ML20056C744

Rev 0.M to ODCM Chapters 10,11 & 12 for Braidwood Station

ML20056C744
Person / Time
Site:	Braidwood
Issue date:	06/30/1993
From:	COMMONWEALTH EDISON CO.
To:
References
PROC-930630-01, NUDOCS 9307220294
Download: ML20056C744 (30)

Text

July 8,1993 Attached are the recent revisions to the Offsite Dose Calculation Manual's (ODCM Chapter 10,11, and 12 for Braidwood Station, as approved through Onsite Review.

These changes include containment purge setpoint factor modification, TLD location additions / clarifications, and general updating to Chapter 12 since the RETS have been removed from the Braidwood Station Technical Specifications. Please complete the following manual update:

Remove insert Braidwood Station Annex Braidwood Station Annex -

Chapter 10 Chapter 10 P. 10-1,10-4 P.10-1,10-4 '

Rev. 0.K Rev. 0.M Braidwood Station Annex Braidwood Station Annex Chapter 11 Chapter 11 P. 11-1, 11-3,11-4,11-5, P.11-i, 11-3, 11-4, 11-5, 11-15, 11-16 11-15, 11-16 Rev. 0.M Braidwood Station Annex Braidwood Station Annex P.12-i,12-ii,12-lii,12-iv,12-v, P.12-i,12-ii,12-iii,12-iv,12-v, 12-1, 12-5, 12-7, 12-8, 12-9, 12-10, 12-1, 12-5, 12-7, 12-8, 12-9, 12-10, 12-13, 12-15, 12-16, 12-19, 12-20, 12-13, 12-15, 12-16, 12-19, 12-20, 12-21, 12-22, 12-29, 12-30, 12-51 12-21, 12-22, 12-29, 12-30, 12-51 Revision 0.M YOUR SIGNATURE INDICATES YOU HAVE VERIFIED THAT YOUR CONTROL NUMBER IS CORRECT AND YOlU HAVE UPDATED YOUR MANUAL.

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REVISION 0.M: ?i ny JUNE 1993

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-BRAIDWOOD ANNEX-INDEX  !

PAGE REVISION CHARER 10 '

10-1 0.M 11 .O.K f

10-111 0.K ,

10-iv O.K 10-v 0. K -

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10-1' 'O.K-10-2 '

O.K 10-3 0.K 10-4 0.M . ,

10-5 O.K 10-6 0.K .

10-7 0. K ' 9 10-8 0K 10-9' . O.K ,

10-10 0.K 10 '

0.K~ '

10-12 0.K 10 0.K 10-14 0.K 10-15: 0.K:

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,s 10.1.3.1.2 Containment Purge Effluent Monitors t

k ~,,)

The setpoints are established at 1.50 times the analyzed containment noble gas activity during purge, plus the background reading of the monitor prior to purge.

10.1.3.1.3 Waste Gas Decay Tank Effluent Monitors The setpoints are established at 1.25 times the analyzed waste gas tank activity during release.

10.1.3.1.4 Component Cooling Water Monitors The setpoint is based on the radior.uclide mix in Table 10-1.

The total calculated detector response is divided by 2 to obtain the final setpoint. (See section 10.2.3.5 for the conversion factor).

10.1.3.2 Release Limits Alarm and trip setpoints of gaseous effluent monitors are established to ensure that the release rate limits of 10 CFR 20 are not exceeded. The release limits are found by solving Equations 10-1 and 10-2 for the total allowed release rate of' vent releases, Q,,.

(1.11)Q,, E {Kf,} s 500 mrem /yr (10-1)

Q,, { {(f,) [G(X/Q), exp(-1,R/3600u,)*

(10-2).

+ 1.11V,]) < 3000 rem /yr The summations are over noble gas radionuclides i.

f, Fractional Radionuclide Composition The release rate of noble gas radionuclide i divided by the total release rate of all noble gas radionuclides.

Q,, Total Allowed Releast Rate, Vent Release [pCi/sec)

The total allowed release rate of all noble gas radionuclides released as vent releases.

exp (-1,R/3600U ) is set equal to 1.0 for setpoint calculations.

4 1

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'r BRAIDHOOD~ REVISION 0.M

- JUNE 1993 BRAIDHOOD ANNEX INDEX .

P_A_G1 REVISIOP

' l'D CHAPTER 11

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Exposure Pathway

_3nd/or Samole Sampling or Type and Frequency Samolina or Monitorina Locationsa Collection Freauency of Analysis

2. Direct Radiation a. Lnner RingC Quarterly Gamma dose quarterly Inditalori q

BD-101-1, 0.6 mi N (1.0 km A) 80-101-2, 0.6 ml N (1.0 km A) 80-101-3, 0.5 mi N (0.8 km A)

BD-101-4, 0.5 mi N (0.8 km A) 80-102-1, 1.2 mi NNE (1.9 km B) 80-102-2, 1.1 mi NNE (1.8 km B) 60-103-1, 1.0 mi NE (1.6 km C) 8D-103-2, 1.0 mi NE (1.6 km C) 80-104-1, 0.7 mi ENE (1.1 km C) 80-104-2, 0.7 mi ENE (1.1 km D) 80-105-1, 1.5 ml E (2.4 km E) 80-105-2, 1.5 mi E (2.4 km E) 80-106-1, 1.7 mi ESE (2.7 km F) 80-106-2, 1.7 mi ESE (2.7 km F) 80-107-1, 2.0 mi SE L3.2 km G) 80-107-2, 2.0 mi SE (3.2 km G) 8D-108-1, 2.0 mi SSE (3.2 km H) 80-108-2, 2.0 mi SSE (3.2 km H) 80-109-1, 2.5 mi S (4.0 km J) 80-109-2, 2.5 mi S (4.0 km J)

BD-Il0-1, 1.8 mi SSH (2.9 km K) 80-110-2, l.8 mi SSH (2.9 km K)

BD-lila-1, 1.4 mi SH (2.2 km L)

BD-111a-2, 1.4 ml SH (2.2 km L)

BD-111b-1, 1.1 mi SH (1.8 km L)

BD-llib-2, 1.1 mi SH (1.8 km L) 80-112-1, 0.7 ml HSH (1.1 km M) 80-112-2, 0.7 ml HSH (1.1 km H) 11-3

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JUNE 1993 Table 11-1 (Cont'd)

Exposure Pathway and/or Samole Sampling or Type and Frequency Samulina or Monitorina Locationsa Collection Frequenny of Analysis

2. Direct Radiation 80-113a-1, 0.5 mi H (Cont'd) (0.8 km N)

BD-Il3a-2, 0.5 ml H (0.8 km N)

BD-Il3b-1, 0.4 mi W (0.6 km N) 80-Il3b-2, 0.4 ml H (0.6 km N) 80-114-1, 0.4 ml HNH (0.6 km P) 80-114-2, 0.4 mi HNH (0.6 km P) 80-115-1, 0.3 mi NH (0.5 km Q) 80-115-2, 0.3 ml ini (0.5 km Q)

B0-116-1, 0.4 ml NNH (0.6 km R) 80-116-2, 0.5 mi NNH (0.8 km R)

b. Outer Ring b Quarterly Gamma dose quarterly Indicators 80-201-1, 4.2 mi N (6.8 km A) 80-201-2, 4.2 mi N (6.8 km A)

BO-202-1, 4.8 mi NNE (7.7 km B)

B0-202-2, 4.8 mi NNE (7.7 km B) 80-203-1, 4.9 mi NE (7.9 km C) 80-203-2, 4.9 mi NE (7.9 km C) 80-204-1, 4.3 mi ENE (6.9 km 0) 80-204-2, 4.3 mi ENE (6.9 km 0) 80-205-1, 4.0 mi E (6.4 km E) 80-205-2, 4.0 mi E (6.4 km E) 80-206-1, 4.5 mi ESE (7.2 km F)

B0-206-2, 4.5 mi ESE (7.2 km F) 80-207-l, 4.1 mi ESE (6.6 km F) 80-207-2, 4.1 mi ESE (6.6 km F)

B0-208-1, 4.5 ml SSE (7.2 km H) 80-208-2, 4.5 mi SSE (7.2 km H) 11-4

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Table 11-1 (Cont'd) '

. Exposure Pathway and/cr Samolel Sampling or Type and Frequency

__lamolina or Monllorina Locationsa Collection Freaueary ~

of Analysis -

'2. Direct Radiation 80-209-1,. 4.8 ml S (Cont'd) (7.7 km J) 80-209-2, 4.8 nel S (7.7 km J) 80-210-1, 4.9 mi SSH (7.9 km K)

BD-210-2, 4.9 mi SSH. (7.9 km K)'

BD-211-1, 4.8 mi'SH (7.7 km L)

B0-211-2, 4.8 mi SH (7.7 km L) 80-212-1, 4.7 ml HSH - (7.6 km H) 80-212-2, 4.7 ml HSH - (7.6 km H) 80-212-3, 5.0 ml HSH (8.0 km H)

BD-212-4, 5.0 ml HSH (8.0 km H) 60-213-1, 4.5 ml H. - (7.2 km N)

BD-213-2, 4.5 ml H (7.2 km N) 8D-213-3, 4.8 mi.*H (7.7 km N) 80-213-4, 4.8 ml H. ( 7. ,' km N)

BD-214-1, 4.3 ml HNH (6.9 k.n P) 80-214-2, 4.3 mi HNH (6.9 km P)

BD-215-1, 4.5 ml NH BD-215-2, (7.2 km Q) 4.5 mi-NH - (7.7 km Q) 80-216-1, 4.4 mi NNH (7 I km R)

BD-216-2, 4.4 mi NNH (7.1 km R)

c. Soecial Interest. I; Quarterly Gamma' dose quarterly In!11141Qrl on each TLD.

Two TLDs.at each of the airborne pathway indicator locations specified in Parti 1 of this table.

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' REVISION 0.M

-JUNE-1993 BRAIDWOOD

,, -~

CHAPTER 12.0 SPECIAL NOTE ,.

The transfer of the Radiological Effluent Technical Specifications to the ODCM by Technical Specification, Amendment 35, dated April 13, 1992, was approved by the Nuclear Regulatory Commission.

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' REVISION'O.M-JUNE 1993 BRAIDWOOD BRAIDHOOD ANNEX INDEX EAGE REVISION

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. REVISION 0.M ]

JUNE'1993 BRAIDWOOD

/-~~. MIDM ANNEX INDEX

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12 - 52 9, 12 - 53 0.A 12 - 54 0.A 12 - 55 0.A 12 - 56 0.A 12 - 57 0.A 12 - 58 0.A 12 - 59 0.A 12 - 60 0.A I2 - 61 0.A n

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.. REVISION.O.M" n.

JUNE.1993-- i s- .

CHAPTER 12. N

' RADIO 4CTIVE EFFLUENT TECHNICAL. STANDARDS qd L-Ti (RETS)

TABLE OF CONTENTS PAGE  :

12.1 DEFINITIONS 12 ,

12.2 INSTRIMENTATION 12-5' 12.2.1 Radioactive Liquid' Effluent Monitoring' Instrumentation 12 >

12.2.2 Radioactive Gaseous-Effluent .

Monitoring Instrumentation .

12-10 t 12.3 LIQUID EFFLUENTS ~ 12-17?

12.3.1 Concentration 12-17 12.3.2 Dose 12 12.3.3 Liquid Radwaste Treatment System 12-25: i 12.4 GASEOUS EFFLUENTS 112-27 r a

12.4.1 Dose Rate 12 '

-12.4.2 . Dose - Noble Gases c 12-32' 12.4.3 Dose - Iodine-131 and 133. Tritium, ,

Lfe -and Radioactive Materialfin Particulate Form .12-34~

( 12.4.4 Gaseous Radwaste Treatment System 12.4.5 .12-36' Total' Dose 12-38

12.5 RADIOLOGICAL ENVIROWlENTAL MONITORING 40' 12.5.1- Monitoring Program-12.5.2 12 Land _Use Census 12.5.3 12 Interlaboratory Comparison Program 12-55 12.6 REPORTING REQUIRONENTS 12-56' 12.6.1 Annual Radiological Environmental Operating Report

+

12.6.2 12-56 Semiannual Radioactive _ Effluent Release Report 12-58 12.6.3 Offsite Dose Caculation Manual.(ODCM) 12.6.4 12  !

Major Changes to Liquid and Gaseous ~Radwaste Treatment Systems j 12-60 j

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' l REVISION!0.H!

, si-DJUNE71 993?

'i

'CHAPTERl12 I t RADIDACTIVE EFFLUENT-TECHNICAL' STANDARDS:

', J (RETS):

LIST OF TABLES fAGE 12.1-1 Frequency Notations

'

12-4; 12.2-1 u Radioactive Liquid Effluent Monitoring 1

Instrumentation .

. 12-6f 12.2-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements- 12-8; ,

12.2-3 Radioactive Gaseous Effluent Monitoring Instrumentation 12-11

' 12.2-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surve111ance' Requirements ,

14 12.3-1 Radioactive Liquid Haste Sampling and Analysis Program '

12- 19..

12.4-1. ' Radioactive Gaseous Haste: Sampling.and Analysis' Program- ~

29 .,

1

~- 12.5-1 Radiologica1' Environmental Monitoring Program ~ 12 c

- f 12.5-2 Reporting' Levels for. Radioactivity Concentrations I in Environmental Samples .

12-49 ' "

12.5-3 Detection. Capabilities for Environmental / Sample' ~

Analysis 12-50

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-  : REVISION.O.M l JUNE 1993 BRAIDWOOD i-

, ja 12.0- RADIOLOGICAL ENVIRONMENTAL TECHNICAL STANDARDS E! I' x_ / 12.1 DEFINITIONS O 12.1.1 Action shall be that which prescribes remedial measures required  :

under designated conditions.

12.1.2 Analoo Channel Ooerational Test shall be the ' injection of a simulated signal into the channel as close to the sensor as. ,

practicable to verify OPERABILITY of alarm,. interlock and/or trip functions. The ANALOG CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the alarm interlock and/or Trip Setpoints such that the Setpoints are within the required. range and accuracy.

12.1.3 Channel Calibration shall be the adjustment, as necessary, of the channel such that it responds within the' required range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip functions and may'be performed by any series of secuential, overlapping, or total channel steps such that the entire channel is calibrated.

12.1 4 Channel Check shall be the qualitative assessment of_ channel "

behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication .

s and/or status with other indications and/or status derived from

( ) independent instrument channels measuring the same parameter.

12.1.5 Dioital Channel Doerational Test shall consist of exercising the 2 digital computer hardware using data base manipulation and injecting simulated process data to verify OPERABILITY of alarm and/or trip functions.

12.1.6 Dose Ecuivalent I-131 shall be that connection of I-131 (microcurie / gram) which alone would produce the same thyroid dose-as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, .

r and I-135 actually present. The thyroid dose conversion f actors used for this calculation shall be'those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites".

12.1.7 Member (s) of the Public shall includ'e a11' persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors or vendors and ,

persons who enter the site to service equipment or to make deliveries. This category does include persor.s who use portions of the site for recreational, occupational, or other purposes not '

associated with the plant.

. f s, 12-1 t

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REVISION 0.M' l

- JUNE 1993 ,

BRAIDWOOD i 12.2 INSTRUMENTATION -

12.2.1 Radioactive Liquid Effluent Monitoring Instrumentation Onerability Reauirements 12.2.1.A The radioactive liquid effluent monitoring instrumentation .

channels shown in Table 12.2-1 shall be OPERABLE with their '

Alarm / Trip Setpoints set to ensure that the limits of 12.3.1.A are not exceeded. The Alarm / Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

Aeolicab111tv: At all times A.Ct10.0

1. Hith a radioactive liquid effluent. monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable. ,

2. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels'0PERABLE, take the ACTION shown in Table 12.2-1. Restore the inoperable .

instrumentation to OPERABLE status within the time specified

.O -

In the ACTION, or explain in the next Semi-annual Radioactive Effluent Release Report pursuant to Section 12.6 why this inoperability was not corrected within the time specified.

Surveillance Reavirements 12.2.1.B Each radioactive 11guld effluent monitoring instrumentation .

channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and DIGITAL and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 12.2-2.

Bases 12.2.1.C The radioactive liquid effluent instrumentation is provided to t monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCH to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR .

)

Part 20. The OPERABILITY and use of this instrumentation.is-consistent with the requirements of General Design Criteria 60, l 63, and 64 of Appendix A to 10 CFR Part 50.

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l 12-5

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- . REVISION 0.M

-JUNE 1993 BRAIDH000 TABLE 12.2-1 (Continued) 3 (\- ACTION STATEMENTS

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ACTION 31 - Hith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this t pathway may continue for up to 14 days provided that prior to initiating a release: '

a. At least two independent samples are, analyzed in accordance ,

with Section 12.3 and'

b. At least two technically qualified members of the facility-staff independently verify the release rate calculations 1and discharge line~ valving.

Otherwise, suspend release of radioactive effluents via this pathway. .

ACTION 32 - Hith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are. collected and analyzed for radioactivity at a lower limit of detection as specified in-Table 12.3-1.

ACTION 33 - Hith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this O pathway may continue for up to 30 days provided the flow rate'is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.during actual releases. Pump performance curves generated'in. place may be used to estimate ,

flow. ,

i ACTION 34 - With the number of channels OPERABLE less-than requirea by-the.

Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for radioactivity at a lower limit of detection as specified in Table 12.3-1:

a.

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT I-131. or b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the.

secondary coolant i; less than or equal to 0.01  :

microcurie / gram DOSE EQUIVALENT I-131.

9 12-7

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-REVISION JUNE.1993 0.H(\.

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TABLE 12.2-2 RADIOACTIVE LIOUID EFFLUENT HONITORING INSTRUMENTATION SURVEILLANCE REOUIR DIGITAL ANALOG CHANNEL CHANNEL INSTRUMENT CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL CHECK CHERE CALIBRATION TEST

. TEST

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release-

a. Liquid Radwas te Effluent Line (ORE-PR001) D P R(3)# Q(1) N.A.

b. Fire and Oil Sump Discharge (ORE-PR005) D M R(3)

~

Q(1) N.A.

c. Condensate Polisher Sump Discharge (ORE-PR041) D H R(3) Q(1)* N.A.

2. Radioactivity Monitors Providing Alarm But Not

-Providing Automatic Termination of Release

a. Essential Service Hater

1) Unit I a) RCFC IA and IC Outlet (IRE-PR002) D H. R(3)#

b) RCFC IB and 10 Outlet (IRE-PR003) Q(2) N.A.

D H R(3)# Q(2)- N.A.

2) Uni t 2 a) RCFC 2A and 2C Outlet (2RE-PR002) D H R(3)#

b) RCFC 28 and 2D Outlet (2RE-PR003) Q(2) N.A.

D H R(3)# Q(2) N.A.

b .- -Station Blowdown Line- (ORE-PRO 10) D H R(3)# Q(2) N.A.

3. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line (Loop-HX001) D(4) N.A. R# N.A. O

b. Liquid Radwaste' Effluent Low Flow Line ' 0 (g4 )

-(Loop-HX630) N.A. R N.A Q

c. Station Blowdown'Line.(Loop-CH032): D(4) N.A. .R NIA.

12-8 -Q

_ _ _ _ _ _ _ _ _ _ =_ _ _ _ - - , .

REVISION 0.M JUNE'1993 BRAIDWOOD

IA_DLE 12.2-2-(Continued)

TABLE NOTATIONS

,b V #The specified 18 month interval may be extended to 32 months for cycle 1 only.

(1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation '

occur if any of the following conditions exists:

a. Instrument indicates measured levels above th'e Alarm / Trip Setpoint,_

or

b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor-loss of power), or c -. Detector check source test failure, or

d. Detector channel out-of-service, or .

e. Monitor loss of sample flow. This is only applicable for ORE-PR001 and ORE-PR005. Honitor ORE-PR041 will not trip on loss of sample flow.

(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

/ a. Instrument indicates measured levels above the Alarm Setpoint, or

b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or

c. Detector check source test failure, or

d. Detector channel out-of-service, or

e. Monitor loss of sample flow.

(3) The initial CHANNEL CALIBRATION shall be performed using one_or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that t participate in measurement assurance activities with NBS. These ,

standards shall permit calibrating the system over its intended range cf energy and measurement range. For subsequent CHANNEL CALIBRATION,

eurces that have been related to the initial calibration shall be used. ,

(4)

CHANNEL CHECK shall consist of verifying indication of flow during periods of_ release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.

O 12-9

REVISION 0.M  ;

JUNE 1993-

~

, ,- BRAIDHOOD 12.2.2 .l Radioactive Gaseous Effluent Monitorina Instrumentation l Operability Reavirements ig)

V 12.2.2.A The radioactive gaseous effluent monitoring instrumentation channels shown in Table 12.2-3 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Section 12.4 are.not exceeded. The Alarm / Trip-Setpoints of these channels shall be determined.and adjusted in accordance with the methodology and parameters in the ODCM.

Aeolicability: As shown in Table 12.2-3 Action:

1. With a radioactive gaseous effluent monitoring-instrumentation channel Alarm / Trip Setpoint less conservative than required by the above section, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable.

2. With less than the minimum number.of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 12.2-3. Restore the inoperable instrumentation to OPERABLE status within the time specified  ;

in the ACTION, or explain in the next Semlannual Radioactive Effluent Release Report pursuant to Section 12.6 why this.

Inoperability was not corrected within the time.specified.

Surveillance Reautrements 12.2.2.B Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and DIGITAL and CHANNEL OPERATIONAL TEST at the frequencies shown in Table 12.2-4, Bases 12.2.2.C The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materidis in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm / Trip Setpoints for  ;

these instruments shall be calculated'and adjusted in accordance with the methodology and parameters in the 0DCM to ensure that ,

the alarm / trip will occur prior to exceeding the. limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is '

consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. The sensitivity of any noble gas activity monitor used to show compliance with the gaseous effluent release requirements of Section 12 4 shall be such that concentrations as low as 1x10-6 uCi/cc are measurable.

12-10

REVISION 0.M JUNE 1993

, ,-- BRAIDWOOD TABLE 12.2-3 (Continued)

'/ TABLE NOTATIONS k[ *At all times.

ACTION 35 - With the number ~of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 14 days-provided that prior to initiating the release:

a. At least two independent samples-of the tank's contents are analyzed, and b.

At least two technically qualified members of the facility staff independently verify the_ release rate calculations and discharge valve lineup.

Otherwise, suspend release of radioactive effluents:via this pathway.

ACTION 36 - With the number of channels OPERABLE less than reauired by the~

Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the' flow rate is estimated at least once-per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 37 - Hith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately. suspend PURGING of radioactive effluents via this pathway.

ACTION 3B - Not used.

ACTION 39 - Hith the number of channels OPERABLE less than required by the:

Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are-taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for radioactivity. within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 40 - Hith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as ~

required in Table 12.4-1.

ACTION al - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE tequirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> liquid-grab samples are collected-and analyzed for radioactivity at a lower limit of detection as specified in Table 12.3-1 gA 12-13 9

(G *q

\

R2VISIONO.U l' - -

s_ / _ -

f BkK10H000 JUNE 1993J V TABLE 12.2-4 (Continued) 4

' RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE R DIGITAL CHANNEL MODES FOR HHICH CHANNEL ' SOURCE CHANNEL FUNCTIQliAL UNIT OPERATIONAL SURVEILLANCE CHECK CHECK CALIBRATION TEST IS REOUIRED

2. Plant Vent Monitoring System - Unit 2 (Continued)

'c. Particulate Sampler (2RE-PR028C) D M R(3)##

• 3 Q(2)

d. Effluent System Flow Rate Measuring 0 -N.A. R##

• Device (LOOP-VA020) Q

e. Sampler Flow Rate Measuring Device D N.A. R## *

(2FT-PRl65) Q

3. Not Used

4. Gas Decay Iank System

a. Noble Gas Activity Monitor Providing Alarm and Automatic P P R(3)## Q(1)*

• Termination of Release (ORE-PR002A and 2B)

5. Containment Purge Systam-

a. Noble Gas Activity Monitor-Providing Alarm (RE-PR0018) D .P 'R(3)## ~ Q(2). *

b. Iodine Sampler (RE-PR001C) P P R(3)## N.A. *

c. Particulate Sampler (RE-PR001A)

P: P R(3)## N.A. *

6. Radioactivity Monitors Providing Alarm and Automatic Closure of Surge Tank Vent-Component Cooling Hater Line- .

~

(ORE-PR009tand'RE-PR009)- D M .R(3)##_ - Q(1)'

• 112-15

---*y w + , 3-w-- . e m - s-_ _ m- m

REVISION 0.H JUNE 1993 \

BRAIDWOOD TABLE 12.2-4 (Continued) p).

'l '

TABLE NOTATIONS At all times.

1. 1. The specified 18 month interval may be extended to 32 months for cycle 1 only.

(1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that 1

automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:

a. Instrument indicates measured levels above the Alarm / Trip Setpoint, or

b. Circuit failure (monitor loss of communications alarm only, detector loss of counts, or monitor loss of power), or

c. Detector check source test failure, or

d. Detector channel out-of-service, or

• e. Monitor loss of sample flow. Monitoring ORE-PR002A and 2B will not trip on loss of sample flow. This is only applicable for functional unit 6. ORE-PR009 and RE-PR009.

(2)

The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that O control room alarm annunciation occurs if any of the following conditions exists:

a. Instrument indicates measured levels above the Alarm Setpoint, or

b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or

c. Detector check source test failure, or

d. Detector channel out-of-service, or

e. Monitor loss of sample flow.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

r3 U

12-16

REVISION:0.M-BRAIDHOOD; LTABLE 12.3-1 RADI0 ACTIVE LIOUID HASTE SAMPLING AND ANALYSIS PROGRAM i

LOHER LIMIT. i MINIMUM. OF DETECTION j LIQUID RELEASE SAMPLING ANALYSIS .TYPEOFACTIVITYL (LLD)(I)

. TYPE' FREQUENCY FREQUENCY. ANALYSIS (pC)/ml). '!'

1. Batch Release P P Principal Gamma .5x10-7  !

Tanks (2) 'Each Batch Each Batch Emitters _'(3) y I-131 1x10 P H Dissolved and 1x10-5 ,

One Batch /M Entrained Gases i (Gamma Emitters)

P M H-3 1210 Each Batch Composite (4)  :

Gross Alpha 1x10-7

-P Q Sr-89, Sr-90 5x10 Os .Each Batch Composite I4}  !

Fe-55 1xib-6

2. Continuous N Principal Gamma (5) 5x10-7 ~

(6) (6) '

Releases Continuous Composite Emitters (3)

I-131 '1x10-6

a. Circulating M M Dissolved and 1x10 ,

4 Water Blowdown Grab Sample Entrained Gases ,

(Gamma Emitters)

b. Haste Water Treatment M

. Discharge to Continuous (6) Composite (6) H-3 1x10-5 Circulating- 1

-Water Discharge Gross Alpha 1x10-7 ,

c. Condensate Q Sr-89, Sr-90 5x10-8 l

Polisher Sump continuous (6) Composite (6)

O ,

Discharge - ,. Fe-55 1x10 ,

12-19

,m

REVISION 0,M ,

JUNE 1993-

,, BRAIDN000- i

~

TABLE 12.3-1 (Continued)'

i

RADIDACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM  !

i LOWER / LIMIT-MINIMUM.

LIQUID RELEASE SAMPLING ANALYSIS OFDET{gJION ,-

TYPE OF ACTIVITY (LLD).

TYPE FREQUENCY' -FREQUENCY ANALYSIS -(pC1/ml)~  ;

3. Continuous' WI7) HI7) Principal Gamma. 5x10-7 Release (5) Grab Sample Emitters (3)"

. Essential ,

~ Service Water

• Reactor Containment Fan' Cooler (RCFC)

Outlet Line '

I-131 1x10-6 ,

Dissolved and:

O Entrained Gases (Gamma' Emitters) 1x10-5 H-3 -1x10-3:

4.. Continuous Principal Gamma -5x10-7 Surge Tank Emitters.(8): .

None None Vent-Component Dissolved and Cooligg) water Entrained Gases (8) 1x10-5 Line ,

(Gamma Emitters)

I-131 1x10-6 i L

4 L

e 12-20

I" 'hn olun U.M j

,BRAIDWOOD ~ JUNE 1993

. j

~ TABLE 12.3-1 (Continued) ,

fY TABLE NOTATIONS' (1) The LLD is defined, for purposes of these. sections, 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 "real" signal.

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

LLD - 66s b

E

• V = 2.22 x 106 . y , e x p (-la t )

Where:

LLD - the lower limit of detection (microCuries per unit mass or volume), ,

sb - the standard deviation of the background count'ing rate or of the counting rate of a blank sample as appropriate (counts per minute),

E = the counting efficiency (counts per disintegration),

(~}

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

2.22 x 10 6 - the number of disintegrations per minute per microcurie, Y - the fractional radiochemical yleid, when applicable, A - thp),

(sec - radioactive and decay constant for the particular radionuclide at - the elasped 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.

(

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

(2) A batch release is the discharge of liquid wastes of afdiscrete volume. . Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in.the ODCM to' assure representative sampling.

O U ..

12-21

~ -- -

. REVISION:0.M= .,,

, BRAIDWOODL JUNE'1993 3.- l

~

TABLE 12 3-1 (Continued);

- TABL E - NOTATIONS -

-(3) The principal. gamma emitters for which the LLD specification applies-include'the following radionuclides: .-Hn-54,.Fe-59, Co-58,;Co-60,=

2n-65, Ho-99, Cs-134. Cs-137,.Ce-141, and Ce-144 This: list does not~ _. y mean that'only these nuclides are-to be; considered, 0ther.' gamma peaks . ,

that are identifiable,:together with^those of the above nuclides, shall also'be_ analyzed and reported in the Semiannua1' Radioactive Effluent Release Report pursuant to Section 12.6.2 in the-format outilned in.

Regulatory Guide 1.21, Appendix lB, Revision'1. JuneL1974; (4) A composite sample.is one in which th'e' quantity of_11guld. sampled-is. s proportional to:the quantity of 11guld waste _ discharged and in which the method of sampling employed results.in a' specimen that'is representative'of the liquids released. :1 r

(5) A continuous release is'the 11scharge:of: liquid 1 wastes'of a:nondiscreteL volume, e.g., from a volume of a' system that has anfinput flow during..

the continuous; release.

(6) To be representative of the quantities and concentrations of

~

radioactive materials in liquid effluents, samples-shall be. collected continuously in proportion to the rate of flow:of'the effluent ~ stream.  ;

Prior to analyses, all samples taken-for the composite.shall'be ~

thoroughly mixed in order for the composite sample to be representative  ;

of the effluent release. '

O

-. t (7) Not required unless the Essential. Service Hater RCFC Outlet Radiation MonitgrsRE-PR002 andre-PR003indicatesmeasuredlevelsigreaterithan j

l 1x10- pCi/mi above background at any time during the ' week.

l ,

(8) . .

The principal gamma emitters for which the LLD specification applies 2

include the following radionuclides:.Kr-87,-Kr-88, Xe-133, Xe-133m,- 4 J

Xe-135, and Xe-138 for dissolved and entrained _ gases and Hn154 Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137,' Ce-141,'and Ce-144 for principal gamma emitters. This list does not mean that only thes.e.- i nuclides are'to be considered. Other gamma peaks.that are ' -  ;

identifiable,'together with those of-the above nuclides, shall also~bei  !

analyzed and reported in the Semiannual ~ Radioactive-Effluent Release Report pursuantLto.Section 12.6.2, in'the format ~ outlines in' Regulatory Guide 1.21, Appendix B, Revision 1 June _1974.

(9) A continuous. release is the discharge of dissolved and entrained  ;

gaseous waste from a nondiscrete liquid volume.

j 1 12-22

.. i,

REVISION 0.M7 b

• M. k" JUNE 1993' -

BRAIDWOOD TABLE 12.4-_1 RADIOACTIVE GASEOUS HASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM SAMPLING ANALYSIS LOHER LIMIT 0F TYPE OF DETECTION (LLD)CI)

GASEOUS RELEASE TYPE FRE00ENCY FRE00ENCY ACTIVITY ANALYSIS (uCl/cc)

P P 'l ~

1. Haste Gas' Decay EachiTank' Each Tank Tank Principal Gamma Emitters (2) 1x10-4 Grab Sample P P

2. Containment Purge Each Purge (3) Each Purge (3) Principal Gamma Emitters (2) 1x10-4 Grab Sample H-3 1x10-#

3.. Auxillary Bldg. M(4)(S) Principal Gamma Emitters (2)

Vent Stack Grab Sample M 1x10-4 (Unit I and 2) H-3 1x10-#

Continuous (6) g(7) I-13I 1x10-12 Charcoal Sample I-133 1x10-lu Continuousibi H '>

i Principal Gamma Emitters"#

Particulate 1x10-ii Sample.

Continuoust03 Mi '# -_ Gross Alpha Composite 1x10-'8 Particulate Sample

• Continuousib> .Q Sr-89, Sr-90 Composite l x 10-l i' Particulate Sample Continuous Noble Gas Monitor'. Noble Gases-Gross Beta or 1x10-b Gamma 12-29

-- REVISION O.M i

• + BRAIDHOOD JUNE 1993 m j

TABLE 12.4-1 (Continued) i TABLE NOTATIONS f)

() (1) The LLD is defined, for purposes of these specifications, as the~

smallest concentration of radioactive material in a sample that will  !

yield a net count, above system background, that will be detected.with 95% probability with only 5% probability of falsely concluding that a- ~

blank observation represents a "real" signal.

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

LLO -- 4.66s b

E V 2.22 x 106 . y . exp (-Aot)

Whe,e:

LLD - the lower limit of detection (microCuries per unit. mass or volume),

sb - 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 106 - the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield' when applicable,

.(sec A - thy),

- radioactive and decay constant for the particular radionuclide at - the elasped 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.

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

(2) The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Hn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131 Cs-134., Cs-137, Ce-141, and Ce-144 in ,

iodine and particulate releases. This list does not mean that only these nuclides are,to be considered.

4 12-30

-s -

z REVISION 0.M-BRAIDHOOD JUNE 1993 4 *-

TABLE 12.5-3 (Continued)

TABLE NOTATIONS n

( ,)! '

(1) This list does not mean that only these nuclides are 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 pursuant to Section 12.6.1.

(2) Required detection capabilities for~thermoluminescent dosimeters used for environment measurements shall be in accordance with the-recommendations of Regulatory Guide 4.13.

(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 "real" signal.

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

.66s LLD - b Ea V = 2722

• Y a exp (-Aot) l.

Where:

,-~s

( LLD - the "a priort" lower limit-of detection (picoCuries per unit

- v) mass or volume),

P sb - 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 - the number of disintegrations per minute per picocurie, Y - the fractional radiochemical yield, when applicable, A - thp),

(sec - radioactive and decay constant for the particular radionuclide .

at - the elasped 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

/'~N limit representing the capability of a measurement system and not as~an after the fact limit for a particular measurement.

b .

12-51