Part 50 and the design objectwo given in Secten ll.D of Appendix l to 10 CFR Part 50. The specified limits goveming the use of appropnate portons of the Gaseous Radweste Treatment System were specified as a suitable frachon of the dose design objectives set forth in Secton ll.B and ll.C of Appendix 1,10 CFR Part 50, for gaseous emuents. This secten apples to the release of radioactwo matenals in gaseous emuents from each - unit at the site. When shared Radweste Treatment Systems are used by more thaa one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, -- the efnuent releases cannot accurately be asenbod to a specific unit. An estimate should be made of the contributons from each unit based on input comfitions, e.g., flow rates and radioactwity concentrations, or, if not predM, the treated emuent releases may be allocated equally to each of the radioactwo waste producing units sharing the Radwaste ' Treatment System. For determining widvirr nce to Operability Requiremants, these allocatens from shared Radwaste Treatment Systems are to be added to the releases wiuity attributed to each unit to obtain the total releases per unit. L I (- L' i , ( 1 g wmbdcrniennextyronty12ri 5.coc 12-37 i f ~ ~ . _, +. - ..., +.,. - - -,...... + -..,- - .~

BYRON Revision 1.5

• i October 1997 12.4.5 Iotal Dose Ooerability Reauirements 12.4.5.A.

The annual (calendar year) dose or dose commitment to any MEMOER OF THE PUBLIC due to releases of radeoactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. i Anoticabilitv: At all times. Action 1. With the cale'. stated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Sections 12.3.2,12.4.2, or 12.4.3, calculations should be made including direct radiation contributions from the units and from outside storage tanks to determine whether the above limits of Section 12.4.5 have been exceedei If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequer;t releases to prevent recurrence of exceeding the above limits and includes the schedule for acheving conformance with the above limits. This Special Report, as defined in 10 CFR 20.2203, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this reprt. It shall also describe levels of radiation and concentration of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 100. Submittal of the report is considered a ;imely request, and a variance is granted until staff action on the request is complete. Surveillance Reauirements 12.4.5.B.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in l accordance with Sections 12.3.2,12.4.2, and 12.4.3, and in accordance with the methodology and parameters in the ODCM. 12.4.5.B.2 Cumulative dose contributions from direct radiation from the units and from radwaste l storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in ACTION 1 of Section 12.4.5. 12.4.5.B.3 Initial estimates of expected dose rates at the Old Steam Generator Storage Facility (OSGSF) are provided through calculatons. After the old steam generators are placed in the facility and the equipment opening is sealed, a radiation survey of the walls and roof will be performed. The measured dose rates will be used for compcrison to the calculated dose rates and to confirm or adjust the initial estimates for use in 10 CFR 20,10 CFR 50, Appendix 1, and 40 CFR 190 compliance determinations. O - g iembdcm\\pnnex\\byronty12r1-5 doc 12-38 a

BYRON R vision 1.5 October 1997 12.4.5 Total Dose (Continued) o (v) Surveillance Reouirements An environmental TLD is posted at the single fence nearnt tne OSGSF. The TLD is processed quarterly to determine the dose at that location hr trending purposes. Quarterly monitoring of the sump for indications of liquid is pe.1ormed and, if liquid is present and seepage appears to have occurred, a sample will be taken and analyzed. Bases 12.4.5.C.1 This section is proviced to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The Section requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix 1, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of at.; tion that should result in the limitation of the annual doso to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negiigible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE O' PUBLIC is estimated to exceed the requirements of 40 CFR Part 100, the Special Report v with a request for a variance (provided the release conditions resulting in violation cf 40 CFR Part 190 have not already been corrected), in accordance wi*h the provisions of 40 CFR 190.11 and 10 CFR 20.2203, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed The vanance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Sections 12.3.1 and 12.4.1. An individualis not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. 12.4.5.C.2 The OSGSF was constructed to provide long-term storage of the four old steam generators removed from Byron Station Unit i during the Steam Generator Replacement Outage. The facility is designed to ensure that the dose rates at the wall and roof meet the limits of 10 CFR Part 20 (UFSAR Zone I-A for the walls and Zone I-B for the roof). The facility is also designed to ensure that the dose rates at the site boundary and to the nearest resident meet the limits of 10 CFR Part 20 and 40 CFR Part 190. The OSGSF design includes 2'-6' thick concrete walls and 1'-6* inch thick concrete roof. Personnel access is through a labyrinth-style vestibule with a locked exterior door and a lockable sliding door for access beyond the vestibule to the interior of the facility. A water collection sump is provided with access from the vestibule for sarapling water if liquid is present. The opening used for placement of the steam generators inside the facility will be sealed with concrete panels. The panels have a tongue and groove design to preclude radiation " shine' after innta!!ation. p l g Wmbdctn\\ annex \\byromby12r15 doe 12-39 l t

l BYRON Revision 1.5 October 1997 12.4.5 Total Dose (Continued) hinats The potential for radiological release from the OSGSF is also minimized by sealing openings in the steam generators caused by removed piping with welded structural cover plates or seal plugs. Trunnions installed during removal of the old steam generators from the Containment and existing opening covers remain attached to the steam generators to ensure the penetrations are leaktight. Extemal exposed surfaces of the steam generators are coated to seal and fix surface contamination to the steam generators. O 9 g Wmwdemunnext~roney12rt 5. doc 12-40 9

BYRON R::vhion 1.5 October 1997 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM O 12.5.1 Monitorino Proaram Q' Ooerability Reauirements 12.5.1. A The Radiological Environmental Monitoring Program shall be conducted as specified in Table 12.5-1. Acolicabilrtv: At all times. Action 1. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 12.5-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Section 12.6.1, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal availability, malfunction of uampling equipment, if a person / business who participates in the program goes out of business or no longer can provide sample, or contractor omission which is corrected as soon as discovered. If the equipment malfunctions, corrective actions shall be completed as soon as practical. If a person / business supplying saraples goes out of business, a replacement supplier shall be found as soon as possible. All deviations from the sampling schedule will be described in the ~ Annual Radiological Environmental Operating Report. v 2. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 12.5-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose

• to a MEMBER OF THE PUBLIC is less than the calendar year limits of Section 12.3.2,12.4.2, or 12.4.3. When more than one of the radionuclides in Table 12.5.2 are detected in the sampling medium, this report shall be submitted if.

concentration (1) concentration (2) + ..t 1.0 reporting 10 vel (1) reporting level (2) When radionuclides other than those in Table 12.5-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose

• to A MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Section 12.3.2,12.4.2, or 12.4.3. This report is not required if the measured level of radioactivity was not th.3 result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Section 12.6.1.
• The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE fm PUBLIC shall be indicated in this report.

g Wmbacmwnnextyronwy12rt-5 doc 12-41

BYRON Revision 1.5 October 1997 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued) O 3. If the sample type or sampling location (s) as required by Tabit 12.5-1 become(s) permanently unavailable, identify suitable attemative sampling media for the pathway of interest and/or specific locations for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program as soon as practicable. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Prepare and submit controlled version of the ODCM within 180 days including a revised figure (s) and table reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of new location (s) for obtaining samples. Surveillance Reauirements 12.5.1.8 The radiological environmental monitoring program samples shall be collected pursuant to Table 12.5-1 from the specific locations givea in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 12.5-1 and the detection capabilities required by Table 12.5-3. Bases 12.5.1.C The Radiological Environmental Monitoring Program required by this section provides representative measurements of radiation and of radioactive materials in thosc exposure pathways and for those radionuclidcs that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implements Section IV.D.2 of Appendix 1 to 10 CFR Part 50 and thereby supplements the radiologicci effluent monitoring program by verifying that the measurable enneentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specifwsd monitoring program will be effective for at least the first 3 years of commercial operation. Following this peried, program changes may be initiated based on cperational experience. The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 12.5-3 are considered optimum for routine environmental measurements in industriallaboratories. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact lirr,it for a particular measurement. Detailed discus = ion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, LA., " Limits for Qualitative Detectior, and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40,586 93 (1968), and Hartwell, JK," Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975). O g%mWk:nnannextyronty12r15. doc 12-42

l ~ BYRON Revtion 1.5 October 1997 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued) O-Interoretahons 12.5.1.D ~ Table 12.5-1 requires."one sample of each cor vnunity drinking water supply downstream of the plant within 10 kilometers." Drinking water supply is defined as water taken from rivers, lakes, or reservoirs (not well water) which is used for drinking. 3 i w h g mwwwxwrong12r14 doc 12-43

^ BYRON Revision 1.5 October 1997 TABLE 12.5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMFLING AND COLLECTION TYPE AND ANDI OR SAMPLE AND SAMPLE LOCATIONS"8 FREQUENCY FREQUENCY OF ANALYSIS

1. Airborne Samples from a tota: of eight locations:

Continuous particulate sampler Radiotodine Canistec Radiobdine and operation with sample collection 1-131 analysis biweekly Particulates

a. Indicator-Hear Field weekly, or more frequently if on near field samples and required due to dustloading, and control."

Four samples from locations within 4 km (2.5 mi) radiciodine canister collection in different sectors. biweekly. Particulate Samoler-Gross beta analysis

b. Indicator-Far Field followirg'and gamma weekly filter change Three additio :.nllocations within 4 to 10 km (2.5 isotopic analysis")

to G.2 mi) in different sectors. quarterly on composite filters by location on near

c. Control field samples and control."

One sample : um a control location within 10 to 30 km (6.2 to 18_6 mi). g Wnbdcmunnextyrormy12rt-5 doc 12-44 O O O m s

7 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND ANOIOR SAMPLE AND SF 'LE LOCATIONSm FREQUENCY FREQUENCY OF ANALYSIS

2. Direct Fr> N routine mointonng stations either with a Quarterty Gamma dose on each Radiation * -

the noluminescent docJ neter (TLD) or with one TLD quarterfy. instrument for measuring dose rate continuously, placed as follows

a. Indicator-Inner Ring (100 Series Tl D) l One in each meteorological sector, in the general area of the SITE BOUNDARY i

(0.1 to 2 miles);

b. Indcator-Outer Ring (200 Senes TLD)

One in each meteorological sector, within 3.2 to 10 km (2 to 6.2 mi); and

c. Other One at each Airbome location given in part 1.a. and 1.b.

The balance of the TLDs to be placed at special I interest locations beyond the Restricted Area where either a MEMBER OF THE PUBLIC or Commonwealth Edison employees have routine m ss. (300 Sener TLD) g h/Aiennex%ronty12ri-5 doc - 12-45 m:

BVRON Revision 1.5 l October 1997 l l TABLE 12.5-1 (Continued) i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND ANDIOR SAMPLE AND SAMPLE LOCATIONS"3 FREQUENCY FREQUENCY OF l ANALYSIS

2. Direct

d. Contre

• Quarterly Gamma dose on each Radiation * (Cont'd)

TLD quarterly. One at cach Airborne control location given in i part 1.c

3. Waterbome

a. Indicator Quarterly Gamma isotopic and W

a. Ground / Well tritium analysis quarterfy.

i Samples from thrt e sources only if likely to be affected?' ~~EDridingC-~~~~~~~Ein~dicator-~~~~~~~~~~~---~~~-~~~~~ Weekly g aEsin~1ples~~-~~~~~ -~~- ~ ~ ieEn~aiid garE5a-Gross t isotopic analyses on One Sample from each community drinking monthly composite; water supply that could be affected by the tritium analysis on l station discharge within 10 km (6.2 mi) quarterl _d wnstreampf djscharge_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _y composite. P.

c. Surface if no community water supply (Drinking Water)

Weekly grab samples. Gross beta and gamma Water

• exists within 10 km downstream of discharge isotopic ana!yses) on then surface water samp!ing shall be performed.

monthly composite; tritium analysis on

a. Indicator quarterly composite.

_ _9Ee sampi.e.dgwnstream_ _ _ _ _ _ _ _ _ _ _ _ _ _

d. Control

a. Control Weekly grab samples.

Gross beta and gamma Sample") isotopic analyses") on One surface sample upstream of discharge. monthly composite; tritium analyrig on quarterly compi'ite. g \\embdcm'.annextyron\\by12r1-5 doc O F" 9

7 .g TABLE C'1 (Continued) RADIOLOGICAL ENVIRONMENTAL MOWITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND ANDIOR SAMPLE AND SAMPLF LOCATIONSm FREQUENCY FREQUENCY OF ANALYSIS

e. Sediment

a. Indcator Semennually Gar me isotope m

At least one sample from downstream area - within 10 km (6.2 mi). y y pasture (May through October), 1-131"* analysis on each

a. Milk

• Samples from milking animals from a monthly at other times sample maximum of three locations within 10 km (November through April).

(6.2 mi) distance. I

b. Control One sample from milking animals at a control locatim_with_in 10_tp,30,_km_16;2_to 18;6,mi). ___

---

__-__-_----____-a. Indicator Two times annually.

Gamma isotopic

b. Fish analysis

• on edible 1

Representative samples of commercially and portens - 1 recreationally important spece in discharge area. j

b. Control Representative samp!es of commercially and recreationally important species in control I locations upstream of discharge.

g wnwsennannexeyrenty12rt-5 doc 12-47 = -.... r -

BYRON Revision 1.5 October 1997 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPbSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND ANDIOR SAMPLE AND SAMPLE LOCATIONSm FREQUENCY FREQUENCY OF ANALYSIS

c. Food Products

a. Indcator Annually Gamma isotopic"'

analysis on each sample. Two representative samplas from the principal food pathways grown in each of four rnajor quadrants within 10 km (6.2 mi): At least one root vegetable sample"U At least one broad leaf vegetable (or vegetation)""

b. Control Two representative samples similar to indicator samples grown within 1E to 30 km (9.3 to 18.6 mi).

g wmbocmunroxeyroney12rt-5 doc O 6' O

p

BYRON:

- Revtion 1.5 l

• 4

.s October 1997 ~ ,.C ^ . TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONME' TAL MONITORING PROGRAM ~ n TABLE NOT/.TIONS l(1): Specific parameters of distance and direction from the centerline of the midpoint of the ~ two units and additioMI description where pertinent, shall be provided for each and every sample location in Table 11 1 of the ODCM Station Annexes, Refer to NOREG-0133, " Preparation of Radiological Efnuent Technical Spect6catens for Nuclear Power Plants," i: October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. ~ e-(2) Far Aeld samples are analyz'ed when the respectrve near field sample results are inconsistent with previous measurements and radioecbvity is confirmed as having its . origin in airbome efnuents from the station, or at the discreton of the Radiation Protecten

Director, i~

(3) . Airbome particulate sample Alters shall be analyzed for gross beta radioactivity 24 hours - or more after sampling to allow for redon and thoron daughter decay, if gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotope anmiysis shall be performed on the individual samples (4) - Gamma isotope analysis means the identificat,on and quantifcation of gamma emitting redenuclides that may be attnbutable to the ofRaents from the station. 4 .(5) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimetersf Film badges shali not be used as dosimeters for measuring r!irect radiation. The 40 locations is not an absolute number. The number of direct radiation monitoring - stations may be reduced according to geographicallimitations; e.g. if a station is adjacent to a lake, some sectors may be over water thereby reducing the number of dosimeters which could be placed at the indicated distances. The frequency of analysis or readout for TLD systems will depend upon the characteristes of the specific system used and should be selected to obtain optimum dose information with minimal fading. (6) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination. '(7) - The " downstream" s6mple shall be taken in an area beyond but near the mixing zone. ~ The

• upstream sample'shall be taken at a distance beyond significant influence of the discharge Upstream samples in an estuary must be taken far enough upstream to be y

beyond the station influence. (8) If milking animals are not found in the designated indcator locations, or if the owners ' decline to participate in the REMP, all milk sampling may be discontinued. p 1 _(9) Biweekly refers to every two weeks. p . (10) : 1 131 analysis means the analytical separation and counting procedure are specific for: .-this radionuclide. 4 ,(11), fOne sample shall consist of a volume / weight of sample large enough to fill contractor i. specified container, - - f i g WmodcmWmo&yfoey12rt 5. doc 1249 + .i.,, +.,. - -,~,..:-,.-- ,1

BYRON Revision 1.5 October 1997 TABLE 12.5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS WATER AIRBORNE PARTICULATE FISH MILA FOOD PRODUCTS ANALYSIS (pCi/I) OR GASES (pCi/m') (pCi/kg wet) (pCill) (pCi/kg, wet) H-3 20,000'" Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,006 l Co-60 300 10,000 Zn-65 300 20,000 l Zr-Nb95 400 1-131 2* 0.9 3 100 i Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 (1) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCill may be used. (2) If no drinking water pathway exists, a value of 20 pCi/I may be used. l gMmbdentannextyronby12rt-5 doc l 12-50 O O O

BYRON s TAELE 12.5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYS4"8 LOWER LIMIT OF DETECTION (LLD)*3 L j WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT - ANALYSIS (pCi/i) O ' GASES (pCi/m*) (pCi/kg. wet) (pCi/I) (pCi/kg wet) - (pCi/kg. dry) Gross Beta 4 0.01 1000 H-3 2,000

• Mn-54 15 130 Fe-59 30 260 Co-58,60 15' 130 Zn-65 30 260 Zr-Nb-95 15 l-131*

1/15"' O.07 100 0.5/5 ' 60 I 0 Cs-134 15 0.01 100 15 60 150 Cs-137 18 0.01 100 18 80 180 Ba-La-140 15 15 g%mbocmWnnextyronty12rt-5 doc 12-51

BYRON R: vision 1.5 October 1997 TABLE 12,5 3 (Continued) DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS (1) Tt e nuchdes on this hst are 7,ot tb. only nuchdes ir' tended to be considered Other peaks that are identifiable, tcgether with those of the above nuchdes, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report. (2) '4equired detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be j in accordance with the re ommendations of Regulatory Guide 4.13. (3) The Lower Limit of Detection (LLD)is defined, for purposes of these specifications, as the smallest concentration of radioactive mr* Jrialin a sample that will yield a net count, above system background, that will be detected with 95% probabikty with only 5% probabihty of falsety concluding that a blank observation represents a real" signct. For a particular measurement system, which may include radiocnemical separation, the LLD is defined as follows: 4.66 S, + 3/t, = (E) (V)(2.22)(Y)(exp ( bt)) 4.66 S. LLD (E) (V) (2.22) (Y) (exp (-ht)) Where: 4.66 S n 3/t, the "a prion" FAnimum Detectable Concentration (picoCtrles per t;nst mass or volume), LLD = i the standard deviation of the background counting rate or of the counting rate of a blank sample, s, = as appropriate (counts per minute), JTotal Counts la a E = the counting efficiency (counts per disintegration), V = the sample size (units of mass or vclume), 2.22 = the number of disintegrations per minute per picocurie, Y = the fractional radiochemic,al yield, when apphcable, A = the radioacth

• L ey constant for the parttular radionuclide (sec"),

O g%mbdcmunnexeyron%12r15 doc 12-52

t d e BYRON - Revision 1.5 October 1997 TABLE 12.5 3 (Continued) ) DETECTION CAPABILITIES FOR ENVIRONMENTAL SARIPLE ANALYSIS [ TABLE NOTATIONS ccanting time of the backgrcund or blank (minutes), and f t, a at =_ the elapsed time between sample collecbon, or end of the sample collection period, and the time i l of counting (sec). i Typical values of E, V, Y, and at shotM be used in the calculation. L it should be recognized that the LLD is defined as a before the fact limiuepresenting the capability of a f measurement system and not as an aftet the fact limit for a particular measurement Analyses shall be performed h1 such a manner that the stated LLDs will be achieved under routine conditions. Occasionally, background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render those LLDs unschievable. In such cases, the contributing factors i shall be identiflod and described in the Annual Radiological Environmental Operating Report. (4) If no drinking water pathway exists, the value of 15 pCM may be used. '(5)- A value of 0.5 pCill shall be used when the animals are on pasture (May through October) and a value of 5 pCill shall be used at all other times (November through April). ^ (6) This LLD applies only when the analytical separation and counting procedure are specific for this radionuclide. (7) _ This LLD is the minimum allowable, however, vendors performing environmental sample analyses off. site will be required to meet an LLD of 200 pCill. 4 W . h s 4 t ol } 12-53 a

BYRON Revrion 1.5 Octc,ber 1997 12.5.2 Land Use Censua Ooerability Recuirements 12.5.2 A A Land Use Census shall be conducted and shsilidentify within a distance of 10 km (6.2 miles) the location in each of the 16 meteorological sectors' cf the nearest milk animal, the nearest residence", and an enumeration of Svestock. For dose calculation, a garden will be assumed at the nearest residence. 6potreability: At al! times. Action

1. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment, via the rame exposure pathway 20% greater than at a location from which samples are currently being obtained in accordance with Section 12.5.1, add the new loca,tions) within 30 days to the Radiological Environmental Monitoring Program ghten in Chapter 11. The sampling location (s), excluding the control location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Submit in the next Annual Radiological Environmental Operating Report documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODCM reflecting the new location (s) with information supporting the change in sampling locations.

• This requirement may be reduced according to geographical limitations: e.g. at a lake site where some sector's will be over water.

"The nearest industrial facility shall also be documented if closer than the nearest residence. Surygi!Iance Reauirements O 12.5.2 B The Land Use Census shall be canducted during the growing saason, between June 1 and October 1, at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, senal survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report. Bases 12.5.2.C This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are ida.Uned and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of this census. This census sam,fies the requirements of Section IV.8.3 of Appendix l to 10 CFR Part 50. An annual garden census will not be required since the licensee will assume that there is a garden at the nearest residence in each sector for dose calculations. O g WmWcmunnexbyronty12r15 doc 12 54 ^

. _ - ~. BYRON Revison 1.5 October 1997 12 5.3 Inlarimboratory CLmpannon Program m p= ^==a:.s 12.5.3.A Analyses shall be performed on rMW matonali supplied as part of an interlaboratory Comparison Program that correspond to samples required by Table 12.51. Appleabddy' At all times. -- m 1. With analyses not being performed as required above, report the correctwo actens taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operstmg Report. Su, _^ s p=as h ;.;.".2 i 12.5.3.B A summary of the reseis obtained as part of the above required interlsboratory Comparison Program shall be included in the Annual Radiologica! Environmental Operating Report. Banet, 12.5.3.C The requirement for participaten in an Interlaboratory Comparison Program 12 provided to ensure that indspondent : checks on the precision and accuracy of the measuromonts of radioactwo materialin environmental samples matricos are performed as part of the qublity assurance program for environmental monitoring in order o demonstrate that the results are va;sd for the purposes of Secten IV.B.2 of Appendix 1 to 10 CFR Part 50. i O 5 E i i f 1 L- - $ i r ( giornWhutnerwiesdbysenty12rt.$tioc _ 12-55

BYRON R:vrion 1.5 Octotcr 1997 12.6 BFJORTING REQUIREMEN?S 12.6.1 Annua! Radioloaical Envirr.Aty tal Ooeratino Reoort' Routine Annual Radiological dnvironmental Operating Report covering the operation of the Unit (s) during the previous calendar year shall be submitteo prior to May 1 of each year. The Annual Radiological Environmental Operating Report shall incluve summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a companson with operational controls as appropnate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment-The Annual Radiological Enviror. mental Operating Report shallinclude the results of all radiological envircamental samples and of al! environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures in Chapter 11 of the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Ast,essment Branch Technical Posrtion, Revision 1, November 1979. In the event that some individual 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 as soon as possible in a supplementary report. The reports shall also include the following: a summaly description of the Radiological Environmental Monitoring Program; le,!ble maps covering all sampling locations k?yed to a table giving distances and directions from the midpoint between the two units; reasons for not conducting the Radiological Environmental Monitoring Program as required by Section 12.5.1, a Table of Missed Samples and a Table of Sample Anomalies for all deviations from the sampling schedule of Table 11.1 1; discussion of environmental sample measurements that exceed the reporting levels of Table 12.5-2 but are not the result of plant effluents, discussion of all analyses in which the LLD required by Table 12.5-3 was not achievable; result of the Land Use Census required by Section 12.5.2; and the results of the licensee participation in an Intertaboratory Comparison Program and the corrective accons being taken if the specified program is not being performed as required by Section 12.5.3. 'A sing'e submittal may be made for a multiple unit station. O g wmwocmwnnexwyroney12rt s doc 12-56

~ o BYRON Revrion 1.5 October 1997 j 12.6 REPORTING REQUIREMENTS (Cont'd) [ Annual Radioloaical Environmental Ooeratina Reoort (Cont'd) 's_/ The Annual Radiological Environmental Operating Report shall also include an annual summary of hourly meteorological data collected over the applicable year. Th;s annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmosphenc stability, in lieu of submission with the Annual Radiological Environmental Operating Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided ta the., NRC upon request. The Annual Radiological Environmental Operating Report shall also include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the Unit or Station during the previous calendar year. This repoit shall also include an assessment of the radiation doses to the most likely exposed MEMBER OF THE PUBLIC from reactor.eleases and other near-by uranium fuel cycle.ources including doses from primary effluent pathways and direct radiation, for the previous calendar year. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM, and in compliance with 10CFR20 and 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation." n) q gwmecomwnnex%roney12r15 doc 12 57

i u, BYRON R; vision 1.5 12.6 REPORTING REOb!REMENTS (Cont'd) l 12.6.2 Annual Radioactlye Effluent Release Reoort" i Routine Annual Ra.ficactive Effluent Release Reports covering the operation of the unit during the previous calendar year of operation shall be submitted prior to May 1 of the following year. The Annual Radsoactive Effluent Release Reports shallinclude a sumrrary of the quantities of rad;oactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three additional categories: class of solid wastes (as defined by 10 CFR Part 61), type of contain6r (e.g., LSA, Type A, Type B, Large Quantrty), and SOLIDIFICATION agent or absorbent (e.g., cement, urea formaldehyde). The Annual Radioactive Effluent Release Reports shallincluC) a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period. The Annual Radioactive Effluerit Release Reports shallinclude any changes made during the seporting period to the PCP as well as any major changes to Liquid, Gaseous or Solid Radwaste Treatment Systems, pursuant to Section 12.6.3. The Annual Radioactive Effluent Release Reports shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within tbs time specified in Section 12.2.1 or 12.2.2, respectively; and description of the events leading to liquid holdup tanks or gas storge tanks exceeding the limits of Technical Specification 3.11.1.4 or 3.11.2.6, respectively. Ns' ingle submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive matenal from each unit. O g%miodem\\nnnexWyronty12ri-s doc 12-58

l e ** BYRON Revbtn 1.5 October 1997 12.6.3 Offada Dona Calculahon Manual (ODCM) .1 The ODCM shall be approvad by the Commission prior to implementation. 12.6.3.2 Licensee-initiated changes to the ODCM: s. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2. This documentation shall contain: j 1. Sufficient informaton to support the change together with the appropriate analyses or evaluations justifying the changes (s); and 2. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR Part 20,40 CFR Part 190,10 CFR 50.36a, and Appendix i to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculatons. bi Shall become effective after review and acceptance by the Onsite Review and Investigative Function and - the approval of the Plant Mar'eger on the date specified by the Onsite Review and Investigative Function. c. Shall be submit.ed to the Commission in the form of the complete, legible copy of the entire ODCM, or i updated pages if the Commission retains a contrclied copy. If an entire copy of the ODCM is submitted, it shall be submitted as a part of or concurrent with the Annual Radioactive Emuent Release Report for the period of the report in which any chang 6 to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented. i gWrnodcmWwtostyronty12ri-5 doc 12-59 j

BYRON R: vision 1.0 i October 1997 12.6.4 Maior Chances to Liouid and Gaseous Radwaste Treatment Systems" Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous): a. Shall be reported to the Commission in the Annual Radioactive Eff'uent Release Report for the period in which the evaluation was reviewed by the Onsite Review and Investigative Function. The discussion of each change shall contain: 1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; 2) Sufficient detailed information to totally support the reason for the change without benefit of additional and supplemental information; 3) A detailed description of the equipment, componente, and processes involved and the interfaces with other plant systems. 4) An evaluation of the change which shows the predicted releases of radioactive materials in Equid and gaseous effluents that differ from those previously predict &d in the License application and amendments thereto; 5) An evaluatbn of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the License application and amendments thereto; 6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, to the actual releases for tne period prior to when the changes are to be mado; O 7) An estimate of the exposure to plant operating per'onnel as a result of the change; and 8) Documentation of the fact that the change was reviewed and found acceptable by the Onsite Review and Investigative Fanction. b. Shall become effective upon review and acceptance by the Onsite Review and investigative Function. " Licensees may choose to submit the information called for in this standard as part of the annual FSAR update. O g %mbacm\\ennexbyronty12ri s doc 12-60 >}}