ML19309F630

Compilation of Reported Noble Gas Effluent Monitor Capabilities at Operating Nuclear Power Plants

ML19309F630
Person / Time
Issue date:	04/30/1980
From:	Block S, Fialkovich J Office of Nuclear Reactor Regulation
To:
References
NUREG-0592, NUREG-592, NUDOCS 8004300206
Download: ML19309F630 (30)

Text

8004gogpg g.

NUREG-0592 Compiation of Reported Noble Gas EYluent Monitor Capabilities at Clperating Nuclear Power Plants J. E. Fialkovich, S. Block ea Reactor Regulation US uclear Regulatory

,p'%q, peaengg

'"= '

i i

Available from GP0 Sales Program Division o.f Technical Information and Document Control U.S. Nuclear Regulatory Commission Washington, D.C.

20555 and

(

National Technical Information Service Springfield, Virginia 22161 t

i

NUREG-0592 Compilation of Reported Noble Gas Effluent Monitor Capabilities at Operating Nuclear Power Plants

=raTen J. E. Fialkovich, S. Block Divi:lon of Operating Reactors Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Wrhington, D.C. 20555 I

i ABSTRACT A compilation of noble gas effluent monitoring systems was made for all nuclear power plants operating in the United States in order to characterize their effectiveness in monitoring an event comparable to the Three Mile Island accident. Thia report summarizes the capability of existing monitoring systems that existed during early 1979. These systems deal with the measurement of ihe maximum detectable concentrations (pCi/cc) and release rates (Ci/sec), readout ranges, and any automatic isolation and/or alarm functions for wl.ich they are designed.

Operating reactors have been upgrading effluent monitoring systems since the accident at Three Mile Island in response to the NRC Lessons Learned Implementation Program.

Consequently, much of the data may be obsolete.

lii

TABLE OF CONTENTS

?*iLe iii ABSTRACT........................

1.

INTRODUCTION.....'..............

1 2.

DISCUSSION OF NOBLE GAS EFFLUENT MONITORING 2

SYSTEMS......................

3.

NO3LE GAS MONITORING CAPABILITIES AT OPERATING 3

REACTORS.....................

LIST OF TABLES Table 1 Operating Reactor Noble Gas Effluent Monitor Data Table 2 Comparison of Noble Gas Effluent Monitors at Operating Reactors i

l l

Y l

COMPILATION OF REPORTED NOBLE GAS EFFLUENT MONITORING CAPABILITIES AT OPERATING NUCLEAR POWER PLANTS 1.

INTRODUCTION On May 14, 1979, in testimony before Congress concerning the Three Mile Island (TMI) accident, Chairman Hendrie noted that the TMI noble gas stack monitors registered a high amount of radiation due to the amount of activity being released.

In his testimony, Chairman Hendrie committed to provide Congressman Moffitt a report of the plants where the noble gas stack monitoring equipment may require modification so that these monitors could follow the course of a TMI type of accident.

Chairman Hendrie noted that, even though the TMI high-range noble gas stack monitor was not essential in determining the amount of radfai.1on the public around the TMI site received, it would have been helpful to have a noble gas monitor with high-range capabilities to follow the course of the accident by measuring the real-time releases.

As a result of Chairman Hendrie's commitment made in May and June 1979, the staff infer; ally collected the necessary information to describe the capa-bilities of noble gas effluent monitors in all operating plants within the United States. This report summarizes and presents a compilation of the information received by the staff of the characteristics of noble gas effluent monitors currently installed in operating power reactors at that time.

Since the data for this report was assembled, substantial modifications have been made, or are being planned, to noble gas effluent monitors at currently operating power plants.

To implement the recommendations resulting from studies of the Lessons Learned Task Force (NUREG-0578), the NRC has required operating reactors to upgrade effluent monitors to increase upper ranges so l

that the monitors would remain on scale during an accident.

Consequently, much of the technical data in this report may be obsolete or incomplete for existing operating power reactors.

i l

l l

2.

DISCUSSION OF NOBLE GAS EFFLUENT MONITORING SYSTEMS General Design Criteria 64 (10 CFR Part 50, Appendix A) requires licensees to monitor radioactive gaseous effluents and all effluent discharge paths in all nuclear power plants in order to measure the releases to the environment.

Although many different types of noble gas effluent monitoring systems exist in the nuclear industry, these essential systems are basically designed to perform the following functions:

(1) To determine if the plant's releases are in compliance with the limits set in 10 CFR Part 20 and if they are "as low as is reasonably achievable" (10 CFR Part 50, Appendix I);

(2) To provide information on the principal radionuclides released to unrestric-ted areas in gaseous effluents, which is required by Section 50.36(a)(2) of 10 CFR Part 50 in a semiannual report to the NRC; (3) To determine the effectiveness of radwaste effluent reduction systems; (4) To provide alarm and isolation functions if a predetermined setpoint is exceeded; and (5) To provide information on the severity of' unplanned releases and the effectiveness of actions taken to reduce the releases and potential impact to the public.

l 2

3.

N0BLE GAS MONITORING CAPABILITIES AT OPERATING REACTORS The staff collected information on the capabilities of existing monitoring systems to provide data necessary to characterize effluent releases through principal release points during normal and accidental operating conditions from 67 to 70 operating plants in the United States.

Data was not collected from Arkansas 2, Dresden 1, and Indian Point 1.

Arkansas 2 is in power ascen-sion and data is not available on it at this time.

Dresden 1 is undergoing extensive modifications, and a date has not been set for completion.

Indian Point 1 has not been operation since October 31, 1974; all fuel has been unloaded and no decision has been made on future operation.

To provide for this report, the licensees provided informal answers to a series of questions dealing with site-specific noble ' gas effluent monitors as follows:

(1) What is the location of the effluent monitor or monitoring system (i.e.,

principal release point, building ventilation exhaust point)?

(2) What detector is being used (e.g., Geiger-Mueller, plastic scintillator, sodium iodide)?

(3) What is the readout range of the detector (minimum / maximum cpm)?

(4) What is the maximum release rate that can be detected on-scale by the detector (Ci/sec)?

3 (5) What calibration factor is used for the system (cpm per pCi/cm )?

(6) What is the reference radionuclide used to calibrate the system (e.g.,

85Kr,233Xe)?

(7) What is the alarm setpoint for the system (cpm or pCi/cc)?

(8) What is the alarm function of the system (e.g., isolation of purge, alarm in control room,.etc.)?

3 l

Table 1 gives a compilation of the responses by the licensees to the preceding.

questions.

Table 1 includes the responses from TMI Unit 2.

According to our best estimates, the TMI releases during the first few days of the accident ranged between 10 and 100 Ci/sec.

The upper limit on the TMI stack monitor was approximately 0.5 Ci/sec and, therefore, was high off the scale during most of the accident.

Table 1 gives the various nuclides that were used to calibrate the effluent monitors in each plant.

The maximum limit of detection for the plants, there-fore, is reflected by the specific nuclide used as the calibration source.

Use of this limit of detection for other radionuclides may not be applicable.

At present, 10 of the 67 operating reactors in the United States have monitors capable of detecting releases greater than 100 Ci/sec.

Twenty-two of the 67 reactors have monitors with an upper limit of detection between 10 and 100 Ci/sec.

Twenty-eight of the 67 reactors have monitors with an upper limit between 0.5 and 10 C1/sec.

Including TMI Unit 2, 7 of the 67 reactors have monitors whose upper limits are below 0.5 Ci/sec.

A comparison of all of the operating reactors maximum limits of detection (Ci/sec) are given in Table 2.

t 9

I 4

NOMENCLATURE APPEARING IN TABLE 1 ABI auxiliary building isolation ABSVS auxiliary building special ventilation system AE air ejector AID air inlet damper CI containment isolation cont.

containment cpm counts per minute cps counts'per second CRI control room isolation CVI containment ventilation isolation CVPV containment vacuum pump valve ED exhaust dampers EV exhaust valve FHBVI fuel handling building ventilation isolation 1

G-M Geiger-Mueller LA local alarm LL lower level mR/h milli-Roentgen per hour N/A not applicable OGI off gas isolation PA purge alarm PF purge fans PI-purge isolation PRLI pressure relief lines isolated RB reactor building RBESI reactor building exhaust system isolation RBVI reactor building ventilation isolation R/h Roentgen per hour RV release valve SBGT standby gas tanks SBGTS standby gas treatment system scint.

scintillation SD supply ducts SFBI spent fuel building isolation TBESI turbine building exhaust system isolation U1 Unit 1 U2 Unit 2 UL upper level VI vent isolation WGDTI waste pas decay tank isolation 2xBKGND twice the background radiation i

I f

5 l

TABLE 1 OPERATING RDCTOR NOBLE GAS EFFLUENT MONITOR DATA Maximum Maximum Detectable Detectable Calibration Concentra-Release Factor Monitor tion Rate Reference Readout (cpm per Alarm Trip Plant Location (uci/cc)

(Cf/sec)

Nuclide(s)

Range pCf/cc)

Type Setpoint Function

• ARKANSAS NUCLEAR

1. Station 2.38E-02 8.40E-01 188Xe 10-10s cpm 4.20E+07 Beta Tech. specs.

CRI a

ONE-1, vent Russelville, scint.

Arkansas Type: PWR Capacity: 836 MWe BEAVEA VALLEY 1,

1. Auxiliary 5.29E-01 1.56E+01 ssKr and 10-10s eps 1.89E+06 NaI 1.40E+02 cpm *C Diverts air D

Shippingport, butiding 188Xe 1.40E+03 through filters Pennsylvania

2. Auxiliary 1.72E-02 4.00E-01 for all 10-108 cpm 5.81E+07 Beta 1.60E+04 Diverts air Type: PWR building monitors scint.

1.60E+05 through filters Capacity: 800 PRde

3. Auxiliary 2.51E-02 1.42E-02 10-108 3.98E+07 NaI 5.00E+05 cpm WGOTI building 1.00E+06 m BIG ROCK POINT,

1. Main stack 1.41E-01 3.30E+00 Mixture 108-105 cps 4.25E+07 Mal 4.70E-01 Cf/s None Big Rock Pt.,

Michigan Type: BWR Capacity: 65 PRde BROWNS FERRY 1/2/3,

1. Reactor 3.00E-01 1.30E+01 na7Cs 10-1-10s 3.33E+03 G-M 1.00E+02 mR/h Diverts air d

Decatur, Alabama zone mR/h from RB to Type: BWR exhaust SBGT Capacity: 1065 PRde

2. Reactor 1.11E-02 1.39E+00 10-10s cpm 9.00E+07 G-M 9.33E+03 cpm None for all 3 units refueling and turbine building

3. Turbine 1.11E-01 2.30E-01 10-10s cpm 9.00E+07 G-M 3.91E+04 cpm None building roof vent

4. Radwaste 1.11E-02 1.49E-01 10-10s cpm 9.00E+07 G-M 8.81E+04 cpm None building "All monitors have control room alarms.

w

TABLE 1 (Continued)

Maximum Maximum Detectable Detectable Calibration Concentra-Release Factor Monitor tion Rate Reference Readout (cpm per Alarm Trip Plant Location (pCi/cc)

(Ci/sec)

Nuclide(s)

Range pC1/cc)

Type Setpoint Function

• BRUNSWICK 1,

1. Common 8.26E-02 3.35E+00 Mixture 10-10s cps 7.26E+08 Nal 1.41E+05 cps PA Southport, stack cps 4.35E+08 Nal 1.28E+05 cps PA North Carolina

2. Common 1.38E-01 5.60E+00 Mixture 10-108 Type: BWR stack.

cpm 1.18E+07 Beta 1.42E+02 cpm None Capacity: 790 MWe

3. Reactor 8.47E-02 6.91E+00 ssKr 10-108 scint.

buf1 ding cpm 1.25E+07 Beta 1.73+03 cpm OGI

4. Turbine 8.00E-02 5.70E-01 asKr 10-108 building scint.

BKUNSWICK 2,

1. Common 8.26E-02 3.35E+00 Mixture 10-1-10s cps 7.26E+08 Na1 1.41E+05 cps PA Southport, stack North Carolina

2. Common

1. 38E-01 5.60E+00 Mixture 10-1-10s cps 4.35E+08 Nal 1.28E+05 cps PA Type: BWR stack Capacity: 790 MWe

3. Reactor 2.32E-02 1.89E+00 asKr 10-10s cpm 4.31E+07 Beta 5.17E+02 cpm None scint.

building

'd

4. Turbine 2.33E-02 1.70E-01 asgp jo.jo cpm 4.29E+07 Beta 5.47E+03 cpm OGI s

scint.

building 10 -108 cpm 5.00E+07 G-M_

5.00E+02 cpe*

None 0

CALVERT CLIFFS 1/2

1. Condenser 2.00E-02 5.60E+00 88'Cs Lusby, Maryland vacuum for all 2.00E+02 cpm Type: PWR.

discharge monitors 10 -10s cpm 5.00E+07 G-M 2.00E+03 cpm None 0

Capacity: 810 MWe

2. ECCS pump 2.00E-02 1.40E+00 1.00E+03 cpm room ventilation cpm 5.00E+07 G-M 6.00E+02 cpm None

3. Waste 2.00E-02 2.17E+01 100-108 3.00E+02 cpm processing area 10 -10s cpm 5.00E+07 G-M 7.20E+02 cpm None 0

4. Main 2.00E-02 4.46E+01 ventilation i

10 -10s cpm 5.00E+07 G-M 2.00E+05 cpm None 0

5. Containment 2.00E-02 2.36E+01 4.00E+04 cpm atmosphere "All monitors have control room alarms.

l l

l

TABLE I (Continued)

Maximus Maximus Detectable Detectable Calibration Concentra-Release Factor Monitor tion Rate Reference ReeJout (cpm per Alare Trip Plant Location (pCl/cc)

(Cf/sec)

Nuclide(s)

Ranoe pCi/cc)

Type Setpoint Function

• CALVERT CLIFFS 1/2

6. Control 2.00E-02 2.00E+01 100-108 cpe 5.00E+07 G-M 1.20E+02 cpe Closes AID (Continued) room ventilation and ED starts filter fans

7. Fuel hand-2.00E-02 1.60E+01 0

10 -108 cpm 5.00E+07 G-M 6.00E+02 cpe

-None ling area ventilation

8. Access con-2.00E-02 3.30E+00 100-108 cpe 5.00E+07 G-M 1.00E+02 cpe None trol area ventilation

9. Gaseous 2.00E-02 2.50E+01 10-107 cpm 6.67E+07 G-M 1.70E+04 cpe None waste discharge COOK 1/2,

1. Lower con-1.40E-02 N/A Mixture 10-10s cpm 7.14E+07 Scint.

2xBKGND CVI Bridgman, Michigan tainment for all radiogas monitors Type: PWR

2. Ireline 1.60E-02 5.90E-04 10-108 cpe 6.25E+07 G-M 1.25E-05 pCf/cc None Capacity: 1044 fede radiogas

3. Waste gas 4.60E-02 2.20E-03 10-108 cpe 2.17E+07 G-M 1.00E-01 pCl/cc Mone

4. Waste 1.40E-02 4.92E-04 10-10e cpe 7.14E+07 G-M 1.20E-01 pCl/cc None 11guld off-gas monitor

5. Unit vent 4.50E-02 2.72E+00'10-10s cps 2.22E+07 Scint.

2.30E-05 pCf/cc WGDTI radiogas 2.19E+00 process monitor

6. Unit vent 3.50E+02 3.18E+04 10-10e cpe 2.86E+03 Beta 3.50E-01 pCi/cc None high level 2.56E+04 scint.

radiogas monitor

7. Gland seal 4.00E-02 1.10E-02 10-108 cpe 2.50E+07 G-M 5.00E-06 pCi/cc None 1

exhaust monitor "All monitors have control room alarms.

s

TABLE 1 (Continued)

Maximum Maximum Oetectable Detectable Calibration Concentra-Release Factor Monitor tion Rate Reference Readout (cpm per Alarm Trip Plant Location (pci/cc)

(Ci/sec)

Nuclide(s)

Range pCi/cc)

Type Setpoint Function"

COOPER,

1. Elevated 1.45E-01 5.40E+00 Mixture 10-8-108 cps 4.14E+08 Scint.

3.50E+04 eps None Brownv111e, release Nebraska point Type: BWR

2. Elevated 4.76E-02 7.40E-02 587Cs10-10s cpm 2.10E+07 G-M 5.40E+05 cpm None Capacity: 764 Mde

. release point

3. Reactor 4.76E-02 1.00E+00 istCs10-10s cpm 2.10E+07 G-M 1.30E+04 cpm None building vent

4. Reactor N/A N/A

• • Co 10-1-108 mR/h N/A G-M 5.00E+00 mR/h CI, starts 1.00E+01 mR/h SBGTS building vent

5. Turbine 5.56E-02 4.50E+00 187Cs10-10s cpm 1.80E+07 G-M 1.00E+03 cpm None building

e vent

6. Augmented 1.00E-01 5.80E-01 tstCs10-108 cpm 1.00E+07 G-M 1.70E+03 cpm None off gas vent building d

b 10 -10 mR/h 1.20E+03 Ion 1.70E+02 mR/h OGI 8

7. Steam jet 8.33E+02 1.50E+01 Mixture chamber 5.40E+02 mR/h air ejector cpm 3.33E+07 G-M Tech. specs.

PI CRYSTAL RIVER 3,

1. Reactor 3.00E-02 6.37E-01 asKr 10-108 Red Level. Florida building Type: PWR

2. Auxiliary 2.80E-02 2.11E+00 asKr 10-108 cpm 3.57E+07 G-M Tech. specs.

WGOTI Capacity: 797 mie building DAVIS-BESSE, 1.' Station 2.38E-02 8.40E-01 tssXe 10-10s cpm 4.20E+07 Beta Tech specs.

CRI scint.

Oak Harbor, Ohio vent Type: PWR Capacity: 906 mie "All monitors have control room alarms.

TABLE I (Continued)

Maximum Maximum Oetectable Detectable Calibration Concentra--

Release Factor Monitor tion Rate Refererce Readout (cpm per Alarm Trip Plant Location (pC1/cc)

(Ci/sec).

Nuclide(s)

Range pC1/cc)

Type Setpoint Function

• DRE50EN 2,

1. Main stack 9.23E-01 7.50E+01 Mixture 10-1-10s cps 6.50E+07 NaI 7.80E+04 cpm None Morris, Illinois

2. Off gas 1.41E+04 3.60E+01 for all 0

d 10 -10s mR/h 7.10E+01 Ion 8.65E+01 pCi/cc OGI Type: BWR holdup lines monitors chamber Capacity: 772 MWe

3. Reactor 6.67E-05 2.00E-03 10-1-102 mR/h 1.50E+06 G-M 2.10E-06 pCi/cc RBVI and d

building SBGT DRES0EN 3,

1. Main stack 9.23E-01 7.50E+01 Mixture 10-8-108 cps 6.50E+07 Nai 1.30E+03 cps None Morris, Illinois

2. Off gas 1.01E+04 1.06E+02 for all 0

d 10 -10s mR/h 9.90E+01 Ion 4.33E+01 pC1/cc OGI Type: BWR holdup lines monitors chamber Capacity: 773 MWe

3. Reactor 1.35E-04 6.00E-03 10-8-102 mR/h 7.40E+05

' G-M 5.20E-06 pCf/cc RBVI and building SBGT DUANE A;;NOLD,

1. 100m off-6.'72E+01 2.91E-01 esKr used 10-1-10s cps 8.93E+05 Na!

4.00E+03 cps None D

Palo, Iowa gas stack for both 1.50E+04 cps Type: BWR

2. Reactor 2.33E-01 7.92-01 monitors10-10s cpm 4.29E+06 G-M 6.00E+03 cph LA

, Capacity: 515 MWe building o

FARLEY 1,

1. Plant vent 2.85F-02 1.90E+00 80Sr 10-10s cpm 3.51E+07 G-M 5.50E+04 cpm WGOTI Dothan, Alabama stack Type: PWR

2. Condenser 2.85E-02 S.59E-04 80$r 10-108 cpm 3.51E+07 G-M 2.00E+03 cpm None Capacity: 829 MWe

3. Plant vent' 2.85E-02 1.90E+00 80Sr 10-10s cpm 3.51E+07 G-M 7.00E+02 cpm None

~

stack

4. Containment 3.14E-02 7.26E-01 188Ba and 10-10s cpm 3.18E+07 Scint.

1.30E+04 cpm PI and LA is7CS FITZPATRICK.'

1. Reactor 1.11E-02 3.19E-01 asKr for 10-10s cpm 9.00E+07 G-M 2.70E+05 cpm RBESI Scriba, New York building all moni-Type: BWR

2. Refuel 1.11E-02 3.67E-01 tors10-10s cpm 9.00E+07 G-M 2.70E+05 cpm RBESI

' Capacity: 800 Mde floor

3. Turbine 1.11E-02 5.60E-01 10-108 cpm 9.00E+07 G-M 1.80E+05 cpm TBESI building

4. Radwaste 1.11E-02 1.69E-01 10-10s cpm 9.00E+07 G-M 6.70E+05 cpm RWBESI building

5. Stack 8.00E-01 2.49E+00 10-8-10s cps 7.50E+07 Scint.

4.00E+04 cps None "All monitors have control room alarms.

s

~

TABLE 1 (Continued)

Maximum Maxinue Detectable Detectable Calibration Concentra-Release Factor Monitor tion Rate

• eference Readout (cpe per Alare Trip Plant Location (pCi/cc)

(C1/sec)

Nuclide(s)

Rang pCi/cc)

Type Setpoint Function

• FORT CALHOUN 1,

1. Stack went 2.50E-02

1. 44P 90 888Xe for 10-to cpe

4. 00E407 Beta 9.57E+03 cpe*

C1, diverts s

Fzrt Calhoun, all moni-scint.

1.28E+04 cpm air to Nebraska

2. Stack vent 4.17E-01 2.40E+01 tors10-108 cpm 2.40E+06 G-M 8.59E+03 cpm filters Type: PWR 1.71E+04 cpe None Capacity: 445 MWe

3. Condenser 2.50E-02 1.44E+00 10-10e cpe 4.00E+07 Beta 8.50E+02 cpm Closes PCV-978 off gas scint.

3.16E+03 cpm vent

4. Stack vent 2.50E-02 1.44E+00 10-10e cpe 4.00E+07 Beta 2.02E+03 cpm CI, diverts scint.

8.09E+03 cpe air to filters FORT ST. VRAIN,

1. Plant 3.70E-01 5.90E+00 asKr and 10-107 cpm 2.70E+07 Scint.

7.70E+04 cpe f

Pittteville, exhaust C31orado

2. Plant 9.52E+00 1.52E+02 888Xe for 10-107 cpe 1.05E+06 Scint.

2.00E+03 cpe f

Type: HTGR exhaust all moni-Capacity: 330 MWe

3. Air ejector 2.30E+00 3.62E-02 tors10-108 cpe 4.35E+%

Scint.

5.00E+02 cpe LA 5

exhaust

4. Plant -

1.79E-01 2.90E-01 10-108 cpm 5.60E+06 Scint.

3.00E+03 cpn FV6351, WGDTI exhaust

Gas waste 2.90E+00 1.10E-01 10-107 cpm

.3.43E+06 Scint.

2.30E+06 cpe e.haust

GINNA,

1. Intermedf-1.80E-01 2.12E+00 asKr 10-108 cpm 5.55E+06 G-M 3.50E+04 cpm CVI Ontario, New York ate building Type: PWR

2. Intermedi-3.00E-02 6.37E+00 10-M8 cpe 3.33E+07 G-M 1.10E+03 cpm g

Capacity: 470 W e ate building

3. Turbine 1.36E+00 3.20E-01 issXe 10-10e cpe 7.35E+05 Na1 1.50E+03 cpe Nonc building HA00AM NECK-

1. Main stack 3.13E-02 4.90E+00 85Kr 10-108 cpm 3.20E+07 G-M 7.00E+03 cpe WGOTI Haddas Necv Connecti~#4 Type: U Capactti. 550 We "All monitors have control room alanes.

4 m.

i TABLE 1 (Continued)

Maximum Maximum Detectable Detectable Calibration Concentra-Release Factor

. Monitor tion Rate Reference Readout (cpm per.

Alarm.

Trip.

Plant

. Location (pCi/cc)

(Ci/sec)

Nucliae(s)

Range pCi/cc)

Type Setpoint

. Function *'

D I

HATCH 1,.

1. Main stack 2.18E+00 1.03E+01 Mixture 10-8-10* cps 2.75E+07 NaI '

1.54E+04 pC1/s None Baxleyi Georgia for all 5.72E+05 pCi/s Type: BWR-2.- Recombiner 2.73E-01 1.08E-03 monitors10-108 cps 2.20E+08 Beta 3.67E+02 pCi/s None Capacity: 4700 MWe building scint.

4.02E+04 pCi/s

3. Reactor 5.13E-2 7.26E+00 10-10s cpm 1.95E+07 Beta 3.67E+02 pCi/s None building scint.

4.02E+04 pC1/s vent stack

4. Main stack Being eval-Being eval-100-105 R/h Being eval-Ion Being evaluated None uated by uated by uated by chamber by licensee licensee licensee licensee b

~ HATCH 2,'

1. Main stack 2.18E+00 1.03E+01 Mixture 10-8-10s cps 2.75E+07 NaI 1.54E+04 pCi/s None Baxley, Georgia for all 5.72E+05 pCi/s Type: BWR '

2. Reactor-4.60E-02 3.69E+00 monitors10-108 cpm 2.18+07 Beta.

3.67E+02 pCi/s None Capacity: 700 MWe

-building

.scint.

4.02E+04 pCi/s vent stack'

~;G

3. Main stack Being eval-Being eval-100-105 R/h Jeing eval-Ion Being evaluated None uated by uated by uated by

' chamber by licensee licensee licensee Itcensee HUMBOLDT BAY,

1. Ventilation 4.29E-01 1.00E+01 Mixture 10-10s cpm 2.33E+06 Gamma 5.00E-02 Ci/s None Eureka, California-stack scint.

Type: BWR Capacity: 63 MWe INDIAN POINT 2,

1. Plant vent 3.00E-03 2.83E-01 Mixture 10-108 cpm 3.33E+08 G-M 1.70E+04 cpm WGDTI Buchanan, New York

2. Main 1.00E-01 3.80E-03 for all 10-10s cpm 1.00E+07 G-M 8.50E+03 cpm h

Type: PWR condenser monitors Capacity 864 MWe

3. Containment 5.00E-02 9.40E-01 10-108 cpm 2.00E+07 G-M 2.70E+04 cpm PI and PRLI

. INDIAN POINT 3,

1. Penetration 6.67E-02 1.22E+00 asKr and 10-8-10s cpm 1.50E+07 G-M 1.00E+04 cpm CVI-

.Suchanan, New York area 188Xe Type:.. PWR

2. Vent stack 2.22E 4.20E-03 asKr and 10-8-10s cpm

4. 50E+ 09 G-M 4.00E+03 com WGDTI 188Xe Capacity:.873 MWe' 2.08E-02 2.00E-03 Mixture 10-8-10s cpm 4.80E+07 G-M 1.40E+04 cpm 1

.3. Tur51ne.

- butiding "All monitors have control room alarms.

a

TABLE 1 (Continued)

Maximum Maximum Oetectable Detectable Calibration Concentra-Release Factor Monitor tion Rate Reference Readout (cpm per Alarm Trip Plant Location (pC1/ce)

(Ci/sec)

Nuclide(s)

Range pCi/cc)

Type Setpoint Function *

KEWAUNEE,

1. Containment 1.00E-03 1.53E-02 askr3 10-e.jo-s 1.67E+07 G-M 4.40E+03 cpm CVI Ctriton, Wisconsin ventilation 1.00E-03 388Xe pCi/cc 1.21E+06

. Type: BWR stack b

Capacity: 521 MWe

2. Auxiliary 1.00E-04 1.90E-03 asKr' 10-7-10-4 4.54E+08 G-M 9.00E+03 cpa k-building 1.00E-04 888Xe pCi/cc 7.54E+07 9.00E+04 cpm ventilation stack

3. Auxiliary 1.00E-04 1.90E-03 asKr 10-7 4 6.67E+08 G-M 1.00E+05 cpm

'k building 1.00E-04 issXe pCi/cc 4.50E+07 ventilation stack

4. Condenser 1.00E-03 9.50E-07 esKr 10-e_10-3 5.00E+07 6.00E+02 cpm None 1.00E-03 tasXe pC1/cc 2.90E+06 G-M

5. Containment 1.00E-03 1.53E-02 asKr 10-s.jo-s 6.67E+07 Scint.

3.00E+03 cpm CVI O-1.00E-03 388Xe p;i/cc 3.10E+07 1.00E+04 cpm

6. Control 1.00E-03 Factored in asKr 10~5-10-s 2.50E+06 4.00E+02 cpr Diverts air.

room 1.00E-03 auxiliary tasXe pCi/cc 7.14E+07 to filters ventilation building l

LACROSSE.

1. Outlet of 1.93E+01 6.40E+02 tssXe and 10-10s cpm 5.18E+04 NaI 3.62E+05 cpo CRI Lacrosse, Wisconsin 10-minute asKr for 7.69E+05 cpm Type: BWR holdup all mont-Capacity: 48 MWe

2. Outlet of 4.63E+01 7.60E+03 toes10-105 cpm 2.16E+03 G-M 1.24E+04 cpm None storage 2.64E+04 cpm tanks

3. CB exhaust 1.78E-01 5.90E+00 10-10s cpm 5.62E+06 Nal 1.21E+05 cpm CRI 2.60E+05 cpm

4. Stack 5.28E-02 1.70E+00 10-108 cpm 1.89E+07 Na1 5.09E+03 cpm None 5.67E+03 cpm MAINE YANKEE,'

1. Primary 2.33E-02 6.40E-01 asKrl 10-10s cpm 4.30E+07 G-M 1.00E+03 cpm PI Wiscasset, Maine vent stack 9.09E-01 2.50E+01 assXe 1.10E+06 Type: PWR Capacity: 760 MWe "All monitors have control room alarms.

.~

i TABLE 1 (Continued)

Maximum Maximum Detectable Detectable Calibration Concentra-Release Factor Monitor tion Rate Reference Readout (cpm per Alarm Trip-Plant' Location (pCf/cc)

(Ci/sec)

Nuclide(s)

Range pCi/cc)

Type Setpoint Function

• b MILLSTONE 1/2,

1. Stack (U1) 8.72E-01 7.00E+01 Mixture 10-s.jo cps 6.88E+07 NaI 2.00E+03 cps None s

3.90E+03 cps

'Waterford,,

Connecticut

2. Roof vent 1.34E-01 6.08E+00 asKr 10-108 cpa 7.45E+06 Scint.'

9.00E+03 cpm None

, Type: BWR; PWR (U2)

Capacity: 654 We 7% MWe MONTICELLO,

1. Plant stack 8.00E-01 1.50E+00 Mixture 10-8-108 cps 7.50E+07 NaI 8.00E+04 cps OGI, RBVI d

.Monticello,

. 2. Reactor 9.90E-03 7.00E-01 for all 10-2-102 mR/h 1.01E+04 G-M 3.00E+00 mR/h SBGTS Minnesota building monitors Type: BWR vent plenum Capacity: 536 MWe

3. Reactor 5.00E-03

3. ME+00 10-104 cps 1.20E+08 Beta 6.00E+01 cps

.None

~

building scint.

g vent D

CINE MILE POINT, 1.' Stack 3.00E+01 5.00E+01 887Cs for 10-8-108 cps 2.00E+06

- NaI 1.00E+03 cps None Scriba, New Ycrk both 2.00E+03 cps Type: BWR monitors yCapacity: 610 MWe

. 2. Stack 1.00E+02 1.00E+00 10-108 cpm 1.00E+08 Beta-1.00E+05 cpe scint.

l D~

MORTH ANNA 1,

1. Auxiliary 2.22E-02 2.30E-01 asKr '"10-108 cpm 4.50E+07

.G-M 4.00E+04 cpe PI Mineral, Virginia building 8.55E-01' 8.90E+00 888Xe 1.17E+06 8.00E+04 cpe Type: PWR

2. Auxiliary 2.22E-02 1.68E+00 esKr 10-108 cpm 4.50E+07 G-M 2.00E+02 cpe None

. Capacity: 907 MWe building 8.55E-01 6.47E+01 888Xe 1.17E+06 4.00E+02 cpm

3. Auxiliary 2.22E-02

-3.50E-03 asgp 30.jos cpm 4.50E+07 G-M 5.00E+04 cpm n.

butiding 8.55E-01 1.34E-01 888Xe 1.17E+06 1.00E+05 cps

-4. Turbine 8.33E+01 1.96E+00 asKr 10-10s cps 1.20E+04 G-M 5.00E+02 cpm Diverts AE to building.

2.50E+03 6.90E+01 188Xe 4.00E+02 1.00E+03 cpm containment 1.47E-01 8.08E+00 esKr 10-107 cpm 6.80E+07.

Scint.

1.50E+03 cpm None

5. Auxiliary ^ 3.70E-01 2.04E+01 as:Xe 2.70E+07 2.00E+03 cpe

' building I

'"All monitors have control room alarms.

TABLE 1 (Continued)

Maximum Maximum

-Detectable Detectable Calibration Concentr -

Release Factor a

Monitor tW Rate Reference Readout (cpm per Alarm Trip Plant Location (pCf/cc)

(Ci/sec)

Nuclide(s)

Ranoe pCi/cc)

Type Setpoint Function *

'OCONEE 1/2/3,

1. Unit vent 4.00E+03 9.44E+04 ssKr 10-1-10s cpm 2.50E+02 G-M None

~None Seneca, South

. monitor 8.77E-03 888Xe 1.14E+08 Beta 3.20E-04 pCi/cc Ctrolina scint.

Type: PWR 2.. Gaseous 2.00E+01 3.78E-01 asgp jo-a.jo ep, c.M Tech. specs.

None s

Capacity: 860 MWe

=- t? dis-2.70E-02 188Xe 3.70E+07 Beta cv Me scint.

monite D

3. Interim 2.SOE-02 2.09E-01 188Xe 10-1-108 cpm 3.85E+07 Na!

8.30E-06 pC1/cc None rindwaste 2.50E-05 pC1/cc building monitor 0

d b

OYSTER C9EEK,

1. Turbine 1.90E+03 5.00E+02 80Co and 10 -10s mR/h 5.26E+02 Ion 1.13E+04 a.R/h OGI.

Toms Riner, building 187Cs chamber 1.50E+04 mR/h g New Jersey

2. Stack gas ' 4.92E-01 5.00E+01 10~8-10s cps 1.22E+08 NaI 5.25E+03 cps None Type: BWR 7.00E+03 cps Capacity: 620 MWe PALISADES,

1. Main stack 6.67E+01 3.00E+00 188Xe 102.jo cpm 1.50E+04 NaI 8.00E+03 cpm None s

South Haven, Michigan Type: PWR Capacity: 635 MWe D

PEACH BOTTOM 2,

1. Main stack 1.08E+02 1.30E+02 asKr for 10-8-108 cps 5.58E+05 Na!

4.50E+02 cps None.

.P ach Bottom, all mon-2.00E+04 cps Pennsylvania

2. Main stack' 8.33E+01 1.30E+02 itors 10-1-108 cps 7.20E+05 Na!

4.50E+02 cps None Type:. BWR Capacity: 1051 MWe 2.00E+04 cps

3. Roof vent

'1.45E-01 4.50E+01 10~1-10s cpm 6.90E+08 Beta 2.70E+03 cpm None scint.

5.00E+03 cpm.

4. Roof vent 1.54E-01 4.50E+01 10-8-10s cpm 6.50E+08 Beta 1.98E+03 cpm None scint.

5.00E+03 cpm "All monitors have control room alarms.

..i

4 TABLE 1 (Continued)

Maximum Maximum Detectable Detectable Calibration Concentra-Release Factor Monitor tion Rate Reference Readout (cpm per Alarm Trip Plant' Location (pC1/cc)

(Ci/sec)

Nuclide(s)

Range pCf/cc)

Type Setpoint Function

• b cps 5.58E+05 Na!

'4.50E+02 cps None

-PEACH BOTTOM 3,.

1. Main s'.ack 1.08E+02 1.30E+02 asKr for 10-8-108 2.00E+04 cps Peach Bottom '

all mon-7.20E+05 Na!

4.50E+03 cps None

2. 'ain stack 8.33E+01 1.30E+02 itors 10-8-108 cps Pennsylvania e

Type: BWR 2.00E+04 cps Capacity:.1035 MWe

3. Roof vent 1.75E-01 4.20E+01 10-8-10s cpm 5.70E+08 Beta 3.45E+03 cpm None scint.

5.56E+03 cpm -

4. Reof vent 1.61E-01 4.20E+01 10-8-10s cpm 6.20E+08 Beta 2.70E+03 cpm.

None scint.

5.56E+03 cpm b

PILGRIM 1,

1. Main stack 5.94E-(2 5.bOE+00

-Mixture.

10-8-10e cps 1.01E+09 Na!

5.36E+05 cpa None

Plymouth, for both 1.07E+06 cpm Malsachusetts 2.. Reactor 5.41E->2 5.10E+00 monitors ia-8-108 cps 1.11E+09 Na!

7.06E+05 cpm None 9.41E+05 cpm

'Typer BWR building

, Capacity: 670 MWe vent

e cpm 1.50E+09 G-M 3.00E+03 cpm WGOTI, diverts POINT; BEACH 1,

1. Auxiliary E.67E-04 2.90E-02 Mixture 10-108 Two C Jeks,.

building.

for all AB air to Wisconsin monitors fi.:ars Type: PWR

1. Drum atea 2.70E-04 1.30E-02 10-10s cpm 3.70E+09 G-M 4.00E+03 cpm None Capacity: 495 MWa 3. Gas.

'1.10E-02 6.10E-02 10-108 cpm 9.10E+07 eA.

1.00E+04 cpm None s+. ripper cpm 1.10E+06 Beta 8.00E+03 cpm None

4. CAE duct 9.09E-01 3.10E-02 10-108 scint.

5. State air 1.15E-02 1.70E-03 10-10s cpm 8.70E+07 G-M 5.00E+04 cpm None ejector

6. Containment 8.33E-02 1.19E+00 10-108 cpm

1. 20E+.

G-M 3.00E+03 cpm PI'

All monitors have controf room alarms.

TABLE 1 (Continued)

Maxi.aum Max 1ium Detectable Detectable Calibration Concentra-Release Factor Monitor tion Rate Reference Readout (cpm per Alare Trip Plant' Location (pCi/cc)

(Ci/sec)

Nuclide(s)

Range pCi/cc)

Type Setpoint Function *

' POINT BEACH 2,-

1. Auxiliary 6.67E-04 2.90E-02 Mixture 10-10s cpm 1.50E+09 G-M 3.00E+03 cpm WGDTI, diverts Two Creeks, building for all AB air to Wisconsin monitors filters Type: PWR

2. Drum area 2.70E-04 1.30E-02 10-108 cpm 3.70E+09 G-M 4.00E+03 cpm None Capacity: 495 We

3. Gas 1.10E-02 6.10E-02 10-108 cpm 9.10E+07 G-M 1.00E+04 cpm None stripper

4. CAE duct 9.09E-01 3.10E-02 10-108 cpm 1.10E+06 Beta 8.00E+03 cpm None scint.

5. Steam air 1.69E-01 1.70E-02 10-10s cpm 5.90E+06 G-M 4.00E+02 cpm None ejector

6. Containment 1.00E-01 1.29E+00 10-108 cpm 1.00E+07 G-M 1.00E+03 cpm PI' PRAIRIE ISLAND 1/2,

1. Reactor 1.90-01 2.90E+00 188Xe 10-108 cpm 5.25E+06 G-M 6.00E+03 cpm PI Red Wing, building O Minnesota

2. Reactor

4. s E-01 6.20E+00 188Xe 10-10" cpm 2.50E+06 G-M 2.50E+03 cpm PI M *: PWR building Capacity: 507 MWe-

3. Auxiliary 1.00E+00 1.37E+01 188Xe 10-10e cpm 1.00E+06 G-M 1.00E+03 cpm VI and ABSVS building

4. Auxiliary 1.00E+00 1.93E+01 188xe 10-108 cpm 1.00E+06 G-M 1.00E+03 cpm VI and ABSYS j

building

5. Air ejector 1.50E-01

.7.10E-04 188Xe 10-108 cpm 6.67E+06 G-M 1.00E+03 cpm None

6. Spent fuel 1.17E-02 1.00E-01 asKr 10-10e cpm -

8.55E+07 G-H 1.00E+04 cpm VI and ABSYS pool

7. Radwaste 1.00E+00 2.90E+00 888Xe 10-108 cpm 1.00E+06 G-M 3.00E+03 None building QUAD ITIES 1/2,

1. Main stack 7.50E-01 1.00E+02 Hixture 10~3-108 cps 8.00E+07 Nal 3.75E+02 cp';D None Co dova Illinois for all 8.00E+02 cps 8

d

'sype: BWR

2. Off gas 2.00E+04 2.50E+01 monitors 10 -10s mR/h 5.00E+01 Ion 3.75E+04 pC1/s

.T -

Capacity: 760 MWe hold pipe chamber 3.00E+04 pCi/s

,3. Reactor 1.00E-01 5.00E+00 10-2 102 mR/h 1.00E+03 G-M 1.00E+00 mR/h RBVI and SBGT building 2.00E+00 mR/h "All monitors have control room alarms.

j

4 TABLE I (Continued)

Maximum Maximum Detectable Detectable Calibration Concentra-Release Factor Monitor tion

. Rate Reference Readout (cpm per Alare Trip Plant Location (pCi/cc)

(C1/sec)

Nuclide(s)

Ranae pCi/cc)

Type Setpoint Function

• RANCHO SECO 1,

1. Auxiliary 3.85E-02 1.75E+00 issXe for 10-10e cpm 2.60E+07 Scint.

6.00E-04 pC1/cc Stops PF Clay Station.

-building all mon-California itors

. Type: BWR

2. Auxiliary 3.85E-02 1.35E+00 10-10e cpm 2.60E+07 Scint.

1.00E-03 pCi/cc WGOTI Capacity: 873 MWe building

3. Auxiliary 3.850-02 4.60E-01 10-108 cpm 2.60E+07 Scint.

1.00E-03 pCi/cc Stops PF building ROBINSON 2, 1.' Plant vent 1.00E-02 4.10E+00 issXe 10-108 cpm 1.00E+08 G-M 1.02E+04 cpm

• WGDTI Hartsville, exhaust cpm 1.00E+07 G-M 5.00E+03 cpm FHBVI (LL)

South Carolina

2. Fuel 1.00E-01 4.00E+01 308Cd and 10-108 Type: PWR handling as7Cs Capacity: 665 MWe building

3. Fuel 1.00E-01 5.30E+01 10'Cd and 10-10e cpm 1.00E+07 G-M 3.80E+03 cpm FHovl (UL) handling 887Cs building

4. Plant vent 7.14E-02 7.50E+0i 188Xe 10-10e cpm 1.40E+07 G-M None None

5. Condenser 1.00E-01 1.40E-El 808Cd 10-10e cpm 1.00E+07 G-M 4.75E+03 cpm Diverts AI exhaust SALEM 1,

1. Containment 2.27E-06 7.24E-04 s*Mn 10-10e cpm 4.40E+11 Gamma 7.00E+03 cpm CI and PI scint.

Sales, New Jersey

2. Containment 4.76E-01 2.80E+t1 188Xe and 10-10e cpm 2.10E+06 G-M 3.00E+04 cpm CI and PI Type: PWR ssKr capacity: 1090 MWe

3. Containment 3.33E-04 3.60E-0.t 188Ba 10-108 cpm 3.00E+09 Gamma 1.50E+04 cpm CI and PI scint.

4. Plant vent 2.78E-02 1.60E+00 assXg 10-108 cpm 3.60E+07 G-M 5.00E+05 cpm None

5. Waste gas 1.36E+04 3.50E+01 esKr 10-10e cpm 7.34E+01 G-M 2.00E+04 cpm WGDTI 5.00E+01 888Xe 2.00E+04

6. Condenser 2.22E-01 3.00E+00 188Xe 10-10e cpm 4.50E+06 G-M 1.00E+04 cpm None "All monitors have control room alarms.

TABLE 1 (Centinued)

Maximum Maximum Detectable Detectable Calibration Concentra-Release Factor Monitor tion Rate Reference Readout (cpm per Alare Trip Plant Location (pC1/cc)

(C1/sec)

Nuclide(s)

Range pCi/cc)

Type Setpoint Function l

SAN ONOFRE 1,

1. Stack 1.79E-01 6.00E-01 ssKr 'P 10~ -108 cpm 5.60E+06 G-M 2 x Inservice PI

-San Clemente.

4. 76E-01 888Xe 2.10E+06 Reading C:ilifornia

2. Stack 5.41E-03 6.00E-01 asKr 10-8-108 cpm 1.85E+08 G-M 8.00E+04 cpm WGOTI

-Type: PWR 1.33E-02 188Xe 7.50E+07 Capacity: 436 MWe

3. Stack 1.89E-02 6.00E-01 asKr 10-8-10e cpm 5.30E+07 G-M 2 x BKGNO None 5.00E-02 issXe 2.00E+07 ST. LUCIE 1,

1. Reactor 2.77E-02 1.83E+00 Mixture 10-10e cpm 3.61E+07 Beta 2.00E+04 cpm None Ftrt Pierce. Florida auxiliary for both scint.

Type: PWR.

building monitors Capacity: 777 MWe

2. Fuel 2.70E-02 3.06E-01 10-10e cpm 3.70E+07 Beta 5.00E+04 cpm None handling scint.

building SURRY 1/2

1. Turbine.

2.06E+02 1.41E-01 ssKrl b

10-108 cpm 4.85E+03 G-M 2.00E+04 cpo Diverts air Grcvel Neck.

building

.I.21E+01 188Xe 8.25E+04 1.00E+05 cpm from vent to Virginia (U1) cont.

Type: PWR

2. Turbine 2.06E+02 1.14E-01 asKr 10-10e cpm 4.85E+03 G-M 1.07E+04 cpa Diverts air b

Capacity: 775 MWe building 1.21E+01 888Xe 8.25E+04 1.07E+05 cpm from vent to (U2) cont.

3.'Ventila-9.62E-03 1.38E+00 ssKr 10-10ecpm 1.04E+08 Beta 1.00E+05 cpm None tion vent 2.53E-02 assXe 3.96E+07 scint.

3.00E+05 cpm

4. Auxiliary 9.62E-02 3.57E-02 esKr 10-10e cpm 1.04E+07 Beta 7.50E+04 cpm WGOTI building 2.53E-01 issXe 3.96E+06 scint.

1.50E+05 cpm CVPV closed THREE MILE

1. Station 2.82E-02 1.44E+00 887Cs10-10e cpm 3.55E+07 Beta 5.00E+03 cpm WGOTI9 ISLAND 1/2 vent (U1) scint.

Middletown,

2. Station 1.00E+02 4.72E+01 10-10s cpu 1.00E+08 Beta.

1.00E-05 pC1/cc Not available Pennsylvania vent (U2) scint.

Type: PWR Capacity: 792, 880 MWe.

"All monitors have control room alarms.

.....i.-

TABLE 1 (Continued)

Maxieue Maximus Detectable Detectable Calibration Concentra-Release Factor

-Monitor tion Rate Reference Readout (cpm per Alare Trip -

Plant Location

-(pCi/cc)

(Cf/sec)

Nuclide(s)

Range pCi/cc)

Type Setpoint Function"

TROJAN,

1. Containment 2.50E+02 5.83E+03 188Xe and 10-10s cpe 4.00E+03 G-M 4 x BKGNO Closes EV-and SD Prescott, Oregon

2. Auxiliary 2.86E-02(as) 3.33E+01 esKr for 10-108 cpm 3.50E+07 Beta 2 x BKGNO Closes EV all scint.

and 50

' Type: <PWR building monitors D

Capacity: 1080 MWe

3. Auxiliary 2.86E-02(as) 1.42E+00 10-10e cpe 3.50E+07 Beta 2.00E+03 cpe None building scint.

2.00E+04 cpm

4. Turbine 2.86E+00 1.61E-01 10-10s cpm 3.50E+05 Beta 3.50E+04 cpe None building scint.

3.50E+05 cpe 1.50E+05 cpm cpe 2.03E+07 G-M 1.60E+03 cpe CI TURKEY POINT 3/4,-

1. Auxiliary 4.93E-02 8.15E-01 Mixture 10-108 F1Grida City, Florida building for all Type: PWR

2. Auxiliary 7.14E-01 3.30E+01 monitors10-108 cpe 1.40E+06 G-M 1.00E+06 cpe LA

. Capacity: 666 mie building cpm 1.43E+08 G-M 3.60E+04 cpe WGOTI 1 El

3. Plant vent 6.99E-03 3.30E-01 10-108

1. Plant 1.00E-02 8.00E-01 Mixture 10-10e cpe 1.00E+08 Scint.

6.00E+04 cpe None VERMONT YANKEE, ~

stack Vernon, Vermont Type: BWR Capacity: 504 MWe YANKEE R0WE,

1. Primary 3.03E-02 3.00E-01 Mixture 10-108 cpe 3.30E+07 Beta 3.50E+03 cpe" None Rowe, Massachusetts vent stack scint.

-Type: PWR Capacity: 175 mie ZION 1/2,

1. Auxiliary' 1.00E-02 1.90E+00 ssKr 10-e.jo-2 None G-M 6.00E+04 pCi/s None pCi/cc

-Zion Illinois building

' Type: PWR.

2. Auxiliary 1.11E-03 2.10E-01 ssKrl cpe 9.00E+08 G-M 6.00E+04 pCi/s None --

10-108

' Capacity: 1010 Mde.

building 1.11E-02 2.10E+00 888Xe 9.00E+07

^

3. Containment 1.00E-02 2.77E-01 asKr 10-s.jo-2 None G-M 6.00E+04 pCf/s PF stopped pCf/cc "All sonitors have control room alarus.

~

TABLE 1 (Continued)

Maximum Maximum Detectable Detectable Calibration Concentra-Release Factor Plant

, Monitor tion Rate Reference Readout (cpm per Alarm Trip Location (pCf/cc)

(C1/sec)

Nuclide(s)

Range pCi/cc)

Type Setpoint Function *'

l ZION 1/2

'(continued).

4. Gas decay' 1.00E+02 2.36E+01 asKr 10-2-108 None G-M 6.00E+04 pCi/s

. Isolate RV tank pC1/cc

5. Miscellan-1.00E+02 5.60E-02 asKr 10-8-102 None G-M 6.00E+04 pC1/s None:

eous vents pCi/cc

6. Condenser 1.54E-02 1.00E-02 asKrl 10-10s cpm 6.50E+0/

G-M 6.00E+04 pC1/s None air ejector 4.00E-01 2.70E-01 888Xe 2.50E+06 "All monitors have control room alarms.

'3 a -.

n

FOOTNOTES FOR TABLE 1 a.

2.38E-02=2.38x10 2, b.

The first value indicates the high alarm setpoint.

The second value indicates the high-high alarm setpoint.

c.

All alarm setpoint values were submitted under new technical specifica-tions and are not presently in use.

d.

Units for calibration factor are given in mR/hr/pCi/cc.

e.

The first value indicates the alarm setpoint for Unit 1.

The second value indicates the alarm setpoint for Unit 2.

f.

Closes VU-6351, diverts gas to gas waste vacuum tank, shuts down outside vent, and begins recirculation of ventilation.

g.

Isolates the following:

(1) RCV-014 gas decay tank release valve (2) Auxiliary building exhaust fan 1C (3) Auxiliary building exhaust fan 1P (4) Auxiliary building supply air handling units lA and 1B (5)

Intermediate building exhaust fans lA or 18 and 1C h.

Diverts air ejector exhaust to containment, shuts down flash evaporator, and isolates steam to condenser primary ejectors.

i.

Three separate controls are activated to prevent excessive radiogas release to the environment.

(1) This signal opens the containment isolation valves to allow venting the air ejector discharge to containment.

Then 50V-ll69 is de-energized and PCV-ll69 changes position to vent the air ejector to containment via the blower which is started by this signal.

(2) PCV-1133 (steam to condenser priming ejectors) is closed if open and/or denied permission to be opened.

This protects the detector from overtemperature and protects against an uncontrolled release since the priming ejector discharge is not monitored by this channel R-15.

l (3) The flash evaporator is shut down by this signal to prevent activity l

from the extraction steam from getting to the atmosphere or contamina-ting the flash evaporator.

This channel R-15 will trip the brine recycle pumps, brine heater drain pumps, distillate pumps, and the vacuum pump of the flash evaporator.

j.

The monitor was calibrated twice, once with 85Kr and once with 188Xe.

22-

l l

l k.

Stops supply and exhaust fans, starte auxiliary building special vent fans, closes all boundary dampers, maintains vacuum in auxiliary building, and routes exhaust through HEPA filters.

1.

First valve is the alarm setpoint when one blower is used.

The second valve is the setpoint when two blowers are used.

80Sr was used by the manufacturer to calibrate the monitors but the m.

officials at the plant used asKr and tasXe.

n.

Closes containment vacuum pump discharge to heat exchanger valves and closes decay tanks. atmospheric vent through GW charcoal filter.

o.

The values given are the setpoints above background.

p.

187Cs was used by the manufacturer to calibrate the monitors but the officials at the plant used asKr and 188Xe.

q.

Trips the following:

(1) Fuel handling building supply fans (2) Auxiliary building supply fans (3) Reactor building supply fans (4) Reactor building purge system r.

Within 120 days, this monitor will be changed to a monitor identical to the one in the containment.

23 L

TABLE 2 COMPARISON OF N0BLE GAS EFFLUENT MONITORS AT OPERATING REACTORS P1rnts with mon? tors Plants with monitors Plants with monitors Plants with monitors cap:ble of detecting that have an upper that have an upper notcapableofdetectd ralctses greater than limit between 10 and limit between 0.5 and ing releases above 100 Ci/sec. 100 Ci/sec.

10 Ci/sec.

0.5 Ci/sec.

Ccck 1 Beaver Valley 1 Arkansas 1 Indian Point 2 Cock 2 Browns Ferry 1 Big Rock Point 1 Indian Point 3 Fcrt St. Vrain Browns Ferry 2 Brunswick 1 Kewaunee Oconia 1 Browns Ferry 3 Brunswick 2 Point Beach 1 Ocen o 2 Calvert Cliffs 1 Cooper Station Point Beach 2 Ocen33 Calvert Cliffs 2 Crystal River 3 Yankee Rowe Perch Bottom 2 Dresden 2 Davis Besse Three Mile Island 2 PEch Bottom 3 Dresden 3 Duane Arnold Quad Cities 1 Fort Calhoun Farley 1 Quad Cities 2 Hatch 1 FitzPatrick Hatch 2 Ginna Humboldt Bay Haddam Neck Maine Yankee Lacrosse Millstone 1 Millstone 2 Nine Mile Point Monticello North Anna 1 Palisades Oyster Creek Pilgrim 1 Prairie Island 1 Rancho Seco Prairie Island 2 Salem 1 Robinson 2 San Onofre Turkey Point 3 St. Lucie Turkey Point 4 Surry 1 Surry 2 Three Mile Island 1 Trojan Vermont Yankee Zion 1 Zion 2 24

U.S. NUCLEAR RE'!ULATORY COMMISSION 7

BIBLIOGRAPHIC DATA SHEET NUREG-0592 1 TITLE AND SUBTITLE (Add Volume No., etaparceresfr/

2. (Leave 6/m41 Compilation of Reported Noble Gas Effluent Monitor Capabilities at Operating Nuclear Power Plants

3. neclPIENT S ACCESSION NO.

7. AUTHOR $)

S. DATE REPORT COMPLETED I Y[9" J. E. Fialkovich, S. B1ock "yfo'y* ember 5 1

9. PE RFORMING ORGANIZATION N AME AND M AILfNG ADDRESS (/nclude Isp Codel DATE REPORT ISSUED Division of Operating-Reactors wonts lve4R Office of Nuclear Reactor Regulation an, n 1990 U. S. Nuclear Regulatory Commission s (tes'v, wen *>

Washington, D. C.

20555

8. (Leeve Nanki

12. SPONSORING ORGANIZATION NAME AND MAILING ADDRESS (/nclude lap Codel

10. PROJECT / TASK / WORK UNIT NO.

n. CONTRACT NO.

Same as above

13. TYPE OF REPORT PE RIOD COVE RED (/nclusive deersf Technical Report

15. SUPPLEMENTARY NOTES

14. (Leeve elekJ

16. ABSTR ACT 000 words or less)

A compilation of noble gas effluent monitoring systems was made for all nuclear power plants operating in the United States in order to characterize their effec-tiveness in monitoring an event comparable to the Three Mile Island accident.

This report summarizes the capability of existing systems with respect to measure-ment of the maximum detectable concentrations (pCi/cc) and release rates (Ci/sec),

readout ranges, and any automatic isolation and/or alarm functions they are designed to perform.

17. KEY WORDS AND DOCUMENT AN ALYSIS 17a. DESCRIPTORS 17b. IDENTIFIERS /OPEN.EN DE D TERMS i

i

18. AVAILA8ILITY STATEMENT

19. SECURITY CLASS (This toport) 21.NO. OF PAGES Unc1assified

20. SECURITY CLASS (This pegel

22. PRICE Unlimited S

~RCFORM336 (7 77)

UNITED STATES f.

7 NUCLEAR REGULATORY COMMisstON W ASHINGTON, D. C. 20565 postaos aNo yass raio U.E NUCLE AR RTGULATORY OFFICI AL SU$lNESS commiss6on PEN ALTY FOR PRIVATE USE, $300

.g L

J L L Cn > > t os t J 4t. n n tJ S

.M u a

5LLY PuoLAL ULL JM-ie s nou-t3KafwH Lh4tr 115 1 LJed

.v A 5 il (s o T L.

oc c ) S '; 5 I

f

_a EY