Text

Revs to Ocdm,Including Rev 1.3 to Chapter 11, Radiologicial Environ Monitoring Program & Rev 1.6 to Chapter 12, Radiological Effluent Technical Stds (Rets)
	ML20198M249
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Issue date:	12/18/1997
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Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Conunission Mail Station PI-137 Washington,IX: 20555 December 18,1997 Attached is a resision to the Offsite Dose Calculation Manual, Dresden Annex, Chapteral1 and

12. Please update your manual as follows:

Remove:

9tesden Chapter 11. Resision 1.2 Dresden Chapter 12, Resision 1.5 laatit:

Dresden Chapter i1, Revision 1.3 Dresden Chapter 12, Resision 1.6 O

V

?lcase sign below irviicating your manual has been updated and that your controlled cc7y number is correct.

Name Date Return to :

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l Dresden Station Chapter 11 Change Summary O

ODCM Revision 1.3, December 1997 Page Change DescrintiQD 11 1 Updated the revision number.a.nd date.

. ll il -

Updated the List of Tables and List of Figures for t e new revision.

h 11-1 Updated the description of the Figures.

112 throug!.

Changed the sample / monitoring locations, sampling frequency, and analyses I l-8 type / frequency to reflect the Comed Uniform Radiological Environmental Monitoring Program (UREMP).

11 9,10 Updated the Figures to illustrate the sampling / monitoring locations for UREMP.

O 9

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3 i

DRE8 DEN Rsvision 1.3 l

l Deccmber 1997 Ci! APTER 11 0

DRESDEN ANNEXINDEX Revision "i.3' W

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I DRESDEN R:vtion 1.3 December 1997 j

CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE OF CONTENTS CHAPTER IIILE PAGE 11 Radiological Environmental Monitoring Program 11 1 LIST OF TABLES NUMBER IIILE PAGE 11 1 Radiological Environmen'.al Monitoring Program 11 2 LIST OF FIGURES NUMHES IIILE PAGE 11 1 Fixed Air Sampling and TLD Sites and Outer Ring TLD Locations 11 9 11 2 inner Ring TLD Locations and Near Station Water Sample Locations 11 10 O

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DRESDEN R::vi-ion 1.3 December 1997 i

CHAPTER 11

- RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i

The Redir., logical Environmental Monitoring Program for the environs around Dre: den Stat #on is given in Tabic 11 1.

Figures 11 1 and 112 show general sampling and monkoring locations.

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DRESDEN Revision 1.3 December 1997 Table 11-1 Radiological Environmental Monitoring Program i

i i

Exposure Pathway a

Sampling or Type and Frequency i

and/or Samole l

Samole or Mcn.tsind Locatiorf l

CcDecbon Frecuency l

ofAnahrsis s

e i

_____________.._}_________________________________..p________________p_________________

1. Airbome 8

l Continuous sampler l Bad!Q52 dine Cantsters.

e e operation with particulate Radiciodine and 8 a.

Indicators-Near Field l sample collecbon weekfy, l I-131 analysis biweekly on Particulates

or more frequently if a near field and control l

D-04 Collins Road. 0.9 mi W (1.4 kra N) l required by dust loading.

l sarnoles'.

D-06, Witt County Road,1.4 mi SE (2.2 km G) : and radiciodme canister l

D-07. Clay Products,2.0 mi S (3.2 kra J) l collection biweek!y.

l Particulate Sameler ;

l D-45, McKinley Woods Rd,1.5 mi ENE (2.4 km D) 8 l

l l Gross beta analysis jb. Indicators-Far Field l

l hange and gamma weekly fitter i

i ec l

D-08, Prairie Parks,4.0,1 SW (6.4 km L) l l isotopic anatysis' quarterly D-10. Goose Lake Viitage, 3.8 mi SSW (6.1 km K) i en composite filters by i

l D-13, Minocka,4.5 mi N (7.2 km A) '

l location on near fielo and j

D-14 Channahon,3_5 mi NE (5.6 km C) I e controlsamples '

i t

i I

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lc. Controls l

l I

1 4

D-12. Lisbon,10.0 mi NW (16.0 km O) :

1 I

I I

I l d. Spectaf l

l e

e i

l i

I l

D-01, Onsite Station 1,0.6 mi NW (1.0 km O) l l

l D-02, Onsite Station 2,0.3 mi NE (0.5 km C) l l

l D-03 Onsite Station 3,0.4 mi S (0 6 km J) l l

t 9

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t i

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11-2 O

O O

December 1997 Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program s

a a

Exposure Pathway e

i Sampiing or Type and Frequency and/or Samole l Sarpole or Monitorino location

l CO';ech Frecuency l of Analysts._

1 1

I l______---

2.

Direct Radiation e a. Indicators-Inner Ring 8 Quarterty a Gamma dose on each TLD l

D-101-1, 1.0 mi N (1.6 km A) quarterty.

l D-101-2, 1.0 mi N (1.6 km A) 8 l

D-102-1, 1.3 mi NNE (2.1 km B) a

.l D-102-2, 1.3 mi NNE (2.1 km B) l l

t D-103-1, 1.2 mi NE (1.9 km C) a l

D-103-2, 1.2 mi NE (1.9 km C) l l

0-104-1, 1.5 mi ENE (2.4 km D) i l

D-104-2, 1.5 mi ENE (2.4 km D) l l

8 D-10%1, 1.4 mi E (2.2 km E) 8 l

D-105-2, 1.4 mi E (2.2 km E) l l

D-106-1, 0.9 mi ESE (1.4 km F) l l

D-106-2, 0.9 mi ESE (1.4 km F) i i

l D-107-1, t.3 mi SE (2.1 km G) l l

i D-107-2, 1.3 mi SE (2.1 km G) a l

D-108-1, 1.9 mi SSE (3.0 km H) l 8

D-108-2, 1.9 mi SSE (3.0 km H) i l

D-109-1, 0.8 mi S (1.3 km J) l l

l D-109-2, 0.8 mi S (1.3 km J) l l

D-110-3, 0.8 mi SSW (1.3 km K) e l

D-110-4, 0.8 eni SSW (1.3 km K) l l

D-111-1, DE mi SW (1.0 km L) e l

D-111-2, 0.6 mi SW (1.0 km L) l l

0-112a-1, 0.8 mi WSW (1.3 km M) i l

D-112a-2, 0.8 mi WSW (1.3 km M) l l

D-113-1, 0.9 mi W (1.4 km N) 8 8

l D-113-2, 0.9 mi W (1.4 km N)

D-114-1, 1.0 mi WNW (1.6 km P) l D-114-2, 1.0 mi WNW (1.6 km P) a l

D-t 15-1, 0.8 mi NW (1.3 km Q) l D-115-2, 0.8 mi NW (1.3 km Q) i

.i l

D-116-1, 1.0 mi NNW (1.6 km R) l l

8 D-116-2, 1.0 mi NNW (1.6 km R) l 11-3 Mr"

DRESDEN Revision 1.3 December 1997 Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program Exposure Pathway 8

8 Sampling or Type and Frequency and/or Samole Samele or Monitorina Location

Collection Frecuency cfAnaNsis

____________.___y______.__________________________l a

r______-

-______r_________________.

2. Direct Radiatinn 8 b. Irr.R.oiw@er Ring a

8 (Cont'd) l D-201-1, 4.5 mi N (7 2 km A) l l

l D-201-2, 4.5 mi N (7.2 km A) l l

D-202-1, 5.0 mi NNE (8.0 km B) a l

D-202-2, o.O mi NNE (8.0 km si l

l D-203-1, 4.5 mi NE (7.2 km C) e i

l D-203-2, 4.5 mi NE (7.2 km C) l l

8 D-204-1, 5.0 mi ENE (8.0 km D) e i

l D-204-2, 5.0 mi ENE (8.0 km D) l l

8-D-205-1, 4.2 mi E (6.7 km E) 8 8

D-205-2, 4.2 mi E (6.7 km E) l l

l D-206-1, 3.5 mi ESE (5.6 km F) l l

D-206-2, 3.5 mi ESE (5.6 km F) e i

l l

D-207-1, 4.5 mi SE (7.2 km G) l l

e D-207-2, 4.5 mi SE (7.2 km G) a l

D-208-1, 5.0 mi SSE (8 0 km H) l l

8 D-208-2, 5.0 mi SSE (8.0 km H) 8 l

D-209-1, 5.0 mi S (8.0 km J) l l

l D-209-2, 5.0 mi S (8.0 km J) l l

D-210-1, 4.8 mi SSW (7.7 km K) a l

D-21G-2, 4.8 mi SSW (7.7 km K) l l

e D-211-1, 5.0 mi SW (8.0 km L) e l

D-211-2, 5.0 mi SW (8.0 km L) l l

8 D-212-3, 6.0 mi WSW (9.7 km M) e s

l D-212-4, 6.0 mi WSW (9.7 km M) l l

l 8

D-213-1, 4.5 mi W (7.2 km N) 8 8

D-213-2, 4.5 mi W (7.2 km N) l l

l D-214-1, 4.5 mi WNW (7.2 km P) l l

e D-214-2, 4.5 mi WNW (7.2 km P) a l

l D-215-1, 5.1 mi NW (8.2 km Q) l I

D-215-2, 5.1 mi NW (8.2 km Q) a l

D-216-1, 4.8 mi NNW (7.7 km R) l l

l l

D-216-2, 4.8 mi NNW (7.7 km R) l l

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DEN Revis December 1997 Table 11-1 (Cont'd)

Radiological Environmental Reonitoring Program E

5 i

Exposure pathway e

i Sampring or i

Type and Frequency and/or Samole l

Samole or Mc6ituiino Locaton' l

Cdlechon Freauency l

q[f s hrsas

_________p____________________________._____p____-

2.. Direct Radiation 8 c. Other 8

8 I

I I

(Cont'd) e i

Indicatois 8

8 1

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One at each of the airbome locaton given in part 1.a l l

s and 1.b.

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8 d. Controls t

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Ont'at each airborne controllocation given in part l

l 1.c.

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11-5

DRESDEN Revision 1.3 December 1997 Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program 4

4 Exposure Pathway i

4 4

Sampling or i

e Type and Frequency and/or Samole l-Samole or Monitorino location

l Conectron Frecuency l

of Analysis 4

t I

_______________p_________________________________p________________p_________________

3. Waterbome 8

8 8

4 I

a..

Ground /Well la. Indicators l Quarterly l Gamma isotopic' and tritium i

a analysisquarterfy e

l D-23. Thorsen Well,0.7 mi S (1.1 km J) l l

D-35. Dresden Lock & Dam. 0.5 mi NW(0 8 km O) e i

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9 I

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I b.

Dr'nkino Water l There is no drinking water pathway within 6.2 mi l

l l

downstream of station.

l 8

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e c.

Surface Water e a.

Indicator i Weekly grab sample i Gros *, beta and gamma l

l isotopic analysis on D-51, Dresden Lock & Dam. 0.5 mi NW (0.8 km Q) i e month!y composite, tritium l

l l analysis on quarterfy l

l l composite.

i i

d.

Control la. Controi l Weekly grab sample l Gross beta and gamma i

e isotopicanalysis on i

l D-52, DesPlaines River,0.9 mi ESE (1.4 km F)

' monthly composite; tr tium i

e i analysis on quarterty l

l l composite.

I I

I e.

Sediments

! a Indicatot l Semiannually l Gamma isotopic analysis' l

' semianniJally.

D-27. Dresden Lock & Dam,0.5 mi NW (0.8 km O) i i

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December 1997 Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program I

i i

i Expcsure Pathway and/or Sample l

Samole or Monitoring Location

l Collectron Frecuency l

of Anahis '

l Sampling or Type and Frequency 1

I I

_______________p_________________________________p________________p_________________.

4.

Inoestion s

8 e

I I

I 8

a. Milk

,a Indicators 8

l Biweeldy: May through

' Gamma isotopic

and 1-131 i October, Monthly:

i analysis"' on each sample.

e' There are no dairies within 6.2 rnles of the station.

l November through April l

1 i

I lb. Control l

l 9

I t

l D-25, Vince Biros Farm.11.5 mi SW (18.5 km L) l l

i la. Indicator b.

Eish' l

' Gamma isotopic analysis' D-28, Dresden Pool of lilinois Rrver, i Two times annually i on edible portkre of each s

l 0.5 rni NW (0.8 km Q) l l

lb. Control l

l 1

I I

l D-40. DesP!aines River upstream of discharge.

l l

l 0.9 mi E (1.4 km E) l la. Indk:ators l

l c.

Food Products e i

e l

Two samples from each of the four major quadrants l l

i within 6.2 miles of the station.

8 Gamma isotopic analysis' l

l Annually l each sample.

l Sample locations for food products may vary based l 8,

on availability and therefate are not required to be e

i i

l identified here but shall be taken, if available.

l l

1 I

I lb. Controls l

l t

i 1

l Two samples withir' 9.3 to 18.6 miles of the station. l l

11-7 m

DRESDEN Revision 1.3 Cwwmtsi S997 Table 11-1 (Cor t'd)

Radiological Environmental Monitoring Program U~- field samples are analyzed when near field results are inconsistent vnti prevous measurements and radioactivity is confirmed as havin orige in airbome emuents released from Ae station, or at the discretion of the Radiation Protechon Director.

Airbome particulate sample filters shall be anayred for gross beta radMvi*y 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay if gross beta activity in air particulate samples is greater than 10 times the yearty mean of control samples, gamma isotopic analysis shall be pe;1ormed on the individual samples.

Gamma isotopic analysis means the identification and quantification of gamma emitting radios urdides that may be attributable to the emuents from the station.

l-131 analysis means the analytical separation and counting procedure are speofic for this radionuclide.

The fish monitoring locations are not identified exactly on the map. The points D-28 and D-46, represent the general area where the samples are taken.

Distances provided for sampling / monitor locations are approximate.

7-The analysis requirements listed are for the REMP-required samples only. The special samples require only quarterfy gamma isotopic analyses on the composite filters.

These samp!ing locations do not constitute REMP samples, but are special samples required per Section 11.5.1.10 of the UFSAR. They may be discor.tinued pending revision of the aforementioned see'aon O

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DRESDEN Rrision 1.3 Decorrber 1997 O

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Air sampling t.ocation PDGD AIR SAMPUNG AND11.D SNES AND a T1.D t.ocation CUTER RING TLDIJTATENS 11-9

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Dresden Station i

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- Chapter 12 Change Summary.

- ODCM Revision 1.6, December 1997-'

l p.., -

ch..

Dancrintinn l

12 1 Updated revision number in file designator.

i 1 2 -11' Updated revision number.

l I

12 lil '

Updated page numbers in Table of Contents.

- t 12-iv '

Updated page numbers and Section titles in Table of Contents.

12 v -

Updated page numbers in List of Tables.

-12 27,28-

.Added definition of LLD, including equation. Included alternate LLD

- methodology. Made table title consistent with first page of table.-

12-40,41 Added definition of LLD, including equation included attemate LLD methodology.

12 35,37 Corrected typographical errors in the Technical Specifications references.

-i 12-45 through Revised Section 12.5, Radiological Environmental Monitoring Program, to 12-60 reflect implementation of the Comed Uniform REMP. New sampling / monitoring locations and frequencies and the new analyses types and frequencies correspond with the standardized program.

12-45.

Changed the reference to ODCM section numbers to address the new section numbers.

12-55 The LLD for tritium was changed to reflect the LLD value specified in NUREG-1301.

'12-62 Changed the reference to ODCM section numbers to address the new section numbers.

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Revision 1.6 Decernber 1997 CHAPTER 12.0 SPECIAL NOTE

- The requirements of the Technical Specifications shall take precedence over this chapter, should any differences occur.

The transfer of the Radicogical Efiluent Technical Specificatens (RETS) to the ODCM for Unit 1 has been approved by the Nuclear Regulatory Commission in Amendment 39.

The transfer of the Radiological Emuent Technical Specifications (RETS) to the ODCM for Units 2 and 3 has been approved by the Nuclear Regulatory Commission in Amendments 150 and 145.

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DRESDEN R: vision 1.6 December 1997 DRESDEN ANNEX INDEX O

CHAPTER 12 Revision 1.6 9

9 12-ii O

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DRESDEN Revision 1.6 I

December 1997 CHAPTER 12 O-RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS V

(RETS)

TABLE OF CONTENTS PAGE 12.1 DEFINITIONS 12 1 12.2 INSTRUMENTATION 12 5 A. Radioactive Liquid Effluent Monitoring Instrumentation 12 5 1.

Radioactive Liquid Effluent Monitoring Instrumentation Operability 12 5

2. Radioactive Liquid Emuent Monitoring Instrumentation Surveillance

.12-5 B. Radioactive Gaseous Emuent Monito.4ng Instrumentation 12-5 1.

Radioactive Geseous Emuen' Monitoring instrumentation Operabihty 12 5 2.

Radioactive Gaseous Effhat Monitoring Instrumentation Surveillance 12-6 C. Liquid and Gaseous Emuents 8%trumer ation Bases 12 19 12.3 LIQUID EFFLUENTS 12 20 A. Liquid Emuents Limits and Reporting Operability 12-20 1.

Concentration in Unrestricted Areas 12 20 2.

Dose from Liould Emuents 12 20 -

3.

Dose Projoctons 12 21 4.

Liquid Radioactive Waste Treatment System 12-22 5.

System Operability and Plant Operations 12 22 B Liquid Emuents Surveillance 12 22 1.

Concentration in Unrestricted Areas 12-22 1

Dose from Liquid Effluents 12 23 3.

Dose Projections 12-23 C. Liquid Emuents Bases 12 30 1.

Concentration 12 30 2.

Dose 12 30 3.

Liquid Waste Treatment 12 30 4.

Mechanical Vacuum Pump 12-31 12.4 G.A',EOUS EFFLUENTS 12-32 A. Gaseous Emuents Limits and Reporting Operability 11 32 1.

Dose Rate 12-32 2.

Noble Gas Dose 12-32 3.

lodine-131, lodine-133, Tritium and Particulate Dose 12 33 4.

Off-Gas Treatment 12-34 5.

Main Condenser Air Ejector 12-35 6.

System Operabikty and Plant Operations 12-35 B. Gaseous Effluents Surn!!!ance 12 36 1.

Dose Rate 12-36 2.

Noble Gas Dose 12-36 3.

lodine-131, lodine-133, Tritium and Particulate Dose 12-36 4.

Off-Ges Treatment 12-36 5.

Noble Gases at the Main Condenser Air Ejector 12-37 u

12-iii

DRESDEN Revision 1.6 December 1997 CHAPTER 12 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS (RETS)

TABLE OF CONTENTS CONTINUED PAGE 12.4 GASEOUS EFFLUENTS (Cont'd) 12-43 C.

Gaseous Emuents Bases 12-43 1.

Gaseous Ef?aents, Dose 2.

Dose, Noble Gases 12 43 3.

Dose, Radioiodines, Radioactive Materialin Particulate Form and Radionuclides Other than Noble Gases 12-44 4.

Gaseous Wasta Treatment 12-44 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12-45 1.

Monitoring Prograrn 12-45 2.

Land Use Census 12 59 3.

Intertaboratory Comparison Program 12-60 12.6 RECORDKEEPING AND REPORTING 12-61 l

1.

Station Operating Records 12 61 2.

Reports 12-61 1.

Radioactive Effluent Release Report 12-61 2.

Annual Radiological Environmental Operating Report 12-61 3.

Non-Routine Environmental Report 12-62 3.

Offsite Dose Calculation Manual (ODCM) 12-63 4.

Major Changes to Radioactive Waste Treatment Systems (Liquid and Gaseous) 12-64 O

12-iv

DRESDEN Revision 1.6 December 1997 O'

CHAPTER 12 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS (RETS)

LIST OF TABLES NUMBER TITLE PAGE 12.1 1 Surveillance Frequency Notation 12 3 12.1 2 Operational Modes 12-4 12.2 1 Radioactive Liquid Effluent Monitoring instrumentation 12 7 12.2 2 Radioactive Liquid Effluent Monitoring instrumentation Surveillance Requirements 12 9 12.2 3 Radioactive Gaseous Effluent Monitoring instrumentation 12-12 12.2 4 Radioactive Gaseous Eif!uent Monitoring instrumentation Surveillance Requirements 12 16 12.3-1 Allowable Concentration of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Waste 12 24

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12.3-2 Radioactive Liquid Waste Sampling and Analysis Program 12 25 12.4-1 Radioactive Gaseous Waste Sampling and Analysis Program 12 38 12.5-1 Radiological Environmental Monitorir,g Program 12 48 12.5-2 Reporting Levels for Radioactiv"y Concentrations in Environmental Samples 12-54 Reporting Levels 12.5-3 Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection 12-55 12 v

DRE3 DEN Revision 1.6

+

December 1997 12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS m

12.1 DEFINITIONS 1.

Dose Eauivalent 1 131 - That concentration of I-131 (microcurie / gram) whidi alone would produce the same thyroid dose as the quantity and isotopic mixture of l-131,1 132,1-133, 1134, and 1135 actually present. The thyroid Mse conversion factors used for this calculation shall be those listed in Table 111 of TID 14844," Calculation of Distance Factors for Power and Test Reactor Sites",

2.

Freauenev Notation Table 12.1 1 provides the d'afinitions of various frequencies for which surveillances, sampling, etc., are performed unless defined otherwise. Refer to Technical Specification Table 1-1.

3.

jmmediate Immediate means that the required action will be initiated as soon as practicable considering the safe operation of the unit and the importance of the rtsquired action.

4.

Instrument Calibration An instrument calibration means the adjustment of an instrument signal output so that it corresponds. within acceptable range and accuracy, to a known value(s) of the parameter which the instrument monitors. Calibration shall encompass the entire instrument, including actuation, alarm, or trip.

5.

Instrument Check - An instrument check is qualiiative determination of acceptable operability by observation of instrument behavior during operation. This determination shallinclude, where possible, comparison of the instrument with other independent gh instruments measuring the same variable.

V 6.

Instrument Functional Test - An instrument functional test means the injection of a simulated signal into the instrument primary sensor to verify the proper instrument response alarm and/or initiating action.

7.

Member of the Public any individual except when that individualis receiving an occupational dose.

8.

Mode - Reactor modes are desenbed in Table 12.12 (per Technical Specification Table 1 -2).

l l

9.

Occucational Dose-The dose received by an individualin the course of employment in which the individuars assigned duties involve exposure to radiation and/or to radioactive material from licensed and unlicensed sources of radiation, whether in I

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 medicel research programs, or as a member of the public.

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DRESDEN Revbion 1.6

.l December 1997 12.1 DEFINITIONS ', Cont'd) j 10.

The offsite Dose Calculation Manual (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs described in Section 12.5 and (2) descriptions of the information that should be included in the Annual Radiological Enviror mental Operating and Radioactive Effluent Release Reports required by Sections 12.6.2.1 and 12.6.2.2.

11.

Operable. A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, co; ling or seal water, lubrication or othar auxiliary equipment that are required for the system, subsystem, train, component or device to perform its specified safety function (s) are also capable of perfomiing their related support function (s).

12.

The Process Control Proaram (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packsping of sobd radioactive wastes based on demonstrated processing of actual or simulted wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20,61, and 71, State regulations, burial ground requirements, and other requirements goveming the disposal of solid radioactive waste.

13.

Rated Thermal Power - Rated thermal power shall be a total reactor core heat transfer rate to the reactor coolant of 2527 thermal megawatts.

14.

Reactor Power Ooeration - Reactor power operation is any operation witn the mode switch in the *Startup/ Hot Standby" or 'Run" position with the reactor critical and above 1% rated thermal power.

15.

Source Check The qualitative assessment of Channel response when the Channel sensor is exposed to a radioactive source.

16.

Definitions Related to Estimating Dose to the Public Using the ODCM Comouter Proaram:

1.

Actual-Refers to using known release data to project the dose to the public for the previous month. These data are stored in the database and used to demonstrate compliance with the reporting requirements of Chapter 12.

2.

Projected - Refers to using known release data from the previous month or estimated release data to forecast a future dose to the public. These data are RQIincorporated into tne database.

O INorddatsbocrnWn12r14 doc 12-2

DRESDEN Revision 1.6 December 1997 -

TABLE 12.1 1 SURVElLLANCE FREQUENCY NOTATION NOTATION FREQUENCY

S (Shiftly)

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D (Daily)'

Atleast once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months T

At least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months -

W(Wookly)

At least once per 7 days M (Monthly)

Atleast once per 31 days Q (Quarterfy)

At least once per 92 days SA (Semiannually)

At least once per 184 days A (Annually)

At least once per 366 days E (Sesquiannually)

At least once per 18 months (550 days)

S/U (Startup)

Prior to each reactor startup NA (Not Applicable)

Not applicable

Each surveillance requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. The bases to Technical

- Specifications 4.0.8 provides clarification to this statement. These definitions do not apply to the Radiological Environmental Monitoring Program (Section 12.5).

d

./

3

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hAmonidatawdomWn12r14. doc j-12-3 E

DRESDEN Revision 1.6 December 1997 TABLE 12.12 O

OPERATIONAL MODES MODE SWITCH AVERAGE REACTOR 0

MODE POSITION _

OOOLANT TEMPERATURE

1. POWEF. OPERATION Run Any temperature

2. STARTUP Startup/ Hot Standby Any temperature

3. HOT SHUTDOWN Shutdown'**)

> 212*F

4. COLD SHUTDOWN Shutdown'***) '

5 212*F

5. REFUELING

Shuidown or ReNel'"'

5140*F TABLE NOTATIONS d') The reactor mode switch may be placed in the Run, Startup/ Hot Standby, or Refuel asition to test the switch interlock functions provided the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified individual.

) The reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per Technical Specification 3.10.l.

'*8 Fuelin the reactor vessel with one or more vessel head closure bon less than fully tensioned or with the head removed.

See Technical Specification Special Test Exceptions 3.12.A and 3.12.B.

) The reactor trode switch may be placed in the Refuel position while a single control rod is being moved provided the one-rod-out interlock is OPERABLE.

When there is no fuel in the reauor vessel, the reactor is considered not to be in any OPERATIONAL MODE. The raactor mode switch may then be in any position or may be inoperable.

O h worddatabden 'dn'1t14 doc 12-4

DRESDEN Revision 1.6 l-

~

i December 1997 12.2 INSTRUMENTATION A. Radmactive t_lauid Eff'nent Monitorino Instrumentation

1. Rad-tive Liouid Effluent Monitorino Instrumentation Ooerability 1.

The emuent rnonitoring instrumentation shown in Table 12.0-1 shall be operable with alarm t-ip setpoints set to insure that the limits of Section 12.3.A are not exceeded. The abrm setpoints shall be determined in accordance with the -

ODCM.

2.

With a radicactive liquid effluent monitering instrumeat alarm / trip setpoint less conserva'.ive than required, without delay suspend the release of radioactive -

liquid effluents monitored by the affected instrument, or declare the instrument inoperable, or change the setpoint so it is acceptably conservative.

3.

With one or more radioactive liquid effluent monitoring instruments inoperable, take the action showr in Table 12.2-1. Retum the instrument to operable status within 30 days and, if unsuccessful, explain in the next Radioactive Emuent Relea:e Report why the inoperabiuty was not corrected in a timely manner. This is in lieu of an LER.-

e in the event operability requirements and associated action requirements cannot be satisfied because of circumstances in excess of those addressed in the specifications, provide a 30-day written report to the NRC and no changes are required in the operational corrjition of the plant, and this does not prevent the plant from entry into any opert,tional mode.

2. Radioactive Liouid EMluent Monitorino Instmmentation Surveillance 1.

Each radioactive liquid effluent monitoring instrument shown in Table 12.2-2 shall be demonstrated operable by performance of the given source check, instrument check, calibration, and functional test operations at the frequencies shewn in l

Tabie 12.2-2, B. Radioactive Gaseous Effluent Monitorino Instrumentation

1. Radioactive Gaseous Effluent Mocitorino instrumentation Ooerability 1.

The effluent monitoring instrumentation shown in Table 12.2-3 shall be operable with alarm / trip setpoints set to ensure that the limits of Section 12.4.A are not exceeded. The alarm / trip setpoints shall be determined in accordance with the ODCM.

2.

With a radioactive gayaous effluent monitoring instruments alarm /t-ip set point less conservative than required, without delay suspend the release of radioactive gaseous effluents mon: tor 6d by the affected instrument, or declare the ins'rument inoperable, or change the setpoint so it is acceptably conservative.

A h%on$d/abocmWn12r14 doc 12-5

Di<ESDEN Revision 1.6 December 1997 '

12.2.B.1 Bad 10 active Gaseous Effluent Monitoring Instrumentation Ooerability (Cont'd) 3.

With one or more radioactive gaseous effluent monitoring instruments inoperable, take the action shown in Table 12.2-3. Return the instrument to operable status W

within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner. This is in lieu of an LER.

4.

The Unit 2/3 plant chimney gas sampling system may be out of service for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months for the purpose of servicing the high range noble gas monitor as long as the following conditions are satisfied:

1.

Both units are at steady state conditions with the recombiners and charcoal absorbers in service for the operating unit (s).

2. The dose rate in unrestricted areas must be shown by calculation to be less than the limits of 12.4.A assuming the charcoal absorbers are bypassed on both units.

3.

Both offgas monitors on Unit 2 and Unit 3 must be operational and the raonitor reading correlated to the chimney release rate based on the conservative assumption of both units' charcoal absorbers being bypassed.

4.

If the provisions of 12.4.A.1.1c12.4A1.2, or 12.4.A.1.3 cannot be met, an orderly load reduction of the unit (s) shall be initiated immediately.

5.

In the event operability requirements and associated action requirements cannot be satisfied because of circumstances in excess of those addressed in this fection, crovide a 30-day written report to the NRC and no changes are required in the operational condition of the plant, and thb does not prevent tne plant from entry into any operation mode.

j A

2. Radioactive Gaseous EffluentMonitoring Instrumentation SurgijilaDCC Each radioactive gaseous radiation monitoring instrument in Table 12.2-4 shall be demonstrated operatele by performance of the given source check, instrument check, calibration, and functional test operations at the frequency shown in Table 12.2-4.

O h"worddataWmWn12ri 6 doc 12 4

DRESDEN R: vision 1.6 December 1997 TASLE 12.21 RADIOACilVE LIQUID EFFLUENT MONITORING INSTRUMENTATION UNIT 1 Minimum Total Channels No. of r

Instrument Operable Channe's Action Discharge Canal 1

1 12 Sampler

ACTIONS

. ACTION 12 -

Operability is verified prior to performing and once a day during planned discharge.

When Instrument is unavailable ar.d associated actions cannot be performed, then discharget may not be made.

O O

lthwicmwn12r14 doc 12-7

i DRESDEN RIvision 1.6

(

December 1997 TA'.,LE 12.2-1 RADnOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION UNITS 2 & 3 Minimum Total Channels No. of Instrument Operable Channels Action 1.

Service Water Effluent i

1 10 GTss Activity Monitor 2.

Liquid Radwaste Effluent 1

1 11 Gross Activity Monitor ACTIONS ACTION 10 -

With less than the minimum number of operable channels, releases via this pathway may continue, provided that at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months grab samples are collected and analyzed for beta or gamma activity at an LLD of less than or equal to 10 uCl/ml.

(The grab sample should normally be taken at the Service Water Monitor or at a location which would be representative of the Service Water which is monitored.)

ACTION 11 -

With less than a minimum number of operable channels, effluent releases via this palhway may continue, provided that pnot to initiating a release, at ' east 2 independent samples are anatyzed, and at least 2 members of the facility staff independently verify the release calculation and discharge valving. Otherwise, suspend release of radioactive effluent via this pathway.

O1 1

Ithtabdcmwn12rt 6. doc j

12-8

DRESDEN R:vi-ion 1.6 Decemrcr 1997 TABLE i 2-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS UNIT 1 Functional Calibration *')

Instrument Source instrt ment Test Checkm Check Discharge Canal Sampler

8'

When instrument is unavailable and associated actions cannot be performed, then discharges may not be made.

O h mbdcrnun12rt-6 doc 12-9

ORESDEN Revision 1.6 Dec0mber 1997 TABLE 12.2 2 i RADIOACTIVE LIQUID F. ' FLUENT MONITORING INSTRUMENTATION SURVr. !U.ANCE REQUIREMENTS UNITS 2 & 3 Functional Calibration (**

Instrument Source instrument Test"

Check" Check 1.

Liquid Radwasta Effluent Gross O("

E(*

D E*

Activity Monitor 2.

Service Water Effluent Gross Q'O EW D

E Activity Monitor O

O h Wata\\odemWn12r14 doc 12 10 o

DRESDEN R;vtion 1.6 December 1997 TABLE 12.2-2 (Cont'd) k RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIONS 2

'*)

The instrument Functional Test shall also demonstrate that control room alarm atenunciation occurs, if any of the following condrbons exist, where applicable.

1.

Instrument indicated levels above the alarm setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

7 4.

nstrument controls not set in OFERATE mode.

Calibration shallinclude performance of a functional test.

"I Cahbration shallinclude performance of a source check.

")

Source check shall consist of observing instrument response dunng a discharge.

Functional tests may be performed by using trip check and test circuitry associated with the monitor chassis.

m Functional tests, calibrations, and instrument checks ara not required when these instruments are not

,'x required to be opetable or are tripped. Calibration is not required to be performed more than once every 18 months.

Operabihty is verified prior to performing discharge and once a day during planned discharge.

Iv hkotidatabdcmWn12r16 doc 12-11

DRESDEN Rsvision 1.6 December 1997 TABLE 12.2-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION UNIT 1 Minimum Total Applicable Channels No. of Operatior.at instrument Operable Channels Modes Action 1.

Main Chimney SPING Noble Gas 1

3 28 Monitors 2.

Main Ctamney Particulate 1

1 27 Samplers 3.

Main Chimney lodine Samplers 1

1 27

At all tirnes.

O 1

l h%crddatabdcmWn12r14.dec l

12-12

DRESDEN R vision 1.6 L

December 1997 TABLE 12.2-3 i

' U(N RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION UNITS 2 & 3 Minimum Total Appleable Channels No. of Operational Instrumen' Operable Channels Modes Action 1.

Main Chimney Noble Gas /SPING/

1 3

20 GE Low Range Activity Monitor i4 2.

Main Chimney SPING Noble Gas 1

1 26 Monitors Mid, Hi Range 3.

Main Chimney lodine Sampler 1

1 22 4.

Main Chimney Particulate Sampler 1

1 22 5.

Main Chimney Flow Rate Monitor 1

1 21 6.

Main Chimney Sampler Flow Rate 1

1 21 Monitor 7.

Reactor Building Vent Exhaust See Technical Specifications Section 3/4.2 Duct Radiation Monitor 7

i 8.

Reactor Building Vent SPING 1

1 25 Noble Gas Monitor Low, Md.

High Range 9.

Reactor BuiloIng Vent Flow 1

1 21 Rate Monitor

10. Reactor Building Vent Sampler 1

1 21 Flow Rate Monitor

11. Reactor Building Vent lodine 1

1 22 Sampler t

12. Reactor Building Vent 1

1 22 l

Particulate Samrler

13. Offgas Radiation Activity 1

2 29 Monitor -

At all times.

- During Steam Jet Air Ejector operation.

V tOnorddatabdcmWn12rt 6 doc 12-13

DRESDEN Revision 1.6 December 1997 TABLE 12.2-3 (Cont'd)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION i

ACTIONS AND TABLE NOTATIONS ACTION 20-With less tilan the minimum channels operable, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and analyzed for noble gas within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

(The SPING has one low range noble gas channel, Channel 5, while the GE Low Range Activity Monitor has two low-range noble gas channels.

The grab samples are usually taken at either the SPING, if it is aligned in the flow path, or at the GE Low Range Activity Monitor Skid.)

ACTION 21 -

Wth the number of operable channels less titan the minimum required, effluent releases via this pathway may continue provided that the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

(The Main Chimney Flow Rate Monitor and the Reactor Building Vent Flow Rate Monitor are used for flow through the ChimneyNent. Channel 10 of the SPING gives the ChimneyNent ficw rate. This value can also be obtained from Point History.

The Main Chimney Sampler Flow Rate Monitor and the Reactor Building Vent Sampler Flow Rate Monitor are used for the flow through the SPING or backup sampler. Channel 15 of the SPING gives the sampler flow rate for the SPING. The U2, U3 and GE Backup systems each have a flow rate monitor.)

ACTION 22 -

Wth less than the minimum channels operable, effluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling equipment, as required in Table 12.4-1.

(The normai sampler for 2/3 Main Chimney is the 2/3 Main Chimney SPING while for the 2/3 Reactor Building Vent it is the 2/3 Reactor Building Vent SPING.

If the 2/3 Chimney SPING is not operational, the normal backup is the GE Low Range Activity Skid. This skid collects an lodine ar'd Particulate sample.

If the 2/3 Reactor Building Vent SPING is not operational, the normal backups are the U2 and U3 Reactor Building Vent Samplers. The sampler for each vent collects an lodine and Particulate sample.

If the normal backup sampler is not available, use of an attemate sampler should be used as long as it pulls from tr ' same process stream.)

ACTION 25 -

Wth less than the minimum channels operable, effluent releases via this pathway may continue provided ti. ' the minimum number of operable channels for the Reactor Building Vent Exhaust Duct Radiation Monitor are operable.

(These are Channels 5 (low range),7 (mid range) and 9 (high-range) on the 2/3 Reactor Building Vent SPING.)

ACTION 26-Wth less than the minimum channeN operable, effluent releases via this pathway may continue wided the low range monitor is operable and on scale. Restore the ItbronMatabdcmWn12f16 doc l

12-14

-.. ~ _. _.. _ _

.CRESDEN Revhion 1.6) l December 1997 inoperable aquipment to operable status within 21 ' days, or prepare and submit a

'i=

report to the Commission pursuant in Technical Spec #fication 6.9.B within the next 30 days outlining the plans, actions taken and procedures to be used to provide for the

(

loss of sampimg capability of the system.

- (These are Channels 7 (mid-range) and 9 (high-range) on the 2/3 Main Chimney.

SPING.)..

t ACTION 27 The main chimney SPING monitor may be out-of-service for calibration and mai.itenance provided that particulate and iodine samples are taken and analyzed.

The samples shall be collected using altemate filter holders and pumps connected to the main chimney sample stream.

4

. (The normal lodine and Particulate sampler for D1 Main Chimney is the D1 Main Chimney SPING. If the D1 Chimney SPING is not operatonal, the normal backup is

- a sample pump attached to the sample stream from the Main Chimney, The sample pump collects an lodine and Farticulate sample.)

ACTION 28 -

. With less than the minimum channels operable, effluent releases via this pathway may continue provided daily noble gas samples are taken and analyzed daily. Restore the ~

inoperable equipment to operrkle status within 30 days. : If service can not be retumed, document squipment availebility difficulties within the Radioactive Effluent Release Report for the period including actions taken in response to the equipment and procedures used to provide for the loss of sampling capability of the system.

-(The normal noble gas monitors are Channels 5 (low-range), 7 (mid-range) ar d 9 (high-mnge) on the D1 Chimney SPING. Grab samples can either be taken off of D.

the SPING or taps on the piping for the sample stream.).

i ACTION 29 -

Witn less than the minimum channels operable, gases from the main condenser off l

gas system may be released to the environment for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months provided the off gas system is not bypassed and at least one chimney monitor is operable; otherwise, be in HOT STANDBY in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4

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h.mudemWn12r14 doc 12-15 q

9

-a,

DRESDEN R:; vision 1.6 Dee:n ber 1997 TABLE 12.2-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS UNIT 1 Applicable Functional Calibration *)

instrument Source Operational Instrument Test**)

Check Check Modes 1.

Main Chimney SPING Q

E D

M Noble Gas Monitor Low Range

At all times.

O O

h Watak dcmkm12ri 6 coe 12-16

1 DRESDEN Revision 1.6 December 1997

- TABLE 12.2 f]

RADIOACTIVE GASEOUS EFF, 'NT MONITORING G

INSTRUMENTATION SURVEILLANCE REQUIREMENTS UNITS 2 & 3 Applicable Functional Calibration ("

Instrument Source Operational instrurnent Test'"

Check "'

Check Modes 1.

Main Chimnay Noble Q

E D

M Gas Activity Monitor 9

2.

Main Chimney SPING Q

E D

M Noble Gas Monitor Lo, Mixi, High Range 3.

Main Chimney NA NA D"'

NA Particulate and lodine Sampler 4.

Main Chimney Flow Q

E D

NA Rate Monitor 5.

Main Chimney Sampler Q'*

E D

NA Flow Rate Monitor

(

Reactor Bldg Vent Sw Technical Specifications Secton 3/4.2 Exhaust Duct 4

Radiation Monitor 7.

Rnactor Bldg Vent O

E D

M SPING Noble Gas-Monitor Lo, Mid, High Range 8.

Reactor Bldg Vent Q

E D

NA Flow Rate Monitor 9.

Reactor Bldg Sampler Q(*

E D

NA Flow Rate Monitor 10.

Reactor Bldg Vent NA NA D"'

NA Particulate and lodine Sampler 11.

Off Gas Radiation Q

E D

E Actnnty Monitor

At all times.

" During Steam Jet Air Ejector operation.

f^.

A.

h.hcrdcataVxicmV!n12ri-6. doc 12-17

DRESDEN Rsvision 1.6 December 1997 I

TABLE 12.2-4 (Conrd)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIONS The Instrument Functional Test shall also demonstrate that control room alarm annunciation occurs, if any of the following conditions exist, where applicable.

1.

Instrument indicates levels above the alarm setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

4.

Instrument controls not set in OPERATE mode.

Calibration shallinclude performance of a functional test.

Instrument check to verify operability of sampler, that the sampler is in place and functioning properly.

Functional tet ' shall be performed on local switches providing low flow alarm.

Functional tests, calibrations, and instrument checks are not required when these instruments are not required to be operable or are tripped. Calibration is not required to be perforrned more than once every 18 months.

O hMorddatawcmWn12ri 6 doc 12-18 l

DRESDEN R; vision 1.6 Dec:mber 1997 12.2.C Liauid And Gaseous Effluents Instrumentation Bases N

1.

The radioactive liquid and gaseous effluent instrumentation is provided to mon ~ tor the release of radioactive materials in liquid and gaseous effluents during

e releases. The alarm setpoints for the instruments arc provided to ensure that the alarms wiil occur prior to exceeding the limits of RETS.

s

)

O v

ttwatabocmW112r14tx 12-19

DRESDEN R:; vision 1.6 December 1997 12.3 LIQUID EFFLUff{LS 12.3.A Ljpuid Effluents Lim)ts and Reoortina Ooerability 1.

Concentration in Unrestricted Areas The concentration of radioactive mate %I released from the site to unrestricted areas (at or beyond the site boundary, Dresden Station ODCM Annex, Append:x F, Figure F-1) shall be limited to the concentrations specified in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402', for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gasts, the concentration shall be limited to the values listed in Table 12.3-1.

With the concentration of radioactwe material released from the site to unrestncted areas exceeding the above limits, without delay decrease the release rate of radioactive materials and/or increase the dilution flow rate to restore the concentration to within the above Irmits.

2.

Dose from Liauid Effluents The dose or dose commitment above background to a member of the public from radioactive materials in liquid affluents released to unrestricted areas (at or beyond the site boundary) from the site shall be limited to the following:

1.

During any Calendar Quarter:

(1)

Less than or equal to 3 mrem to the wtiole body.

(2)

Less than or equal to 10 mrem to any organ.

2.

During any Calendar Year:

(1)

Less than or equal to 6 mrem to the whole body.

(2)

Less than or equal to 20 mrem to any organ.

3.

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days a Special Report which identifies the cause(s) and defines the corrective actions taken and the proposed actions to be taken to ensure that future releases are in compliance with Sections 12.3.A.2.1 and 12.3.A.2.2. This is in lieu of a Licensee Event Repon

Upon technical specification approval, ten (10) times the Appendix B value may be ussi to determine the maximun, instantaneous licuid release.

I tonorddawodemwnt2r14 doc 12-20

-.I DRESDEN Revision 16 1

4

^

December 1997 i

.12.3.A Limad EfDuants Limits and Reporting Onoratulity (Cont'd) -

)

1

.4.

With the calculated dose from the release of radoactrve materials in

~

p-Q liquid ofnuents exceeding the limits of Sectens 12.3.A 2.1 or 12.3A2.2.,-.

g prepare and submit a Specal Report to the Comrmssion within 30 days and limit the subesquent releases such that the dose or dose commitment to a member of the public from all uranium fuel cycle '

sources is limited to less than or equal to 25 mrom to the total body or

. any organ (except thyroid, which is hmited to less than or equal to 75 E

mrom) over 12 consecutud months. This Special Report shall include an -

analysis which demonstrales that radiation exposures to all real

individuals from all ur mium fuel cycle sources (including all ofRuant pathways and direct radiation) are less than the 40 CFR Part 190

. Standard. Otherwise obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Monderd. The radiation _

i

.i exposure analysis contair:ed in the Special Report shall use methods

+

prescribed in the ODCMc This report is in lieu of a Licensee Event Report.__

5.

. When the projected annual whole body or any intemal organ dose computed at the nearest downstream community water system is equal to or exceeds 2 mrom from ali radioactive materials released in liquid ofRuents from the Station, prepare and submit a Special Report within 30 days to the operator of the community water system. The report is prepared to assist the operator in meeting the requirements of 40 CFR -.

Part 141, EPA Primary Drinking Water Standards.- A copy of this report -

will be sent to the NRC. This is in lieu of a Licensae Event Report.-

3; Dose Prolactions At all times during processing prior to discharge to the environs, process and control equipment provided to reduce the amount or concentration of radioactive materials shall be operated when the projected dose due to liquid effluent '

releases to unrestricted areas (Dresden Station ODCM Annex, Appendix F, Figure F-1), when averaged over 31 days, exceeds 0.12 mrem to the total t,ody

[

or 0.40 mrom to any organ *,

n

These values represent 2% of the annual dose limits of Appendix I to 10CFR50.

c

)

A

\\

, IGNOM$1100thM$Cmh$n12fias GOC 12-21 q

~

DRESDEN R:, vision 1.6 December 1997 12.3.A.

Lbuid Effluents Limits and Reoortino Ooerability (Cont'd) 4.

Licuid Radnetive Waste Treatment System if liquid waste has to be or is being discharged without treatment as required above, prepare and submit to the Commission with 30 days, a report which includes the following information.

1.

Identification of the defective equipment.

2.

Cause of the defect in the equipment.

3.

Action (s) taken to restore the equipment to an operating status.

4.

Length of time the above requirerrtents were not satisfied.

5.

Volume and curie content of the waste discharged which was not processed by the appropriate equipment but which required processing.

6.

Action (s) taken to prevent a recurrence of equipment failures.

This is in lieu of a Licensee Event Report.

5.

Sy.11tLm Ooerability and Plant Ooerations in the event a limit and/or associated action requirements identified in Sections 12.3.A and 12.3.8 cannot be satirfied because of circumstances in excess of those addressed in this Section, no changes are required in the operational condition of the plant, and this does not prevent t% plant from entry into any operational mode.

12.3.B Llaultj Effluents Surveillance 1.

Concentration in Unrestricted Areas The concentration of radioactive matenalin unrestricted areas shall be determined to be within the prescribed limits by obtaining representative samples in accordance with the sampling and analysis program specified in Table 12.3-2.

The sample analysis results will be used with the calculational methods in the ODCM to determine that the concentrations are within the limits of Section 12.3.A.1, O,

toworddataVxk:mV!n12r14 doc 12-22

DRESDEN Rcytion 1.6 December 1997 12,3.B t_iauid Emuents Surveillance (Cont'd)

~

2.

Dose from Liould Emuents J

The dose contribution from measured quanttes of radioactwe material shall be determined by calculation at least once per 31 cays and cumulatue summation of these total body and organ dosed shall be maintained fcr each calendar quarter.

Doses computed at the nearest community water system will consider only the drinking water pathway and shall be projected using the methods prescribed in ODCM, at least once per 92 days.

3.

Dose Proiactio6s Doses due to liquid releases to unrestricteo areas (at or beyond the site boundary) shall be projected et least once per 31 days in accordance with the ODCM.

1 O

4

. MnorddetabdcmWo12r14 doc 12 23

DRESDEN R0 vision 1.6 a

Dec:mber 1997 TABLE 12.3-1 ALLOWABLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE NUCLlDE AC(uCi/mn*

Kr-85m 2 x 10" Kr-85 5 x 10" 4

Kr-87 4 x 10 4

Kr-88 9 x 10 4

Ar-41 7 x 10 Xe-131m 7 x 10" Xe-133m 5 x 10" d

Xe-133 6 x 10 Xe-135m 2 x 10" Xe-135 2 x 10" Computed from Equation 20 of ICRP Publication 2 (1959), adjusted for infinite cloud submersion in water, and R = 0.01 remtweek, density = 1.0 g/cc and Pw/Pt = 1.0.

O h:hworddatabdcrnidn12r14 doc '

12-24

DRESDEN R: vision 1.6 Dec;mber 1997 TABLE 12.3-2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM UNIT 1 LOWER LIMIT OF T)OE OF ACTIVITY DETECTION LIQUID RELEASE SAMPLING MINIMUM ANALYSIS ANALYSIS (LLD)")(pCi/ml)

TYPE FREQUENCY (')

FREQUENCY (')

Above See TS 3/4.8.J See TS 3/4.8.J Principal Gamma 5x10 Ground Emitters (5)

Liquid Storage Dissolved & Entrained 1x10

Tanks Gases (')(Gamma Emitters)

O 4

N

' h%vorddatakxicmW12r14 doc 12-25 l

DRESDEN Revision 1.6 December 1997

)

TABLE 12.3-2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 4

UNITS 2 & 3 i

LOWER LIMIT OF TYPE OF ACTIVITY DETECTION LIQUID RELEASE SAMPLING MINIMUM ANALYSIS ANALYSIS

- (LLD)")(pCi/ml)

TYPE FREQUENCY" FREQUENCY

A. Batch Prior to Prior to Principal Gamma 5x10

Release Each Batch Each Batch Emitters

4 Tonks 1-131 1x10 Prior to M

Gross Alpha 1 x10

Each Batch Composito*

H-3 1x104 4

Prior to O

Fe-55 1x10 Es.:h Batch Composite

Sr-89, Sr-90 5x104 4

Prior to M

Dissolved & Entrained 1x10 Cne Batch /M Gases *(Gamma Emitters) 8 Plant M*

M*

l-131 1x10d Continuous (Grab Sample)

RCleases*

M*

M

Principal Gamma 5x10

(Grab Sample)

Emitters

M*

M*

Disso!ved & Entrained 1x104 iGrab Sample)

Gases *(Gamma Emitters)

M*

H-3 1x104 (Grab Sample)

Gross Alpha 1x10 Q*

Q*

Sr-89, Sr-90 5x104 (Grab Sampic) 4 Fe-55 1x10 C. Above Ground See TS 3/4.8.J P,iS 3/4.8.J Principal Gamma 5x10#

Liquid Storag6 Emitters

Tanks 4

Dissolved & Entrained 1x10 Gases *(Gamma Emitters)

~~

.r.

h%ottidatakv$cmVfn12f14 doc 12-26 JumA i

DRESDEN RIvision 1.6 December 1997 f

TABl E 12.3-2 (Cont'd)

I,g]

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIQB 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% probability with only 5% probability of falsely concluding that a blank observation represents a " rear signal.

For a particular measurement system, which may include radiochemical separation:

LLD=

4.66S __

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),

V = the sample size (units of mass or volume),

2.22 x 10' = the number of disintegrations per minute per microcurie, Y = the fractional radicchemical yield, wheti applicable.

A= the radioactive decay constant for the particular radionuclide (sec "), and at = the elapsed time between the micpoint of sample collection and the time of counting (sec).

Typical values of E. V, Y, and At should be used in the calculation.

A11ga;T* t_LD Methodolooy An alternate methodology for LLD determination follows and is similar to the above LLD equation:

(2.71 + 4.65VB) Decay LLD =

E q b Y t (2.22E06)

Ii I

h botJdatabdcmWn12r14 doc 12-27

DRESDEN R;vtion 1.6 Dec:mber 1997 TABLE 12 3-2 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION Where:

B = tsackground sum (counts)

E = counting efficiency, (counts detected / disintegrations) q = sample quantity,(mass or volume) b = abundance,(if applicable)

Y = fractional radochemical yield or collection efficiency, (if applicable) t = count time (minutes) 2.22E06 = number of disintegrations per minute per microcurie (2.71 + 4.65VB) = k' + (2k 4 2 4 b), and k = 1.645.

(k=value of tne t statistic from the single-tailed t distribution at a significance level of 0.95% and infinite degrees of freedom. This means that the LLD result represents a 95% detection probability with a 5% probability of falsely concluding that the nuclide present when it is not or that the nuclide is not present when it is.)

O Decay = e*"[ ART /(1-e#)][AT /(1 e'*")), (if applicable)

A = raoioactive decay constant, (units consistent with 6t, RT and T.)

At = " delta t*, or the elapsed time t4 tween sample collection or the midpoint of sample collection and the time the count is started, depending on the type of sarr pie.

(units consistent with A)

RT = elapsed real time, or the duration of the sample count, (units consistent with A)

T = sample deposition time, or the duration of analyte collection onto the sample media, (unit consistent with A)

The LLD may be determined using in'.talled radioanalytical software, if available. In addition to determining the correct number of channels over which to total the background sum, utihzing the software s ability to perforrr my corrections (i.e. during sample collection, from sample collection to start of analysis and during counting), this alternate method will result in a more accus, a determination of the LLD.

It should be recognized that the LLD is defined as a before the fact limit and not as an after the fact limit for e particular measurement.

O h%rorddatabdcmWn12n 6 doc 12-28

DRESDEN Rtvision 1.6 December 1997 i

TABLE 12.3-2 (Cont'd)

A RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM

()

16BLE NOTATION A composite sample is one in which the quantity of liquid samples is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

If the alarm setpoint of the service water efficent monitor as determined in the ODCM is exceeded, the frequency of anarysis shall be increased to daily until the condition no longer exists.

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 to assure representative sampling. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e g.,

from a volume or system that has an input flow during the release.

The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-60, Zn-65, Co-58, Mo-99, Cs 134, Cs-137, Ce-141, and Ce-144.

Other peaks which are measurable and identifiable by gamma ray spectrometry together with the above nuclides, shall be also identified and reported when the actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being present at the LLD level for that nuclide.

The dissolved and entrained gases (gamma emitters) for which the LLD specification applies exclusively are the fo!!owing radionuclides: Kr-87, Kr 88, Xe-133, Xe-133m, Xe-135, and Xe-138.

Other dissolved and entrained gases (gamma emitters) which are measurable and identifiable by gamma ray spectrometry, together with the above nuclides, shall also be identified and reported g

when an actual analysis is performed on a sample. Nuc1 des which are below the LLD for the x

analyses shall not be reported as being present Lt the LLD level for that nuclide.

O

\\

hNrorddatabdcrnWn12r14 doc 12-29

DRESDEN Revision 9.6 December 1997 12.3.C LIQUID EFFLUENTS BASES i

1.

Concentration This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402.

2.

D.ose This specification is provided to implement the requirements of Sections ll.A, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The operational requirements implements the guides set forth in Section li.A of Appendix 1. The statements provide the required operating flexibihty 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 liquid effluents will be kept "as low as reasonably achievable". The dose calculations in the ODCM implement the requirements tra Section Ill.A of Appendix l that conformance with the guides of Appendix I be shown by r,alculational procedures based on models and data such that the actual exposure of an individual 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 liquid effluents will be 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 1.113," Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendix I", April 1977.

NUREG-0113 provides methods for dose calculations consistent with Reg Guide 1.109 and 1.113.

3.

Liouid Waste Treatment The operability of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section 11.D of Appendix I to 10 CFR Part 50.

O hDordcataWcmWn12r1-6 doc 12 30

DRESDEN Revtion 1.3 Dec;mber 1997 12.3.C LIQUID EFFLUENTS BASES-(Continued) 4.

Mechanical Vacuum Pumo -

The purpose of isolating the rnechanical vacuum line is to limit release of activity from the main condenser. During an accident, fission products would be transported frem the reactor through the main steam line to the main condenser. The fission product radioactivity would be sensed by the main steamline radioactivity monitors which initiate isolation.

/ 'l O

m h Matabdcm'dn12ti-6. doc 12-31

DRESDEN RIvizion 1.6 I

December 1997 12.4 GASEOUS EFFLUENTS A.

Gastous Effluents Limits and Reoortino Ooerability 1.

Dose Rate The dose rate in unrestricted areas at or beycod the site boundary (Dresden Station ODCM Annex, Appendix F, Figure F 1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following.

1.

For Noble Gases:

(1)

Less than a dose rate of 500 mrem / year to the whole body.

(2)

Less than a dose rate of 3000 mrem / year to the skin.

2.

For iodine 131, for iodine-133, tritium and for all radionuclides in particulate form with half-lives greater than 8 days, less than a dose rate of 1500 mrem / year.

3.

If the dose rates exceed the above limits, without delay decrease the release rates to bring the dose rates within the limits, and provide notification to the Commission (per 10 CFR Part 20.2203).

2.

Noble Gas Dose The air dose in unrestricted areas at or beyond the site boundary due to noble gases released in gaseous effluents from 'he unit shall be limited to the following:

1.

For Gamma Radiation (1)

Less than or equal to 5 mrad during.any calendar quarter.

(2)

Less than or equal to 10 mrad during any calendar year.

2.

For Beta Radiation (1)

Less than or equel to 10 mrad during any calendar quarter.

(2)

Less than or equal to 20 mrad during any calendar year.

3.

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to ensure that future releases are in compliance with Sections 12.4.A.2.1 and 12.4.A.2.2. This is in lieu of a Licensee Event Report.

hDorddatawdemW612t14 doc 12-32

DRESDEN Revision 1.6 i

December 1997 12.4.A Gaseous Effluents Limits and Renortino Ooerability (Cont'd)

(

4.

With the calculated air dose from radioactive noble gases in gaseous

(

effluents exceeding the limitr, of Sections 12.4.A.2.1 or 12.4.A.2.2, prepare and subrnit a Special Report to the Commission within 30 days and limit the subsequent releases such that the doses or dose commitment to a member of the publiWom all uranium fuel cycle sources is limited to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months. This Special Report sha!! include an analysis which demonstrates that radiation exposures to all meTibem of the public from all uranium fuel cycle sources (including all emuen, pathways and direct radiation) ::rc lees than 40 CFR Part 190 Standard. Otherwise, obtain a variance from the Commiss'on to permit releases whic) exceed tne 40CFR Part 190 Standard. The radiation exposure analysis contained in the Special Report shall use the methods prescribed in the ODCM. This report is in isu of a Licensee Event Report.

5.

Process and control equipment pravided to reduce the amount or concentration of radioactue materials shall be aperated when the projected dose due to gaseous effluents released to the unrestricted areas, when 4

averaged over 31 days, excoeds 2% of the annual dose limits of Appendix l to 10CrR50.

3.

lodine-131. lodine-133. Tritium. and Parivulate Dose The dose to a member of the public in unrestricted areas at or Myond the site boundary from iodine-121, lodine 133, tntium, and all radionwides in par +t 11 ate form with half-lives greater than 8 dcys in gaseous xffluents released from the unit shall be limited to the following.

1.

Less than or equal to 7.5 mrem to any organ during any calendar quarter.

2.

Less than or equal to 15 mrom to any organ during any calendar year.

3.

With the criculated dose from the release of lof.ine-131, iodine 133, tritium, and all radionuchdes h1 particulate form with half-lives greater than 8 days in gaseous effluents exceeding any of the above limits, prepare and submit te the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and detines the corrective actions taken to ensure that future releases are in compliance with Section 12.4.A.3.1 and 12A.A.3.2. This is in lieu of a Licensee Event Report.

4.

With the calculated dose from the release of iodine-131, iodine 133, tritium, and all radionuchdes in particulate form with half-lives gmater than 8 days in gaseous effluents exceeding the limits of Sections 12.4.A.3.1. or 12,4.A.3.2.,

prepare and submit a Special Report to the Cornmissbn within 30 days and limit subsequent releases such that the dose or dose commitment to a member of the public from all uranium fuel sources Q)-

ftWorodatabdcmWn12r16. doc 12-33 lu.._.......__...m--

-A

- ~ ~ ~ - - " - - -

DRESDEN Revision 1.6 December 1997 12.4.A An..ous Effluents Limits and Reoortino Ooerability (Cont'd) is limited to less than or equal to 25 mrem to the total bocy or organ (except the ihyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months. This Special Report shall include an analysis which demonstmtes that radiation exposures to all members of the public from all uranium fu61 cycle sources (including all effluent pathways and direct radiation) are less than the.40 CFR Part 190 Standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard. The radiation exposure analysis contained in th6, Special Report shall use the methods prescribed in the ODCM. This report is in lieu of a Licensee Event Report.

5.

Process and control equipment provided to reduce the amount or concentration of radioactive materials shall be operated when the projected dose due to gaseous effluents released to the unrestricted areas, when averaged over 31 drvs, exceeds 2% of the annual dose limits of Appendix l to 10CFR50.

4.

Off-Gas Treatment 1.

At all times during processing for discharge to the environs, process and control equipment provided to reduce the amount of concentration of radioactive materials shall be operated.

2.

The above specification shall not apply for the Off-Gas Charcoal Adsorber Beds below 30 percent of rated thermal power.

O 3.

The recombiner shall be operable whenever the reactor is operating at a pressure greater than 900 psig.

4.

The recombiner may be inoperable for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

5.

With either the recorr.biners inoperable, or all charcoal beds by-passed for more than 7 days in a calendar quarter while operating abe /e 30 percent of the rated thermal power, prepare and submit to the Commission within 30 days a Special Report which includes the following information.

a.

Identification of the defective equipment.

b.

Cause of the defect in the equipmed c.

Actbn(s) taken to restore the equipment to an operating status.

d.

Length of time the above tequirements were not satisfied.

e.

Volume and curie content of the waste discharged.vhich was not pmcerJed by the inoperable equipment but which required processing.

O l

h:WortMatmedcmWn12ri 6 doc 12 34 m

DRESDEN Revision 1.6 December 1997 12 4.A Geseous Effluents Limits and Reoortina Ooerabihtv (Cont'd) f.

Action (s) taken to prevent a recurrence of equipment failures.

This is in lieu of a Licensee Event Report.

5.

!/ain Condenser Air Eiector The release rate of the sum of the activities from the noble gases measured at the main condenser air ejector shall be limited to s 100 microcuries/sec per MWt (after 30 minutes decay) wher. in ri. odes 1,2*, and 3' With the release rs.le of the sum of the activities from noble gabes at the main condenser air ejector effluent (as measured nrior to the offges holdup !ine) > 100 microcuries/see per MWt, after 30 minutes

- decay, rastore the release rate to within its limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or be in at least STARTUP with the main steam isolation valves closed within the ne: t 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . (Refer to Technical Specification 3.8.1.)

6.

System Ooerabihtv and P! ant Ooerations in the event a limit and/or associated action requirements identified in Sections 12.4.A s

and 12.4.B cannot be satisfi;:d because of circumstances in excess of those addressed in tiils Section, no changes are required in the operational cond.' tion of the plant, and tnis does not prevent the plant from entry into any operational mode.

v) 4 t

When the main condenser air ejector is in operation.

/~)

h hvorddatabocmVin12r14 doc 12 35

DRESDEN Revision 1.6 December 1997 12.4.8 Gaseous Effluents Surveillance 1.

Dose Rate The dose rates due to radioactive materials release d in gaseous effluents from the site shail be determined to be within the prescribed limits by obtaining representative samples in accordance with the sampling and analysis program specified in Table 12.41. The dose rates are calculated using methods prescribed in the ODCM.

2.

HQble Gas Done The air dose duc to re' eases of radioactive noble gases in gaseous effluents shall be determined to be within the prescribed firrits by obtaining representative samoles in accordance with the sampling and analysis program specified in Sections A knd B of Table 12.41. The allocation of effluents between units having shared effluent control system and the determination of cumulative and projected dose contributions for the current calendar quarter and current calendai year shall be determined in accordance with the methodology and parameters in the ODCM at least once every 31 days.

3.

lodine-131 lodine-133. Tritium and Particulate Dose T*.e dose to a member of the public due to releases of iodine-131, lodine-133, tritium, and all radionuclides in parthlate form with half-lives greater than 8 days shall be determined to be within the r rescribed limits by obtaining representatis e samples in s

accordance with the sare,p'ing and analysis program specified in Table 12.41.

Foi radionuclides not c'etermined in each batch or weekly composite, the dose contnbetion to the current calendar quarter cumulative summation may be estimated by assuming an average monthly concentration based on the previous morthly or quarterly composite analyses. However, for reporting purposes, the calculated dose contributions shall be based on the actual composite analyces when possible.

The allocation of effluents between units having shared effluent control system and the determination of cumulative and projected dose contributions for the current calendar quarter and cunent calendar year shall be determined in accordance with the methodok gf and parameters in the ODCM at least once every 31 days.

4.

Off-Gas Treatment Doses due to treated gases released to unrestricted areas at or beyond the site boundary shall be projected at least once per 31 days in accordance with the ODCM.

O hboradatabdcrnWn12ri 6 doc 12-36

.~.

.-. --..~.- -- -_-

DRESDEN" Revision 1.6 s

December 1997 12.4.8 Ogap,us Effluards Survedlance Contr.ued I

- Q 5.

Noble Ganas at the Main Condenaar Air Epr

)

The rele:.ee rate of noble gases frs.1 the main condenser air ejector shall be continuously mondored The release rate of the sum of the activites from noble i

gases from the main condenser air ejector shall be determined to be within the limits of 12.4 A5 at the following fmquencies by performing an isotopic analysis of a representative sample of gases taken at the recombmer outlet, or at the air ejector outlet if the recombiner is by-passed.

i 1.

At least once per 31 days.

2.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following determinsbon of an increase of greater than 50%.

1 (Refer to Technical Specification 4.8.l.)

e f

i e

_1'j' O

12 37' y--

- +,..

w y

v-w-

w

-.v-, -

--,,.-2-w-

,y--

r%,-.

.cy r-w w

y-+,, -,-,, -,

w y,-m-y

DRESDEN Revision. 6 a

December 1997 TABLE 12.41 O

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM UNIT 1 GASEOUS SAMPLING MINIMUM

'iYPE OF ACTIVITY LOWER LIMIT OF RELEASE FREQUENCY ANALYSIS ANALYSIS DETECTION (LLD)"'

TYPE FREQUENCY (pCi/ml) 4 A. Main M

M PrincipalGamma 1x10 Chimney (Grab Sample)

Emitters *)

4 Tritium 1x10 4

Noble Gases 1x10 M'")

M*

l131 1 x10~'8 (Continuous) lodine Sample 1-133 1 x10

M")

M*

Principal Gamma 1 x10'"

(Continuous)

Particulate Sample Emitters

Q Q

Sr 89, Sr-90 1x10'"

(Continuous)

Composite Gross Alpha Particulate Sample h kvorddetaWJcmVin12r14 doc 12-38

DRESDEN Revtion 1.6 December 1997 Table 12.41 O

RADIOACTIVE GASEOUS WASTE SAMPUNG AND ANALYSIS PROGRAM UNITS 2 & 3 LOWER LIMIT GASEOUS SAMPLING MINIMUM TYPE OF ACTIVITY OF RELEASE FREQUENCY ANALYSIS ANALYSIS DETECTION TYPE FREQUENCY (LLD)")(pCi/ml)

A. Main M

M(2)

Principal Chimney (Grab Sample)

Gamma Emitters")

1x10d Reactor 4

Bldg.

Tritium 1x10 Vant Stack B. All Continuous ')

l131 1x10"'

i Release ~

lodine Sample 1-133 1x10"'

Types as Listed in A above Continuous

M' Principal Gamma 1x10'"

{

j Particulate Sample Emitters "'

Continuous")

Q Sr 89 1 x10'"

Composite Particulate Sample Sr 90 1 x10'"

Continuous)

Q Gross Alpha 1 x10'"

Composite Particulate Sample C. Main Continuous

Noble Gas Monitor Noble Gases 1x104 Chimney D. Reactor Continuous (*)

Noble Gas Monitor Noble Gases 1x10d Bldg.

Vent Stack i

\\

V h %worddateWW12r14 doc 12.

e w

w y-v w

---*,-'e og-e-

+

e-r 9-3

DRESDEN Revrion 1.6 December 1997 TABLE 12.41 (Cont'd)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTA *3Of4 "3

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% probability with only 5% probability of falsely concluding that a blank observation represents a "reof" signal.

For a partcular measurement system, which may include radiochemical separation-LLD =

4.66S:

E V

2.22 x 10'. Y. exp ( Aat)

Where:

LLD = the lower hmrt of detection (microCuries per uriit mass or volume),

s, = the standard deviation of the background counting rate or of the counting rate of a blank samp!v as appropriate (counts per minute),

E = the counting efficiency (counts per oisintegration),

V = the sample size (units of mass or volume),

2.22 x 10' = the number of disintegrations por minute per raicroCurie, 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, and at should be used in the calculation.

Alternate LLD Methodoloav An attemate methodology for LLD determination follows and is similar to the above LLD equation:

(2.71 + 4.65VB)* Decay LLD =

E q b Y t (2.22E06)

O h Worddatabdctndn12rt-6 doc 12-40

DRESDEN Revtion 1.6

(

December 1997 TABLE 12.41 (Continued)

%/-

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS Where:

B = background aum (counts)

E = counting efficiency, (counts detected / disintegrations) q = sample quantity,(mass or volume) b = abundance,(if applicable)

Y = fractional radiocheinhal yield or collection efficiency, (if applicable) t = count time (minutes) 2.22E06 = number of disintegrations per minute per microcurie 8

(2.71 + 4.6548) = k + (2k V 2 V B), and k = 1.645.

(k=value of the t statistic from the single-t&' led t distribution at a significance level of 0.95% and infinite degrees of freedom. This means that the LLD result g) represents a 95% detection probability with a 5% probability of falsely concluding that the nuclide present when it is not or that the nudide is not present when it is.)

Decay = e* [ ART /(1-e"))[AT,/(1-e'"')), (if applicable)

A = radioactive decay constant, (units consistent with At, RT and T )

At = ' delta t", or the elapsed time between sampWcollection or the midpoint of sample collection and the time the count is started, depending on the type of sample, (units consistentwith A)

RT = elapsed real time, or the duration of the sample count, (units consistent with A)

T = samr'o deposition time, or the duration of analyte collection onto the sample media, (unit consistent with A)

The LLD may be determined using Installed radioanalytical softvtare, if available. In addition to determining the correct number of channels over which to total the background sum, utilizing the software's ability to perform decay corrections (i.e. during sample collection, from s inple collection to start of analysis and during counting), this attemate method will result in e more accurate determination of the LLD.

It should be recognized that the LLD is defined as a before the fact limit and not as an after the fact limit for a particular measurement.

U hAworddatabdanWn12r14 doc 1241 1

I

DRESDEN R: vision 1.6 December 1997 TABLE 12.41 (Cont'd)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION Sampling and analyses shall also be performed following shutdown, startup, or a thermal power change exceeding 20 percent of mted thermal power in i hour unless (1) analysis shows that the dose equivalent 1131 concentration in the pnmary coolant has not increased more than a factor of 5, and (2) de noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.

Samples shall be changed at least once per 7 days and the analyses completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after removal from the sampler. Sampling shall also be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following each shutdown, startup, or thermal power level change exceeding 20% of rated thermal power in one hour. This requirement does not apply if 1) analysis shows that the dose equivalent 1 131 concentration in the pnmary coolant has not increased more than a factor of 5, and 2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.

When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are anaiyzed, the corresponding LLDs may be increased by a factor of 10.

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

The principal gamma ernitters for which the LLD specification applies exc.lusively are the following radionuchdes: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions, and Mn 54, Fe-59, Co-60,2n-65, Co-58, Mo-99, Cs-134, Cs-137, Ce 141, and Ce-144 for particulate emissions. Other peaks whic.1 are measurable and identifiable by gamma ray spectrometry, together with the above nuchdes, shall be also identified and reported when an actual analysis is performed on a sample. Nuchdes which are below the LLD for the analyses shall not be reported as being present at the LLD level for the nuchde.

Analyt.is frequency shall be increased to 1/ week if release rates exceed 1% of any applicable hmit referenced in the ODCM, when added to Units 2 and 3 airbome effluents.

O h WortMatabdcmWn12ri 6 doc 12-42

DPESDEN Revision 1.6 December 1997 12.4.C Gngrus Emuents Bast.3 Q) f 1.

Gaseous Effluents - Dose This Section is provided to ensure that the dos 7 at the unrestricted area boundary from gaseous effluents from the units on site will be within the annual dose limits of 10CFR20 for unrestricted areas. These limits provide reasonable assurance that radiovtive matsrial discharged in gaseous effluents wiii not result in the exposure of an ludividual in an unrestricted area to annual average concentrations exceeding the limits specified in Appendix B, Table 2 of 10CFR20.1001-2402. The release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the unrestricted area boundary to less than or equal to 500 mrem / year to the total body or to less than or equal to 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyloid dose rate above background via ble inhalato" pinhway to less than or equal to 1500 mremfyear. For purposes of calcu!ston doses resulting from altbome releases, the main chimney is considered to be an elevated release point and the reactor building vent stack is considered to be a mixed mode release pomt 2.

RoseJoble Gase.s This Soction is provided to implament the requirements of Sections ll.B, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Operability R1tquirements implement the geides set forth in Section 11.3 of Append!x 1. TM statems. sts provide the required operatirg flexibility and at the same time implement the guides set forth in Sechon IV.A of Appendix l to assure thut the ieleases of radaoactive materialin gaseous effluents will be kept "as tow as is mason 3bly achievable." The surveillance requiroments implement the requirements

/,\\

in Section lil A of Appendix i that conformance with the guides of Appendix 1 is to be

\\-

shown by calculational procedures based on models and data sucirthat the actual exposure of an individual 'hrough the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Ftegulatory Guide 1.109," Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of y

Evaluating Compliance with 10 CFR Part 50, Appendix 1,* Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Eftluents in Routine Releases from Ught Water Cooled Reactors," Revision 1, July 1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.103 and 1.111.

(3

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hvcatkletsNcmWn12ri 6 rioc 12 43

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DRESDEN Revision 1.6 December 1997 1

12.4.C Gageous Effluents Bases (Cont'd) 3.

Dose. Radiciodines Radioactive Materialin Particulate Form ar.d Radionuclides Other than Noble Gases This Section is provided to implement the i Jttements of Sections ll.C, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Operabilrty Requirements are the guides set forth in i

Secton ll.C of Appendix 1. The statements provide the required operating flexibility and at the same time implement the guide, set forth in Section IV.A of Appendix I to assure that i

the releases of radioactive materials in gaseous effluents will be kept "as low as 1

1 reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section Ill.A of Appendix l that conformance with the guides of Appendix l be shown by calculational procedures based on models and data such that the actual exposure of an inolvidual through appropriate pathways is un!ikely to be substantially underestimated. The ODCM calculational methods approved by NRC for calculating the doses due to the actual release rates of the subject materials are required to be 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 1.111," Methods for Estimating Atmospheric Transport and Dispersion of Gar,eous Effluents in Routine Releases from Light-Water Cooled Reactors,"

Revision 1, July 1977. These equations also provide for determining the actual doses based upon the histoncal overage atmospheric conditions. The release rate limits for radbeodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these limits were: 1) individualinhalation of airboms radionuclides,2) deposition of radionuclides onto green leafy vegetat on with subsequent consumption by man and 3) depor,ition onto grassy areas where milk animals graze with consumption of the milk by man.

4.

Gaseous Waste Treatment The operability of the gaseous waste treatment which reduces amounts or concentrations of radioactive materials ensures that the system will be available for use whenever gaseous effluents require treatment pnor to release to the environment. The requirement that the appropnate portions of this system be operable when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, Genera! Design Criterion 60 of Appendix A to 10 CFR Part 50, ano design objective Section ll.D of Appendix 1 to 10 CFR Part 50.

O h WeddataVx$cmVin12r14 doc 12-44

DRESDEN Revision 1.6 December 1997 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l

12.5.1 Mondorina Proaram Doerabihty Reauirements 12.5.1. A The Radiological Environmental Monitoring Program shall be conducted as specified in Table 12.5-1.

Aeolicabilrtv: At all times.

Action i

1.

With the Radiole, el Environmental Monitoring Program not being conducted as specified in Table.2.51, prepare and subm4 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, sear.onal availability, malknetion of sampling 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 samples gous 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.

D

.1 With the level ol radioactrvity 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 C,nmmission within 30 days, pursuant to Technical Specification 6.9." 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 hmits of Section 12.3.A.2,12.4.A.2, or 12.4.A.3. When more than one cf the radionuchdes in Table 12.5-2 are detected in the sampling medium, this report shall be submitted if.

concentration (1) concentration (2) +.. 21.0 reporting level (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 kmits of Section 12.3A2,12.4 A2, or 12.4.A.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Section 12.6.1.

"The methodology and narameters used to estimate the potential ab iual dose to a MEMBER OF THE O

PUBLIC shall be indicated in this report.

\\,,)

h krorddatabdcmun12r16 doc 12-45

DRESDEN Revision 1.6 Decembs '.997 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued) 3.

If the sample type or samr5ng location (s) as required by Table 12.5-1 become(s) permanently unavailable, ioentify suitable attemative sampling rnedia for the pathway of interest and/or specific locations for obtaining replacement samples and add them to the Radiological Environmental Mondoring Program as soon es practicable. The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Prepare and submit controlled vention of tha 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 Reagirements._

12.5.1.B The radiological environmental monitoring program samples shall be collected pursuant to Table 12.5-1 from the specific locations given in the table and figure (s) in the ODCM, and chall be analyzed pursuant to the requirements cf Table 12.5-1 and the dstection capabihties required by Table 12.5-3.

flaat1._.

12.5...u The Rauc'ogical Environmental Monitoring Program iequi ed by this section provides representative measurements of radia'. son and of radioactive matt. rials in those exposure pathways and for those rtidionuchdes that lead to the highest potenth31 radLMhn exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoririg program implementsSection IV.B.2 of Appendix 1 to 10 CFR Part 50 and thereby supplements the radiological eff,uent monitoring program by verifying that the menswable concer.tratione 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 specifed monitoring program will be effective for at least the f;rst 3 years of commercial operation. Following this period, program changes may be initiated based on operatonal experience.

The required detection capabilities for envircnmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 12.5-3 are considsrer) optimum for routine environmental macsurements in indussial laboratories. It shouic be recognized that the LLD is defined as a before the fact limit repcesenting the capab!h'y of a measurement system and not as an after the fact hmit for a particular measurement.

Detailad discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, LA., " Limits for Quahtative Detection and Quantitative Determination - Applicatiori to Radiochemistry," Anal. Chem.

40, 586-93 (1968), and Hartwell, J.K., " Detection limits for Radioana!ytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

O h1woredatabdcment2tt 6 doc 12-46

DRESDEN Revision 1.6 Decernber 1997 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued) n intar W % s 12.5.1.0 Tabb 12.51 requires "one sample of each community dnnking water suppy downstream of the plant withh 10 kilometers." Drinking water supply is defined as water taken from rivers, lakes, or reservoirs (not well water) which is osed for drinking.

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12-47.

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DRESDEN Revision 1.6 December 1997 TABLE 12.5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND ANDIOR SAMPLE AND SAMPLE LOCATIONS"3 FREQUENCY FREQUENCY OF ANALYSIS

1. Aarbome Samples from a total of eight locatons:

Continuous partctiate sampier Radciorm Canister-Radioiodine and operaton with sample cceed;vn 1-131 analysis beweekly Particulates

a. Iridicator-Near Field weeldy, or more frequently if on near Seid samples and A

required due to dust loading, and control Four samples from locations within 4 km (2.5 rni) radioiodene canister carh in different sectors.

beweekly.

Pahlate Samomr Gross beta anaysis

b. Indicator-Far Field weekly filter change and gsmma Four additional locations within 4 to 10 km (2 5 to isotopic analysis"'

l 6 2 mi) in dMerent sectors.

quarterty on composite filters bylocatort on near

c. Control feld samples and l

control.*

One sample from a controllocaton within 10 to 30 km (6.2 to 18.6 mi).

i hNrorddatabdcmMn12rt-6 doc 12-48 e

9 9

(s)

D N

Revis December 1997 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIROfJMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING #ND COLLECTION TYPE AND ANDIOR SAMPLE AND SAMPLE LOCATIONSm FREQUENCY FREQUENCY OF ANALYSIS

2. Direct Forty routine monitonng stations either with a Quarterty Gamma dose on each Radiation

thermo!uminescent %imeter (TLD) or with one TLD quarterty instrument for measuring dose rate continuously, placed as follows:

a. Indicator-Inner Ring (100 Series TLD)

One in each meteorological sector, in the general area of the SITE BOUNDARY (0.1 to 2 mi!es),

b. Indicator-Outer Ring (200 Series 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 interest locations beyond the Restricted Area where either a MEMBER OF THE PUBLIC or "enwealth E("z,on employees have routine j access.

1 (300 Series TLD) h hvorddatahdn12ri 4 doc 12-49

DRESDEN Revision 1.6 Deceir M 1997 1 ABLE 12.5-1 (Contimico)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND ANDIOR SAMPLE AND SAMPLE LOCATIONSM FREQUENCY FREQUENCY OF ANALYSIS

2. Direct

d. Control Quarterly Gamma dose on sach Radiation * (Cont'd)

TLD quarterty.

One at each Asrborne controllocation given in part 1.c

3. Waterbome

a. Indicabr Quartetty Gamma isotopic ^ and

a. Ground / Well tntium analysis quarterfy.

Samples from three sources only if hkely to be

_ _ _ _ _ _..._ affec_ted '*' _ _ _ _ _ _ _ - _ _ _ _ _ -_ _ _ _ _ _ _ -_ -_ __ _

isotopic analyses"' on One Sample from each community drinking monthly composite; water supp'y that could be affected by the tritium analysis on station discharge within 10 km (6.2 mi) quarterly composde.

_do_*11tream oldl5ch8_rae_ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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

Weekly grab samples Gross beta and gamma Water

cxists within 10 km downstream of disch:rge isotopic analyses") on then surface water sampling shall be performed monthly cun W te; i

tritiura analysis on a Indicator quarterly composite.

_9=_5amELe do*nStrea_m_ _ _ _ ________ __

d. Control

a. Contral Weekly grab samples Gross beta and gamma Sample (')

isotopic analyses"' on One surface sample upstream of discharge.

monthly composite; tritium analysis on quarterly composite.

h hvorddatabdcmW12r14 dec e

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C9 N

Revisio v

December 1997 TABLE 12 ".,-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND ANDIOR SAMPLE AND SAMPLE LOCATIONS"3 FREQUENCY FREQUENCY OF ANALYSIS

e. Sediment

a. Indicator Semiannually.

Gamma isotopic analysis

sem: annually.

At least one sample from downstream

area

--- ------------ within 10 km (6 2 mi).

- T,g-pasture (May through October).

1-131"* analysis on each

a. Milk

Samples from milking anima's from a monthly at other times sample.

maximum of three locations within 10 km (November through April).

(6.2 mi) distance.

l

b. Control One sample from milking animals at a control

__'ocaton_*1 thin 11tp}{km{6 2Jg 18,6 Q____

L

b. Fish

a. Indcator Two times annuaPy.

Gamma % tope analysis

on edible Representative samples of commercially and portons recreationally important species in discharge area.

I

b. Control Representative samples of commercia!!y and recreationally important species in control locations upstream of discharge.

l h hvorddatabdcmVin12rt-6 doc 12-51

DRESDEN Revtson 1.6 December 1997 TABLE 12.5-1 (Continued; RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY -

NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AP'D COLLECTION TYPE AND ANDIOR SAMPLE AND SAMPLE LOCATIONS"8 FREQUENCY FREQUENCY OF ANALYSIS

c. Food Products

a. Indcator Antv.saffy Gamma isotg analysi on each sample.

=

Two representative samples from the principal food pathways grown in each of four major quadrants within 10 km (6.2 mi):

At least one root vegetable sample""

Atleast one broad leaf vegetable (or vegetation)""

b. Control Two representative samples similar to indicator samples grown within 15 to 30 km (9.3 to 18.6 mi).

t e

h Watabdomwr:12r14 do:

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DRESDEN Revision 1.6 December 1997 i

TABLE 12.61 (Contmun RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

~

TABLE NOTATIONS H

(1)

Specife parameters of riistance and direction from the centerime of the midpoint of the

- two units and addrional desicnpton where pertinent, shall be provided for each and every sample locaten in Table 1.1<1 of the ODCM Station Annexes. Refer to NUREG-0133,

" Preparation of Radologeal Effluent Technical Specificatons for Nuclear Power Plants,"

October 1978, and to Radiological Assessment Branch Technical Positon. Revision 1, November 1979.

(2)

Far fleid samples are analyzed when the respective near field sample results are inconsistent with previous measurements and radioactivity is confirmed as having its origin in airbome effluents from the station, or at the disc ttion of the Radiation Protection Director.

(3)-

Airborne parbculate sample fi ters shall be analyzed for gross beta radioactrvity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for redon and thoron daughter decay. If gross beta -

activity in air particulate sampic : '. greater than 10 times the yearly mean of control samples, gan.ma isotopic analys es shall be performed on the individual samples.

(4)

Gamme isotopic analysis means the identifica'Jon and quantification of gamrna emitting radionuclides that may be attributable to the effluents from the station.

(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

+

dosimeters. Film badges shalli ot be used as dosimeters for measuring direct radiation.

The 40 locations is not an absolute number. The number of direct radiation monitoring st.tions may be reduced according to geographicallimitations; e.g., if a station is adjacent to n lake, some sectors may be over water thereby reducing the number of dosimeters o

which could be placed at the indicated distances. The frequency of analysis or readovi for TLD systems will depend upon the characteristics of the specific system used and i

- should be selected to obtain optimum dose information with minimal fading.

(6)

Groundwatcr samples shall be taken when this source M tapped for drinking or irrigation purposes in areas whee the hydraulic gradient or reenwrge properues are suitable for contaminston.

.. (7)

The " downstream" samp's shall be taken in an area ! nond but near the mixing zone.

The "upstraarr. 3 ample" shall be taken et a distance beyond significant influence of the dischstge. Upstream samples in an estuary must be taken far enough upstream to be txyond the station influence.

'(8)

If milking animals are not found in the designated indicator locations, or if the owners dtcline to participate in the REMP, all milk sampling may be discontinued.

.(9)

Biweekly refers to every two weeks.

(10) 1 131 analysis means the analytical separation and counting procedure are specif.c for this radionuclide.

(11); One sample shall consist of a volume / weight of sample large enough to fill contractor 7

specifled contairer, l

rWuoredeteWdomun12r14 doc T 53 3-

~. - - -.. - -.

DRESDEN Revision 1.6 Decerreer 1997 TABLE 12.5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS WATER AIRBORNE PARTICULATE FISH MILK FO9D PRODUCTS ANALYSIS (pCill)

OR GASES (pCi/m')

(pCilkg, wet)

(pCill)

(pCi/kg, wet)

H-5 20,000*

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30.000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2*

0.9 3

100 C3-134 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 na drinking water pathway exists, a value of 20 pCi/I may be used.

i l

h Wi4Latuk.rMdn12r14 doc i

12-54 9

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D EN R

'L December 1997 TABLE 12.5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSISM LOWER LIMIT OF DETECTION (LLD)"

WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT ANALYSIS (pCi/!)

OR GASES (pCi/m')

(pCi/kg, wet)

(pCi/I)

(pCilkg, wet)

(pCi/kg, dry)

Gross Beta 4

0.01 1000

- H-3 2,000m Mn-54 15 130 Fe-59 30 260 Co-56,60 15 130 Zn-65 30 260 Zr-Nb-95 15 t

1-131"'

1/15*

0.07 100 0.5/5"3 60 Cs-134 15 0.01 100

.15 60 150 Cs-137 18 0.01 100 18 80 180 Ba-La-140 15 15 h hvorddataVx!crnMn12rt-6 doc 12-55

DRESDEN Revision 1.6 December 1997 TABLE 12.5-3 (Continued)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS I

I TABLE NOTATIONS (1)

The nuclides on this 14st are not the only nuclides intended to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.

(2)

Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations 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 material in a sample that will yield a net count, above system background, that will be detected with 95% probab!!ity 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, the LLD is defined as follows:

4.66 S, + 3/t, LLD

=

(E) (V) (2.22) (Y) (exp (-ht))

4.66 S.

LLD (E) (V) (2.22) (Y) (exp (-ht))

l I

Where: 4.66 S, n 3/t, the "a priori" Minimum Detectable Concentration (picoCuries per unit mass or volume),

LLD

=

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

=

E the counting efficiency (counts per di integration),

=

the sample size (units of mass or volume),

V

=

2.22

=

the number of disintagrations per minute per picocurie, Y

the fractional radiochemical yield, when applicable,

=

A

=

the radioactive decay constant for the particular radionuclide (sec"),

l I

h brordcata'odemWn12r14 doc 12 56

DRESDEN Ruision 1.6 December 1997 TABLE 12.5 3 (Continued)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS g/

TABLE NOTATIONS counting time of the background or blanx (minutes), and t,

a a'

=

the elapsed time between sample collection, or end of the sample collection period, and the time of counting (sec).

Typical values 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 hmit representing the capabihty of a measurement system and not as an after the fact hmit for a particular measurement.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.

Occasionally, background fluctuations, unavoidable smah sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unschievable. In such cases, the contributing factors shall be identified and described in the Annua! Radiological Environmental Operating Report.

Altemate I i n Methodoloay An attemate methodology for LLD determination follows and is similar to the above LLD equation:

(2.71 + 4.65VB)+ Decay LLD =

pd E q b Y t (2.22E06)

Where:

B = background sum (counts)

E = counting efficiency, (counts detected / disintegrations) q = sample quantity, (mass or volume) b = abundance, (if applicable)

Y = fractional radiochemical yield or collection efficiency, (if apphcable) t a count time (minutes) 2.22E06 = number of disintegrations per minute per microcurie (2.71 + 4.65VB) = k' + (2k V 2 V 8), and k = 1.645.

(k=value of the i statistic f,om the single-tailed t distribution at a significance level of 0.95% and infinite darees of freedom. This means that the LLD result represents a 95% detection probability with a 5% probabihty of falsely concluding that the nuclide present when it is not or that the nuchde is not present when it is.)

f3 Decay = e"[ ART /(1-e"))[AT,/(1-e*)]. (if applicable)

();

h WrorddetaWRmWnt?r14 doc 12 57

DRESDEN R: vision 1.6 -

Dec:mber 1997 TABLE 12.5-3 DETECTION CAPABILITIES FOR ENVIROMMENTAL SAMPLE ANALYSIS TABLE NOTATIONS A = radioactive decay constar.t, (units consistent with At, RT and T.)

At =

delta t", or the elapsed time between sample collection or the midpoint of sample collection and the time the count is started, depending on the type of sample, (units consistent v/tn A)

RT = elapsed real time, or the duration of the sample count, (units consistent with A)

T. = sample deposition time, or the duration of analyte collection onto the sample media, (unit cons,istent with A)

The LLD may be determined using installed radioanalytical software, if available. l'1 addition to determining the correct number of channels over which to total the background sum, utilizing the software's ability to perform decay corrections (i.e. during sample collection, from sample collection to start of analysis and during counting), this attemate method will result in a more accurate determination of the LLD.

It should be recognized that the LLO is defined as a before the fact limit and t'ot as an after the fact limit for a particular measurement.

(4)

If no dnnking water pathway exists, the value of 15 pCill r,',ay be used.

(5)

A value of 0.5 pCili sha!! be used when tr,e animals are on pasture (May through October) and a value of 5 pCi/l 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.

O 12-58 n

DRESDEN Revision 1.6 December 1997 12.5.2 Land Une census hN1ftv Reauirements 1212A A Land Use Census shall be conducted and shall identify within a distance of 10 km (6.2 miles) the location in each of the 16 meteorological sectors' of the nearest milk enimal, the nearest residence", and an enumeration of Irvestock. For dose calculation, a garden will be assumed at the nearest residence.

Anchenbihtv: At all times.

Action

1. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment, via the same exposure pathway 20% greater than at a location from which samples are currently being obtained in accordance with Secten 12.5.1, add the new location (s) within 30 days to the Radiological Environmental Monitoring Program given in Chapter 11. The sampling location (s), excluding the control location, having the lowest calculated dosa 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 Radological Environmer,tal 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 samphng locations.

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

"The nearest industrial facihty shall also be documented if closer than the nearest residence.

Surveillance Reauirements 1

B The Lsnd Use Census shall be conducted during the growing season, 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, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Consus 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 beyono the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made lf required by the results of this census.

This census satisfies the requirements of Section IV.B.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.

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DRESDSN R: vision 1.6 Dec:;mber 1997 12.5.?

Interlaboratory Comoarison Procram QpgIgbihty Reauirements 12.5.3. A Analyses shall be performed on radioactive materials supplied as part of an intertaboratory Comparison Program that correspond to samples required by Table 12.5-1.

Acolicabihty: At all times.

Action 1.

With analyses not being perform'ed as required above, report the corrective actions taker. to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

Surveillance Reauirements 12.5.3.B A summary of the results obtained as part of the above required intertaboratory Comparison Program shall be included in the Anr>ual Radiological Environmental Operating Report.

B.R!its 12.5.3.C The requirement for participation in an Inter:aboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive matenalin environmental samples matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix 1 to 10 CFR Part 50.

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DRESDEN Revision 1.6 December 1997 12.6 RECORDKEEPING AND REFORTING

- Q( N 12.6.1. Station Oo' ratino Records 1,

Recoids and/or logs relative to the following items shall be kept in a manner conven%nt for review and shall be retained for at seast five years.

1.

- Records and periodic checks, inspection and/or calibrations performed to verify the surveillance requirements (See the applicable surveillance in the Instrumentation, Liquid Effluents, Gaseous Efflueats, and Radiological Environmenta! Monitoring Sections) are being met. All equipment failing to meet serveillance reluirements and the corrective action taken shall t:3 recorded.

2.~

Records of radioactive shipments.

2.

Records and/or logs relative to the f ~owing items shall be recorded in a manner i

convenient for review and shall be re shed for the life of the p! ant.

p 1.

Records of off-site environmental monitoring surveys.

s 2.

Reccrds of radioactNity in liquid cnd gaseous wastes released to *he en /ironment.

3.

Records of reviews performed for changes made to the ODCM.

h 176.2. Reports Y

1.

Radioactive Effluent Release Report Tne Radioactive Effluent Release Report covering the opennon of the unit during the previous 12 months of operatio, shall be submitted to the Commission prior to April 1 of each par. The report shallinclude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

The material provided sr.all be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR Part 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

2.

Annual Radiological Environmental Operatins Rescrt The Anr.uel Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall.re submitted prior to May 1 of each year. The report shall.nclude summaries, hterpretations. and ana!) sis of trends of the results of the Rvdiological Environmental Monitoring Program for the repor$.,g period. The material provided shall be consistent with the objectives in (1) the ODCM and (2) Sections IV.B.2., IV.B.3, and IV.C of Appendix i to 10 CFR Part 50. A detailed listing of the requirement of the report is giv3n below:

Mworddata\\odem\\dn12ri-6 doc 12-61

-_____________-.__________.-__.------------._______________________________________.----__________________________________J

DRESDEN Revtion 16 December 1997 12.6.2 Reports-(Cont'd)

(a)-

Results of environmental sampling summartzed on a quarterly basis following the format of Regulatory Guide 4.8 Table 1 (December 197ti),

(individual sample results will be retained at the station);

in the event that some results are not available for inclusion with the report, ths report shall be submitted noting and explaining the reasons for the n, ming results. Summaries, interpretations, and analysis of trends of the msults are to be provided.

(b)

An assessment n' the monitoring recults and radiation dose via the principal pathwa',s of exposure resulting from plant emissions of radioactivity including the maximum noble gas gamma and beta air doses in the unrestricted area. The assessment of radiation doses shall be performed in accordance with tr:s ODCM.

(c)

Results of the census to determine the locations of anstrals producing milk for human consumption, and the pasture season feedirsg practices at dairies in the monitoring program.

(d)

The reason for the omission if the nearest oairy to the staticn is not in the monitoring program.

(e)

An annual summary of meteorological conditions concurrent with the releases of gaseous effluents in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.

(f)

The results of the interlaboratory comparison program described in Section 12.5.3.

(g)

The results of the 40 CFR Pnrt 190 uranium fuel cycle dese analysis for each calendar year.

(h)

A summary of the monitoring program, including maps showing sampling locations and tables giving distance and direction of sampling locations from the station.

3.

Non-Routine Environmental Report (a)

If a confirmed measured radionuclide concentration in an environmental sampling medium averaged over any calendar quarter sampling period exceeds the reporting level given in Table 12.5-2 and if the radioactivity is attributable to plant operation, a written report shall be submitted to the Regional Administrator of NRC Regional Office, with a copy to the Director, Office of Nuclear Reactor Regulation, within 30 days from the end of the quarter. When more than one of the radionuclides in Table 12.5-2 are detected in the medium, the reporting level shall have been exceeded if IC/(RL), % equal to or greater than 1 where C is the concentration of the.' radioruJclide in the medium and RL is the reporting levei of radiont:lide i.

O h'\\worddatabdcmWn12rt 6. doc 12-62

l o..*

DRESDEN R:vtion 1.6 December 1997 12.6.2 Reports -(Cont'd)

(b)

If radionuclides other than those in Table 12.5-2 are detected and are due to plant efflugnts, a reporting levelis exceeded if the potential annual dose to an individual is equal to or greater than the design objective

foses of 10 CFR Part 50, Appendix 1.

(c)

This report shal! include an eva!uation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous affect.

12.6.3. Offsite Dose Calculation Manual (ODCM) 1.

The ODCM shall contain the methodology and parameters used in tha calculation of offsite doses due to radioacNe gaseous and liquid effluents and in the c

calculation of gaseous and liquid effluent monitoring Alarm / Trip setpoints and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Mcnitoring Programs described in Section 12.2 - 12.5 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Sections 12.6.2.1 and 12.6.2.2.

The ODCM shall t'e subject to review and approval by the Commission prior to initialimplemer% tion.

2.

Changes to the ODCM:

(1)

Shall be documented and records of reviews performed shd he retained as required by Technical Specification 6.14.A. This docurreNtion shall contain:

(a)

Sufficient information to support the change together v.ith tppropriate analyses or evaluations justifying the change (s); and (b)

A determination that the change will maintain the level of radioactive effluent control required by 10 CFR Part 20.1302,40 CFR Part 190,10 CFR Part 50.36a and Appendir I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dese or set point calculations.

(2)

Shall be effective after review and acceptance by the Cnsite Review &

Investigative Function and the appioval of the Station Manager, on the date specified by the Onsite Review and investigative Function.

t h:hvorddatabdcrMdn12ri 6 doc 12 63

DRESDEN R:: vision 1.6

.g l

Dec::mber 1997 l

l 12.6.3 Offsite Dose Calculation Manual (ODCMi-(Cont'd)

(3)

Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM or updated pages, if the Commission retains a controlled copy. If an entire copy of the ODCM is submitted, it shall be submitted as a part of or concurrent with the Radioactive Effluent Relesse Report for the period of the report in which any change 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 /yt.ar) me change was implemented.

12.6.4. Maior Chances to Radbactive Waste Treatrnent Systems (Liouid and Gaseous)

NOTE: This information may be submitted as part of the annual FSAR update.

1.

Licensee initiated major changes to the radioactive waste systems may be made provided:

The change is reported in the Monthly Operating Report for the period in which the evaluation was reviewed by the On-Site 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 Part 50.59; (2)

Sufficient detailed information to support the reason for the change; (3)

A detailed dercription of the equipment, components, and process involved and the interfaces with other plant systems; (4)

An evaluation of the change which shows the predicted retsases of radioactise materials in liquid and gaseous effluents that differ from those previously predicted in the license application and amendments; (5)

A comparison of the predicted releases oi radioactive materia!s in liquid and gaseous effluents to the actual releases for the period in which the changes were made; (6)

An estimate of the exposure to plant operating personnel as a result of the change; and (7)

Documentation of the fact that the change was reviewed and found acceptable by the On-Site Review and investicative Function.

2.

The change shall become effective upon review and acceptance by the On-Site Review and Investigative Function.

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ML20198M249

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