ML20006E067

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Application for Renewal of License SNM-0108,deleting U-235 & Pu Sample.Supporting Documentation Encl
ML20006E067
Person / Time
Site: 07000115
Issue date: 01/27/1989
From: Robkin M
WASHINGTON, UNIV. OF, SEATTLE, WA
To: Riedlinger B, Scarano R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20006E066 List:
References
570908, 70908, NUDOCS 9002160189
Download: ML20006E067 (47)
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Text

{{#Wiki_filter:( ^y ~, p s._ %c ? is ( . :. y_iED j AEGiUN y i i University'of Washington 09dd27 AID: 54 ie ' College of Engineering Nuclear Engineering Laboratories i Hail Stop FD-10 -Seattle, WA 98195 t January 26, 1989 j I', Mr. Ross A. Scarano Director-Dhision of Radiological Safety and Safeguards Programs: U.S. Nuclear Regulatory Commission Region V C Materials Radiation Protection Section l 1450 Maria Lane. Suite 210 - h Walnut Creek, California 94596 i F Attention: Beth Riedlinger ~i 4

Subject:

Application for Renewal of Special Nuclear [. Materials License SNM-108 Docket No. 070-00115 m 5 ' Dear Mr. Scaranot ? + rn 1 ~ In accordance with notice of expiration dated 11/01/88-and the provisions of 10 Code of Federal Regulations Part 70.. Section 70.33, l-application for renewal of Special Nuclear Materials License SNM-108 is - hereby submitted. Please direct inquiries on the content of this application to either William P. Miller or Maurice A. Robkin at (206-543-4170). 1 The application is similar to the past renewal applications. Changes ' since the last application are: 1. Deletion of U-235 and Pu sample (Items 6(D) and 6(E)) on expiring license. Both items were reported on RIS HAY and when j shipped were. transferred on the 741 forms to the RIS indicated below. The U-235 metal shipped to Martin-Marrietta Energy Systems Inc., Y-12 Plant. Oak Ridge TN on 4/10/84 to RIS FZF. Contaminated laboratory material and U-235 waste were shipped

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to Rockwell Hanford Operations, Richland, WA on 9/28/84 to RIS VRA to complete disposal of this material. i ' '4 Ggk$ thi & I a a 9002160t89 890417 - _% / M #> REG 5 LIC70 SNM-0108 PDR

Paga 2 -SNM-108 Univ 0 city cf Wahington Jcnu:ry 26, 1989 The 5 Pu-Al foils were shipped to Rockwell Hanford Operations. Richland. WA on 6/6/84 to RIS RRA. i 2. Revision of the values for the U-235 content of the General Electric Fission detectors to reflect the actual amount of i U-235 in the detectors. This application is being rubmitted as an up-to-date renewal application with no references to past documents. I trust that this information will suffice to extend our license for an additional five year period. Sincere yours i C-C urice Robkin. Ph. D. irector Nuclear Engineering Laboratories i Encle l Renewal Application for SNM 108 Gamma Calibration of Ion Chamber Survey Instruments General Source Use Material Pulse Rate Meter Calibration Procedure for Receiving Packages Containing Radioactive Material Procedure for Opening Packages Containing Licensed Radioactive Material Radiologica1 Control - l Radiation Emergency Procedure Emergency Phone List 1 l l l l

University of Washington Renewal Application for SNM 108 Docket No. 070-00115 Administration and Personnel 1. The University of Washington is a state university located in Seattle, Washington. Of ficials of the University include the following: President: William P. Gerbording Provosv: Laurel L. Wilkening Executive Vice President: Tallman Trask, til Vice Provost for Research and Dean of the Graduate School: Gene L. Woodruff

2. Technical Quallfications of Persons Responsible for Radiation Safety Training and Experlence.

Maurice A. Robkin - Prof essor of Environmental Health and Professor of Nuclear Engineering. Dr. Robkin received his Ph. D. In Nuclear Engineering from MIT in 1961.. He was emp l oyed by Genera l E l ectric at their Val lecitos f acility until 1967 and since that time has been on the f aculty of the University of Washington. On July 1,1983 he assumed the duties of Director of the Nuclear Engineering Laboratories. Albert L. Babb - Prof essor of Nuclear Engineering, Prof essor of Chemical Engineering Dr. Babb received his Ph. D. f rom the University of l l l inols in 1951 and has been a member of the Unlversity of Washington faculty since August, 1952. He became responsible for the University of Washington Nuclear Engineering program in 1957 and in 1962 was named Director of the Nucl ear Reactor Laboratories. In this' latter capacity, he was project engineer for the installation and procritical testing of the Univerity's 100 kw nuclear reactor which commenced operation in 1961. Dr. Babb was chairman of the Department of Nuclear Engineering f rom 1965 through August of 1981. Wil llam P. Mil ler - Associate Director f or Reactor Operations Mr. Miller received his Master's degree in Radiological Sciences at the University of Washington in 1963 and since that time has been employed at the University of Washington Nuclear Reactor Facility in various capacities. Through December 1988, he held a Senior Operator's License f or the U. W. Nuclear Reactor. His duties include being the UWNR Health Physicist. l ~

r pcgo 2'Gf 10 SNM-108 R;nceal JOD 190' [ DeLoss L. Fry - Assistant. Director for Facilltles Engineering 4 Mr. Fry recolved his BS degree in Chemical Engineering f rom Purdue in 1958. He has been employed by the University of Washington since Jan 3, 1962, In the department of Nuclear Engineering since 1969, and in his present position since 1980. Until September 1988 he held a Senior Operator's License for the U.W. Nuclear Reactor. Michael J. O'Brien - Radiation Saf ety Of fice, Department of. Env ironmenta l Health and Saf ety M r. O'Brien received his Master's Degree ' in Hygiene from the L University cf Pittsburgh in 1973. He has twenty seven years experience in professional health physics, including the Un!- versity of Washlnton, Brookhaven National Laboratory and the U. S. Pub l ic Hea lth Serv ice. He is certlflod by the American Board of Health Physics.- His duties at the University of Washington cover radiation saf ety for al i University radiation sources. I l l t

r-Pcgo 3 of 10 SNM-108 Ronocal Jan 1989 l Description of'Special Nuclear Material

1. P l uton ium-Bery l l ium Neutron Sources l

t

a. One-Curlo Sources l

The five 1-curle plutonium-beryllium sources are f abricated as i virtually identical sources containing 15.9 grams of p l uton ium(0.98 curies) m1xed with 7.94 grams of beryl I lum 4 metal powder. Each source is encapsulated in a Jacket of tantalum and stelniess steel 0.90" high by 0.825" inner diameter and 1.596" overa l I x 1.025" outer d iameter. Encapsulation was performed by Mound Laboratories. Source Pu Content Neutron Emission August 1961 (neutrons /sec) i-M-83 15.82 gm 1.70 x 106 M-84 15.96 gm 1.69 x 106 6 M-85 15.87 gm 1.70 x 10 6 M-86 15.99 gm 1.68 x 10 6 M-87 15.93 gm 1.68 x 10 Dose rate at 1 cm - unshleided = 1.9 rad /hr neutron and 0.2 rem /hr gamma,

b. Pu-Be source M-915 Source M-915 1s a 2-curle source containing 31.99 grams of Pu and 15.91 grams of Be.

The container is made of tantalum and stainless steel. Inside dimension: 0.82" ~l. D. x 1.49" high. Outside dimension: 1. 0 2" 0.D. x w a s 3.32 x 10g.19" h i g h. T h e e m i s s i o n r a t e L on February 5,1961 n/sec. The encapsulation was performed by Mound Laboratories. This source is authorized under License R-73 and has been used as the Reactor start-up L source. l l

2. The Uranium-235 Fission Detectors l

The Uranium-235 special nuclear material is contained as follows: a. 1.72 gram cathode pl ate on the inner surface of the Westinghouse E l ectric Corporation Model WL-6375 F iss ion Counter l l

gr Pcgo 4 of 10 SNM-108 R0nocal Jcn 1989

b. 2.286 mil l igrams U-235 in Genera l Electric Flssion Chambers as follows:

Model Serial No. Milligrams Enrichment Milligrams Number Uranium U-235 NA-200 6,584,953 1.76 93.035 1.637 NA-100 6,572,554 0.44 93.035 0.409 NA-200 TAETX4-1A 1.07 21.99 0.24 Description of Use of Special Nuclear Material ? 1. Plutonium-beryl llum sources are used for the following purposes: a.- Demonstration of neutron Instrument technology 1

b. Testing and checking detectors t

'c. Operation of a standard plie

d. Demonstrat ion of phys ica l properties of neutron activation, moderation and attenuation, etc.

p e.. Calibration of neutron survey Instruements. p l The term " demonstration" used in items above refers to use by L University of Washington Instructors (approved by the Director l L of the Nuclear Engineering-Laboratories) for theoretical and i practical laboratory Instruction of duly enrolled students and i auditors. The. breadth of this program of Intended use is justif ied in that it permits these materia l s to be used to meet a number of teaching commitments and permits the staff of -the Nuclear Engineering Laboratories and the Radiological L Saf ety Division to concentrate more attention on fewer materials, particularl y the sources. l

2. Urantum-235 F!ssion Detectors l

The fisson detectors are used for neutron flux measurements and demonstrations of neutron Instrument characteristics. Description of Storage of Special Nuclear Material

1. The Pu-Be sources and 235-U fission counters may be used or stored at the following locations:
a. The reactor room of the Nucicar Reactor Building (Restricted Area) and used under supervision of listed i

personnel in control led areas of build ing.

b. Nuclear Engineering Laboratories in Benson Ha l I (Control l ed Area)

l PCgo-5_of 10 SNM-108 Ronecal Jan 1989

2. This material, subject to authorizaton of the Director of the j

Nuclear Engineering Laboratories and the provision of control l and radiation monitoring by the Radiological Saf ety Division l may also be used in such locations asi j a.' Nuclear Physics Laboratory

b. Physics Building student laboratories as required for Instructional purposes
c. Benson Hal I student laboratories as required f or Instructional purposes.

Description of Equipnent, Facilities and Equipment i

1. The number, type and length of remote handling devices.

Two sets of'four foot long tongs. Various rods up to three-feet in length with ends bent to hook-eye bolts on sources. I

2. Storage Containers and Facilities Sources are stored between periods of use in a 55 gal lon steel drum shlelded with 150 pounds of paraffin.

The steel drum has i a mechanical clamp which can be locked to secure the contents.

3. Containers, dev ices, protect i ve c l othing, aux t l ary sh le i d ing, etc. employed in using materials.

For auxillary shleiding a supply of paraf fin, polyethylene and lead bricks are available as needed. Smal ler containers i filled with paraf fin are available for transporting and temporary storage of the Pu-Bo sources. Protective clothing is not necessary with sealed sources and detectors.

4. Physical Plant, laboratory or working area faclities.

See above for storage and use locations. l -s----

6 Pcgo 6 of 10

  • SNM-108 Ron0wal Jan 1989

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5. Radiation Detection Equipment Available for Use
a. Description of instruments 1

Instrument Manufacture Rad iat ion Sensitivity Window Use j Model No. Detected Range Thickness mg/cm Snoopy-Portab le Tracerl eb Neutrons 0-2 mrom/hr NA Survey Neutron Monitor WR-1 i L Portable Bicron Gamma 0-5 mr/hr 400 Survey Survey Meter RSO-5 Beta 7 lon Chaser X-ray / Gamma Keithley Gamme 0-200 mr/hr 417 Survey ) Survey Meter 36100 Beta 50 lon Chaser Portable Alpha Eberline-Alpha 0-500 cpm 1.5 Survey ) Survey Meter AC-15AGA Alpha Survey Eberline Alpha 0-500 cpm 1.5 Survey Meter RM-15 L ContInous air EberiIne AIpha 0-500 cpm 0 air Sampie , Monitor Alpha-1 I ZnS on photo-Baird Atomic Alpha Cnts/ unit time O Swipes and L multipiter 530 Spectrometer air samples l' 6. Instrument Calibration l Rad iation survey meters are ca l lbrated quarterl y. See below l. for detalls for different types.- Calibration data is attached )' to each unit af ter calibration. The calibrations are done by or under the superyIslon of W P Mil ler or M J O'Brien. a.: lon Chambers for gamma. The Northwest Regional Instrument Cal ibration Facil ity (NRICF) Is located at the University of Washington with equipment and J sources'on loan f rom the National Bureau of Standards. The ) Facility is operated by the Radiation Safety Division of the ] University of Washington and is available to other radiation user groups. Source Data: J L Shepherd Mode l No. 81 S/N 7006 Cs-137 Nominal 3 Curie J L Shepherd Model No. 10 S/N 11007 Cs-137 Nominal 0.03 Curie 1 Source accuracy not determined. Cal ibrations ref erred to measurement of gamma exposure rate with graphite chamber and associated equipment suppl led to the Regional Cal ibration i

Pcgo 7 of.10 SNM-108 Ronocal Jan 1989 Facility by NBS. The accuracy of survey meter callbration is i presently 1 7 5. l See attached NRICF Procedures f or gamma calibration of exposure meters and general source use. I b. For pulse type Instruments,l.a.,the portable alpha monitors. i Source Data: New England Nuclear NES-300 Am-241 0.0072 microcures Oct1969 EberlIne Model CS10 Th-230 Nominal 0.003 microcuries Eberline Model CS12 Th-230 Nomina l 0.01 microcuries i Source Accuracy for Am-241 from New England Nuclear is i 4.5 % with direct comparison to a standard certified by National Bureau of Standards. Th-230 sources are compared annually with Am-241 source. l See attached NRICF Procedure for pulse-type Instrument callbration with the ef ficiency of the detector determined using a Th-230 source.

c. Neutron Survey Meter (Snoopy) calibration.

Source Data: Mound Laboratories M-87 Pu-Be Approximatel y 1 i Curle Pu-239 in 1961, Mound Laboratory Calibration measured the output of the neutron sources with a standard error of i 2 %. The present output of.the sources has been corrected f or buildup of-Am-241 with the assumptions that the original Pu-241 content was 0.7 % and the plutonium was sogarated in 1957. The ca lcu l ated neutron output is 2.12 x 10 n/sec. For the cal ibration of the Tracerlab WR-1 Portab le Neutron Monitor (Snoopy) the meter is positioned approximately 3 feet above the floor. Source M-87 Is placed on an aluminum support at distances of 1 meter,50 cm, 40 cm and next to the unit. The neutron scattering increases the meter response - compared to the ca lcu l ated dose rate. The calibration consists of checking that the unit reads consistently over time. With scattering and source bulldup the absolute accuracy is not determined.jftheconversionfactorused for Pu-Be neutrons is 3.5 x 10~ mrem per neutron / square centimeter then the dose rate from the above sources is approximate l y 2.2 mrem /hr at I meter with no scattering. The source is handled w!th a rod. The calibrator has a film badge and stands away f rom the source to read the meter.

Pcgdf8 of 10 SNM-108 Renocal_Jan 1989 { ? I d. 2nS' Scinti l l at ion Count ing System f or air monitoring and swipe samples. j System is calibrated with an Americum-241 (New England Nuclear NES-300) and checked dall y with a Th-230 source (cal lbrated l against Am-241 source). ) Source Data: New England Nuclear NES-300 Am-241 0.0072 microcurles Oct 1969 l Eberline Cs-10 Th-230 nominal 0.003 microcurles Source accuracy _for Am-241 source f rom manuf acturer is i 4.5 % with direct comparison to a standard certifled by National l Bureau of Standards. l The Am-241 source is used to calibrate the activity of the Th-230 source which is used f or dall y check of Instrument. Annual ly f or Intercomparison of Am-241 with Th-230 source which is used for dally check of Instrument. Other instruments available or new units acquired would be calibrated as appropriate before using for radiation monitoring. Proposed Procedures to Protect Health and Minimize Dunger

1. Appropriate shleiding for reduction of neutron exposure hazards during use is provided.

'2. Use of thermal l y f issionab le p l utonium sources and uran t um detectors inside the UWNR wilI be consistent with l i mitat ions , imposed by the UWNR license (R-73).

3. Exposed sources, experiment f acilities or shleids containing Pu-Be sources are Identified with caution signs.

Where app l icab l e, exposed spaces adjacent to neutron sources f acilities are barricaded and provided with caution signs.

4. Relocations of the sources to areas outside the immediate jurisdiction of the Director of the Nuclear Engineering Lab-oratories are performed by the Radiation Safety Division. The Radiation Safety Division provides a University owned vehicle for Intercampus transfers of the materials. This provides security during transfer, and serves as notification that surveillance is needed at the receiving location.
5. See attached procedures for receiving packages containing radioactive material and opening packages containing l icensed radioactive material.
6. A copy of the red lological control for the f acility is posted on the door entering the reactor room is enclosed.

p- -Pcge 9 of_10 SNM-108 Ronceal Jan 1989 L

7. A copy of the radiation emergency procedure f or the f acility Is enclosed.
8. The~ current list with names and telephone numbers of n

responsible persons to be called in case of an emergency is ?; enclosed. This Iist is posted and updated as changes are made in personnel. .s -

9. Training f or Individuals Working in or Frequenting Restricted

{ Areas. Personnel using the licensed material under the supervision of authorized user are instructed as required by 10 CFR 19.12 In one of the following ways

a. Take the 8 hour course of f ered by the University of

'i Washington Radiation Saf ety Olvision. The course consists of four 2-hour sessions covering basic radiation physics, l biological ef fects of radiation, radiation protection procedures, and University / State / Federal regul ations and rules governing the use of radioactive materials.

b. Due to schedule confilets of personnel, a condensed version of the course described above has been presented by the University Radiation Safety Officer.
c. A lecture to subordinates covering the material wilI be given on occession by the authorized user.

Any personel who wil I use any of the material covered by this lleense under the supervision of an authorized user will Intial ly be instructed as above and rsf reshed on annual basis. The encli lary personnel are f ew at this f acility. For the most part' they are University personnel doing maintenance and repair for short time span. The personnel invol ved are escorted _upon entering a restricted area. At these times the sources would be in storage. Individual s are instructed prior to entry to the restricted area as to potential hazard, of any exposure they may receive. Specification of Radiation Saf ety Responsibility and Duties The Nuclear Engineering Laboratories of the Department of Nuclear Engineering and the Radiation Saf ety Division maintain ~l_ the f acil ities to properl y saf eguard possib l e neutron exposure U i and alpha contamination hazards f rom these special nuclear materials. The responsibility is ultimately with the Director of the Nuclear Engineering Laboratory or the University Radiation Safety Officer depending upon the location and use of the sources. ?

E L t f Pcgo 10 of 10 SNM-108 Roncoci Jan 1989 Personnel Monitoring Persons manipulating Pu-Bo sources or performing unsupervised activities in connection with the sources are provided film badges or acceptable personnel monitors. Film badges are currently supplied to the University of Washington by R.S. 4 Landauer, Glenwood, IL on a monthly basis. The film badges Issued to this f acility include neutron sensitive film. Radiation Survey Program

1. In the areas used for storage or use of the sources, routine surveillance, including Instrument monitoring and personnel dosimetry will be prov ided by the the Radiation Saf ety D i v is ion.

The Radiation Safety Division wili extend thse service to other Interim locations of' storage and use.

2. Sources are leak tested at quarterly Intervals by the Radiation Saf ety Division which maintains a permanent record of the resu lts. The leak tests are performed by wiping the source (or as close as f easible if in a holder) with a dry filter paper. The swipes are then analyzed for alpha activity.

Waste Mangement There should be little or no waste with these sealed sources and detectors. Non-transuranic low-level rad ioactive waste is transferred to Radiation Safety f or disposal at an approved burial site. At the present time we are not sure how we would d ispose of transuran ic(i.e. Pu-Be sources) waste. At the present time low level transuranics can be buried at Richland, WA. 1 s -m. m - m - m .m-m .. -, _ _. __ -~

r~- y-I Chapter 13 j GAMMA CALIBRATION OF ION CHAMBER SURVEY INSTRUMENTS 13.1 DISCUSSION These procedures apply to ion chamber survey instruments. Refer to Chapter 17, Gamma Cr.libration of Geiger-Muller Instruments, for the procedure applied to GM type instruments used for gamma exposure rate measurements. These calibrations are performed with a mCs source (photon energy: 662 kev) between 3500 mR/hr and 3 mR/hr. The owner is advised that extension of this calibration to other photon energies and/or exposure rates is at the owner's risk. The calibration values are based on readings normalized to one standard atmosphere (760 mm Hg) and to normal room temperature (22* C) for instruments with probes vented to the atmosphere. The user is advised that instrument readings taken at temperatures and pressures different from these conditions will need to be normalized back to 760 mm Hg and 22' O. Readings are multiplied by the temperature pressure correction factor, C,, to i p ') normalize them back to the calibration conditions. C,, is calculated by the formula: } } (273.15 + T)

  • 760

? 295.15 P ? - f where T s the ambient temperature in ' Celsius [ P s the ambient pressure in mm Hg ] The value of the reference field has been demonstrated to be within i3% of the actual value as determined by comparison with the national standard. 73 1

~ ,y p. ~ \\ l ,j ciuur catinnArios or son citrunirn sunvi:V issTncui'NTs snier nocenensjsgeg3rge, 13.2. ENVIRONMENTAL CONSTRAINTS

1. The ternperature should be between 10'C and 25'C.
2. The barometric pressure should be between 730 mm Hg and 790 mrn Hg.

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3. The relative humidity should be between 15% and 05%.

EXPOSURE RANGES GREATER THAN 50 mR/hr 13.3 13.3.1 Equipment Required 1, 3 Ci 5"Cs source (refer to Chapter 4 General Source Use Procedures)

2. Calibration Track i
3. Positioning Laser k

4.s Hewlett-Packard HP 340 calculator

5. Fluke 8022B DMM G. Booklet containing NRICF Form 03-01-00 CALIBRATION WORKSHEET - lon Chamber Exposure Rate Survey Meter (use NRICF Form 03-0101 booklet for Uni-versity of Washington instruments and NRICF Form 03 0102 booklet for Washing-c ton State D.S.H.S. Instruments) 01-13.3.2 Source Start Up i

(Refer to Figure 4.2 for calibration facility layout.) M

l. Refer to and follow the source start up procedures in Chapter 4, General Source p-L Use Procedures.

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2. Begin filling out the first available calibiation worksheet (see Figure 13.1) in the~

f( booklet for the instrument being calibrated. .a i f,b, ' lI[ 74 3 ) t; - - - - - - ' ' ~ ~ ~ ~

7 CAMMA CAllBRATION OF ION CH AMDER SURVEY INSTRUMENTS NRICF PROCEDURF)$)ygl6 GW N NORTHWEST RADIATION CAusRAT10N =0RxSattf " n T." n. r INSTRUMENT CAllBRATION TT* 1 FACILITY ION CHAWBER EXPOSURE Raft SVRVEY WCTER '

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Cahbration Room Temperature (*C). itLE.1 J 13 L Calibration Ro6m freessre' (m m'Hg')."*'.31Pf *-" * '? ' " -" 'he 9 - Cahbr a tion Roo m Hu midity (%) ~====.*- M -~.".-."."-a 11 '*'ha., Correction Factors, gp g TYPE j 8 Value Pre s sure-Tiliiersturei

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/. ! 'I t e n},;lp.,,-i a . g ;4,r. s m - y.,n : - h.g'4 .O ;; 1**"****" CAUBRATION SOURCE Comma Ray Source. Activity (milheuries) 1 800 to l Source Serial Numb r: -- IOOk H004 ' 9% [.. ' _,,,,,]. C0WWtNTS o 2- - 1 :.- %.a w.m.- ~ ~ -t'- - r',t,;., g F.,. e. L p. f-....T, ,.. n u v, $.., e -a Q mc.. # g j,1 Nw .t 48 MlA eift. P /s/tt' cAusRitto BT; i +Q t L V.; Figure 13.1: Gamma Exposure Rate Meter Calibration Worksheet (NRICF Form j 'W ~ 03-0100), page 1 I,, l o s

wp..,,._- p l lQ ' l.R sps. 'e J. g. s O 4 ,j - > :;k .{ L. / j F - j 5 4MA' CAL,1DRATION OF lON CHAMBER St'RVEY INSTRUMENT, NRICF PROCEDURgsjig]'gtg K t GAWM A R4Y EXPOSURE DATA .] ) IN Rt.d(NI jN$f#WENT CORet itD* P (NT TRUt(etaetNIsPOSVR(/ A0 JUS 1t0 CohedtNT p-tsPo$ ( at ? i aAl D 1(C - ALE 4LA01 ACAO, - 3]AO!NG T/N OR (mm/h,). (.e ).' ,p 9 ~ (**/h, (=R/h R Mo 'p. I Roo o.., 4.<.6 - %1r - o3 '

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g,4 o, % ex y, ^ I ' [CAMMA CALIDMAT!oN OF loN CHAMBER SURVEY INSTRUMENTS NRICF PRoCEDURg,gg " ' ~ ~ [ _a a w e <u. .............w. w, t,g f_p_ _ F ........ =. Figure 13.3: Equipment Setup for Exposure R te Meter Calibration 13.3.3 Instrument Precheck IL Test the batteries in the instrument. Use the " Battery Test" capability of the in ; strument,if available. Otherwise remove the batteries and test them with the Fluke - 8022B DMM. Replace the batteries if they are less than 70% of their nominal value. Record the battery condition on the calibration worksheet (see Figure 13.1).

2. Examine the meter readout to see that it is in good condition. Return the instrument to the owner for repair if the meter readout is damaged. Record the meter readout condition on the calibration worksheet.
3. Examine the general condition of the instrument to see that it is in good condition.

Return the instrument to the owner for repair if the instrument is damaged. Record the instrument's general condition on the calibration worksheet.

4. Record any other preliminary observations on the calibration worksheet.
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[ 13.3.4 Instrument Positioning '+ g

1. De sure that the source is down.

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2. Place the instrument on the cart and raise or lower the platform until the center of the instrument chamber is centered on the laser beam and the platform is level.
3. Check that the instrument is oriented on the cart as shown in Figure 13.3. The NRICF calibrates ion chamber survey instruments with the long axis of the chamber
L parallel with the photon beam axis, unless the client requests a different orientation.

~ For those instruments which do not have a preferred axis, point the window end towards the source; leave the window closed or covered. j 77 k-3

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C AMMA CALIBRATION or ION Cll AMUEH SURVEY INsTRUMI:NTS NRICF l'hoCEDUnijSjigi ?

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4.. Position the video calucra to view the instrument meter.
5. Roll the cart forward or backward until the center of the chamber is one (1) meter j

from the center of the source (the source center is 1.1 cm behind the front of the j source window). Use the meter stick to measure a distance of 98.9 cm from the.

source window.

~ 0. Set the~ cart position marker at one (1) meter (on the positioning tape). This allows the instrument to be accurately positioned at distances other than one (1) meter. 13.3.5. Instrument Calibration - 1. Position cart at a distance from the source corresponding to the desired exposure rate. Refer to Appendix C, Use of the HP 34C Calculator, Section C.4, page 170 for the procedures used to calculate source-detector distances based on prior reference field measurements. - Instruments with several scales will be calibrated at two (2) points on each scale. The first calibration point should be between 25% and 33% of full scale; the second point I should be between 66% and 75% of full scale. The exact values should correspond to a meter scale marking for instruments with meter readouts or a round number for instruments with digital readouts. For an instrument with a logarithmic meter readout, choose one point near the midrange of each decade. For an autoranging instrument, choose four (4) points equally spaced over the instrument's range and within the range of the reference field exposure rates, i

2. Secure the beam area and assure that all the interlocks are clear.
3. Press the red " Irradiate" button on the source control box. A piercing whistle will sound for fifteen (15) seconds and then the source will raise.
4. Read.the instrument response on the VTR screen.
5. Press the green "Off" button on the source control box or turn off the approach interlock control box. Either of these actions will drop the source.
6. Correct the instrument reading for pressure and temperature if the instrument's detection chamber is -vented to the atmosphere (unsealed). Refer to the HP-34C calculator procedures (Appendix C, Use of the HP-34C Calculator, Section C.3, page 108) for the procedures used to calculate this value.

7J Make any required adjustments of the calibration pots and re-irradiate the instru-ment. All corrected instrument readings are expected to be within i10% of the reference field exposure rate at each calibration point. If the instrument cannot be o adjusted such that readings on two points on the scale being tested fall within 10 % 1 x, n8 .M ~ k.

m i C AMMA CALIBRATloN or. loN CHAMHER SURVEY INSTRUMENTS NRICF PRoCEDURF)$ gi r a - of the reference field exposure rate, then calculate a correction factor for that scale. When readings on that scale are multiplied by the correction factor, all readings will. come within 110% of the reference field exposure rate.

8. Record the source-detector distance, the reference field value, I, the observed in-T strument reading, Xo, the corrected instrument reading, Xc, the percent error be-5 tween the corrected instrument reading and the true exposure rate, and the correction factor (ratio of the reference field reading to the corrected instrument reading) on the calibration worksheet. The percent error is calculated using the following equation:

PE = ~ C r x 100% i Xr where PE-s_ percent error in the instrument response Ic _ s' instrument reading, corrected to 22*C and 760 mm Hg (mR/hr) ir a reference field exposure rate (mR/h'r) The percent error is used to show compliance with the applicable NRC Regulatory Guides. Use the following equation to calculate the correction factor: ~CF=' Xc where CF a correction factor all other terms a defined above

9. Prepare a Report of Calibration (see Figure 13.4)- for each instrument using the-relevant information on the calibration worksheet. Transfer the calibration number from the worksheet to the report. Follow the report audit procedure in Chapter 3,

' Auditing of Data and Reports. Make a copy of the report. 10."Unless requested otherwise by the owner, transfer the relevant information from the calibration worksheet to the calibration sticker for all scales of the instrument which . have been calibrated. Place the sticker on the instrument. NRC Regulatory Guides require recalibration periods of not more than one (1) year. Enter a recalibration date of one (1) year from the current date, unless requested otherwise by the owner.

11. Return the instrument and the original of the calibration report to the owner. File the copy of the instrument calibration report.

13.3.6 Source Shutdown

1. Refer to and follow the procedures for source shutdown in Chapter 4, General Source Use Procedures.

79 L

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4 AMM A CAUHRATION OF ION CHAMHER SimVEY INSTRUMl;NT$ - . NRICF Pitoci;pt!)tgji; tigt s '~ NORTHWEST RADIATION ' "E'm or Cm4m V INSTRUMENT CALIBRATION FACILITY ~

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  • 6' r 5" P"" R * S a'r ""

f HRICT FORM 00 01 00(j/67). n.. Cabbrettor. Report Numbr: !~' W *i -l~ Calibretton Performed for:"" hC M Oa

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3 Ruh. u4 ix th keu.h - k% i Div w eik. un Che nt Re f e r e nc e Nu m be .t '- - "-- --- ------ ----- - -- t no,.e,...,,a,R'. A m 'y c-l : survey veter Information viao. won...e,...., l ill a woe. n 6.. a uon u.e. n se o es w or: tWo 5enei miehers't

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fhI p,.y - ; ; g .f"*"T.7 m; -,:p Cabbretton Results set t e ry Ca.n es i 6 o ryT". %) r t e es > Poten; yP ,,e, ca ...e c....e,..n,.e... ..e....., let *1 ' (nergy . Rote et 22'C. 76e an ng Se.ese (6v 0.* (6ev) l - (mR/ht) [aaR/be) (tr.e/.beerwee) 'M (.a Nh L let l - +3D A O* O 100 '... = - -.ws o+

e. qi

.259. 100. a. 1.c o ~+f..... 300 o 9 l'. .}r. 3pp ,,g ..... R E.. too. e.g r 15 2o 1_,,e 15 I 3o t oo 7f I w 1.e t 1.r I 10 t og 'A f l ...'T= Y o tt g.s. 1 g,o .e.._ 5'8#': E sp- %. k.. T\\e. am 4.. k* a J : h,. -,.... -..,d f 4 d Ai l-e 7. l. i. u,~4 s a w [j. % f., 01_:_, _.. g Comments. il i.

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/ !1 gd, .7 r s f, k 'f { This cahbration was performed using a procet ure which is etO1c ed in the Scope of Accreditttlen issued bf 4he Conference *'of Radiation Control Program Directors. Inc." % 4.; .t i.. L.A 42 8* (Please see back of report) k[b Date: 'l /f /W Cahbration Performed By: Cahbration Report Checked By: 7 FAN!L'p7 6 Date; d< ' O / ' Figure 13.4: Ganuna Exposure Rate Meter Calibration Report (NRICP Form 00-0100), page1 80 i 1 l

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CAMM A CALIDitATION OF lON CilAMBER SURVEY INSTitUMENTS NRICI' PitoCEDUltigtgg16 The correction factors given in this report are quotients of the gemme-ray exposure and the g

response to that exposure by the instrument. The instrument was cattbrated at Leo poirds on each scale, for muita-scaled anstruments. and at three points on single-scaled instruments. li ' the chamber mes open to the atmosphere the measurements were normehsed to one standard .etmosphere (760 mm Jtg) and 22 degrees Celsius. Use of the chamber at ether pressures and temperatures rer uire' s normehsation of the results to these reference condillons The normal. 4 ising factor (Cpg) is

omputed from the loDo* win'g*Trpression:

] f !:.J a lps = (273 35.e$ )~ 1 ]l' C J 760

2. *

}W T l 'Cib wherer*? *' T m ' temperature 2n' degrees Tels:us t j 'y P = pressure la sillhmeters mercury J - ~......, The esposure rates at the cabbration positions are t.ased on prior,' measurements by a Shonke-Wyckoff ionssation chamber. and corrected to the date of cahbration froa pretteusly measured values by decay corrections bened on a half-hfe of 30 0 years for *Cs.W .ld..,: The value of the reference field has been demonstrated by e perfo{mance' test to be within 20 03*. of the actual value es, determined,,by,,, comparison with,the,,rjetione,) standard. Id Information on techn cal aspects of this~ report may'be 'ottenned from'**l" bef"C~E'UE. - Ndrthwest' Rediatieri Instrument Cohbration Facshty D'epartment of Eneironm'ntal Health and Safety CS-05 Ifaleersity of Washingte. ; ..., e S'esttle, Washington 8195 l_ (206) 543-0463, nn -3,..,- ($06),533354,5__L T ',,,,,,,,_i v'-- nfm&T Tm 7-r'r :'a ': t-t np N., ..J.O V),,p

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\\ _-.................m .4. .s.. ~.s ..........i ,,,,.......--..--...~....c. .....i.... 'Nh!. s.....,_.-...._,! x w. ..........i..dm...t.s y .s .-..g *, 3,, t2u ..,;.r . dd A.n. 1 ' O. N,'% j. m ;";... *.

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l Figure 13.5: Gamma Exposure Rate Meter Calibration Report (NRICF Form 00-01-00)' page-., 81 1 l k l

.c Y iciMM A CAullRATjoN OF ION Cil AMbt:R SURVEY INSTRUMt;NTS . NRICF l'HoCEDURijsygttg g W Paseo

  • e chesua f ann CALIBRATED

/i[4y[LI

Cahbration Date SenalNo' I$0 Source N Energy Ab2 Exposure instru-

~ Correc. Rate ment tion ,P . m A. hr - Scale Reacing ' Factor. N50 femfhe' fnl ' " A L w t/I, 2 % "/2r itea-t/l,.. D /n.o # %.sf 'W Ehk ^ hs- '~d,o - F[/2.r' 10 N(v bl 9M

2. g 3 g n g, y Next Cahbration Date MND -

- Cga3c,at 22*C,760 mm Hg > Figure 13.0: Gannna Exposure Rate hieter Calibration Sticker + 11 3.4 EXPOSURE RANGES LESS THAN OR EQUAL TO 50 mR/hr 13.4.1 Equipment Required 3

1. 30 mci '37Cs source (refer to Chapter 4, General Source Use Procedures) l y

v

2. Calibration Track 47 j'{'
3. Positioning Laser

,ek

4. Hewlett-Packard HP-34C calculator
fe.

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5. Fluke 8022D DMh!

cj - y, Q: ' 6. Booklet containing NRICF Form 03-01 00 CALIDRATION WORKSHEET - Ion 31 Chamber Exposure Rate Survey hieter (use NRICF Form 03-01-01 booklet for Uni-l: versity of Washington instruments and NRICF Form 03-01-02 booklet for Washing-L., ton State D.S.H.S. Instruments) 8' 1 l 3,( .hl ~

p r. r C AMMA CAUBRATjoN OF loN CHAMBER SURVEY INSTRUMENTS 1 NRICF PRoCEDURgg'g ' i 13.4.2 Source Start Up t 1.. Refer to a'nd follow the General Source Use Procedures. 4

2. Begin filling out the first available calibration worksheet (see Figure 13.1)-in the i

l booklet for the instrument being calibrated. .13.4.3. Instrunwnt Positioning

1. Place the second cart on the track and place the instrument on this cart as shown in

- Figure ~13.3. 2 Raise or lower the platform until the center of the instrument chamber is centered on the laser beam and check that the instrument is positioned on the cart as shown-in Figure 13.3 (excluding ~ video camera). The instrument should be positioned with - the long axis of the chamber parallel with the photon beam axis, unless requested otherwise by the client. - For those instruments which do not have a preferred axis, i point the window end towards the source; leave the window closed or covered.

3. Roll the cart forward or back until the center of the chamber is one (1) meter from the source. Use the tape attached to the side of the source to make this measurement.

The tape is stiff so the slight slack in the tape introduces only a very small error in the distances measured. 13.4.4 Instrument Calibration

1. Position the cart holding the instrument at a desired distance from the source cor-responding to the desired exposure rate. Measure the distance with the tape on the side of the source container. Refer to Appendix C, Use of the HP-34C Cal-culator, Section C.4, page 170 for the procedures used to calculate source-detector distances based on prior reference field measurements. Lock the cart in position with the thumbscrew lock on the front left side of the cart.

~ ~1

2. Remove the plug covering the source.
3. The instrument can be read directly as long as care is taken to limit the amount of time spent in the radiation field. The nominal exposure rate from this source is 10 mR/hr at one (1) meter.
4. Adjustments may also be made while the instrument is being irradiated as long as care is taken to limit radiation doses to the personnel involved.

4 l a s i 83 a 1 :. l

.Nj l:, ' G AMM A cal.lilRATioN or loN Cil AMitEn SURVEY INSTHL'Mf;NTS NRier PhoCEDURFjsgtg

5. Record the instrument response, the true exposure rate, the source-detector distance, -

a . the percent error between the instruinent readilig alid the true exposure rate, and the correction factor'on the calibration worksheet. The equations for calculating the percent error and the correction factor are given in Section 13.3.5, Exposure Ranges Above 50 mR/hr.

6. Prepare a " Report of Calibration" for the instrument based on the corresponding-calibration worksheet. Transfer the relevent information, including the calibration-number, to the calibration report. Follow the report audit procedure in Chapter 3,.

Auditing of Data and Reports. Make a copy of the calibration report.

7. Transfer the relevant information from the calibration worksheet to the calibration sticker for all the scales of the instrument which have been calibrated, unless oth-crwise' requested by the client. Place the sticker on the instrument. Return the instrument and the original of the calibration' report to the owner. File the copy of-the instrument calibration report.

13.4.5 Source Shutdown-

1. Refer to and follow the procedures for source shutdown in Chapter 4, General Source Use Procedures.

.t e i 4 7 - - - _ - - _ - _ - - ~ - - -. - - - - - - - - " - - - - - ' - - " ~ ~

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( l p i . Chapter 4 't . GENERAL SOURCE USE PROCEDURES 4.1 3 CURIE 137Cs SOURCE (Shepherd Model 81-- ~ 8A) L 4.1.1 Pre-operational Source Checks and Procedures. Refer to the calibration facility layout diagram (Figure 4.2). Before operating the source:

1. Remove the lock pin from the source turntable and rotate the turntable 3 Ci437 the turntable. Refer to the source stand detail dia
2. Check to be sure that the 20' collimator is in place.
3. Turn on the air supply to the 3 C1187 the_ supply line which should read 40 psi. The gas bottle p at least 80 psi. Adjust the supply line valves to read 40 psi if needed read bottle (Nitrogen, 224 cubic foot bottle, 99.95% purity, available from UW Stores) if the gas bottle pressure drops below 80 psi.
4. Turn on the source interlock (on/off switch located on the source hous
5. Turn on the alignment laser.
6. Turn on the beam monitor.
7. Plug in the approach interlock lights (on storage case),
8. Turn on the approach interlock control box (on the table next to the sourc box). The source will not raise if the approach interlock is not turned on.

17

T ~ t s 9 JNERAL SOURCE USE PRoCf.DL'RES : .NRICF PRoCEDURgygt'gtg g !l!}: 1'

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'H H iHl!"!M"I MiF F!! - " it:: li ii li il i ilii!!! il! !!!!il,!di !!.' i !!11!!! U !l! ' I 33!diI!! !! !!!! id! H E' il l t ii.". 3 l!8 49'!!Ii!8 it 811 '8!d 8'!! l!f!!!h i ' UN!!!!!! t 8'!N!!! !!! !l?l!!I !! i !!N'I!"i!9 '"i"l!!! !! ' !' I!!lill!!!!!!IN Mfl!N!i ' !!MI!H ll1l"l1il lill!!!!!illili! idll! !! !!lil'.!!!!!:llii ill I!!iiill!!lI"!liiiii!I lij,ii h .li !!!!ilitii !! lil !!!!!!!!!!'til liti!!- If ? 11!!!!!! i i liIll!lill { ] 1 { 'l ii if ] g ' H ! l 'j!j. ij ii{ ij! { ]l j Turntoble/Stond 'i g i i i i i! ! -i i i (Sources not Shown) n n-i i i 1 l i i i ! I i il i 1 il ! ! :t -.i l i - i ri i ! !! i i: t i sp 54 i n i .l i t!. !t CJ Figure 4.1: So'urce Stand Detail-Turntable 9.' Turn on the source' control box.

10. Turn on the VTR system.
1.2
' Source Use L Refer to the source control box diagram (Figure 4.3).
1. Irradiatian control directions:

(a)- For. manual source control set the time control toggle switch on the source control box to " Preset" and set the timer to 999.999 minutes. (b' For timed source control set the time control toggle switch on the source control )- box to " Preset" and set the timer to the irradiate time desired for automatic source drop, less 0.001 minutes. The source takes 0.001 minutes to rise and drop and the timer on/off switch is at the top of the source rod travel.

2. Visually inspect the beam area and assure that all the interlocks are clear.
3. Press the red " Irradiate" button on the source control box. A piercing whistle will sound for fifteen (15) seconds and then the source will raise.
4. Verify that the area monitor is responding.

18 i

  • 9 a

.i ) 2 I ^ Chapter 16 P-ULSE-RATE METER . CALIBRATION 1 l-16.1 LIMITATIONS AND CONSTRAINTS i, This is a general procedure for calibrating instruments used to detect radioactive ma. t'erials contamination. Calibration of GM instruments for radiation field measurement is covered in Chapter 17, Gamma Calibration of Geiger-Muller Instruments. This-procedure is limited to the classes of instruments listed in Table 16.1. The electronic calibration is limited to rates between 1 Hz and 1000 000 Hz. The-radiatio.n detection calibration is limited to the radionuclide check sources for which the NRICF has calibration data (refer to Appendix I, Sealed Source and Check Source Data). - The efficiency calculated is for the geometry of the calibration jig used by the NRICF. Field use at.other count rates, with other sources or in other geometries, must be - at'the discretion of the owner. . Refer to the notebook " PULSE-RATE METER CALIBRATION NOTES" for specific information concerning particular instruments. This notebook contains hand-written notes + on pulse-rate instruments which have been through the facility and which had unusual properties or settings. There is also a file of operating and technical manuals for a limited number of instruments. Instrument repairs are normally not made. If any problems with the instrument occur which are beyond the scope of calibration services, make a note of the condition on the calibration report and return the instrument to the owner. Always make a copy of each calibration report. Make a note of all adjustments and replacements on the calibration teorksheet (see Figure 16.2). This procedure may not be accurate for instruments which have a logarithmic output. Check with the operating manual for such instruments,if possible. Log-scale instruments -designed to measure exposure rates that are calibrated using this procedure will probably not read correctly in a radiation field. Refer to the chapter on calibration of GM exposure rate meters. 111

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~ [ ' CENERAl($oURCE USE PROCEDURES ' NRICF PRoCEDURfjSggil: L4.2 --301MILLICURIE: 137Cs SOURCE (Shepherd-Se-: a ,l ries 10) 4.2'.1 -Source Start:Up Refer to the calibration facility layout diagram (Figure 4.2). tyL ~ 1. Turn on the positioning laser. ,2.! Remove the lock pin from the source turntable andLrotate the turntable.until the '30 mci 337Cs source is aimed down the calibration' track axis. Replace the lock pin in the turntable. 4.2.2' ' Source Use s

1. Remove the shield plug covering the source, thus allowing an external radiation beam.
2. Take care to limit the amount of time spent in the radiation field. The exposure rate

. from this source is about 20 mR/hr at one (1) meter from the source. The source beam is about 40 cm in diameter at one'(1) meter and diverges to 80 cm at two (2) ~ meters. -

3. In keeping with'the principles of ALARA, take care to limit radiation doses to the 4

r f personnel involved. 4.2.3. ! Source Shutdown ' I.', Replace and lock the source cover plug. 2'. Turn off the laser. s r A A 20 1

= 5 'l t ypp 3 E -, ' Pt't.SE RATE METEk'C ALIBRATioN/ ~. ' NRICF PRoCEDt'Itgs At 'g 1 4, 16.3' -LINEARITY CHECK 16.3.1 Equipment Required f p, '1. Instrument under test -

2. Berkeley Nucleonics pulser
3. Tektronix 2215 oscilloscope 4.'UW Nuclear Reactor built special NIM bin (high voltage / pulse divider) 5.: Canberra Industries Model 2022 spectroscopy amplifier O.: Harshaw Type NC 12 single channel analyzer vc 7.- Canberra Industries Model 2017 dual counter-timer 8L Fluke 8022B digital multimeter (DMM)
9. Fluke 80K 40 high voltage probe 110. Cables as needed

{}3 ( .'11.~ Booklet containing NRICF Form 03-04-00 ' CALIBRATION WORKSHEET - Count U . Rate Survey Meter 3{ ' 16.3'.2-Linearity Check Procedure 7,; r 1 g i. l1. Connect the test equipment as shown in Figure 16.1. I s

2. Turn on the instrument.
3. Turn on the NIM bin.-

P

4. Turn on the pulser, i #

j

5. Turn on the oscilloscope, 1

'g

6. Set the pulser to apply a fast, low voltage pulse about one microsecond (1 ps) wide

.g with a fast (nearly vertical) rise time. This should result in a pulse with a fall time appropriate to the detector. Attach the oscilloscope to the pulser to set the pulse shape. 113 s-u I s L

j r.=, o s ;; 1 4 ~ [' ' (f. ' ) l e -- i :- j ] = 1; OENERAL SOURCE USE PROCEDURES NRICF PRoCEDURygig'g 1 y u n I 4 TQ lNT@@ $060A to auAh ATrui 70 Im1PLOCK vaca O O: (NTUtLOCKS ' IMaetatt to *CTOCELL !WT a o --a~< o-o o. 0 e.cn 2. .e 4 nct - en asset =4 APP 40ACM (uf@ LOCK CDefROL Wit SHOAA0 ac0(L 81-da Cont (44 uwif - Figure 4,3: Shepherd 81-8A Control Box (front panel) and Approach Interlock ' Control , Unit ' f s \\- x Source Plug g rowards Loser Moosuring Tope p ne 14; I y n Ja a=s i Figure 4.4: Shepherd Series 10 Calibrator (side view) 22 n:

g y f1 i V ' PULSE.R ATE METER cat.!BRATIoN NidCF PRoCEDUREgig]'gt6 7.' Set the pulser to provide'a pulse of the proper size for the instrument being cali< brated. This is an empirical process. In general, instruments which use an Nal probe accept a negative pulse about 10 millivolts high (use the oscilloscope to set the pulse. height); and G.\\f instruments accept a negative pulse about 2 volts high. (As specific examples. Ludlum instruments accept pulses about 10 millivolts high regardless of the probe, while Johnson instruments accept a 2 volt pulse regardless of the probe.) Check the notebook or the technical manual for specific information concerning the instrument at hand.

8. Disconnect the probe from the detector.

0.- Check the mechanical zero of the meter, adjusting the meter to read zero (0) if necessary.

10. Check the condition of the batteries. Replace any battery that is less than 70% of its nominal voltage,
11. Connect the instrument to the test equipment.
12. Turn on the instrument. Use the multimeter to measure the high voltage bias applied to the probe. This tells us if the bias supply'is working and will be compared to past measurements to tell if_ the bias is set correctly. (The value should be in the range of 900 V to 1000 V for GM probes and 650 V to 900 V for scintillation probes.)
13. Adjust the amplifier, single channel analyzer and timer / scaler in the NIM bin to measure the pulse being sent to the survey meter. Remember that most meters read in counts per minute (cpm, c/m) and that the pulser settings are in pulses per second (hertz, Hz). Yau can check the value shown on'the timer / scaler against the frequency of pulses on the oscilloscope to be sure that the timer / scaler is reading correctly
14. For each scale:

(a) Check each scale of the instrument at two (2) points. The first point should be about 25% to 33% of full scale; and the second point should be about 66Pc to 75% of full scale. (Check logarithmic scale instruments at the midpoint of each decade. Check autoranging instruments at three (3) points between 257o and 75% of full scale.) Set the pulser at a convenient count rate and adjust s the scale potentiometer (usually inside the unit) until the meter reads properly, within loro. Record the pulser output, the' meter scale and reading, and the ratio of the pulser output to the meter reading (gll,',*jfy) on the calibration [ worksheet.

y (b) Recheck the other effected points tested if adjustments were made. Not all in.

struments have a separate pot for each scale, so a compromise may be necessary l g [ between having the "most often used" scales in better ca!!bration than other l 1 F 115 A n I - i.

+ } PL*LSE.R ATE METER CALIDRATION ' NRICF PRoCEDLlRgsg pg + Portable Gh! Contamination hionitors Bench top Gh! Contamination hionitors Portable Nal Contamination hionitors : Bench top Nal Contamination h!onitors Portable Zns Contamination hionitors Bench top.Zns Contamination hionitors Table 10.1 Instrument Classes Acceptable for Pulse Rate hieter Calibration This procedure is not covered in the " Scope of Accreditation" issued from the CRCPD. 16 ~. 21 -MECHANICAL REPAIR AND CHECK r b

16.2.1 - Equipment Required
1. Instrument undEr test
2. Fluke 8022B digital multimeter
3. Booklet containing NRICF Form 03-04-00 CALIBRATION WORKSHEET - Count Rate Survey hieter v

16.2.2 -Mechanical Repair and Check Procedure

11. Begin -filling out the first available calibration worksheet (see Figure 16.2) in the

.worksheet booklet with the calibration report number, o~wnership information and instrutnent infortnation. 1

12. Check the batteries using the instrument's battery test function, if available,or using -

the Fluke Dhthi. Replace the batteries if the battery test indication is low or if the -i Fluke Dhlh! reading is less than 70% of the nominal battery value. Record the state ' of the batteries on the calibration worksheet. (see Figure 16.2).

13. Check the meter readout for dirt, cracks and other signs of disrepair. Return the i

instrument to the owner for repair if the meter shows signs of disrepair. Record the - condition of the meter on the worksheet, s-t Check' the instrument for corrosion, dirt, physical abuse and other signs of disre-pair. Return the instrument to the owner for repair if the instrument shows signs of disrepair. Record the condition of the instrument on the worksheet.

5. Record any other comments concerning the mechanical repair of the instrument on the worksheet.

112 j

Q t l PULSE RATid METER CAltitRATioN ' NRICf' PROCEDt'RgS jlgt'g g g DETECTOR EFFICIENCY EVALUATION 5 Probe Type.' % L A I - Probe Serial. High voltage 6M I 7pecial Comments. Le1 6 WW h4*1-

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' 1* cf - I i. IW -0.e tT.h-i i s oa--, t-'T. *9 -I' t et o MET % %) 1 57.. .. A 44;...J-. 6 %. J... o. 4 C...... s i1o <r.. ' Probe Type. Probe Seriel: High Voltage + l' t* Il 3pecial Comments. 'l lt..., ' l (CPw/eson.e,4.) a.e 6.,.i. e. a.e4.ii.. asn.ii, u.i., t e n. i..., I t, n. s..e, 5.u taelt.d (uci) 4.odias (CN/D'wli

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~ * " * ~ "89 i+HN C Y4 i % ' *t f

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a I l -i i ...d" ...Jia.a. A i.;i. % i Probe Type. '6 Probe Serial. s f. 'l 81 ..,i High Voltage. 'g Special Comments: + i e.eleti.. a.ei. tis. (n.,g, - . A.tl.it,., . v. t... -. - ..t f f l. i..e, a... iJ tefl s.wes. f.m6tt.e (=Ct) neesing (CN/ Dew) (cPwA iene, a.ev,1.)- m...,...e } i .T +-*-,*:-'"' '*"i" ' -- l' -"- ;,.~ - a --r 1 1 g s j %.s i Probe Type. Probi Serief High Voltage: 1 .

  • j ': " ' Tl? f^r W r i, 3:

~~ ~ - - 4'--*'--*l** I Speciel comments 1 a.ei.tl.. (n.,gy A.gl,g ~- p.T1* *9'* '* *' y 'tt je g. y ; '} e.e l e,.t i.. 3 3,g,L,u.t., .g .;j. ggrie,,, $.v taitt.e (ed O Ae.e6ng P(CPW/0PW) ( CPW/te.a.s v,6. ) .t.nar.w g I U* l' ~ a l t %{.. ( i j r (A i \\ [ ~% voltages , Probe Senet-Probe Type. lugh Special Cimments: ,-a..dia, J. ten.i.dp.-(caweawn.pi ..e i. o... ..e i e o... t..,,,. acii.ii,

u....

tensa., s.... wn. -(e r-- r.s (cPwm.a...,i.) ,,,.,y, i i i i I I i i I i i i i Figure 16.3: Pulse. Rate Meter Calibration Worksheet (NRICF Form 03 04-00), page 2 1!7

1 8 t s T

D E.R AT E Mf;T ER C AtlHRATIOh'.

NRICF PROCEDURFgg]'g C O OO WO..O O e 0 .g.. . 5_o l l ~. 0000: O. O' 000000.0.. ~.. ~... ~ l I '~[~ .9 e.. o l l O .c..( .se. - q3,:::' o . uu i O e...-, G s %.q -..a g. o-s3 e oO fi~O l '3' 5' O yd ss st- ~ ~W '=- =.'..:::-..:::rr.!.:: '4.:'... :: en. =.mi. ~~ -- - I I 7, N N I I \\ i L e o,, n s -s n. o n.... 6.lGN WO4 t AG( P.Ket I n.: on n. PlGitat adulttwtge L l Figure 16.1: Pulse-Rate Meter Calibration Setup I w

1 - rutsc.nATc McTER cAttiinATioN snier enoctocars s,i33,gt,-- 3g 0.2 Place the probe over the opening above each source and record the instrument reading on the worksheet. Repeat for each source used. 7.- Place the probe over the table and away from the jig to determine the background ' count rate. Record the reading. 8.5 Turn off the instrument.

9. Calculate the following efficiencies:

(a).\\feter reading per disintegration rate (choose the units of disintegration rate to e match the_ units of the instrument): ' R, - Rs (s =

DsA, where (d E efficiency (e.g.

for. an instrument which reads out in counts per minute, the units of (g will be counts per minute per disintegration per minute, CPhtlDPhi) ~ -R, s instrument reading from source ~s (e.g. in CPhl) Rs s instrument reading due to background (e.g. in CPhi) 3 Da a disintegration rate of source per nanocurie of ac- -tivity (= 2220@'= 37 y) J I A, E activity of source s in nanocuries, nCi (b).\\leter reading per nanocurie of activity: f R, - Rs is = A, where (a s efficiency (e.g. for an instrument which reads out in counts per minute, the units of c4 will be counts per minute per nanocurie, C[c7) all other terms a defined above

10. Record the above efliciencies on the worksheet.
11. Prepare a -Report of Calibration" by transferring the relevant material from the

}). worksheet to the report (see Figure 16.5). Prepare one report for each probe cali-brated. .N. t -. 119 1

NL.$E. RATE METER CALIBRATION. NRICP PROCEDUitggigg. 630ts' - g 4'g' -- NORTHWEST RADIATION c^usRAT10N =0Rxswert. INSTRUMENT CALIBRATION.- FACILITY COUNT RATE SVRVEY WCTER l

  1. R/Cr TORW 03-04rpf f 8/ts)

University of washingt,on,,, Instruments y OwWERSHIP !NFORMAk'1098 - [U* *t 'l 'l AUR Number I l** i

  • i Last Name, d' 4 's4 %

6 lit so i

Department, f'* P+ 8 % /hoF fl.:

'1" I l t 't is - IN STRUW ENT D&ORW ATICI(,L, _,,,_ _,,,,,,,,,,,,,.,,,,. ,e n ili-I Wenuf acturer. L AW Serial Number. 44% Wodel Name. U W. Property Numbee l'hWh 6.3 'I d ' w *

  • 4-Model Number.,,,. I4 Other ID Number.

j@d il ti ' Detector Type. L d t =** Mai= 1

  • ka NJ (Type )..

' " lui y WECMANICAL REPAIR AND C' MECK q g gli ( ... w. .<epiesee j' ether (seeer m ) 1 t'll IIA Betteries - Weter Reedout C n/e -en/ots,, General Condition, c v. ; , ve .ait e,,e, 5 Olif' lser output (volta). i' l^ 5 tarEARITY CHECK _ le (volts).' b " t 7,: < Pu +/C 8 01 Detector High Volte. p-.u,. i.. a te Puleer Date U: Pv i se r. 61.5aet rimeet Ja . aseter Puleer.outeut/ i Commente output i seese i neeeing ueter neeeing l . m t qvi i 3ooeo. mas-j - Iti. par' T-- *3,y o e is'" - i - a M#** N* "J - - 'tt'a e * * - --"** ! i.iV=' i %~t t'o

o. =t c i

%oe v 10'. l tt**- 1,1% ' I ty e. l- ) (' gy A i ho -)qo .. j ' l" " ' " g (y, T -it oT * .I i I .l _ s.u.4s } i,s. .o A - *- i t l j i i 6 i i i NA l _. _.. l 1 l COWWENTs N- .aw , [ 11 6 .E'.iIt$ i s r, j...'d H, ~tt

p, tr g.

-l; - .t s ,i -! 1 s; 3 i o q \\,5 '.]$[ }k .j 8M_M DATE. S/4 /k BY: Figure 16.2: Pulse-Rate Meter Calibration Worksheet (NRICF Form 03-04-00), page 1 116

y t' I 4'; 7 PULSE. RATE METER CALIBR ATION NRICP PROCEDUHQgig'gig NORTHWEST RADIATION, ' REPORT OF cal. BRATION INSTRUMENT CALIBRATION FACILITY-C'"a' ""' 3"r" r "" umer row op.oe.oo<sess> Please complete one form for each probe celibrated Calibration Report Number: W"ll S*l ., t Cahbration performed for ' M *3 d%ti4 = I N L u. R ee t t.a. t 5.E.a H >ua -j Client Reference Number.' ' to o Detector Information Probe Information ', g ~ weave.eiereri tsd W u.a.t ec i ve, r : _LJl- ^ woe.it w '91 i vese n S.r.i m, oer: W i, series %,.e.r:

    • e s

Cahbretton Results - ' " " " ' ' * ' ' ' ' " " * ' " " " " ' " * ' " ' " " * " " " * " " ~ ~ " ' ' ~ ~ " esiteer ou en o.ii..rrt " ~' ~ u -h w.ter e.....e uni e-(.ithra'i sosit'- ~ h u misn.esi.e. (sie.) en ch.., (. ins): 62 j ..ei.ii.a n.e..i..a ca.re ~* "*as i.. i r, u.i., m..... cin...., s,ra. taiti e (vci)' p..s i n g ""' (cew/DPw) (cew/wea.cwri ) (mV1. ...,,.vae i go. % C. -i a trs -

0. t SY l

asto O.co 3 Ii is-- "a ci no &.oit+ t <,as o.ot mo

    • I C Ws3 u.,

s5 o;foi ULoco

c. o 5" tio s iv i i

-"~ r - 8f, -{.,..._;...---.....-9 W. W .......... - J e. b gp - g ~*E' ..i.- I t. ,1 Comments ui ' ',' (*N.,

j. *

.,a t9,:.

  • 84 ;'":..._.

, i. '! T'?*"" -.* uI -m .f~~--"* -(j. .i in "This calibration was performed using a procedure which is C as not included in the Scope of Accreditation issued by the Conference 'of Radiation Control Program Dtr,setors. Inc/* ~s.d SL J (Please see back of report) Calabration Performed By: OW bW Date;

e. / ' IW Cahbration Report Checked By:

GM/MW,Wt Date: W h '[#d' Figure 16.5: Pulse-Rate Meter Calibration Report (NRICF Form 00 04-00), page 1 121

3:j -1 / 'y

.- l

] i.sc.nATE METEn cAttenATioN Nascr racccounr)sgtgtjg scales. Large discrepancies between the meter reading and the true rate should . be clearly noted on the calibration report, j .15.. Turn off th' oscilloscope. j e i .c. 16.~ Turn off the pulser. 117.: Turn off the NIhi bine '18. Turn off the instrument and disconnect'it from the test equipment. t 46.49 -DETECTION EFFICIENCY EVALUATION I6.4.1 Equipment Needed- ,l'. Check source counting jig

2,' Check sources appropriate to the instrument (refer to Appendix'I, Sealed Source.

. land Check Source Data) 7

3. Instrument under test.

}

4. Booklet' containing NRICF Form 03-04-00 CALIBRATION WORKSHEET - Count

< Rate Survey hieter

j 1.0.4.2 Detection Efficiency Evaluation Procedure
.Tieasure the detection efficiency for each probe accompanying the instrument:

9

1. Attach the probe to the instrument.
2. Turn on the instrument.

' 3. Use check sources which match or simulate isotopes which are commonly found in the lab where the instrument is used. Refer to Appendix 1, Scaled Source and Check Source Data for the check sources available. Record the check sources used, the

radiation emitted from each source, the radiation energies and th'e activity of each source on the worksheet.

~ '!4. : Place the' check sources in the calibration jig. The jig can ' hold up to three (3) idifferent sources. The jig places the probe one centimeter (1 cm) from the source. Note on the worksheet if the detection eficiency is measured at a diferent distance. ' 5.EPlace the plastic probe support platform over the calibration jig. 4 118

Q + .i j l i .1 C ' VLSE.R ATE METER CAllBR ATioN. NRICF PRoCEDt:ItF)Syly'g. 1 1 w ~.w n.w w m y rvc.ve< w exx, CALIBRATED ,/ N By [ Cahbration Date _ Serial No. 14 "i k Source. Rad. ht Energy cpm nanocuries ~ Y f5 if h 76 NT) 4 72o 19 0 M 3 _3t 12 0 Spurce to Detector Distance-1 centimeter Next Calibration Due /l/O w rva,.n e.w Figure 16.4: Pulse-Rate Meter Calibration Sticker 1 e

12. Unless otherwise requested by the owner, prepare the instrument sticker (see Fig-ure 16.4)and set the recommended recalibration date to one (1) year after the current J

date. This is in accordance with NRC Regulatory Guides. Attach the sticker to the

instrument.

-13. Return the instrument to the owner along with a copy of the calibration report. File the original report; i Li4. Record any special methods for calibrating the instrument, such as an unusual pulse-size, la' k of calibration pots, etc. in the " PULSE-RATE METER CALIBRATION c -NOTES" notebook. 120

P Pt'LSE. RATE METER CALIBRATION SRICT PROCEDURgs htg% [ g. The efficiency values reported are based on seasurements from e disk source et a source-detector distence of one (1) cetdimeter detector-probe combinetton as made. No evoluetten of deed time or resolving Lane of the The disk source octavnaes are traceable to the notnenal stenderd l e, J l Informeben on technical aepects et this repUt may be obtained fres:.. ( M C, ' Q ) !ai ' . 3.'Uf! Northwest Radiatson Instrument Cohbration Feefhtyih. D'epartment 'of Environmental Heatterne tafety's CS-06 drdversete..of. Weehtngles.a.=.a=.m.-e!.J- '" Seattla. Washington 98196 (206) 543-0463 (cos) 543-2545 99I fft ! 3j[ .A lei 1 r ; *- : .3 9, ,a g,f j

l. a -

4.is. /~*W '

  1. : g.I,--a-

-d--. q,Th t.. , d. d .'.I ,. t a. %.\\ t '.. .. w. -.c 3,. l y m. ,.<,1 - :,m s. ,y \\ N, h . r u.5, 1,-- w.t= w---- r- - o-- ..~ 1 r,1-a;"' g,9i - z n . c., t' i .s,N. er :d:A; ') , q_ L. m 7',.17m ._ u t.. u.i .>.4 ...~ ~

  1. fgmM2rTIN.

..a.- i I b iM L u. '%e pn 5t.,l> L. J,P', l. i i t-Figure 16.6: Pulse-Rate Meter Calibration Report (NRICF Form 00-04-00), page 2 I l 122 t' --w

c= y.

y

-m p3?. ~ y e. - p Lect.sc. narc METen cAusnarios; macr enoctount3gigi,.gi,. SPECIAL NOTE .i p: Regulatory Guide 8.6 establishes ANSI Standard N42.3(1909), also known as IEEE Stan-l 1 - dard No. 309, as the ' preferred test /calibraition procedure for Geiger-MG!ler counters, i The present procedure above does not conform to all points of ANSI N42.3(1969). 'e p-4 )' (' - i k a i k r F 'P L i i I[ 123 !i r - - -

~. 1 ~ Procedure-for Receiving Packages Containing Radioactive Material 1. This procedure is written to cover l'0 CRF 20.205(d) and shou ld be checked f or current regu l ations. It is adv isab l e to know the current regul ations as changes are made over the years. Therefore in anticipationaof a receipt of radioactive materia l, the.regu lations should be consulted. 2. Check packing.I ist and shipping papers f or Isotope (s), amount of activity, and shipper's survey data. ~Any special or unusual package opening requirements should be noted and followed. 3. For packages containing in excess of Type A quantitles as l isted ~1n 10 CFR 20.205(b): Surveys of externa l dose rates and checks f or removab l e~ contamination need to be performed within 3 hours of receiving a package containing radioactive material. 't -f 4 '. Survey of package'for radiation levels: The dose rates should be determined at external surface-of package and at three feet from package. The measurements shou l d agree with shipper's data. In'any event, if they exceed 10 mrem /hr at 3 feet.or 200 mrem /hr at surf ace,.the del ivering carrier and Region ~ Y of-the NRC need to~be immediately notified. 5. Determination of removab le contamination on external' surface of package. 0Using a filter paper, swipe 100 square centimeters of the L external surface of the package and determine the L removab l e acti v ity, i f any. I f the removab le rad ioactive l contamination exceeds 0.01 microcurles per 100 square l ' centimeters the del ivering carrier and Region V of the L NRC need to be notifled immediately. [ h

.{ I 1 PROCEDURE FOR OPENING PACKAGES CONTAINING LICENSED RADIOACTIVE-MATERIAL 'l 1

The recelpt:of radioactive shipments and the openingiot such a

packages very-sel dom occurs at the U of W'Nucl ear Reactor. Hence It-Is adv Isab. e to have the assistance of. the radiation saf ety d iv ision f or opening packages invol y Ing activity greater 'than - ) exempt amounts. The current regul ations need to be consu J ted f or the exempt amounts. In any case, the l ead t ime wou I d al low f or j specif ic pl anning needed for the package in question. The packing iist and shipping papers should Indicate the isotope,_ activity,7 type of packaging, and.the shipper's rad iat ion survey Information. There may be special._ packaging and x consequent l y special. opening procedures f or.the -package which - need to' f o l I owed.. After-the initial receiving procedure has been perf ormed, i 'the f oi l owing basic ~ procedure shou l d ~ be used f or the saf e opening { of packages containg radioactive material. l Personnel opening the package should-have their film badge, approprlcte. survey meters for the iso + opes and activItles in 3 package, swipes, and p l astic g loves. Open.the outer container, survey the Inner container as appropriate. Take a swipe _of the inner container and check with y appropriateLmonitor for removable constamination. If there is more than-one' Inner. container, repeat. if any unexpected removable contamination is detected, the cause'wllI need to be determined and appropriate-actions taken. The aid of radiation safety in monitoring during the opening proceJure would-ald in determining'these actions. Depending upon.the activity and Isotope contained in the package, it may be advisable to have some temporary shleiding available. d 4 r

University of Washington Nuclear Reactor Building l t A RADIOLOGICAL CONTROL f i General rules for the reactor room: g3 RfAQUIREMENTS j i 1. Personnel wli l e ear a monitoring device (film badge, TLD, or i personnel dosimeter). i l 2. Ylsitors are to be escorted. 3. When handling radioactive samples or chemicals, personnel wil l wear a l abcoat. 4 AlI personnel l eaving reactor room wil I normal l y exit through' the door by the chemistry l ab. This wilI facilitate Aar.sonnel monitoring f or Alpha and beta gamma as each person leaves the reactor. room. t 5. If any contamination is found, the help of a responsible person is needed, (f aci l ity personne l or rad iation monitor), they should be contected and appropriate action taken. i 6. Personnel that have been in only the computor room and counting room will normally not be required to monitor upon exiting. 7. I f radioactive sampl es are being hand led, the samples need to be monitored by either the experimenter or reactor personnel. If radioactive materials samples are being handled, the person should wear plastic gloves for protection f rom l contamination. Sampl e handling wil I require the person to monitor their nesJs after completion of the work. 8. Any openlag of a reactor beam port, vertical hole, or thermal column requires that a f acility staf f member or redletion monitor be present and a radiation survey be performed. 9. Personnel using a sealed source ( Pu-Be, Cs-137, Co-60) will need to use tho approplate survey meter (s) during source manipulation.

10. Items removed from the reactor romm must be monitored for contamination by Radiation Saf ety or Reactor Staf f Personnel.

1 ~ ,o-

i 2.2 Radiation Emergency Procedure A radiation emergency is any present, suspected or imminent situation involving redletion which threatens the health and j safety of personnel and/or the publIc. I A. A radiation emergency is Indicated by: I

1. Audible oscillating sound over P.A.

l

2. " Radiation Emergency" light in reception ares
3. P.A. Announcement by building personnel Under amorgency conditions, if necessary, an Individual may remain in the Reactor Room until a 100 mrom dose is accumu-lated. An emergency dose up to 50 Rom for lifesaving and up l

fo 3 Rom for equipment salvage may be allowed. An automatic alarm is set of f by either (a) high area radiation monitor trip (set point is usually 1.5 to 10 mr/hr) or (b) high A-41 release or high stack monitor reading. B. When the alarm sounds (or P.A. anouncement is made): l

1. Reactor operators shall do the following
a. Scram reactor
b. Push emergency button on ventilation control panel Acth n:
1) turns of f f an and closes damper which is also the exhaust from the Reactor Room i
2) puts the Control Room on 100 per cent fresh alr l

3).does not af feet rest of building control

c. Turn of f Reactor Room f an on ventilation control panel Action:
1) turns of f the recirculation f an in Reactor Room only
2) does not af f act intake to the Reactor Room i
d. Turn Reactor Room fresh air to 0 on ventilation control penci Action:
1) closes intake vent to reactor room by 99 per cent
e. Observe the following:
1) Area radiation monitors for high dose rates
2) Steck monitor increase dose rates
3) Remain at the Console and continue to observe and record ccaditions.

If any monitor shows over 200 mr/hr when reactor is below one watt, consider leaving 4'

f. False Alarm if the reactor operator or other persons are cognizant of i

the radiation alarm situation and it does not constitute a radletion emergency this should be announced over the P.A. When this information is known in advance, the alarm systsm should be " held of f" by another staf f member before proceeding as usual, e.g., testing alarm or Internal transfer of hot source. +

2. Other personnel
a. Secure current project
b. Observe area and people in immediate area
c. Assemble immediately at reception desk area
3. At reception desk
e. Senior staff member present will be in charge Date 10/30/86 Rev 4

{ i

b. Account f:r all p^rsonnal in building, y

[

c. Attempt to identif y the problem l
d. Notify senior staff if not present
e. Notify radiation safety of fIce l
4. Search Operation
a. If someone has remained inside or it is not certain j

that everyone has evacuated the Reactor Room a search operation should proceed. Ylew Reactor Room from balcony. l Check lof t,all of fices, rest rooms and counting room. j If necessary search mechanical and chemlstry room. Search operations should proceed without delay. j

5. Rescuo Operatlon
a. Rescue operations should proceed with consideration for i

risks in moving injured personnel versus radiation i ,evels. University Police should.be notifled to obtain L medical assistance (anbulance). I

6. Radiation monitoring and contamination control
a. Radiation surveys should be made as soon as possible l

after life saving activities. Measurements should be i t recorded and persons-'In charge should be kept aware of conditions. t L

b. Contaminat ton control is very Important. Anyone leaving the buffor zone inside the Reactor Room should be monitored, including injured personnel. This contamina-tion control area must be respected except for the most l

serious injurles. l

c. Injured personnel who are contaminated should be l-decontaminated. If possible a radiation safety person y

should accompany the injured into the Emergency Room. p Injured may be taken to either University Hospital or Harborview Medical Center.

7. Off-hours - building unoccupied
a. Universit'y Police, becoming aware of the alarm, should not enter the butIding. They should notify M. J. O'Brlen l

(University Radiaton Safety Of ficer) via the EH & S Paging l and one of the following: W. P. MIllor 527-2921 D. F. Fry 522-5867 M. A. Robkin 453-9401

8. Others to be notified
a. Radiological Assistance Team (Richland) should be called if needed.
b. Notification of the Nuclear Regulatory Commission may be required by 10CFR20.

R

c. State Radiation Control Unit should be notifled according to provisions of WAC 402-24.
d. NEPA(Insurance) should be notified if (a),(b), or (c) above is required.
9. Annual high radiation drill
a. A radiation emorgency drill shall be held least annually.

This drill will cover sections 2.2A through 2.2B6. Refer to the beginning of this section for emergency dose Iimits. Date 10/30/86 Rev 4

(7?TT EMERGENCY PHONE LIST I + t i REACTOR STAFF WORKING HOURS NON-WORKING HOURS i Dr. M. Robkin 3-4170 3-0692 453-9401 f William P Miller .3-4170 527-2921 f DeLoss Fry-3-4170 522-5867 POLICE and ElBE DEPARTMENT l Seattle Fire Department 9-911 University Pollco - Emergency 9-911 or 222 University Police - Campus No. 3-9331 i RADIATION _ SAFETY CONTACTS . Campus Radiation Safety Office p -M.J. O'Brien Radiation Safety Officer 3-0463 Home - 525-8128 l t Monitor's Office (T-Wing Health Science) 3-6328 i: OTHERS l NRC Headquarters.Bethesda (301)-951-0550 l 24 hour in case of emergency j Backup Bethesda. Numbers for -(301)-427-4056 Backup. NRC In case 301-951-0550 (301)-427-4259 Backup is not answering (301)-492-8893 Backup NRC-Walnut Creek Office (Region Y) (415)-943-3700 Insurance (NEPA)- (203)-677-7305 State of Washington Radiation Control 682-5327 Interagency Radiological Assistance Richland Operations Office DOE (509)-376-7381 February 2, 1988 5 L. L l' -1. ..n ,,v. -v- ,,-w ~}}

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