Text

Rev 4 to Odcm
	ML20058B674
Person / Time
Site:	Comanche Peak
Issue date:	10/22/1990
From:	Woodlan D; TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	;
References
	PROC-901022, NUDOCS 9010300379
	Download: ML20058B674 (23)
	v • d • e

..

l"l1UELECTRIC CPSES# 9023943 i

Log # TUS 90392 OFFICEAfEA10RANDUh1 File # 953

\\

October 22, 1990 i

)

I TO:

All Copy Holders COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

J REVISION 4 TO THE CPSES OFFSITE DOSE CALCULATION MANUAL (ODCM)

Enclosed is Revision 4 to the CPSCS Offsite Dose Calculation Manual (ODCM) and a receipt acknowledgement sheet.

Please page check your assigned copy of the ODCM against the updated Effective Page Listing (EPL) which is included with Revision 4.

Return the acknowledgement sheet as specified.

If you have any questions regarding the ODCM, contact Greg Bell at (214) 812-4373.

D. R. Woodlan Docket Licensing Manager GLB/grp Enclosure l

1 1-l l Vl M*32MEE $8$8[$gs e

L 3o2-9 L

i

(~'s COMANCHE PEAK STEAM ELECTRIC STATION d

0FFSITE DOSE CALCULATION MANUAL INSTRUCTION SHEET The following instructional information is being furnished to help insert Revision 4 into the Comanche Peak Steam Electric Station ODCM.

In accordance with CPSES Technical Specification 6.14b, ODCM Revision 4 became effective when it was approved by the Vice President, Nuclear Operations on October 9, J

1990.

Discard the old sheets and insert the new sheets as indicated below.

Holders of the CPSES ODCM should keep these instruction sheets in the front of the Effective Page Listing as a record of the changes, until a new listing is issued.

Remove Insert Part I 1 3/4-9 through 11 I 3/4-9 through 11 1 B 3/4-6 through 12 1 B 3/4 6 through 11

)

Part 11

!! 2 2 11 2-2 11 2 5 11 2 5 11 2-7 11 2-7 EPL I-l through EPL 11-4 EPL-1 through EPL-8 l

'3" O

O U,

=~

TABLE 3.3-8 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS

-INSTRUMENT OPERABLE APPLICA81LITY ACTION 1.

WASTE GAS HOLDUP SYSTEM

a. Noble Gas Release Rate Monitor - Providing Alarm and Automatic Termination of Release

[XRE-5570A & XRE-55708 (effluent release rate channel)]

1/ stack 34 2.

PRIMARY PLANT VENTILATION

a. Noble Gas Release Rate Monitor 1

[XRE-5570A & XRE-55708 L

(effluent release rate channel)]

1/ stack 36

b. Iodine Sampler (WRGM sample skid) 1/ stack 37

c. Particulate Sampler

. 1/ stack 37

d. Sampler Flow Rate Monitor, SMPL Flow 1 (X-RFT-5570A-1, 4

X-RFT-55708-1) 1/ stack 35 4

RE g 5.

hi ".:.

'8

_h O

i TABLE 3.3 8 (Continued) l (G '

TABLE NOTATIQM

At all times.

- During Batch Radioactive Releases via this pathway.

ACTION 34-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 provided i

that prior to initiating the release:

a.

The auxiliary building vent duct monitor (XRE-5701) is confirmed OPERABLE, or r

b.

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

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 s

this pathway.

ACTION 35-With the number of channels OPERABLE less than required by 4

the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the sample h7 flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 36-With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that:

(a) A Plant Vent Noble Gas Activity Monitor (XRE 5570A, XRE-5570B (low range activity) or XRE-5567A, XRE-55678) is OPERABLE, and the plant vent flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or i

(b)ThePlant flow Rate Monitor, PROC FLOW N 4

(X-FT 5570 X-FT 55708 1), is OPERABLE, and an alternate Vent Noble Gas Activity Monitor is OPERABLE (X w oS67A, XRE 55678) or grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or (c) The plant vent flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , and grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 37-With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent (d

releases via the affected pathway may continue provided

~N samples are continuously collected with auxiliary sampling equipment as required ~ in Table 4.11-2.

I 3/4-10 Revision 4 October 22, 1990

d TABLE 4.'.)

v'

~

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG DIGITAt CHANNEL UIANNil CHANNEL SOURCE CHANNEL OPERATIONAL OP[RAll0NAL INSTRUMENT CHECK CHECK CAlfBRATION TEST TEST 1.

WASTE GAS HOLDUP SYSTEM a.

Noble Gas Release Rate Monitor -

Providing Alarm and Automatic Termination of Release

[XRE-5570A, XRE-55708 (effluent

-release rate channel)]

P P

R(3)

N.A.

Q(1) 2.

PRIMARY PLANT VENTILATION a.

Noble Gas Release Rate Monitor

[XRE-5570A, XRE-55708 (effluent release rate channel))

D R(3)

N.A.

Q(2) w b.

Iodine Sampler p

(WRGM sample skid)

W(4)

N.A.

~

c.

Particulate Sampler (WRGM Sample Skid)

W(4)

N.A.

d.

Sampler Flow Rate Monitor, SMPL Flow 1 4

(X-RFT-5570A-1,X-RFT-55708-1)

D N.A.

R Q

N.A.

4 55.

Sin

'8

.,h G

O

RADI0 ACTIVE EFF!tig(I}

BASES

\\ q; L

3/4.11.2 -GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This control is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10CFR20 to UNRESTRICTED AREAS.

The annual dose limits are the doses associated with the concentrations of 10CFR20 Appendix B Table !!, Column 1.

These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Table II of 10CFR20, Appendix B (10CFR 20.106(b)).

For MEMBERS OF THE PUBLIC who may at times be within the SITE I

BOUNDARY, the occupancy of that W.C ER OF THE PUBLIC will usually be

-sufficiently. low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.

The methodology for calculating doses for sucn MEMBERS OF THE PUBLIC shall be given in the 00CM.

The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates abo n background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/ year to the whole body or to less than or equal to 3000 mroms/ year to the skin.

These release rate limits also restrict, at all times, the corresponding thyroid dose rate dove background to a child via the inhalation pathway to less than or equa!

~

'to 1500 mrems/ year.

'This control applies to the release of radioactive materials in gaseous-effluents from all units at the site.

.The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection'(LLDs).

Detailed discussion of the LLDs and other detection limits can be found in Currie, L. A., " Lower Limit-of Detection Definition and Elaboration of a Proposed Position for Radiological Effluent' and Environmental Measurements."

NUREG/CR-4007 (September.1984), and in' the HASL Procedures Manual, HASL-300.,

f i

a j

h COMANCHE PEAX - UNIT 1 I B 3/4-6 Octobar 22, 1990 J

e y

',Ti e

t v-

RADIOACTIVE EFFLUENTS BASES

V 3/4.11.2.2 DOSE NO9LE GASES This control is provided to implement the requirements of Sections II.B.

Ill.A and IV.A of 10CFR50, Appendix 1.

The control implements the guides set forth in Section 1.8 of Appendix 1.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix ! to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix ! be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the 00CM for cciculating the doses due to the actual release rates of the radioactive noble gases in gaseous effluents are consistent with the methodology provided in. Regulatory Guide 1.109, " Calculation of Annual Dose to Man from Routine Releases of Reactor Ef fluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix 1," Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in

'y ~

Routine Releases from-Light Water Cooled Reactors," Revision 1, July 1977.

The ODCM equations provided-for determining.the air doses at and beyond the SITE B0UNDARY are based upon the historical average atmospheric conditions.

l~ j This control applies to the release of radioactive materials in gaseous d" '

effluents from each unit-at the site.

For units with shared radwaste treatment systems, the gaseous effluents from the shared system are 1

proportioned among the units sharing that *ystem.

1 1.

(:

p l

J' l COMANCHE PEAK - UNIT 1 I B 3/4 7 October 22, 1990 x

1 e

a a

.1 RADI0 ACTIVE EFFLUENTS j -

BASES 3/4.ll a.3 DOSE - 10 DINE 131. 10 DINE 133. TRITIUM. AND RADIOACTIVE MATERig IN PARTLCULATE_M This control is provided to implement the requirements of Sections !!.C,

!!!. A. and IV. A of 10CFR50, Appendix 1.

The Controls are the guides set forth in Section II.C of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV. A of Appendix 1 to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable " The 00CM calculational methods specified in the Surveillance Requirements implement the requirements in Section !!I.A of Appendix I that conformance with the guides of Appendix ! be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of 1

Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimat.ing Atmospheric Transport and Disperston of Gaseous 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 historical average atmospheric conditions.

The release rate specification for lodine 131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater.than 8 days is dependent upon the existing radionuclide L

. pathways to man in the areas at and beyond the SITE BOUNDARY.

The pathways that were examined in the development of the calculations were:

(1)

-individual. inhalation of airborne radionucludes, (2) deposition of radionuclides onto green leafy utgetation with subsequent consumption by man, (3) deposition onto grassy areas where. milk animals and meat producing animals-graze with. consumption of the milk and meat by man, and'(4) deposition on the ground with subsequent ~ exposure of man.

s 0

This-control applies to the release of radioactive' materials in gaseous l

effluents from each unit at the site.

For units with shared radwaste.

y

- treatment systems, the gaseous effluents from the shared system are t

- proportioned among the units ~ sharing that system.

4j.,

4 h

COMANCHE PEAKL-UNIT 1

'! B 3/4-8 October 22, 1990 s

a

l L

\\

~

RADI0 ACTIVE EFFLUENTS l

BASES

)

3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM l

Th.7 OPERABILITY of the WASTE GAS HOLOUP SYSTEM and the PRIMARY PLANT l

l SYSTEM snsures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment.

The requirement that the appropriate protions of these systems be used, when

)

specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR 50.36a',

General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section 11.0 of Appendix ! to 10 CFR Part 50.

The specified limits governing the use of appropriate portions of the systems were i

specified as a suitable fraction of the dose design objectives set forth in Sections II.B and !!.C of Appendix I,10 CFR Part 50, for gaseous effluents.

This control applies to the release of radioactive materials in gaseous effluents from each unit at the site.

For units with shared Radwaste Treatment Systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

i h

COMANCHE PEAK - UNIT 1 I B 3/4 9 October 22, 1990 l

~

W !0 ACTIVE EFFLUENTS m rs y

3 4.11.4 TOTAL DOSE i

This control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The control recuires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to rattiation from i

uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

For sites ccntaining up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives'of Appendix 1, and if direct radiation doses from the units (including outside storage tanks, etc.) are kept small.. The Special Report will describe a course-of action that should result in the limitation of the annual dose to a MEMBER OF _THE PUBLIC to within the 40 CFR Part 190 limits.

For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radious of 8 km must be considered.

If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190,_the Special Report with a request for a

. variance (provided the release conditions resulting in violation of 40 CFR j

Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405(c), is considered to be a timely request t]

and fulfills the requirements of 40 CFR Part 190 until NRC staff action is

\\

completed.

The variance only relates to the limits of 40 CFR Part 190, and 1

t does not apply-in any way to the other requirements for dose limitation of 10 I

CFR Part 20, as addressed in Controls 3.11.1.1 and 3.11.2.1.

An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

L L

1 L

l i]

COMANCHE PEAK - UNIT 1 I B 3/4-10 October 22, 1990 n

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ^ - -

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The Radiological Environmental Monitoring Program required by this control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of MEMBERS OF THE PUBLIC resulting from the plant operation. This monitoring program implementsSection IV.B.2 of Appendix ! to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measureable concentrations 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, Revision 1 November 1979.

The initially specified monitoring program will be effective for at least the first 3 years of commercial operation.

Following this period, program changes may be initiated u

based on operational experience.

t The required detection capabilities for environmental sample analyses are v

tabulated in terms of the lower limits of detection (LLDs).

The LL0s required by Table 4.12-1 are considered optimum for routine environmental measurements in industrial laboratories.

It should be recognized that the LLD is defined-as, an a nig.ti (before the fact) limit representing the capability of a measurement system.and not as an A nosteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLO, and other detectit-.imits, can be found in Currie, L. A., " Lower Limit of Detection:

Definition and Elaboration of a

~

l Proposed Position for Radiological Effluent and Environmental Measurements,"

L NUREG/CR 4007 (September 1984), and in the HASL Procedures Manual, HASL 300.

g l

3/4.12.2 LAND USE CENSUS

.i This control-.is provided to~ ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the u

Radiological Environmental Monitoring Program given in the 00CM are made-if.

L required by the results of this census.

The best information from the door-to door survey, from. aerial survey or from consulting with-local agricultural L

L

- authorities shall be used. This census satisfies the requirements of Section 1

IV.B.3 of Appendi l

. greater than 50 m'g I to 10 CFR Part 50.

Restricting the census.to gardens of.

provides assurance.that significant exposure pathways via leafy vegetables will be-identified and monitored since a garden of this size is-the minimum required to produce the' quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for. consumption by a child.. To determine this minimum garden size, the following assumptions were made:

(1) 20%:of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m2 COMANCHE PEAK, UNIT 1 I B 3/4-11 October 22, 1990 l:

\\

b 5

.- -o

l j

RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the esults are valid for the purposes of Section IV.B.2 of Appendix ! to 10 CFR Part 50.

L (7

yJ l

t e

7,,

fy,)-

COMANCHE PEAK UNIT 1 I B 3/4 12 October 22, 1990 4

The WRGMs are designated as monitors XRE-5570A and XRE 55708 for n

Stacks A and B, respectively.

Each WRGM consists of a low range kJ (10*7 to 10-1 uCi/cc), mid range (10 4 to 102 uCi/cc), and high range (10-1 to 105 uti/cc) noble gas activity detector.

The 4

WRGMs also have an effluent release rate channel which uses inputs from the appropriate WRGM noble gas activity detectors and the plant vent stack flow rate detectors (X-FT-5570A 1/B 1) to provide an indication of noble gas release rate in uCi/sec.

Alarm setpoints are established for the WRGM effluent release rate channel to fulfill the requirements of Radiological Effluent Control 3/4.3.3.5.

Exceeding the WRGH effluent release rate cht.nnel high alarm setpoint also initiates automatic termination of Waste Gas Decay Tank releases.

The stack PIGS are designated as particulate channels XRE-5568A and XRE-5568B, iodine channels XRE-5575A and XRE-55758, and noble gas channels XRE-5567A and XRE-5567B for Stacks A and B, respectively.

The stack PIG noble gas channels may be used as a back-up to the WRGM when no automatic control functions are required. Therefore, a methodology is provided for calculating the PIG noble gas monitor setpoints. Additionally, methodologies are provided for calculating setpoints for the PIG particulate and iodine channels, although these channels are not required by the Radiological Effluent Controls Program.

Other monitors that may be used for effluent monitoring and control 4

are the Auxiliary Building Ventilaticn Duct Monitor, XRE-5701, and-the y

. Containment PIG Noble. Gas Monitor,1RE-5503.

XRE-5701 may be used to monitor Waste Gas Decay Tank releases by monitoring the Auxiliary Building Ventilation Duct..XRE-5701 also provides the automatic control' function for termination of Waste Gas Decay Tank releases.

IRE-5503 monitors the Containment atmosphere and provides the only automatic control function for termination.of Containment vents or t

. purges.

b;O 11.2-2 Revision 4 October 22, 1990 m

~

l Fc = The continuous flow rate contribution of each plant stack (cm3 sec).

These flow rates

/

are measured directly in each plant vent stack (X-FT 5570A 1/B-1).

l4 XiB = The concentration of radionuclide i in the batch release as sampled in accordance with Radiological Effluent Control 3/4.11.2.1, 4

Table 4.11-2.

These samples are taken prior to release from the confinement to be released.

FB = The estimated flow rate contribution associated with the release of the batch source (cm3 sec)

/

1/2 = factor to account for distribution of the batch release to each plant vent stack, assuming uniform distribution of the batch release between both stacks. (unitiess)

NOTE:

If there is no batch release source, fa and XiB are zero, and X y = X c-i i

[O The flow rate at each plant vent, Fy, is given by:

1 Fy Fe + (1/2) FB

[Eq. 2-5]

NOTE:

If there is no batch release source, FB is zero, and Fv = fc.

2.1.2 Plant Vent Stack Noble Gas Activity Monitor.1 XRE 5570A/B flow rance noble cas activitvi and XRE 5567A/B These channels may be used for establishing noble gas activity setpoints when no^ automatic control functions are required by Radiological Effluent Control 3/4.3.3.5.

The alarm setpoint for, these channels will be calculated'using' Eqs. 2-6 and 2-7. _ These g

calculations will be performed for each plant vent stack.

.' X 500 x SF x AF =

CV (Eq. 2-6) gy O

t t

Cg = the lesser of-<

X 3000 x SF x AF =

CV

[Eq. 2-7]

gy D,

s 11 2-5 Revision 4 October-22, 1990

+

2,1.3 Plant Vent Effluent Release Rate and Samnle Flow Rate Monitors A.

Plant Vent Stack Release Rate Monitors XRE-5570A/B-(Effluent Release Rate Channel)

The WRGM effluent release rate channels monitor the 4

release rate of radioactive materials from each plant vent stack by combining inputs from the WRGM noble gas activity channel (uti/cm3) indication and a stack flow rate (cm3 sec) indication (X-FT-5570A-1/B 1) to yield an

/

effluent release rate (uti/sec).

By establishing an alarm setpoint for this monitor, an increase in either the noble gas activity or stack flow rate will cause an alarm trip.

The WRGM effluent channel also provides an automatic control function for termination of Waste Gas Decay Tank Releases.

The setpoint for each plant vent effluent release rate monitor will be calculated using Eq.

2-8.

This calculation will be performed for each plant vent stack.

l Cr - Co Fv

[Eq. 2-8]

where:

Cr - The setpoint for each plant vent stack effluent release rate monitor.

(uCi/sec)

All other terms are previously definesi.

![

B.

Samnler Flow' Rate Monitors (X-RFT-5570A-1/B-1) 4 The WRGMs are designed to sample isokinetically from the plant vent stacks.

Isokinetic-sample. flow is maintained automatically by the monitor microprocessor.- The sampler "i

flow rate monitors are designed such that if there is a A

p-loss of sample' flow, the stack monitor automatic control 3

functions are initiated. The loss of sample flow alarm-setpoints are established permanently in accordance with' L

vendor specifications.

I h

i 11 2-7 Revision 4 October 22, 1990 w

i CPSES - ODCM List of Effective Pages Preface The Effective Page Listing (EPL) provides a tabulation of the current pages in the CPSES ODCM, Each page in the CPSES ODCM is identified with a page number, including pages that contain tables or figures.

A revision number and date are included on each page. The revision number and date are changed when the change represents a substantive revision to the information that is provided on the page.

If the page is revised or reprinted but the revision is not considered substantive (i.e., it is an editorial correction), the revision number vill not be changed, but will have the reprint date.

Since the EPL may not b'e updated with each revision, an Instruction Sheet (s) 4 will be provided for subsequent revisions of the CPSES ODCM; it should be retained immediately in front of the EPL.

To identify the effective revision level of a page in the CPSES ODCM, check these Instruction Sheets first and, if not found,.the EPL second.

If any effective page cannot be found, notify TV Electric Nuclear Licensing and the required effective pages will be provided.

Contact may be made by phone (214/812-8873)-or by mail. A marked up copy of pages from the

(

Instruction Sheets or the EPL is a convenient way to identify the required pages.

i i

I EPL-1 October 22,'1989

._7 CPSES ODCM i

Effective Page Listing 9

j Pace No.

Revision No.

TABLE OF CONTENTS i

2 11 1

i iii 0

iv 1

y 1

vi 0

vii 0

viii 0

ix 0

x 0

xi 1

xii 0

xiii 1

PART I Il0 0

I l-1 0

-]

I l-2 0

Il3 0

1 1-4 0

Il5 0

I l-6 0

1 2-0

'l I3/4-0 0-1 3/4-1 0

13/4 0' I'3/4-3 0

1 3/4-4 0

t I3/4-5 0

-I 3/4 0-I3/4-7 0

I 3/4-8_

1 I 3/4-9 4-I3/4-10

~4

't

\\

O EPL-2 October 22, 1989

CPSES ODCM j]

Effective Page Listing i

Paae No.

Revision No.

PART I-1 I 3/4-11 4

I 3/4-12 0

1 3/4 13 0

1 3/4-14 0

I 3/4-15 0

1 3/4-16 0

I 3/4-17 0

I 3/4-18 3

I 3/4-19 0

I 3/4-20 3

I 3/4 21 0

I 3/4 22 1

I 3/4 22a 2

I 3/4-22b 2

.I 3/4-23 0

1 3/4-24' 1

I 3/4 25 0

I 3/4-26 0

.h I 3/4-27 0

~'

I 3/4-28 0

I 3/4-29 0

1 3/4-30 0

I 3/4-31 0

.I 3/4-32' 0

I 3/4-33' 0

11-3/4-34 0

1 3/4.

0

.I 3/4-36 (rev. bar was inadvertently omitted) 1 I 3/4-37.(rev. bar.was inadvertently omitted) 1 I 3/4-38 (rev, bai was inadvertently omitted) 1 I 3/4-39 0

1 3/4-40 0

.I 3/4-41 0

1 3/4-42 (rev. bar should be deleted) 0 I 3/4-43 0

I.3/4-44 1

o -

I 3/4-45:

0 4

.)

EPL-3 October 22, 1989

e

't CPSES ODCM Effective Page Listing Paae No.

Revision No.

PART I I B 3/4 0 1

1 B 3/4-1 0

I B 3/4-2 0

I B 3/4-3 0

1 B 3/4-4 2

I B 3/4-5 2

I.B 3/4-6 Oct. 22, 1990 I B 3/4-7 Oct. 22, 1990 I-B 3/4-B Oct. 22, 1990 1 B 3/4-9 Oct. 22, 1990 I B 3/4-10 Oct. 22, 1990 1 B 3/4 11 Oct. 22, 1990

.I B 3/4-12 Oct. 22, 1990 I 5-0 (no revision no. & no date)

I 5-1 0

L I-5-2 0

g I 6-0 (no revision no. & no date)

I 6-1 o

I.6-2 0

I63

-1 1 6-4 o

4 i

i.

l..

l EPL-4 October 22, 1989-

~

=

CPSES ODCM Effective Page Listing Page No.

Revision No.

PART II

!! l-1 0

11 1-2 1

11 1-3 1

11 1-4 1

1 11 1-4a 1

11 1-5 0

11 1 6 0

!! l-7 0

11 1 8 0

11 1 9 0

11 1-10 0

11 1-11 0

11 1-12 0

11 1-13 0

11 1-14 0

11 1-15 0

Il 1-16 1

11'1-17 1

[d N

11 1-18 0

11 1 0 Il 1 0 11 1-21 O

11 1-22 3

11 1-23 0-II l-24 0

11 1-25 0

+,

II 2-1:

0 II 2-2' 4

11 2-3' 0

'11'2-4 0

11 2 5

-4 11 2-6 0

11 2 7 4

11 2-8 0

t

=11 2-9 0

o Av q

EPL-5 October 22, 1989

N CPSES ODCM X'

Effective Page Listing V

Paae No.

Revision No.

PART II i

11 2-10 0

11 2-11 0

l 11 2-12 0

II 2 13 0

11 2 14 1

11 2-15 0

II 2-16 1

11 2-17 0

11 2-18 0

11 2-19 0

-11 2-20 0

11 2-21 0

II 2-22 0

11 2-23 0

II 2-24 0

11 2 0 II 2-26 0

11 2-27 0

[]'

11 2 28 0

11 2 29

.0 11 2-30 0

,11 2-31 0

11 2-32 0

11 2-33 0

11 2-34 0

II 2-35 0

11.2-36 0

II 2-37 0

II 2-38

.0 11.2-39 0

11 2-40 0

11 2-41

-0 II-2-42 0

11'2-43 0

II 2-44 0

11.2-45 0

1

-A-V

.i EPL-6' October 22, 1989

('\\-

?.

CPSES ODCM

(~T.

Effective Page Listing

U.-

Pace No.

Revision No.

PART 11 11 2 46 0

11 2-47 0

11 2-48 0

11 2 49 0

11 2 50 1

-11 2-51 0

1 11 2-52 0

11 2-53 0

II 2-54 0

11 2 55 1

~

11 2 56 0

11 2-57 0

11 2-58 0

11 2-59 0

11 2 60 0

11 3-1 0

11 3-2 0

L[

II 3-3 0

L 11 3-4 0

II 3-5 0

t II 3-6 0

11 3-7 0.

11 3-8 0

II 3-9 0

II A-1 0

11-B-1 0

11 C-1 1

II D 1 0

.II D-2 0

II E-1 0

II:E-2:

0 II F-1 0

11 F-2 0

1 EPL-7 October 22, 1989

CPSES ODCM Effective Page Listing Paae No.

Revision No.

PART 11 G0 1

G-1 1

G2 1

G3 1

G-4 1

G5 1

G6 1

/O l

l w

1r 1:

I

-j l

l:

.v EPL-8 October 22, 1989 m

v m

- -

ML20058B674

Text

Navigation menu

Search