Text

License Renewal Application - Supplement Uftr Operating License
	ML12075A174
Person / Time
Site:	05000083
Issue date:	03/13/2012
From:	Shea B; Univ of Florida
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML12075A174 (54)
	v • d • e

UFUNIVERSITY IFLORIDA of College of Engineering 202 Nuclear Sciences Center UF Training Reactor Facility PO Box 118300 Gainesville, FL 32611-8300 352-392-1401 bshea@ufl.edu March 13, 2012 Document Control Desk License Renewal Application - Supplement U.S. Nuclear Regulatory Commission UFTR Operating License R-56, Docket 50-83.

Washington, D.C. 20555 LCO 3.4.2(3) - Operations Limit (EFPH)

Per request, the UFTR is providing the enclosed supplemental information to docket the UFTR procedural controls used to ensure compliance with current UFTR Technical Specification 3.4.2(3).

During periods of normal operation, UFTR surveillance procedure, SOP-E.6, Argon-41 Concentration Measurement, is performed semiannually to measure the instantaneous full-power Ar-41 stack effluent. Based on the results of these measurements, a monthly equivalent full-power hour (EFPH) limit is calculated, documented in memo format, and posted in the UFTR control room.

Prior to reactor operation, a daily checkout is performed in accordance with SOP-A. 1, Pre-Operational Checks. During performance of this surveillance procedure, the operator ensures EFPHs of operation have been tallied and documented in the UFTR Operations Log. If the monthly EFPH tally is greater than 4,500 kW-hr, the operator is required to note it in the Operations Log and inform the Reactor Manager prior to reactor startup to prevent exceeding the monthly EFPH limit.

This combination of UFTR procedural controls ensures the requirements of LCO 3.4.2(3) are met.

This supplement to our license renewal application has been reviewed and approved by UFTR management.

Please let us know if you need further information.

Sincerely, Brian Shea Reactor Manager cc: Dean - College of Engineering UFTR Reactor Manager Reactor Safety Review Subcommittee UFTR Licensing Coordinator UFTR Facility Director NRC Project Manager Sworn and subscribed this 13 day of March 2012 Auq-6 The Foundationfor The Gator Nation An Equal Opportunity Institution I A-o2b

SOP E.6 Page 1 of 15 UFTR OPERATING PROCEDURE E.6 1.0 Argon-41 Concentration Measurement 2.0 Approval Reactor Safety Review Subcommittee ... ,od 6/6 Date Facility D irector ....................

Date REV 2, 10/03

SOP E.6 Page 2 of 15 3.0 Purpose and Discussion 3.1 Air in the cracks and void spaces in the reactor is activated in the neutron flux near the core; the core vent system is designed to prevent the isotopes formed from exfiltrating to the UFTR cell by means of exhausting air from the core into the environment. This effluent air stream is continuously monitored by the stack radiation monitor.

3.1.1 A sample of the effluent air stream is also periodically analyzed to ensure that the most significant isotope, Argon-4 1, does not exceed acceptable limits for effluent discharge as specified in the UFTR Technical Specifications.

3.1.2 In addition, as required by UFTR Technical Specifications surveillances, the 100 kW instantaneous release concentration and the average monthly release of Argon-41 are calculated and reported in the UFTR monthly report and the Annual Activity Report submitted to the Nuclear Regulatory Commission.

3.2 An accurate determination of the efficiency of the counting system used to analyze the samples is essential to determine the Argon-41 concentration. A Cobalt-60 standard, counted on the system to be used, permits determination of the efficiency of the system over a small energy range that brackets the Argon-41 decay energy. The Cobalt-60 standard is homogeneously impregnated in a suspension medium inside a Marinelli beaker, duplicating the geometry of the sample itself. A simulated gas standard is also available which simulates a gaseous Co-60 source. The simulated gas standard is preferred.

NOTE: Per discussions at previous Reactor Safety Review Subcommittee meetings, these NBS/NIST traceable sources are allowed to be used beyond their nominal expiration dates for isotopes whose half-lives are long enough to permit adequate count rates.

3.3 Samples should be drawn from the core vent effluent and then analyzed with as little delay as possible in order to prevent excessive decay of the Argon-41 (110 minute half-life) and resultant poor counting statistics. This provision will ensure that a statistically significant Argon-41 decay rate occurs over a relatively short count time. Consequently this procedure should be coordinated with the laboratory intended to provide the analysis.

3.4 The Argon-41 emission level as indicated by the stack monitor requires several hours of reactor operation to stabilize; therefore the UFTR should be operated at steady-state full power for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to collecting the core vent effluent samples to assure an equilibrium Argon-41 level.

REV 2, 10/03

SOP E.6 Page 3 of 15 3.5 The following material should be available for use in drawing the sample:

3.5.1 Purge volume container (a 1-gallon plastic carton is recommended as it is of sufficient size, and easily obtained);

3.5.2 Plastic, tygon, or polyethylene hose, at least 18 inches long; 3.5.3 Bucket capable of holding all the water from the purge volume and the Marinelli beakers (1 gallon purge and about 1 gallon (4 liters) from the beakers);

3.5.4 Cobalt-60 standard source; 3.5.5 Marinelli beakers (4 beakers, nominally 1 liter each with actual volume of 1.25 liters).

4.0 Limits and Precautions 4.1 The Argon-41 discharge concentration shall be measured semi-annually at intervals not to exceed 8 months as per UFTR Technical Specifications Section 4.2.4, Paragraph (2).

4.2 The concentration of Argon-41 in the gaseous effluent discharge of the UFTR is determined by averaging it over 1 month as per State of Florida regulations and UFTR Technical Specification Section 4.2.4, Paragraph (1); therefore, the monthly release rate of Argon-41 is based on an average release using values calculated for the instantaneous release rate and a period of 1 month (30 days or 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months for purposes of this procedure).

4.3 A factor of 200 may be used to account for atmospheric dilution of Argon-41 for determination of stack effluent concentrations, as per UFTR Technical Specifications, Section 4.2.4, Paragraph (2). This dilution is in addition to that resulting from the operation of the stack Diluting Fan, which is required to produce stack air flow at a rate of 10,000 cfin or greater as per Technical Specifications, Section 3.4.2, Paragraph (2).

4.4 After calculations as indicated in Sections 4.2 and 4.3, discharge concentrations of Argon-41 shall not exceed MPC (1.0 x 10.8 microCuries/ml per the revised 10 CFR 20);

release from the facility above the maximum permissible limits (MPC) as specified in Appendix B, Table II, 10 CFR 20 when averaged over 30 days is immediately reportable as a violation of Technical Specifications, Section 3.4.2, which contains the limiting conditions for operation concerning Argon-41 discharge.

4.5 This procedure for the measurement of Argon-41 effluent discharge concentrations is based on sampling core vent flow prior to dilution by the Diluting Fan, and prior to inclusion of the authorized atmospheric dilution factor of 200.

REV 2, 10/03

SOP E.6 Page 4 of 15 4.6 Three samples are required to be analyzed and averaged for reportable concentrations; however, 4 will normally be drawn and counted so that 1 inconsistent sample or faulty measurement may be disregarded, and the requirement for 3 samples will still be met.

4.7 All time measurements should be made using the same timepiece, or time standards must be correlated to calculate delay times.

4.8 Argon-41 detection efficiency must be calculated for each detector used in the counting process.

4.9 The volumetric vent and stack air flow will be determined concurrently with the determination of the Argon-41 discharge concentration as far as possible; this determination should be made prior to the reactor operation during which core vent effluent samples will be taken for the Argon-41 effluent measurement.

4.10 It is recommended that personnel accomplishing the measurement of stack air flows maintain radio communications with an operator at the control console.

5.0 References 5.1 UFTR Semi-annual File S-4 5.2 UFTR Technical Specifications 5.3 UFTR Safety Analysis Report 6.0 Records Required 6.1 Calculations and results shall be retained as specified in UFTR Technical Specifications, Section 6.7, "Records."

6.2 Letter generated by the Reactor Manager/Facility Director specifying limits on monthly UFTR energy generation (kW-hr) to prevent exceeding the limits on the monthly average Argon-41 discharge concentration.

6.3 UFTR Daily Operations Log 6.4 Monthly report tabulations of UFTR energy generation (kW-hr).

6.5 Annual Report summarizing Argon-41 releases REV 2, 10/03

SOP E.6 Page 5 of 15 7.0 Instructions 7.1 Conduct a reactor startup to full power as per SOP-A.2 and SOP-A.3 and allow the Argon-41 emission level indicated by the stack monitor to stabilize (at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ).

7.2 Collect samples representative of core vent effluent as follows:

7.2.1 Collect a purge volume in the designated container as follows:

7.2.1.1 Fill the purge volume container with water; 7.2.1.2 Check closed the sample line quick-throw stack monitor access plate; 7.2.1.3 Connect one end of the hose to the sample line connection; 7.2.1.4 Place enough water in the bucket so that the purge volume container opening may be placed completely under water, forming a water seal that holds water in the purge volume container while the bulk of the container remains above the surface of the water in the bucket; 7.2.1.5 Place the loose end of the hose connected to the sample line under the surface of the water in the bucket, and into the neck of the purge volume container; 7.2.1.6 Open the sample line quick throw valve, so that the water in the purge volume container no longer has a water seal holding water in that container; 7.2.1.7 When the purge volume container is drained, close the sample line quick throw valve, remove the hose from the container, remove the container from the bucket.

7.2.2 Collect 4 air samples in the Marinelli beakers as follows:

7.2.2.1 Fill the beakers completely with water (the recommended method is to submerge the beaker and open all valves on the beaker, repositioning the beaker under water to allow as much air as possible to enter).

7.2.2.2 Connect the loose end of the hose to the sample line connection on the beaker.

7.2.2.3 Open the quick throw valve on the sample line connection on the beaker; 7.2.2.4 Open the quick throw valve on the sample line connection mounted on the stack monitor access plate; REV 2, 10/03

SOP E.6 Page 6 of 15 7.2.2.5 Open the pet-cock on the beaker and pump the purge bulb on the sample line, allowing water to drain into the bucket, replaced by core vent effluent air, until all the water is removed.

7.2.2.6 Close the pet-cock, and record the time on UFTR Form SOP-E.6B.

CAUTION All time measurements should be made using the same timepiece to prevent inaccuracies in calculating delay times in counting samples and accounting for Argon-41 decay.

NOTE: If using a computer counting system, set the computer time to the timepiece used for sampling.

7.2.2.7 Close the sample line connection quick-throw valves on the Marinelli beaker and on the stack monitor access plate.

7.2.2.8 Repeat the process (in Steps 7.2.2.1 through 7.2.2.7) for all 4 beakers. When all 4 beakers are filled with core vent effluent, transport the samples to the counting facility reserved for sample analysis.

7.3 Analyze the samples:

7.3.1 Count each sample and the Co-60 standard using a high purity germanium (HPGe) detector system (or a system of comparable capability such as GeLi or Nal detector system) and a multi-channel analyzer.

7.3.1.1 Count the Cobalt-60 standard separately on each detector used or to be used to provide the basis for an independent measurement of each detector efficiency for Cobalt-60.

NOTE: The Cobalt-60 standard is normally counted prior to obtaining the samples but this is not required. Only one detector is normally used.

7.3.1.2 Record the time when counting begins for each sample on UFTR Form SOP-E.6B.

7.3.1.3 Determine the net number of counts under the peak at 1293 keV for each sample, and the number of counts under the two peaks for Co-60 (1173 keV and 1332 keV) for the Cobalt-60 standard.

7.3.1.4 Record the net count rate (number of counts/sample count time in minutes) on UFTR Form SOP-E.6B for each sample and on SOP-E.6A for the Cobalt-60 standard.

REV 2, 10/03

SOP E.6 Page 7 of 15 7.3.2 Calculate the delay time (as previously noted) between the time the sample was taken and the average of the time when counting begins and ends for the sample in question; record the applicable delay time on UFTR Form SOP-E.6B separately for each sample.

7.3.2.1 Using the recorded delay time, correct the count rates back to the time sampling was completed using the radioactive decay formula as noted on UFTR Form SOP-E.6A:

CPM (Back Corrected) = CPM x EXP [(0.693/110 min) x DELAY TIME (min)]

7.3.2.2 To obtain the average concentration, average the delay compensated count rates and record on UFTR Form SOP-E.6B.

7.3.3 Using the calibration data for the Co-60 source, calculate the applicable decay time of the source to the date on which it is used.

7.3.4 Calculate the activity of the Co-60 source in DPM; then determine the counting efficiency for each of the two Co-60 peaks; record the results of that calculation on UFTR Form SOP-E.6A.

7.3.4.1 Interpolate between the efficiencies for the Co-60 peaks (1173 and 1332 keV) to find the efficiency for the Ar-41 energy peak (1293 keV).

7.3.5 Using the calculated detector efficiency for Argon-4 1:

7.3.5.1 Determine the activity of the samples in DPM (CPM/Efficiency);

7.3.5.2 Record calculated sample activities on UFTR Form SOP-E.6B.

7.3.6 Record the average value of the sample activities on UFTR Form SOP-E.6B.

7.3.7 Convert the average sample activity (DPM) to microCuries by using the equivalence that 1 microCurie is 2.22E6 DPM and record these results on UFTR Form SOP-E.6B.

7.3.8 Determine the average Argon-41 concentration (activity) of the samples (microCuries/ml) by dividing the activity by the volume of the sample (the volume of the Marinelli beaker = 1250 ml); record the undiluted concentration value on UFTR Form SOP-E.6B.

7.3.9 Determine applicable average stack air flow rate (see section 7.4) and record the value on UFTR, Form SOP-E.6C.

REV 2, 10/03

SOP E.6 Page 8 of 15 7.3.10 Calculate the diluted effluent concentration by multiplying the undiluted concentration (from 7.3.8) by the formula below:

CORE VENT FLOW (CFM) 200 x [CORE VENT (CFM) + MEASURED STACK FLOW (CFM]

This value shall be recorded as the instantaneous Argon-41 stack release concentration on UFTR Form SOP-E.6B.

7.3.11 The determination of the total monthly release (Curies) of Argon-41 for the monthly UFTR General Activities and Utilization Report will be calculated as follows:

RELEASE (Curies) = [kW-hr OPERATION] x [EFFLUENT CONCENTRATION

@ 100 kW (Ci/ml)] x [STACK FLOW (cfm)] x [60 min/hr][28317 ml/ft3 ]

7.4 The volumetric air flow rate will be determined concurrently with the measurement of the Argon-41 discharge concentration as far as possible; this determination should be made prior to the reactor operation during which core vent effluent samples are taken for the Argon-41 effluent measurement.

7.4.1 Measure chimney action at the stack exhaust.

7.4.1.1 It is recommended that personnel accomplishing the measurement of the stack air flow rate maintain radio communications with an operator at the control console.

7.4.1.2 Secure the core vent and the dilution fans.

7.4.1.3 Using a 3 by 3 grid-sectional pattern, measure with an anemometer the air flow at the center of each of 9 sections at the exhaust of the stack for 1 minute each; record values on UFTR Form SOP-E.6C.

NOTE: Kurz Minianemometer (Model 490) is preferred but the Taylor Anemometer (Model 3132) or other anemometer may be utilized as necessary.

7.4.1.4 Record the sum of all values.

7.4.1.5 Record the average of all values.

7.4.1.6 Record the correction factor for the averaged value determined from the calibration chart, Appendix 1I when the Taylor Anemometer or other vane type meter is used in Step 7.4.1.3.

7.4.1.7 Record the sum of the average value and the correction factor as True Chimney Action.

REV 2, 10/03 TCN: 10/04

SOP E.6 Page 9 of 15 7.4.2 Measure and calculate normal stack air flow rate:

7.4.2.1 Start the dilution fan.

7.4.2.2 Using a 3 by 3 grid-sectional pattern, measure with an anemometer the air flow at the center of each of 9 sections at the exhaust of the stack for 1 minute each; record values on UFTR Form SOP-E.6C.

7.4.2.3 Record the sum of all values.

7.4.2.4 Record the average of all values.

7.4.2.5 Record the correction factor for the averaged value determined from the calibration chart, Appendix II when the Taylor Anemometer or other vane type meter is used in Step 7.4.2.2.

7.4.2.6 Record the sum of the average value and the correction factor as True Normal Action.

7.4.3 Calculate air flow as indicated on UFTR Form SOP-E.6C and enter that value on UFTR Form SOP-E.6B for use in the Argon-41 dilution calculation.

REV 2, 10/03

SOP E.6 Page 10 of 15 APPENDIX I FORMS FOR ARGON-41 CONCENTRATION MEASUREMENTS AND CALCULATIONS REV 2, 10/03

SOP E.6 Page 11 of 15 UFTR FORM SOP-E.6A DETECTOR EFFICIENCY MEASUREMENT PART I: DATA ON COBALT-60 STANDARD Serial Number: Date of Measurement:

Assay Date: Individual Performing Efficiency Measurement:

Assay Activity: Detector Identification:

PART II: MEASUREMENTS ON COBALT-60 STANDARD A Co-60 standard source with two primary gamma ray energies spanning the Ar-41 primary gamma energy is used to determine the efficiency of the detector system used to measure the Argon-41 activity in the UFTR core vent air samples.

The calculations and results for the detector efficiency measurement are documented as follows:

ENERGY CALCULATED MEASURED DETECTION ISOTOPE DETECTED ACTIVITY (A2)* ACTIVITY** EFFICIENCY***

(keV) (DPM) (CPM)

Cobalt-60 E, = 1173 E, =

Cobalt-60 E 2 =1332 E2 =

The calculated activity of the Co-60 source is based upon the initial activity (A1) and the 5.271 year half-life of the isotope: A2 = A, e-zt where X = 0.693/5.271 yr.

- Measured activity is the activity recorded by the counting system.

The Energy-dependent Detection Efficiency for the two Co-60 gamma energies is simply:

Measured Activity Calculated Activity PART III: ARGON-41 DETECTION EFFICIENCY CALCULATION The detector efficiency for Argon-41 gamnma rays (E = 1293 keV) is determined as a simple linear interpolation of the efficiency for counting the two different energy Cobalt-60 gamma rays as follows:

6 3 (1293keV) = 61 -2 x [1293 - El] +

Argon-41 Gamma Detection Efficiency: 63 (1293) =

PART IV: VERIFICATION Form Filled Out By Date RMIFD Acknowledgment Date REV 2,10/03

SOP E.6 Page 12 of 15 UFTR FORM SOP-E.6B ARGON-41 STACK EFFLUENT CONCENTRATION PART I: SAMPLING CONDITIONS Argon-41 Detection Efficiency (From Form SOP-E.6A):

Stack Air Flow Without Core Vent (From Form SOP-E.6C):

Reactor Power (kW)/Stack Monitor Reading (CPS) Prior to Sampling:

Length of Full Power Run Prior to Sampling:

Name of Individual Collecting Samples: Date of Sampling:

PART II: RESULTS OF DATA ACQUISITION SAMPLE TIME SAMPLING TIME STARTED DELAY COUNT UNCORRECTED NUMBER COMPLETED COUNTING TIME DURATION COUNT RATE (sec) (min) (CPM)

PART III: RESULTS OF DATA REDUCTION SAMPLE COUNT RATE SAMPLE SAMPLE SAMPLE INSTANTANEOUS*

NUMBER COMPENSATED DECAY RATE ACTIVITY ACTIVITY AR-41 CONC. IN STACK FOR DELAY (CPM) (CPM/E) ([ICi) (iCi/m1) EFFLUENT (IXCi/ml)

F + 4-

-t F 4- 4-

Includes effects of core vent and diluting fan flow as well as NRC-TECH SPEC allowed 200-to-1 atmospheric dilution factor.

PART IV: VERIFICATION Form Filled Out By Date RM/FD Acknowledgment Date REV 2, 10/03

SOP E.6 Page 13 of 15 UFTR FORM SOP-E.6C STACK DILUTION AIR FLOW MEASUREMENT PART I: SAMPLING CONDITIONS Chimney Cross Sectional Area: 6.354 ft2 Date of Air Flow Measurement:

Individual Measuring Air Flow: Time of Measurement:

Temperature: Barometric Pressure:

Wind Speed and Direction:

General Weather Conditions:

Anemometer Description (Kurz Minianemometer Model 490):

NOTE: These measurements should be made during calm weather.

PART II: RESULTS OF DATA ACQUISITION Chimney Action Normal Rate N N a b c a b c d e f d e f W W g h i g h PART III: RESULTS OF DATA REDUCTION Chimney Action Sum: ft/min Normal Action Sum: ft/min Chimney Action Ave: ft/min Normal Action Ave: ft/min Correction: ft/min Correction: ft/min True Chimney Action: ft/min True Normal Action: ft/min Stack Dilution Air Flow = (True NormalAction - True Chimney Action) x Chimney Area Stack Dilution Air Flow =_(_ ) x 6.354 ft 2 Stack Dilution Air Flow Core Vent Flow Rate =_cfm (Convert Vent Flow Manometer Reading to cfin)

PART IV: VERIFICATION Form Filled Out By Date RM/FD Acknowledgment

SOP E.6 Page 14 of 15 APPENDIX II TAYLOR ANEMOMETER CALIBRATION CHART REV 2, 10/03

+20

+10

+0 - - --

> -10

<T -2 o

-20

-30

-33 z *-40 0

2

-50

-60

-70

. 0

-80 a 200 400 600 800 1000 1200 1400 1600 1800 2.000 2200 2400 2600 2800 3000 ý4 MEASURED VELOCITY (ft/min)

Figure E.6-1 Anemometer Correction Chart (Positive values are added to anemometer readings while negative values should be subtracted from anemometer readings.)

College of Engineering 202 Nuclear Sciences Bldg.

Department ofNuclear & Radiological Engineering PO Box 118300 UFTR Nuclear Facilities Gainesville, FL 32611-8300 352-392-1401 352-392-33.80 Fax www.nre.ufl.edu October 14, 2008 MEMORANDUM TO: Reactor Staff FROM: B. Shea SU.BJECT: LIMITATION ON UFTR EQUIVALENT FULI,-POWER HOURS .OPERATION (Latest Argon-41 Measurements Were, Performed on October, 2008 - -6.5 Months Following Previous Measurements .Performed on May 13, 2008 Themost recent (October 14, 2008) Argon-4 I.survey results based on four equilibrium stack. samples (none rejected) at 100.kWth indicate that the average cncentralion atithe base of the stack.(prior to dilution) is 13.00 *x10-4 pLCi/ml with the highest being 13.50"x. 1O4 ACi/ml. The results represent a slight increase from the last measuremcnts.on May 13, 2008 (12.64 x 10-1 RCi/ml) as the third measurement::for the new LEU core, and. from the measurements on March 9, 2007(10.10x, 1,0 jCi/mrl).as thefirst, measurements for the LEU core. The results represent agenerally. agreeable value compared with mostrecent measurements but..

considerably higher.

When diluting fan.flow rate (13,407 cfm): along with the allowed 200:1 atmospheric dilution; of the stack plume. (see Tech Specs, Section .3.4.2,: Paragraph (2)) is incorporated, the average concentraton ofAr-41 in the gaseous effluent is 10.50 x [1.08pCi/m ,, up from 9.770 x I0"8 pCi/ml in May 2008, up from 6.200 x 10- plCi/ml in November 2007,. and from 9.590 x 10-1 IiCi/ml in March 2007, .as the last three measurements. These results:are :generally in agreement with .the list:of all results since 1988 in the attached Table 1. This instantaneous, Ar-41 release concentration is 10.50 "MPC" given as 1.0:x 10-s ACi/mI (averaged annually in 10 CFR 20 and monthly in~the UFTR Tech Specs, Section 3.4.2, Paragraph (3)).

H-Iowever, the UFTR Tech Specs (Section 3.4.2, Paragraph (1)) allow.the Ar-41 concentration in the gaseous:effiuent. discharge of the:.UFTR to be determined by averaging it over a consecutive, 30-day period (a calendar month -for our purposes).

Since Ar-4l.ins*.intaneous release:v"alues are 10.50 "MPC," the integrated UFTR kW-hrs allowed, over any one month (UFTR Tech Specs.specify one. month average versus State of Florida Regulations annual average)are restricted to 6,857.14 kW-hrs to assure a monthly averaged value within the UFTRTS limits (see Section ?.4.2,. Paragraphs (1)-(3)). Since the UFTR Environmental Impact Appraisal specifies that:

the UFTRis already limited.to0.235 EFPHs per month, monthly energy generation shall not exceed 6,857.l4 kW-hrs as the more conservative value.

The Foundationfor The Gator Nation.

ARGON-41 EMISSION CALCULATIONS FOR OCTOBER.2008 MONTHLY REPORT

1. The latest October 14, 2008 Argon-41 measurements give the following data based on4 samples:

A. Argon-41 concentration at fullpower = 10.50 x 10-8 gtCi/ml in stackIll effluent including 200-to-I atmospheric dilution factor (unchanged),

B. Stack flow rate. = 13,407 ft3/min based upon Kurz.Minianemometer readings.

II. The allowable UFTR equivalent full-power hours are determined from the following equation:

EFPHy ilable x Instantaneous Argon-41 = I0CFR20:Argon-41 Monthly Hours Available Effluent Concentration Concentration Limit where: Hours Available (1 month) 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months (Standard)

Instantaneous Argon-41 Effluent Concentration 10.50 x 10-8. PCi/mi 10 CPR 20 Argon-4l Concentration Limit 1.0 x 10-8 pCi/ml (new Part 20)

EFPHmi, = 1..0 x IO's gCi/ml x 720.hours = 68.5714 EFPH 10.50 x l 0.8 PCi/m!

II1. Emissions for the month are based upon the. following calculations:

3 A. 10.50 x 10-8 uj..x:200 = 2.10 x 104* ACi/cmM concentration in stack exhaust at full power (without 200/1. dilution) ml B. Release rate at full power:

..2. I0 x 1.0-5pCi/cm.. x 13,407. f 3/min x 2.8317 x 104 cm3 = 7,972.57 pgCilmin

.ft3

C. Release per kW-hr of operation:

7,972.56 jiCi x I x 60 min 4,783.54gpCi/kW-hr.

min 100 kW hr D. Energy generation in September 2008 = 47.611 kW-hrs IV. Emissions for September 2008:

A. Curies released:

47.611 kW-hrs x 4,783.54 tCi = 2.277491 x W0pCi (reported) kW-hr B. Average release concentration:

10.S0 x 10-" ~ix 0.45 EFPRk 1 month = 6.562500 x 10"11 pCi/ml (reported).121 ml 720 hrs The measured fullpower Argon-41! stack concentration at 10.50 x 10"8 ACi/ml is up from9.770 x 10's p1Ci/mI in May 2008, from 9.590 x 10"' [iCi/mI in March2007, from 8.700 x 10"8 pCi/ml in December 2005 and from 9.3175 x 10"8 ACi/ml in February2005, but dox*n from 10.309 x 10"s tCi/ml in September 2004, and is generally in the range of values per measurements since 1988..as listed in attached Table I, and is generally within the expected range.

121 The average release concentration is well within the limit.of.1.0 x 10-8p Ci/ml required by the new 10 CFR 20 and well characteriZed per the latest evaluative analysis documented in.the memorandum dated August 29, 1988 for using the gas standard and in the memorandum dated August 30, 1989 for, using the preferred 1250.ml gas standard volume.

Rx Mgr/Facilities Director Approval Date

Table 1. Argon-41 Measurement Data for the UFTR Concentration Before Dilution(Pi/ni) Instantaneous Argon-41 Measurement Number Concentration in Effluent Date of Samples Average (xlO4 ) Maximum (xl0 4 ) (iACi/ml xI.0i) 08/30/88 3 9.60 9.92 8.88

... 06/89 4 9.014 (9.04) 0( 9.392. 8.177 (8.24) "

08/24/89 4 1.1.3 I L7. 10.8 01/05190 4 11.04 11.55 10.0 07/12/90 3 10.27 10.45 8.456' 02/05/91 4 9.76 9.98 9.56 06'19/91 3 8.19 8.47 8.72 01/03/92 3 10,1:2 10.20 8.10 06/24/92 3 8A486 8.566 7.46 12/18/92 .4 9.107 9.358 8.13 07/2093 .4 .10.24 10.3.1 9.18 02/08/94 4 .10.27 10.61 8.07 07/1.8/94 4 9.482 9.632 7.884 (7.865) Z 12/30/94 4 9.914 10.14 8.549 08I11 /95 4 9.643 10.49 8.003 02/13/96. 4 9.393 9.632 8.930.

07/18/96 3 9.405 9.792 7.671:

01/23/97 4 9.741 1:056 8.504 07)25/97 3 8,331 8,760 6.982 01/22198 3 8.355 9.912 6.773 07/27/990 4 10.208 11.387 .1.1937 01/3.1/00" 4 9.627 10.220 8.520 08/04!00 4 10.670 10.880 9.543.

04/04101 4 11.275 12.620 9.598 1.0/25/01 4 12.210 12.500( 10.40 02/27/03. 4 12.375 12.584. 11.19 08/22/03 4 121128. 12.630 8.773:

02/26/04 4 12.013 13.011 7A879ý 09/ 7/0*4 4 .1.3.209 14.006 10.309.

02/24/05 4 12.073.. 12.439 9.3175 12!22/05 0 3 11.340 I 1.450 8.700.

03/09/07 0 3 10.100 10.600 9.590 (LEU) 1t/01/07 3 8.147 9.620 6.200 (LEU) 05/13/08 4 12.650 13.000 9.770 (LEU) 10/14/08 4 13.000 13.500 .10.50 (LEU) 0 Vatues in.parentheses are the v~alues reported but were changed because of a slight rounding.error.

.0 Values in parentheses are the values reported but were changed due to a slight averaging errornoted during data review in July 1996 0 Delayed due to lengthy outage and prorated to 100kW based on heat balance at.:95 kW for measurements to be conservative.

I)elayed but completed prior to return to normal operations per Tech:Spec LCO requirements.

D)elayed due to lengthy outage and prorated to 100 kW based on heat balance at .95.6 kW for measurements to be conservative.

SOP-A.1 Page 1 of 35 UFTR OPERATING PROCEDURE A.1 1.0 Pre-operational Checks 2.0 Approval Reactor Safety Review Subcommittee ... _-__-- ____

Dat Ze 6 Director, Nuclear Facilities ........... __.__ _

Date

_ _ _

REV 18, 9/06

SOP-A.1 Page 2 of 35 3.0 Purpose and Discussion 3.1 General 3.1.1 The pre-operational checks shall be performed by a licensed reactor operator or trainee(s) under the direct supervision of a licensed reactor operator.

3.1.2 Pre-operational checkoff sheets and other materials documenting completion of the checkouts shall be maintained in accordance with the Technical Specifications.

3.1.3 The following conventions shall be used with this procedure:

3.1.3.1 An underlined statement implies a conniand, or action to be taken.

3.1.3.2 Quotation marks indicate annunciation at the console.

3.1.3.3 Parentheses are used to denote the required indication or instrument reading.

3.1.3.4 Discrepancies shall be noted with an asterisk in the blank provided on the check off sheet and explained in the comments section of the respective weekly or daily checkoff sheets.

3.1.3.5 Asterisks (*) are used to indicate items requiring values to be recorded within the instructions sections of this procedure, or on the Weekly Pre-operational Checkout List (UFTR Form SOP-A. IA), or on the Daily Pre-operational Checkout List (UFTR Forn SOP-A. IB) when used to record the results of the weekly and daily checkouts.

3.1.4 The reactor console key must be under the control of a licensed reactor operator at all times. If the console is left unattended, the key shall be secured by being in the actual possession of a licensed reactor operator or locked in the designated key cabinet.

REV 18, 9/06

SOP-A.1 Page 3 of 35 3.2 Weekly Pre-operational Checks 3.2.1 The weekly pre-operational checkout of the UFTR will be performed routinely on the first working day of the week when the reactor is operable. During extended shutdown periods for administrative purposes, maintenance, or modifications, the weekly pre-operational checks will be performed each week on the operable systems.

3.2.1.1 A single page abbreviated form (UJFTR Form SOP-A. 1A) as contained in Appendix I will normally be used to record these checkout actions and results, but 3.2.1.2 A copy of SOP-A. 1 (Steps 7.0 through 7.1.25) may be used to document performance of the weekly checkout.

3.2.2 The weekly pre-operational checks (SOP-A.1, Steps 7.0 to 7.1.25) shall have been completely performed within seven (7) days prior to reactor startup except that any item or situation not required by Technical Specifications for operation or to make the reactor operable may be omitted provided that:

3.2.2.1 The deviation is noted on UJFTR Form SOP-A.1A (Weekly Pre-operational Checkout List) or on the copy of SOP-A. 1 (Steps 7.0 through 7.1.25) used to document the performance of the weekly checkout in the comments section when the deviation occurs during the performance of the weekly checkout, and upon discovery in the Operations Log; and 3.2.2.2 All operations that involve making the reactor operable must be specifically authorized by the Reactor Manager or the Facility Director and noted in the Operations Log indicating that the deviating condition is compatible with the Technical Specifications requirement for startup or reactor operability.

3.3 Daily Pre-operational Checks 3.3.1 The daily pre-operational checkout of the UFTR will be performed in accordance with the checklist starting with Step 7.2.

3.3.1.1 A two page abbreviated form (UJFTR Form SOP-A.1B) as contained in Appendix I will normally be used to record these checkout actions and results, but 3.3.1.2 A copy of SOP-A. 1 (Steps 7.2 to 7.2.6.4) may be used to document completion of the daily checkout.

REV 18, 9/06

SOP-A.1 Page 4 of 35 3.3.2 A daily pre-operational check must have been started and satisfactorily completed within eight (8) hours prior to reactor startup. Items or situations checked by SOP-A. 1, Steps 7.2 to 7.2.6.4 may be omitted for satisfactory completion of the daily pre-operational check, provided that:

3.3.2.1 Such deviation is noted in the comments section of UFTR Form SOP-A.IB or the copy of SOP-A. 1 (Steps 7.2 to 7.2.6.4) used to document the daily checkout in the Operations Log; and 3.3.2.2 The operation that the startup supports has been specifically authorized by the Reactor Manager or the Facility Director, who shall indicate with the authorization that:

3.3.2.2.1 The Reactor Manager and/or the Facility Director is fully cognizant of the deviating condition, and 3.3.2.2.2 The deviating condition is compatible with the Technical Specifications requirements for startup or reactor operability.

3.3.3 The requirements for actual completion of the daily and weekly checkouts may be waived providing that the reactor startup is made within six (6) hours of a normal reactor shutdown. For these purposes, a normal reactor shutdown means that the reactor had been critical with proper functioning of all instruments and components, and that a shutdown had been effected under normal conditions.

3.3.4 A deenergization of the nuclear instrumentation (loss of electrical power or opening of the circuit breaker behind the console rear center door) or electrical transient which drops out a scram relay requires a subsequent completion of the daily pre-operational check before the reactor may be started. This startup must be authorized by a licensed senior reactor operator to include "documented verbal concurrence," which must be entered in the reactor Operations Log.

3.4 Successful completion of a weekly pre-operational checkout or a daily pre-operational checkout is defined as performance of all steps listed in the appropriate checklist with attendant observation of required equipment conditions and response except as noted in Sections 3.2.2 and 3.3.2.

REV 18, 9/06

SOP-A.1 Page 5 of 35 4.0 Limits and Precautions 4.1 General 4.1.1 After reactor operation at power, it may take up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for the Argon-41 in the core to decay to a background level (about 1 cps). If the diluting and/or vent fans are stopped while Argon-41 levels are still high, the radiation levels in the reactor cell may become high enough to set off the low level trip on the area monitors. Section 3.3.1 of the UFTR Technical Specifications states that the vent system shall be operated until the stack monitor indicates less than 10 counts per second unless otherwise indicated by facility conditions to include:

4.1.1.1 Loss of building electrical power.

4.1. 1.2 Equipment failure.

4.1.1.3 Cycling console power to dump primary coolant.

4.1.1.4 Performance of tests and surveillances.

4.1.1.5 Initiation of evacuation alarm for tests and surveillances including emergency drills.

NOTE: If the stack count rate monitor indicates 10 cps or higher, the time these fans are secured for these reasons should be minimized.

CAUTION When the stack count rate monitor indicates 10 cps or higher, the diluting and/or vent fans shall not be secured except for one of the conditions delineated in items 4.1.1.1 through 4.1.1.5.

4.1.2 Prior to a startup, no known condition may exist which has the capability of preventing a successful completion of a weekly or daily checkout except as noted in Sections 3.2.2 and 3.3.2.

REV 18, 9/06

SOP-A.1 Page 6 of 35 4.2 Weekly Pre-operational Checks 4.2.1 Entry into the equipment pit is to be controlled by the guidelines enumerated in UFTR SOP-D.3, "Primary Equipment Pit Entry."

4.2.2 Entry into the equipment pit shall be made no sooner than 15 minutes after shutdown from a power run above 1 kW to allow Nitrogen-16 activity to decay. The radiation level shall be checked prior to and during each initial entry. Twenty-four hours after shutdown, gamma levels are normally less than 5 mR/hr. However, contact gamma level at the demineralizer can remain as high as 100 mR/hr.

4.2.3 Prior to entry into the equipment pit, a check shall be made for evidence of primary water leakage. If wet spots or water marks are visible, full Anti-C's will be required until Radiation Control determines that no surface contamination exists above limits specified in UFTR SOP-D. 1. All primary coolant leakage must be reported immediately to the Reactor Manager and the Radiation Control Officer or alternate.

4.2.4 Upon initial entry into the equipment pit, partial Anti-C's shall be worn and swipes taken to determnine the level of contamination. Checks shall be made routinely for visible leaks. UFTR surface contamination limits are 100 DPM/100 cm 2 beta-gamma and 50 DPM/100 cm 2 alpha. If actual levels of contamination are less than these limits, subsequent pit entry does not require Anti-C protection.

5.0 References 5.1 UFTR Safety Analysis Report 5.2 UFTR Technical Specifications 5.3 UFTR Emergency Response Plan 5.4 UFTR Physical Security Plan 5.5 UFTR Operation and Maintenance Manual 5.6 UFTR SOP-D.1, "Radiation Protection and Control" 5.7 UFTR SOP-D.2, "Radiation Work Permit" 5.8 UFTR SOP-D.3, "Primary Equipment Pit Entry" 5.9 UFTR SOP-E. 1, "Changing Primary Purification Demineralizer Resins" 5.10 UFTR ALARA Program REV 18, 9/06

SOP-A.1 Page 7 of 35 6.0 Records Required 6.1 UFTR Operations Log entry 6.2 UFTR Forn SOP-A. 1A (Weekly Pre-operational Checkout List) 6.3 UFTR Form SOP-A.lB (Daily Pre-operational Checkout List) 7.0 Instructions 7.1 Weekly Pre-operational Checks Record start time on UFTR Form SOP-A. IA (if UFTR Form SOP-A. IA is used to record the performance of the weekly pre-operational checks) ..

The time taken to accomplish checkouts following this procedure is needed to accurately reflect utilization and training time at the UFTR and should be entered into the reactor Operations Log.

7.1.1 Stop Core Vent and Stack Dilute Fans ..........................

7.1.2 Diluting Fan System (access from the reactor building annex basement) 7.1.2.1 Check Diluting Fan Drive Belts (condition and tension) .........

(Proper tension is indicated by a deflection of about 1 inch.)

7.1.2.2 Check temperature of motor and diluting fan bearings by touch for excessive heat ...............................

7.1.2.3 Check integrity of fabric coupling between blower housing and duct work ...................................

7.1.2.4 Check the direct reading tachometer (magnetic sensing/hall effect tachometer including magnet physical integrity or optical tachometer including reflective tape) .........................

REV 18, 9/06

SOP-A.1 Page 8 of 35 7.1.3 Check blade gear box oil levels ................................

(Oil level should just be visible. If breather cap air hole is plugged, it may cause abnormal level indication. Add oil as needed with Macoma No. 33

[Shell Oil] or equivalent. Add only the amount of oil required to establish a visible level. A maintenance log page should be used to control oil addition.)

7.1.4 Check zero level of inclined manometers and the M agnehelic gage .........................................

7.1.5 Source Check portal monitor for proper response (each detector should be confirmed to yield a light and an alarm for proper operation) ..........................................

7.1.6 Core Vent and Diluting Fan Systems 7.1.6.1 Depress Core Vent Fan Switch to check core vent fan interlock ..........................................

(With the dilutant fan deenergized, the lower half of the core vent light will illuminate with the upper half deenergized.)

7.1.6.2 Start Stack Diluting Fan (540 rpm minimum) and record rpm indication ...........................................

rpm 7.1.6.3 Verif proper operation of the core vent damper by either of two methods:

7.1.6.3.1 Verif that a significant length of time elapses between fan start and stable flow indication; or ..........................

7.1.6.3.2 Observe that the core vent damper opens slowly as the core vent fan is energized ....................................

7.1.6.4 Record D/P indications for core vent filters and vent flow rate:

Rough Filter (D/P in green range of manometer) ............

in Absolute Filter (D/P in blue range of manometer) ...........

in Vent flow (D/P consistent with flow desired-refer to chart posted under instrument) ...............................

in REV 18, 9/06 TCN: 9/07

SOP-A.1 Page 9 of 35 7.1.7 Start Shield W ater Recirculation Pump .........................

7.1.8 Start Demineralizer Pump ....................................

7.1.9 Reset Magnet Power Key and release (maintain slight down pressure on the key while turning it) ...................................

CAUTION Prior to energizing control blade circuits (drive or clutch), an authorizing signature is required to be entered in the Operations Log, a qualified second person is required to be present in the UFTR complex, and a designated SRO is required to be readily available on call.

NOTE: Any deenergized scram relay ensures that control blade circuits remain deenergized.

(If the dump valve buzzes excessively, cycle console "POWER ON" switch, and repea Step 7.1.9.)

7.1.10 Check exterior lights (4) indicating reactor may be operating ....... _

7.1.11 Start log/linear neutron recorder and check for proper operation and adequate ink and chart paper supply ........................

(The log/linear recorder is placed into operation to provide a record of the neutron level during core filling [Step 7.1.12]. The addition of water adds positive reactivity and therefore reduces shutdown margin.)

7.1.12 Start Primary Coolant Pump and record flow, when stable .......

gpm (Normal flow is about 46-48 gpm; stable flow rate is achieved in about 2 minutes of pump operation.) (Flow shall be > 41 gpm.)

REV 18, 9/06

SOP-A.1 Page 10 of 35 7.1.13 Source Alarm Check 7.1.13.1 Depress Source In/Out Alarm Switch and leave in the "IN" position to energize the source alarm. Rotate Safety I Calibration Switch to Position 3. Operate Safety 1 Trip Test Control to advance indication on log power scale. Verify that at 10-1 % power indication, audible alarm annunciates.

Return Source In/Out Alarm Switch to the "OUT" position (if applicable). Return Safety 1 Controls to OFF or OPERA TE ...........................................

7.1.14 Primary Coolant Resistivity Determinations 7.1.14.1 Check in-line primary coolant resistivity at SOLU-Bridge mounted on the control room wall. Set compensating temperature to temperature indicated by Point 7 (primary coolant inlet) on temperature monitoring panel ..............

7.1.14.2 Check resistivity at inlet to demineralizer ............

Megohm-cm 7.1.14.3 Check resistivity at outlet firom demineralizer and return sensor to monitor inlet to demineralizer .............

Megohm-cm (When outlet resistivity drops and stays below 1 Megohrn-cm, demineralizer resins should be changed. A Radiation Work Permit (RWP) must be prepared (see UFTR SOP-D.2) and used for changing of primary resins, as per UFTR SOP-E. 1.)

7.1.15 Blade Withdrawal Time Measurements NOTE: Commencement of this step requires that a qualified second person be entered in the Operations Log, and present in the UFTR complex, and that an authorizing signature be made by the Reactor Manager or his assigned representative approving the reactor operation of putting the UFTR in a non-secured status. A designated SRO is also required to be readily available on call.

These checks verify proper operation of the blade drive motors and digital indicators.

REV 18, 9/06

SOP-A.1 Page 11 of 35 7.1.15.1 Sequentially measure and record elapsed time for a full withdrawal of each blade as indicated by the red upper limit light illuminated, record the blade position at fully inserted and fully withdrawn and return the blade to the fully inserted position (white down light illuminated).

NOTE: As one blade is being inserted, the next in the test sequence may be withdrawn.

NOTE: Proper functioning of neutron instrumentation should always be observed during reactivity changes such as these; abnormalities should be noted by log entry for further investigation.

BLADE POSITION WITHDRAWAL BLADE Full In Full Out TIME (Seconds)

Safety 1 Safety 2 Safety 3 Regulating 7.1.16 Dump primary coolant as per UFTR SOP-A.4 Step 7.9 ............

7.1.17 Secure the console Magnet Power Key ......... ...............

The reactor console key must always be under direct control of a licensed operator or locked in the key cabinet mounted on the east side of the reactor.

7.1.18 Secure log/linear recorder and temperature monitor/recorder as necessary or appropriate. Secure core vent and stack dilution fans if appropriate.

See Argon-41 Caution in Item 4.1.1.

Log/linear recorder is normally left with chart drive off and both pens lifted.

REV 18, 9/06

SOP-A.1 Page 12 of 35 7.1.19 Equipment Pit Checkout 7.1.19.1 Preparation for equipment pit checkout:

7.1.19.1.1 Remove the shielding from the primary equipment pit ........

7.1.19.1.2 Assemble three (3) capped, labelled plastic bottles for sample collection, one (1) one liter bottle and two (2) bottles of at least 100 ml capacity. Rinse sample bottles with demineralized water prior to entry into the pit.

Verify that the capped bottles do not leak.

7.1.19.1.3 Fill a fourth large bottle about one-half full of tap water for an equipment pit alarm check. Place all bottles on the stepoff pad for the primary equipment pit.

7.1.19.1.4 Place a low level beta gamma survey meter on the equipment pit stepoff pad. Record survey instrument and serial number .................................. * /*

7.1.19.1.5 Prepare four (4) or more swipes for contamination survey and place on the equipment pit stepoff pad.

7.1.19.1.6 Perform a pit entry per SOP-D.3 ..........................

7.1.19.2 Gamma Radiation Levels 7.1.19.2.1 Check Primary Coolant Tank (Maximum Gamma Level) ....................................

mR/hr (Nonnally at or near background-abnonrmal reading could indicate fuel meat is exposed to cooling water or possible secondary to primary leak. A pin hole leak in the fuel cladding could cause a noticeable increase in the radiation level of the storage tank. Radiation levels will normally be higher than background for a time after shutdown.)

7.1.19.2.2 Check Core Vent Filters (Maximum Garnma Level) externally, on contact ...............................

_ mR/hr (Normally at or near background-abnormal reading could be the result of radioactive products from an experiment that is vented to the core vent system, from a coolant leak (during operation) near the core, or from fission products or activation products in the primary coolant storage tank.)

REV 18, 9/06

SOP-A.1 Page 13 of 35 7.1.19.2.3 Check Primary Purification Demineralizer (Maximum Gamma Level) ...........................

mR/hr (Levels can be as high as 100 mR/br, depending on recent operational history.)

7.1.19.3 Check operation of equipment pit alarm ....................

(Veri alarm occurs when sump is filled with prepared tap water, clears when sump is drained - the bottle will now be used as a purge volume for water samples.)

7.1.19.4 Obtain primary, secondary sample tank, and secondary heat exchanger water samples ................................

Partially fill purge bottle prior to sampling each point to flush the sample lines; then fill the sample bottle about 3/4 full. Properly c bottles.

The primary sample is taken from the inlet side of the demineralizer system into the one liter bottle and is representative of the water in the coolant storage tank.

The sample tank collects a sample of secondary cooling water anytime the secondary cooling system is in operation. This sample is collected in a 100 ml or larger bottle and is representative of the radioactive content of effluent discharged to the storm drains in the event of a primary to secondary leak.

The secondary heat exchanger sample is a sample representative of conditions in the secondary heat exchanger at the time of sampling. This sample is collected into a 100 ml or larger bottle.

7.1.19.5 Check Demineralizer Flow ............................

gpm (Flow is read at the indicator line near the middle of the flow indicator and taken with the demineralizer pump running.

Nonnal flow for the demineralizer pump is about 0.7 gpm if all filters in line are clean.)

REV 18, 9/06

SOP-A.1 Page 14 of 35 7.1.19.6 Check Rupture Disk for Moisture .........................

(Feel bottom surface gently; moisture could indicate a leak or crack in the disk.)

7.1.19.7 Check Dump Valve ....................................

(Dump valve should operate freely when operated by hand.

Check for water leakage along stem.)

7.1.19.8 Check Primary Coolant Storage Tank Level (20 inches m inim um) ..................................

in CAUTION Water shall not be added to the Primary Coolant Storage Tank after reactor startup commences.

NOTE: Starting the Primary Coolant Pump causes water level to drop about 7 inches in the storage tank, corresponding to 44 gal of water. During power operation, primary coolant is lost due to evaporation at the rate of about 10-30 gal/week for 50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months of 100 kW operation.

7.1.19.9 Perform swipe survey of the equipment pit ..................

7.1.20 Water Sample Analysis 7.1.20.1 Prepare resistivity bridge:

7.1.20.1.1 Monitor resistivity of demineralized water flow at 1.0 gpm until resistivity is one Megohmn-cm or higher.

7.1.20.1.2 Leave the probe immersed in demineralized water; rinse all equipment to be used in collection or analysis.

REV 18, 9/06

SOP-A.1 Page 15 of 35 7.1.20.2 Determine primary coolant sample resistivity:

Add sufficient primary coolant to the beaker to cover the probe electrodes and the vent hole. Record a resistivity value when all air is vented from the probe. (Resistivity shall be greater than 0.4 Megohm-cm.) ..............

Megohrn-cm Empty beaker into reactor cell holdup tank (tank is drained periodically to a radiological waste storage tank). Rinse beaker and probe with demineralized water to decontaminate them.

NOTE: Because secondary water pressure in the heat exchanger is greater than that of the primary, first evidence of a primary-secondary leak should be a large reduction of primary water resistivity.

7.1.20.3 Determine primary coolant sample pH (pH shall be less than 7.0).

Record pH value ..................................... _*

7.1.20.4 Deliver remaining primary sample (100 ml minimum in a properly capped bottle) to Radiation Control for activity analysis as per UFTR SOP-D. 1 ...........................

Primary coolant activity analysis consists of:

1. Gross beta-ganima for general activity.

2. Alpha to detect possible fuel plate leakage.

3. Gross beta-gamma to check for the presence of long-lived activity.

NOTE: Additional spectral analysis on a high purity germanium (HPGe) or equivalent detector system may be performed as deemed advisable. Such spectral analysis should be performed whenever the sample indicates an unusually or unexpectedly high level of activity.

7.1.20.5 Obtain shield water sample.

7.1.20.6 Check shield water system resistivity (0.6 Megohm-cm minimum) ......................

Megohm-cm 7.1.20.7 Deliver a sample of shield water (100 ml minimum) to Radiation Control to be checked for gross activity as per U FTR SOP-D . 1 ........................................

REV 18, 9/06

SOP-A.1 Page 16 of 35 7.1.20.8 Deliver a sample of water (100 ml minimum) from the heat exchanger to Radiation Control for analysis of gross activity as per UFTR SOP-D. 1 ..................................

7.1.20.9 Deliver a sample of water (up to 100 ml) from the Secondary Sample Tank to Radiation Control for analysis of gross activity as per UFTR SOP-D. I ............................

7.1.21 Air Particulate Detectors NOTE: Only one of two air particulate detectors is required to be operating to meet the requirements for a valid weekly checkout.

CAUTION Great care must be taken when changing the APD filter paper. Insertion of fingers or foreign objects into the unit may destroy the thin Mylar window of the detector.

7.1.21.1 Stop air pump, replace filter paper, restart pump for each APD (AIM-3BL/AM S 4) ................................ ____________/___________

The removed filter paper should be treated as potentially contaminated material and given to cognizant Radiation Control personnel for counting.

The pre-replacement flow rate for both APDs and the integrated air flow since the previous filter paper replacement for the AMS 4 should be kept with the filter papers for later reference.

7.1.21.2 For Air Particulate Detector #1 (AIM-3BL):

7.1.21.2.1 Turn screw on the bail so the filter holder is snug against inner gasket to ensure air flow does not bypass filter paper.

Check alarm by turning pointer upscale to contact meter pointer.

Alarm indications consist of an intermittent ringing bell and a red light.

Range switch is normally left on the x 10 range.

Move pointer to 0% of scale and reset alarm by depressing reset sw itch .........................................

7.1.21.2.2 Check air flow at middle of the ball (10-45 liters per m inute) .......................................

lpm REV 18, 9/06

SOP-A.1 Page 17 of 35 7.1.21.3 For Air Particulate Detector #2 (AMS 4 ):

7.1.21.3.1 Press the detector lid until the latch is engaged.

Using the front panel keypad, test the inputs and outputs of the unit to include alarm function. Return the unit to nonrmal operation ....................................

7.1.21.3.2 Check airflow via front panel indications (required to be above 10 liters per minute) (AMS4 ) ..................

Ipm 7.1.21.4 Check proper operation of each recorder (ATM3BL/AMS 4 ) ....

7.1.22 Radiation Monitor Console 7.1.22.1 Stack Effluent Monitors 7.1.22.1.1 Check adjustable alarm on Auxiliary Alarm Panel by bringing red pointer of meter down to contact the black indicating pointer. Red light should illuminate and bell should ring. Clear alarm by raising alarm pointer .............

7.1.22.1.2 Check high level non-adjustable alarm by turning switch on stack monitor control module to TRIP ADJ position and holding. Trip 2 (yellow light) and Trip 1 (red light) should illuminate and sonalert alarm should activate. Release switch.

Press TRIP lights to reset stack module if needed .............

7.1.22.2 Area Radiation Monitors NOTE: Occupants in the annex and reactor building should be notified that the siren will be tested.

Place siren in bypass on auxiliary alarm panel ................

Check response of each area monitor trip unit (Trip 2, yellow light; Trip 1, red light and audible alarm) by placing test switch in CHECK SOURCE position.

East North South Trip 2 (2.5 mR/hr) mR/hr Trip 1 (10 mR/hr) mR/hr REV 18, 9/06

SOP-A.1 Page 18 of 35 Check coincidence circuitry by placing two (2) test switches in CHECK SOURCE to lock in the Trip 1 signal for two area monitors in the following combinations:

1. East and South

2. East and North

3. North and South Observe red flashing light indicating siren is operative each time (siren should not sound) .................................

7.1.22.3 With two area monitors alarming at 10 mR/hr and red siren light flashing on, quickly turn siren bypass key to normal and back to bypass for siren test. (Check that green power lights on auxiliary alarm panel labeled "UFTR" and "Annex" go out as sirens activate to indicate proper functioning of both sirens.

Minimize length of time that sirens are on so this exercise can be recognized as a test.) Clear alarm lights on area monitor modules and return bypass key switch to normal and rem ove key ...........................................

Check that red light on air conditioning control box is on, and check that core diluting and vent fans are tripped (bottom halves of control switches energized, top halves deenergized) ..........................................

7.1.22.4 Test manual evacuation alarm, momentarily activating the manual alarnm switch (red toggle switch) on the auxiliary alarm panel. Observe red light. Check that the Green indicating lights go out m om entarily .....................................

7.1.22.5 Reset air conditioner (A/C) (red light on A/C control box goes out) by pressing switch on the bottom of the A/C control box; reset diluting and vent fans by depressing "Reset Fans" button on auxiliary alarm panel .................................

7.1.23 Secure or check secured secondary water, and clean secondary strain er . . . . . . . . . . . . . . . . .. . . . . . . .. . . . . . . . . . .. . . . . . . . . . . . . .

7.1.24 Check for proper operation of security system monitors ............

REV 18, 9/06

SOP-A.1 Page 19 of 35 7.1.25 Complete Records 7.1.25.1 Complete UFTR Form SOP-A.1A (if used):

7.1.25.1.1 Record operator of record and trainees.

7.1.25.1.2 Record time and date checkout was completed.

7.1.25.1.3 Record any discrepancies in the comments section.

7.1.25.2 Complete Operations Log (Pre-operational Check, Weekly Checks section):

7.1.25.2.1 Record operator of record (trainees may be noted).

7.1.25.2.2 Record time and date the weekly checkout was completed as recorded in Step 7.1.25.1.2.

7.1.25.2.3 Complete section labeled "Comments."

If the weekly checkout was completed satisfactorily, indicate satisfactory completion; if the weekly checkout could not be completely performed as written, note any discrepancies and/or abnormalities ................ _*

7.1.25.3 If SOP-A. 1 Steps 7.1 to 7.1.24 are used as a record of completion of the daily pre-operational check, complete the following information:

Time Completed: Date Completed:

Operator:

Trainee:

Comments:

REV 18, 9/06

SOP-A.1 Page 20 of 35 7.2 Daily Pre-operational Checks Record start time in the indicated space at the top of UFTR Form SOP-A.1B (if used to record the performance of the daily pre-operational checks) ....................................... _*

7.2.1 Console and Equipment Power 7.2.1.1 Ensure both east wall electrical power breakers are on .........

7.2.1.2 Ensure well pump motor breaker on, unless on city water .......

7.2.1.3 Depress console "POWER ON" backlit switch, if off, to illuminate ............................................

NOTE: If console appears to be completely deenergized, check overload trip breaker, inside rear center door of console.

If tripped, reset. If it trips again, stop; proceed no further with the checkout. Notify Senior Reactor Operator or Reactor Manager of the situation.

7.2.1.4 Light Bulb Check 7.2.1.4.1 Cycle green "POWER ON" switch to illuminate all scram annunciator lamps on left panel ..........................

NOTE: "INT'LK," "PERIOD," and "SOURCE" lights indicate interlocks (not scrams) and may not illuminate at this time.

7.2.1.4.2 Depress any unlit switch on right motor control annunciator panel .....................................

NOTE: "DUMP VALVE," "FLOW SCRAM," and "WARN WELL" indicators are not switches, but should illuminate due to system conditions.

7.2.1.4.3 Cycle mode selector switch, and leave in "MANUAL" position to verify lamps in both modes are functional .........

7.2.1.4.4 Verify illumination. of control blade "DOWN" lights .........

REV 18, 9/06

SOP-A.1 Page 21 of 35 7.2.1.5 Recorder Checkouts 7.2.1.5.1 Check for sufficient chart and ink supply on Log/Linear recorder.

If off, turn amplifier power and chart drive power on. Lower both pens and check for proper operation ...................

NOTE: If pens are not inking properly, they should be replaced with on-hand spares from the reactor use only locker.

7.2.1.5.2 Check for chart paper supply and proper operation on Area Monitor, Stack Monitor and Air Particulate Detector(s) .......

CAUTION The striker pointers of these Rustrak recorders are very easily damaged by improper chart loading.

7.2.1.5.3 Check for adequate chart paper supply on the temperature m onitor strip chart recorder ..............................

7.2.1.6 Radiation Monitor Console Checkout 7.2.1.6.1 Verify Stack and Radiation Monitor meters are properly functioning with live zeros ...............................

7.2.1.6.2 Verify illumination of green "NO FAIL" lights (4 lamps) .......

7.2.1.6.3 Position fail toggle switch in OFF, trip 2 toggle switch in OFF and alarm toggle switch in ALARM on alarm module .....

7.2.1.6.4 Depress black push button test switch on alarm module and check illumination of all low and high level alarm lamps and operation of audible alarm ............................

7.2.1.6.5 Verify illumination of 2 green lamps and 1 yellow lamp on both units of 24 volt DC power supplies. Open lower panel and verify illumination of 2 red lamps on each battery charger .........................................

REV 18, 9/06

SOP-A.1 Page 22 of 35 7.2.1.7 Auxiliary Alarm Panel Checkout 7.2.1.7.1 Verif that 4 green lights are on ...........................

7.2.1.8 Dump Valve CAUTION Do not perform this step within 3 minutes of a prior interruption of primary flow. Closing of dump valve while water is draining from core will result in a water hammer which will break the rupture disk.

7.2.1.8.1 Rotate Magnet Power Key to RESET (maintaining slight down pressure on key) and release (see Note below).

Check "DUMP VALVE" light goes out (key has returned to OPERATE position) ..................................

NOTE: Prior to energizing control blade circuits (clutch or drive) an authorizing signature is required to be entered in the Operations Log, a qualified second person is required to be present at the UFTR complex and a designated SRO is required to be readily available on call.

If the dump valve buzzes excessively after closing, ccle console "POWER ON" switch and reclose the valve. Repeat as necessary.

7.2.1.8.2 Rotate console Magnet Power Key to OFF; remove and secure the key .........................................

NOTE: Any deenergized scram relay ensures that control blade circuits remain deenergized.

7.2.1.9 Operational Equipment Startup and Checkout Start the following equipment items, and note that the corresponding lights go out:

7.2.1.9.1 Diluting Fan, "STACK DILUTE" (>540 rpm);

record value ........................................

rpm 7.2.1.9.2 Core Vent Fan, "CORE VENT" ... .......................

REV 18, 9/06 TCN: 9/07

SOP-A.1 Page 23 of 35 7.2.1.9.3 Demineralizer Pump, "DEMIN PUMP" . ..................

7.2.1.9.4 Primary Coolant Pump, "PRI COOLANT" (lower half of "DEMIN PUMP" light illuminates); check that primary flow indication stabilizes at normal value; record value ..... * .gpm 7.2.1.9.5 Shield W ater Pum p .....................................

7.2.1.10 Shield Tank Recirculation System 7.2.1.10.1 Check system for no leaks or abnormal noises in pump or w ater line ...........................................

7.2.1.10.2 Check for proper flow (rotameter flow indicator ball should be at or near the top of the indicator scale) ............

7.2.1.10.3 Check for proper valve alignment ........................

7.2.1.11 Air Particulate Detectors 7.2.1.11.1 Check meter, recorder and motor for proper functioning; filter holder screwed up snug; some count level indicated on instrument for AIM-3BL system .......................

Check meter, recorder and motor for proper functioning; filter holder snug for AMS 4 system .......................

7.2.1 .11i.2 Check and record air flow rate for AIM-3BL system (normally 10-45 liters/minute) and also check and record air flow rate for AMS4 system (normally above 10 liters/minute) ............................. ** 1pmn/* 1pm 7.2.1.11.3 Check range switch at normal setting for AIM-3BL system (xl1 ) .......................................

7.2.1.11.4 Check "READY" light on, "MALFUNCTION" light off for AM S4 system ....................................

7.2.1.12 Check portal monitor for power on and no malfunction or alarm indicated ........................................

REV 18, 9/06

SOP-A.1 Page 24 of 35 7.2.1.13 In-line Primary Resistivity Bridge Checks 7.2.1.13.1 Verify power switch is on and green lamp is illuminated; check for operability of red lamp ........................

7.2.1.13.2 Set compensating temperature (from primary coolant inlet temperature), place selector switch at INLET, read resistivity by turning indicating pointer until red light comes on and record resistivity indicated ..........

Megohrm-cm 7.2.1.13.3 Place selector switch at OUTLET, read and record resistivity as above ................................

Megohmn-cm 7.2.1.13.4 Place instrument in use by setting switch to INLET and indicating pointer at about 1 Megohm-cm with green light on ......................................

7.2.2 Operational Checks NOTE: Commencement of the operational checks requires an authorizing signature by the Reactor Manager or his designated representative to be entered in the Operations Log approving the reactor operation and further requires that a qualified second person (name also entered in the Operations Log) be present in the UFTR complex and that a designated SRO be readily available on-call.

7.2.2.1 Rotate console Magnet Power Key to RESET and hold ........

7.2.2.1.1 Verify magnet clutch yellow "ON" lights remain extinguished ........................................

7.2.2.2 Return Console Magnet Key Switch to OPERATE (holding slight down pressure) and verify that:

7.2.2.2.1 All scram lights are out on left annunciator panel ...........

7.2.2.2.2 Magnetic clutch "ON" lights are illuminated ...............

7.2.2.2.3 Red rotating beacon is in operation ......................

7.2.2.2.4 Temperature monitor strip chart recorder is in operation .....

REV 18, 9/06

SOP-A.1 Page 25 of 35 7.2.3 Blade Interlock Checks (Table 4.1 of UFTR Technical Specifications):

NOTE: Before beginning these checks, clear any indicated scram by operation of the console Magnet Power Key to RESET.

7.2.3.1 Place all Calibrate and Trip Test switches in OPERATE or O FF ..............................................

7.2.3.2 Record whether "SOURCE" interlock light is on (illuminated) or off ...............................................

7.2.3.2.1 If "SOURCE" interlock light is on, verify that no control blade can be withdrawn ...............................

7.2.3.2.2 Observe neutron count level; if below 2 cps, insert PuBe source into a vertical port (CVP preferred). Record neutron count level (should be >2 cps) ..................

cps CAUTION If PuBe source is inserted, depress source alarm to display red light, post warning sign, and document source insertion in the Operations Log.

7.2.3.2.3 Clear "SOURCE" interlock (if needed) by operation of Safety-1/Log Calibrate Switch to position 2 and return to OPERA TE .........................................

7.2.3.3 Calibrate and Trip Test Switches 7.2.3.3.1 Rotate Safety 1 Calibrate Switch to ZERO and verify "INT'LK" (interlock) light comes on and return to O PERA TE .........................................

7.2.3.3.2 Momentarily activate Period Calibrate Switch to verify that "INT'LK" light comes on. Release switch and verify "INT'LK" light goes out ..............................

7.2.3.3.3 Hold Safety 2 Calibrate Switch in ZERO position to verify that "INT'LK" light comes on. Release switch and verify "INT'LK" light goes out .........................

REV 18, 9/06

SOP-A.1 Page 26 of 35 7.2.3.3.4 Activate Safety-1 Trip Test Switch (rotate switch only until it clears the OFF position) and verify that no control blade can be withdrawn. Return switch to OFF ............

7.2.3.4 Ten Second Period Interlock 7.2.3.4.1 Activate Period Trip Test Control circuit and verif. that "FAST PERIOD" interlock comes on at 10 seconds .........

7.2.3.4.2 Advance the control to keep indicated period between 10 and 3 seconds and verify that no control blade can be withdrawn. Return control to OFF ......................

7.2.3.5 Multiple Blade Withdrawal Interlocks 7.2.3.5.1 Verify that no combination of 2 blades can simultaneously be withdrawn. Check all six (6) combinations of 2 b lades .................. ........................

7.2.4 Nuclear Instrument and Calibration Checks 7.2.4.1 Hold Period Calibrate Switch in CALIBRATE position and verify period meter indicates 3 seconds. (If meter advances only part way and then drops back, release switch momentarily and repeat.) Release switch for return to OPERATE .........

sec 7.2.4.2 Safety Channel 1 Calibrate Meter Indications 7.2.4.2.1 Place Safety 1 Calibrate Switch in ZERO position and verify Safety Channel 1 meter indicates 0% .............. * %

7.2.4.2.2 Place Safety 1 Calibrate Switch in CALIBRATE and verify Safety Channel 1 meter indicates 100% ............ * %

7.2.4.2.3 Place switch consecutively in positions 1 through 6.

Verify that Wide Range Meter indicates approximately at successive red marks, and that the green pen of the recorder follows. Verify that "EXTENDED RANGE" light goes out at position 2. Return switch to OPERATE ................

REV 18, 9/06

SOP-A.1 Page 27 of 35 7.2.4.3 Linear Range Selector Switch 7.2.4.3.1 Rotate to ZERO, and verify red pen of recorder indicates 0% . Record results ................................. * %

7.2.4.3.2 Record previously determined linear pen calibration level ... *%

Rotate to CALIBRATE and verify red pen of recorder indicates calibration level determined by SOP-E.4, UFTR Nuclear Instrumentation Calibration Check +/-2%.

Record results ...................................... * %

7.2.4.3.3 Return switch to operating range (red pen somewhere on scale) ......................................

7.2.4.4 Safety Channel 2 Calibrate Switch 7.2.4.4.1 Hold in ZERO and verify Safety Channel 2 meter indicates 0%. Release switch and record results ........... *%

7.2.4.4.2 Hold in CALIBRATE and verify meter indicates 100%.

Release switch and record results ...................... *%

7.2.5 Scram and Anmunciation Checks NOTE: Before beginning these checks, clear any indicated scram by operation of the console Magnet Power Key to RESET.

7.2.5.1 Secondary Pressure (Secondary Water Flow) Scram (Well or City Water Logic) 7.2.5.1.1 Rotate Safety I Calibrate Switch to Position 4. Press and hold the well pump power trip bypass switch (well water only).

Operate Safety-1 Trip Test Control to advance indication on log power scale. Verify that at 1% power indication, "SEC PRESS" scram illuminates (on well water, a red warning light will illuminate about 10 seconds before the scram occurs) and "ON" lights go out. Release the bypass switch if used for well water logic ..................

7.2.5.1.2 Start secondary flow and verify flow indication. Operate console Magnet Power Key to RESET and verify that "SEC PRESS" clears ..................................

7.2.5.1.3 Return both controls to OFF or OPERATE .................

REV 18, 9/06

SOP-A.1 Page 28 of 35 7.2.5.2 High Primary Coolant Temperature Scrams 7.2.5.2.1 Set primary coolant inlet temperature selector switch (Point 7) to 970 F. Set inlet trip test switch to TRIP TEST. Verify audible alarm annunciates at 970 F. Record results .........

OF 7.2.5.2.2 Set primary coolant inlet temperature selector switch to 97' F.

Verify "HI PC TEMP" scram is indicated. Record results ....

OF 7.2.5.2.3 Restore temperature monitor/recorder to normal configuration ........................................

7.2.5.2.4 Operate console Magnet Power Key to clear all scrams .......

7.2.5.2.5 Set temperature selector switch to 1500 F. Set trip test switch to TRIP TEST. Verify audible alarm annunciates at 150' F for all points except primary coolant inlet (Point 7).

R ecord results ........................................ OF 7.2.5.2.6 Set temperature selector switch to 155' F. Veri "HI PC TEMP" scram is indicated. Record results ................ *g 7.2.5.2.7 Restore temperature monitor/recorder to normal configuration ........................................

7.2.5.3 Manual Scram 7.2.5.3.1 Operate console Magnet Power Key to clear all scrams.

Raise Safety Blade 1 to about 40 units .....................

7.2.5.3.2 Depress "SCRAM" Bar and verify that "ON" lights go out, "MANUAL" scram illuminates and Safety Blade 1 drops to the bottom position, illuminating "DOWN" lights .

7.2.5.4 Safety Channel 1 High Power Scram 7.2.5.4.1 Operate console Magnet Power Key to clear all scrams.

Raise Safety Blade 2 to about 40 units .....................

7.2.5.4.2 Rotate Safety 1 Calibrate Switch to Position 1 (to stabilize the period circuitry) ...................................

REV 18, 9/06

SOP-A.1 Page 29 of 35 7.2.5.4.3 Rotate Safety Channel 1 Trip Test Control to advance indication on Safety Channel 1 Percent Power Meter.

Verify and record that at 119%, "SAFETY 1" scram illuminates, "ON" lights go out and Safety Blade 2 drops to bottom illuminating "DOWN" lights ...................

7.2.5.4.4 Return both switches to OFF or OPERATE ................

7.2.5.5 Period Scram 7.2.5.5.1 Operate console Magnet Power Key to clear all scrams.

Raise Safety Blade 3 to about 40 units .....................

7.2.5.5.2 Rotate Safety 1 Calibrate Switch to Position 1 ..............

7.2.5.5.3 Rotate Period Trip Test Control and verify and record that at an indicated 3 second period, "PERIOD" scram illuminates, "ON" lights go out and Safety-3 drops to bottom, illuminating "DOWN" lights .................... sec 7.2.5.5.4 Return both switches to OFF or OPERATE ................

7.2.5.6 Safety Channel 2 High Power Scram 7.2.5.6.1 Operate console Magnet Power Key to clear all scrams.

Raise Regulating Blade and any Safety Blade to about 40 units .............................................

7.2.5.6.2 Rotate Safety Channel 2 Trip Test Control to advance indication on Safety Channel 2 Percent Power meter.

Verify and record that at indicated 119%, "SAFETY 2" scram illum inates ................................... * %/

"DUMP VALVE" illuminates (right panel) .................

Lower half of "PRI COOLANT" illuminates (right panel) .....

Three (3) primary coolant scrams illuminate

("COOLANT PUMP," "COOLANT FLOW" and "COOLANT LEVEL") ................................

REV 18, 9/06

SOP-A.1 Page 30 of 35 All control blade magnetic clutch "ON" lights go out .........

All control blade "DOWN" lights illuminate with all control blades at bottom positions ........................

WARNING At this point, DO NOT operate the console magnet power key to RESET. It may be rotated only to the OFF position.

Premature operation (<3 minutes) to the RESET position may result in breakage of the rupture disc because of water hammer.

I 7.2.5.6.3 Return Safety Channel 2 Trip Test Control to OFF ............

7.2.5.6.4 Indicate whether secondary water is shut off or left on (O N/O FF) .......................................... _*

7.2.5.6.5 Secure console Magnet Power Key to proper control .........

7.2.5.6.6 Secure the Log/Linear recorder unless there is a need for its continued operation; shut off the chart drive and lift b oth pens ...........................................

7.2.5.6.7 If the source is to remain inserted in the reactor, ensure the PuBe source light is on (red) and the reminder sign is on disp lay .........................................

7.2.5.6.8 Mark all control room charts with time and date .............

7.2.6 Complete Records 7.2.6.1 Complete UFTR Form SOP-A.1B (if used).

7.2.6.1.1 Record operator of record and trainees.

7.2.6.1.2 Record time and date checkout was completed as indicated by Step 7.2.5.6.9.

7.2.6.1.3 Record any discrepancies in the comments section.

REV 18, 9/06

SOP-A.1 Page 31 of 35 7.2.6.2 Complete Operations Log (Pre-operational Check, Daily Check section).

7.2.6.2.1 Record operator of record (Trainees should be noted).

7.2.6.2.2 Record time daily checkout was begun as recorded in Step 7.2 and time and date the daily checkout was completed as recorded in Step 7.2.5.6.9.

7.2.6.2.3 Complete section labeled "Comments."

If the daily checkout was completed satisfactorily, indicate satisfactory completion; if the daily checkout could not be completely performed as written, note any discrepancies and/or abnormalities.

7.2.6.3 If SOP-A.1 Steps 7.2 to 7.2.6 are used as a record of completion of the daily pre-operational check, complete the following information:

Time Completed: Date Completed:

Operator:

Trainee:

Comments:

7.2.6.4 On the Operations Log for the end of the previous week, ensure "FPH this month," and "FPH this sheet" are completed.

If "FPH this month" as noted is above 4,500 kW-hr, then that fact shall be noted in the comments section of the Operations Log, and the Reactor Manager shall be informed prior to reactor startup to prevent exceeding the posted monthly limit on energy generation.

REV 18, 9/06

SOP-A.1 Page 32 of 35 APPENDIX I WEEKLY AND DAILY CHECKOUT FORMS REV 18, 9/06

SOP-A.1 Page 33 of 35 UFTR FORM SOP-A.IA WEEKLY PRE-OPERATIONAL CHECKOUT LIST DATE START:

7.1 RECORD Start Time ........................... _* 7.1.19.4 OBTAIN Water Samples (Primary Coolant, Secondary Heat Exchanger, Secondary Sample Tank) ............

7.1.1 STOP Core Vent/Stack Dilute Fans .................

7.1.19.5 CHECK Demin. Flow .......................... _*

7.1.2.1 CHECK Dilute Fan Drive Belts ....................

7.1.19.6 CHECK Rupture Disk ...........................

7.1.2.2 CHECK Motor/Fan Bearing Temps .................

7.1.19.7 CHECK Dump Valve ...........................

7.1.2.3 CHECK Blower-Stack Coupling ...................

7.1.19.8 CHECK Storage Tank Level (20" min) ............. _*

7.1.2.4 CHECK Direct Reading Tachometer ................

7.1.19.9 PERFORM Pit Swipe Survey .....................

7.1.3 CHECK Blade Drive Gear Box Oil .................

7.1.20.2 CHECK PC Resistivity from Grab Sample .......... _*

7.1.4 CHECK Manometers/Magnehelic Zero ..............

7.1.20.3 CHECK PC pH from Grab Sample ................ _*

7.1.5 SOURCE CHECK Portal Monitor .................

7.1.20.4 DELIVER Remaining PC Sample to Radcon .........

7.1.6.1 CHECK Vent/Dilute Fan Interlock .................

7.1.20.6 CHECK Shield Tank Sample Resistivity ............ _*

7.1.6.2 START Stack Dilute Fan ........................ _*

7.1.20.7 DELIVER Shield Tank Sample to Radcon ...........

7.1.6.3.1 VERIFY Delay Fan Start to Flow ..................

or 7.1.20.8 DELIVER Heat Exch. Sample to Radcon ............

7.1.6.3.2 OBSERVE Slow Opening Vent Damper .............

7.1.20.9 DELIVER See. Samp. Tank Sample to Radcon .......

7.1.6.4 RECORD D/P - Rough Filter ............... _*

- Absolute Filter .............. _* 7.1.21.1 CHANGE APD Filter Paper (AIM-3BIJAMS 4 ) ....... /

- Vent Flow ..................

7.1.21.2.1 CHECK APD Alanr (AIM-3BL) ..................

7.1.7 START Shield Water Recirculation Pump ............

7.1.21.2.2 CHECK APD Air Flow (AIM-3BL) ............... _*

7.1.8 START Demineralizer Pump ......................

4 7.1.21.3.1 CHECK APD Inputs/Outputs (AMS ) ................

7.1.9 RESET Magnet Power (requires authorization) ........

4 7.1.21.3.2 CHECK APD Air Flow (AMS ) .................. _*

7.1.10 CHECK Exterior Reactor Lights ...................

4 7.1.21.4 CHECK APD Recorders Operation(AIM-3BL/AMS ) .. /

7.1.11 START Log/Linear Recorder ......................

7.1.22.1.1 CHECK Stack Alarm (Aux Alarm Panel) ............

7.1.12 START PC Pump, RECORD Flow ............... _*

7.1.22.1.2 CHECK Stack Alarm (Rad Mon Console) ...........

7.1.13.1 CHECK Source Alarm ...........................

7.1.22.2 PLACE Siren in Bypass, SOURCE CHECK Area Monitors:

7.1.14.1 SET Compensating Temp ........................

East North South 7.1.14.2 CHECK Demin. Inlet Resistivity .................. _* Trip 2 mR/Hr Trip 1 mR/Hr 7.1.14.3 CHECK Demin. Outlet Resistivity ................ _*

7.1.22.3 CHECK Coincidence Circuitry/Red Flashing Light ....

7.1.15.1 MEASURE AND RECORD: TEST Siren in Automatic Mode ....................

Withdrawal Blade Position Time to CHECK Siren/Ventilation Interlock ................

Full In Full Out Full Out S-1 7.1.22.4 TEST Siren in Manual Mode ......................

S-2 S-3 OBSERVE Evacuation Siren Indicator Regulating (Constant Red Light) ............................

7.1.16 DUMP Primary Coolant .......................... 7.1.22.5 RESET Fans/Air Conditioner .....................

7.1.17 SECURE Console Magnet Power Key ............... 7.1.23 CLEAN Secondary Strainer .......................

7.1.18 SECURE Temperature-Log/Linear Recorders ......... 7.1.24 CHECK Security System Operation ................

7.1.19.1.1 REM OVE Pit Shielding .......................... 7.1.25.1.1 RECORD Operator/Trainees .

7.1.19.1.4 RECORD Survey Instrument/Serial Number ...... */

7.1.19.1.6 ENTER Equipment Pit .......................... 7.1.25.1.2 RECORD Completion Time/Date .

_

7.1.19.2.1 CHECK Primary Coolant Tank Gamma Rad Level .... . 7.1.25.1.3 RECORD Discrepancies (use reverse side as needed) ...

7.1.19.2.2 CHECK Core Vent Filters Gamma Radiation Level ...

7.1.25.2.1 RECORD Operator/Trainees (Daily OPS Log) ........

7.1.19.2.3 CHECK Detain. Gamma Radiation Level ........... _*

7.1.25.2.2 RECORD Completion Time/Date (Daily OPS Log) ....

7.1.19.3 CHECK Pit Alarm ..............................

7.1.25.2.3 RECORD Comments (Daily OPS Log) SAT/UNSAT...

REV 18, 9/06

SOP-A.1 Page 34 of 35 UFTR FORM SOP-A.1B DAILY PRE-OPERATIONAL CHECKOUT LIST DATE:

7.2 RECORD Start Time ........................... Air Particulate Detectors Console and Equipment Power 7.2.1.11.1 CHECK APD Operation (AIM3BUAMS 4 ) ......... /

4 7.2.1.1 CHECK East Wall Power Breakers ON ............ 7.2.1.11.2 CHECK APD Air Flow (AIM3BUAMS ) .... */

7.2.1.2 CHECK Well Pump Breaker ON .................. __ 7.2.1.11.3 CHECK Range Switch (xl0) (AIM3BL) ........... _*

7.2.1.3 ILLUMINATE Console "POWER ON" Backlit Switch 7.2.1.11.4 CHECK "READY" Light On, "MALFUNCTION" Light Off (AMS 4) ............................. __

7.2.1.4.1 CYCLE Console "POWER ON" Backlit Switch ......

7.2.1.12 CHECK Portal M onitor ........................

7.2.1.4.2 DEPRESS Unlit Switches, Right Motor Control Annunciator Panel ............................. Resistivity Bridge 7.2.1.4.3 CYCLE Mode Selector Switch, Leave in "MANUAL" . 7.2.1.13.1 CHECK Resistivity Bridge Power ON, Red Light Functional ...................................

7.2.1.4.4 VERIFY "DOWN" Lights ON .................... _ i 7.2.1.13.2 . CHECK Demin Inlet Resistivity ................. ___ _*

Recorder Checkouts 7.2.1.13.3 CHECK Demin Outlet Resistivity ................ _*

7.2.1.5.1 MAKE and/or CHECK Log/Lin Recorder Operational; Amplifier Power, Chart Drive, 7.2.1.13.4 SET Switch to Inlet/Alarm to t Megohm-cm ........ __

C hart Paper ...................................

Operational Checks 7.2.1.5.2 CHECK Operation, Chart Paper for Area Monitors, Stack Monitor, and APD(s) ...................... __ 7.2.2.1 ROTATE Console Magnet Power Key to RESET .. . __

7.2.1.5.3 CHECK Chart Paper for Temperature Monitor ....... __ 7.2.2.1.1 VERIFY Clutch Lights Out ..................... __

Radiation Monitor Console 7.2.2.2.1 RETURN Console Magnet Power Key to OPERATE, VERIFY Scram Lights Out ..................... __

7.2.1.6.1 VERIFY Operation Stack/Radiation Monitors ........ __

7.2.2.2.2 VERIFY Clutch Lights ON ..................... __

7.2.1.6.2 VERIFY "NO FAIL" Lights Illuminated ............ _ I 7.2.2.2.3 VERIFY Red Rotating Beacon On ............... __

7.2.1.6.3 POSITION Radiation Monitor Power Supply Toggle Switches: "FAIL" in OFF, "TRIP 2" in OFF, 7.2.2.2.4 VERIFY Temperature Monitor Strip Chart "ALARM " in ALARM .......................... Recorder Operating ........................... __

7.2.1.6.4 DEPRESS Push Button, CHECK Illumination of Blade Interlock Checks Alarm Lights on Modules and Audible Alarm ........

7.2.3.1 PLACE Calibrate and Test Switches to 7.2.1.6.5 VERIFY all AC and DC Power Supplies Functional .. OPERATE or OFF ............................

Auxiliary Alarm Panel 7.2.3.2 RECORD "SOURCE" Light ON or OFF ..........

7.2.1.7 VERIFY 4 Green Lights ON ..................... 7.2.3.2.1 IF "SOURCE" Interlock ON, VERIFY No Control Blade Can Be Withdrawn .......................

Dump Valve 7.2.3.2.2 IF Less than 2 CPS, INSERT PuBe Source, 7.2.1.8.1 RESET Console Magnet Power Key, CHECK "DUMP RECORD Counts ............................ _

VALVE" Light Out, Key in OPERATE .............

7.2.3.2.3 CLEAR "SOURCE" Interlock ...................

7.2.1.8.2 REMOVE, SECURE Console Magnet Power Key ....

7.2.3.3.1 ROTATE Safety 1 Calibrate Switch to ZERO, Operational Equipment Startup and Checkout VERIFY "INT'LK" Light ON ...................

7.2.1.9.1 START Dilute Fan, RECORD RPM .............. _

7.2.3.3.2 ACTIVATE Period Calibrate Switch, VERIFY "INT'LK" Light ON ...................

7.2.1.9.2 START Core Vent Fan .........................

7.2.3.3.3 HOLD Safety 2 Cal in Zero, "INT'LK" ON .........

7.2.1.9.3 START Demineralizer Pump .....................

7.2.3.3.4 ACTIVATE Safety I Trip Test Switch, 7.2.1.9.4 START Primary Coolant Pump, RECORD Flow ..... _

VERIFY No Control Blade Can Be Withdrawn .....

7.2.1.9.5 START Shield Water Pump ...................... 7.2.3.4.1 ACTIVATE Period Trip Test Control Switch, VERIFY "FAST PERIOD" On at 10 Sec Period ....

Shield Tank Recirculation 7.2.3.4.2 VERIFY No Control Blade Can Be Withdrawn .....

7.2.1.10.1 CHECK Shield Water Recirc Operation ...........

7.2.3.5.1 VERIFY Multiple Blade Interlock ................

7.2.1.10.2 CHECK for Proper Flow .......................

7.2.1.10.3 CHECK for Proper Valve Alignment .............

REV 18, 9/06

SOP-A.1 Page 35 of 35 UFTR FORM SOP-A.IB DAILY PRE-OPERATIONAL CHECKOUT LIST (continued)

Nuclear Instrument and Calibration Checks 7.2.5.4.1 RESET Console Magnet Power Key, RAISE Safety Blade 2 to 40 Units ...................... __

7.2.4.1 Period Switch in Calibrate, Indicated 3 Sec Period ..

7.2.5.4.2 Safety 1 Cal to Position 1 ....................... __

7.2.4.2.1 Safety I Cal in Zero, 0% Indicated ................

Safety 1 Cal in Cal, 100% Indicated ............... _*

7.2.5.4.3 ROTATE Safety Channel 1 Trip Test, at 119%:

7.2.4.2.2 "ON" Lights Out, "DOWN" Lights On, "SAFETY 1" Scram Indicator ON ................ _

7.2.4.2.3 Safety I Cal in Positions 1-6, VERIFY Wide Range Meter at Red Marks, "EXTENDED RANGE" 7.2.5.4.4 Switches to OPERATE or OFF ..................

Light Out at Position 2, Log Pen Follows .......... __

7.2.5.5.1 RESET Console Magnet Power Key, RAISE Safety 7.2.4.3.1 Linear Range to Zero, 0% Indicated .............. _* Blade 3 to 40 Units ............................

7.2.4.3.2 Linear Range to Calibrate, * ......... 7.2.5.5.2 ROTATE Safety I Cal to Position I ..............

7.2.4.3.3 Linear Range to Range of Operation .............. __ 7.2.5.5.3 ROTATE Period Trip Test, at 3 See Period: "ON" Lights Out, "DOWN" Lights On, "PERIOD" Scram 7.2.4.4.1 Safety 2 Calibrate in Zero, 0% Indicated ........... _

Illuminates ..................................

7.2.4.4.2 Safety 2 Calibrate in Cal, 100% Indicated .......... _

7.2.5.5.4 RETURN Switches to OFF or OPERATE ..........

7.2.5.6.1 RESET Console Magnet Power Key, RAISE Regulating and any Safety Blade to 40 Units ........ __

Scram and Annunciation Checks 7.2.5.6.2 ROTATE Safety Channel 2 Trip Test, at 119%:

7.2.5.1.1 Safety I Cal to Position 4, Press and Hold Well Pump "SAFETY 2" Scram On, "DUMP VALVE" On, Bypass Switch (Well Water Only), Safety 1 Trip Test Lower Half "PRI COOLANT" On, "COOLANT PUMP,"

to 1%: VERIFY "SEC PRESS" (-10 See Delay) "COOLANT FLOW," "COOLANT LEVEL" Scram and "ON" Lights Out, Release Bypass Switch (Well Lights On, "ON" Lights Out, "DOWN" Lights On .... _

Water Only) ................................. __

7.2.5.6.3 RETURN Safety 2 Trip Test Switch to OFF ........ __

7.2.5.1.2 START Secondary Cooling, VERIFY Flow, RESET Magnet Power Key, VERIFY "SEC PRESS" 7.2.5.6.4 Secondary Cooling Status (ON/OFF) .............. _*

C lears . . .. .. . . . . . . . . . . . . .. . . . . . . . . . .. . . .. ..

7.2.5.6J5 SECURE Console Magnet Power Key ............ __

7.2.5.1.3 Controls to OPERATE or OFF ..................

7.2.5.6.6 SECURE Log/Lin Recorder Drive, LIFT Pens ......

7.2.5.2.1 SET Inlet Temperature Selector Switch (Point 7) to 970 F, SET Inlet Trip Test Switch to TRIP TEST, 7.2.5.6.7 IF PuBe Source In, CHECK Red Light On, Sign on VERIFY and RECORD Audible at 97 F ......... D isp lay ... .. ..... .. .... ...... ...............

7.2.5.2.2 SET Inlet Temperature Selector Switch to 990 F, 7.2.5.6.8 MARK Control Room Charts with Time/Date ......

VERIFY and RECORD "HI PC TEMP" Scram is On, "ON" Lights Out at 990 F ....................... __

7.2.5.2.3 RESTORE Monitor/Recorder to Normal Complete Records C onfiguration ................................

7.2.6.1.1 RECORD Operator/Trainees 7.2.5.2.4 RESET Console Magnet Power Key ..............

7.2.5.2.5 SET Temperature Selector Switch to 150'F, SET Trip 7.2.6.1.2 RECORD Completion Time/Date Test Switch to TRIP TEST, VERIFY and RECORD Audible Alarm at 150'F (all but Pt. 7) .... . 7.2.6.1.3 RECORD Discrepancies (use reverse side as needed) 7.2.5.2.6 SET Temperature Selector Switch to 1551F, VERIFY and RECORD "HI PC TEMP" Scram On, "ON" Lights Out at 1551F (all but Pt. 7) ........... 7.2.6.2.1 RECORD Operator (in Operations Log) ...........

7.2.5.2.7 RESTORE Monitor/Recorder to Normal .......... 7.2.6.2.2 RECORD Time Checkout was Begun, Time and Date Completed (in Operations Log) ...................

7.2.5.3.1 RESET Console Magnet Power Key, RAISE Safety Blade 1 to 40 Units ...................... 7.2.6.2.3 RECORD Comments (in Operations Log) .........

7.2.5.3.2 DEPRESS Manual Scram Bar, VERIFY "ON" Lights 7.2.6.4 CHECK "FPH THIS MONTH," "FPH THIS SHEET" Out, "DOWN" Lights On, "MANUAL" Scram On ... (in Operations Log); IF necessary, CONTACT Reactor M anager .............................

REV 18, 9/06

ML12075A174

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