ML20069L574

Forwards Info for post-implementation Review of NUREG-0737, Item II.B.3, Post-Accident Sampling Sys, Per Util .Certain Requested Info Will Not Be Available Until After Completion Date of 831231

ML20069L574
Person / Time
Site:	Davis Besse
Issue date:	04/25/1983
From:	Crouse R TOLEDO EDISON CO.
To:	Stolz J Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM 931, TAC-44432, NUDOCS 8304280245
Download: ML20069L574 (39)

Text

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. 1 TOLEDO EDISON Docket No. 50-346 a[cm License No. NPF-3 "is> 2maai Serial No. 931 April 25, 1983 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz Operating Reactor Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Stolz:

Your letter dated July 21, 1982 (Log No. 1036) requested information for a post-implementation review of NUREG-0737 Item II.B.3 Post-Accident Sampling System. We are providing the requested information as an attachment per our letter of September 29, 1982 (Scrial No. 863) for the Davis-Besse Nuclear Power Station Unit No. 1.

As discussed in your Order Confirming our commitments dated March 14, 1983 (Log No. 1245), t1e schedule for completing the Post-Accident

^

Sampling System is December 31, 1983. Therefore, some of the information needed-to provide responses to your requested information will not be available until after December 31, 1983. These items are indicated in our responses.

Very truly yours, ff e-L RPC:LDY:lah attachment cc: DB-1 NRC Res!. dent Inspector 1

PDR DOC PDR P

THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652

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Docket No.,50-346 License No. NPF-3

' Serial No. 931 April 25, 1983 Page 1.

Attachment 1

. Criterion: -(1) The licensee shall have the capability to promptly

-obtain' reactor coolant samples and containment atmos-phere samples. The combined time allotted for sampling and analysis should be 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> or less from the time a decision is made to take a sample.

Clarification: Provide information on sampling (s) and analytical laboratories locations including a discussion of relative elevations,-distances and methods for sample transport. Responses to this item should elso include a discussion of sample recirculation, sample handling and analytical times to demonstrate that the three-hour time limit will be met (see (6) below relative to radiation exposure). Also describe provisions for sampling during loss of off-site power (i.e. designate an: alternative backup power source,'not necessarily the vital (Class IE) bus, that can be energized in sufficient time to meet the three-hour sampling and analysis time limit).

Response: The Post Accident S ,opling System (PASS) is to provide the capability to obtain highly radioactive reactor coolant-grab samples after an accident. System drawings are attached. The grab samples can be taken from the following:

1. Pressurizer liquid and vapor spaces

2. Reactor Coolant Cold leg loop 2

3. Containment Emergency Sump via the Decay Heat-System

4. Letdown System

-The Post Accident Sampling System consists of 2

. panels, the control panel C1708 to'be installed in room 106 at Elevation 545 and the sample SKID S1708 which will be mounted in room 106A.

The following instruments will be mounted on the control panel:

5 sigma indicators

' inlet pressure cooler temp inlet cooler temp outlet Dual Indicator sample flow sample pressure dissolved H c ncentration 2

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V Dockst:No.,50-346

License No. NPF-3 Serial No'. 931 l ' April 25, 1983 Page 2

- Attachment 1 The following indicators will be mounted on the control panel:

Pressurizer Vapor Sample Pressurizer Liquid Sample:

RCS Cold Leg Loop 2 Containment Sample Isolation Valve A Containment Sample Isolation Valve B Sample Flow The following control switches will.be mounted on the control panel:

Letdown System Sample Isolation Valve Decay Heat Loop 1 Sample Isolation Valve Decay Heat Loop 2 Sample Isolation Valve Isolation Valve for Normal Sample from RCS Isolation Valve for Decay Heat Sample from Normal Sample System-PASS Isolation Valve Demin Water to PASS Isolation Valve Demin Water to Sample Cooler Pressurizer Undiluted Sample Isolation Valve High Pressure Grab Sample Hydrogen Sample Isolation =

and Bypass Valves . .

Pressure Control Valve for High Pressure Sample Bypass Isolation Valve for Quench Tank Depressurized Undiluted Sample Isolation Valve Undiluted Sample Grab Sample Isolation and Bypass Valves Undiluted Sample Isolation Valve to RCDT or

_. Quench Tank

- Diluted Sample Isolation and Bypass Valves Diluted Sample Isolation Valve to RCDT or Quench Tank Sample Panel Discharge Valve to RCDT or Quench Tank.

Demin Water Pump Sample Pump Pressure Control Valve Control Several types of samples are capable of being obtained from the PASS. These are:

1. Pressurized undiluted samples

2. Depressurized undiluted samples

, 3. Diluted samples

'DockrtNo.50-3k6 License No. NPF-3 Serial No. 931 April ~25, 1983

-Page 3

' Attachment 1 The capability to obtain diluted samples is provided by'the installation of 2 metering pumps. These are controlled by Potentiometers and control switches on the PASS Panel. Control Valves are provided for sample isolation.

The following equipment will be mounted on the sample SKID:

Cooler outlet temp sensor Sample inlet pressure Sample System Flow Pressure control valve Bypass Isolation valve High Pressure sample isolation valve Grab sample isolation valve Hydrogen Concentration Analyzer Pressure control valve for high pressure sample pressure control High Pressure Sample to Quench Tank or RCDT isolation valve Depressurized sample inlet isolation valve Depressurized sample to Quench Tank or RCDT:

isolation valve Sample metering pump Sample metering pump isolation valve Demin water pump Demin water purge isolation valve Diluted sample flow Dilute sample to Quench Tank or RCDT isolation valve.

Sample panel isolation valve Depressurized Sample pressure Auxiliary equipment to be mounted on sample SKID will be:

High pressure sample discharge pressure to RCDT or Quench Tank 1Depressurized. sample pressure Sample pump and-Demin pump discharge check valves Sample cooler bank l

Dock:t Ns.j50-346

-License No. NPF-3 Serial No. 931' April 25, 1983 Page'4.

Attachment 1 The calculated sample time (15 minutes.or less) is the time required under normal operating conditions.

to obtain a sample. The undiluted and diluted samples will be reduced in pressure to a maximum value of 50 psig. The high pressure sample will be obtained between a pressure range of 1,800 to-2,000.psig.

The power supply for the PASS is the non-essential bus. In the event of a loss of off-site power there is no backup power source. However, power can be restored which will allow the sample to be taken and analyzed within the three hour time frame.

The Post Accident Containment Atmosphere Sample System is to obtain a containment atmosphere grab sample after an accident. The sample can be obtained from the installed post accident containment radiation monitoring system or a location in the spent fuel area. Samples taken from either location will include particulate, noble gases and iodine.

If the sample location at the post accident radiation containment air monitor is, inaccessible then the-spent fuel area = grab sample -of containment air will be utilized.

' Criterion: (2) The licensee shall establish an on-site radiological and chemical analysis capability to provide, within three-hour frame established above, quantification of the following:

(a) certain radionuclides in the reactor coolant and containment atmosphere that may be indicators of the degree of core damage (e.g.,' noble gases; iodines and cesiums, and nonvolatile isotopes);

(b) hydrogen levels in the containment atmosphere; (c) dissolved gases (e.g., H 9), chloride (time allotted for analysis subject to discussion.

below), and boron concentration of liquids; (d) alternatively, have inline monitoring capabilities to perform all or part of the above analyses.

DockztNo.l50-346 License No. NPF-3

~

LSerial No. 931 April 25,:1983

'Page 5-Attachment'l Clarification: 2. (a) A' discussion of themcounting equipment capabilities is.needed, including provisions-i to handle samples and reduce background radiation to minimize ~ personnel radiation-exposures (ALARA). Also a procedure is required for. relating radionuclide concen-trations to core damage. The procedure should include:

1. Monitoring.for short and long. lived volatile and nonvolatile' radionuclides such as'133 85 ~

140 and8k',131,137(See Vol.C , 134TI,PahE,2, pp. 524-527 kfRogovinReportforfurther information).

4

2. Provisions to estimate the extent of core damage based on radionuclide concentrations and taking into consideration other physical parameters such as core temperature data and sample location.

2. (b) Show a capability to 'obtain a grab' sample, .

transport and analyze for hydrogen.

2. (c) Discuss the capabilities to sample and analyze

' for the accident sample species listed here and in. Regulatory Guide 1.97 Rev. 2.

2. (d) Provide a discussion of the reliability-and maintenance information to demonstrate that the selected on-line instrument is appropriate for this application. (See (8) and (10) below

. relative to back-up' grab sample capability and

instrument range and accuracy.)

Response: 2. (a) -A description of the on-site. counting equipment is contained in Procedure AD 1850.04 Section 5.4,-

(see Attachment II) Post Accident Radiological Sampling and Counting, which includes volatile and nonvolatile radionuclides. In order to reduce the background, the. samples will be

, _ diluted or counted in a shielded container.

. A procedure to evaluate core damage has not been developed but will be prepared by December, 1983.

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Dock 2t No. 50-346

-. License No'. NPF-3 y- Serial No. 931

-AprilH2.5, 1983~

=Page 6 ~

Attachment 1

2. (b) There are-two hydrogen analyzers that can be used to determine the hydrogen concentration in the containment. These analyzers provide a local and remote readout in'the control room for'expeditous' input to the operators in accordance with ITUREG 0737 Item II.F.1.6. A grab ~s ample may be obtained for off-site analysis althet:gh the three-hour time frame could not be met if this were done. (See attached drawings)

2. (c) There are provisions to perform the analyses listed in Regulatory Guide 1.97 Rev. 2. Gross activities will not be performed since a gamma isotopic analysis is performed. Boron analysis can be made using an automatic titrator located behind lead shielding. Chloride and pH analysis will be performed at an off-site laboratory. Containment air samples'can be analyzed for hydrogen.using the installed

-hydrogen analyzer and gamma enitting radio-nuclides via a grab sample. Dissolved hydrogen in the reactor coolant system will be monitored.

2. ~(d) On-line monitors-are not used for post accident sampling.

Criterion: (3) . Reactor coolant and containment' atmosphere sampling -

during pose accident conditions'shall not require an isolated auxiliary system (e.g', the letdown system, reactor water cleanup system (RWCUS)] to be placed in operation in order to use the sampling system.

Clarification: System schematics-and discussions should clearly demonstrate that post accident sampling, including recirculation, from earn' sample source is possible without use of an isolated auxiliary system. It should be verified that valves which are not accessible after an accident-are environmentally qualified for the conditions in which they must operate.

Response: The reactor coolant sampling system does not require an isolated auxiliary system to be placed in operation to obtain a sample. The containment sample isolation valves, which are controlled from the control room, are. environmentally qualified.

L' 4 DocketNo.50-3k6 License No. NPF-3 Serial No. 931 s

April 25, 1983 Page 7-Attach, ment 1 x The containment atmosphere sampling.does not require an isolated auxiliary system to be placed

'in operation.

' Criterion:4 ' (4) Pressurized reactor coolant samples are not required

' if the licensee-can quantify.the amount of dissolved gases with unpressurized reactor coolant samples.

The measurement of either total dissolved gases or

. .H., gas in reactor coolant samples is considered a8 equate. _ Measuring the20 e ncentration is recommended, but is not maRdatory.

. Clarification: Discus's the method.whereby total dissolved gas or hydrogen and oxygen can be measured and related to

, reactor coolant system concentrations. Additionally, if chlorides exceed 0.15 ppa, verification that dissolved' oxygen is less than 0.1 ppe is necessary.

Verification that dissolved oxygen is <0.1 ppm by

% measurement of a dissolved hydrogen residual of >. _

10 cc/kg is acceptable for up to 30. days after the accident. Within 30 days, consistent with minimizing personnel radiation exposures (ALARA), direct

.D monitoring for ' dissolved oxygen is recomunended.

s Response: A. dissolved hydrogen monitor is provided for measurement of reactor coolant concentrations. The system utilizes electrochemical sensors to measure the hydrogen partial pressure in the liquid coolant sample. .These measurements are converted by the electronics to concentration of dissolved hydrogen in ccH2(STP) pe'r kilogram of water.

It is' felt that analyzing for oxygen directly is not required. However, depending on radiological conditions at the time, a portable " ppb" oxygen y monitor will be made available for. daily measurement of. dissolved oxygen concentrations.

Criterion: (5) The Time for a chloride analycis to be performed is 5 dependent upon two factors: (a) if the plant's coolant water is seawater or brackish water and (b) if there is only a single barrier between primary containment systems and the cooling water. Under both of the above conditions the licensee shall provide for a chloride analysis within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the' sample being taken. For all other cases, the 1

licensee shall provide for the analysis to be

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completed within 4 days. The chloride analysis does not have to be done on-site.

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Docket No.,50-346 License.No. NPF-3 Serial No. 931 April 25, 1983 Page 8 Attachment 1 Clarification: BWR's on sea or brackieh water sites and plants which use sea or brackfish water in essential heat exchangers (e.g. shutdown cooling) that have only single barrier protection between the reactor coolant are required to analyze chloride within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. All other plants have 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> to perform a chloride analysis. Samples diluted by up to n ,

factor of one thousand are acceptable as initial scoping analysis for chloride, provided (1) the results are reported as ppm C1 (the licensee should establish this value; the number in the blank should be no greater than 10.0 ppm C1) in the reactor coolant system and (2) that dissolved oxygen can be verified at <0.1 ppm, consistent with the guidelines above in clarification No. 4.

Additionally, if chloride analysis is performed on a diluted sample, an undiluted sample need also be taken and retained for analysis within 30 days, consistent wit 5 ALARA.

Response: Davis-Besse does not use brackish or sea water for an essential heat exchanger and there is a double barrier between the primary coolant and the cooling water.

Samples can be diluted by up to a factor of 1,000 to yield a lower level of detection of 10 ppm chloride. Arrangements have been made for off-site analysis with results within four days. Either diluted or undiluted samples may be analyzed. If a diluted sample is sent, an undiluted sample will be taken and retained for analysis within 30 days, consistent with ALARA.

Criterion: (6) The design basis for plant equipment for reactor coolant and containment atmosphere sampling and analysis must assume that it is possible to obtain and analyze a sample without radiation exposures to any individual exceeding the criteria of GDC 19 (Appendix A, 10 CFR Part 50) (i.e., 5 rem whole body, 75 rem extremities). (Note that the design and operational review criterion was changed from the operational limits of 10 CFR Part 20 (NUREG-0578) to the GDC 19 criterion (October 30, 1979 letter from H. R. Denton to all licensees).

Dock;t Na. 50-346 License No. NPF-3 Serial No. 931 April 25, 1983 Page 9 Attachment 1 Clarification: Consistent with Regulatory Guide 1.3 or 1.4 source terms, provide information on the predicted personnel exposures based on person-motion for sampling, transport and analysis of all required parameters.

Response: The radiation levels have been evaluated with the source terms listed in Regulatory Guide 1.4. The initial accident radiation zone maps are being revised to be completed by December, 1983.

Criterion: (7) The analysis of primary coolant samples for boron is required for PWRs. (Note that Rev. 2 of Regulatory Guide 1.97 specifies the need for primary coolant boron analysis capability at BWR plants).

Clarification: PWR's need to perform boron analysis. The guidelines for BWR's are to have the capability to perform boron analysis but they do not have to do so unless boron was injected.

Response: Boron analysis can be made using an automatic titrator located behind lead shielding.

Criterion: (8) If inline monitoring is used for any sampling and analytical capability specified herein, the licensee shall provide backup sampling through grab samples, and shall demonstrate the capability of analyzing the samples. Established planning for analysis at off-site facilities is acceptable. Equipment provided for backup sampling shall be capable of providing at least one sample per day for 7 days following onset of the accident, and at least one sample per week until the accident condition no longer exists.

Clarification: A capability to obtain both diluted and undiluted backup samples is required. Provisions to flush inline monitors to facilitate access for repair is desirable. If an off-site laboratory is to be relied on for the backup analysis, an explanation of the capability to ship and obtain analysis for one sample per week thereafter until accident condition no longer exists should be provided.

Response: No inline monitoring is used. Monitoring capability and equipment for all required analysis is described in our response to Criterion 2(c).

DockstLNa. 50-3'64

• License No'. NPF-3 Serial.No. 931 April 25, 1983 Page 10 Attachment 1 I

- Criterion: (9) The licensee's. radiological and chemical sample analysis' capability.shall include provisions to:

(a) Identify and quantify the isotopes of the-nuclide categories discussed above the levels corresponding to the source terms given in-Regulatory Guide 1.3 or 1.4 and 1.7. Where necessary and practicable, the . ability to

,~

dilute samples to provide capability for measure and reduction of personnel exposure should be provided. Sensitivity of on-site liquid sample analysis capability should be such as to permit measurement of nuclide concentration in the range from approximately 1p Ci/g to 10 Ci/g.

(b) Restrict background levels of radiation in the radiological and chemical analysis facility from sources such that the sample analysis will provide results with an acceptably small error (approximately a factor of 2). This can be accomplished through the use of sufficient shielding around samples and outside sources, and by the use of a ventilation system design which will control the presence of airborne radioactivity.

Clarification: (9) (a) Provide a discussion of the predicted activity in the samples to be taken and the methods of i handling / dilution that will be employed to reduce the activity sufficiently to perform the required analysis. Discuss the range of

, radionuclide concentration which can be analyzed for, including an assessment of the amount of overlap between post accident and normal sampling capabilities.

(9) (b) State the predicted background radiation levels in the-counting room, including the contribution from samples which are present.

Also provide data demonstrating what the background radiation levels and radiation effect will be on a sample being counted to assure an accuracy within a factor of 2.

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Dockat N). 50-346

• License No. NPF-3 Serial No. 931 April 25, 1983 i Page 11 j Attachment 1 '

Response: (9) (a) A reactor coolant system water up to 10 Ci/g can be collected with the post accident system which will be completed by December, 1983. 1 The system can dilute samples by a factor of 1,000. Dilution is accomplished by use of a metering pump and demineralized water. The samples are transferred in containers that are shielded with 3 inches of lead. Normal samples can be collected up to a radiation level of approximately 1-R/hr. There is no lower limit for collecting samples with the emergency samples, the upper limit is 10 Ci/g.

(9) (b) The background radiation levels in the counting room are not expected to increase significantly to prevent use of the equipment. Should the levels increase to a level where the counting room would become unavailable for use, the counting equipment would be moved to another predetermined location in accordance with procedure AD 1850.04.

The error contribution from radioactive samples in the room will not interfere more than a factor of 2 because excess samples will be removed from the counting room. Samples will be diluted or counted inside a shielded container.

Criterion: (10) Accuracy, range, and sensitivity shall be adequate to provide pertinent data to the operator in order to describe radiological and chemical status of the reactor coolant systems.

Clarification: The recommended ranges for the required accident sample analyses are given in Regulatory Guide 1.97, Rev. 2. The necessary accuracy within the recommended ranges are as follows:

Gross activity, gamma spectrum: measured to estimate core damage, these analyses should be accurate within a factor of two across the entire range.

- Boron: measure to verify shutdown margin.

y7 Dock:t N3.,50-3'46

• License No. NPF-3 Serial.No. 931

' April 25, 1983 Page 12 Attachment 1 .

In general this analysis should be accurate within i 5% of the measured value (i.e., at 6,000 ppm B the tolerance is i 300 ppm while at 1,000 ppm B the tolerance is i 50 ppm). For concentrations below 1,000 ppm the tolerance band should remain at i 50 ppm.

Chloride: measured to determine coolant corrosion potential.

For concentrations between 0.5 and 20.0 ppm chloride the analysis should be accurate within 10% of the measured value. At concentrations below 0.5 ppm the tolerance band remains at 0.05 ppm.

Hydrogen or Total Gas: monitored to estimate core degradation and corrosion potential of the coolant.

An accuracy of i 10% is desirable between 50 and 2,000 cc/kg but i 20% can be acceptable. For concentration below 50 cc/kg the tolerance remains at i 5.0 cc/kg.

Oxygen: monitored to assess coolant corrosion potential.

For concentrations between 0.5 and 20.0 ppm oxygen the analysis should be accurate within 10% of the measured value. At concentrations below 0.5 ppm the tolersuce band remains at 0.05 ppm.

pH: measured to assess coolant corrosion potential.

Between a pH of 5 to 9, the reading should be accurate withing 1 0.3 pH units. For all other ranges 0.5 pH units is acceptable.

To demonstrate that the selected procedures and instrumentation will achieve the above listed accuracies, it is necessary to provide information demonstrating their applicability in the post accident water chemistry and radiation environment.

This can be accomplished by performing tests utilizing the standard test matrix provided below or by providing evidence that the selected procedure c>r instrument has been used successfully in a similar environment.

. l Dock:t'No. 50-346

• l License No. NPF-3 1

Serial No. 931

-April 25, 1983 i Page 13 Attachment 1 STANDARD TEST MATRIX FOR UNDILUTED REACTOR COOLANT SAMPLES IN A POST ACCIDENT ENVIRONMENT Nominal Constituient - Concentration'(ppm) Added as (chemical salt) i I- 40 Potassium Iodine Cs+ 250 Cesium Nitrate Ba+2 10 Barium Nitrate f La+3- 5 Lanthanum Chloride

Ce+4 5 Ammonium Cerium Nitrate

! C1- 10

. B 2,000 Beric Acid Li+ - 2 Lithium Hydroxide NO3 150

, NHi- 5 K+ 20 Gamma Radiation 104 Rad /gm of ~ Adsorbed Dose (Induced Field) Reactor Coolant

- NOTES:

. 1) Instrumentation and procedures which are applicable to diluted samples only, should be tested with an equally diluted chemical test matrix. The induced radiation environment should be adjusted consensurate with the weight of actual reactor coolant in the sample being tested.

2) For PWRs, procedures which may be affected by spray additive chemicals must be tested in both the standard test matrix plus appropriate spray additives. Both procedures (with and without spray additives) are-required to be available.

3) For EWRs, if' procedures are verified with boron in the test matrix, they do not have to be tested without boron.

4) In lieu of conducting tests utilizing the standard test

matrix for instruments and procedures,-provide evidence that the selected instrument or procedure has been used successfully in a similar environment.

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Dock:t-Ns. 50-3'45 -

License No'..NPF-3 Serial No. 931 April 25, 1983' Page 14 Attachment 1 All equipment and procedures which are used for post accident sampling and analyses should be-calibrated or tested at a frequency which will ensure, to a high degree of, reliability, that it will be available if required. Operators should receive initial and refresher training in post accident sampling, analysis and transport. A minimum frequency for the above efforts is considered to be every six months i. f indicated by testing. These provisions should be submitted in

-revised Technical Specifications in accordance with Enclosure 1 of NUREG-0737. -The staff will provide model~ Technical Specifications at a later date.

Response: Gamma emitting radionuclides can be measured within a factor of 2 across the entire range.

Boron analysis will' be performed using an automatic tritator with an accuracy of 5%.

- Chloride analysis will be performed off-site with an accuracy of i 10% for concentrations greater than 500 ppb and 50 ppb for concentrations less than 500 ppb.

The on-site hydrogen monitor has an accuracy of 4%

between 20 and 2,000 cc/kg.

It is felt that analyt.'.ng for oxygen directly is not required. However, depending on radiological conditions at the time a portable " ppb" oxygen monitor will be made available for daily measurement of dissolved oxygen concentration.

The pH of liquid samples will be measured to an accuracy of i 0.3 units.

The response to the test matrix will be provided after clarification is received from the Davis-Besse NRC Project Manager.

-Criterion: (11) In the design of the post accident sampling and analysis capability, consideration should be given to-the following items:

Dockst No.,50-3'46 -

License No. NPF-3 Serial No. 931 April 25, 1983

-Page 15 Attachment 1 (a) Provisions for purging sample lines, for reducing plateout in sample lines, for minimizing sample loss or distortion, for preventing blockage-of sample lines by loose.

material in the RCS or containment,.for appropriate disposal of the samples, and for flow restrictions to limit reactor coolant loss from'a rupture of the sample line. The

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post accident. reactor coolant'and containment atmosphere samples should be representative of the reactor coolant in the core. area and the containment atmosphere following a transient or accident. The sample lines should be asi short as possible to minimize the velume of -

fluid to be taken from containment. The residues of sample collection should be returned to containment or to a closed system.

(b) The ventilation exhaust from the sampling station should be filtered with charcoal absorbers and high-efficiency particulate air (KEPA) filters.

Clarification: (11) (a) A ' description of the provisions which address each of the items in clarification 11.a should be provided. Such items, as heat tracing.and-purge velocities, should'be addressed. To demonstrate that samples are representative of core conditions a discussion.of mixing, both short and long term, is needed. If a given sample location can be rendered inaccurate due to the accident-(i.e., sampling from a hot or cold leg loop which may have a steam or gas.

pocket) describe the backup sampling capabilities or address the maximum time that this condition can exist.

.~.

BWRs should.specifically address samples which are taken from the core shroud area.and demonstrate how they are representative of core conditions.

Passive flow restrictors in the sample lines may be replaced by redundant, environmentally qualified, remotely operated isolation valves to limit potential leakage from sampling lines. The automatic containment isolation valves should close on containment isolation or safety injection signals.

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License No. NPF Serial No. 931 April'25,-1983 Page116

. Attachment.I'.

t' (11) (b) A dedicated' sample station filtration system is not required, provided a positive exhaust exists which is subsequently routed through

. charcoal-absorbers and HEPA filters.

Response: (11)-(a) The PASS system has installed provisions to purge the sample lines before samples are taken. The samples are taken from the installed

. sample locations on Lthe pressurizer, cold leg loop 2,' discharge of decay heat pump loop l' and 2 and the letdown system, which are-4~

representive of core conditions. . By purging the lines to the reactor coolant drain tank or

' the quench tank a representative sample can be obtained. The flow through the PASS tubing is greater than 15 ft./sec. to prevent blockage

> of' sample lines by loose material in_high pressure lines. 'The PASS has-installed flow restrictors which will limit loss of coolant in the event of a rupture of a sample line.

The operator during sampling will be able to tell from the PASS panel if a rupture has occurred and can notify the control room to '

isolate the sample system. These valves are automatically isolated on SEAS actuation and are environmentally qualified. The sample locations will allow for backup from various points in theLevent a sample location is rendered inoperable by a steam or gas pocket.

When the system pressure is reduced and the plant is on the decay heat system, a sample can also be taken.

(11) (b) The room ventillation where the PASS is located is: designed to exhaust through charcoal absorbers and HEPA filters. A fan must be replaced in this system before it is considered i operable.

The containment atmosphere sample locations exhaust through a charcoal absorber and a HEPA filter.

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F DocketNo.50-346 License No. NPF-3 Serial No. 931 April 25, 1983 Attachment II AD 1850.04

-5.4 Onsite Counting Facility

~4 In order to meet the 3-hour post-accident radiological sampling and analysis requirement for RCS and containment atmosphere samples, an operational, adequately equipped, onsite counting facility must be available.

The location chosen for the Onsite Counting Facility must be set up where the radiation level is low, such as the entrance lobby on the east side of the Office Building (585 ft. elevation)or in the Water Plant Lab.

5.4.1 Equipment A Canberra Model 8100 or 8180 multichannel pulse height analyzer (MCA), presently onsite, has been assigned for use in the Onsite Counting Facility in the event of an accident. Should utilization of the Facility be required, a Ge(Li) detector assembly

- will be removed from the Counting Room (603 ft.

elevation) and relocated in a low radiation area where it will be connected with the Canberra MCA and other necessary equipment to provide the required gamma spectral analysis capability.

Ef ficiency charts and/or data tables are available in the counting room manual to provide necessary counting information for each of the following samples:

1. Reactor coolant

2. Containment atmosphere (noble gases)

m 9' AD 1850.04.4'

3. . Stack exhaust (noble gases).

4.

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Stack particulates filter T5. Stack iodine cartridge.

.5.4.2 Procedure

'Uponideclaration of an emergency requiring activation of_the Onsite Counting Facility, the~following procedure will be followed:

14 l. If the Counting Room cannot be used transport '

Canberra Model 8100 or 8180 to a-suitable loca-tion, i.e., the. Station Lobby, Water Plant. Lab, -

or Radiological Testing Lab at the DBAB.

~

2. In Counting Room, gradually reduce high voltage to the Ge(Li) detector until high voltage is off.

. Turn off power _to the NIM bin in which the high voltage supply and amplifier.are located.

3. Disconnect' cables at the Ge(Li) ' detector, amplifier, and MCA;

4. Remove Ge(Li) detector from shield and immedi-ately place in 'a dewar of LN2 . Relocate in a low radiation area with NIM bin containing high voltage and amplifier. Bring a sample' shelf assembly along.

5. Reconnect high voltage, pre-amp power, and signal cables between the NIM bin components and the Ge(Li) detector _ per Attachment 3.

6. Turn on NIH bin power and gradually bring high voltage up to normal operating voltage (3000 volts). Allow about 15 minutes for the system to stabilize.

7. To achieve 0.5-kev / channel energy calibration, adjust the amplifier fine gain until the number.

of channels between two reference peaks is two times _the difference between the peaks in key.

Then adjust the baseline until a reference peak is in the channel equal to two times the energy in key. It is not necessary to have exactly 0.5 kev / channel.

8. Determine background spectrum before counting samples. Good operating practice would recommend the stationing of an operating thin-window G-M i

~-

M

'10 AD 1850.04.4 survey meter with audible -output at the Onsite. .

Counting Facility. .This would. alert personnel:to high atmospheric noble gas activity which could disrupt counting.

9. -After counting appropriate samples, the data

-reduction. necessary to determine._ the activity for each principal gamma emitter will be performed

~

per RC 4502.00, Gamma Spectral Analysis.

10. Specific information for counting the RCS sampling system (i.e., the 40-ce bomb inside 3-inches of 1ead shielding).

~

'4 (1)~ Remove the collimator pin from-the shielding.

(2) Use Attachment 4 for radionuclide data.

.(3) Use Attachment 5 for efficiencies. These efficiencies in Attachment 5 are for counting at 1 1/4 inches between the container (at the collimator) and the detector edge with the collimator centered on the center of the detector. To get efficiencies for one foot divide the 1 1/4 inch' efficiencies by 116.

To get three foot efficiencies, divide the.1 1/4 inch efficiencies by 1208'.

(4) Use Attachment 6 for instructions to perform calculations manually if the computer is'not-available.

(5) If the RCS sampling system is needed to collect another sample, the sample which has been counted will be flushed out of the bomb when the next sample is to be recirculated.

r- 1 i

I l

13 AD 1850.04.2 Portable GeLi Gamma Spectroscopy System i i

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2 Attachment 3

14 AD 1850.04.2 Nu:LIoE GAMMA ABUND NALF-LIFE (N1N) f(j{([

• 39893.7 2204070 - ;

ee-51 7.s0000eE-02 834 827 HN-54 0 99970 450144.

0.99860 2 768861E+0i 1173.21 Co-60 i415.02 ZN-65 G .507:0 -- 351504 KR-87 0 49400 76.0000 402 550 0.54600 94320.0 756 700 2R-95

• 743 400 * --

R= 97 0.93300 1000.00 765 790 NS-95 0.99000 50544.0 0.80000 11577.6 364 5C0 1-131 667.700-"--

1-13. Gi98000 136.800 0.87000 1248.00 529 889 I-133 1072.55 I-134 0.15300 52.6000

,re133 - J.37100 - <617.6v u O . 9 97 0 ---*

XE133M 0.10:00 31-5.04 233.1E0 0.90600 550.000 249 741 XE-135 2264620 AE13"M G48120G 151300G 0.85000 1.578377E+07 661 638 CS-137 1435.86 CS-138 0.7*000 32.2000 s;23800 48417;o .37 3Ss L A <14 0 KRB5M 0.75500 268 000 151 160 0.94900 49.7000 555.570 Y91H o7334; 27?Cis

-- t'O=203 0481",00 0.64000 165600. 391.700 SN-113 513 960 SR-85 1 00000 93888.0 en=T33 4767000 .,7729040E+04 a55n00-0.97950 1 377072E+06 1274.52 NA-22 1121.20 TA-182 0.35800 165600.

6.99993 7 00 00s 1368:60

--- MA=2. 1260.41 2-135 0.29300 396 600 0.32000 1434.00 685 700 W-107 4771590----

E-J Ut10300 76723.2 0.99160 109 620 1293.64 AR-41 889 258 SC-46 0.99984 120744.

, .300000E-03 ---Si439&B8E+06 132790 nR=85 1836.C0 RB-88 0.22100 17.8000 0.26710 7.148160E+06 344 200 EU-152 o 07i7C 2-----

5 R<124 0498000 66688.6 5.000000E-03 762 600 1345.80 CU-64 881 600 BR-84 0.41600 31.8000 2 200000E-03 8 4 25 4 .^ 4 - 4 2 08. 0 0 --~~

1 - F1 934.500 Y-92 0.13720 211 800 0.88000 4680.00 228.200 TE-132 163:930 XEt31H 2 00000CE-02-----17265.6 121 500 KR-90 0 50000 0.53866 0 32000 3.84000 455.380 XE-137 258.*310 XE-235 0 29000 14r170G 0.450,00 0.67333 218.590 XE-139 1283.23 CS-139 6.700000E-02 9.3C000 Gr19000 33.3000 165480G 34-139 4.414768E+07 43 4500 PU-238 3.800000E-04 0.27800 3384.00 106 140 NP-239 646.600 ----

nR-So J.99000-- 155.220 -

0.33400 585 000 1024.30 SR-91 1031.83 RB-89 0.64100 15 6000 -

0.88000 iTtB3737E+06 795. e0 2--

ca-434 18720.0 818 5C0 CS-136 1 00000 0.85200 388800. 122.060 CO-57 46728.0 145.400 CE-141 0.48000 0.22500 3.16000 220.900 KR-89 311.890 PA-233 0.34000 38880.0 0.41300 1980.00 293.260 CE-143 511 000 F-18 1.94000 109.700 0.10800 409248. 133 530 CE-144 421.e00 J-198 G.94700 3882.24 0.73300 360576. 884.650 AG110M 1481.90 N1-65 0.25700 153 600 0;56500 - 6 4224. 0 ~ A 099. 22 ---

FE-5? 361 800 140.300 1C99M 0.90000 0.95330 2415.60 1596.18 LA-140 - - 102 5 711~~ 810i?5i L0-55 0.99440' 196 300 KR-88 0.20000 171 600 0.14000 4C01.40 739.580 NO-99 1642.40

-- CL-3 8 G.40000 - ~37i1800 2.99000 73.6000 658.100 NB-97 1383.94 SR-92 0.90000 162 600 Oa22100 1712 6 0C 1836.00 ----

-- E b s0 9 2 Attachment 4

N .

KEV ********** EFFICIENCIES FOR GEOMETRY 30 DETECTOR 1 **********

40 HLeSTEEL + LEADeCOLLINATEDe1.25 INCHES

-- 1Tr41 E 1.037E 2 ; 794E-00 4.053E-00 '5i457E-00 7.640E~00- 1.003E=07- IT206E-07 1.615Ee07- 1;V71E 20 2.416E-07 2.090E-07 3.412E-07 3.904E-07 4.603E-07 5.270E-07 5.903E-07 6.741E-07 7.542E-07 0.303E-07 30 9.264E-07 1.010E-06 1.113E-06 1.212E-06 1.313E-06 1.410E-06 1.524E-06 1 633E-06 1.745E-06 1.050E-06 4 0 -"1. 973E-06 ' 2. 009E-06 2.206E-06 2.325E-06 2.444E-06 2.564C-06 2.604E 2iUOSE-06 2 i925E 3; 046E-06 -- -

50 3.166E-06 3.206E-06 3.406E-06 3.525E-06 3.643E-06 3.761E-06 3.077E-06 3.992E-06 4.107E-06 4.220E-06 60 4.331E-06 4.442E-06 4.551E-04 4.650E-06 4.764E-06 4.060E-06 4.970E-06 5.071E-06 5 170E-06 5.267C-06

-- 70 5.362E-06 5.456E-06 5.547E-04 5.637E-06" 5.725E-06 5.010E-06 5.094E-06 ~5.976E-06' 6.056E-06 6.1340 -

00 6.210E-06 6.204E-06 6.357E-06 6.427E-06 6.495E-04 6 561E-06 6.626E-06 6.600E-06 6.749E-06 6.000F-06 90 6.065E-06 6.920E-06 6.Y73C-06 7.024E-06 7.074E-06 7 122E-06 7 160E-06 7.212C-06 7.255E-06 7.296E-06

- 2 00- 7.335E-06 - 7.373E-06 '7.409E-06 7.443E-06' 7.476E-06 7.507E-06 ~7.537E 7.546E-06 7.592E-06' 7.610E-06 '

110 7.642E-06 7.665E-06 7.606E-06 7.706E-06 7.724C-06 7.742E-06 7.750E-06 7.772E-06 7.706E-06 7.790E-06 120 7.010E-06 7.020E-06 7.020E-04 7.036E-06 7.043E-06 7.049E-06 7 053E-06 7.057E-04 7.060E-04 7.061E-06

--8 30-- 7. 062E 7. 062E-06 7.061C-06 7.059E-06 7.056E-06 7.052C-06 7. 010E-06 --7. 012C- 06 7.036E-06 7.029E 140 7.022E-06 7.013E-06 7.604E-06 7.795E-06 7.704E-06 7.7/3E-06 7.761E-06 7.749E-06 7.734E-06 7.723C-06 150 7.709E-06 7.694E-06 7.47YC-06 7.663E-06 7.647E-06 7.630E-04 7.613C-06 7.595C"06 7.577E-06 7.55?E-06

--160 --7. 54 0 E 7. 520E-06 7.500E 7.400E-06 7.460E-06 '7.439E-06 7.417E 7;396E-04"7e374E-06 ~7.351E 170 ~7.329E-06 7.306E-06 7.203E-06 7.259C-06 7.236E-06 7.212C-06 7.107E-06 7.163C-04 7.130E-06 7.113C-06 100 7.000E-06 7.063E-06 7.037E-06 7.011E-06 6.90SE-06 6.959E-06 6.933E-06 6.90/E-06 6.000E-06 6.053E-06

~190--6.02/E-06 6.000E-06 6.7/3C-06 6.745E-06 '6.710E-06 6.691L 6. 663E-06 -- 6. 636E-06 6.600E-04' 6.S00E-06 200 6.552E-06 6.525E-06 6.497E-06 6.449E-06 6.441E-06 6 412E-04 4.304E-06 6.356E-04 6.120E-06 6.3000 06 210 6.271E-06 6.243E-06 6.215E-06 6.107E-06 6.250E-06 6.130E-06 6.102C-06 6.073E-06 6.0 45E -06 6.01/E-06* ~

2207 5.900E 5.960E-06 5. 932E -06 5. 904E-06 ' '5. 075E " 5.047E-06 ~ 5. 019E 5; 791 E-06 ' 5.763E-06 5.735E-06' "

230 5.707E-06 5.679E-06 5.651E-06 5.623E-06 5.595E-06 5.560E-06 5.540E-06 5. 12E-06 5.405E-04 5.45/E-06 240 5.430E-06 5.402E-06 5.375E-06 5.340E-06 5.321E-06 5.293E-06 5.266E-06 5.24.' 04 5.213E-06 5.116E-06

~250 5.159E-06' 5.007E-06 5.063E-06 5.039E-06 5.016E-04 4.993E-06 '4.970E-06 4.947E-u. 4.925E-06 4.903F-06 260 4.000E-06 4.059E-06 4.037E-06 4.015E-06 4.794E-06 4.773E-06 4.752E-06 4.731E-04 4.711E-06 4.690E-06 270 4.d70E-06 4.650E-06 4.630E-06 4.610E-06 4.591E-04 4. 571 E -04 4.552E-06 4.533F-06 4.514E-06 4.495f-06

$N 200" 4.477E-064.450E-06 4.440E-06 4.422E-04 4.404E-06 4.306E-06 4.360E-06 4 350E-06~~4.333E-06 4.316E-06 b gg 290 4.299E-06 4.202E-06 4.265E-06 4.240E-06 4.231E-06 4.215E-06 4.190E-06 4.10?E-06 4.166E-06 4.150E-06 -

on 300 4.134E-06 4.110E-06 4.103E-06 310 3.902E-06 3.967E-06 3.953E-06 4.007E-06 4.072E-06 4.056E-06 4.041E-06 4.026E-04 4.011E-06 3.996E-06 3.93DE-06 '3.924E-06 3 910E-06 3.096E-06 3.002E-06 3.060E-06 3.054E-06 g

g {

m 320 3.040E-06 3.027C-06 3.013E-06 3.000E-06 3.706E-06 3. 7 73C -06 3.760E-06 3.747E-06 3.734E-06 3.721E-06 o

%% 330 3.709C-06 3.696E-06 3.603E-06 3.67]E-06 3.650E-06 3.646E-06 3.634E-06 3.622L-06 3.610E-06 3.590E-06 0 3 40 --3. 506E 3.574E-06 3.562E-06 3.550E-06 -3.539C-06 3 527E-04 3.516E 3.504C-06 3. 493E-06 3.402E-06 *

• • 350 3.471E-06 3.460E-06 3.449E-06 3.430E-06 3.427E-06 3.416E-06 3.405C-06 3.394E-06 3.304E-06 3. 3 73C -0 6 360 3.363E-06 3.352C-04 3.342E-06 3.332E-06 3 322E-06 3.312C-06 3.301E-06 3.291E-06 3.201E-06 3.2/2C-06

1. 370 - 3.262E-06 3 252E-06 3.242E-06 3.233E-06 3.223E-06 3.213E-06 3.204E-04' 3.195E-04 3.105E-06 3.176E-06 300 3.167E-06 3.157E-06 3.140E-06 3.139E-06 3.130E-06 3.121E-06 3.112E-04 3.103E-06 3.094E-06 3.006E-06 390 3.077E-06 3.060E-04 3.060E-06 3.051E-06 3.042E-06 3.034E-06 3.026E-06 3.017E-06 3.00YC-06 3.001E-06 400 -2.992C-06 2.904E-06 2.976C-06 2.96HE-06 2.960E-04 2.952C-06 2.944E-06 2.934C-06 2.920E-06 2.920E 410 2.912E-06 2.905E-06 2.097E-06 2.009E-06 2.002E-06 2.074E-06 2.066E-06 2.059E-06 2.051C-06 2.044E-06 f 420 2.837E-06 2.029E-06 2.022E-06 2 015E-06 2.007E-06 2.000E-06 2.793E-06 2.706E-06 2.779E-06 2.772E-06 430-~2.765E-06 2.750E-06 2.751E-06 2.744E-06' 2.737E-06 2.730E-06 2.724E-04 2.717C-06 2.710E-06 2.703E-06 440 2.69/E-06 2.690F-06 2.603E-06 2.677E-06 2.670E-06 2.664E-06 2.65/E-06 2.651C-06 2. 6 * *,E-06 2.6 mL 06

'450 2.632E-06 2.626E-06 2.619E-06 2.613E-06 2.607E-06 2.601E-06 2.59b0-06 2.500E-06 2.5H2E-06 2.S76E 05

- 4 6 0 -- 2. 5 70 E-06 2.564E-06 2.550E-06 2.552E-06 2.547E-06 '2.541E-06 2.535E-06 -- 2.529E 2.523E-06 ' 2.517E -0 6 -

470 2.512E-06 2.506E-06 2.500E-06 2.495C-06 2.409E-06 2.403E-06 2.470E-06 2.472E-06 2.467E-06 2. 4 61 E ',6

l 9

YEY 400 2.456E-06 2.450E-06 2.445E-06 2.439E-06 2.434E-06' 2 429E-06 2.423E-06 2.410E-06 2 366E-06 2.413E-06 2.361E-06 2.4070-06 2.354C-06 490 2 402E-06 2.397E-06 2.392E-06 2.307E-06 2.302E-06 2 376E-06 2.371E-06

- 300 " 2. 351 E-06 --2 3 4 6E-06 2 341E-06 2.336E-06 --2.33 3 E - 2 326E-06-- 2 6 322E-06 --2 ;317C-06 --2 6 312C 2.307E- 06 2.290E-06 2.293E-06 2.200E-06 2.203E-06 2 279E-06 2.274E-06 2.269E-06 2 265E-06 2.260E-06 510 2.302E-06 2.220E-06 2.215E-06 520 2.256E-06 2.251E-06 2.246E-06 2.242E-06 2.237E-06 2.233E-06 2.220E-06 2 224E-C6 2.190E 2.193E-06-'2 109E-06 2.10$E-06--2.100E-04' 2.176E-06 2.172E-06 530 2.211E-06'-2.206E-06 2.202E-06 2.143E-04 2.139E-06 2 135E-06 2.13tE-06 340 2.160E-06 2.'164E-06 2.159E-06 2 105E-06 2.1S1E-06 2 147C-06 2.122E-06 2.110C-06 2.114E-06 2 110E-06 2 107C-06 2.103C-06 2.099F"06 2.09aC-06 2.0Ytt 06 330 2 127E-06 2.054C-06~ 2.053E - 560 -2.007E-06 2.003C-06 2.079E-06 2.075E 2.071 E 2.060E-06 ~2.064E-06 ~ 2.060E -04 570 2.,049E-06 2.045E-06 2.041E-06 2.030E-06 2.034E-06 2.930E-06 2.027E-06 2.023E-04 2.019C-06 2.016E-06 -

300 2.012E-06 2.009E-06 2.0050-06 2.001E-06 1.990E-06 1.994E-06 1.991E-06 1.907E-06 1.904E-06 1.900E-06

-590 -1.977E-06 1.973E-06 1.970E-06 1 966E 1.963E 1.960E-0 6 - 1.956E 1.Y53E -04 1.9SOE-04 -~ 1.9 46E 600 1 943E-06 1.939E-06 1.936C-06 1.933E-06 1.930E-06 1 926E-05 1.923E-06 1. 920E --0 4 1.916E-06 1 913E-04 610 1.910E-06 1.907E-06 1.904E-06 1.900E-04 1.U97E-06 1 094E-06 1.091E-04 1.00HC-06 1 005L-06 1.002E-04

~ 620 --1 070E-06 1.075E-06 1.072E-06 1.069E-06 -1.066E 1 063E-06 1.060E-06' 1.057E-06 1.054E-06 1.051E-06 630 1.040E-06 1.045E-06 1.042E-06 1.039E-04 1.036E-06 1 033E-06 1.030E-06 1.027E-06 1.024E-06 1.021E-06 640 1.010E-06 1.015E-06 1.013E-06 1.010E-06 1.007E-06 1 004E-06 1.001E-06 1.790E-06 1.796E-06 1.793E-06

- 630 -1 790E-06 1.707E-06 1.704E-06 1 70?E 1.779E 1 776E - 1.773E 1.771E -04 1 76HE 1.765E 660 1.762E-06 1.760E-06 1.757E-06 1 754E-06 1. 732E- 06 1.749E-04 1.746E-06 1.744E-06 1 741E-06 1.73HE-06 670 1.736E-06 1.733E-06 1.730E-04 1.720E-06 1.725E-06 1.723C-06 1.720E-06 1.710E-06 1.715E-06 1.712E-06

~600 -~1.710E-06 1.707E-06 1.705E-06 1.702E-06 "1.700E-06' 1.697E-06-'1 695E-06 1;692E-06~ 1;690E-06 1.607E-06--

690 1.605E-06 1.602E-04 1.600E-06 1.67DE-06 1.675E-06 1.673E-06 1.670E-06 1.660E-06 1.665E-06 1.663E-06 700, 1.661E-06 1 650E-06 1.656E-06 1.654E-06 1.651E-06 1.649E-06 1.646E-06 1.644E-06 1 642E-06 1.639E-06

- 710 - 1. 637E-05 1.635E-06 1.433E-06 1.630E-06 1.620E-06 1 626E-06 1.623E-06 ~1.621E-06 1. 619E 1. 617F - 06 720 1.614E-06 1.612E-06 1 610E-06 1.600E-06 1.605E-06 1.603E-06 1.601E-06 1.599E-06 1.597E-06 1.591E-06 730 1.592E-06 1.590E-06 1.bOHE-06 1.506E-06 1.504E-06 1.501E-06 1.579E-06 Ic577E-06 1.575E-06 1.573E-06

~ 74 0 --1. 571 E 1. 569E-06 -1.567E-06 1.565E-06 ~ 1.562E-06 ~ 1.560E-06 1.550E 1.554E-06 1.554E-06~1.552C-06'~

750 1.550E-06 1.540E-06 1.546E-04 1.544E-06 1.542E-06 1 540E-06 1.510E-06 1.536E-06 1.534E-06 1.532E-06 760 1.530E-06 1.520E-06 1.526E-06 1.524E-06 1.522E-04 1.520E-06 1.510E-06 1.516E-06 1.514E-06 1.512E-06 yy -770 - 1.510E-06 1.500E-06 1.506E-06 1.504E-06 1.502C-06 1.500E-06 1. 499E-06 -- 1. 49 7E-06 1.495E-06 1.493C-04 p 1.40SE-06 1.403E-06 1.40?E-06 1.400E-06 1.470E-06 1.476E-06 1.474E-06 O oe 700 1.491E-06 1.409E-06 1.407E-06 1.465E-04 1.463E-06 1.461E-06 1 440E- 06 1.45HE-06 1.454E-06 -

$[n -000 -- 1. 4 54 E-06 790 1.472E-06 1.471E-06 1.469C-06 1.452E-06' 1.451E-04 1.467E-06 1.449E-06 1.447E-06 1. 4 45E 1. 4 4 4E-06 -- 1 4 42C 1.4 40E-06 1. 4 30E-06 00 N[ 010 1.437E-06 1.435E-06 1.433E-06 1.431E-06 1.430E-06 1.420E-06 1.426E-06 1.425E-06 1.423E-04 1.421E-06 $

• om 020 1.419E-06 1.410E-06 1.416E-06 1.414E-06 1.413E-06 1.411E-06 1 409E-06 1.400E-06 1.406E-04 1.404E-06 -

• e $ - 030 1.403E-06 1.401E-06 1.399E-06 1.390C-06 1. 396E -06 1.395E-06 1.393E-04 1.391F-04 1.3900-04 1.3H0E-06 O 040 1.306E-06 1.305E-06 1.303E-06 1.302E-06 1.3n0E-06 1.37HC-06 1 377E-06 1 375E-06 1.374E-06 1. 3 72r -06 -

H50 1.371E-06 1.369E-04 1.367E-04 1.366E-06 1.364E-06 1.363C-06 1.361E-06 1.340Ea06 1.350E-06 1 357E-06 "060 -1.355E-06 1.354E-06 1.352E-06 1.351E-04 1.349E-06 -1.340E-06 1 '. 3 4 6E-0 6 -- 1. 3 4 5E- 0 6 1.343E-06 1.342E 06 -

070 1.340E-06 1.339E-06 1.337E-06 1.336E-06 1.334E-06 1.333E-06 1.331E-06 1.330E-06 1.320E-06 1.327E-06

. 000 1.325E-06 1.324E-06 1 322E-06 1.321E-06 1.319E-06 1.310E-06 1.317E-06 1.315E-04 1.314E-06 1.312E 06 090 1.311E-06 1.309E-06 1.300E-06 1.307E-06 1.305E-06 1.304E-06 1.30?E-06 1.301E-04 1.300E-06 1.2VHF 900 1.297E-06 1.295E-06 1.294E-06 1.293E-06 1.291E-06 1.290E-06 1.209E-06 1.207E-06 1.206E-06 1.205E-06 910 1.203E-06 1.202E-06 1.200E-06 1.279E-06 1.270E-06 1.276E-06 1 275E-06 1.274E-06 1.272E-06 1.271E-06 920 1.270E-06 1.260E-06 1.267E-06 1.266E-06 -1.264E-06 1.263E-06 ~ ~ 1.262E-06 -~1 261E 1.259E-06 1.250E -

930 1.257E-06 1.255E-06 1.254E-06 1.253E-06 1.252E-04 1.250E "6 1.249E-06 1.240E-06 1.246E-06 1.245E-06 i

s- - #. .

1 9 .

fh k '

- .J.,..... n. .

. ... .'1 *

9-1940 1.244E-06 1.243E-06 1.241E-04--1.240E-06 '1 239E-C6' 1.230E-06. 1.236E-C6 1.235E-dS 1.234E-dA li233E-06 950

1.231E 1.230E-04 1.229E-06 1.220E-06 '1.226E-06 .1.225E 1.224E-06 1.223E-06 1.222E-06 :1 2?OF-06 .

- 960 -~1 219E-06 ~ 1.218E-06 ' 1.217E 1.216E-06-~1 ;214E 1.213E 13 212E 11211E-06' 't.3IDE-06 ' t .20sE-06 -'

970 1.207E-06 1.206E-06 1.205E-06 1.204E-06 1.202E-04 1.201E-06. 1.200E-06 1.199E-069 J.19df-06g it.197Er06 "

900 1.196E-06[1.194E-06 1.193E-45 1.192E-06 1.191E-06.:1.190E-04 1.189E-06 1.107E-06 6 q .186E-04 yf.1056-%03,- ,

- 990 ~1.10 4 E-06 -- 1.103E-06 '1.102E-(6 1.101E 1.100E 1.170E 1.177E 1.176C-06 1.175d'06 I"1.174E-06

.1000 1 173E-06 1.172E 1 171E-06 1.170E-04 1 160E-04. 1 167E-06 1.166E-06 -1.165E-06' 1 1(.4C-06 11 163C-06 1010 1' .162 E-06 1.161E-06 1 160E-06 1.159E-06 1.150E-06 1.154E-06 1 155E-06 1.154E-06 1.153C-06 1.152E-06

--1020 --1.151 E 1.150E-06 1.14VE-06 1.140E 1.147C-06 ' 1.146E-06 -1.14SE-06 --1.14 4C-06 1.143E-06 1.142E-04 1030 1 141E,06 1.140E-06 1.139E-06 1.130E-06 1.136E-06 1.135E-06 1.134E-06 1.133E-06 .1.132E-06 1.131E-06 1040 '1.130E-06 1.129E-06 1.120E-06 1.127E-06 1.126E-06' 1.125E-06 1.124E 1.123E-06 1.122E-06 1 121E --1050 - 1.120E 1.119E-06 1.110E-06 1.117E-06 -1.116E-06 1.115E-06 16114E-04-- 1.113E-06 1.112E-06 1.111E .

1060' 1.110E-06 1.109E-06 1.100E-06 1.107C-06 1.106E-06 1.105E-06 :1.104E-06 1.104E-06 _1.103E-06 1.102E-06 1070 1.101E-06 1.100E-06 1.099E-06 1.090E-06 1.097E-06 1.096E-06 1.095E-06 1.094E-06 1.093E-06 1.092E-06

- 1000 -1. 0V1E-06 ' ~ 1.090E-06 1.009E-06' 1.000E-06 -1.007E-06 1.006E-06-"1.006E-06 -1.005E-04 1.004E-04 *1.003E-06 ,

1090 1.002E-06 1.001E-06 1.000E-06 1.079E-06 1.070E-06 1.077E-06 1.076E-06 1.075E-06 1.074E-06 1.074E-06 1100 1.073E-06 1.072E-06 1.071E-06 1.070E-06 1.069E 1.060E-06 1.067E-06 1.066E 1.065E-06 1.065E-06 4

- 1110 - 1'. 064E-06 -- 1.063E-06 1.062E-06 1.061E-06 -- 1.060C-06 1.059E 1.050E l iO53E-06 ' '1.037E-06 ~ 1.054C-06 1120 1.055E-06 1.054E-06 1.053E-06 1 052E-06 1.051E-06 1.051E-06 1.050E-06 1.049C-06 1.040E-06 1.047E-06 1130 1.046E-06 1.045E-06 1 045E-06 1.044E-06 1.043E-04 1.042E-06 1.041C-06 1.040E-061 1.039E-04 1.039C-06 1140 1.030E-06 1.037E-06 1.036E-06 1.035E-06 " 1.034C-06 ~ 1.034E 1;033E t iO32C-06 ~ 1.031E-04 1.030E 1150 1 029E-06 1 029E-06 1.020E-06 1.027E-06 1.026E-06 1.025C-06 1 025E-06 1.024C-06 1.023E-06 1.022E-06 1160 1.021E-06 1.020E-06 1.020E-06 1.019E-06 1.010E-06 1 017E-06 1.016E-06 1.014C-06 1.015E-04 1.014E-06

-1170 - 1.013E-06 "1.012C 1 012E 1 011E 1.010E-06 "1.009E-06--1.000E-06'--16 000C-06 " 1.007E-06 -1.006E-06 * ..

1100 1.005E-06 1.005E-06 1.004E-06 1.003E-06 1.002C-06 1.001E-06 1 001E-06 9.999E 9.992E-07 '9.901E-07 1190' 9.976E-07 9.960E-07 9.961E-07 9 953C-07 9.946E-07 9.930C-07 9.930C-07 9.923E-07 9.915E-07 9.900E-07

-- 1200 - 9. 900E-07 " 9. 093E-07 9. 005E-07 9. 077E 9. 070E-07'" 9. 063C-07 ""9. 055C-07 "- 9. 0 40C-07 " 9. 0 40C-07" ? . 033C-07 1210 9.02SE-07 9.010E-07 9.010E-07 9.003E-07 9.796E-07 9.700E-07 9.701E-07 9.774E-07 9.766E-07 9.75?E-07 1220 9.752E-07 9.745E-07 9.737E-07 9.730E-07 9.723E-07 9.716E-07 .9.700E-07 9.701E-07 9.694E-07 9.687E-07 r.

- 1230 9.600E-07 9.672E-07 9.665E 9.650E-07 ' 9.651E 9.644E-07 9.637E-07 9.630E-07 '9.623E-07 '9.616E-07 **

1240 9.609E-07 9.602E-07 9.594E-07 9.507E-07 9.500E-07 9.573E-07 9.547E-07 9.560C-07 9.553E-07 9.546E-07 1250 9.539E-07 9.532E-07 9.525E-07 9.510E-07 9.511E-07 9.504E-07 9.497E-07 9.491E-07 9.404E-07 9.477E-07 1260 9.470E-07 9.463E-07 9.454C-07' 9.450E-07' 9.443E 9.436E-07 9.42?E 9i423E-07 9 416E-07 -~9. 409E-07 '

1270 9.403E-07 9.394E-07 9.389E-07 9.302E-07 9.376E-07 9.369E-07 9.363E-07 9.356E-07 9.349E-07 9.343E-07 1200 9.336E-07 9.329E-07 9.323E-07 9.316E-07 9.310E-07 9.303E-07 9.297E-07. 9.290C-07 9.204E-07 9.277E-07 N > ~~1290 9.271E-07 ~ 9.264E-07 9.250E-07 9.251E 9.245E 9.230E-07 9.232E-07 9.226E-07 '9.219E-07 9.213C-07 @

0 1300 1310 9.206E-07 9 200E-07 9.194E-07 9.107E-07 9.101E-07 9.175E-07 9.160E-07 9.162E-07 9.156E-07 -9.149C-07 9.143E-07 9.137E-07 9.131E-07 9.124E-07 9.110E-07 9 112E-07 9.106E-07 9.099C-07 9.093E-07 9.001E-07. g g

se y --1320 - 9. 001 E 9. 075E-07 9.069E-07 9. 062E 9. 056E 9. 050E -0 7"- 9.0 4 4E 9.030E-07" 9.032E-07 9 4 026E-07 ' vi .

oy 1330 9.020E-07 9.013E-07 9.007E-07 9.001E-07 0.995E-07 B.909E-07 0.903E-07 0.977E-07 8.971E-07 0.965E-07 P o

ma 1340 0.959E-07 8.953E-07 0.947E-07 0.941E-07 0.935E-07 0.929E-07 8.923E-07 0.917E-07 8.912E-07 9.906E-07 "

p" .- 1350 0.900E-07 0.094E-07 0.000E-07 0.00?E-07 0.076E-07 0.010E-07 0.065E-07 -0.059E-07. 0.053E-07 8.017E-07 .

N U' 1360 0.041E-07 0.035E-07 0.030E-07 8.024E-07 0.010C-07 8.012E-07 0.007E-07 0.001C-07 8.795E-07 8.7ti?E-07 1370 0.704E-07 0.770E-07 0.772E-07 0.767E-07 8.761E-07 0.755E-07 0.749E-07 0.744C-07 8.73flE-07 8.713E-07 i

-1300 0.727E-07 0.721C-07 0.716E-07 0.710E-07 0.704E-07 0.699E-07 0.693E-07 0.600C-07 0.602E-07 0.677C 1390 0.671E-07 8.665E-07 0.660E-07 0.654E-07 8.649E-07 8.643E-07 8.630E-07 0.632E-07 8.627E-07 D.621E-07 1400 0.616E-07 8.610E-07 0.605C-07 0.600E-07 8.594E-07 0 509E-07 8.583E-07 8.570E-07. 0.572E-07 8.567E-07

- 1410 - 0.562E-07 0.556E-07 ~0.551E-07 0 546E-07 8.540E-07 0.535E-07 0.529E-07 0.524E-07 8.519E-07 D.513E 1420 0.500E-07 8.503E- 07 0.490E-07 0.492E-07 0.407E-07 0 402E-07 8.476E-07 8.471E-07 0.466E-07 8.461E-07 -

1430 0.455E-07 0.450E-07 0.445E-07 9.440E-07 0.435E-07 8.429E-07 0.424C-07 0.419E-07 0.414E-07 'B.409E-07

-1440 0.404E 0.390E-07 0.393E-07 0.300E-07' O.303E-07 0.370E-07" 8.373C-07 0.360E D.363E-07 0.357E 1450 'O.352E-07 0.347E-07 8.342E-07 8.337E-07 8.332E-07 0 327E-07 8.322E-07 8.317E-07 8.312E-07 8.307E-07:

1460 0.302E-07 0.297E-07 0.292E-07 0.2C7E-07 0.202E-07 0.277E-07 8.272E-07 0.267E-07 0.262E-07 0.257E-07 14/o n . ?n?l of H.24 /r o r H.?4?r or H.?r/r-o/ u.?tpr 07 n.??/r 07 n.2: Sir-o/ n.?sur:Op n.?t.tr-07 0.? mis or ,

1400 0.203C-07 0.190E-07 0.193F.-07 0.100E-07 0.101C-07 0.1/9E-07 0.1/4E -0/ 0.169C-0/ 0. t 441: -0 7 0 . l u. I 07

. I e

• MN" -in gr - -m _ _ - - __ __ __ - _Tr-

l w

. g KEV  ;

Ur140E=0'7- ST1J6E=07-07131C307 13 r126E*07 1371711407 UT116C:07-- 0.06?C-07 D;112C-07 0.065C-07 ~

1490- Ir 155t=07 O r150C"07 0;145E=07 0.000E-07' O.003E-07 0.07?E-07 0.074E-07 0.093E-07 1500 0.107E-07 0.102E-07 0.051E-07 0.046E-07 0.041C-07 0 037E-07 0.032E-07 0.027E-07 0. 02:lC-07 fl.01HE-07 G.0?DE-07 C 1510 0.060E-07 0.055E-07

" 1500

0. 013C-07 " 0. 009 E-07

• 0. 004E-07 -" 0. 000C 7 i 995E-07 7 991 C*07-7.945E-07 7 ; 906E"07-7.941E-07 71901 C-07 7.936E-07 -- 7. 9 77C-7.732E-07 07 - 7. 9 72 7.927E-07 1530 7 960E-07 7.963E-07 7.95?E-07 7.954C-07 '7 950E-07 7.700E-07 7.076E-07 7.071E-07 7.007E-07 7 utI?C-07 7.910E-07 7.914E-07 7.909E-07 7 905E-07 7.tl3 tic 0 7 1540 7.923E-07 7.06"E-07 7 060E-07 7 05/ E-0 7 " 7 0S2E-07 '"7.Il4 7C-0 7 7.1141C-07 7.7??E-07 7.7vst-07

~~ 1550 7 070E-07

• 77.030C-07 074C-07 ~ 7.06?E-07 7.00GE-07 7.021E-07 7.017E-07 7.01?C-07 7.00HE-07 7.001C-07 1560 7.031E-07 7.77.lE-07 7 749E-07 7 . 7 /.5 E-07 7.761C-07 7.756C-07 7.772C-07 1570 7 791E-07 7.706E-07 7.702E-07 7.770E-07 7.735C-07 7.731E-07 7 727E-07 7 722E 7.71HC-07 7.714 C-07 7. 710C-0 7 - *

- 1500 7.*740C-07* 7.743C-07 7.739C-07 7.600E-07 7.676C-07 7.672C-07 7.640E-07 7.693E-07 7.40?E-07 7 605E-07 1590 7.705E-07 7.701E-07 7.697E-07 7.631E-07 7 627C-07 1600 7.664E-07 7.660E-07 7.655E-07 7.651E-07 7.647E-07 7 643E-07 7.63?E-07 7.635E-07 7.590E 7.504E-0 7 -

7 6 606E-07

• 7 602E 7.590E-07--7 574C-07 7.550C-07 7.5440-07

--1610 - 7. 4 23E-07 -- 7 610E-07 7. 614C-07 7.610E-07 7.500E-07 7.57DE-07 7.574C-07 7.570E-07 7.566E-07 7.542E-07 7.550E-07 7.554C-07 1420 7 522C-07 7.510C-07 7.514E-07 7 510E-07

• 7.506C-07 1630 7.542E-07 7.530E-07 7.534E-07 7.530E-07 7,.5?4E-07

- 1440- 7.502E-07 "7 4?OE-07 7.494E-07 *7.470E-07' 7.404E-07 ~7.402E-07 ~7.470E-07-*7.475C-07 ~7.471E-07 '7 1650 7 463E-07 7.45?C-07 7.455E-07 7.451E-07 7.447E-07 7 443E-07 7.440E-07 7.416E-07 7.413E-07 7 40?C-07 7 405E-07 7.401E-07 7.377E-077.436E-07I 7 394E-077 432E-07 7.3700-077 420C-07 1460' 7.424E-07 7.420E-07 7.35?C-0 7 -

- 1670- -7.306E-07 --7.302E-07 7.3 70E-07 -7. 375C-07 " 7.371E 7 367E-07 --7.363C-07-~7.35?E-07 '- 7.354C-07 7.3tn'-07 1600 7.34HE-07 7.344E-07 7.341E-07 7.337E-07 7.333E-07 7 329E-07 7.326E-07 7.322C-07 '7.310E-07 7 20lE-07 7.27tlE-07 1690 7 311E-07 7.307E-07 7.304C-07 7.300E-07 7.2Y6C-07 7 272C-07 7.20VC-07 7.205E-07 7 2 45E 7,2 41 C -0 7 -

1700 - 7 2 74 E-07 -- 7 270E 7.267E-07" 7.263C 7.227E-07 7. 25?E-07 7.223E-07

• 7 254C-07 7.220E-07 -~7.252E 7.214E-07 7'.2 4?C-07 7.212C-07 7 20?C-07 7 205C-07 1710 7.230E-07 7 234E-07 7.230E-07 7 104E-07 7.200E-07 7.177E-07 7.173E-07 7 170C-07 1720 *7.202C-07 7 1YDE-07 7.195E-07 7.191E-07 7.107E-07

-173 0 -- 7116 6E-07 7.143E-0 7 "7.157E-0 7 7 & l 56E-07 --7.152E-07. 7.149E-07. -7 145E*07 --77.107C-07

& 142C-07 "77103E-07 13nt 77.100C-07 135C-0 7 7.120C-07 7.124E-07 7 121E-07 7.117E-07 7.114E-07 7.110E-07 1740 7.131E-07 7.07?E-07 7 076E-07 7 072C-07 7.06?C-07 .7,0AAE-07 -

1750 7.096E-07 7.093E-07 7 010E-07 7 006E-07 7.003E-07 1740--7.062E-07 --7.05?E-07 " 7.055E-07 7 052E 7.040E-07 ~ 7.045C-07 7;042E-07 7.030E-07( 7.035C-07-6.990E-07 7.032E-07

• 1770 7.020E-07 7.025E-07 7.021E-07 7.010E-07 7.015E-07 7.011E-07 6.970E-07 7 000E-07 6.975C-07 7 005E-07 6.971E-07 7.001E-07 6.76t1C-07 6.965C-07 6.901E-07 1700 6.995E-07 6.991E-07 6 900E-07 6.705E-07

'17?O- 6.962E-07 'd.950E-07 "6.Y55E-07 6.752E-07 -6.940C-07 6.945E-07 6 & 9 42E 6.93?C-07 r6.?O3E-07 6.Y35C 6.73?C-0 7 6.900r-07 6.916E-07 6.913E-07 6.90?C-07 6 70/.C-07 1000 6.929E-07 6.926E-07 6.?22E-07 6.71?E-V7 6.000C-07 4.077E-07 4.074C-07 4.071C-07 6.IlotC-07 ,

6.096E-07 6.093E-07 6.0?oC-07 6.007E-07 6.004E-07 y3 o "

$ C~30101020 - 6.06 4 E-07 -6.061E 6.050E 6.055E 6.052E 6. 0 4 9E-07 -6. 0 45C A; 0 42C 6 113?E-0 7 " 6.1136C-0 7 6.033C-07 6.030E-07 6.026E-07 4.023E-07 6.020E-07 4.017C-07 6.014E-07 6.011E-07 6.000E-07 6.005C-07 6.774C-07[X 3 C.1030 6.70?E-07 6.706E-07 6.703C-07 6.700E-07 4. 6.777C-07 6 1040 6.001E-07 4.790E-07 6.7Y5E-07 6.792E-07 6. 755E-07-- 6.7 52E-07 -- 6. 7 4 VC-0 7 7 4 6 E-0 7 4.743E-07 o

$ $ 1050-- 6.7 70E-07" 6.767E-07 - 6. 7 6 4 C-0 7 - 6. 7/.1 C-07 6.731E-07 - 6. 750E-07 6.720E-07 6.725E-07 6.722E-07 6.719E-07 6.714E-07 6.781C-u?'o

" 1060 6.740E-07 6.737E-07 6.734E-07 6.695E-07 6.692E-07 6.60VE-07 6 606E-07 6.603C-07."

6.710E-07 6.707E-07 6 704C-07 6.701C-07 6.670E-07 en 1870

-100 0 - 6. 6 00 E-07

• 6. 677E-0 7 ~ 6. 674 E-07 -4.630E-07

6. 6 71E-07 --6.660E-07 6.635E-07 - 4. 665E-0 6.632E-07 7 ~ 6.6.627C-07 6.62YE-07 642E-07--6i 45?C-n7"-6 &

6.624C-07 65 1890 6.6SOE-07 6.647E-07 6.644E-07 6.641E-07 6.60?E-07 6.606E-07 6 603E-07 6.600E-07 6.577C-07 6.5v5t-07 1900 6.421E-07 6.610E-07 6.615C-07 6.612E-07 6.577E-07 6.574E-07 6.572C 6.569E-07 6.566E-0 7

- 1 Y 10 - 6 592E 6.50?E-07/6.506E-07 6.503C-07 6.500E-07

• 1920 6.563E-07 6.560E-07 6.557E-07 4.554E-07 4.552C-07 6.54?C-07 4.546E-07 6.343E-07 6.540E-07 6.51/C-07 6.512E-07 6.50?C-07 6.520E-07 6.510E-07 6.51tC-07 1930 6.535E-07 6.532E-07 6.52?E-07 6.526C-07 4.523E-07 6.495E-07' 6.493E-07 6.470E-07-~4.407C-07 6.404C-07 6.4ntC-n7 1740 6.506C-07*"6.504C-07 ~6.50lE-07 6.470C-07 6.45?C-07 6.4".7E-07 6.4540-07 1960 6.47?E-07 6.476E-07 6.473E-07 4.470E-07 6.460E-07 6.465E-07 6.462E-07 6.440E-07 6.430E-07 6.435E-07 6.432C-07 6.42VE-07 6.427E-07 1760 4.451E-07 6.44DE-07 6.446C-07 6.443E-07 6. 413E 6. 410E-07 6. 400C 6.405C-0 7 6. 402E 4. 40eC- o /

-1?70 6.424E-07 6.421E-07 6.41?E-07 6.416E-07 6.3/IIC-07 6.377.F-07 6.11.tr . o /

1900 6.377E-07 6.3Y4E-07 6.392E-07 6.30VE-07 6.304E-07 4.3114E-07 6.301E-07 6.3'.1E-07 6.3b21:-0 7 6.34v1 07 6..l17: O!

1990 '

10E-07 6.36HE-07 6.365C-07 4.362C-07 4.360C-07 4.357E-07 1.331E 6.320E-07--4.326C-0 7 6.32.lC-07 6.32' *i /

- 2 0 0.^ .de ^7 A.741E-07 6.33?C-07 6.336E 6.333E-0 I

7 19 AD 1850.04.3 Manual Calculations for Gamma Spectros s Sample No. Description Sample Date and Time Counting Date and Time Decay Time min Volume ml Count Time see Detector Geometry Nuclide Energy key C

pCi/ml = A- Bx( 2

)

3.7 x 104 xExFxGxHxJ Where:

A = Counts in total peak area B = Number of channels integrated C = Counts in first channel.of peak D = Counts in last channel of peak E = Efficiency for the detector and geometry used F.= Volume of sample in milliliters G = Gamma abundance of photopeak (decimal fraction)

'H = Decay factor e-Ati. WhereA equals 0.693147 divided by the half life and t is the decay time in the same units as the half-life.

J = (1 - eat 2) where t2 is the count time in seconds and A is in inverse A seconds. If the count time is less than 10% of the half-life, simply enter the count time in seconds for "J".

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