ML20207F890

Monthly Operating Rept for June 1986

ML20207F890
Person / Time
Site:	Byron
Issue date:	06/30/1986
From:	Dandrea P, Querio R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
(-325M-62M), (025M-62M), (25M-62M), BYRON-86-0615, BYRON-86-615, NOR-860630, NUDOCS 8607220633
Download: ML20207F890 (46)

Text

a BYRON NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-454 LICENSE NO. NPF-37 9

8607220633 860630 DR ADOCK 05000454 PDR (0625M/62M) 4 t

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Monthly Report for Byron Unit 1 A.

-Summary of Operating Experience for Unit 1 1

The Unit _ was at power for the entire reporting period.

I A discretionary load reduction to 70% was initiated on May 17th to minimize the rate of Steam Generator Tube corrosion and to prevent a back to back outage schedule with Unit 2.

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OPERATING DATA REPORT DCCKET NO.: 050-4L4 UNIT: Byron Cne DATE: 7/11/86 COMPILED BY:

P. Dandres TELEPHONE:

(815)234-5441 x2341 OPERATING STATUS 1.

Reporting Period: June 1985. Gross Hours:

720 2.

Currently Authorized Power Le. vel (MWt): 3411 Design Electrical Rating: 1175 (MWe-gross)

Design Electrical Rating: 1120 (MWe-net)

Max Dcpendable Capacity (MWe-net): NOT DETERMINED 3.

Power Level to Which Restricted (If Any): 1152 (MWe-gross) 4.

Reasons for Restriction (If Any): Not meeting minimum requirement on. split feedwater flow.

e THIS MONTH YR TO DATE CUMULATIVE

• 5.

Report Period Hrs.

720 4343 6912 6.

Rx Critical Hours 720 3961.1 5953.6 7.

Rx Reserve Shutdown Hours 0

21.7 37.E 8.

Hours Generator on Line 720 3916.0 5108.4 9.

Unit Reserve Shutdown Hours 0

0 0

10. Gross Thermal Energy (MWH) 1777104 11618701 14957893

11. Gross Elec. Energy (MWH) 605942 3927127 5015717 i

12. Net Elec. Energy (MWH) 566356 3707262 4720160

13. Reactor Service Factoe 100 91.2 86.1

14. Reactor Availability Factor 100 91.7 86.7

15. Unit Service Factor 100 90.2 73.9

16. Unit Availability Factor 100 90.2 73.9 i-

17. Unit Capacity Factor (MDC net)

N/A N/A N/A

18. Unit Capacity Factor (DER net) 70.2 76.2 61.0

19. Unit Forced Outage Mrs.

0 102.7 205.3

20. Unit Forced Outage Rate 0

2.6 3.9 l

21. Shutdowns Scheduled Over Next 6 Months: None.

22. If Shutdown at End of Report Period, Estimated Date of Startup: N/A

23. Units in Test Status (Prior to Commercial Operation)

None

• Note - The cumulative numbers do not reflect power generated prior to cc.mercial service.

(0625M/62M)

C.

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.:

050-454 UNIT:

Byron One DATE:

7/11/86 COMPILED BY:

P. Dandrea TELEPHONE:

(815)234-5441 x2341 MONTH: June, 1986 j

DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1.

803 MW 17.

795 MW 2.

799 MW 18.

910 MW 3.

803 MW 19.

958 MW 4.

803 MW 20.

957 MW 5.

798 MW 21.

354 MW i

6.

798 MW 22.

555 MW a

7.

_,_800 MW 23.

746 MW 8.

804 MW 24.

796 MW 9.

804 MW 25.

795 MW 10.

894 MW 26.

784 MW 11.

85S MW 27.

802 MW 12.

805 MW 28.

803 MW 13.

806_MW__

29.

722 MW 14.

805 MW 30.

800 MW 3

15.

800 E4 _ _____

16, 118 15f INSTRUCTIONS l

On this form list the average daily unit power level in MWe-Net for each day in the reporting month. Coepute to the nearest whole megawatt. These figures will be used to plot a graph fer each reporting month. Note that when maximum dependable capacity is used for the net electrical rating of the unit there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line.)

In such cases the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

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cerec<,cecocccccccoo :::eco Report Period June, 1986 UNIT SHUTDOWNS / REDUCTIONS o

BYRON O

No.

Date Type Hours Reason Method LER Number System Component Cause & Corrective Action to Prevent Recurrence 9) 6/21/86 S

0 B

5 N/A N/A N/A Scheduled partial stroke surveillance cecoce*********

30 days of power operations.

0 Summary ocecce*********

TYPE Reason Method System & Component F-Forced A-Equip Failure F-Admin 1-Manual Exhibit F & H S-Sched B-Maint or Test G-Oper Error 2-Manual Scram Instructions for C-Refueling H-Other 3-Auto Scram Preparation of D-Regulatory Restriction 4-Continued Data Entry Sheet E-Operator Training 5-Reduced Load Licensee Event Report

& License Examination 9-Other (LER) File (NUREG-0161)

(0625M/0062M)

E.

UNIQUE REPORTING REQUIREMENTS 1.

Safety / Relief valve operations for Unit One.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT None 2.

Licensee generated changes to ODCM.

(Y/N)

Yes, see AttacFaent A.

(0625M/62M)

F.

LICENSEE EVENT REPOR"'S The following is a tabular sunnary of all Licer.ce Event Reports for Byron Nuclear Power Station, Unit One, cubmitted dering the reporting period, June 1 through June 30, 1986, This information is provided pursuant t.o the reportable occurrence reporting requiremer'ts as set forth in 10CFR 50.72.

Licensee Event Report Number Date T_itle of Occurrence 86-015-00 6-03-86 Incorrect Boron Dilution e

Protection System Flux Doubling Setpoint Calibration and Testing due to ir. adequate procedure.

86-016-00 6-20-86 River Scree.n liouse Fire Watch removed prio.r tc Fire Suppression Svstern operability r'storation.

e 86-017-00 6-30-86 Soth Trains of Control Room Ventilation System inoperable due to failure of Post Modification Installation Testing on 'R' Truin and Make-up Unit Fan Trip on 'A' Train.

86-018-00 6-10-86 Main Control Room Uectilation Engineered Safety Feature Actuation Due to Misalignment of Radiation Monitor Check Source.

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JUST!FICATION TOR CHANGES:

The revielons indicated on ppges 8.142 and 8.1-5 (see On-Site R, view 8$-040 minutes) are for clerification. They do not affect the original content of the isections they revisa.

On p&ga 8.2.-3, the third nentence under ssctior. 8.2.3 bas Lecn revised *y j

teflect the installation of thet new liquid release tank GWX16T).

The revlsiens indicated on page 8,2-5, and the first pacagraph on page 9.Z-6, serva to clarify release tank menitor setpoint deteritinatiors. The origina) 4 contents of these _e.ectior.s remains unchanged.

Tne third para, graph under section 8,2.6 (pags B.2-6) has been revised td more clearly eiplain how the alant./ trip setpoints on the efflueet monitocing system work to prevent exceeding 10 CFR Phkf 23 liquia release. limits.

I

'Ine thifd sentence in the first paragrapn ander cection 8.3.o, seption 3.S.C, and figure 8.2-) have been revised to ref',ect the installatida of the new liquid relsasa tank (OW:26T).

The revisions made in Table 8.4-1, sections 2 ar.d 3, serve to clarify

ampling/inonitcring locations.

The LLD for iodine in table 6.4-3 has been revised to ae.:ura tely reflect the

[

value given in Byron Station Technical Specincaticns.

Section 9 of the Offsite Dose Calculation Manual wac revi5wed for <:cmplaaSce to regulatory requireraents, Technical Specifications, St.atior. proced res, add clarity. All changes.have been reviewed and found acceptable oy Onsite Review 66-04Q and the invcatigative Function.

In additien, At has br an daturnined 1

that none of the changes will reduce the accuracy or reliability of dose calculations or Setpoint determinations.

The date of Onsite Review was March 24, 1986. Ihm date of ODC:' RGv. IlA implementation was June 1, 1986.

(0625M/62M) i

)

BYRON REVISION llA MARCH 1986 ODCM TABLE OF CONTENTS FOR BYRON SECTION 8.0 PAGE 8.0 RADIOACTIVE EFFLUENT TREATMENT SYSTEMS, MODELS FOR SETTING GASEOUS AND LIQUID EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, AND ENVIRONMENT RADIOLOGICAL MONITORING 8.1-1 I

8.1 GASEOUS RELEASES 8.1-1 8.1.1

System Design

8.1-1 0.1.1.1 Gaseous Radwaste Treatment System 8.1-1 B.1.1.2 Ventilation Exhaust Treatment System 8.1-1 8.1.2 Alarm and Trip Setpoints 8.1-1 8,1.3 Station Vent Stack Monitors 8.1-3 8.1.4 Containment Purge Effluent Monitors 8.1-4 8.1.5 Gas Decay Tank Monitors 8.1-5 l

8.1.6 Allocation of Effluents from Common Release Points 8.1-6 8,1.7 Symbols Used in Section 8.1 8.1-7 3.1.8 Constants Used in Section 8.1 8.1-8 0.2 LIQUID RELEASES 8.2-1 8.2.1 system Design 8.2-1 8.2.3 Alarm Setpoints 8.2-1 l

8.2.3 Liquid Radwaste Effluent Monitor 8.2-3 P.2.4 Station Blowdown Monitor 8.2-4 8.2.5 Reactor Containment Fan Cooler (RCFC) and Essential Service Water Outlet Line Monitors 8.2-5 8.2.6 Administrative and Procedural Controls for Radwaste Discharges 8.2-6 8.2.7 Determination of Initial Dilution Stream Flow Rates 8.2-6 8.2.8 Allocation of Effluents from Common Release Points 8.2-7 R.2.9 Symbols Used in Section 8.2 8.2-7 8.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM 8.3-1 8.4 ENVIRONMENTAL RADIOLOGICAL MONITORING 8.4-1 8-i

BYRON RFVISION llA MARCH 1986 ODCM LIST OF TABLES FOR BYRON SECTION 8.0 NUMBER TITLE PAGE 8.4-1 Environmental Radiological Monitoring Program 8.4-2 i

8.4-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 8.4-7 8.4-3 Detection Capabilities for Environmental Sample Analysis 2.4-S l

i.

2 l

l 8-11 i

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DYRCN RcyISION J.1A MARCH 1986 CDCP LIST CF FIGURES FCR_DYRON SECTION 6.0 NUMBER TITLE 8.1-1 Sirplified UVAC and Gaseous Effluent Flow Diagram 8.231 Liquid Release Flowpath 8.4-1 Onsite Air Sampling Locations 8.4-2 Offsite Air Sampling Locations 8.4 3 Inner Ring and Outer Ring TLD Locations 8.4-4 Ingestion and Waterborne Exposure Pathway l

Sample Locations I

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BYRON REVISION llA MARCH 1986 i

j X.8.0 RADIOACTIVE EFFLUENT TREATMENT SYSTEMS,

/

MODELS FOR SETTING GASEOUS AND LIQUID EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, AND ENVIRONMENTAL RADIOLOGICAL MONITORING 8.1 GASEOUS RELEASES

?

m 8.1.1. System Design I

,aseous Radwaste Treatment System 8.1.1.1 G

, i A gaceous radwaste treatment system shall be any system

-des'igned and installed to reduce radioactive gaseous effluents by collecting primary coolant system off-gases from the f

purpose of reducing the total radioactivity prior to release p'r"imary system and providing for delay or holdup for the I'L s

i to the environment.

Refer to Figure 8.1-1 for a simplified system flowpath diagram.

s 8.1;1.2 Ventilation Exhaust Treatment System A ventilation exhaust treatment system shall be any system i

i designed and installed to reduce gaseous radioiodine or radioactive ^ material in particulate form in effluents by 1

l passing ven,tilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing l

iodines or particulates from the gaseous exhaust stream f

-prior,to thh release to the environment (such a system is nc.t considered to have any effect on noble gas effluents).

Engineered Safety Feature (ESP) atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components.' ',

8.1.2 Alarm and Trip Setpoints Alarm and trip setpoints of gaseous effluent monitors at the principal points of release of ventilation exhaust air I

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BYRON REVISION llA MARCH 1986 containing radioactivity are established to ensure that the release limits of 10 CFR 20 are not exceeded.

The set-points are found by solving Equations 2.6* and 2.7**

for each class of releases.

For these equations, the radioactivity mixture in the exhaust l

air is assumed to have the composition of gases listed in Table 3.5-7 of the Environmental Report Operating License Stage.

According to Subsection 3.5.3.4 of the report, releases of radionuclides in gaseous effluents were calculated using the PWR-GALE computer program and the parameters listed in Table 3.5-5.

Equation 2.6* is rewritten using the fractional composition of each nuclide, f, and a total release rate, Q, f r station vent i

t stack releases (the principal point of release of ventilation exhaust air containing radioactivity):

1.11 O

51*f)

< 500 mrem /yr

( 8.1) tv i

f Fractional Radionuclide Composition g

The release rate of radionuclide i divided by the total release rate of all radionuclides.

l O

Total Release Rate, Vent Release (pCi/sec) tv The release rate for all radionuclides due to a station vent stack release.

Oiv " Otv i (8.2) l Equation 8.1 can be solved for Q for release limit tv determinations.

Similarly, Equation 2.7** can be rewritten:

g (X/Q), Oey g exp

(- l R/3600 u ) +

f g

y 1.11 V Q

f

< 3000 mrem /yr (8.3) g tv i

i

• Equation 2.9 of Revision 2.

1 i

• • Equation 2.10 of Revision 2.

8.1-2

I 1

BYRON REVISION llA MARCH 1986 and a corresponding release Equation 8.3 can be solved for Qtv limit can be determined.

The most conservative release limit from Equations 8.1 and 8.3 will be used in selecting the appropriate alarm and trip setpoints for a vent release.

The exact settings will be selected to ensure that 10 CFR 20 limits are not exceeded.

Surveillance frequencies for gaseous effluent monitors will be as stated in Table 4.3-9 of the Technical Specifications.

Calibration methods will be consistent with the definitions found in Section 1.0 of the Technical Specifications.

8.1.3 Station vent Stack Monitors Detectors 1RE-PR028A, B, C,D, and E (particulate, low gas, iodine, high gas, and background subtraction channels, respec-tively) and 2RE-PR028A, B, C, D, and E monitor station vent stack effluent from the auxiliary building vent stacks.

The particulate detector utilizes a beta scintillator and

-11

-5 has a range of 10 to 10 pCi/cc.

The low and high gas

-6 detectors utilize beta scintillators and have ranges of 10

-2

-2 2

to 10 pCi/cc and 10 to 10 pCi/cc, respectively.

The iodine detector utilizes a NaI(Tl) scintillator and has a range

-11 to 10-5 pCi/cc.

of 10 Both vent stack effluent monitors feature automatic isokinetic sampling, automatic gaseous composite grab sampling, and tritium sampling.

The monitor skids with associated pumps, detectors, and local controls are located in the auxiliary building on the 477-foot elevation.

8.1-3

BYRON REVISION llA MARCH 1986 Each monitor has a microprocessor (RM-80) which utilizes digital processing techniques to analyze data and control monitor functions.

Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on a CRT display (RM-ll) in the main control room.

A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and provides the high voltage for the detectors.

The power supply unit is located on the monitor skids.

The monitors are powered by local 120-Vac instrumentation buses.

Alarm setpoint determination is addressed in Subsection 8.1.2.

The release limits (uci/sec) obtained from Equations 8.1 and 8.3 are divided by the normal auxiliary building vent stack flow rates (cc/sec) to obtain the pCi/cc alarm setpoint values.

Readouts for the vent stack monitors are in pCi/cc.

The cpm to pCi/cc conversion is accomplished by use of conversion factors in the radiation monitoring system software.

8.1.4 Containment Purge Effluent Monitors

(

Detectors 1RE-PR001A, B, and C (particulate, gas, and iod..te channels, respectively) and 2RE-PR001A, B, and C monitor containment purge effluent discharge to the auxiliary building vent stacks for Units 1 and 2, respectively.

l The particulate detector utilizes a beta scintillator and

-11

-5 has a range of 10 to 10 pCi/cc.

The gas detector utilizes

-6

-2 a beta scintillator and has a range of 10 to 10 pCi/cc.

The iodine detector utilizes a NaI(Tl) scintillator and

-11

-5 has a range of 10 to 10 pCi/cc.

8.1-4

BYRON REVISION 11A MARCH 1986 The monitor skids with associated pumps, detectors, and local controls are located in the auxiliary building on the 475-foot elevation.

Each monitor has a microprocessor (RM-80) which utilizes digital processing techniques to analyze data and control monitor functions.

Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on a CRT display (RM-11) in the main control room.

A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and provides the high voltage for the detectors.

The power supply unit is located on the monitor skids.

The monitors are powered by local 120-Vac instrumentation buses.

A containment atmosphere sample is obtained and analyzed

(

prior to each containment purge release.

The isotopic analysis results of this sample are used to determine the maximum allowed containment purge flow rate.

This isotopic analysis or the containment atmosphere monitor 1(2)RE-PR011 readings are utilized as the basis for determining the containment l

purge effluent monitor setpoints.

8.1.5 Gas Decay Tank Monitors Detectors ORE-PR002A and B (low range gas and high range gas, respectively) monitor the radiation level of the gas decay tank discharge to the auxiliary building vent stacks.

Detectors ORE-PR00 2A and B are interlocked with valve OGWRCV014.

Automatically, on a high radiation and/or instrument f ailure signal from the detectors, vent valve OGWRCV014 closes to l

isolate the gas decay tank discharge line.

1 8.1-5

BYRON REVISION llA MARCH 1986 Both the low range and high range gas detectors utilize

-6

-2 beta scintillators and have ranges of 10 to 10 pCi/cc

-2 2

and 10 to 10 pCi/ce, respectively.

The monitor skid with associated pump, detectors, and local controls is located in the auxiliary building on the 346-foot elevation.

The monitor has a microprocessor (RM-80) which utilizes digital processing techniques to analyze data and control monitor functions.

Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on a CRT display (RM-ll) in the main control room.

A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and provides the high voltage for the detectors.

The poser supply unit is located'on the monitor skid.

The monitor is powered by local 120-Vac instrumentation buses.

A grab sample from the gas decay tank to be released is obtained and analyzed prior to each gas decay tank discharge.

The isotopic analysis results of this sample are used to determine the maximum allowed gas decay tank discharge line flow rate and as a basis for determining the gas decay tank monitor interlock and high alarm setpoints.

8.1.6 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the auxiliary building, miscellaneous ventilation system, and the gas decay tanks are comprised of contributions from both units.

Under normal operating conditions, it is difficult to apportion the radioactivity between the units.

Consequently, allocation will normally be made evenly between units.

8.1-6

BYRON REVISION llA MARCH 1986 8.1.7 Symbols Used in Section 8.1 SYMBOLS NAME UNIT Q

Total Release Rate, Vent Release (pCi/sec) tv V

Gamma Whole Body Dose Constant, g

Vent Release (mrad /yr per pCi/sec) f Fractional Radionuclide Composition g

E Eeta Skin Dose Constant (lmrem/yr per pCi/m )

g (X/Q),

Relative Effluent Concentration, 3

Vent Release (sec/m )

A Radiological Decay Constant (hr-1) g R

Downwind Range (m) u Average Wind Speed, Vent Release (m/sec) y Q

Release Rate, Vent Release (pCi/sec) gy i

V Gamma Dose Constant, Vent Release (mrad /yr per UCi/sec) g l

8.1-7

BYRON REVISION 11A MARCH 1986 8.1.8 Constants Used in Section 8.1 NUMERICAL VALUE NAME UNIT 1.11 Conversion Constant (mrem / mrad) 3600 Conversion Constant (sec/hr) 8.1-8

REVlSION llA MARCH 1986

!! " E i" 3 E

EE E

-. E iew 230 0' E

2 above gek 3*

3 000 g

h Coata< ament ua.:.

,3 g (Typsca0 Int.PRC28 2ag pac 28 l

l 3000 M

C 43 900 ni M --

c v ~

0 M

C M LJ F

43 900 400 g ag.pmoot A

N 0

A Come. amen.

1m E -Pm 011 I

un,2 F

43 900 2AE PA001 Siec.1 Siack 2 Fue. han.6eng M

159 000 21 000 t___

M Aussisa n

'y g

162.300 A4ce...r.a.

g 133 800 b

M g

c 2

20.m,

. charge D i..

ORE PR002 159 000

.00

.uuskary w. i.

M eM ana 1000

,,s

.ue i.

M 14 105M 8

s..P i.w,,

M 4 250 e

e u

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p.

i BYRON STATION FIGURE 8.1-1 SIMPLIFIED HVAC AND GASE0US EFFLUENT FLOW DIAGRAM (SHEET 10F 2) 3720-6R 04 279

REVISION 11A MARCH 1986 i

i N

1.432 Gland steam 1.400 g condenser y

y H C C H steam pt 32 3 g ___q ser etector j

ggy g stack 1 stack 2 1 400 p N

1.432 Gtand steam d

condenser v

F 0

steam pt g

32 airetector p

i soi d red.asie ;

o sie(n 3.t00 s_

WWume reduction H C C H A Containment atmosphere radiation monitor C Charcoal filter F Refueling G Noble gas radiation monitor (offline)

H HEPA filter l

M Three-channel radiation monitor for particulate, lodine, and l

noble gas (offline)

N Normal operation P Particulate monitor (offline)

R Hyd. ogen recombiner S Normal range stock radiation monitor (perticulate, lodine, and noble gas)

W Wide-range stack noble gas radiation monitor All flow rates are cubic feet per minute BYRON STATION FIGURE 8.1-1 SIMPLIFIED HVAC AND GASE0US EFFLUENT FLOW DIAGRAM (SHEET 2 0F 2) 37 m m 04-86-279

~. - _ - _.. -

BYRON REVISION llA MARCH 1986 8.2 LICUID RELEASES 8.2.1

System Design

A liquid radwaste treatment system shall be a system designed and installed to reduce radioactive liquid effluents by collecting the liquids, providing for retention or holdup, and providing for treatment by demineralizer or a concentrator for the purpose of reducing the total radioactivity prior to release to the environment.

Refer to Figure 8.2-1 for a simplified system flowpath diagram.

8.2.2 Alarm Setpoints Alarm setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of 10 CFR 20 are not exceeded in the unrestricted area.

Prior to each batch release, a grab sample from the release tank is obtained and analyzed.

Equation 8.4 is evaluated for the radionuclide mix identified in the grab sample iso-l topic analysis results to determine the maximum allowable flow rate in the liquid radwaste discharge line.

6 7act F[,,=

,y gg,4) 1 MSC g

{

F,,

Maximum Permissible Flow Rate, Radwaste Discharge (gpm)

The maximum flow rate peruitted in the liquid radwaste discharge line that meets 10 CFR 20 limits.

8.2-1

(

BYRON REVISION llA MARCH 1986 F

Actual Flow Rate, Initial Dilution ct Stream (gpm)

The actual flow rate of the initial dilution stream which carries the radionuclides to the unrestricted area boundary.

MPC Maximum Permissible Concentration f

of Radionuclide i in the Unrestricted Area (10 CFR 20, Appendix B, Table II, Column 2)

(pCi/ml)

C Concentration of Radionuclide i f

in the Release Tank (uCi/ml)

K Conservatism Constant Determined by Station Procedures for Liquid Releases; K> 1.0.

Division by K allows station management to provide a margin of conservatism for liquid batch releases.

After determining F,,, from Equation 8.4, 10 CFR 20 compliance is verified using Equations 8.5 and 8.6.

F"#"*

(8.5)

C"i = Ci r

o p

,g max act C"=

Concentration of Radionuclide i in the Unrestricted Area.

(pCi/ml)

[

C" i

I MPC g 8.2-2

BYRON REVISION 11A MARCH 1986 The alarm setpoints for the liquid radwaste effluent monitor (ORE-PR001) are determined prior to each release and are based on the isotopic analysis results of the release tank grab sample.

The alarm setpoints are set so that any deviations f rom the isotopic analysis results will result in the automatic ter-mination of the release.

Readouts for the liquid effluent monitor are in pCi/ml.

The cpm to pCi/ml conversion is accom-plished by use of conversion factors in the radiation monitoring system software.

8.2.3 Liquid Radwaste Ef fluent Monitor Radiation monitor ORE-PR001 monitors liquid radwaste ef fluent and is interlocked with release tank discharge valve 0WX353.

On high radiation in the liquid radwaste effluent, the release tank discharge valve is closed automatically.

A Each release tank (OWXOlT and OWX26T) holds 30,000 gallons.

Both ara located in the turbine building on the 401-foot elevation.

The monitor utilizes a NaI(Tl) detector with a range for

-8

-2 gamma radiation of 10 pCi/ml to 10 uCi/ml.

The monitor skid and associated features are located in the turbine building on the 401-foot elevation.

The monitor has a microprocessor (RM-80) which utilizes digital processing techniques to analyze data and control monitor functions.

Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on a CRT display (RM-ll) in the main control room.

8.2-3 4

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.._.,.,c.,_._-._

BYRON REVISION llA MARCH 1986 A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and provides the high voltage for the detector.

The power supply is located on the monitor skid.

The monitor is powered from local 120-Vac instrumentation buses.

A discussion of alarm setpoints for ORE-PR001 is included in Subsection 8.2.2.

8.2.4 Station Blowdown Monitor Radiation monitor ORE-PRO 10 continuously monitors the circulating water blowdown for radioactivity.

The monitor utilizes a

~0 NaI(Tl) detector with a range for gamma radiation of 10 pCi/ml

-2 to 10 uCi/ml.

The monitor skid and associated features are located in the turbine building on the 364-foot elevation.

(

The monitor has a microprocessor (RM-80) which utilizes digital processing techniques to analyze data and control monitor functions.

Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on a CRT display (RM-ll) in the main control room.

A power supply unit furnishes.the positive and negative voltages for the circuits, relays, and alarm lights and provides high voltage for the detector.

The power supply 4

is located on the monitor skid.

The monitor is powered from local 120-Vac instrumentation buses.

The alarm setpoints for the station blowdown monitor are determined prior to each release and are based on the isotopic analysis results of the release tank grab sample and the actual dilution flow rates.

The alarm setpoints are set so 8.2-4

i BYRON REVISION 11A MARCH 1986 that unexpected deviations f rom the isotopic analysis results l

or f rom the specified dilution flow rate will result in an alarm from the monitor.

Between batch releases, the station blowdown monitor alert and high alarm setpoints are established at levels specified by station procedures.

l 8.2.5 Reactor Containment Fan Cooler (:RCFC) and Essential Service Water Outlet Line Monitors Radiation monitors 1RE-PR002, 2RE-PR002, 1RE-PR003, and 2RE-PR003 monitor the RCFC and essential service water out-

~

let lines for radioactivity.

The monitor utilizes a NaI(TI)

-8 detector with a range for gamma radiation of 10 UCi/ml

-2 to 10 pCi/ml.

The monitor skid and associated f eatures are located in the auxiliary building on the 401-foot eleva-

tion, The monitor has a microprocessor (RM-80) which utilizes s

digital processing techniques to analyze data and control monitor functions.

Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on a CRT display (RM-11) in the main control room.

A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and provides high voltage for the detector.

The power supply is located on the monitor skid.

The monitor is powered f rom local 120-Vac instrumentation buses.

Unit I radiation monitor high alarm setpoints are based on detector response to a mix of several radionuclides -

those listed on Table 11.2-4 of FSAR which are capable of 8.2-5 l

BYRON REVISION 11A MARCH 1986 i

being detected by the monitor's sodium iodine detector.

I Each nuclide in the mix is at a concentration which is 10%

of the MPC value given in 10 CFR 20 Appendix B, Table 2, t e high a arm s tpoi t D

ng U 2 sta t-up, aler o

and high alarms are set at twice the observed backgro,und.

8.2.6 Administrative and Procedural Controls for Radwaste Discharges Administrative and procedural controls have been designed l

to ensure proper control of radioactive liquid radwaste discharge in order to preclude a release in excess of 10 CFR 20 limits.

The discharge rate for each batch is calcu-lated by radiation chemistry personnel (Equation 8.4) and then provided to operating staff personnel.

All liquid radwaste discharges will be f rom either release tank OWXOlT k

or release tank OWX26T.

On high radiation in the liquid radwaste effluent, the release tank discharge valve 0WX353 is closed automatically.

The proper valve lineup is performed by the operator prior The actual to each batch discharge, per station procedures.

discharge is authorized by the shift engineer.

The effluent monitoring instrumentation system is equipped with alarm / trip setpoints which, if exceeded, initiate auto-matic valve closure on the release tank discharge line.

This system is used to prevent exceeding 10 CFR 20 liquid release limits.

Determination of Initial Dilution Stream Flow Rates t

8.2.7 l

For those release paths which have installed flow monitoring instrumentation, that instrumentation will be used to deter-This mine the flow rate of the initial dilution stream.

8.2-6

BYRON REVISION 11A MARCH 1986 instrumentation will be operated and maintained as prescribed by the Technical Specifications.

For those release paths which do not have installed flow monitoring instrumentation, flow rates will be determined by use of appropriate engineering data such as pump curves, differential pressures, or valve position indication.

8. 2.8 Allocation of Ef fluents from Common Release Points Radioactive liquid effluents released from either release tank (0WX0lT or OWX26T) are comprised of contributions from l

both units.

Under normal operating conditions, it is difficult to apportion the radioactivity between the units.

Conse-quently, allocation will normally be made evenly between units.

8.2.9 Symbols Used In Section 8.2 SYMBOL NAME UNIT a

C Concentration of Radionuclide 1 (pCi/ml) in the Unrestricted Area l

C Concentration of Radionuclide 1 (pCi/ml) g in the Release Tank MPC Maximum Permissible (uCi/ml) g Concentration of Radionuclide i in the Unrestricted Area F,,

Maximum Permissible Flow (g pm)

Rate, Radwaste Discharge F

Actual Flow Rate, (g pm) t Initial Dilution Stream 8.2-7 l

(-. - - -

BYRON REVISION 11A MARCH 1986 K

Conservatism Constant Determined by Station Procedures for Liquid Releases; K>

1.0 N

i 8.2-8

R!. VISION llA taE PR002 f1 ARCH 19EE

~

}

unn 1 RCFC A 8 C Sa Systern n

1RE PR003 L

Unit 1 RCFC 8 & D r

Su System 2RE PR002

'g Unit 2 RCrC A & C 1

1 Su Systerr:

2RE PR003 Unit 2 RCFC5&D Ss System Release tank OWXOIT 09E-PR001 a

r b.

t.

..In Station Prior to Each Release) l Station Blowdown '

l I

/ (Flowrote ideasured Ey R ase tank Station Prior to Esch Relesee)

)

ORE-PR010,L

' Y 1

l l

neck R.ve.

l l

l L

' Liquid Process Radiation Monitor BYRON STATION I

RCFC ' Reactor Containtnent Fan Cooler 1

FIGURE 8.2-1 i

LIQUID F.ELEASE FLOWPATH l

3720 04 86 - 2,79 e-

-,-r

,--y,

<---n--,,,

,,,-v---

--w,,_

c,w

,, _w,

BYRON REVISION llA MARCH 1966 8.3 S_OLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM The process control program (PCP) shall contain the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is ensured.

D l

8.3-1

4 BYRON REVISION llA l

MARCH 1986 8.4 ENVTRONMENTAL RADIOLOGICAL MONITCRING i

The environmental radiological monitoring program for the environs around Eyron Station is given in Table 8.4-1.

Reporting levels and lower limits of detection for this program are given Jr. Tables 8.4-2 and 8.4-3, respectively.

Figures 8.4-1, 8.4-2, 8,4-3, and S.4-4 show sampling and l

monitoring locations.

I I

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EYRON REVISION 11A MARCH 1986 6

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TABLE 8.0-1 (Cont'd)

EXPOSURE PATHWAY SAMPLING OR TYPE AND PREQUENCY AND/0E SAMPLE SAMPLING OR MONI10 RING IDf'AYlONS COLLECTION FREQUENCY OF ANALYSIS

1. Direct Radiation (Cont'd)

Indicators (Cont'd)

b.,0ute.r Ring (Cont'd) 206-1, 4.2 mi ESE

'206-2, 4.3 al SE 207-1, 4.2 mi SE 207-2, 3.7 mi SE 208-1, 4.1 mi SSE 208-2, 3.8 mi SSE 209-1, 3.8 mi S 209-2, 3.9 mi ssw 210-1, 3.6 mi SSW 210-2, 3.6 mi sw 211-1, 5.2 al SW 211-2, 4.8 mi WSW i

212-1, 4.9 mi WSW 212-2, 5.1 mi w 213-1, 5.0 mi w 213-2, 5.2 mi wNW 214-1, 4.8 si WWW 214-2, 5.2 mi NW 215-1, 5.4 wi NW 215-2, 5.2 mi NW 216-1, 4.'S mi Nuw i

216-2, 5.1 el NNW E

too

c. S ecial Interett L*

P as l

e At each cl the airborne pathway indicator locatione specified in Part 2 of this table.

Controlo At each of the airborne pathway control locations specified in Part 2 of this table.

2. Airborne Radiolodine and Indicators Continuous sampler operation Radiciodine Canister Particulates

a. Sesr fite Boundary with sample collection 1-131 analysis weekly.

l t

97-21, North Parking Lot, 0.27 mi N weekly, or more frequently BY-22, Ceco Property. 0.30 ml E if required by dust loading.

Particulate Sampler:

l BY-23, South of Plant on Deerpath Road,

s. Gross bets radioactivity Xg 0.59 mi S analysis folloging PY-24, Met Tower, 0.66 mi SW filter change.

{l {'

s

b. Near community with Hithest Calculated-

b. Cease isotopie analysio

[l@

pnwssa Average Ground Level D/Q of composite (by j",,

BY-1, Syron, 1.5 si MNE location) quarterly.'

H>

r. St-A9, 90 analysin of composite (by locat ion) quarterly.

f TABLE 4.te-1 (Cont'd)

SAMPLING OR YYPf AftD FREQUEhCY EXPOSI'RE PATHWAY AND/OR SAMPLE SAMPLING OR MONITORING LOCATIONS COLLECTION FREQtFENCY OF ANALYSIS 2.

Airborne (Cont'd)

Indicators (Cont'd)

c. Other BY-2, Stillman Valley, 6.2 mi NE LY-3, Nearsite - East, 3.8 mi E ST-4, Paynes Pt., 4.5 mi SE EY-5, Nearsite - South, 3.6 mi S BY-6, Oregon, 4.6 mi SSW controls BY-7, Mt. Morrie, 7.8 mi WSW BY-8, leaf River, 7.0 si NW

3. Waterborne

s. Surface Indicatore Weekly Crossbeteanalysisweegly.

RY-9, Woodland Creek, 2.3 mi W Camma isotopic analysis BY-12, Oregan Pool of Rock River, monthly. Composite' for Downetream of Discharge, 4.5 mi SSW tritiuer and Sr-99, 90 analysis quarterly.

to

,88 Controls BY-13, Rock River, tipstream of Intake, g d a

8 c5 i

2.6 at W.W x

b. Cooling Water

~Indiretore Weekly Croon beta analysis weekly.

BY-11, Byron Discharge Pipe / River, at Station Composite for gaussa isotopic, tritium and St-89, 90 aulysis monthly.

Controle BY-10, Byron Intake Pipe / River, at Station

c. Cround Indicators Quarterly Cases isatapic#, tritium, BY-18. McCoy Farmatesd, 1.25 mi SW gions beca and Sr-89, 90 analysis quarterly.

Controls l

EY-14 CECO Property, 0.1 mi E g8p

d. Sediment from Shoreline indiceters Yhree timis.o year Casema testopig and groes 9J BY -12. Oregon Pool cf 'tock River, beta realysis thr?e t awe DM Dwastream of Discherse, 4.5 mi SSW a year.

vo

e. x as Onntrols

• 5 87-i3, rark alver, ti.s c ream of I..take, 2.6 mi WNW

s TABLE d.4-1 (Csit'1) h c

thPOSURE PATH ET S.9tPLING Ost TYPR AnD FREQtMcCY NG/GR CWEPLE SAMrLINC OR MonitDell4C IAC.%Y!ONf.

COLLECT 19st F2 FOUET Q

_ 0F AD.LYSIE-

3. 5'sterborne (Coat 'd) k

e. Precipitatten-sv-15,.I.

4.- Reeverts Pine Hill Osirf, Monthlf Ooss leta.nalysis mun*hly.*

3.2 al ESE Composite for gasm.e isotopic,

5?-16, Krsnet?. Du?ist Farm, 7.0 mi SE Tritiw Lad Sr-89, 90 analyais-FY-17, Rosecher/kingel Ferm, 7.9 mi PE quarterly SYd20 Ed Seabeld Farm, 2.5 mi NY

f. Aquatic _ Plants Indlettora 3 ree *1mee a wear Cross bets and geasms isotopic

• SY Oregon Fuel o f Rot h pi rer, analysis three ti.ses a Oownetream of Discharge,'e.5 mi SSW year Contrcle SC -13, 29ck Ri se r, Ur,s t r=asa o f in t ak e,

2.6 al WKA

4. ingestioA

a. Mil'a Ind ic a tore BY-15 J. A. deeverte Pine Hilt ediry, 81weekty when aniasts ate Carmes isotopic *, I-Ill and 3.2 mi ESE on " pasture, monthly at other 3r-89, 90 analysis biweekly ce RY-16, Lenneth burien Faryg 7.0 mi SF

times, when animals are on pasture, M

4 BY-20, Ed Seabo?i term. E.5 mi PE monthly at other times.

O e"

i Controls

-BY-17,BoseckerfLingelharm, 7.0 ai NC

b. Fish and levertebrates Indicaiors fleree times per year (spring, Csime isotopic", gross beta Qresentative a:,aples t BY-12, 0refon ?ool of Recit Pivera aumer, and fall),

and St-89, 90 analysis on 4

atonmercially anJ 1% stress af Discharge, 4.5 sei 55W edible portions.

reersationctly importset species.

Controla

~MM, Rock River, Ups t ream o f in tak e, f

2.6 el Wel

e. V y tabtwa ind ic a tori.

Annually Crosa beta, gaussa isotopic

• BY 29-l. Oreyess Vegetable Stand, 7.5 mi SSW and Sr-89, 90 analysis BY-19-2, 0-egon Tegetable Stand, 7.5 mi SSW annually. I-131 analysis EM on leafy vegetables annually.

5 E ow c

MM

d. Catt 4 f'eed ar.d Crees Indiesto,s Quarterly Cross beta, gamma isotopic and J

BY-15, J. A. Reeverts Pine Hill Dairy, Sr-89, 90 analysis quarterly, ez 3.2 mi t.EE

$g 27-16, Kenn(th Durien Farm, 7.0 mi SE N

BY-20. 'std Seabold Farm, 2.5 mi NE i

l Coetrols 4

BY-17. Bosecker/Lingel Dairy Farm, 7.0 mi SE 1

i f

TABLE R.4-1 (Cont'd) l 9

9 l

Ilote s t "Deviatione are permitted from the regelred esepling schedule if specimens are unobtainable due to hasardous conditione, ocasonal unavallebilit y, malfunction of automatic sampling equipment and other legitieste reasone. If specimene are unobtainable due to sampling equipment malfunction, every effort shall be moda to complere corrective action prior to the end of the nest sampling period. All deviatione from the sampling schedule shall be documented in the Asemal 3.diological savironmental Operating Report. It le recognised that, at times, it may not be possible or j

practicable to continee to obtain comptes of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be cheeen for the particular pathway in question and appropriate substitutione made within 30 days in the radiological environmental monitoring program. The cause of the unavailability of eseples for that pathway and the new location (e) for obtaining replacceent seaples shall be identified in a Snecial Report to the Iloclear Regulatory causeission within 30 days. The report shall also include a revised figure (s) and table for the 000t reflecting the new location (s).

Airborne particulate oeuple filtete shall be analysed for groes beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after emepling to allow for redon and thoron daughter decay. If grose beta activity in air particulate samples is greater than ten tiara the yearly mean of control samples, gasses isotopic analysis shall be perfsreed on t%e individual samples.

'camma isotopic analyele means the identification and quantification of aseena-emitting radionuclides that may he attributable to the ef fluente f,um o f.et uty.

E i

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=

f TABLE 8.4-2 REPORTINC IEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS l

WATER AIRBORNE PARTICUy)TE FISH MILK FOOD PRODUCTS ANALYSIS (pCi/1)

OR CASES (pCi/m (pCi/kg, wet)

(pCi/1)

(pCi/kg, wet)

H-3 20,000*

.Mn-54 1,000 30,000 1

Fe-59 400 10,000 Co-58 1,000 30,000 K

Co-60 300 10,000 ce Z

Zn-65 300 20,000 t"

Zr-Nb-95 400 I-131 2

0.9 3

100 Cs-134 30 10 1,000 60 1,000 l

,Cs-137 50 20 2,000 70 2,000 l

Ba-La-140 200 300 3 :e i

>M

• For drinking water samples. This is 40 CFR Part 141 value.

If no' drinking water pathway exists, a value of 30,000 pCi/L eay be used.

Mm g

so WZ 1

CO

&H H>

I

_ = _.

TABLE 8.4-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS

• LOWER LIMIT OF DETECTION (LLD) i AIRBORNE PARTIy) TE FISH MILK FOOD PRODUCTS SEDIMEttr WATER ANALYSIS (pCi/1)

OR CAS (pCi/m (pCi/kg, wet)

(pCi/E)

Mi/kg, wet)

(pCi/kg, dry)

Gross Beta 4

0.01 H-3 2000*

Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 N

8

=

2n-65 30 260 Z

j Z.r-Nb-95 15 d

I-131 I

0.07 1

60 l

cs-134 15 0.05 i;3 15 60 150 CS-137 18 0.06 150 18 80 180 Ba-La-140 15 15 i

(

l NN to <:

c e.

• If no drinking water pathway exists, a value of 3000 pC1/2 may be used.

j$

• o O

• < Z HH WH m

(

BYRON REVISION llA MARCH 1986 TABLE 8.4-3 (Cont'd)

• This list does not mean that only these nuclides are to be considered.

Other peaks that are identifiable, together with those of the abave nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.

Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

• The LLD is defined, for purposes of these specifications, as the smallest Y

concentration of radioactive material in a sample that will yield a net l

count, above system background, that will be detected with 95 percent

!r probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.

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

4.66 s b

E ' V + 2.22 + Y exp (- A6t) f where:

LLD = the "a priori" lower limit of detection (picoCuries per unit mass or volume),

= the standard deviation of the background counting rate or of s

b the counting rate of a blank sample as appropriate (counts per i

(

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

= the ydioactive decay constant for the particular radionuclide, (sec

), and At

= the elapsed time between sample collection, or end of the sample collection period, and 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 an a priori (before the fact) limit representing the capability of a measurement system and not as an a_ posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will" be achieved under routine conditions. Occasionally I

i 8.4-9

,~.._.,__.~n,

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

-,._,..,,,,,,.,n_n,.-.,..amn,

,,nr,,,.n,,__.

.-,.,,.,,,,,m

BYRON REVISION llA MARCH 1986 TABLE 8.4-3 (Cont'd) background fluctuations, unavoidable small s;mple 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 Annual Radiological Environmental Operating Report.

d LLD for drinking water samples.

If ro drinking water pathway exists, an LLD of 60 pCi/L may be used.

~

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REVISION llA MARCH 1986 1

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REVISION 11A MARCH 1986 s'

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10KMS BYRON STATION FIGURE 8.4-4 INGESTION AND WATERBORNE EXPOSURE PATHWAY SAMPLE LOCATIONS

o July 11, 1986 LTR:

BYRON 86-0615 File:

2.7.200 Director, Office of Management Information and Program Control United States Nuclear Regulatory Commission Washington, D.C.

20555 ATTN:

Document Control Desk Gentlemen:

Enclosed for your information is the Monthly Performance Report covering Byron Nuclear Power Station for the period June 1 through June 30, 1986.

Very truly yours,

/0

/

R. E. Querio Station Manager Byron Nuclear Power Station REQ /PHD/Ir Enclosures cc:

J.G. Keppler, NRC, Region III NRC Resident Inspector Byron Gary Wright, Ill. Dept. of Nuclear Safety D.P. Galle T. J. Maiman D.L. Farrar Nuclear Fuel Services, PWR Plant Support L. Anastasia, Station Nuclear Engineering INPO Records Center Thermal Group, Tech Staff Byron Station Nuclear Group, Tech Staff Byron Station L. Olshan - USNRC P. H. Dandrea (0625M/62M) si,