Latest revision as of 16:56, 6 January 2021

Text

Operations Semiannual Rept Jul-Dec 1993
	ML20063M204
Person / Time
Site:	University of Missouri-Columbia
Issue date:	12/31/1993
From:	Meyer W; MISSOURI, UNIV. OF, COLUMBIA, MO
To:	Weiss S; NRC
References
	NUDOCS 9403110208
	Download: ML20063M204 (273)
	v • d • e

{{#Wiki_filter:4 5 Research Reactor Facility II Research Park Columbia. Missouri 65211 UNIVERSITY OF MISSOURI-COLUMBIA Telephone 82 March 3,1994 Seymour H. Weiss, Director U. S. Nuclear Regulatory Commission PDNP M.S.11-B-20 Washington, DC 20555

REFERENCE:

Docket 50-186 University of Missouri Research Reactor License R-103 We have sent, under separate cover, two copies of the Reactor Operations Semi-Annual Report for the University of Missouri Research Reactor. The reporting peric6 covers 1 July 1993 through 31 December 1993. Ifyou have any questions, please feel free to call. Si cerely, bd Walt A. Meyer, Jr. Reactor Manager WAM:bjb enclosure xc: document Control Desk, USNRC p e s , 3 a. y/ 8 .9 Ld - lE COLUMBIA KANSAS CITY ROLLA ST. LOUIS

      #sM /                              w ns wwy nm,n 9403110208 931231 6 PDR    ADOCK 0500 R

1 l sr_ UNIVERSITY OF MISSOURI UNIVERSITY OF MISSOURI RESEARCH REACTOR OPERATIONS SEMI-ANNUAL REPORT 1 July 1993 - 31 December 1993 ggy ,9 re B a NAs l dN$ $ RESEARCH REACTOR FACILITY l

UNIVERSITY OF MISSOURI-UNIVERSITY OF MISSOURI RESEARCH REACTOR- - OPERATIONS SE3/II-ANNUAL REPORT 1 July 1998 - 31. December 1993 RESEARCH REACTOR FACILITY:

6 MIVERSITY- OF MISSOURI J UNIVERSITY OF MISSOURI i RESEARCH REACTOR ] I OPERATIONS SEMI-AXSUAL REPORT i 1 July 1998 - 31 December 1993 I l I l l

#2*

RESEARCH REACTOR FACILITY

 . . . - .   .    -     -~   -           - - - .- - . . -

y 1 9 UNIVERSITY.OF MISSOURI RESEARCH REACTOR FACILITY ;! l l REACTOR OPERATIONS . SEMI-ANNUAL REPORT - 1

Compiled by the Reactor Staff Submitted Februar 1994 by cs V . l Walt A. Me[ r, Jr. l Reactor Manager Reviewed and Apyved Fbo, h J. Charles McKibben Associate Director i ! l y

b i l TABLE OF CONTENTS , Section Pace l 1 I. Reactor Operations Summary I-1 through 6 II. MURR Procedures II-1 through 7 A. Changes to Standard Operating Procedures l B. Changes to MURR Site Emergency Procedures

              & Facility Emergency Procedures C. Changes to Health Physics Standard Operating Procedures D. MURR Shipping Procedures III. Revisions to the Hazards Summary Report           III-1 IV. Plant and System Modifications                     IV-1 V. New Tests and Experiments                         V-1 VI. Special Nuclear Material Activities                VI-1 through 2 VII. Reactor Physics Activities                         VII-1 through 2 VIII. Summary of Radioactive Efiluent Released to the Environment                                     VIII-1 through 6 -

IX. Summary of Environmental Surveys IX-1 through 7 X. Summary of Radiation Exposures to Facility Staff, Experimenters and Visitors X-1 through 2 ii

 ..       - - . _         -            -.     -                     .  =        -_.                .   .. .   --

i i I SECTION I REACTOR OPERATIONS

SUMMARY

1 July 1993 through 31 December 1993 The following table and discussion smnmarizes reactor operations in the period 1 July 1993 through 31 December 1993. Full Power Percent Date Full Power Hours Mecawatt Days of Total Time of Schedule

July 1993 679.19 283.17 91.29 102.24 Aug. 1993 653.12 275.53 87.78 98.32 Sept. 1993 646.12 269.42 89.74 100.51 Oct. 1993 679.52 283.45 91.21 102.16 Nov. 1993 615.58 256.63 85.50 95.76 i Dec. 1993 668.11 278.60 S.! LED 100.58 Total for six 3,941.64 1,646.80 89.24% of 99.95% of month period Time for 6 mos. Sched. Time for at 10 MW 6 mos. at 10 MW
MURR is scheduled to average at least 150 hours per week at 10 MW. Total time is the number of hours in a month or half year. A two day maintenance outage (SMP-31) to replace original graphite elements #2 and #3 on Nov. 22-23,1993, was one reason MURR approached, ,

but did not achieve, its targets of full power operation greater than 90% of total time and 100% of scheduled time. , s There were nine unscheduled shutdowns recorded during the six month period 1 July 1993 through 31 December 1993. Of these unscheduled shutdowns, four were i scrams and five were rod run-ins (RRIs). Seven of the unscheduled shutdowns were spurious in nature, with four of the ; spurious shutdowns attributed to the Trip Actuator Amplifier (TAA) associated with i reactor scram and rod run-in circuits. In addition to normally scheduled testing of the TAAs, the electronics technicians have begun a program to systematically renovate the TAA modules by replacing discrete components in the TAA circuits. July 1993 The reactor operated continuously in July with the following exceptions: four shutdowns for scheduled maintenance and refueling; two unscheduled shutdowns. On July 1, a reactor isolation and reactor scram was initiated when the high , voltage circuit board became disconnected in the high range detector module for the reactor bridge, a part of the area radiation monitoring system (ARMS). There was no ~ I-1 , i

1 high airborne radioactivity levelin contaimnent. The disconnected circuit board caused a loss-of-signal to the ARMS module, a cor dition which automatically initiates a reactor isolation and scram. The circuit board most likely became loose due to vibration during normal operation and sample bandling evolutions on the bridge. The circuit board has since been secured to its connector with cable ties and no further problems of this type have occurred. On July 6, an anti-siphon high level rod run-in occurred during a normal startup < after a scheduled maintenance shutdown. Control room. operators immediately drained the water from the anti-siphon system and reset the rod run-in. With the reactor suberitical, operators monitored the anti siphon system for any indication of leakage by the anti-siphon valves (543 A & B). Anti-siphon pressure decreased and stabilized at or near primary system pressure, indicating seepage past one or both of the 543 valves. The reactor was then shutdown to determine the cause of the leak. ! The 543 A/B valve operating linkages were visually inspected while being operated pneumatically and manually and were found to be intact and operating ! freely. After cycling the valves numerous times, the primary system was placed on-line with no evidence ofleakage past the valves. The primary system was shutdown and the valves were again cycled numerous times. This is consistent with the ; procedure called for in Special Maintenance Preedure (SMP-10), Renlacement of l V543 A/B to seat the valves after replacement of the o-ring seals on the 543 valve ! discs (4" butterfly valves). The primary system was then placed on-line and the anti-siphon system pressure was monitored for approximately one hour with no evidence of pressure decrease and therefore no indication ofleakage. It appears most likely that this problem was an isolated event where one of the valve disc o-rings did not seat ; properly in the valve body. The 543 valves were determined to be capable of performing their safety function and no further problems of this type have since occurred. l Major maintenance items for the month included: physically securing with cable i ties, the high voltage circuit board in the high range area radiation monitor for the reactor bridge; repairing a pin-hole leak on the secondary shell side of pool heat ; exchanger (521B); modifying and repairing the rotary switch assemblies for ! l containment ventilation isolation doors 504 and 505. The switch assembly for door 505 malfunctioned twice during testing of the isolation system with the reactor shutdown because it failed to initiate the door gasketinflation sequence required to l isolate the return side of the containment ventilation system. A Licensee Event l Report describing these events and the corrective actions was forwarded to the Director of Nuclear Reactor Regulation on August 12,1993. - I-2 i

5 Aucust 1993 The reactor operated continuously in August with the following exceptions: four shutdowns for scheduled maintenance and refueling; one unscheduled rod run-in. On August 16, a rod run-in of unknown origin occurred shortly after a normal startup had been completed following a scheduled maintenance / refueling day. No

annunciation or other indication of.the rod run-in occurred. The operators hadjust completed a potentiometer adjustment on the channel #4 wide range monitor. All other reactor indications were normal. The rod run-in was subsequently reset.

Investigation of the reactor systems revealed that all reactor and auxiliary systems indicated normal. The reactor was returned to normal operation at 10 megawatts. On the following maintenance day, electronics technicians attempted to determine if the channel #4 (wide range monitor) potentiometer change was related to the rod run-in. They were unable to verify any correlation. Major maintenance items for the month included: installing and commencing operation of modification package 93-1, Facility Deionized Water Tanks--with this , modification, a separate deionized water source (three 420 gallon tanks) has been installed for laboratory users while the main tanks--7,000 gallon T-300 and T-301-- { remain dedicated to reactor systems; replacing cooling tower fan #3 fan blades and hub assembly and repairing gear box mounting bracket; shipping 8 spent fuel i elements in the BMI-1 shipping cask; replacing primary 501B pump; replacmg : cooling tower fan #2 breaker; transferring into drying barrels depleted pool ; deionization bed "R" and loading new pool deionization bed "L". : Sectember 1993 The reactor operated continuously in September with the following exceptions: ! four shutdowns for scheduled maintenance and refueling. There were no unscheduled . shutdowns this month. On September 7,1993, while performing compliance testing of the Primary

Coolant flow safety channel connected to flow transmitter FT-912E, the scram setpoint for the low flow scram for the heat exchanger 503B leg was below the Limiting Safety System Setpoint (LSSS) of 160 gpm required by Technical Specification 2.2. A Licmsee Event Report detailing the corrective action taken was . sent to the Director of Nuclear Reactor Regulation, Washington, D.C., on September 27,1993. l Significant maintenance activity for the month included: replacing reactor loop ; flow alarm trip unit 920C; replacing the socket for relay K-38 (reactor loop low flow); j 1 I-3

     ---        .       ..            .    .      -- .         ~                      - . -

t I 4 l shipping 8 spent fuel elements; replacing the air seals on the actuator for the reactor .; outlet isolation valve 507A; replacing the yellow scram-leg trip actuator amplifier. l l October 1993 The reactor operated continuously in October with the following exceptions: four shutdowns for scheduled maintenance and refueling; three unscheduled shutdowns. 1 On October 5, a rod not in contact with magnet rod run-in was automatically initiated when the trip actuator amplifier (TAA) for the " green" leg of the safety system spuriously tripped, dropping rods "C" and "D". There were no safety syste a trips annunciated for either " green" or " yellow" leg of the safety system. The TA A was replaced with a spare unit and tested satisfactorily. The reactor was refueled and returned to normal operation. The cause of the spurious scram on the " green" leg , TAA is similar to one that occurred in Sept.1991, where differences in the trip point between the " green" and " yellow" leg TAA (~ 1 volt) could allow a small electrical power transient to trip only one TAA. A valid scram signal in either leg would have scrammed all four rods because of the non-coincidence logic circuits. On the subsequent startup with the reactor subcritical, a rod not in contact with magnet rod run-in occurred when control blade "A" separated from its magnet. The cause was believed to be misalignment between the magnet and control rod anvil (magnet seating surface). The guide tube alignment was checked and the magnet and anvil surfaces were inspected and cleaned. The reactor was returned to normal operation and no further problems of this type have occurred. - On October 7, a spurious reactor loop low pressure scram from pressure transmitter 943 occurred. Reactor loop pressure indications were within the normal pressure band when observed on this and other reactor loop pressure indicators (PT 944A and PT 944B). A compliance check on pressure transmitter 943 indicated that its low pressure scram trip setpoint was one pound (p.s.i.) higher than normal (a conservative direction). The spurious scram occurred as a result of normal meter needle oscillation while operating with system pressure in close proximity to the scram setpoint. The scram trip setpoint was reset to the middle ofits trip band and tested satisfactorily. In addition, the alarm trip lamp was replaced and the scram was again retested. No further problems of this type have occurred. We are evaluating the current setpoint ranges for the required pressure scrams and alarms and pressurizer functions, with regard to their relationship to normal operating i

     - ranges, to provide greater separation from the scram setpoint and the normal operating band. Over the years, we had continued to move our trip setpoints as close i                                                                                                  ,

I-4

q I l as feasible to the operating band so all safety trips will occur as far from the LSSS as possible without causing operational problems due to spurious scrams. Major maintenance items for the month included: replacing the " green" safety - system leg trip actuator amplifier; replacing the alarm trip light on the meter for pressure transmitter 943; and filling beamport "B" and "C" experimental cans with deionized water. November 1993 The reactor operated continuously in November with the following exceptions: six , shutdowns for scheduled maintenance and refueling or sample change-outs. There were no unscheduled shutdowns this month. - Major maintenance items for the month included replacing relay 2K20 (yellow safety leg voltage control to control blades "A" and "B"); and replacing the solenoid for valve 529G which operates valve 509 (pool isolation). Special Maintenance Procedure (SMP-31) was commenced November 22,1993, as scheduled maintenance to replace graphite reflector elements 2 and 3. This maintenance, which requires pulling back Beamports "B" and "C", was terminated when more than normal leakage (relative to five previous beamport pulling procedures) was experienced pulling Beamport "B", the only beamport that had not previously been pulled back. Reactor and Facilities Operations engineering staff decided that the beamport pulling fixture that had been successfully used on all other beamports would need to be redesigned for pulling Beamport"B". [ Editorial note: Additional fixtures and tools were designed and built and SMP-31 was re-initiated February 7,1994. Beamport "B" was pulled back and its seating surfaces to the biological shield were inspected. There was no evidence of significant corrosion at the seating surfaces. The reason for more than normal leakage was attributed to the original mating of the seating , surfaces not being as true as other beamports. The packing ring for Beamport "B" also had only one ring of packing where other beamports had two rings. Graphite elements 2 and 3 were replaced without further problems.] December 1993 The reactor operated continuouslyin December with the following exceptions: four shutdowns for scheduled maintenance and refueling; three unscheduled shutdowns. On December 3 and again on December 4, spurious rod run-ins occurred with no rod run-in annunciation. There were no abnormalindications evident on any , I-5

- . ~ . - - - - - -. - instrumentation or any rod run-in initiating channels. In each case, the rod run-in ; trip actuator amplifier (TAA) tripped, causing the control rods to automatically _ insert. After verifying all operating conditions were normal, the rod run-ins were reset and the reactor was returned to normal operation. On the following maintenance day, December 6, the relays associated with the " rod not in contact with magnet" rod , run-in circuit were replaced, the contacts on all other accessible rod run-in relays - were cleaned. Additionally, the rod run-in TAA was removed, inspected and tested l satisfactorily, and reinstalled. The compliance checks for the effected rod run-in channels were performed satisfactorily and no further spurious rod run-ins have since. occurred. On December 13, a spurious reactor scram occurred while shifting the wide range switch upscale during a normal reactor startup. The cause was suspected to be a sticking relay contact in the feedback network of the picoammeter module for channel #4. The wide range switch was cycled through its full range several times and operated notTnally. A normal startup was completed with no further problems of this type. The design of the WRM switch and circuitry has historically made it a source of spurious shutdowns. Within the last five years, the number of spurious scrams attributed to the WRM switch has been reduced because of the electronic ! technicians' preventive maintenance activities for the WRM switch. Major maintenance items for the month included: loading a new pool deionization bed; replacing a 12 inch PVC spacer in Beamport "F" with 24 inches oflead a collimators; replacing relays K-40, K-42, K-44, and K-46 associated with the " rod not ' in contact with magnet" rod run-in circuit; replacing pressurizer valve 526 (nitrogen addition) due to a stem o-ring air leak; replacing primary pump 501B due to excessive shaft seal leakage; replacing valve 527F (primary domineralizer outlet) position indication micro switches; replacing capacitor C-8 in the primary / pool flow dual trip unit as part of preventative maintenance; replacing air solenoids 529G and 529U for poolisolation valve 509. 1 I-6 t I

4 SECTION II , 1 July 1993 through 31 December 1993 A. CHANGES TO THE STANDARD OPERATING PROCEDURES, 2nd Edition, Effective Date: 5/2/89 (Revisions #1 through #24 to the October 1981 printing were incorporated.) As required by the MURR Technical Specifications, the Reactor Manager

                                                                                                        ~l reviewed and approved the following:                                                     ,

Revision No.10, dated 7/29/93 Revision No.11, dated 8/31/93 B. CHANGES TO THE MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES (dated January 1985, and revised May 13,1988) NOTE: New manual printed May 13,1988 As required by the MURR Technical Specifications, the Reactor Manager reviewed and approved the following:

                  - Revision No.13, dated 7/8/93 Revision No.14, dated 12/28/93                                                    ,

NOTE: SEP-7, page 2: Social Security Numbers have been omitted per request by Nuclear Regulatory Commission, Al Adams,9/87. C. CHANGES TO HEALTH PHYSICS STANDARD OPERATING PROCEDURES ; NOTE: New manualissued 10/29/90 HP-27, Revision No. 4, dated 8/25/93 D. MURR SHIPPING PROCEDURES: SAS-0 (issued 4/13/93), SAS-2 (issued 4/15/93), SAS-3 (issued 4/15/93),- SAS-4 (issued 2/17/93), SAS-5 (issued 5/17/93) The revisions to the Standard Operating Procedures, MURR Site Emergency , Procedures / Facility Emergency Procedures, and Health Physics Standard Operating i Procedures are contained in this section with the part of each page that was revised marked on the right side of the page by a bracket ()). l l 11-1

STANDARD OPERATING PROCEDURES 2nd Edition, Effective Date: 5/2/89 (Revisions #1 through #24 to the October 1981 printing were incorporated.) ' Revision Number 10 Revision Date: 7/29/93 ' Pace Number Daig Pace NumbrI Hate Table of Contents, i - iv 7/29/93 SOPNIII-43 7/29/93 List of Effective Pages, y - viii 7/29/93 SOPNIII-44 7/29/93 SOPNIII-45 7/29/93 SOP /I-1 7/29/93 SOPNIII-46 7/16/91 SOPA-2 7/29/93 SOPM-3 7/29/93 REP-12-1 7/29/93 i SOPM-4 7/29/93 SOPR-15 8/14/89 REP-221 7/29/93 SOPS 16 7/29/93 SOP /I-17 7/29/93 SOP /A-5a 7/30/85 SOPM-18 7/29/93 SOP /A-5b 7/29/93 SOPMII-9 8/27/92 SOP /A-8a 2/28/92 , SOP /III-10 7/29/93 SOP /A-8b 7/29/93 SOPNI-7 7/29/93 SOP /A-18a 7/29/93 SOPNI-8 7/29/93 SOP /A-18b 5/2/89 SOPNII-3 10/18/90 SOP /A-21a 7/29/93 SOPNII-4 7/29/93 SOP /A-21b 7/29/93 SOPNII-5 7/29/93 SOP /A-21e 7/29/93 SOPNII-6 7/29/93 SOP /A-21d 7/29/93 SOPNII-7 7/29/93 SOP /A-21e 7/29/93 - SOPNII-8 7/29/93 SOP /A-21f 7/29/93 i SOPNII-9 7/29/93 SOPNII-10 7/29/93 SOP /A-22a 7/29/93 , SOPNII-11 7/29/93 SOP /A-22b 7/29/93 l SOPNII-12 7/29/93 SOP /A-22c 7/29/93 l SOPNII-13 7/29/93 SOP /A-22d 7/29/93 ! SOPNII-14 7/29/93 SOPNIII-11 5/2/89 ; SOPNIII-12 7/29/93 2 SOPNIII-13 7/29/93 SOPNIII 14 7/29/93 ')i SOPNIII 14a 7/29/93 SOPNIII-15 5/2/89 SOPNIII-16 7/29/93 SOPNIII-17 7/29/93 SOPNIII-17a 7/29/93 SOPNIII-18 5/2/89 1 l II-2 j 1

TABLE OF CONTENTS,2ND EDITION . (Revisions #1 through #24 to the October 1981 printing have been incorporated.) SECTION NO. PAGE NO. I ADMINISTRATIVE OPERATING POLICIES SOP /I-1 I.1 Purpose SOPR1 1.2 Scope SOPS-1 I.3 Reactor Operating Parameters SOP /I 1 l 1.4 Administrative Policies SOPA-2 II REACTOR OPERATING PROCEDURES SOPHI-1 11.1 Routine Reactor Operation SOPHI-1 II.2 Fuel Handling Procedure SOP /II-9 II.3 Control Blade Offset Mechanism Removal SOP /II-12 11.4 Waste Tank Analysis SOPHI-15 III REACTOR CONTROL AND INSTRUMENTATION SYSTEM SOPHII-1 IIL1 Preparation of Reactor Instrumentation for Operation SOPMII-1 . III.2 Pre-Start Up Check of Source Range Nuclear Instrumi.nt Channel 1 SOP /III-2 III.3 Pre-Start Up Check ofIntermediate Range Nuclear Instrument Channels 2 and 3 SOP /III-3 III.4 Pre-Start Up Check of Wide Range Nuclear Instrument Channel 4 SOPMII-4 III.5 Pre-Start Up Check of Power Range Nuclear Instrument Channels 5 and 6 SOP /III-5 III.6 Procedure for Physically Adjusting NI Detectors at Power SOPSII-7 III.7 Procedure for Adjusting Indicated Power on NI Channels 4,5,6 . (While at Power) SOPAII-8 III.8 Check of Process Radiation Monitors SOP /III 9 III.9 Area Radiation Monitoring System SOPHII 10 IV PRIMARY COOLING SYSTEM SOP /IV-1 IV.1 Startup of Reactor Cooling Loop SOP /IV-1 IV.2 Shutdown of Primary System SOPAV-3 IV.3 Operation of the Antisiphon System SOP /IV-5 IV.4 Depressurization of Pressurizer SOP /IV-6 IV 5 Isolation, Draining, Filling and Normal Operation of ] Primary IIcat Exchanger Loops SOP /IV-6 ] IV.6 Isolation, Draining, Filling and Normal Operation of ] ; Primary Loops SOP /IV-6 ] V POOL COOLING SYSTEM SOPN-1 V.1 Pool Cooling System Startup SOPN-1 V.2 Pool System Shutdown Procedure SOPN-3 V.3 Partial Pool Filling Procedures (Pool at Refuel Level or Above) SOPN-3 V.4 Pool Lowering Procedure SOPN-4 i Rev. 7/29/93 App'd

p TABLE OF CONTENTS,2ND EDITION (Revisions #1 through #24 to the October 1981 printing have been incorporated.) I SECTION NO. PAGE NO. i V.5 Pool Cleanup System SOPN-5 1 V.6 Single Pool Pump Operating Procedure SOPN-6 VI SECONDARY COOLING SYSTEM SOP /VI-1 , VI.1 Startup of the Secondary System ~ SOPNI-1 Procedure for Operation of Bypass Control Valves S-1 and S-2 SOPNI-3 I VI.2 VI.3 Cooling Tower Operations SOPNI-5 VI.4 Shutdown of the Secondary System SOPNI-6 VI.5 Draining and Filling the Secondary System Heat Exchanger and Piping SOPNI-7 VI.6 Secondary Water Treatment Procedures SOPNI-7

VI.7 Secondary System Operation on Maintenance / Refueling Days SOPNI-8 ]

VII AUXILIARY SYSTEMS SOPNII-1 VII.1 Reactor Power Calculator SOPNII 1 VII.2 Ventilation Exhaust System (EF-13/EF-14) SOPNII-2 VII.3 Emergency Power System SOPNII-3 ' VIL4 Reactor Demineralizer System SOPNII VII.5 Skimmer System SOPNII-15 VII.6 Primary / Pool Drain Collection System SOPNII-17

VII.7 Primary and Pool Sample Station SOPNII-19 VII.8 Liquid Waste Disposal System SOPNII-20 l VIL9 Nitrogen System SOPNII-30 [

VII.10 Compressed Air Systems SOPNII-30 I VIL11 Sulphuric Acid System SOPNII-34 VIII REACTOR EXPERIMENTS SOPNIII-1 . VIII.1 General Requirements SOPNIII-1 VIII.2 In-Pool Irradiations SOPNIII-5 VIII.3 Pneumatic Tube (P-tube) System Irradiations SOPNIII-8 VIIL4 Beamport Experiments SOPNIII-19 VIIL5 Handling and Release ofIrradiated Samples SOPNIII-38 VIIL6 Response Procedures for the Nuclepore Irradiation Facility SOPNIII-38 VIIL7 Thermal Column Door Operations SOPNIII 40 VIIL8 Response Procedures for the Alpha Laboratory SOPNIII-43 i p 4 ii i t Rev. 7/29/93 App'd - i

TABLE OF CONTENTS,2ND EDITION (Revisions #1 through #24 to'the October 1981 printing have been incorporated.) , SECTION NO. PAGE NO. , REACTOR EMERGENCY PROCEDURES: Table of Contents REP-0-1 REP-0 Introduction REP-0-2 REP-1 Failure to Scram or Rod Run-In REP-1-1 REP-2 Reactor Scram REP-2-1 REP-3 Reactor Scram from Loss of Primary System Pressure or Flow REP-3-1 REP-4 High Radiation Levels REP-4-1 , REP-5 Nuclear Instrument Failure REP-5-1 REP-6 Area Radiation Monitoring System (ARMS) Failure to Actuate Reactor Isolation REP-6-1 REP-7 Loss of Communications Between Reactor Control Room and Experimenters REP-7-1 REP-8 Control Rod Drive Failure / Stuck Rod REP-81 REP-9 Electrical Anomalies REP-9-1;2;3;4 REP-10 Failure of Experimental Apparatus REP-10-1 REP-11 Low Fire Main Pressure REP-11-1 REP-12 Loss of Domestic Cold Water to Facility REP-12-1 ] i REP-13 Complete of Partial Loss of Secondary Flow REP-13-1;2 REP-14 Loss of Pool Flow During Reactor Operation REP-14-1 REP-15 Loss of Pool Water During Reactor Operation REP 15-1;2;3;4 REP-16 Reactor Loop Isolation Valves (507A & 507B) Fail to Close Automatically REP-16-1 REP-17 Pressurizer Valves Fail to Operate REP-17-1 REP-18 Both Antisiphon Valves (543A s 543B) Fail to Open Automatically REP-18-1 REP-19 Emergency Core Cooling Valves (546 A/B) Fail to Open Automatically REP 19-1;2 REP-20 High Activity Levels in the l'rimary Cooling System REP-20-1;2;3 REP-21 High Stack Monitor Indicathns REP-21-1;2 REP-22 Bomb or Other Overt Threats REP-22-1 l iii Rev. 7/29/93 App *d M l j a

TABLE OF CONTENTS,2ND EDITION l (Revisions #1 through #24 to the October 1981 printing have been incorporated.) i SECTION NO. PAGE NO. APPENDIX A: SOP /A-1 Reactor Startup Checksheet-Full Power Operation SOP /A-la;b;c;d SOP /A-2 Deviation from Standard Operating Procedure SOP /A-2a;b SOP /A-3 Reactor Short-Form Pre-Critical Checksheet SOP /A-3a;b .; SOP /A 4 Reactor Shutdown Checksheet SOP /A-4a;b l SOP /A-5 Nuclear Data / Process Data SOP /A-5a;b;c;d SOP /A-6 Startup Nuclear Data SOP /A-6a;b , SOP /A-7 Pneumatic Tube Irradiations SOP /A-7a;b SOP /A-8 Reactor Routine Patrol SOP /A-8a;b;c;d l' SOP /A-9 Unscheduled Reductions in Power Report No. SOP /A-9a;b SOP /A-10 Radiation Work Permit SOP /A-10a;b , SOP /A-11 Waste Tank Sample Report SOP /A-11a;b SOP /A-12 Primary System Normal Operating Valve Lineup Checksheet SOP /A-12a;b;c;d , SOP /A-13 Secondary Water Activity Analysis SOP /A-13a;b SOP /A-14 Pool System Valve Lineup Checksheet SOP /A-14a;b;c;d , SOP /A-15 MURR Pool Water Analysis SOP /A-15a;b ! SOP /A-16 D. I. 200 Series Resin Log For Bed SOP /A-16a;b I SOP /A-17 TAG - DO NOT OPERATE SOP /A-17a;b ! SOP /A-18 D. I. Water Makeup Log (Fill in only if sending D. I. water.) SOP /A 18a;b SOP /A-19 MURR Operator Active Status log SOP /A-19a;b SOP /A-20 MURR Tag Out Sheet SOP /A-20a;b;c;d MURR Tag Out Index Record SOP /A-21 Secondary System Normal Operation Valve Line-Up SOP /A-21a;b;c; ] ; Checksheet d;e;f ] ; SOP /A-22 DI System Valve Line Up Checksheet SOP /A 22a;b;c;d] ;

                                                                                                       't APPENDIX B:                                                                                          1 SOP /B-1       Toxic Materials With Restricted Use in the Containment Building                                                      SOP /B-la;b          (

iv , t Rev. 7/29/93 App'd

LIST OPEFFEdTIVE PAGES,2ND EDITION (Revisions #1 through #24 to the October 1981 printing have been incorporated.) Egce Number Date Revised Pace Number Date Revised Title Page 5/2/89 SOPAI 8 8/14/89 Assignment Sheet 5/2/89 SOPAI 9 10/18 S 0 Revision No. & Date Page 5/2/89 SOP /II 10 5/2/89 Table of Contents: SOP /II-11 5/2/89 i 7/29 S 3 ] SOPAl-12 5/2/89 ii 7/29S 3 ] SOPAI 13 8/14/89 iii 7/29S 3 ) ' SOP /II-14 1/16SO iv ' 7/29S3 ] SOPal-15 1/16S 0 List of Effective Pages: SOPAI.16 10/18SO v 7/29S 3 ] SOPAII-l 10/18SO vi 7/29S3 ] SOPAll-2 8/27S 2 vii 7/29S 3 ] SOPAll-3 8/27S2 viii 7/29S3 ] SOPAII-4 8/27S2 SOPA-1 7/2983 ] SOPS 11-5 8/27 S 2 SOPA-2 7/29S3 1 SOPAll-6 8/27B2 SOP /I-3 7/29S3 ] SOPSil-7 5/2/89 SOP /1-4 7/29 S 3 ] SOPAll-8 New 8/27S 2 SOPA-5 5/2/89 SOPall-9 Renumbered 8/27/12 SOPA-6 5/2/89 SOP /lll-10 7/29N3 ] SOPA-7 5/2/89 SOPSII-l1 Reset 8/27 S 2 . SOPA-8 5/2/89 SOP /Ill-12 Reset 8/27B2 SOP /I-9 8/14/89 SOP /IV-1 10/0/81 SOPA-10 5/2/89 SOP /IV-2 5/2/89 SOPA-ll 10/18S 0 SOPSV-3 10/0/81 SOPA-12 . 8/14/89 - SOPAV-4 5/2/89 SOPA 8/14/89 SOP /IV-5 _10/0/81 SOPA-14 8/14/89 SOPAV-6 5/2/89 SOP /I-15 8/14/89 SOP /V 1. 5/2/89 SOPA-16 7/29S3 ] SOP /V-2 5/2/89 SOPA-17 7/2993 ] SOP /V-3 8/14/89 SOPA-18 7/29S3 ] SOP /V-4 1/16SO SOP /1-19 10/18S 0 SOP /V-5 5/2/89 ' SOPM-20 10/18SO SOP /V-6 1/16S 0 SOP /I-21 10/18 S 0 SOP /V-7 1/16S 0 SOPA-22 10/18S 0 SOP /V-8 1/16SO SOPA-23 10/18/90 SOP /VI-l 4/30S 1 SOPA-24 10/18SO SOP /VI 2 1/16SO SOP 41-1 5/2/89 SOP /VI-3 5/2/89 SOPSI-2 5/2/89 SOP /VI-4 5/2/89 SOPAI-3 5/2/89 SOP /VI-5 5/2/89 SOPAI-4 5/2/89 SOP /VI-6 4/3031 SOPAI-5 10/0/81 SOP /VI-7 7/29 S 3 ] SOPAI-6 5/2/89 SOP /VI 8 7/29S 3 } SOPMI-7 12/16/89 Y Rev. 7/29/93 App'd #

LIST OF EFFECTIVE PAGEI,2ND-EDITION . .

                                                                                            .                l (Revisions #1 through #24 to the October 1981 printing have been incorporated.).               i Pace Number                      Date Revised       Pace Number                     Date Revised SOP /VII                           10/0/81      SOP /VIII-7                         10/18SO SOP /VII-2                            4/30S 1       SOP / Vill-8                           5/2/89 SOP /VII 3                           10/18S 0       SOP / Vill-9                           5/2/89        D 1

SOP /VII 4 7/29S 3 ] SOP / Vill-10 5/2/89-SOP /VII 5 7/29S3 1 SOP / Vill-11 5/2/89 SOP /VII-6 7/29S3 ] SOP /VIII-12 7/2993 ) fj ' SOP /VII 7 7/29S3 1 SOP / Vill-13 7/29 S 3 -]. SOP /VII-8 7/29S3 ] SOP /VIII-14 7/29 S 3 )- SOP /VII-9 7/29S3 ] SOP /VIII-14a 7/2993 )L ; SOP /VII-10 7/2963 1 SOP / Vill-15 5/2/89 SOP /VII Il 7/29 S 3 ] SOP / Vill-16 7/2993 ] i SOP /VII-12 7/29S3 ] SOP /VIII-17 7/2993 ] SOP /VII-13 7/29 S 3 1 SOP /VIII-17a New 7/2993 ] SOP /VII-14 7/29S3 1 SOP /VIII 18 5/2/89 : SOP /VII-15 5/2/89 SOP / Vill-19 10/18SO SOP /VII-16 5/2/89 SOP /VIII-20 5/2/89 SOP /VII-I7 5/2/89 SOP /VIII-21 5/2/89' f SOP /VII-l8 5/2/89 SOP / Vill-22 5/2/89-SOP /VII-19 5/2/89 SOP /VIII-23 5/2/89 i SOP /VII 20 4/30S1 SOP /VI!!-24 . 5/2/89 SOP /VII 21 5/2/89 SOP /VIII-25 5/2/89 SOP /VII-22 10/18S 0 SOP / Vill 26 -5/2/89 SOP /VII-23 5/2/89 SOP /VIII 27 5/2/89 SOP /Vil 24 5/2/89 SOP /VIII-28 5/2/89 SOP /VII 25 1/2B2 SOP /VIII-29 5/2/89 ; SOP /VII-26 1/2S2 SOP /VIII-30 5/2/89 ~j SOP /VII-27 5/2/89 SOP /VIII-31 5/2/89 , SOP /VII-28 5/2/89 SOP / Vill-32 ~ 5/2/89 - SOP /VII 29 1/16/90 SOP /VIII-33 8/14/89 i SOP /VII-30 2/28S2 SOP /VIII-34 5/2/89 ; ' SOP /VII 31 2/28S2 SOP /VIII-35 8/14/89 , SOP /V11-32 2/28S2 SOP / vill-36 5/2/89 SOP /VII 33 2/28S 2 SOP / Vill-37 8/14/89 , SOP /VII-34 New 8/27S 2 SOP /VIII-38 8/27 S 2 ' ] SOP /VII 35 New 8/27B2 SOP /VIII-39 2/28 S 2 , SOP /VII-36 New 8/27S 2 SOP /VIII-40 2/28S2 SOP /VIII-l 10/0/81 SOP /VIII-41 5/2/89 SOP /VIII-2 10/18SO SOP /VIII-42 5/2/89

' SOP /VIII-3                            5/2/89      SOP / Vill-43                        7/2993      ]

SOP /VIII-4 5/2/89 SOP /VIII-44 7/2993- ) SOP /VI!!-5 5/2/89 SOP / Vill-45 7/2993 ].' SOP /VIII-6 5/2/89 SOP / Vill-46 7/16S1 - vi , Rev. 7/29/93 App'd M 1

p LIST OF EFFECTIVE PAGES,2ND EDITION REP-0-1 (Table of Contents) 7/16S 1 REP 1 6/27N1 REP-9-1 6/2761 REP-9-2 6/27SI REP-9-3 6/27BI REP-9-4 6/27S1 REP-13-1 6/2781 REP-15-1 6/27SI REP-15-2 6/27Si REP-17-1 6/27S1 REP-19-1 6/2781 REP-20-1 6/27B1 REP-21 2 2/28S 2 REP-22-1 7/2993 SOP /A-14d 5/2/89 =: SOP /A-15a 5/2/89 SOP /A-15b SOP /A-16a 5/2/89 i vii Rev. 7/29/93 App'd M i -l (Revisions' #1 through #24 to the October 1981 printing have been incorporated.) j Pace Number Date Revised Pace Number Date Revised REACTOR EMERGENCY PROCEDURES: APPENDIX A: SOP /A-la 2/28S2 l REP-0-2 6/27S1 SOP /A-lb 4/30S 1 REP-1 1 6/27S1 SOP /A-lc 2/28S2 REP-2-1 6/27B1 SOP /A-1d 2/18S1 REP-3-1 6/27 S 1 SOP /A-2a 5/2/89 REP 4-1 6/27/91 SOP /A 2b 5/2/89 l REP-5-1 6/27S1 SOP /A-3a 2/28B2 REP-6-1 6/27S 1 SOP /A-3b 6/0/80 REP 1 6/27Si SOP /A-4a 5/2/89 ., SOP /A-4b 5/2/89 ! SOP /A-5a 7/30/85 ) SOP /A-5b 7/29S3 } SOP /A-5c 6/0/80 . SOP /A-5d 6/0/80 REP-10-1 6/27SI SOP /A-6a 3 S/83 j REP-1 l-1 6/27S1 SOP /A-6b 5/2/89 REP-12-1 7/29S3 1 SOP /A 7a 9/19/83 - SOP /A-7b 6/0/80 REP-13-2 6/27 S 1 SOP /A-8a 2/28S2 REP-14-1 6/27B1 SOP /A-8b 7/29 S 3 ) SOP /A-8c 2/28S2 ; SOP /A-8d 8/14/89 j REP-15-3 6/27S 1 SOP /A-9a 5/2/89 l REP-15-4 6/27St SOP /A-9b 6/0/80 REP-16-1 6/27S1 SOP /A-10a 10/8/86 i SOP /A-10b 10/8/86 REP-18-1 6/27SI SOP /A-lla 1/2B2 , SOP /A-llb 12/15/82 l REP-19-2 6/27S 1 SOP /A-12a 5/2/89 . SOP /A-12b 5/2/89 REP-20-2 6/27S1 SOP /A-12e 8/14/89 REP-20-3 6/27/91 SOP /A-12d 5/2/89 REP-21-1 2/28 S 2 SOP /A-13a 5/2/89 ; SOP /A-13b 5/2/89 REP-21-3 2/28S2 SOP /A-14a 1/16SO t ] SOP /A-14b 1/16S 0 SOP /A-14c 5/2/89 ; 5/2/89 . i SOP /A-16b 5/2/89 ; '! '

LIST OF EFFECTIVE PAGE'S,2ND EDITION ; l! (Revisions #1 through #24 to the October - 1981 printing have been incorporated.) 1 Pace Number Date Revised Pace Number Date Revised SOP /A-17a 5/2/89 SOP /A-17b 5/2/E9 SOP /A 18a 7/29 S 3 ] SOP /A-18b 5/2/89 , SOP /A-19a 5/2/89 SOP /A-19b 5/2/89 SOP /A-20a 10/1890 SOP /A-20b 10/18SO , SOP /A-20c 10/1860 SOP /A-20d 10/18SO SOP /A-21a New 7/29S3 ) SOP /A-21b New 7/29N3 1 SOP /A-21c New 7/2993 ] SOP /A-21d New 7/29S3 ] SOP /A-21e New 7/2983 )

       - SOP /A-21f     New                   7/29S3    ]                                                l SOP /A-22a     New                   7/29S 3   ]                                                l SOP /A-22b     New                   7/29S3. 1 SOP /A-22c     New                   7/29S 3   ]                                                 ;

SOP /A-22d New 7/2993 ) APPENDIX B: SOP /B-la 5/2/89 , SOP /B-lb 5/2/89 i 1 l viii Rev. 7/29/93 App'd b

SECTION I ADMINISTRATIVE OPERATING PO'LICIES j I I.1 Purpose To establish methods of operation for the reactor and associated systems i which ensure safety and performance within the technical specifications ] ! set forth for the University of Missouri Research Reactor. ; I.2 Scope . l These procedures are not to be construed to constitute a part of the technical ; specifications. In event of any discrepancy between the information given herein and the technical specifications, limits set forth in the technical i specifications apply. Changes to these procedures, and to any other special , operating or maintenance procedures which have safety significance, must be , reviewed by tl e Reactor Procedures Review Subcommittee (RPRS). Changes , which are editorial or have no safety significance may be made by the Reactor Manager, Reactor Operations Engineer or the Shift Supervisor, but must be : documented ar4d subsequently reviewed by the RPRS. The documentation will ; be done by filling out a SOP Deviation Form (see Appendix A) to petition a SOP , change or to explain the deviation. I.3 Reactor Operating Parameters The reactor will be operated under conditions and limitations as set forth in the technical specifications, Appendix A to License R-103. -l 1.4 Administrative Policies I.4.1 Standing Orders New procedures prior to becoming part of these Standard Operatmg e Procedures, procedures to be in effect for a short period, and special ; instructions relating to operation of the reactor, will be issued as Standing Orders. All effective Standing Orders, as well as a listing of current orders, will i be maintained in a log in the reactor control room. Standing Orders that are no longer applicable or that are incorporated into the Standard Operating ; Procedures will be canceled and removed from the log. All Standing Orders will ; be approved by signature of the Reactor Manager or his authorized delegate. , i l Rev. 7/29/93 App'd th0Th SOP /I-1 ! i I

l I.4.2 General Operating Policies 1 A. Safety l Safe operation of the reactor will take precedence over other considerations. B. Supervisory Authority The importance of one coordinator for all reactor activities is recognized for safety and effective control of operation. The Reactor Manager will have complete operating authority over all activities related to reactor operation. The Shift Supervisor is the Reactor Manager's delegated representative on shift and is given the authority to direct the activities (both licensed and unlicensed) related to reactor operation during his duty shift. Whenever the Shift Supervisor is absent, a Senior Operator shall assume the lead Senior Operator position. The lead Senior Operator is delegated the Shift Supervisor's authority and responsibility for shift activities during the Shift Supervisor's absence. If the Shift Supervisor is out ] , of the control room for an extended period of. time, the lead ] Senior Operator may be authorized to make routine control room ] ' decisions. However, the Shift Supervisor should be consulted ~ '] for non routine situations and kept informed. The delegation to ] the lead Senior Operator will be left to each Shift Supervisor. ] Any SOP reference to Shift Supervisor applies to the lead Senior Operator when the Shift Supervisor is absent from his duty shift. C. Operating Crews y 1. The minimum number of reactor operators for reactor operation will l be two licensed persons. One of these will be licensed as a Senior Reactor Operator. One exception is allowed for family emergencies. In this case, one Senior Reactor Operator may operate the reactor with another knowledgeable person present in the facility, which exceeds Technical Specification 6.1.i requirements. This mode of operation shall be documented in the console log and minimized by calling in an additionallicensed operator. The Reactor Manager or Operations Engineer should be informed as soon as possible. l l Rev. 7/29/93 App'd M SOP /I-2

4 I.4.2 General Operating Policies (cont'd) ]

2. There will be one licensed operator in the control room at all times whenever the reactor is not considered secured, as defined in Part 1.20 of the Technical Specifications. When the reactoris shutdown but not secured, the control room boundary can be expanded to include the bridge area during refueling or maintenance activities.

D. Console Log A log will be maintained in the control room by the reactor operator providing a detailed diary of reactor operation. E. Corrections to Console Log, Nuclear and Process Data and Routine Patrol Sheets , Any corrections to a log entry or data sheet will be done by a single line through the incorrect entry, plus the initials of the person making the change. If the correction is made at a later date, the person making the , correction will initial and date the change. t F. Changing Reactor Reactivity Operations affecting changes in core reactivity, other than normal steady state power control, i.e., refueling, startup, etc., will be directly supervised by a Senior Operator. G. Malfunction of Reactor Systems While ac Power Any malfunction or abnormal operation of a control or reactor system-shall be immediately brought to the attention of the Shift Supervisor. The decision as to whether to continue operation of the reactor depends upon the severity of the malfunction. It remains with the Shift Supervisor as to what immediate action needs be taken. However, the duty operatoris authorized, in the absence of the Shift Supervisor from the control room, to place the reactor in a safe shutdown mode if he deems it necessary. It is important that the reactor systems, while the reactor is critical, not be experimented with, or reactor control systems tested, unless permission to do so is explicitly granted by either the Reactor Manager or his designated representative. 1 l 1 Rev. 7/29/93 App'd klW\ SOP /I 3 I

o L4.2 General Operating Policies (cont'd) - -] H. Maintenance Performed on Reactor Systems All maintenance on reactor and license related systems and equipment will be reviewed by the Shift Supervisor to ensure operability of these systems prior to reactor operation. I. Maintaining Active Operator Status

1. Actively performing the functions of an Operator or Senior Operator ]

means that an individual has a position on the sinft crew that requires the individual to be licensed as defined in 10 CFR 55, and that the individual carries out and is responsible for the duties covered by that position.

2. If an Operator has not performed licensed duties a minimum of four ]

hours on shift per calendar quarter, before resumption oflicensed activities, the Reactor Manager shall certify that the qualifications and status of the Orcrator are current and valid, and that the Operator has completed a nunimum of six (6) hours of shift functions under the direction of a Senior Operator before returning to active status. . J. Reactor Operating Parameters The reactor shall be operated in strict accordance with the Reactor License R-103 and the operating limits in Tables III and IV. I.4.3 Startup A. Startup Following a Scram The reactor will not be started up following a scram until the cause of the scram has been determined and safe corrective action taken. If, after thorough investigation, the cause of the unscheduled reduction is power cannot be determined and all systems are found to be normal, the reactor may be started up with the approval of the Reactor Manager or his authorized delegate. Rev. 7/29/93 App'd U)M\ SOP /I-4 1 l

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

1 i j . i A. The top portion of the RWP will be prepared by the Job l Supervisor and Health Physics. The time and date spaces should contain the supervisor's estimate of the duration of.the job (0800-2400 September 2, 1988; 0000-2400 . , September 10-12, 1988, etc.). _ The Job Supervisor should be as specific as possible in describing the job. This _ will aid Health Physics in determining the protective ~ measures necessary. . B. Health Physics will assign a number to the RWP and conduct-the necessary surveys and determine the protective measures necessary for the job. Health Physics will complete the remainder of the RWP. indicating the survey results and the protective measures required. Health Physics will then sign and date the RWP, and obtain approval signature from the Job Supervisor and information signature from the Shift i Supervisor, if appropriate. ! C. The Job Supervisor will provide Health Physics with the names of personnel expected to work under the RWP prior to the start of the job. Each person performing work under the RWP ., shall be informed of the required radiation controls and shall acknowledge being informed by signing on' their l designated signature line. Health Physics will have avail-able the approved RWP at the job site for ready reference by the personnel doing the work. D. When the job has been completed and the job site has been , cleaned up and decontaminated, the Job Supervi.sor will deliver the RWP to Health Physics. Health Physics will verify that l the job site is clean and decontaminated, and will record ; estimated dose for each person involved. Health Physics will. )' terminate the RWP and maintain it in an RWP file.. 'Any person who signed. approval or any supervisor can terminate the RWP l 1 by signing the termination block. Health Physics must be a notified if the RWP is terminated by someone .other than a

member of the Health Physics Group.

b 4 Rev. 8/14/89_ App'd VJM S0P/I-15 ] ,

Reset -l

                                         ..                                                                   1

o 1.4.9 ' Radiation Safety The Shift Supervisoris directly responsible for the overall safety of personnel on his shift and indirectly responsible for all personnel whose safety may be affected by activities conducted under his supervision. Radiation safety is a very important part of this responsibility. It should not be construed that surveys, monitoring, or other measurements to check for contamination or radiation are to be made by operations personnel, but rather that the Shift Supervisor is responsible to ensure that through coordination with the Health Physics personnel, adequate protection is provided for evolutions conducted during his shift. I.4.10 Physical Protection of Special Nuclear Materials In accordance with 10 CFR 73, special requirements must be met in safeguarding Special Nttelear Material. The safeguards provided and the procedures applicable to maintaining the security of Special Nuclear Materials are contained in the facility Security Plan and Security Procedures. , I.4.11 Equipment Tag Out Procedure ] I.4.11.1 Purpose The purpose of the tag out system is to prevent injury to personnel and/ ] or damage to equipment. Campus Facilities also has its own tag .] system. When they work on equipment at MURR, with the Shift ] i Supervisor's permission, their tag system serves this same ] ! purpose and shall be honored. All Campus Facilities Tags are to ] be accompanied by MURR tags, ] I.4.11.2 Types of Tags A. Red Tags Red tags will be used to identify equipment which,ifoperated, could present a hazard to personnel. The tag will also contain information pertaining to the reason for the tag. t B. Yellow Tags Yellow tags will be used to identify equipment which, if operated, could present a hazard to that or other equipment. The tag will also contain information pertaining to the reason for the tag. l Rev. 7/29/93 App'd ly9tO SOP /I-16

-1

l I I.4.11.3 Equipment Tag Out A. Tag Out Log

1. The tag out log will be maintained in the control room by the on-duty Shift Supervisor.

2. The tag out log will be made up of six sections:

a. Monthly Audit

b. Tag Out Instructions

c. Index Record

d. Active Tag Out Sheet Section

e. Inactive Tag Out Sheet Section -

f. Blank Sheet Section B. Performing a Tag Out

1. A tag out will be performed by facility personnel with the approval of the on-duty Shift Supervisor.

2. The on-duty Shift Supervisor must approve the hanging or removal of ALL tags.

3. In the event that a tag is discovered missing, the Shift Supervisor will be informed immediately. The Shift Supervisor will determine corrective action.

C. Tag Out Audit A tag out audit will be performed monthly as scheduled by a predetermined DUE DATE. The person performing the Audit will:

1. Inventory all active tags.

2. Note any incorrect or missir1g tags.

3. Sign and date the monthly Audit sheet.

4. Discard the old inactive tag out sheets.

Rev. 7/29/93 App'd M SOP /I-17

l l MURR TAG OUT INSTRUCTIONS Tag Out:

1. Obtain the Shift Supervisor's permission to hang tag (s).

2. Complete the MURR Tag Out Index Record. For tag out use next sequential ,

number (self-explanatory).

3. Complete both sides of the MURR Tag Out Sheet (self-explanatory).

Tag Removal:

1. Obtain the Shift Supervisor's permission to remove tag (s).

2. Complete the MURR Tag Out Sheet (move to the inactive section if all tags are cleared).

3. If all tags are cleared, complete the MURR Tag Out Index Record.

Temporary Tag Removal: (for example, to test equipment) ]

1. Obtain the Shift Supervisor's verbal permission to temporarily ]

remove tag. ]

2. The Shift Supervisor will authorize a MURR staff member to ]

Nmporarily remove the tag. ]

3. ' ;'ter testing, the staff member will report results of test to Shift

Supervisor who will decide if tag should be cleared or re-hung. ] 1

                                                                                    -t 1

Rev. 7/29/93 App'd M_ SOP /I-18 l i

L 2,-- III.8 Check of Process Radiation Monitors ] 111. 8 . 1 Operational Check of Secondary Coolant and Fission Product 1 Monitors respectively. A Lower alarm setpoint until annunciator alarms. H Place level set switch up and adjust alarm setting to 10k cpm + 10%. , C Lower alarm setpoint until annunci'ator alarms. D. Place level set switch up to and adjust alarm setting to 12k cpm + 10%. 111. 8 . 2 Operational Check of Stack Monitor ] A The. operator conducting the test in the West Tower shall establish communication with the control room via the intercom a Place the mode switch for the iodine detector in the 'T' (test) position. C Verify that the recorder pen indicates 3600 cpm + 10%, and that the stack monitor high activity annunciation is received. Also verify that the local meter reads within 10% of the test ! reading marked on the meter face. , D. Return the iodine mode switch to the "N" position. E. Press the " reset" button until the iodine meter and recorder readings return to normal, do not drive them to the downscale position. Reset the annunciator. F. Place the mode switch for the particulate / gas monitor in the "T" position. G. Verify that the particulate recorder and gas recorder pens indicate 3600 cpm + 10% and that the stack monitor high - activity annunciation is received. Also verify that the local - meter reads 3600 cpm + 10%. H. Return the particulate mode switch to "OP" position. I. Press the " reset" button until the particulate meter and recorder readings return to normal; do not drive it to the , downscale position. Reset the annunciator. : J. Test the low flow alarm in the control room by securing the l blower. > K. Return the blower switch to "on". verify "high" and " low" alarms cleared. t Rev. App'd M SOP /III-9 ] Sections renumbered only

l III.9 Area Radiation Monitoring System j The area radiation monitoring system will be in operation continuously and is to be I turned ofronly during maintenance on the system. When handling samples, or l during maintenance, place the Bridge Upscale Switch in the upscale position. Ensure Bridge Upscale Switch is returned to normal position afler handling samples. The station trip points shall be set as follows: Station 1 BP North Wall 2 X acceptable background Station 2 BP West Wall 2 X acceptable background Station 3 BP South Wall 2 X acceptable background Station 4 Exhaust Plenum 1 mr/hr or E X normal operating background Station 6 Bridge ALARA 300 mrdir alert 10K mr/hr alarm / trip Station 7 Bridge 50 mr/hr or 10 X normal operating background Station 8 Nuclepore 2 X normal operating background Station 9 Fuel Vault 2 X normal operating background Station 10 Room 114 2 X nonnal operating background Station 11 Exhaust Plenum #2 1 mr/hr or 10 X normal operating background At least once a month for stations 4,6,7 and 11, and once a quarter for the remaining stations, the system will be checked according to the following procedure: NOTE: GREEN Lamp serves as Normallight and Check Source actuating switch (push to actuate source). AMBER Lamp serves as Alert alarm (push to reset). ; RED Lamp serves as High alarm (push to reset). The alert has been set up on all ARMS units except for the Bridge ALARA. ] A. At station 1, operate the check source pushbutton and verify that when trip point is reached, the RED alarm lamp lights at the Electronic Channel, and the RED alarm lamp lights and the AUDIBLE alarm sounds at the Remote Alarm Unit. B. Repeat step A for Stations 2,3,8,9 and 10.

Rev. 7/29/93 App'd M SOP /III-10

*4

l VI.4 Shutdown of the Secondary System (cont'd) ] i B. Verify that system flow recorder indicates no flow and that the chiller pump, P-4, has automatically started to provide coolant flow to the chiller unit. C. Turn off cooling tower fans. ' VI.5 Draining and Filling the Secondary System Heat Exchanger and Piping This section has been moved to SMP-21. VI.6 Secondary Water Treatment Procedures VI.G.1 Secondary Water System Responsibility The responsibility of the secondary water treatment is within the operations group of the reactor, with two individuals given prime responsibility to learn , and be closely associated with the total operation. The secondary water , treatment system is designed to minimize corrosion, deposition, micro-biological growth, and other major chemical problems which are present in the secondary cooling water system. VI.6.2 Secondary Water Conductivity Control To control conductivity (total dissolved solids), water is sampled and monitored by the conductivity unit. If the conductivity is greater than the . system setpoint, an automatic blowdown is initiated. The freshwater ] makeup, which replaces the water lost through the blowdown, lowers the ] conductivity. VI.G.3 Secondary Water pH Control To control pH, water is sampled and monitored by the pH unit located in the tunnel entrance of room 114. If the pH increases above the system setpoint, the acid injection valves automatically open and acid is gravity fed into the . tower sump. The acid used is concentrated sulfuric acid supplied from the 250-gallon day tank in the cooling tower. VI.G.4 Sample Paths for pH and Conductivity J A. During normal operation of the secondary system, the automatic pH and conductivity control units receive their sample water through valves S104 and S151. ~ Rev. 7/29/93 App'd bMrM SOP /VI-7 l

.)

[ l l VI.G.4 Sample Paths for pH and Conductivity (cont'd) ] B. During operation of the secondary system with the air conditioning units secured and isolated, close S104 and open S103. This provides a representative sample for these units to control pH and conductivity. C. The pH and conductivity units shut down when secondary pumps (P-1, P-2, and P-3) are secured. VI.6.5 Secondary Water Corrosion Prevention A. The prevention of corrosion in the secondary system is accomplished by automatic addition of a corrosion inhibiter. B. These chemicals are fed automatically by a metering pump system

based on makeup flow.

VI.6.6 Secondary Silt, Algae and Mud Control Silt and mud buildup is controlled by the feeding of a chemical silt dispersant to the cooling tower basin. The dispersant is added to ensure solids remain suspended a sufficient amount of time to allow the secondary blowdown to remove them from the system. This reduces secondary conductivity and minimizes the buildup of silt in low flow areas, a fouling condition. . Microbiological and algae growth is controlled by the addition of two microbiocides/algaecides. The addition frequency is determined by weather conditions and reactor operations. VI.7 Secondary System Operation on Maintenance / Refueling Days Start either P-1, P-2, or P-3 and run as necessary to maintain primary and ] pool system temperatures. NOTE: Fans may need to be run also to maintain proper cold deck temperatures. P Rev. 7/29/93 App'd M SOP /VI .

  . VII .3    Emergency Power System                                                     l VII.3.1    Testing of the Emergency Power System At least once a week the emergency generator will be started automatically and permitted to run for at least 30 minutes.

This event will be noted in the console log. A green light ] mounted on a side panelin the control room will energize whenever the emergency generator.is running. In addition to this, the emergency generator will be operated for a period of about 30' minutes prior to each startup after a shutdown , exceeding 24 hours. On a quarterly basis, commercial power ] to the auto transfer switch is internipted at unit substation } l B in order to allow the emergency generator to start and } immediately assume its electrical loads (CP-17). } A modified load test (CP17) shall precede and a full load test (CP-17) shall follow any work on the emergency generator except for routine maintenance that has been proven to not cause a problem. VII.3.2 Manual Start Procedures 1 Afanual starting of the diesel generator under no load l' I conditions is accomplished as follows: Perform normal ) prestart checks (oil, fuel, coolant level, etc.). . Lift and 1 hold the hiANUAL START switch at the START position, ) .; and press and hold the CRANK switch. The starter will

1 ' begin cranking and after afew seconds the engine should ) start. When the engine starts, release both switches. If the 1 l engine does not start after 20 to 60 seconds of cranking, 1 release both switches, waitfor two minutes for the starter 1 -i motor to cool and then repeat the starting procedure. If ) the engine does not nin after a second attempt at starting, 1 refer to the troubleshooting section of the technical manual. ) , After starting, check the normal operating indications as: ) j RPhi ~ 1800, oil pressure - 38 lbs., oil temperature - 150*, } , and water temperature ~ 180*. The alarm panel will l indicate early warning and shutdown alarms. ) l Rev.10/18/90 App'd th SOP /VII-3

VII.3.3 To Stop Engine To Stop engine, place the MANUAL START switch to the OFF position-- where it should remain for normal operation. VII.3.4 Deleted VII.4 Reactor Demineralizer System VII.4.1 Normal Operation Normally there are four mixed resin beds in the system at one time with two beds on-line, one in standby or depleted and one in the storage tank for ] pre-shipment decay. The normal flow path is via a 50 gpm pump, system inlet filters, down through the DI bed, and through system outlet filters. The outlet valve of the system inlet filter is used as a throttling device with the , bypass valve always remaining closed. Although regeneration of a bed is possible, single life pre-generated beds are normally used in this system. If regeneration of DI beds is necessary, the procedures to perform this task are - incorporated into SMP-16. l VII A.1.1 Placing Standby Cleanup Bed on Reactor Service CAUTION must be exercised to prevent a reactor loop low pressure scram from occurring during this procedure! A. Check the DI Resin Log for the status of the affected bed (s). B. Ensure all valves on standby DI colunm are closed. ] C. Open valve DI-2 slightly on standby column to allow pressure to equalize, then open fully D. Open standby column DI-5 to place in parallel with on-line column. E. Remove the depleted bed from service by shutting DI-2 and DI-5 on ; depleted column. - F. Transfer the depleted bed H3 water to the DCT. (see VII.4.2.7) G. Record the transaction in both the DI Resin Log and Console Log. t h t Rev. 7/29/93 App'd VWW\ ' SOP /VII-4 v r- -,%

VII.4.1.2 Placing Standby Cleanup Bed on Pool Service A. Check the DI Resin Log for the status of the affected bed (s). B. Ensure all valves on standby DI column are closed. ] C. Open valve DI-1 slightly on standby column to allow pressure ] to equalize, then fully open. ] D. Open standby column DI-4 to place in parallel with on-line column. ] E. Remove the depleted bed from service by shutting DI-1 and DI-4 on ] depleted column. F. Transfer the depleted column H3 water to DCT. (see VII.4.2.7) ] G. Record the transaction in both the DI Resin Log and Console Log. ] VII.4.2 Resin Transfers Demineralized water will be used for all resin manipulations. The T-300 flow booster pump should be used anytime gravity feed does not supply adequate flow. VII.4.2.1 Resin Loading To load the resins into the regenerator, first drain most of the excess water from the regenerator to allow an increased educting flow rate, then educt the cation (5 cubic feet), next educt the anion (7 cubic feet). The cation level should be just above the acid header. To properly educt resin into the regenerator, enough water must be added to the resin to create a slurry mixture. To educt: A. Ensure the proper DI system valve line up exists per the DI ] System Valve Line-Up Checksheet. ] B. Connect the quick-disconnect hose to the DI supply and open the T-300 valve RE-89. C. Place a barrel under the eductor pipe to contain the resin slurry to be ; educted. D. Open valves RE-7, RE-18, at the regeneration station. E. Open RE-1.5, check closed RE-16. F. Open vent valve RE-9, to allow the regenerator to drain. G. Open RE-13, place the resin suction line in the resin and open RE-12 to add water to make a slurry. Rev. 7/29/93 App'd M SOP /VII-5

i VIIA.2.1 Resin Loading (cont'd) ] ; H. When waterlevelis suflicient, open R-5 to begin eduction. Stir the resin while it is being educted. When water issues from vent valve RE 3, close RE-13 to allow excess water to drain off. Wait approximately 10-15 minutes. Open RE-13 to continue eduction.

1. Repeat step H until desired level of resin is obtained.

J. When water issues from vent valve RE-9, close RE-13, the's close RE-15. NOTE: At this step all resins are covered with water. DO NOT allow resins to dry out; this can destroy them. K. Close remaining valves, R-5, RE-12 (inside DI room) and RE-7, RE-9, RE-18, RE-89 (at regeneration station). L. Open RE-68 to depressurize the flexible hose, then snut RE-68. M. Record the transaction in both the DI Resin Log and Console Log. VIIA.2.2 R-200 Resin Dump A. Obtain a RWP. B. Ensure the proper DI system valve line.up exists per the DI ] System Valve Line-Up Checksheet. ] C. Place the resin drying barrel under the dump pipe. ] D. Ensure the flexible hose is connected to the DI water supply, then ] open RE-89 and RE-18. E. Open RE-25 compressed air isolation valve and set the regulator ] to 60 lbs. F. Open RE-10 to pressurize R-200 to 60 lbs., then close RE-10. ] G. Slowly open RE-11 to dump resin. You may, at sometime during the ] dumping, need to add water to R-200. Use RE-3 for this purpose. IL When dumping is complete, close RE-11, and RE-25, back off on the ] regulator, and vent the air system. l L Open RE-9 to vent any remaining pressure. ] J. Open RE-3 to fill R-200. ] K. When full, close RE-3, RE-9, RE-18, and RE-89 (T-300 to DI-200 ] isolation valve.) L. Open RE-68 to vent the pressure in the flexible hose, then close ] RE-68. , M. Record the transaction in both the DI Resin Log and Console Log. ]

l. N. Close out the RWP. ]-

Rev. 7/29/93 App'd M SOP /VII-6

VII.4.2.3 Transferring Resin from a DI Column to R-200 A. Ensure that waste tank #2 has the capacity to accept Ole transfer ] water. B. Check the DI Resin Log for the status of the affected bed (s). C. Ensure the proper DI system valve line up exists per the DI ] System Valve Line-Up Checksheet. ] D. Ensure the flexible hose is connected to the DI water supply, then ] open RE-89 and RE-18. E. Open the RE-25 compressed air isolation valve and set the regulator to the maximum pressure available. F. Perform an H3 water transfer to the DCT,ifit has not already been done on this bed. (see VII.4.2.7) G. Add water by opening DI-3, DI 8, and R 2. ] H. When full, close DI-3 and R-2. ] L Open DI-9 and DI-13, and drain bed for four minutes. ] J. Close DI-9 and DI-13. ] K. Open DI-7 fully until the sparge begins. You may have to close DI-7. ] Wait until the pressure in the column vents off and then quickly open DI-7 several times before the hard packed resin breaks loose. When it does, throttle back to the most vigorous sounding sparge and continue for at least ten minutes. If you do p_qt hear a good sparge, water may have to be added. L. When completed, close DI-7 and DI-8. ] M. Open DI-3, DI-6, R-1, RE-7, and RE-16. ] N. To start the resin transfer, open R-2 and observe the bullseye for ] resin movement. The DI water booster pump may have to be used for adequate flow. O. After the transfer is completed, close R-2, RE-16, RE-7, R-1, DI-3, ] DI-6, RE-18, and RE-89 (T-300 to DI-200 isolation valve). P. Close RE-25, back off on the air regulator and vent the air system. ] Q. Open RE-68 to vent the pressure in the flexible hose, then close ] RE-68. R. Record the transaction in both the DI Resin Log and the Console Log. ] Rev. 7/29/93 App'd h SOP /VII-7 l

VII.4.2.4 Transfer of Resins from R-200 to Standby DI Column A. Ensure the proper DI system valve line-up exists per the DI ] System Valve Line up Checksheet. ] B. Check the DI Resin Log for the status of the affected bed (s). C. Ensure the flexible hose is connected to the DI water supply, then ] open RE-89 and RE-18. D. Open RE-3, DI-13, and "ON THE STANDBY COLUMN" open DI-3 and DI-9. E. Open R-3 to start the transfer. Observe the resin flow in the bullseye. The DI water booster pump may have to be used to achieve adequate Dow. F. When transfer is complete, close DI-3. G. Open DI-8 and drain bed for four minutes, then close DI-9. ] H. Open RE-25 and set the air regulator to 45 lbs. I. Slowly open DI-7 to achieve a 10-15 cfm flow rate or a rate which gives the most vigorous sounding sparge and sparge for at least ten minutes. .l J. When completed, close DI-7 and open DI-3 to fill the tank. ]; K. When water overflows through the vent line, close DI-3. L. Close DI-13, DI-8, R-3, RE-18, RE-3, RE-25, and back off on the ! regulator and close RE-89 (T-300 to DI-200 isolation valve). M. Open RE-68 to vent the pressure in the flexible hose, then close RE-68. N. Record the transaction in both the DI Resin Log and the Console Log. VII.4.2.5 Transfer of Resin from DI Column to the Storage Tank A. Ensure that waste tank #2 has the capacity to accept the transfer ] water, B. Check the DI Resin Log for the status of the affected bed (s). C. Ensure the proper DI system valve line up exists per the DI ] 1 System Valve Line-Up Checksheet. ] j D. Ensure the flexible hose is connected to the DI water supply, then ] j open RE-89 and RE-18. ' E. Open the RE-25 compressed air isolation valve and set the regulator to the maximum pressure available. F. Perform an H3 water transfer to the DCT, ifit has not already been done on this bed. (see VII.4.2.7) Rev. 7/29/93 App'd UMlv\ SOP /VII-8

VIL4.2.5 Transfer of Resin from DI Column to the Storage Tank (cont'd) ] G. Open DI 3, DI 8 and R 2 until water comes out vent. ] IL Close R 2 and DI 3. ] L Open DI-9 and DI-13 and drain bed for four minutes. ] J. Close DI-9 and DI-13. ] K. Open DI-7 fully until the sparge begins. You may have to close DI-7, ] wait until the pressure in the column vents off and then quickly open i DI-7 several times before the hard packed resin breaks loose. When it does, throttle back to the most vigorous sounding sparge and continue for at least ten minutes. If you do nD1 hear a good sparge, water may have to be added. L. When completed, close DI-7 and DI-8. ] M. Open DI-3, DI-6, RS-3, RS-5 and DI-13. ] N. To start the resin transfer, open R-2 and observe the bullseye for ] resin movement. The DI water booster pump may have to be used for adequate flow. O. After the transfer is completed, close R-2, DI-13, DI-6, DI-3, RS-3, ] RS-5, RE-18 and RE-89 (T-300 to DI-200 isolation valve). P. Close RE-25, back ofr on the air regulator and vent the air ] system. Q. Open RE-68 to vent the pressure in the flexible hose, then close RE-68. ] R Record the transaction in both the DI Resin Log and the Console Log. ] VII.4.2.6 Transfer of Resin from the Storage Tank to R-200 A. Ensure that waste tank #2 has the capacity to accept the transfer ] , of water. B. Check the DI Resin Log for the status of the affected bed (s). C. Ensure the proper DI system valve line-up exists per the DI ] System Valve Line-Up Checksheet. ] D. Ensure the flexible hose is connected to the DI water supply, then ] open RE-89 and RE-18. E. Open the RE-25 compressed air isolation valve and set the regulator to the maximum pressure available. F. Fill storage tank by opening RS-1, RS-2, and R 2 until water ] l comes out vent. ] Rev. 7/29/93 App'd M . SOP /VII-9

VII.4.2.6 Transfer of Resin from the Storage Tank to R-200 (cont'd) ] G. Close R-2 and RS-2. ] H. Open RS-5 and DI-13 and drain bed for four minutes. ] L Close RS-5 and DI-13. ] J. Open RS-4 slowly to achieve the best sounding sparge and allow it to ] sparge for ten minutes. K. When completed, close RS-4 and RS-1. ] L. Open RS-2, RS-7, R-1, RE-7 and RE-16. ] M. Open R-2 to start the transfer. Observe the resin flow in the bullseye. ] The DI water booster pump may have to be used to achieve adequate flow. N. When transfer is complete, close R-2, R-1, RS-2, RS-7, RE-7, RE-16, ] RE-18 and RE-89 (T-300 to DI-200 isolation valve). O. Close RE-25, back off on the air regulator and vent the air system. ] P. Open RE-68 to vent the pressure in the flexible hose, then close RE-68. ] Q. Record the transaction in both the DI Resin Log and the Console Log. ] VII.4.2.7 Transferring Tritiated (3H) Water to the DCT i A. Check the DI Resin Log for the status of the affected bed (s). B. Ensure the proper DI system valve line-up exists per the DI ]

                                   ' System Valve Line Up Checksheet.                                            ]

C. Ensure the operability of the DCT system by pumping down the collection tank prior to this operation. D. Ensure the flexible hose is connected to the DI water supply, then open RE-89 and RE-18. E. Open RE-25. F. Open DI-9 AND DI-14. G. Open DI-10 (DI-200) or DI-Il (DI-201) or DI-12 (DI-202), whichever is applicable to this operation, to start the water transfer. H. When tank is empty, close DI-10, DI-ll or DI-12 (whichever is applicable) , and DI-9. I. Open DI-8, R-2 and DI-3 to fill the tank with water. J. When full, close DI-3 and DI-8. K. Repeat steps F through J so that you have completed two water transfers and fills. The bed will be left in a filled condition. Use CAUTION to ensure that you do not overfill the DCT. ] L. When completed, close DI-14, R-2, RE-25, RE-18 and RE-89 (T-300 to DI-200 isolation valve). M. Open RE-68 to vent pressure in the flexible hose, then close RE-68. N. Record the transaction in both the DI Resin Log and the Console Log. Rev. 7/29/93 App'd h, SOP /VII-10

U.4.3 - Providing DI Water te T-300 or the Facility Demineralized Water ] Tanks ] DI water may be sent to T-300 or the facility DI water tanks with or ] without the use of the reverse osmosis unit as a DI-300 makeup supply. Due to the fact that DCW, after passing through the R.O. Unit,is much more pure than raw DCW, the R.O. Unit is normally utilized to prolong the life of the DI-300 resin regeneration. However, there are provisions for bypassing the R.O. Unit when sending DI-300 water directly to DI-200 (see VII.4.3.3). VII.4.3.1 Providing DI Water to T-300 or the Facility DI Water Tanks with ] Reverse Osmosis Makeup A Culligan (Polishing) bed is used to augment the R.O. unit, A. Open: ]

1. RE-31 if supplying water to T-300. ]

2. DI-21 if supplying water to facility DI water tanks. ]

B. Place product water valve RO-10 to the DI water system position. NOTE: The handle points in the direction of the open port. C. Check open the following R.O. Unit valves: RO-1, RO-2, RO 5, RO-7, RO-8, RO-9 and RO-13. D. Open outlet valve (RO-11) from Culligan bottles. E. Open DI-5. F. Turn conductivity meter te "ON" and place auto valve switch to " AUTO"

                 'irst auto valve should open). If sending to T 300, place high level ]

cutout switch to cutout if high level shutdown exists in facility ] DItanks. ] G. Push the R.O. Unit start button. H. Push reset button under conductivity meter (second auto valve should open). There should be a 3 to 6 second delay before R.O. Unit starts. (Pressure should come up to 190-200 psig.) CAUTION: If valves do not open, the conductivity is at or above alarm setpoint. Place normal / bypass switch to " BYPASS". I. Flush R.O. Unit through DI-5 until conductivity falls below alarm j setpoint. .) J. Open auto valve isolation valve (DI-17) and shut DI-5. l K. Place normal / bypass switch to " NORMAL"if required. L. Fill out the DI water log. l Normally, the water inlet temperature will not require adjustment and is set -l at approximately 25 to 30 C. Allow at least 30 minutes of running time to l stabilize temperature prior to detennining if an adjustment is needed. ! Rev. 7/29/93 App'd WJM SOP /VII-11

i TO SECURE SENDING WATER A. Push the R.O. Unit off button. B. Place auto valve switch to "CLOSE." Turn conductivity meter to "OFF" (both auto valves should be closed). C. Shut auto valve isolation valve (DI-17). D. Shut Culligan bottles discharge valve (RO-11). E. Place product water valve RO-10 to the flush or drain position. F. Shut: ]

1. RE-32 if supplying water to T-300. ]

2. DI-21 if supplying water to facility DI water tanks. ]

CAUTION: The following valves should be left open while the unit is OFF: RO-2 RO 7 RO-5 RO-8 RO-1 RO-9 RO-6 RO-13 G. Fill out the DI water log. When the unit is not in use, DO NOT UNPLUG, PLACE IN STANDBY ONLY. DO NOT SECURE SUPPLY WATER. NOTE: If for any reason the unit must be turned ofror the supply water secured, this condition MUST NOT exist for more than 60 hours or damage will occur to the filter membranes (see technical manual

                       #476 for details).

No regular maintenance is required to operate this unit. For any repair or maintenance, refer to the technical manual.

VII.4.3.2 Providing DI Water to T-300 Without Reverse Osmosis Unit Makeup Transferred to SMP-22. VII.4.3.3 Providing DI Water to DI200 Units Using R300 Bed Transferred to SMP-22. Rev. 7/29/93 App'd M SOPNII-12

I THIS PAGE INTENTIONALLY LEFT BLANK . l i r Rev. 7/29/93 App'd h SOP /VII-13

THIS PAGE INTENTIONALLY LEFT BLANK Rev. 7/29/93 App'd M SOPNII-14

l 1 C. Material which may be irradiated in the p-tube system includes wa.ter, plant- and animal tissue and fluids, bone, air filters, soils, rocks, soil extracts, coal, paper, , meteorites, fibers, dried paint, safe insulation and- ; glass. Pure elements, alloys and compounds not exempted I in D below may also be irradiated subject to the. activity limitations in A. D. Unless it is specifically authorized in the experimenter's l RUR, the following materials will not be irradiated in the p.-tube system: l E. 1. Natural uranium; ]

2. Special nuclear materials as defined in Title 10, Part 70, Paragraph 70.4m of the Federal Code of Regulations (i.e., plutonium, uranium-233, or uranium enriched in isotope 233 or 235);

3. Pure elements: Li , Na , K, Rb, Cs , Ca , Sr, Ba , Hg, Os ,

H, 0, F, Ne, Ar, Kr Xe, and P;

4. Compounds: NH4 H0 3 , CaC 2 , Ca0, perchlorates, perman- ,

ganates, Na20, and Na2 023

5. Materials which chemically react with water to produce undesirable quantities of heat and pressure;

6. Any explosive, flammable, combustible, or toxic materials. ,

F. Capsules may be run shielded with cadmium or boron (as -] boron, BC, or BN) but weight and time are restricted due. l to the heat generated and their reactivity effect on the reactor. The experimenter shall take measures to insure the heat generated can be dissipated without causing damage to the rabbit or sample. The following limitations apply to. shielded capsules in addition to the activity limits of Section VIII.3.2.A: Rev. 5/02/89 App'd' M SOP /VIII-11 ] v a-~ . ., _ , _ . . - -

4 VIII.3.2. Sample Limitations (cont'd) ]

1. The authorized p-tube user will inform the control room he/she ]

is going to run shielded capsules and will insert the rabbit so that the cap is on top when the rabbit is in the reactor.

2. Cadmium shielded capsules:

a. 5 or less grams of cadmium may be run for up to 30 minutes.'

b. 50 or less grams of cadmium may be run for up to 10 seconds in Row 1 or 20 seconds in Row 2.

3. Boron shielded capsules:

NOTE: The weight limit is only on the boron, i.e., the carbon weight in BC does not count towards the weight limit.

a. - The single boron shielded capsule with between 10 to 15 grams ]

of boron may be run for up to 15 seconds in Row 1 or up to 20 ]' seconds in Row 2. ]

b. The double boron shielded capsule with between 15 and ] .

20 grams of boron may be run for up to 10 seconds in , ] Row 1. ]. G. Except for the boron or cadmium shielded samples, the controlling : factor for determining the weight and time limits of a sample to be irradiated in the p. tube is the activity limitation of Section A. If the activity limits do not further restrict a sample's size, the following weight limits shall apply:

1. For irradiation times up to 30 minutes, the maximum weight of irradiated materials in one rabbit will be 2 grams with two i

exceptions: ,

a. A maximum of 10 grams of water or dried feces;

b. Only 1 mg of chemical compounds in solution.

2. Forirradiation times of 30 minutes to 1 hour, the maximum weight ofirradiated materials in one rabbit will be 1 gram with' two exceptions:

a. A maximum of 10 grams of water or dried feces; ,

b. Only 500 mg of chemical compounds in solution. .

 .Rev. 7/29/93   App'd M                                                       SOP /VIII-12

i VIIL3.2 Sample Limitations (cont'd) ] l i The weight limits above do not include the weight of the rabbit, polyethylene vial, or packing, or the cadmium (or other metal) shields. The maximum irradiation time for most samples will be 30 minutes for power levels > 5 MW. Hair, fibers, paint, air filters and flux monitors may be irradiated for a maximum of 2 hours at power levels > 5 MW. The following additional limitations shall apply for irradiations > 10 minutes: i

               ), Primary encapsulation will be heat-scaled high-density polyethylene vials (Holland vials).

2. Liquid samples may be irradiated for up to 30 minutes provided pin ,

holes are punched in the top of the polythylene vial to relieve pressure. Deviations from the above weight and time limitations must be specifically authorized in the experimenter's RUR. VIII.3.3 Rabbit Limitations A. The only type of rabbit which may be used in the p-tube system is the high density rabbit. This type of rabbit will be used for all irradiations (see Section VIII.3.2.B). Each high density rabbit will be limited to six insertions not to exceed a total irradiation time of one hour or a single insertion not to exceed a total of two hours. EXCEPTION: Each high density rabbit, used for 5 second irradia-tions under RUR 254,is authorized to be run a total of 15 times. . To account fbr the irradiation history of high density rabbits, the experimenter will place one mark with a marking pen on the high density rabbit for each insertion up to and including 10 minutes. For , irradiations longer than 10 minutes, a mark will be placed on the ' rabbit for each 10 minute period or fraction there of. For example, if a rabbit is irradiated for 25 minutes, it will receive 3 marks. When a 7 rabbit has received G marks, it will be discarded. Each rabbit must be , examined for cracks or other signs of potential failure before it is used. B. Only high density modified rabbits may be used in the p-tube ] system to run boron shielded rabbits. ] Rev. 7/29/93 App'd b SOP /VIII-13

i VIII.3.4. Sample Irradiation Procedures ) I VIII.3.4.1 When experimenter has met the requirements of VIII.3.3 and is ready ] to run experiment, he/she shall first make certain that the P-tube ] ; system for the desired irradiation position is not in use; i.e., the system "in use light"should be off, and then call the reactor control room giving: ] A. Name B. Laboratory room number l C. Experiment file number D. Project number E. Length of time the sample will be in reflector F. If the irradiations are to be done under the Serial Mode, the ] experimenter must advise the operator that such is the case. ] G. When operating in the Serial Mode, the experimenter must ] contact the control room in the case of any of the following: )

a. Any problems with the dispatch or receipt of a rabbit. ]

b. Any interruption or delay of the intended cycle such that ]

the blowers could be secured if the operator deems it ] i necessary.

c. Any significant change in sample or standard matrix or ]

use of, or discontinuation of use of, a boron capsule. ]

d. Any change in irradiation time. ]

e. Any time the laboratory is left unattended, even for short ]

periods of time. ]

f. Any change of pneumatic tube operators. ] l

g. When the experiment is concluded. ] l IL Any point during the Serial Mode of operation, the experi- ]

menter must be able to expeditiously determine the number ] ofirradiations completed. ] L At the end of the experiment, or at any break point when the ] laboratory is to be left unattended for any period, the experi- ] menter will terminate the Serial Model (seg exception below) ] by the following steps: !

a. Contact the control room and inform the operator that .]

the Serial Mode is being terminated. ]

b. Inform the operator of the total number ofirradiations ]

completed. ]

c. Secure the pneumatic tube control station. ] u

d. Complete the pneumatic tube log. ]

Rev. 7/29/93 App'd \kWTh SOPNIII-14 l 1 l

'l

VIIL3.4.1 Cont'd ] EXCEPTION: With agreement from the control room, the ] experimenter can take short (~ 5 minutes) breaks without ] terminating the run. In such cases the experimenter will ] contact the control room and request a break. The experi- ] menter willlock the lab door. In no case shall the experi- ] menter leave the building during these short breaks. These ] breaks cannot be requested while there is a rabbit in the ] reactor. When the experimenter resumes the run, he/she ] shall again contact the control room and report that the run ] is being resumed. ] VIII.3.4.2 After blowers are verified "ON" by the control room operator, the system will be operated as described in steps A through F of this section. ] When the Serial Mode of operation is to be used, the control room ] operator will stay in audio contact for one cycle. ] (THE POSITION OF ALL CONTROLS AND INDICATIONS ARE SHOWN ON FIGURE VIII-1) NOTE: The " RETURN" pushbutton will return rabbit to fume hood , during any portion ofirradiation cycle. A. Set timer to desired irradiation time.

1. Depress and hold pushbutton I.

2. Depress numbered pushbutton until desired time is indicated on display (HH.MM.SS).

3. Release pushbutton I. ;

4. Timer is now set, and need not be touched again until a new irradiation time is required.

B. Place power switch to "ON"(" System in use" lamp lights). C. Depress " Dispatch" pushbutton (system is now lined-up to accept rabbit). D. Insert rabbit, with cap down. E. Observe that " Rabbit in Reactor" lamp lights, and that the timer ] starts. Then state to the control room operator that "The ] rabbit is in the reactor." ] Rev. 7/29/93 App'd LOMh SOP /VIII-14a ]

l l l, DISPLAY ; i bbbbbb I R P.B. R ABBIT IN REACTOR DISPATCH P.B. RETURN ON SYSTEM IN USE O OFF I 8 ' Figure VIII-1 i Control Station for Laboratories 216, 218, 227, 228 Rev. 5/02/89 App'd M SOP /VIII-15 ] Reset- ,

i l VIII.3.4.2 Cont'd ] F. At the end of the pre-selected irradiation time, the rabbit will be ] returned to the " catcher"in the fume hood. The experimenter ] should state to the control room operator that "The rabbit is ] back." In the case of serial operations, a communication ] should be exchanged between the experimenter and ] operator that such is the case for the first rabbit run. ] G. If more than one rabbitis to be run, using same irradiation time, depress " Dispatch" pushbutton and insert next rabbit. H. After last rabbit is run, place power switch to "OFF." I. Call control room and give the irradiation time for the rabbit and number of rabbits irradiated. Verify numbers consietent with those reported in Section VIII.3.4.1.E and F. If different, determine cause of discrepancy. In the case of serial operations, review steps F ] through I of VIII.3.4.1 above. ] VIII.3.4.3 After the rabbit has returned from the reactor, check the dose rate. VIII.3.5. P-Tube Emergency Procedures VIII.3.5.1 The most common occurrences will be trouble with the station controls, , the possibility of the rabbit sticking in the tube, and the rabbit coming - apart in the pneumatic tube system. VIII.3.5.2 Station Control Malfunction A. If a boron shielded rabbit is in the reactor and is not auto- ] matically returned at the maximum irradiation time, ) immediately notify the control room. The control room ] operator will initiate a manual RRI to about 500 kw. Press ] the " return" pushbutton. Control room operators can then ] listen for rabbit movement. ] B. If a standard rabbit is in the reactor and is not automatically ] discharged, immediately notify the control room and then ] press the " return" pushbutton. The control room operator can ] then listen for rabbit movement. ] C. If the rabbitis not in the reactor and station controls do not work, ] call the control room. The reactor operator will then get in teuch with the electronic technician. NOTE: The expcrimenter is N_QI authorized to attempt repair of the system. Rev. 7/29/93 App'd W SOP /VIII-16 l

I i i VIII.3.5.2 Station Control Malfunction (cont'd) ] l C. Report to the control room the material contained in the sample, the ! , expected activity and dose rate, and the approximate time the rabbit can remain in the reactor without creating any hazard. D. The reactor operator will getin touch with a health physics technician H

to monitor as required.

VIII.3.5.3 Rabbit Stuck in Tube Any time all or any part of a rabbit fails to return to the dispatch station, notify the control room immediately about the problem, stating the material contained in the sample, the weight of the sample, the expected activity and dose rate, and the approximate time the rabbit can remain in

the reactor without creating any hazard or melting.

A. ARer the control room is aware of the problem, press the " return"

pushbutton. Observe the rabbit in reactor light and check with the
control room to see if the operators heard the rabbitleave the reflector region. Hearing the rabbit depart the reflector is the only sure way to know it has leR. If the rabbit was heard to depart the reflector region, check the other connecting station to see if the rabbit: l. was returned there.; i. B. Depress the dispatch button.

I C. Repeat steps A and B several times as directed by the control room. D. If the attempts fail, turn control box off. Gc to the other connecting 2 station,line it up for service and repeat steps A and B. I E. If rabbit still has not returned, a chaser rabbit may be inserted in an l attempt to dislodge the stuck rabbit. Before the chaser rabbit is dispatched it will be marked so that it can be readily identified, thus 5 preventing confusion with the stuck rabbit should it return. CHASER RABBIT ID MARK SHOULD GO ACROSS ONE END CAP, ALONG THE SIDE AND ACROSS THE OTHER END CAP. F. If these procedures have failed, follow up action will be handled by reactor operations and health physics personnel. NOTE: If the rabbit is stuck outside the reactor it may be found by searching the guide tubes with a radiation monitor. If the rabbit is stuck in the reflector, the reactor may have to be shutdown and the p-tube removed. VIII.3.5.4 Wet Rabbit If the outside of the rabbit is wet when it is returned from the reactor, notify the control room immediately. Rev. 7/29/93 App'd M SOP /VIII-17

j l l 1 1 THIS PAGE INTENTIONALLY LEFT BLANK New 7/29M3 App'd W sopyIII.17a ] . l

                                                                ..   .j
                                                                       \

i l V111.3.6 Emergency Return of Rabbit with Malfunctioning P-Tube Control Box l i Dispatch and return of the rabbit is controlled by solenoids in ) cabinet located by the seal trench. All solenoids in use are l labeled by letters in the solenoid cabinet. Procedure to be followed in case of a failure at the local station is as follows: A. Remove cover to solenoid cabinet. B. Turn solenoid power switch off (this de-energizes all solenoids). NOTE: THIS CLOSES OFF ALL TUBES WHICH WILL RESULT IN A HIGH CONCENTRATION OF AR M IF THE REACTOR IS OPERATING. Roon 216 - R and J Dispatch solenoids Roon 218 - Q and J Dispatch solenoids Roca 227 - B and N Dispatch solenoids Roon '228 - A and N Dispatch solenoids Refer to solenoid schedule. C. Energize the P-tube blowers. D. Then, " manually" depress following solenoids in solenoid cabinet. Room 216 - U and L Return solenoids Room 218 - V and L Return solenoids Room 227 - G and 0 Return solenoids Room 228 - H and 0 Return solenoids As an example, the solenoids for return to room 216 should be in the following positions: solenoids R and J "up"; solenoids U and L "down". Rev. 5/02/89 App'd M SOP /VIII-18 ] Reset

VIII.8 RESPONSE PROCEDURES FOR THE ALPHA LABOlMTORY , When responding to alarms from the Alpha Laboratory and the ] Argon Glove Box, an initial attempt to contact the laboratory to ] notify any lab personnel present shall be made. If no answer, or ] if otherwise determined necessary, proceed with the following ] procedure. ] NOTE: Maintaining an inert argon atmosphere is the principal fire safety feature of the argon glove box. The following t.larms may not have immediate safety implications, however, they indicate a degradation in the fire safety feature of the arr;on glove box and indicate a potential loss of glove box integrity. VIII.8.1 RESPONSE TO ALPHA LABORATORY HIGH AIRBORNE RADIOACTIVITY ALARM (Exhaust and/or Room Monitor)

1. Notify shift supervisor and Health Physics Manager.

2. Monitor readings on facility exhaust particulate monitor in control room. An assessment of the off-site radiological consequences shall be made. ]

3. If the stack particulate monitor indicates a steady increase coinciding with an alpha-6 alarm, secure the reactor, and turn off EF-13 ]

and EF-14 at the breakers on the Emergency Distribution Center. ]

4. Ensure persons have evacuated the Alpha Laboratory. If no experimenter is present, call the on-call experimenter as soon as time permits.

WARNING: DO NOT enter room, except for life saving or accident mitigation efforts, until Health Physics arrives. If emergency ] entry is made, wear emergency breathing apparatus. ]

5. Secure the Alpha Laboratory exhaust and supply fans locally.

6. Shut the Alpha Laboratory supply damper only. *

7. With Health Physics coverage, enter Alpha Laboratory using emergency breathing apparatus to locate and repair source of ]

airborne activity. , l SUBSEQUENT ACTION: Assist recovery and decontamination procedures for the Alpha Laboratory and basement in vicinity of Alpha Laboratory. Rev. 7/29/93 App'd lWTY\ SOP /VIII-43

VIII.8.2 HIGH OXYGEN IN GLOVE BOX ALARM NOTE: The continuously operated oxygen monitor (located in the DRI-TRAIN rack)is the most sensitive indication of air leakage into the argon glove box.

1. Verify no increased airborne activity on the stack monitor.

2. Notify Shift Supervisor and Health Physics technician. ]

3. Contact TRUMP-S scientist on call. ]

           .t. a) Check the warning light panel outside the door and check             ]

the argon glove box pressure indicated on the three photohelic ] gauges located on top of the argon glove box. (Normal range ] 0.1 to -2.0 inches of water). ] b) If pressure is near zero, then the possibility of a leak exists and the glove box should be visually inspected from the window to the Alpha Laboratory.

5. Check the Alpha Laboratory exhaust monitor (alpha 6) and the ]

Alpha Laboratory room monitor (alpha 3) for indication of elevated ] activity, a) If no elevated activity is indicated on either monitor, enter the laboratory by normal entry procedure, TAM-10. b) If elevated activity is indicated, see SOP VIII.8.1, Response to Alpha Laboratory High Airborne.

6. Check NITRAIN/DRI-TRAIN units for loss of power. ]

7. Check glove ports covered. ]

8. Check oxygen monitor reading. If reading exceeds 100 ppm, secure ]

the argon box well heater (use range switch ifindication is ] off scale). ]

9. Investigate source ofleakage and temporarily seal,if possible. ]

10. Exit Alpha Laboratory by normal exit procedures, TAM-10. ]

11. Assist TRUMP-S scientist and Health Physics in determining source ]

and corrective action. , Rev. 7/29/93 Appd lh SOPNIII-44

VIIL8.3 LOW ARGON SYSTEM PRESSURE ALARM i NOTE: This alarm may indicate an argon system leak or a loss ofintegrity of the argon glove box or simply low argon bottle pressure. ] (A loss of glove box integrity will also cause High Oxygen Alarm.) ] The pressurized argon gas bottles provide argon makeup to the argon conditioning system (a recirculating purification system) associated with the argon glove box.

1. Check the argon bank pressure at inner passageway. Replace ]

bottles, if necessary.

2. Notify Shift Supervisor and Health Physics technician. ]

3. Call the TRUMP-S scientist on call. ]

4. Inspect argon gas bottle system and argon line to Alpha Laboratory for leaks. Repair any leaks, if possible.

5. a) Check the argon glove box pressure indicate 1 on the photohelic ]

gauge located on top of the argon glove box. (Normal range -0.1 ] to -2.0 inches of water. ] b) If pressure is near zero, then the possibility of a leak exists and : the glove box should be visually inspected from the Alpha Laboratory window. G. Check the Alpha Laboratory exhaust monitor and the Alpha ] Laboratory room monitor for indication of elevated activity. a) If no elevated activity is indicated on either monitor, enter the laboratory by normal entering procedure, TAM-10. b) If activity is indicated, see SOP VIII.3.1, Response to Alpha Laboratory High Airborne Activity.

7. Check NITRAIN/DRI-TRAIN units for loss of electrical power ] :

(pressure control system is part of DRI-TRAIN unit).

8. Inspect argon purification system and argon glove box for leaks. ]

9. If argon pressure cannot be restored in 60 minutes or if oxygen ]

monitor alarms and indicates greater than 100 ppm, secure the argon box well heater. ,

10. Exit Alpha Laboratory by normal exit procedure, TAM-10. ]

11. Assist TRUMP-S scientist and Health Physics in determining ]

corrective actions. Rev. 7/29/93 App'd Im SOP /VIII-45 a

THIS PAGE INTENTIONALIX LEFT BLANK i

                                                                          'l 1

New 10/18/9Q App'd VvM SOP /VIII-46 ] Retyped Only 7/16/91 . I l

REP- 12 LOSS OF DOMESTIC COLD WATER TO FACILITY IMMEDIATE ACTIONS:

1. Send operator to monitor secondary sump level.

2. Secure the main air compressor.

SUBSEQUENT ACTIONS:

1. Notify the Shift Supervisor.

2. Announce to the entire facility that domestic cold water service has been ]

interrupted.

3. IE service water cannot be restored within a reasonable amount of time, ]

SHUTDOWN the reactor and secure primary coolant pumps.

4. Secure and tag out the following equipment: ]

a. Secondary pumps P1, P2, P3, and P4, after the reactor has been shutdown (P4 can be left on for building A/C support at the discretion of the Shift Supervisor).

b. Vacuum unit pumps.

c. Alpha Lab. thermal well (notify Alpha Lab. stafD.

d. Air conditioning units. (If all secondary pumps are secured.)

e. Hot water recirculating pump.

f. Room 212 (north counting room) air conditioner. (Notify Nuclear Analysis Program)

g. Room 232B (west counting room) air conditioner. (Notify Nuclear Analysis Program.)

h. Room 260 air conditioning unit.

i. Ice machine.

j. Control Room water heater.

k. RTAH recirculating pump (tag at motor controller at DI-200 regeneration station).

5. Make console entry that the machinery above has been tagged out as per ]

REP-12, and fill out UNSCHEDULED SHUTDOWN REPORT. RECOVERY ACTIONS:

1. Upon restoration of water to the facility, return all systems to normal status.

2. Announce to entire facility the restoration of domestic cold water service.

Rev. 7/29/93 App'd M REP-12-1

i REP-22 BOMB OR OTHER OVERT THREATS Upon any direct threat or actions by any person or group of persons which may endanger personnel safety or the safe operation of the reactor, the reactor operator ; shall: IMMEDIATE ACTIONS:

1. SH'UTDOWN the reactor immediately. ;

2. Secure the master control switch.

3. Notify the UNIVERSITY POLICE by telephone.

4. Ensure all doors are secure, with priority to the truck entry door and ]

personnel airlock door. <

5. Facility evacuation or partial evacuation may be used to remove persons ,

from affected areas. SUBSEOUENT ACTIONS:

1. Notify the Shift Supervisor.

2. Make console entry and fill out UNSCHEDULED SHUTDOWN REPORT. .i NOTE: Facility staff should not enter any direct conflict except when necessary for their own personal safety.

Rev. 7/29/93 App'd b REP-22-1 l

yo. NUCLEAR DATA nATE:

     . Tim e  Rod Position                   Nuclear instrumentatten                       Power by Heat Average    Channel Channel Channel Channel Channel Channel                 Balance in MW RR      CR        1            2       3       4        5      6      Prirnary / Secondary i

1 h i l Rev. 5/74 App'd 4m l (Retyped only 7/30/85) SOP /A-5a

i DATE MODE PROCESS DATA Time I in Pool IIt. Exch. Pressurizer Level Pool Refl. A P PS 944A PS 944B DPS 928A i DPS 928B DPS 929 Sec.Th (1) I ' Sec.Te (2) ] Sec. A T Sec. Water Flow Pool T e Loop A(3) Pool TeLoop B (4) Sec.Th Pool A(5) ) : Sec.ThPri. A (6) ] Rx Cond In Rx Cond Out Pool Cond In Pool Cond Out Stack Gas Stack Part. Stack Iodine Operator Reader IIeat Balance By i i hianual Calculation: Rev. 7/29/93 App'd _h9fA SOP /A-5b >

REACTOR ROUTINE PATROL DATE:

1. Time of start of patrol

2. Time and date all charts !

3. Visual check of entire pool

4. Anti-siphon tank pressure 36 psig 3 psi

5. North iso door seal pressure 18-28 psig

6. South iso door seal pressure 18-28 psig

7. 5th level backup doors open 8.16" iso viv A air pressure 45-55 psig 9.16" iso viv B air pressure >80 psig )

Bkr closed, viv open,

10. Emerg air compress on standby gage 280 psig }

11. Containment hot sump pumps Operable

12. Door 101 seal pressure 18-28 psig

13. BP floor Conditions normal

14. Fuel vault L.ocked

15. Inner airlock door seal pressure 18-28 psig

16. Outer airlock door seal pressure 18-28 psig

17. Cold deck temperature 45-65 deg F

18. Argon bank pressure >200 psig

19. Full N2 bottles Total > 3

21. Bank on service A or B

23. Bank A bottle pressure > 250 psig

                                    > 250 psig

24. Bank B bottle pressure

25. N2 header pressure 135-145 psi

26. T-300 level >2000 gal On the first routine patrol of the day or the first patrol after a startup, drain all water from the anti-siphon system. If draining causes the pressure to drop signifi-cantly, return to the middle of the band (36 psig) and record the pressure here. If a condition or reading is normal, enter a "4" (for conditions) or the reading in the applicable box. If the condition is abnormal, enter the condition or reading and circle it. Explain all abnormal conditions or readings in the REMARKS on page 3.

Rev 9/?R/o? App'd M SOP /A-8a i

l REACTOR ROUTINE PATROL DATE: ;

27. T-301 level <6000 gal

28. Labyrinth sump Level < Alarm Pt.

29. RO unit Condition normal

30. UPS room NO Alarms Indicated -

Temp 600 - 80 F l.

31. T- 300, T-301 Room Thermostat >55 0F Temp. >40 F

32. Rm 114 particulate filter AP <3.5" water 33a. EG. Rm. (Perform complete Thermostat >60 CF (checklist on Sunday) Temp. >50 F 33b. Battery charging current ' <1 amp 33c. Battery Voltage > 28 V ,

34. External doors All locked except east when sec. on duty

35. CT basin water level 5-10"

36. Automatic secondary makeup viv Auto or open

37. Acid day tank level (Perform Visible weekly level check on Friday on storage tank)

38. Acid control and pH Range as posted

39. Blowdown control /cond. Range as posted

40. CT sump pumps Operable

41. P-pump (s) running

42. Pump strainer AP 0 - 7.0 psi

43. Discharge pressure

44. Pump strainer AP 0 - 7.0 psi

45. Discharge pressure

46. Tunnel sump pumps Operable

47. WT booster fan Running

48. Fission product monitor flow 95 -105 cc/ min

49. Viv control header pressure 90 -125 psig

50. Pressurizer N2 supply press 90 - 100 psig

51. Check rm 114 from door

52. Deltech oil filters " red level"

                                      < 75% dark red and blow down Rev. 7/29/93             App'd W                                                                                                                      SOP /A-8b

D.I. WATER MAKEUP LOG Month / Year Time Conductivity Temp Pressure Prod Flow Water Meter Reading ] Data Start Stop Start Stop (25-30) (190 200) (1.5-2.5) Start Stop T300/ Lab ] me o l l I l Remarks: i Rev. 7/29/93 App'd h SOP /A-18a

                                                                         .i t

NOTE: THIS PAGE INTENTIONALLY LEFT BLANK i e t I L Rev. 5/02/89 App'd ( h 50P/A-18b ]' Reset __ _ e

d SECONDARY SYSTEM NORMAL OPERATION VALVE LINE-UP CHECKSHEET .This checksheet shall be completed when required by the SOP. The operator performing the check will verify the position of each valve and indicate the verification by initialing - the checksheet. Under the direction of the Shift Supervisor, a valve may be positioned other than noted on this sheet. The operator will check the valve to be in the desired i position and write in the actual position of the valve. The reason for the valve being positioned abnormally will be noted in the COMMENTS section. Throttled valves shall be checked to be in the position shown by the tag on the valve. Note the valve's position in the space provided on the checksheet. The following valves will be found in the cooling tower or cooling tower tunnel. Valve # Valve Description Position -

1. S-5 P-1 discharge Open

2. S-6 P-2 discharge Open

3. S-7 P-3 discharge Open

4. S-8 P-1 suction Open

5. S-9 P-2 suction Open Open

6. S-10 P-3 suction

7. S-11 P-4 suction Open

8. S-12 P-4 discharge Open

9. S-105 P-4 strainer DP gauge Open

10. S-106 P-4 strainer DP gauge Open

11. S-107 P-1 strainer DP gauge Open

12. S-108 P-1 strainer DP gauge Open

13. S-109 P-2 strainer DP gauge Open

14. S-110 P-2 strainer DP gauge Open

15. S-111 P-3 strainer DP gauge Open

16. S-112 P-3 strainer DP gauge Open

17. S-114 P-1 suction pressure gauge Open

18. S-115 P-2 suction pressure gauge Open

19. S-116 P-3 suction pressure gauge Open

20. S-117 P-4 discharge pressure gauge Open ,

21. S-118 P-1 discharge pressure gauge Open

22. S-119 P-2 discharge pressure gauge Open

23. S-120 P-3 discharge pressure gauge 'Open

24. S-128 Chemical addition connection (ground level) Open

25. S-155 Chemical addition connection (ground level) Open New 7/29/93 App'd b SOP /A-21a

Valve # Valve Description Position

26. S-163 Drain of relief valve on pump discharge Open

27. S-197- Conductivity and pH sampling (ground level) Open

28. S-198 Conductivity and pH sampling (ground level) Open -

29. S-17 Cooling tower distribution valve Open

30. S-18 Cooling tower distribution valve Open

31. S-19 Cooling tower distribution valve Open

32. S-20 Cooling tower distribution valve Open

33. S-21 Cooling tower distribution valve Open

34. S-22 Cooling tower distribution valve Open :

35. S-47B P-4 return to cooling tower distribution line Open.

36. S-113 Drain isolation (2") on secondary supply Closed -

i

37. S-121 P-4 line vent Closed

38. S-123 P-1,2 & 3 line vent Closed

39. S-125 To floor drain Closed

40. S-101 Return line to floor drain Closed

41. S-126 Return line to floor drain Closed

42. S-102 Condensers to floor drain Closed

43. S-129 Drains return line to cooling tower basin Closed

44. S-127 P-4 discharge to cooling tower (ground level) Closed

45. S-47A P-4 to cell #1 soutl$ (winter & maintenance) Closed

46. S-196 Drain valve for P-4 cell #1 south Closed 1

The following valves will be found in the 114 passageway: ;

i

47. S-170 From building air supply Open

48. S-171 Air supply to primary heat exchangers Open

49. S-172 Air supply to pool heat exchangers Open ,

50. S-202 Corrosion rack isolation -in Open

51. S-203 Corrosion rack isolation - out Open

52. 170 Blowdown isolation Throttled

53. S-103 Supply to conductivity and pH detectors Closed

54. S-151 Return from conductivity and pH detector Closed

55. S-199 Blowdown isolation (ball valve) Closed

56. S-164 Return drain to floor Closed

57. S-165 Supply drain to floor Closed

58. DCWR7 DCW from Alpha Lab Closed l

i New 7/29/93 App'd .kML(L_ SOP /A-21b ) l l

o i The following valves will be found in Room 114: Valve # Valve Description Position

59. -S-161 dp transmitter hp isolation Open .

60. S-183 Rosemount hp isolation Open

61. S-130 Bailey hp isolation Open

62. S-182 Rosemount lp isolation Open

63. S-131 Bailey Ip isolation Open ,

64. S-162 dp transmitter Ip isolation Open

65. S-23 HX503A supply isolation Open

66. S-24 HX503B supply isolation Open >

67. S-25 HX521B supply isolation Open

68. S-26 HX521A supply isolation Open

69. S-30 S-1 supply side isolation Open

70. S-31 S-1 return side isolation Open

71. S-34 S-2 supply side isolation Open

72. S 35 S-2 return side isolation Open

73. S-39 HX503A return side isolation Open

74. S-41 HX503B return side isolation Open

75. S-43 HX521A return side isolation Open

76. S-45 HX521B return side isolation Open

77. S-173 HX521A sparge Open.

78. S-145 HX521A line vent Open

79. S-174 HX521B sparge Open ,

80. S-176 HX503A sparge Open

81. S-178 HX503B sparge Open

82. S-154 Vent return header (HX521B) Closed

83. S-181 Bailey hp test connection Closed

84. S-185 Rosemount hp test connection Closed . ,

85. S-184 Equalizing valve Closed

86. S-186 Rosemount lp test connection Closed

87. S-180 Bailey 1p test connection Closed

88. S-133 Transmitter flush valve Closed

89. S-27 S-1 bypass valve Closed ,

90. S-28 S-2 bypass valve Closed

91. S-29 heat exchanger bypass valve Closed

92. S-157 HX521A flush Closed

93. S-158 HX521A flush Closed

94. S-139 HX521A drain Closed New 7/29/93 . App'd _% SOP /A-21c

l Valve # Valve Description Position

95. S-138 HX521A drain Closed

96. S-143 HX521A vent Closed

97. S-140- HX521B drain Closed

98. S-175 HX521B flush connection Closed

99. S-144 HX521B vent Closed 100. S-137 HX503B drain Closed

101. S-142 HX503B vent Closed 102. S-136 S-1 drain Closed r 103. S-134 Hydro connection Closed 104. S-135 Hydro connection Closed 105. S-141 HX503A vent Closed '

106. S-117 HX503A drain Closed 107. S-145 Vent HX521A Closed 108. S-195 Return to HX503A from waste heat system Closed , 109. S-194 Supply from HX503B to waste heat system Closed The following valve is found in the waste tank room: 110. S-169 Waste tank isolation Closed For operation of the air conditioners with feed water from P-1, P-2, P-3, or P-4. The following valves will be found in Room 278: 111. S-53 Supply to A/C unit #2 Open 112. S-57 Discharge A/C unit #2 Open 113. S-55 Supply to A/C unit #1 (LiBr) Open 114. S-58 Discharge A/C unit #1 (LiBr) Open 115. S-200 Flow isolation Open 116. S-201 Flow isolation Open 117. S-146 Vent (by DI-300) Closed 118. S-54 Vent (by steam supply to LiBr unit) Closed 119. S-149 Vent (by DI-300) Closed New 7/29/93 App'd li/&fW SOP /A-21d

                                                                        ,, m

l For operation of the auxiliary heating and cooling system. , Valve # Valve Description Position 120. AX-2 Auxiliary heat pump suction Open 121. AX-3 Auxiliary heat pump discharge Open 122. AX-4 Auto control valve for auxiliary heat system Open 123. AX-8 Supply side isolation Open 124. AX-9 Return side isolation Open The following valves are open in winter and closed in summer: 125. AK-1 Secondary supply isolation 126. AX-5 Secondary return isolation , The following valves are open in summer and closed in winter: 127. AX-6 Chill water supply isolation 128. AX-7 Chill water return isolation l l New 7/29/93 App'd N SOP /A-21e - -l i

                                                ,                                       I I

i

                                                           -l l

THIS PAGE INTENTIONALLY LEFT BLANK

New 7/29/93 App'd % SOP /A-21f

DI SYSTEM VALVE LINE-UP CHECKSHEET NOTE: Check the DI resin log and status board for the current status of all DI beds and filter banks. Valve Valve Description Position 515Q DI return to pool Closed 515M DI suction from pool Closed

            .515T         DI suction from loop                          Open 515P         DI return to pool                             Open 515AC        Pool DI to blank flange                       Closed 515J         P-513 suction                                 Open 515L         P-513 discharge                               Open DI-10        Air to DI-200                                 Closed DI-11       Air to DI-201                                 Closed DI-12       Air to DI-202                                 Closed DI-13       Drain to floor                                Closed DI-14       Drain to DCT                                  Closed RE-1        Water isolation to vent tank                  Closed RE-2        R-200 water isolation                         Closed RE-3        R-200 water isolation                         Closed RE-4        R-200 water isolation                         Closed RE-5

Closed >

RE-6

Closed RE-7 R-200 isolation to drain Closed RE-8 R-200 isolation to drain Closed RE-9 R-200 vent Closed RE-10 R-200 air isolation Closed RE-11 Resin dump Closed RE-12 Resin suction Closed RE-13 Eductor isolation Closed RE-14 R-200 to vent tank Closed RE-15 to floor drain Closed RE-16 to Water Tank #2 Closed RE-17 10 gpm flow meter throttle valve Closed RE-18 50 gpm flow meter throttle valve Closed RE-19 10 gpm flow meter throttle valve Closed l RE-20 Vent tank vent Closed l RE-21 Waterisolation to sample sink Closed

 *These valves used only when regenerating DI beds per SMP-16.
- New 7/29/93     App'd M                                                      SOP /A-22a i

l l

Valve Valve Description Position RE-22

Closed RE-23 Sample line isolation Closed RE-24 R-200 to floor drain Closed RE-25 Air system isolation -Closed RE-26 DI from DI-300 isolation Closed RE-27 DCW isolation Closed RE-28 DHW isolation Closed RE-30 DI to regneration from DI-300 Closed RE-31 DI to T-300 Closed -

RE-33

Closed RE-34 Air isolation to regeneration Closed RE-47 Vent tank drain Closed RE-52 HP air system bleed valve Closed RE-53 HP air pressure regulator Closed i RE-55
Closed -

RE-56

Closed RE-57
Closed i RE-58
Closed .
Closed i RE 59 RE-60
Closed RE-61
Closed RE-62
Closed RE-63
Closed RE-64
Closed RE-65
Closed -

RE-66

Closed RE-67
Closed RE-68 Hose drain Closed RE-70 Drain to Waste Tank #2 Closed RE-89 DI from T-300 isolation Closed RE-90
Closed RE-91
Closed

  *These valves used only when regenerating DI beds per SMP-16.

New 7/29/93 App'd M SOP /A-22b b

Valvo Valve Description Position RESIN STORAGE TANK ; RS-1 Vent Closed RS-2 Sluice to DI units (top) Closed RS-3 Sluice from DI units (top) Closed RS-4 - Air supply Closed RS-5 Drain Closed RS-6 Sluice to DI units (bottom) Closed RS-7 Sluice from DI units (bottom) Closed B30fl R-1 Sluice from DI units Closed R-2 Water to sluice DI units Closed R-3 Sluice to DI units Closed R-5 Eductor isolation Closed POOL INLET FILTER BANK F-200 F-1 Inlet Open F-2 Bypass Closed F-3 Outlet Open ERIMARY INLET FILTER BANK F-201 F-4 Inlet Open F-5 Bypass Closed F-6 Outlet Open PRIMARY OUTLET FILTER BANKS F-202 off service (on service) F-7 Inlet Closed (Open) F-8 Outlet Closed (Open) F-203 off service (on service) ' F-9 Inlet Closed (Open) F-10 Outlet Closed (Open) POOL OUTLET FILTER BANKS F-204 off service (on service) F-11 Inlet Closed (Open) F-12 Outlet Closed (Open) F-15 Drain Closed F-204 off service (on service) F-13 Inlet Closed (Open) F-14 Outlet Closed (Open) F-16 Drain Closed New 7/29/93 App'd M ' SOP /A-22c

                                                                             'J Valve                        Valve Description    Position ON POOL SERVICE BED DI-DI-1           From pool                        Open DI-2           From reactor                     Closed DI-3           Sluice inlet                     Closed DI-4           To pool                          Open DI-5           To reactor                       Closed DI-6           Sluice outlet                    Closed DI-7           Air supply                       Closed DI-8           Vent                             Closed DI-9           Drain                            Closed ON PRIMARY SERVICE BED DI-DI-1            From pool                       Closed DI-2            From reactor                    Open DI-3            Sluice inlet                    Closed DI-4           To pool                          Closed DI-5           To reactor                       Open DI-6            Sluice outlet                   Closed DI-7           Air supply                       Closed DI-8            Vent                            Closed DI-9            Drain                           Closed STANDBY COLUMN DI-DI-1            From pool                       Closed DI-2            From reactor                    Closed DI-3            Sluice inlet                    Closed DI-4            To pool                         Closed DI-5           To reactor                       Closed DI-6            Sluice outlet                   Closed DI-7            Air supply                      Closed DI-8            Vent                            Closed DI-9            Drain                           Closed            ,

4 New 7/29/93 App'd NM SOP /A-22d I

i l l l STANDARD OPERATING PROCEDURES 2nd Edition, Effective Date: 5/2/89 1 (Revisions #1 through #24 to the October 1981 printing were incorporated.) , i Revision Number 11 Revision Date: 8/31/93 1 Pace Number Date List of Effective Page, y - vi 8/31/93 SOP /III-9 8/31/93 SOP /III-10 7/29/93 SOPNII-11 7/29/93 SOPNII-12 8/31/93 SOPNIII-11 5/2/89 , SOPNIII-12 8/31/93 b II-3

LIST OF EFFECTIVE PAGES,2ND EDITION (Revisions #1 through #24 to the October 1981 printing have been incorporated.) Pace Number Date Revised Pace Number Date Revised Title Page 5/2/89 SOPAl-8 8/14/89 Assignment Sheet 5/2/89 SOP /II-9 10/18B0 Revision No & Date Page 5/2/89 SOPAI-10 5/2/89 Table of Contents: SOPAI-I1 5/2/89 i 7/29S 3 SOPAI-12 5/2/89 il 7/29 S 3 SOPSI-13 8/14/89 iii 7/29B3 SOP /ll-14 1/16S 0 iv 7/29S3 SOPA!-15 1/16SO List of Effective Pages: SOPSI-16 10/18 S 0 v 8/3163 ) SOPall-1 10/18S 0 vi 8/31S3 1 SOP /lil-2 8/27S 2 vii 7/2933 SOPSII-3 8/27B2 viii 7/2993 SOPMIl-4 8/27B2 SOPA-1 7/29 S 3 SOPAll-5 8/27 S 2 SOP /I-2 7/29/93 SOPMII-6 8/27S2 SOP /I-3 7/29 S 3 SOP /III-7 5/2/89 SOPA-4 7/29S3 SOPAll-8 New 8/27S2 SOP /I-5 5/2/89 SOPAII-9 8/31 S 3 ) . SOPS-6 5/2/89 SOPAll-10 7/29B3 SOPA-'7 5/2/89 SOPAll-11 Reset 8/27S 2 SOP /I 8 5/2/89 SOP /III-12 Reset 8/27S 2 SOPM-9 8/14/89 SOP /IV-1 10/0/81 SOP /I-10 5/2/89 SOP /IV-2 5/2/89 SOPA-11 10/18SO SOPAV-3 10/0/81 SOPA-12 8/14/89 SOP /IV-4 5/2/89 SOPA 13 8/14/89 SOPAV-5 10/0/81 SOPA-14 8/14/89 SOPAV-6 5/2/89 SOP /I-15 8/14/89 SOP /V-1 5/2/89 SOPA-16 7/29B3 SOP /V-2 5/2/89 SOPA 17 7/29 S 3 SOP /V-3 8/14/89 SOPA 18 7/29 S 3 SOP /V-4 1/16SO SOPA-19 10/18SO SOP /V-5 5/2/89 SOPM-20 10/18SO SOP /V-6 1/16/90 SOPA-21 10/18 S 0 SOP /V-7 1/16B0 . SOPA-22 10/18SO SOP /V-8 1/16SO SOP /I-23 10/18SO SOP /VI-I 4/30S 1 SOPA-24 10/1880 SOP /VI-2 1/16SO SOP /Il-1 5/2/89 SOP /VI 3 5/2/89 SOPAI-2 5/2/89 SOP /VI-4 5/2/89 , SOPSI-3 5/2/89 SOP /VI-5 5/2/89 SOPAI-4 5/2/89 SOP /VI-6 4/30S 1 SOP /II-5 10/0/81 SOP /VI-7 7/29S 3. SOPAI-6 5/2/89 SOP /VI-8 7/2993 SOPAI-7 12/16/89 Rev. 8/31/93 App'd b

LIST OF EFFECTIVE PAGES,2ND EDITION (Revisions #1 through #24 to the October 1981 printing have been incorporated.)

 . Pace Number                      Date Revised       Page Number                            Date Revised SOP /VII-I                            10/0/81       SOPNIll-7                                  10/18SO SOP /VII-2                            4/30S 1       SOP /VIII-8                                   5/2/89 SOP /VII-3                           10/18S 0       SOP /Vlil-9                                   5/2/89 SOP /VII-4                            7/29S 3       SOP /VIII-10                                  5/2/89 SOP /VII-5                            7/29S3        SOP / Vill-11                                 5/2/89 SOP /VII-6                            7/29 S 3      SOP / Vill-12                               8/31B3                              ]

SOP /VII-7 7/2993 SOP /VIII-13 7/29S3 SOP /VII-8 7/29 S 3 SOP /VIII-14 7/2983 SOP /VII-9 7/29 S 3 SOP /VIII-14a 7/29B3 SOP /VII-10 7/29S3 SOPNIll-15 5/2/89 SOP /VII-11 7/29 S 3 SOP /VIII-16 7/29S3 SOP /Vil-12 8/3193 ) SOP /VIII-17 7/29B3 SOP /VII-13 7/29S 3 SOP / Vill 17a New 7/29S3 SOP /VII-14 7/29S3 SOP /VIII-18 5/2/89 SOP /VII-15 5/2/89 SOP /VIII-19 10/18B0 SOP /VII-16 5/2/89 SOP /VIII-20 5/2/89 SOPNil-17 5/2/89 - SOP /VIII-21 5/2/89 SOP /VII-18 5/2/89 SOP /VIII-22 5/2/89 SOP /Vil-19 5/2/89 SOP /VIII-23 5/2/89 SOP /VII-20 4/30S 1 SOP / Vill-24 5/2/89 SOP /Vil-~21 5/2/89 SOP / Vill-25 5/2/89 SOP /VII-22 10/18SO SOP /VIII-26 5/2/89 SOP /Vll-23 5/2/89 SOP /VIII-27 5/2/89 SOP /VII-24 5/2/89 SOP /VIII-28 5/2/89' SOP /VII-25 1/2S2 SOP / Vill-29 5/2/89 SOP /VII-26 1/2/92 SOP /VIII-30 5/2/89. SOP /VII-27 5/2/89 SOP /VIII-31 5/2/89 SOP /VII-28 5/2/89 SOP /VIII-32 5/2/89 SOP /VII--29 1/16SO SOP /VIII-33 8/14/89 SOP /VII-30 2/28S 2 SOP / Vill-34 5/2/89 SOP /VII-31 2/28S2 SOP / Vill-35 8/14/89 SOP /VII-32 2/28S2 SOP /VIII-36 5/2/89 SOP /VII 33 2/28S2 SOP /VIII 37 8/14/89 SOP /VII-34 New 8/2782 SOP /VIII-38 8/27S 2' SOP /VII-35 New 8/27S2 SOP / Vill-39 2/28S2 SOP /VII-36 New 8/2792 SOP /VIII-40 2/28S 2 SOP /VIII-I 10/0/81 SOP /VIII-41 5/2/89 SOP /VIII-2 10/1890 SOP / Vill-42 5/2/89 SOP / Vill-3 5/2/89 SOP /V111-43 7/29 S 3 SOP / Vill-4 5/2/89 SGP/ Vill-44 7/2983 SOP /VIII-5 5/2/89 SOP /VIII-45 7/29 S 3 SOP /VIII-6 5/2/89 SOP /VIII-46 7/16B1 vi Rev. 8/31/93 App'd M , t

'III.8 Check of Process Radiation Monitors III.8.1 Operational Check of Seccndary Coolant and Fission Product Monitors, respectively. A. Lower alarm setpoint until annunciator alarms. B. Place level switch up and adjust alarm setting to 10k cpm i 10% ] C. Lower alarm setpoint until annunciator alarms. D. Place level switch up and adjust alarm setting to 12k cpm i 10E ], III.8.2 Operational Check of Stack Monitor A. The operator conducting the test in the West Tower shall establish communication with the control room via the intercom B. Place the mode switch for the iodine detectorin the "T"(test) position. C. Verify that the iodine pen on the stack recorder and its local ] meter both read 3600 cpm i 10% (3240 to 3960), and that the ] stack monitor high activity annunciation is received. ] D. Return the iodine mode switch to the "N" position. E. Press the " reset" button until the iodine meter and recorder readings return to normal, do not drive them to the downscale position. Reset the annunciator. F. Place the mode switch for the particulate / gas monitor in the "T" position. G. Verify that the particulate and gas pens on the stack recorder and ] their local meters all read 3600 cpm i 10% (3240 to 3960), and ] that the stack monitor high activity annunciation is received. ] H. Return the particulate mode switch to "OP" position. I. Press the " reset" button until the particulate meter and recorder readings return to normal; do not drive it to the downscale position. Reset the annunciator. J. Test the low flow alarm in the control room by securing the blower. K. Return the blower switch to "on", verify "high" and " low" alarms cleared. Rev. 8/31/93 App'd M SOP /III-9 :

l III.9 Area Radiation Monitoring System - - The area radiation monitoring system will be in operation continuously and is to be-turned off only during maintenance on the system. When handling samples, or during maintenance, place the Bridge Upscale Switch in the upscale position. Ensure Bridge Upscale Switch is returned to normal position after handling samples. The station trip points shall be set as follows: Station 1 BP North Wall 2 X acceptable ~ background Station 2 BP West Wall 2 X acceptable background Station 3 BP South Wall 2 X acceptable background Station 4 Exhaust Plenum 1 mr/hr or 10 X normal operating background Station 6 Bridge ALARA 300 mr/hr alert 10K mr/hr alarm / trip Station 7 Bridge 50 mr/hr or 10 X normal operating background Station 8 Nuclepore 2 X normal operating background Station 9 Fuel Vault 2 X normal operating background Station 10 Room 114 2 X normal operating background , Station 11 Exhaust Plenum'#2 1 mr/hr or 10 X normal operating background At least once a month for stations 4,6,7 and 11, and once a quarter for the remaining stations, the system will be checked according to the following procedure: NOTE: GREEN Lamp serves as Normallight and Check Source actuating switch (push to actuate source). AMBER Lamp serves as Alert alarm (push to reset). RED Lamp serves as High alarm (push to reset). The alert has been set up on all ARMS units except for the Bridge ALAILL ] A. At station 1, operate the check source pushbutton and verify that when trip point is reached, the RED alarm lamp lights at the Electronic Channel, and the RED alarm lamp lights and the AUDIBLE alarm ' sounds at the Remote Alarm Unit. B. Repeat step A for Stations 2,3,8,9 and 10. Rev. 7/29/93 App'd M SOP /III-10 t

II.4.3 Providing DI Water to T-300 or the Facility Demineralized Water ] Tanks ] DI water may be sent to T 300 or the facility DI water tanks with or ] l without the use of the reverse osmosis unit as a DI-300 makeup supply. ! Due to the fact that DCW, after passing through the R.O. Unit, is much more pure than raw DCW, the R.O. Unit is normal 19 utilized to prolong the life of the DI-300 resin regeneration. However, there are provisions for bypassing the R.O. Unit when sending DI-300 water directly to DI-200 (see VII.4.3.3). VII.4.3.1 Providing DI Water to T-300 or the Facility DI Water Tanks with ] Reverse Osmosis Makeup A Culligan (Polishing) bed is used to augment the R.O. unit. A. Open: ]

1. RE 31 if supplying water to T 300. ]

2. DI-21 if supplying water to facility DI water tanks. ]

B. Place product water valve RO-10 to the DI water system position. NOTE: The handle points in the direction of the open port. C. Check open the following R.O. Unit valves: RO-1, RO-2, RO-5, RO-7, RO-8, RO-9 and RO-13. D. Open outlet valve (RO-11) from Culligan bottles. E. Open DI-5. F. Turn conductivity meter to "ON" and place auto valve switch to " AUTO" (first auto valve should open). If sending to T 300, place high level ] cutout switch to cutout if high level shutdown exists in facility ] DI tanks. ] G. Push the R.O. Unit start button. H. Push reset button under conductivity meter (second auto valve should open). There should be a 3 to 6 second delay before R.O. Unit starts. (Pressure should come up to 190 200 psig.) CAUTION: If valves do not open, the conductivity is at or above alarm setpoint. Place normal / bypass switch to " BYPASS". I. Flush R.O. Unit through DI-5 until conductivity falls below alann setpoint. J. Open auto valve isolation valve (DI-17) and shut DI-5. K. Place normal / bypass switch to " NORMAL" if required. L. Fill out the DI waterlog. Normally, the water inlet temperature will not require adjustment and is set at approximately 25 to 30 C. Allow at least 30 minutes of running time to stabilize temperature prior to determining if an adjustment is needed. Rev. 7/29/93 App'd M SOP /VII-11

c TO SECURE SENDING WATER ! l A. Push the R.O. Unit off button. B. Place auto valve switch to "CLOSE." Turn conductivity meter to ;

                   "OFF" (both auto valves should be closed).

C. Shut auto valve isolation valve (DI-17). D. Shut Culligan bottles discharge valve (RO-11). E. Place product water valve RO-10 to the flush or drain position. F. Shut: L RE-31 if supplying water to T-300. ]

2. DI-21 if supplying water to facility DI water tanks.

CAUTION: The following valves should be left open while the unit is OFF: RO-2 RO-7 RO-5 RO-8 RO-1 RO-9 RO-6 RO-13 G. Fill out the DI water log. When the unit is not in use, DO NOT UNPLUG, PLACE IN STANDBY ONLY. DO NOT SECURE SUPPLY WATER. NOTE: If for any reassa the unit must be turned off or the supply water secured, this condition MUST NOT exist for more than 60 hours or damage will occur to the filter membranes (see technical manual #476 for details). No regular maintenance is required to operate this unit. For any repair or

maintenance, refer to the technical manual.

VII.4.3.2 Providing DI Water to T-300 Without Reverse Osmosis Unit Makeup Transferred to SMP-22. VII.4.3.3 Providing DI Water to DI200 Units Using R300 Bed Transferred to SMP-22. t Rev. 8/31/93 App'd im SOPNII-12

C. Material which may be irradiated in the p-tube system-includes. water, plant and animal tissue and fluids, bone, -i air filters, soils, rocks, soil extracts, coal, paper, meteorites, fibers, dried paint, safe insulation and 91 ass. Pure elements, alloys. and compounds not exempted in D below may also be irradiated subject to the activity j limitations in A. D. Unless it is specifically authorized in the experimenter's RUR, the following materials will not be irradiated in the p.-tube system: E. 1. Natural uranium; ]

2. Special nuclear materials' as defined in Title 10, Part 70, Paragraph 70.4m of the Federal Code of Regulations (i .e., plutonium, uranium-233, or uranium enriched in isotope 233 or 235); !

3. Pure elements: Li , Na , K, Rb, Cs , Ca , Sr ' Ba , Hg , Os , ;

H, 0, F, Ne, Ar, Kr, Xe, and P;

4. Compounds: NH4 NO 3 , CaC 2 , Ca0, perchlorates, perman-ganates, Na20, and Na2 023 f

5. Materials which cherically react with water to produce undesirable quantities of heat and pressure; )

6. Any explosive, flammable, combustible, or toxic materials. -]

F. Capsules may be run shielded with cadmium or-boron (as ]' I boron, BC, or BN) but weight and time are restricted due I to the heat generated and their reactivity effect on the 3 reactor. The experimentar'shall take measures to insure l the heat generated can ba dissipated without causing damage to the rabbit or sample. The following limitations apply to shielded capsules in addition to the activity '{ limits of Section VIII.3.2'.A: l 1 Rev. 5/02/89 App'd MM SOP /VIII-11 -] l

                                                        ,-                  S  . .-

VIII.3.2. Sample Limitations (cont'd)

1. The authorized p-tube user will inform the control room he/she is going to run shielded capsules and will insert the rabbit so that the cap is on top when the rabbit is in the reactor.

2. Cadmium shielded capsules:

a. 5 or less grams of cadmium may be run for up to 30 minutes,

b. 50 or less grams of cadmium may be run for up to 10 seconds in Row 1 or 20 seconds in Row 2.

3. Boron shielded capsules:

NOTE: The weight limit is only on the toron, i.e., the carbon weight in BC does not count towards the weight limit.

a. The single boron shielded capsule with between 10 to 15 grams of boron may be run for up to 15 seconds in Row 1 or up to 20 seconds in Row 2.

b. The double boron shielded capsule with between 15 and 20 grams of boron may be run for up to 10 seconds in Row 1. .

G. Except for the boron or cadmium shielded samples, the controlling factor for determining the weight and time limits of a sample to be irradiated in the p-tube is the activity limitation of Section A.' If the activity limits do not further restrict a sample's size, the following I weightlimits shall apply:

1. For irradiation times up to 30 minutes, the maximum weight of ,

irradiated materials in one rabbit will be 2 grmns with two exceptions:

a. A maximum of 10 grams of water or dried feces;

b. Only 1 mg of chemical compoun'ds in solution.

2. Forirradiation times of 30 minutes to I hour, the maximum weight ofirradiated materials in one rabbit will be 1 gram with two exceptions:

a. A maximum of 10 grams of water or dried feces;

b. Only 500 pg of chemical compounds in solution. ]

Rev. 8/31/93 App'd lN1 SOP /VIII-12

l l i MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES l Revision Number 13 Revision Date: 7/8/93 Section Page Number Number Table of Contents i List of Effective Pages i SEP-2 1of5 SEP-2 4 of 5 SEP-3 4 of 6 SEP-3 5 of 6 SEP-7 1 of 4 SEP-7 2 of 4 SEP-10 1of2 SEP 1of2 SEP-11 2 of 2 Emergency Call List FEP Table of Contents ! FEP Alarm & Response Table FEP-1 2 of 7 FEP-1 4 of 7 FEP-1 5 of 7 FEP-3(a) 1of2 f t I t 7 II-4 1

EMERGENCY PROCEDURES - SEP/FEP SECTIONS TABLE OF CONTENTS I. SITE EMERGENCY PROCEDURES (SEP) Pages SEP-1 Activation of Emergency Organization Procedure . . . . . . . . . . . . . . 1-5 SEP-2 Unusual Event Procedure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 SEP-3 Al e rt Proced ure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6 SEP-4 Site Area Emergency Procedure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6 ] SEP-5 Partial Site Area Evacuation Procedure . . . . . . . . .............. 1-2 . SEP-6 Emergency Air Sampling Procedure . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 SEP-7 Public Information Procedure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 SEP-8 Emergency Equipment Maintenance Procedure . . . . . . . . . . . . . . . . 1-3 SEP 9 Training Procedure for Emergency Preparedness . . . . . . . . . . . . . . . 1-2 SEP-10 Emergency Dosimeters for Off-Site Personnel . . . . . . . . . . . . . . . . . . 1-2 SEP-11 Monitoring Planned Exposures in Excess of Limits in 10CFR20 . . 1-2 ] EMERG ENCY CALL LIST . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . l only WORKSHEET A . . . . . . . . . . . . . . . . . . . . . ....... ............... 1 only. WO RKSHE ET B . . . . . . . . . . . . . . . . . . . . . . . . . . . . .................... l only WO R KSH E ET C . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 only WO RKS HE ET D . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 only WO R KS H E ET E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 only II. FACILITY EMERGENCY PROCEDURES (FEP) FEP Table of Co nten ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 only1 FACILITY EMERGENCIES - Classification of Facility Emergencies . . . . 1-2 FEP-1 Facility Evacuation Procedure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-7 FEP-2 Reactor Isolation Procedure . . . . . . . . . .................... 1-4 FEP-3 Fire Procedure . . ............................. .......... 1 only FEP-3(a) Control Room Response to Alpha Laboratory Fire . . . . . . . . . . . . 1-2 ] FEP-4 Medical Emergency Procedure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 UMH&C (Hosoital & Clinics) - RADIATION' DISASTER PLAN i Rev. 7/8/93 App'd M w

MURR EMERGENCY PROCEDURES - SEP/FEP SECTIONS LIST OF EFFECTIVE PAGES Page Date Page Date Section Number Number Revised Section Number Number Revised SEP/FEP T-C i 7/8/93 ] SEP-10 1 7/8/93 ) List of EfTective Pages 11 7/8/93 ) Orig. 2 6/24/85 SEP.1 1 2/10/87 SEP-11 1 7/8/93 ] 2 1/23/92 2 7/8/93 ] j 3 2/10/87 4 2/10/87 Emergency Call List 1 7/8/93 ] 5 6/24/85 l Worksheet A 9/28/92 , SEP-2 1 7/8/93 ] Worksheet B 1/8/85 ! 2 10/16/92 Worksheet C 1/23 S 2 I 3 1/23/92 Worksheet D 1/8/85 4 7/8/93 ] Worksheet E Orig. 6/24/85 5 2/4/93 FEP Table of Contents i 9/13 S 1 SEP-3 1 12/8/89 2 10/16/92 Facility Emergency 1 5/13/88 I 3 9/28/92 Procedure 2 7/8/93 ] 4 7/8/93 ] 5 7/8/93 ] FEP-1 1 3/22/90 - 6 2/4/93 2 7/8/93 ] 3 1/23/92 SEP-4 1 12/8/89 4 7/8/93 ] 2 9/28S 2 5 7/8/93 ] 3 9/28/92 6 7/11/90 4 5/13/88 7 7/11/90 5 1/8/85 I 6 2/4/93 FEP-2 1 7/3/85 2 1/23/92 SEP-5 1 1/8/85 3 1/23S 2 2 2/10/87 4 9/28/92 SEP-6 1 6/24/85 FEP-3 1 9/28/92 I 2 2/10/87 FEP-3(a) 1 7/8/93 ] SEP-7 1 7/8/93 1 2 9/13/91 2 7/8/93 ] 3 9/18/89 FEP-4 1 7/3/85 4 9/18/89 2 2/4/93 3 5/13/88 SEP-8 1 1/23/92 4 5/13/88 2 9/28/92 5 5/13/88 3 9/28/92 UMH&C (Hospital & Clinics) SEP-9 1 1/23/92 Emergency Center Radiation Disaster Plan 2 1/8/85 Rev. 7/8/93 App'd M

Page 1 of 5 SEP-2 UNUSUAL EVENT PROCEDURE ACTIONS LEVELS: IE there is:

a. Report or observation of severe natural phenomenon.

b. Threats to or breaches of security. [See REACTOR EAERGENCY PROCEDURE (REP-22).]

c. Concentration of airborne radioactivity at the stack monitor exceeding 3800 MPC when averaged over 24 hours. [See REACTOR EMERGENCY PROCEDURE (REP-21).]

NOTE: Use Overlay I to determine extent of activity for iodine and particulate. Use Overlay II to determine extent of gaseous activity.

d. The projected concentration of airborne radiological effluents at the distance corresponding to the nearest site boundary exceeding 10 MPC when averaged over 24 hours.

e. Prolonged fire or explosion within the facility that can result in a release of radioactivity that would cause exposures of the public or staff approaching 1 rem whole body or 5 rem thyroid.

f. Other plant conditions exist that warrant ensuring emergency ]

personnel are available to respond to an emergency to prevent exposures of1 rem whole body or 5 rem thyroid to the public or staff. THEN at least an UNUSUAL EVENT condition exists. IMAEDIATE ACTIONS:

1. Activate the Facility Emergency Organization (FEO), as per ACTIVATION OF FACILITY EMERGENCY ORGANIZATION PROCEDU'RE. if not already activated.

2. Operations shall provide information to the EMERGENCY DIRECTOR /

EAERGENCY COORDINATOR.

3. If airborne activity is involved, continue with step 4. If not, go to step 7.

4. Time and date stack monitor chart for reference. ]

Rev. 7/8/93 App'd M ""***We*++m, _ *e = -wa

i 1 SEP-2 (Cont'd) Page 4 of 5 j l 1 CORRECTIVE ACTIONS: !

1. If airborne activity is involved, determine source of airborne radioactivity and try to reduce or climinate the source.

a. REACTOR (1) Check fission product monitor.

(2) Check room 114 ARMS. (3) Check pool for gas releases. (4) Check dose rate on room 114 filter bank. - ] Actions to Consider: (1) Sample primary (2) Procedure REP-20, Hich Activity Levels in Primarv (3) Reactor Isolation (FEP-2) (4) Area Evacuations (5) Port.able air monitor in room 114

b. REACTOR EXPERIMENTS (NUCLEPORE, BEAMPORTS, P-TUBES)

(1) Check ARMS (2) Check changes on off-gas recorders when securing P-tube blowers. (3) Check Nuclepore alarm. (4) Check air monitors on beamport floor. Actions to Consider: (1) Perform air samples with portable monitor. (2) Shut down experiment. (3) Shut down reactor. * (4) Reactor Isolation

c. HOTCELL (1) Check dose rates at hoteell filter bank. ]

Actions to Consider: (1) shut hoteell valve. 1 Rev. 7/8/93 App'd M

l SEP-3 (Cont'd) Page 4 of 6 l i l CORRECTIVE ACTIONS:

1. If the facility was evacuated in Step 8 ofIMMEDIATE ACTIONS, continue. ,

IF NOT, go to step 2. !

a. Commence external surveys of the reactor laboratory building to detect leakage of airborne radioactivity and locate the source radioactivity,

b. Commence air sampling at 400 meters downwind offacility as per ;

EMERGENCY AIR SAMPLING PROCEDURE (SEP-6). ]

c. Evaluate results of surveys to determine possible reentry to parts of facility for further investigation, if necessary.

d. IE leakage concentrations exceed 19,000 MPC averaged over 24 hours, the EMERGENCY DIRECTOR should consider evacuation of USDA, Science Instrument Shop, Dalton Research Center, and Blood Bank, as per SITE AREA EVACUATION PROCEDURE (SEP-5).

IF NOT. EMERGENCY DIRECTOR should evaluate de-escalating to UNUSUAL EVENT classification.

2. Determine source of airborne radioactivity and try to reduce or eliminate the source.

a. REACTOR (1) Check fission product monitor.

(2) Check room 114 ARMS. (3) Check pool for gas releases. (4) Check dose rate on room 114 filter bank. ] Actions to Consider: (1) Sample primary (2) Procedure REP-20, High Activity Levels in Primarv (3) Reactor Isolation (FEP-2) (4) Area Evacuations (5) Portable air monitorin room 114 P Rev. 7/8/93 App'd M l

^'

___i M ~~ 1 1_ _ . _ _ _ _ _ _ _ . .,

SEP-3 (Cont'd) Paga 5 of 6 j

b. REACTOR EXPERIMENTS (NUCLEPORE, BEAMPORTS, P-TUBES) . l (1) Check ARMS l (2) Check changes on off-gas recorders when securing P-tube blowers.

(3) Check Nuclepore alarm. (4) Check air monitors on beamport floor. Actions to Consider: (1) Perform air samples with portable monitor. (2) Shut down experiment. (3) ReactorIsolation

c. HOTCELL (1) Check dose rates at hoteell filter bank. ]

Actions to Consider: (1) Shut hotcell valve,

d. LABORATORIES (1) Determine which laboratory is the source of release, by checking radiation levels in quadrant exhaust ducting.

(a) Southwest Quadrant (b) Northwest Quadrant (c) Northeast Quadrant Actions to Consider: (1) Throttle flow from laboratory quadrant to reduce release rate to less than Technical Specification's limits. (2) Area Evacuations Rev. 7/8/93 App'd b

Page l of 4 SEP-7 PUBLIC INFORMATION PROCEDURE i NOTE: The MU News Bureau shall be activated to handle the release of public information as required in the ALERT or SITE AREA EhERGENCY procedures; whenever offsite emergency assistimce is requested via 911; or whenever deemed appropriate by the EhERGENCY DIRECTOR. A. INITIAL RELEASE OF PUBLIC INFORMATION

1. The Emergency Status Report shall be completed and approved by the EMERGENCY DIRECTOR.

2a. During normal University ofEce hours, activate the MU News Bureau by i calling 882-6211, 882-6214 (Ken Brogdon) or 882-6217 (Jim Muench). ] 2b. At other times, call the following list of MU News Bureau staffin order until one of the individuals listed is reached (NOT their spouse, children, etc.).

1) Ken Brogdon 442-5260 ]

2) Jim Muench 443-0879 ] i

3) Connie Mitchell 442 616G ] l

3. Read the Emergency Status Report as approved by the EMERGENCY DIRECTOR to the MU News Bureau staff member and answer any !

questions concerning definitions, terms, units, etc.

4. Record other questions that the MU News Bureau staff member may have. 4 Enter the name of the MU News Bureau staff member contacted and give !

the completed report to the EAERGENCY COORDINATOR to be kept with l the records of the EhERGENCY. l I j l l l l Rev. 7/8/93 App'd M I i - - _ _ _ . _ . . _ . _ ~ . _ _

SEP-7 (Cont'd) Page 2 of 4

5. The MU News Bureau staff member contacted should verify a call concerning an emergency at the University of Missouri Research Reactor by calling 882-4211 or 874-4119 and asking to speak to a member of the Facility Emergency Organization (FEO). If the person answering the phone does not know who is in the FEO, then ask for anyone from the Director's OfHee, Operations, Health Physics / Reactor Chemistry groups. The individuals in these groups are listed below in alphabetical order. After verifying the person's identity by asking for his social security number, the emergency call can be verified.

VERIFICATION LIST FOR MURR EMERGENCIES Name Soc. Sec. No. Name Soc. Sec. No. Chuck Anderson Charlie McKibben Rex Ayers Walt Meyer Joe Baskett Steve Morris Rita Bonney Paul Muren Kenneth Beamer Phil Neel Barry Bezenek Willy Oldham Chester Edwards Dave Peeler John Ernst Derek Pickett Christine Errante Leslie Powell Les Foyto BillReilly John Fruits Tony Schoone Greg Gunn Jim Schuh Andrew IIartweg ] Tom Seeger Robert Hudson Andrea Shipp

      .Rolly Hultsch                             Vickie Spate Brenda Johnson                             Ray Stevens Vernon Jones                               Nolan Tritschler Mike Kilfoil                               Robert Walker Ron Kitch                                  Mike Wallis Sue Langhorst                              Tim Warner

6. MU News Bureau personnel contacted will determine the need for stalling and equipping an emergency information center and will callin the required staff and arrange for necessary facilities.

7. MU News Bureau personnel willinform news media and others of the public, as necessary, of the emergency.

8. If possible, a MU News Bureau staff member will be sent on site to assist the EMERGENCY DIRECTOR vdth the release ofinformation.

Rev. 7/8/93 App'd M

Paga l of 2 SEP-10 EMEROENCY DOSBETERS FOR OFF SITE PERSONNEL PURPOSE This procedure provides for radiation dosimeters for off-site personnel responding to a call under the MURR Emergency Plan. PROCEDURE The EMERGENCY COORDINATOR will assign a person to issue self-reader pocket chambers (PC) and film badges to off-site personnel as they arrive at MURR. A supply of PCs and film badges are maintained in the lobby at the reception desk. A second supply is maintained in the Health Physics Office. A third ] source of PCs is the film badge racks in the hallway near the lobby. The PCs in the badge racks are assigned to individuals and these would be used only if the lobby and Health Physics Oflice supplies are inadequate. The film badges in the badge rack will not be assigned to off-site personnel. If the two badge supplies are inadequate, only a PC will be assigned and Health Physics willissue a spare film badge as soon as possible. Form SEP-10 Pocket Chamber and Film Badce Record will be stored at the reception desk. When PCs and film badges are issued to off-site personnel, the ] PC and badge identification will be recorded on the form. If time permits, other information indicated on the form will be recorded. In any cace, when the PC and badge are returned to Health Physics, the remaining information will be recorded. for permanent record and for evaluation by Reactor Health Physics OfIice. ; I i i i l

l l Rev. 7/8/93 App'd M

Page l of 2 ] SEP-11 MONITORING PLANNED EXPOSURES IN EXCESS OF LIMITS IN 10CFR20 NOTE: The EMERGENCY DIRECTOR must approve each volunteer to exceed exposure limits of 10CFR20. PURPOSE This procedure provides the guidelines for monitoring, dosimetry and records for persons who volunteer for lifesaving and accident mitigating activities which could result in planned radiation exposures in excess of 10CFR20 limits. GUIDELINES A. Emercency Exnosure Guidelines

1. A volunteer may be authorized to receive up to 75 rem to save human life.

2. A volunteer may be authorized to receive up to 25 rem to prevent radiation exposures to members of the general public in excess of the following Protection Action Guides (PAGs).

The Protective Actions for all classifications are based upon a PAG of 1 rem dose equivalent for whole body and 5 rem dose equivalent thyroid to members of the general public and MURR staff on-site. B. Personnel Selection Considerations

1. Individual is a volunteer (preferably 45 years or older).

2. Individual is familiar with the radiological consequences of emergency radiation exposures.

3. Women of childbearing age shall not take part (Reg. Guide 8.13).

C. Self-reader Dosimeters and Locations Tyre Range (mr) Jocation PC 0 - 200 Receptionist Desk - Lobby PC 0 - 200 Health Physics Office PC 0 - 200 Film Badge Racks PC 0 - 200 Emergency Lockers PC 0 - 200,000 Emergency Lockers ]- NOTE: PC = Self-reader Pocket Chamber Rev. 7/8/93 App'd Uh

l 1 l SEP-11 (Cont'd) Page 2 of 2 ] j PROCEDURE NOTE: Althoughitis preferable to perform and document the steps presented below prior to emergency workers receiving the exposure, the situation ; (e.g., lifesaving measures) may require the EMERGENCY DIRECTOR to verbally authorize the exposure and ensure completion of documentation when time permits.

1. Ensure that the dose rate in the task area is known or measurable.

2. Ensure that volunteer has assigned film badge.

3. Complete Worksheet E giving careful attention to item C considerations.

4. Assign the volunteer a self-reader pocket chamber or equivalent immediate readout monitor with a range double the anticipated total exposure for the assignment.

5. The EMERGENCY DIRECTOR or a delegate shall obtain the exposure recorded by the readout device at a frequency that ensures adequate ]

control to prevent exposures in excess of the planned limits for the volunteer.

a. The exposure received at each reading shall be recorded on Worksheet E.

FOLLOW-UP

1. Expedite processing of volunteer's film badge to verify total exposure as indicated by self-reading dosimeters.

2. Ifindividual's dose equivalent exceeds any 10 CFR 20 limits, they should be examined by a physician to detennine tha need, extent and nature ofmedical surveillance or' treatment.

REPORTING REQUIREMENTS Complete reporting requirements of10 CFR 20.403. Rev. 7/8/93 App'd OlktA

EPERGEtCYPROCEDURE EPERGENCY CALL UST Director's Office Health Phyales/Rx. Chemistry Emergency Support Organizations Phone No. Phorse No. J.Rhyne 442-4967 S. Langhorst' 442-3534 Phone No. i J. C. McKabben 442-6728 R. Stevens 442-2539 UMC Police 882-7201 ! J. Ernet 445-5621 J.Schuh 449-0992 R. Ayers 474-7907 Columbia Fire Deoartment 9-911 W. D. Pickett 474-0709 A. Shipp 442-4304 ] Reactor Operations UM Hosoital & Clinics Phone No. Facliitles Operations Emergency Services 882-6003 W. Meyer 442-7675 Phone No. Ambulance 882-6128 or 9-911 T.Schoone 443-8862 C. Edwards 443-7529 Walk-in (Emergency Center) 882-8091 R. Hultsch 442-6653 D. Peeler 316-848-2471 C Anderson 696-5506 K.Beamer 682-5499 B. Bezenek 445-5680 R. Kitch .875-0664) UMC Health Physics fOffice) 882-7221 G. Gunn 875-1162 C. Kribbs 682-3980 Dr. Phil Lee (Home) 445-5275 N. Tritschler 474-9388 T.Seeger 474-3891 Jamieson Shotts (Home) 474-2194 L Foyto 446-0491 J. Baskett 474-2046 David Spate (Home) 657-9450 J. Fruits 474-0774 A. Hartweg 445-1557 ] Staff Resource Personnel R. Hudson 445-6769 Phone No. MU News Bureau 882-6211 V. Jones 445-2543 S. Morris 445-4217 See Public Information Procedure 882-6214 P. Muren 874-0219 ) V. Spate 637-9450 for other phone numbers (SEP-7). or 882-6217 P. Neel 442 8693 C. Baskett 474-2046 W. Oldham 474-0987 M. Glascod 443-4172 R. Walker 443-0970 B. McCracken 449-7731 State Ernercency Manacement Acency (SEMA) -314-751 2748 l M. Wallis 696-1097 W. Oladiran 443-5658 T. Wamer 816-882-6740 D. Nickolaus 443-0502 G. Ehrhardt 445-3570 NRC Washinaton DC 301-951-0550 A. Ketring 657-9614 B. Yelon 445-8147 M. Kilfoil 449-2524] NRC Recion !!I 708-790-5500 S. Gunn 443-2125 L Krueger 442-0740 T. Storvick 445-4038 American Nuclear insurers 203-561-3433

  *On leave until January 1994.

Rev. 7/8/93 App'd

FACILITY EMERGENCY PROCEDURES TABLE OF CONTENTS Section No. Pace No. FEP Table of Contents i ] FACILITY EMERGENCIES 1-2 Classification of Facility Emergencies FEP-1 Facility Evacuation Procedure 1-7 FEP-2 Reactor Isolation Procedure 1-4 FEP-3 Fire Procedure 1 only FEP-3(a) Control Room Response to Alpha Laboratory Fire 1-2 FEP-4 Medical Emergency Procedure 1-5 UMH&C (IIosoital & Clinics) - RADIATION DISASTER PLAN i Rev. 7/8/93 App'd M

Page 2 of 2 FEP - DESCRIPTION OF RADI ATION ALARMS AND PERSONNEL RESPONSE Facility Staff Non-Staff System Responsible for Alarm location of Sensors Audible location Type of Alarm Personnel bsponse Personnel Response

1. Isolation System a. ManualSwitch in Throughout llorn A e Execute reactor isolation Execute reactor isolation ]

Control Room Containment plan plan

b. Air plenum (ARM)

(fifth level)

c. Reactor bridge (ARM)

d. Air plenum BU moniter

2. Evacuation System a. Control Room Throughout llorn A e Execute facility Execute facility ]

b. Front Imbby Facility evacuation plan evacuation plan

3. Particulate Monitor Variable in Containment Ieeal Bell and red Cause immediate area Vacate containment; I light t to be vacated and notify Notify Reactor ]

Reactor Operations Operations 1

4. Area Radiation Monitor a. South wall.BP Floor local; Control Rm Buzzer and Cause immediate area Vacate immediate area '

(ARM) b. West wall.BP Floor red light A to be vacated and notify ]

c. North wall.BP Floor IIealth Physics

d. Fuel Storage Room I

e. IIeat Exchanger Room .

5. Hand and Foot Monitors Basement exit (outer local Buzzer and Notify IIcalth Physics Notify IIealth Physics ]

corridor) Indication E E ] West corridor Local Buzzer and Notify IIealth Physics Notify IIcalth Physics ] red light E E ] C. Portal Monitor East Exit Iecal Bell and Notify IIealth Physics Notify IIealth Physics ] Indication E E ] A Bell or buzzer and red light in Control Room 1 O Flashing red light near containment entrance ] t Control Room annunciator buzzer and light ] O After normal working hours, notify Reactor Operations 1 Rev. 7/8/93 App'd %

l FEP-1 (Cont'd) Page 2 of 7 I. PERSONNEL WITH PREASSIGNED TASKS (Facility Emergency Organization Members) A. TMMEDIATE ACTIONS: The responsibility for the overall direction in the event of an emergency shall rest with the EAERGENCY DIRECTOR. In the event of a Facility evacuation during normal working hours, the following people shall report to the reactor lobby: the Facility Director, Associate Director, Reactor Manager, Manager of Reactor Health Physics / Reactor Chemistry, Machine and Electronics Shop Supervisors, and Duty Shift Supervisor. The responsibility for EAERGENCY DIRECTOR shall be assumed. The , EAERGENCY DIRECTOR shall ascertain the availability of personnel required to execute the emergency plan and shall appoint an EMERGENCY COORDINATOR. He shallinvestigate the cause of the alarm and the , magnitude of the incident, and shall direct those activities necessary to correct the emergency situation. After the emergency is terminated, he shall direct the procedures necessary to restore normal operation. The EMERGENCY COORDINATOR shall ascertain that the reactor ] containment building, the Facility laboratories, and the mechanical equip-ment room, and below grade areas, have been vacated and secured. He will have the laboratory ventilation fans secured. He shall maintain a roster of all persons released from the site by the EMERGENCY DIRECTOR. If die , pneumatic blower system was in use during the emergency, he shall insure that the samples being irradiated am returned to the laboratory and then have the blowers secured at the local lighting panel (#32). He shall ensure a record of the events following the emergency is maintained. The DUTY OPERATOR shall perform or have performed the following tasks before leaving contairunent: (Do NOT attempt to correct any abnormalities at this time.) A. Verify that the reacter has scrammed as indicated by the instrumentation. B. Verify that all shim rods have bottomed as indicated by the console lights. 1 C. Verify that the containment has sealed as indicated by the ventilation door and the exhaust valve lights. Rev. 7/8/93 App'd J\ pM

FEP-1 (Cont'd) Page 4 of 7 II. PERSONNEL WITHOUT PRE-ASSIGNED TASKS: (Staff other than Facility Emergency Organization members) A. IMMEDIATE ACTIONS:

1. Upon hearing the evacuation alarm, personnel shall proceed to points beyond the area bounded by the outer perimeter of the reactor laboratory .

building. "

2. TOUR GUIDES shall be responsible for the safe evacuation of visit'o rs in their charge from the Facility in accordance with the evacuation routes -

in this plan. VISITORS shall be monitored by Health Physics Technicians as per HP-20 before being released to leave the site.

3. EXPERIMENTERS who are conducting experiments in containment (including pneumatic tube users) shall render their experimental apparatus safe for unattended operation. They shall be responsible for the safe evacuation of visitors in their charge from the facility in accordance with the evacuation routes in this plan.

4. EVACUATION ROUTES (See the map of the routes on Page 5):

A. All personnel within the containment building will exit the containment building and proceed through the east door of the laboratory building and then go to the upwind parking lot. B. All laboratory personnel, support personnel, and guests exterior to the containment building will leave the fa:ility through the nearest exit (north, east, west, or south doors) and then proceed to the ] upwind parkinglot.

5. Once outside, personnel shall note the wind direction indicator at the top of the containment building east tower and proceed to the upwind parking lot.

B. SUBSEOUENT ACTIONS:

1. All staff oersonnel shall remain on standby, unless released by the ,

EMERGENCY DIRECTOR, to provide special services that may be . required to restore normal operation.

2. All staff personnel shall be monitored by Health Physics Technicians as per procedure HP-20 before being released to leave the site.

3. A roster of alreleased personnel will be maintained by the EMERGENCY COORDINATOR. ,

Rev. 7/8/93 App'd (lMrM

                  ~       ~
  ^

PEP-1 (cont'd) ' Page 5 of 7 (s T ! (

                       <                                                                       J

( ' ss L J

                                                                              '                N q                                                                          J qgRgbjN                              -

s 7 '\\ % NN N

                                                            ;f        N g
                                                  .l :'                   :>    r*

h i..-9 L 3 I > l E o C 2 3

                                                                         >                      c t           >
                                                >                        >.       C&

f "J 'hI ! g*g g gf !

lib "

0 04 M2B !

iE1 f i 7 = lM M - PWN PARKING

LOT Wh LJ EVACUATION ROUTES, RESEARCH' REACTOR FACILITY Rev. 7/8/93 App'd W_

Page 1 of 2 FEP-3(a) CONTROL ROOM RESPONSE TO ALPHA LABORATORY FIRE NOTE: Throughout this procedure continue to monitor stack exhaust monitor, Alpha Laboratory exhaust monitor (alpha-6) or Alpha Laboratory room monitor (alpha-3) for indication of airborne radioactivity, as appropriate.

1. If a fire is detected by fire alarm or reported in the Alpha Laboratory, the shift supervisor (or senior licensed person in control) will verify and call the ]

Columbia Fire Department.

2. The shift supervisor will activate the Facility Emergency Organization by page system (or after hours by Emergency Call List) and provide warning to ]

stay clear of facility basement.

3. The Emergency Director will determine nature and specific location of fire (i.e., if fire is in glove box or equipment exterior to glove box).

4. If fire cannot be put out immediately with local fire extinguishers, the reactor will be shut down to focus attention on the fire. ]

5. Ensure Alpha Laboratory doors are shut and personnel are out of the laboratory.

If no experimenter is present, call the on-call experimenter as soon as time . permits.

6. If there is a likelihood of the fire spreading through the ventilntion ]

system, secure EF-13 and EF-14 at breaker on the emergency distribution ] center (in northinner corridor).

7. Secure electrical power to Alpha Laboratory at following locations:

a. Breaker #13 or UPS #2 - in control room (this secures power to the argon glove box and deactivates the glove box exhaust valves in their ]

current position). ]

b. Breaker #17 on 120/208 V distribution center - in north inner corridor (tids secures power to LP-34 which will secure lights and receptacles).

c. Breaker #2 on emergency power panel -in north inner corridor (this secures power to ELP #2 outside Alpha Laboratory, which will secure Alpha Laboratory supply and exhaust fans). ~

8. - Secure ventilation supply fan SF-1, north RTAH, south RTAH, at MCC-3 and .

check closed all fire doors. Rev. 7/8/93 App'd Wih\

MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES Revision Number 14 Revision Date: 12/28/93 - Section Page Number Number List of Effective Pages ii SEP-1 1of5 SEP-1 4 of 5 SEP-1 5 of 5 i SEP-2 l of 5 SEP-2 5 of 5 SEP-3 1 of 6 SEP-3 2 of 6 ~! SEP-3 4 of 6 SEP-3 6 of 6 SEP-4 1of6 ,. SEP-4 2 of 6 SEP-4 4 of 6 SEP-4 6 of 6 SEP-7 1of4 SEP-7 2 of 4 { SEP-11 2 of 2 Emergency Call List ! Worksheet C FEP- Description of Radiation Alarms

      & Personnel Response                     2 of 2
                                                                   .{

FEP-1 1of7 FEP-2 1of4 l FEP-3(a) 1of2 -! FEP-3(a) 2 of 2 1 I l

                                                                    -l II-5                                  ,

l i l

s. - - a +r M ^' - pa .

MURR EMERGENCY PROCEDURES - SEP/FEP SECTIONS l LIST OF EFFECTIVE PAGES l Page Date Page Date Section Number Number Revised Section Number Number Revised l SEP/FEP T-C i 7/8/93 SEP-10 1 7/8/93 List of Effective Pages ii 7/8/93 Orig. 2 6/24/85-SEP-1 1 12/28/93 ] SEP-11 1 7/8/93 2 1/23/92 2 12/28/93 ] 3 2/10/87 4 12/28/93 ] Emergency Call List 1 12/28/93 ] 5 12/28/93 ] Worksheet A 9/28/92 SEP-2 1 12/28/93 ) Worksheet B 1/8/85 2 10/16/92 Worksheet C 12/28/93 ] 3 1/23/92 Worksheet D 1/8/85 4 7/8/93 Worksheet E Orig. 6/24/85 5 12/28/93 ] FEP Table of Contents i 7/8/93 SEP-3 1 12/28/93 ] 2 12/28/93 ) Facility Emergency 1 5/13/88 > 3 9/28/92 Procedure 2 12/28/93 ] 4 12/28/93 ] 5 7/8/93 FEP-1 1 12/28/93 ) ' 6 12/28/93 ] 2 7/8/93 3 1/23/92 SEP-4 1 12/28/93 ] 4 7/8/93 2 12/28/93 ] 5 7/8/93 ; 3 9/28/92 6 7/11/90 t 4 12/28/93 ] 7 7/11/90 $ 5 1/8/85 ; 6 12/28/93 ) FEP-2 _1 12/28/93 ] 1 2 1/23/92 SEP-5 1 1/8/85 3 -1/23/92 ' 2 2/10/87 4 9/28/92 . SEP 6 1 6/24/85 FEP-3 1 9/28/92 f 2 2/10/87 i FEP-3(a) 1 12/28/93 ] i SEP-7 1 12/28/93 ] 2 12/28/93 ] ! 2 12/28/93 ] l 3 9/18/89 FEP-4 1 7/3/85 4 9/18/89 2 2/4/93 t 3 5/13/88 SEP-8 1 1/23/92 4 5/13/88 2 9/28/92 5 5/13/88 t 3 9/28/92 ; UMH&C (Hospital & Clinics) i SEP-9 1 1/23/92 Emergency Center Radiation Disaster Plan > 2 1/8/85 , Rev.12/28/93 App'd M I

7 l

I l Page 1 of 5 l SEP-1 ACTIVATION OF FACILITY EMERGENCY ORGANIZATION PROCEDURE l L FACILITY EMERGENCIES:

1. The Facility Emergency Organization (FEO) shall be activated as per the Facility Emergency Procedures (FEP) for each FACILITY EMERGENCY CLASSIFICATION:

a) Facility Evacuation b) Reactor Isolation c) Fire d) Medical e) Security [ SAFEGUARDS INFORMATION AS PER 10CFR50.34(c)]

2. In addition to the procedures for each FACILITY EMERGENCY CLASSIFICATION, an assessment of off-site consequences shall be detennined.

II. EMERGENCIES WITH POSSIBLE OFF-SITE CONSEQUENCES:

1. The duty shift supervisor or individual authorized to assume the Emergency Director position shall determine the need to activate the FEO for emergencies with possible off-site consequences. This need will be based upon the action levels specified for the minimum classification, UNUSUAL EVENT. These action levels are:

a. Report or observation of severe natural phenomenon.

b. Threats to or breaches of security.

c. Concentration of airborne radioactivity at the stack monitor exceeding 20,000 AEC* when averaged over 24 hours. ]

d The projected concentration of airborne radiological effluent at the distance corresponding to the nearest site boundary exceeding 15 mrem whole body accumulation in 24 hours. -]

e. Prolonged fire or explosion with the facility that can result in a release of radioactivity that would cause exposures of the public or staff approaching 1 rem whole body or 5 rem thyroid.

f. Other plant conditions exist that warrant ensuring emergency ]'

personnel are available to respond to an emergency to prevent exposures of I rem whole body or 5 rem thyroid to the public or staff. _

AEC-Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Column 1. ]

Rev.12/28/93 App'd M

l { SEP-1 (Cont'd) Page 4 of 5 l TABLE I ACTION LEVELS FOR EMERGENCY CLASSES Unusual Event

1. Report or observation of severe natural phenomenon.

2. Threats to or breaches of security.

3. Concentration of airborne radioactivity at the stack monitor exceeding 20,000 AEC* when averaged over 24 hours. ]

4. The projected concentration of airborne radiological efIluent at the distance corresponding to the nearest site boundary exceeding 15 mrem whole body ]

accumulated in 24 hours. ]

5. Prolonged fire or explosion within the facility that can result in a release of radioactivity that would cause exposures of the public or stafTapproaching 1 rem whole body or 5 rem thyroid.

6. Other plant conditions exist that warrant ensuring emergency personnel are ]

available to respond to an emergency to prevent exposures ofI rem whole body or 5 rem thyroid to the public or staff. Mer.1

1. Concentration of airborne radioactivity at the stack monitor exceeding 100,000 AEC* when averaged over 24 hours. ]

2. The projected concentration of airborne radiological effluent at the distance !

corresponding to the nearest site boundary exceeding 75 mrem whole body ] accumulated in 24 hours. ]

3. Radiation levels at the distance corresponding to the nearest site boundary of 20 mrem /hr for 1 hour whole body or 100 rnrem thyroid dose.

4. Loss of physical control of the facility.

5. Other plant conditions exist with a level of significance of a major failure of fuel cladding, but primary and containment boundaries exist to reduce releases.

 *AEC Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Column 1.           1 Rev.12/28/93      App'd M

SEP-1 (Cont'd) Page 5 of 5 TABLE I (Cont'd) ACTION LEVELS FOR EMERGENCY CLASSES Site Area Emercency

1. Concentration of airborne radioactivity at the stack monitor exceeding 500,000 AEC* when averaged over 24 hours. ]

2. The projected concentration of airborne radiological efIluent at the distance corresponding to the nearest site boundary exceeding 375 mrem whole body ]

accumulated in 24 hours. ]

3. Radiation levels at the distance corresponding to the nearest site boundary of 100 mrem /hr for 1 hour whole body or 500 mrem thyroid dose.

4. Other plant conditions exist with a level of significance of major fuel damage and conditions that indicate actual or imminent failure of containment integrity and primary system integrity.

i I

AEC-Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Column 1. ]

Rev.12/28/93 App'd (1%M

Page 1 of 5 SEP-2 UNUSUAL EVENT PROCEDURE ACTIONS LEVELS: IE there is:

a. Report or observation of severe natural phenomenon,

b. Threats to or breaches of security. [See REACTOR EMERGENCY PROCEDURE (REP-22).]

c. Concentration of airborne radioactivity at the stack monitor exceeding 20,000 AEC* when averaged over 24 hours. [See REACTOR ]

EMERGENCY PROCEDURE (REP-21).] NOTE: Use overlays to determine extent of activity for iodine, ] particulate, and gas. ]

d. The projected concentration of airborne radiological effluent at the ,

distance corresponding to the nearest site boundary exceeding 15 mrem whole body accumulated in 24 hours. ]

e. Prolonged fire or explosion within the facility that can result in a release of radioactivity that would cause exposures of the public or staff approaching 1 rem whole body or 5 rem thyroid.

f. Other plant conditions exist that warrant ensuring emergency personnel are available to respond to an emergency to prevent exposures ofI rem whole body or 5 rem thyroid to the public or staff.

THEN at least an UNUSUAL EVENT condition exists. IMMEDIATE ACTIONS:

1. Activate the Facility Emergency Organization (FEO), as per ACTIVATION OF FACILITY EMERGENCY ORGANIZATION PROCEDURE. if not already activated.

2. Operations shall provide information to the Emergency. Director / Emergency Coordinator.

3. If airborne activity is involved, continue with step 4. If not, go to step 7.

4. Time and date stack monitor chart for reference. -

i

AEC-Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Column 1. 1 Rev.12/28/93 App'd M I l

l

SEP-2 (Cont'd) Page 5 of 5 CORRECTIVE ACTIONS: (Cont'd) ]

d. LABORATORIES (1) Determine which laboratory is the source of release by checking radiation levels in quadrant exhauset ducting.

(a) Southwest Quadrant (b) Northwest Quadrant (c) Northeast Quadrant Actions to Consider: (1) Throttle flow from laboratory quadrant to reduce release rate to less than Technical Specification limits. (2) Area Evacuations SUBSEQUENT ACTIONS:

1. Change stack filters when chart reading exceeds 3 x 105 cpm. Reevaluate chart reading to determine if release rate is increasing / decreasing. Record time of filter changeout. ,

2. Evaluate results of correction and subsequent actions to determine need to escalate /de-escalate the emergency classification.

3. Keep record of actions and evaluations and time they were done for documentation. Use procedure worksheets.

4. Notify NRC, Headquarters Operations Officer, Washington, DC ]

[301-951-0550] that an UNUSUAL EVENT has occurred within one hour ] i after eventis classified or reclassified. (Use Worksheet C)

5. Notify American Nuclear Insurers (ANI) [203-561-3433] that an UNUSUAL EVENT has occurred. (Use information in Worksheet C)

6. Notify State Emergency Management Agency (SEMA) [314-751-2748] that an UNUSUAL EVENT has occurred. (Use information in Worksheet C)

RECOVERY ACTIONS:

1. Evaluate potential radiological effects to on-site and off-site personnel before returning access to specific areas effected by UNUSUAL EVENT emergency.

2. Procedures shall be written and approved for handling significant recovery evolutions.

NOTE: During recovery operations, personnel exposures to radiation should be ! maintained with 10CFR20 limits. l Rev.12/28/93 App'd M

Page 1 of 6 SEP-3 - ALERT PROCEDURE ACTIONS LEVELS:

IE there is:

a. Concentration of airborne radioactivity at the stack monitor exceeding 100,000 AEC* when averaged over 24 hours. [See REACTOR ]

EMERGENCY PROCEDURE (REP-21).] NOTE: Use overlays to determine extent of activity for iodine, ] particulate, and gas. ]

b. The projected concentration of airborne radiological effluent at the distance corresponding to the nearest site boundary exceeding 75 mrem whole body accumulated in 24 hours. ]

c. Radiation levels at the distance corresponding to the nearest site boundary of 20 mrem /hr for 1 hour whole body or 100 mrem thyroid dose.

d. Loss of physical control of the facility. <

e. Other plant conditions exist with a level of significance of a major failure of fuel cladding, but primary and containment boundaries exist to reduce releases. -

THEN at least an ALERT condition exists. IMMEDIATE ACTIONS:

1. Activate the Facility Emergency Organization, as per ACTIVATION OF ,

EACRIILEMERGENCYARGANIZATION_PBQCERUBE, if not already activated. *

2. Operations shall provide information to the Emergency Director / Emergency Coordinator.

3. Time and date stack monitor charts for reference.

4. Shut down the reactor. l

AEC Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Colu2nn 1. 1 Rev.12/28/93 App'd M l 1

l

SEP-3 (Cont'd) Page 2 of 6 a IMMEDIATE ACTIONS: (Cont'd) ]

5. Send operator to west tower with radiation monitor to:

NOTE: Communicate by intercom, since the stack monitor is affected by portable radio RF.

a. Verify radiation background at stack monitor.

b. Verify control room readings.

c. Mark initial needle position on analog display with time for future analysis if control room display becomes inaccessible.

d. Verify flow rate through monitor to 5 1 SCFM. If not, use Worksheet A to determine stack monitor values.

6. Pull stack monitor filters and analyzec

( '

7. After determining radionuclide responsible and verifying concentrations greater than 100,000 AEC* (a) secure EF-13 and EF-14;(b) secure RF2, ]

SF2, RF1, SFI; (c) secure all individual vent fans.

8. The Emergency Coordinator shall evaluate the need for a partial or total ;

evacuation of the facility. NOTE: For facility evacuations or northeast quadrant evacuation, have sample countinginstrumentation removed to RPDB. (Ge-Li detector and dewer; High Rasolution Gamma Ray Spectrometer)

9. The Emergency Coordinator shall appoint and have a surveillance team check areas evacuated clear of personnel withiu 30 minutes.

NOTE: Emergency Director approval required for any voluntary radiation exposure in excess of10CFR20 limits. (Up to 75 rem for lifesaving, up to 25 rem to prevent exposure to members of general public in excess of I rem whole body and 5 rem thyroid.)

10. Determine the need for EMERGENCY SUPPORT ORGANIZATIONS and, if needed, activate them or place them on standby. See TABLE III, EMERGENCY SUPPORT ORGANIZATIONS.

    'AEC-Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Column 1.          ]

Rev.12/28/93 App'd M

U I SEP-3 (Cont'd) Page 4 of 6 l 1 CORRECTIVE ACTIONS:

1. If the facility was evacuated in Step 8 of IMMEDIATE ACTIONS, continue.

IF NOT, go to step 2.

a. Commence external surveys of the reactor laboratory building to detect leakage of airborne radioactivity and locate the source radioactivity.

b. Commence air sampling at 400 meters downwind of facility as per EMERGENCY AIR SAMPLING PROCEDURE (SEP-6).

c. Evaluate results of surveys to determine possible reentry to parts of facility for further investigation, if necessary.

d. IE leakage concentrations exceed 100,000 AEC* averaged over, ]

24 hours the Emergency Director should consider evacuation of USDA, Science Instrument Shop, Dalton Research Center, and Blood Bank, as per SITE AREA EVACUATION PROCEDURE (SEP-5). IF NOT. Emergency Director shoulo evaluate de-escalating to UNUSUAL EVENT classification.

2. Determine source of airborne radioactivity and try to reduce or eliminate the source.

a. REACTOR (1) Check fission product monitor.

(2) Check room 114 ARMS. (3) Check pool for gas releases. (4) Check dose rate on room 114 filter bank. Actions to Consider: (1) Sample primary (2) Procedure REP-20, Hich Activity Levels in PrimarX (3) Reactor Isolation (FEP-2) (4) Area Evacuations (5) Portab'2 air moniter in room 114

  *AEC-Air Effluent Concentiation as per 10CFR20, Appendix B, Table 2, Column 1.          1 Rev.12/28/93        App'd hm11 F

SEP-3 (Cont'd) Page 6 of 6 l l 4 SUBSEQUENT ACTIONS: l

1. Evaluate results of corrections and subsequent actions to determine need to l escalate /de-escalate the emergency classification.

2. Keep record of actions and evaluations for documentation. Use procedures and worksheets.

3. Notify NRC, Headquarters Operations Officer, Washington, DC ]

[301-951-0550] that an ALERT condition has occurred within one hour ] after eventis classified or reclassified. (Use Worksheet C)

4. Notify American Nuclear Insurers (ANI)[203-561-3433] that an ALERT ]

condition has occurred. (Use information in Worksheet C)

5. Notify State Emergency Management Agency (SEMA) [314-751-2748] that an ALERT condition has occurred. (Use information in Worksheet C)

RECOVERY ACTIONS:

1. Evaluate potential radiological effects to on-site and off-site personnel before returning access to specific areas effected by ALERT emergency.

2. Procedures shall be written and approved for handling significant recovery ;

evolutions. NOTE: During recovery operations, personnel exposures to radiation should be maintained within 10CFR20 limits. Rev.12/28/93 App'd ())#M

Page 1 of 6 SEP-4 SITE AREA EAERGENCY PROCEDURE , ACTIONS LEVELS: I E there is:

a. Concentration of airborne radioactivity at the stack monitor exceeding 500,000 AEC* when averaged over 24 hours. [See REACTOR ] i EMERGENCY PROCEDURE (REP-21).)

N

              ~ OTE: Use overlays to determine extent of activity for iodine,             ]

particulate, and gas. ]

b. The pr ojected concentration of airborne radiological effluent at the distance co:Tesponding to the nearest site boundary exceeding 375 mrem whole body accumulated in 24 hours. ]

c. Radiation levels at the distance corresponding to the nearest site boundary of100 mrem /hr for I hour whole body or 500 mrem thyroid 1 dose.

d. Other plant conditions exist with a level of significance of major fuel ;

damage and conditions that indicate actual or imminent failure of containment integrity and primary system integrity. THEN a SITE AREA EMERGENCY condition exists. IhBEDIATE ACTIONS:

1. Activate the Facility Emergency Organization, as per ACTIVATION OF FACILITY EMERGENCY ORGANIZATION PROCEDURE,if not already activated.

2. Operations shall provide information to the Emergency Director / Emergency Coordinator.

3. Time and date stack monitor charts for reference.

4. Shut down the reactor.

 *AEC-Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Column 1.           ]

Rev.12/28/93 App'd U JRM ,

e I SEP-4 (Cont'd) Page 2 of 6 - BDfEDIATE ACTIONS: (Cont'd) ]

5. Send operator to west tower with radiation monitor to:

NOTE: Communicate by intercom, since the stack monitor is affected by portable radio RF.

a. Verify radiation background at stack monitor.

b. Verify control room readings.

c. Mark initial needle position on analog display with time for future analysis if control room display becomes inaccessible.

d. Verify flow rate through monitor to 5 1 SCFM. If not, use Worksheet A to determine stack monitor values.

6. Pull stack monitor filters and analyze.

7.' After determming radionuclide responsible and verifying concentrations greater than 500,000 AEC* (a) secure EF-13 and EF-14; (b) secure RF2, ] SF2, RF1, SF1; (c) secure all individual vent fans.

8. The Emergency Coordinator shall evaluate the need for a partial or total evacuation of the facility.

NOTE: For facility evacuations or northeast quadrant evacuation, have sample counting instrumentation removed to RPDB. (Ge-Li detector and dewer; High Resolution Gamma Ray Spectrometer)

9. The Emergency Coordinator shall appoint and have a surveillance team check areas evacuated clear of personnel within 30 minutes.

NOTE: Emergency Director approval required for any voluntary radiation exposure in excess of 10CFR20 limits. (Up to 75 rem for lifesaving, up to 25 rem to prevent exposure to members of general public in excess of I rem whole body and 5 rem thyroid.)

10. Determine the need for EMERGENCY SUPPORT ORGANIZATIONS and, if needed, activate them or place them on standby. See TABLE IV, EMERGENCY SUPPORT ORGANIZATIONS.

 *AEC-Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Coluran 1.          ]

f Rev.12/28/93 App'd-t <- y l

SEP-4 (Cont'd) Page 4 of 6 CORRECTIVE ACTIONS: ,

1. If the facility was evacuated in Step 8 ofIMMEDIATE ACTIONS, continue.

IF NOT, go to step 2.

a. Commence external surveys of the reactor laboratory building to detect leakage of airborne radioactivity and locate the source radioactivity.

b. Commence air sampling at 400 meters downwind of facility as per EMERGENCY AIR SAMPLING PROCEDURE (SEP-6). ]

c. Evaluate results of surveys to determine possible reentry to parts of facility for further investigation, if necessary.

d. IEleakage concentrations exceed 500,000 AEC* averaged over ]

24 hours, the Emergency Director shall commence evacuation of USDA, Science Instrument Shop, Dalton Research Center, and Blood Bank, as per SITE AREA EVACUATION PROCEDURE (SEP-5). IF NOT. Emergency Director should evaluate de-escalating to ALERT classification.

2. Determine source of airborne radioactivity and try to reduce or eliminate the source.

a. REACTOR (1) Check fission product monitor.

(2) Check room 114 ARMS. (3) Check pool for gas releases. Actions to Consider: (1) Sample primary (2) Procedure REP-20, Hich Activity Levels in Primarv (3) Reactor Isolation (FEP-2) (4) Area Evacuations (5) Portable air monitor in room 114 AEC-Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Column 1. 1 Rev.12/28/93 App'd W

SEP-4 (Cont'd) Page 6 of 6 -

                                                                                           -1 SUBSEQUENT ACTIONS:

1. Evaluate results of corrections and subsequent actions to determine need to escalate /de-escalate emergency classification.

2. Keep record of actions and evaluations for documentation. Use procedures and worksheets.

3. Notify NRC, Headquarters Operations Officer, Washington, DC ] <

[3019510550] that a SITE AREA EMERGENCY condition has occurred ] within one hour after event is classified or reclassified. (Use Worksheet C)

4. Notify American Nuclear Insurers (ANI)[203-561-3433] that a SITE AREA EMERGENCY condition has occurred. (Use information in Worksheet C)

5. Notify State Emergency Management Agency (SEMA) [314-751-2748] that a SITE AREA EMERGENCY condition has occurred. (Use information in Worksheet C)

RECOVERY ACTIONS:

1. Evaluate potential radiological effects to on-site and off-site personnel before returning access to specific areas effected by the SITE AREA EMERGENCY.

2. Procedures shall be written and approved for handling significant recovery evolutions.

NOTE: During recovery operations, personnel exposures to radiation should be , maintained within 10CFR20 limits. Rev.12/28/93 App'd M

i Page 1 of 4 SEP-7 PUBLIC INFORMATION PROCEDURE NOTE: The MU News Bureau shall be activated to handle the release of public information as required in the ALERT or SITE AREA EMERGENCY procedures; whenever off-site emergency assistance is requested via 911; or whenever deemed appropriate by the Emergency Director.

A. INITIAL RELEASE OF PUBLIC INFORMATION 1

1. The Emergency Status Report shall be completed and approved by the Emergency Director. (The Emergency Director may consider having ]

the MURR Information Specialist act as communications link with ] MU News Bureau.) ] 2a. During normal University office hours, activate the MU News Bureau by calling 882-6211 (Rhona Williams) or 882-9144 (Connie Mitchell). ] 2b. At other times, call the following list of MU News Bureau staffin order until one of the individuals listed is reached (NOT their spouse, children, etc.).

1) Rhona Williams 449-1586 ]

2) Connie Mitchell 442-6166 ]

3. Read the Emergency Status Report as approved by the Emergency Director to the MU News Bureau staff member and answer any questions concerning definitions, terms, units, etc.

4. Record other questions that the MU News Bureau staff member may have.

Enter the name of the MU News Bureau stafrmember contacted and give the completed report to the Emergency Coordinator to be kept with the records of the emergency. Rev.12/28/93 App'd N I

SEP-7 (Cont'd) Page 2 of 4

5. The MU News Bureau staff member contacted should verify a call concerning an emergency at the University of Missouri Research Reactor by calling 882-4211 or 874-4119 and asking to speak to a member of the Facility Emergency Organization (FEO). If the person answering the phone does not know who is in the FEO, then ask for anyone from the Director's Office, Operations, Health Physics / Reactor Chemistry groups. The individuals in these groups are listed below in alphabetical order. After verifying the person's identity by asking for his social security number, the emergency call can be verified.

VERIFICATION LIST FOR MURR EMERGENCIES Name Soc. Sec. No. Name Soc. Sec. No. Chuck Anderson Walt Meyer Rex Ayers Brenda Montague ] Joe Baskett Steve Morris Rita Bonney Paul Muren Kenneth Beamer Phil Neel Barry Bezenek Willy Oldham Ronita Dinger ] Dave Peeler Chester Edwards Derek Pickett John Ernst Leslie Powell Christine Errante Bill Reilly Les Foyto Jim Rhyne ] John Fruits Tony Schoone Greg Gunn Jim Schuh Andrew Hartweg Tom Seeger Robert Hudson Andrea Shipp Rolly Hultsch Vickie Spate Vernon Jones Ray Stevens Mike Kilfoil Nolan Tritschler Ron Kitch Robert Walker Sue Langhorst Mike Wallis Charlie McKibben Tim Warner

6. MU News Bureau personnel contacted will determine the need for staffing and equipping an emergency information center and will call in the required staff and arrange for necessary facilities.

7. MU News Bureau personnel will inform news media and others of the pubbe, as .

necessary, of the emergency.

8. If possible, a MU News Bureau staff member will be sent on-site to assist the Emergency Director with the release of information.

Rev.12/28/93 App'd M

. SEP-11 (Cont'd) Page 2 of 2 PROCEDURE NOTE: Although it is preferable to perform and document the steps presented below prior to emergency workers receiving the exposure, the situation (e.g., lifesaving measures) may require the Emergency Director to verbally authorize the exposure and ensure completion of documentation when time permits.

1. Ensure that the dose rate in the task area is known or measurable.

2. Ensure that volunteer has assigned film badge.

f

3. Complete Worksheet E giving careful attention to item C considerations.

4. Assign the volunteer a self-reader pocket chamber or equivalent im. mediate readout monitor with a range double the anticipated total exposure for the assignment.

5. The Emergency Director or a delegate shall obtain the exposure recorded by the readout device at a frequency that ensures adequate control to prevent exposures in excess of the planned limits for the volunteer.

a. The exposure received at each reading shall be recorded on Worksheet E.

FOLLOW.UP i

1. Expedite processing of volunteer's film badge to verify total exposure as indicated by self-reading dosimeters.

2. Ifindividual's dose equivalent exceeds any 10CFR20 limits, they should be examined by a physician to determine the need, extent and nature of medical surveillance or treatment.

REPORTING REQUIREMENTS Complete reporting requirements of 10CFR20.2202. ] Rev.12/28/93 App'd (AATM

EMERGENCYPROCEDURES EMERGENCY CALL UST Director's Office Facilities Operations Emergency Support Organizations Phone No. Phone.No. Phone.No. J. Rhyne 442-4967 C. Edwards 443-7529 UMC Police 882-7201 J. C. McKibbon 442-6728 D. Peeler 816-848-2471 K. Beamer 682-5499 Reactor Operations R. Kitch 875-0664 Columbia Fire Deoartment 9-911 Phone.No. C. Knbbs 682-3980 W. Meyer 442-7675 T. Seeger 474-3891 T.Schoone 443-8862 J. Baskett 474-2046 UM Hosoital & C!ints R. Hultsch 442-6653 M. Richardson 446-1014 ] Emergency Services 882-6003 C. Anderson 696-5506 Ambulance 882-6128 or 9-911 B.Bezenek 445-5680 Staff Resource Personnel Walk in (Emergency Center) 882-8091 G.Gunn 875-1162 Phone.No. N. Tritschler 474-9388 S. Moms 445-4217 L. Foyto 446-0491 V. Spate 657 9450 UMC Health Physics (Office) 882-7221 J. Fruits 474-0774 C. Baskett 474 2046 Dr. Phil Lee (Home) 445-5275 A. Hartweg 445-1557 M. Glascock 443-4172 Jamieson Shotts (Home) 474-2194 R. Hudson 445-6769 B. McCracken 449-7731 David Spate (Home) 657 9450 V. Jones 445-2543 W. Oladiran 443-5658 P. Muren 874-0219 D. Nickolaus 443-0502 P. Neel 442-8693 G. Ehrhardt 445-3570 MU News Bureau 882-6211 W. Oldham 474-0987 A. Ketring 657 9614 See Public information Procedure for other 882 6214 R. Walker 443-0970 B. Yelon 445-8147 phone numbers (SEP-7). or 882-6217 M. Wallis 387-4859 ] M. Kilfoil 449-2524 T. Warner 816-882-6740 S.Gunn 443-2125 L. Krueger 442-0740 State Emercency Manaaement Aaency (SEMA) 314-751-2748 Health Physics /Rx. Chemistry T. Storvick 445-4038 Phone No. S. Langhorst* 442-3534 NRC Washinoton. DC 301-951-0550 R. Stevens 442-2539 J. Ernst 445-5621 J.Schuh 449-0992 NRC Reaion 111 708-829-9500] R. Ayers 445-0340 ] W. D. Pickett 474-0709 A. Shipp 442-4304 American Nuclear Insurers 203 561-3433

On leave until January 1994.

R sv. 12/28/93 App'd OM

WORKSHEET C CONTENTS OF INITIAI1 FOLLOWUP EMERGENCY MESSAGES TO

                          " HEADQUARTERS OPERATIONS OFFICER"                             ]

WASHINGTON, D.C. 301-951-0550 ]

1. Provide name, title, telephone number of caller.

2. Location of emergency event.

UNIVERSITY OF MISSOURI RESEARCH REACTOR (LICENSE R-103) ] AT COLUMBIA, MISSOURI

3. Description of emergency event and emergency class:

NOTIFICATION OF UNUSUAL EVENT, ALERT, or SITE AREA EMERGENCY Time of event classification The cause or initiating event, if known.

4. Date and time event started:

5. Status of reactor: e.g. shutdown, fuel damage.

6. Was there actual release of radioactive material? (estimate quantity) ,

i Has the release been terminated? I

7. What protective actions taken? e.g. evacuation of facility, site area evacuation !

8. What outside assistance is required? e.g. SEMA, Fire Department, Medical Facilities j 1

9. Are there any injuries? Are the injured contaminated?

10. Estimate impact of release? e.g., is general public expected to be affected?

i i EMERGENCY DIRECTOR-AUTHORIZATION TO CALL Rev.12/28/93 App'd %

Page 2 of 2 FEP - DESCRIPTION OF RADIATION AIARMS AND PEllSONNEl, RESPONSE Facility Staff Non-Stali System Responsible for Alarm location of Sensors Audible ineation Type of Alarm Personnel Response Personnel Response

1. Isolation System a. Manual Switch in Throughout llorn A e Execute FEP-2, llenc tor Execute FEP-2, Iteactor ]

Control Room Containment Isolation Procedure Isolation Procedure ]

b. Air plenum (ARM)

(fifth level) (2) ]

c. Reactor bridge (ARM) (2) ]

2. Evacuation System a. Control Room -(manual) Thmughout llorn A e Execute FEP-1, Facility Execute FEP-1. Facility ]

b. Front lobby (manual) Facility Evacuation Procedure Evacuation Procedure ]

3. Particulate Monitor Portable in Containment local Bell and red Cause immediate area Vacate containment; ]

light to be vacated and notify Notify Reactor ] Reactor Operations Operations

4. Area Radiation Monitor a. South wall-BP Floor Iecal; Control Rm Buzzer and Execute ItEP-4, liigh Vacate immediate area ]

(ARM) b. West wall-BP Floor red light A Itadiation le vel ]

c. North wall-BP Floor Procedure ]

d. Fuel Storage Room

e. Ileat Exchanger Room (114) ]

5. Iland and Foot Monitors Basement exit (outer Incal Buzzer and Notify llealth Physics Notify llealth Phyws corridor) Indication E E West corridor local Buzzer and Notify llealth Physics Notify llealth Physics red light E E

6. Portal Monitor East Exit local Alarm and Notify llealth Physics Notify llealth Physics ]

Indication E E A Buzzer and red light in Control Room ] O Flashing red light near containment entrance t Control Room annunciator buzzer and light O After normal working hours, notify Reactor Operations Rev. ]2/28/93 App'd Mhk

Page 1 of 7 FEP-1 FACTILITY EVACUATION PROCEDURE NOTE: An assessment of off-site radiological consequences shall be determined. This assessment may require escalating emergency response to a site emergency procedure (UNUSUAL EVENT, ALERT or SITE AREA EMERGENCY). ENTRY CONDITIONS:

1. The Facility Evacuation alarm is actuated manually from two locations:

a. the reactor control room, and

b. the lobby control center.

2. Situations that may warrant FACILITY EVACUATION include:

a. Security emergencies, such as a bomb threat.

b. A major facility fire.

c. Whenever airborne radioactivity is expected to exceed 50 AEC* ] '

throughout the facility.

d. This procedure may be used as part of a Site Emergency Procedure (SEP).

e. Other conditions occur that the Shift Supervisor determines warrant personnel evacuation from the facility. ;

i AUTOMATIC ACTIONS: ! The following events resalt from a Facility Evacuation alarm: l 1. The reactor scrams.

2. The containment ventilation system isolation doors close. i

3. The containment exhaust isolation valves close.

4. The facility horns sound.

5. The flashing red light exterior to the containment personnel airlock door is energized.

                                                      *AEC Air Effluent Concentration as per 10CFR20, Appendix B Table 2, Column 1.                                                                         ]

Rev.12/28/93 App'd M

Page 1 of 4 EEIMI REACTO. ISOLATION NOTE: An assessment of off-site radiological consequences shall be determined. This assessment may require escalating emergency response to a site emergency procedure (UNUSUAL EVENT, ALERT or SITE AREA EMERGENCY). ENTRY CONDITIONS:

1. A REACTOR ISOLATION is automatically initiated by either of two radiation monitors in the containment air exhaust plenum or a radiation monitor on the reactor bridge. They are activated at levels greater than 1 decade above background.

2. A REACTOR ISOLATION may be activated manually at the reactor control console.

3. Shutdowns that may warrant REACTOR ISOLATION include:

a. A prolonged Sre within containment.

b. Whenever airborne radioactivity levels are expected to exceed 50 AEC* ]

in containment.

c. This procedure may be used as part of a Site Emergency Procedure (SEP).

l

d. Other conditions occur that the Shift Supervisor determines warrant

          - personnel evacuation of containment.

AUTOMATIC ACTIONS: The following events result from a Reactor Isolation alarm:

1. The reactor scrams.

2. The containment ventilation system isolation doors close.

3. The containment exhaust isolation valves close.

4. The containment horns sound.

5. The flashing red light exterior to the containment personfiel airlock dox is energized.

i

AEC-Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Column 1. ]

Rev.12/28/93 App'd M j l f

Page l of 2 FEP-3(a) CONTROL ROOM RESPONSE TO ALPHA LABORATORY FIRE NOTE: Throughout this procedure continue to monitor stack exhaust monitor, Alpha Laboratory exhaust monitor (alpha-6) or Alpha Laboratory room monitor (alpha-3) for indication of airborne radioactivity, as appropriate.

1. If a fire is detected by fire alarm or reported in the Alpha Laboratory, the shift supervisor (or senior licensed person in control) will verify and call the Columbia Fire Department.

2. The shift supervisor will activate the Facility Emergency Organization by page system (or after hours by Emergency Call List) and provide warning to stay clear of facility basement.

3. The Emergency Director will determine nature and specific location of fire (i.e., if fire is in glove box or equipment exterior to glove box).

4. If fire cannot be put out immediately with local fire extinguishers, the reactor will be shut down to focus attention on the fire,

5. Ensure Alpha Laboratory doors are shut and personnel are out of the laboratory.

If no experimenter is present, call the on-call experimenter as soon as time permits.

6. If there is a likelihood of the fire spreading through the ventilation system, secure EF-13 and EF-14 at breaker on the emergency distribution center (in north inner corridor).

7 Secure electrical power to Alpha Laboratory at following locations:

a. Breaker #13 on UPS #2 -in control room (this secures power to the argon ] l l glove box and deactivates the glove box exhaust valves in their current '

position). 1

b. Breaker #17 on 120/208 V distribution center - in north inner corridor (this secures power to LP-34 which will secure lights and receptacles).

c. Breaker #2 on emergency power panel - in north inner corridor (this secures f power to ELP #2 outside Alpha Laboratory, which will secure Alpha Laboratory supply and exhaust fans).

Rev.12/28/93 App'd h

i FEP-3(a) (Cont'd) Page 2 of 2

8. Secure ventilation supply fan SF-1, north RTAH, south RTAH, at MCC-3 and check closed all fire doors.

9. Isolate Alpha Laboratory by closing supply damper (above vial cleaning hot cell),

and exhaust damper (overheat, after last exhaust filter bank), if possible.

10. The Emergency Director (or his delegate) should contact Fire Department outside of facility to provide specific information. ,

11. The Emergency Director will stay in contact with Incident Commander to coordinate fire fighting and life saving efforts.

12. Contact MU News Bureau to handle release of public information (SEP 7). ]

Rev.12/28/93 App'd M

HEALTH PHYSICS STANDARD OPERATING PROCEDURES (New manual issued 10/29/90) Section Pace Nos. Resision No. Resision Date . HP-27 1- 19 4 8/25/93 i i 7 i I

                                                                    -l 1

II I II-6 i I

_ .- ~ _. . _. . . _ . . . . . _ . i l SOP HP-27 Rev. 4 Page 1 of 19 ; Appr' d Date Auaust 25. 1993 Calibration of Sample Counting Systems l I. Policy Sample data that has a direct effect on radiation risk evaluation shall be counted with a calibrated instrument. II. Purpose l The purpose of this procedure is to establish a standard ! method for the calibration of the following counting systems: A. Canberra Model 2400 Alpha / Beta / Gamma System. i B. Baird Polyspec Research Spectrometer. C. Eberline Model BC-4 Beta Counter. D. Baird Polyspec Research Spectrometer - Computer J. Controlled. ] E. Tennelec LB-5100 Alpha / Beta. ') III. Procedure -- Canberra 2400 Aloha / Beta / Gamma System -) A. Determining the operating voltage: T

1. Use Pu-239 calibration source for alpha counting .;

only. i

2. Use SrY-90 calibration source for beta and simultaneous alpha / beta counting.

3. Place proper calibration source in planchet and load into elevator magazine. ,

4. Press [ ADVANCE) [ ADVANCE). ;

5. Press [ PLATEAU) . ,

6. Choose a time increment that will yield approximately 10,000 counts in the plateau.

7. Set discriminator window to 0, press [ ENTER].

6 l

l

SOP HP-27 Rev. 4 Page 2 of 19

                                               ' Appr' d            It'n6 Date        Auoust 25, 1993

8. With printer on line, a graph of the plateau curve will automatically print. Choose an operating voltage 50 volts above the knee of the curve.

NOTE: For simultaneous alpha / beta counting, III.B. and III.C. must be completed. For alpha or beta only, go to step III.D. B. Determining window setting:

1. Place beta calibration source in planchet and load into elevator magazine.

2. Press [ ADVANCE) [ ADVANCE). .

3. Press (WINDOW).

4. Select operating voltage determined in III.A.8.

above, press [ ENTER).

5. A graph of DISC vs COUNTS will automatically print. l Choose the DISC setting where counts go to zero. l

6. Optimum window setting is where 0.5-1.0% of beta counts are detected in the alpha-channel. To check the window setting, use the following steps: ,

a. Place beta calibration source in planchet and load into elevator magazine. -l

b. Press [ ADVANCE) [ ADVANCE).

c. Edit program 0 in the following manner:

(after selecting parameter press [ ENTER), if parameter is correct as shown just press (ENTER)). Press [ EDIT) [0] [ ENTER) PRESET COUNT: ~[999999) PSET TIME: [1.00) HIGH VOLTAGE: Select voltage determined in III.A.8. DISC WINDOW: Select setting determined in III.B.5. CHI-SQUARE ( 0=N,1=Y) : [0] ERROR (SIGMA) : [1.96) 1

']

w

                                                                                                                                    .H SOP                   HP-27 Rev         4         Page      3 of 19 ._

Appr' d Ir'rt 5Y Date Auoust 25, 1993-REPEAT #: [0) A EFFIC (%) : [0] l A CROSTLK (%) : [0] l A BKGND (CPM): [0]

                                     'B EFFIC (%) : [0]                                                                                ,

B BKGND (CPM): [0] BKGD TIME (M) : '0) ! VOL UNITS: [0] f VOL (EA) : [1.09) ! ACTIVITY UNITS: [1] ALARM (dpm/V): [200.0)

d. When editing is complete press [RUN) [0] 1

[ ENTER) [ COUNT).

e. Gross alpha and beta counts will print.

                                      ' Divide gross alpha counts into gross beta                                                      ,

counts. If the result is 0.5-1.0% the DISC- , 7 WINDOW is correct.

f. If it is not, go back to III.B.6.c., add 50 to i the current DISC WINDOW setting, and repeat ,

steps d. and e. If the result still does not meet the recommendations, repeat' steps c., d., and e., adding 50 to the DISC WINDOW each time until 0.5-1.0% of the beta counts fall into the alpha channel. C. Measure alpha crosstalk:

1. . Place alpha calibration source in planchet and load into elevator magazine.

2. Press [ ADVANCE) [ ADVANCE).

1

3. Edit program 0 using method described in III.B.6.c.

Enter values for high voltage and disc window , determined in. steps III.A. and III.B> above. i i

4. Press (RUN) [0]- [ ENTER) [ COUNT).

i

5. Gross alpha and; beta counts will print. Alpha ,

crosstalk is calculated using the following l equation: t

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

i l l t ) SOP HP-27 Rev. 4 Page 4 of 19 Appr' d b bn'T i Date Auoust 25. 1993 Crosstalk = beta counts / (alpha counts + beta counts) D. Chi-square test: 1 Use a combination alpha / beta calibration' source or repeat these steps with an alpha and/or a beta calibration source as needed. ;

2. Place calibration source in planchet and load into ;

elevator magazine. :

3. Press [ADVANCEJ [ ADVANCE).

4. Edit program 0 inserting the. values deteu ined in l steps III.A.-III.C., including the following t additional changes to the parameters set'in III.B.6.c.- ;

CHI-SQUARE (0=N ,1=Y) : [1] REPEAT #: [20]

5. Press [RUN) [0] [ ENTER]' [ COUNT). ,

6. The system will count the source 21 times. After' the last count, the chi-square value will print.

For 20 degrees of freedom, a chi-square value i between 11 and 27 is satisfactory. .

7. If the chi-square value is not satisfactory,. repeat section III.A. If the operating voltage has changed, repeat all parts of section III using the new high voltage value. If the operating voltage is the same as determined before,' repeat the steps in III.D. Should the results still be unsatisfactory, contact the Health Physics grou'p, l and do not use the instrument for sample counting.

E. Determining efficiencies: -

1. Place alpha and beta calibration sources in ,

separate planchets. Load the sources, one empty planchet to determine background, and the aluminum end disc into the elevator magazine.

2. Edit a program (normally program 5) in the-l J

SOP MP-27 Rev. 4 Page 5 of 19 Appr'd #3 Date Aucust 25, 1993 !

following manner: (after selecting parameter press [ ENTER), if parameter is correct as shown just press [ ENTER) ) ; Press [ EDIT) [ program #) [ ENTER) PRESET COUNT: [999999) PSET TIME: Select desired count time in minutes, (normally 5 minutes) HIGH VOLTAGE: Select voltage determined in III. A.8. DISC WINDOW: Select disc window determined in III.B. START SAMPLE: [0] ; STOP SAMPLE: [99) ERROR (SIGMA): [1.96) REPEAT #: [0] A EFFIC (%): [0] A CROSTLK (%) : Select value determined in III.C. A BKGND (CPM). [0] > B EFFIC (%) : [0] B BKGND (CPM): [0] BKGD TIME (M). [0] VOL UNITS: [0] VOL (EA): [1] ACTIVITY UNITS: [1] ALARM (dpm/V) : [200]

3. When editing is complete press [RUN) (program #)

[ ENTER) [ RESTACK).

4. Efficiencies are calculated from the following equation:

Efficiency = (Gross counts-bkgd) /4 Pi Source dpm S. If. efficiency differs from the previous value by greater than 10%, contact the Health Physics group. Previous values can'be found in the instrument log book. F. Editing counting program:

1. Choose counting program to be edited. Program 1 is ,

reserved for normal swipe counting, program 2-5 are , available for other sample counting procedures. I Enter parameters in the following manner: (after i l l l,

r:

SOP HP-27 Rev. 4 Page 6 of 19 Appr'd bn Date Auaust'25. 1993 selecting parameter press [ ENTER), if parameter.is correct as shown just press (ENTER]) Press [ EDIT) (program #) [ ENTER) PRESET COUNT: [999999) PSET TIME: Select desired count time in minutes HIGH VOLTAGE: select voltage determined in III.A.8. DISC WINDOW: Select dise window determined in III.B. 6 START SAMPLE: [0] STOP SAMPLE: [99) ERROR (SIGMA) : [1.96) REPEAT #: [0] A EFFIC (%): Select value determined in III.E. A CROSSTLK (%) : Select value determined in III.C. A BKGND (CPM) : Select value determined in III.E. B EFFIC (%) - Select value determined in III.E. B BKGND (CPM) : Select value determined in III.E. BKGD (M): Select. time used in III.E. VOL UNITS: [0] VOL (EA): [1] , I ACTIVITY UNITS: [1] ALARM (dpm/V). [200) G. See HP SOP 33 for sample counting instructions. IV. Erpredure -- Baird Polvsrec Research Soectrometer .) A. Determine plateau:

1. Switch power to off.

2. Adjust switches to following positions:

a. Scaler

1. Preset count /bs -- bs.

1

2. Background subtract -

all zeros. 1

b. Analyzer l

l

1. Diff./integr. -- integr.

l

2. Lower 1. -- 7. l 1

,d. & A A - , 5 ~ . + , - 4 -4, s.m.. p s - . ~.a <._,--us a

                                                                                                       -1 l
                                                                                                       -l l

1 SOP HP-27 Rev. 4 Page 7 of 19 App r' d bM Date Aucust 25. 1993

c. Amplifier ,

1. Coarse gain -- 1/32.

2. Fine gain -- 0.45,

d. Display Set to scal. 1.

1.

e. Timer:

1. Set switen to timer.

2. Time case -- 0.1 sec.

3. Preset time -- 10.

f. Control:

1. Manual / Automatic -- Manual. .

2. Off/drm -- drm.

g. High voltage:

1. Course H.V. -- 1.6 (Switch on back panel .

Caution: any change of this switch should be made while high voltage is in standby.).

2. Fine H.V. -- midrange.

3. On/ Standby -- Standby.

3. Switch power on.

4. Switch on/ standby to on.

S. Place calibration source under detector: Pu-239 for alpha counting or SrY-90 for beta or alpha + beta counting.

6. Press the start button.

SOP HP-27 Rev. 4 Page 8 of 19 Appr' d b'/86 Date Aucust 25. 1993

7. Increase high voltage stepwise until scaler shows a count rate.

8. Decrease high voltage one step.

9. Press stop button.

10. Switch off/drm to off.

11. Set time base to 0.1 minute.

12. Press start button. Take one minute counts, increasing the high voltage 100 volts after each count, until a plateau is reached and counts begin ]

to increase again. Plot a curve of high voltage vs counts per minute.

13. Proper. high voltage setting is approximately the middle of the plateau. Record value in instrument log book.

B. Scaler test function:

1. Adjust switches as described in IV.A.2. with the modifications in IV.A.10. and IV.A.11.

2. Press start.

3. After one minute scaler reading should be approximately 7200. Record value in instrument log book.

C. Chi-square test:

1. Switch printer to on.

2. Place calibration source in planchet. Load planchet on left planchet stand and press start.

When source is under detector switch" planchet changer to off.

3. Adjust switches as described in IV.A.2. with the modifications in IV.A.10. and IV.A.11.

4. Press the start button, allow calibration source to

                                                ,                             . . , . w       w

SOP HP-27 ,

Rev. 4 Page 9 of 19 l Appr' d bw6 1 i Date Auaust 25. 1993 , count 21 times then press stop button.

5. The chi-square is calculated from the following equation:

[ (ai- A)2 7 y~ = n A Where: A = average counting rate a = counting rate observed in any counting , interval n = number of observations X2

                    =    Chi-square value P

6. For 20 degrees of freedom, a chi-square value between 11 and 27 is satisfactory. If the chi-square value is not satisfactory, contact the Health Physics group.

D. Determining efficiencies: ,

1. Adjust switches as described in IV.A.2. with the following modifications:

a. Timer

1. Time base -- 0.3 .inute.

2. Preset time -- 50.

b. Control i

1. Manual / Automatic -- Automatic.

2. Off/drm -- off.

c. High voltage

1. Set value determined in IV.A. ,

i ,. n w.

, l l SOP HP-27 Rev. 4 Page 10 of 19 Appr' d M Date Aucust 25, 1993

2. Set up automatic planchet changer as follows:

4 Single / Recycle -- single,

b. Power switch -- on.

3. Place alpha and beta calibration sources in separate planchets. One the left planchet stand, '

load the ources, and an empty planchet to determ$ ekground.

4. Press start button on planchet changer. ,

5. Efficiencies are calculated from the following equation:

Eff-iciency = (Gross counts-Skgd) /4 Pi ' Source dpm Recor' alue in instrument log. ;

6. If effx.iency differs from the previous.value:by i I

greater than 10%, contact the Health Physics group. Previous values can be found in the instrument log - book. E. See HP-SOP 33 for sample counting instructions.

}-

V. Procedure -- Eberline BC-4 Beta Counter A. Chi-square test:

1. Load beta calibration source in planchet and close- i drawer.

2. Set count time to 1 minute.

3. Count source 21 times, record values. l

4. The chi-square is calculated from the following i equation:

                                                                                                                      -i i

[ (a;- A)2 x=n 2 A 1

                                                                                                                      'I
    ,                      _               _           . _ _ .       -_. _,         ,   -- _ -                   -l

SOP HP-27 Rev. 4 Page 11 of 19 Appr' d 'n # Date Auaust 25. 1993 Where:

A = average counting rate a = counting rate observed in any counting interval n = number of observations X2

                         =   Chi-square value

5. For 20 degrees of freedom, a chi-square value between 11 and 27 is satisfactory. If the chi- ,

square value is not satisfactory, contact the Health Physics group. B. Determining efficiency:

1. Load beta calibration source in planchet and close drawer.

2. Set count time to 5 minutes.

3. Press start. After count is complete record value ,

in instrument log. book in counts per minute.

4. Remove calibration cource, close drawer and count 1 background for 5 minutes. Record value in instrument log book in counts per minute. t

5. Efficiency is calculated from the following j equation: l l

Efficiency = (Gross counts-bkgd) /4 Pi source dpm ; a Record value in instrument log book. )

6. If efficiency differs from previous value by greater that 10% contact Health Physics group.

3 VI. Procedure -- Baird Polyseec - Comnuter Controlled 3 A. Determine-plateau:

1. Switch power to off. I

i SOP HP-27 L Rev. 4 Page 12 of 19

                               ' Appr' d             rm Date       Aucust 25. 1993

2. Adjust switches to the following positions: -) .*

a. Scaler ')

1. Preset count /bs -- bs. ]-

2. Background subtract -- all zeros. )

b. Analyzer ]

1. Diff./integr. -- integr. ]-

2. Lower 1. -- 7. ')

c. Amplifier ]

5

1. Coarse gain -- 1/32. ').

2. Fine gain -- 0.45. )

d. Display )

1. Set to scal. 1. ) i

e. Timer ]

1. Set switch to timer. ]

2. Time base -- 0.1 sec. )

3. Preset time -- 10. ] ,

f. Control ] ,

1. Manual / Automatic -- Manual. }

2. Off/drm -- drm. ]

r

g. High Voltage )

1. Coarse H.V. -- 1.6 (Switch on back panel, )

Caution: any change of this switch must be ] : made while the high voltage is in ] standby.) )

                             ~, - - - -

i SOP HP-27 Rev. 4 Page 13 of 19 . App r ' d Msb Date Aucust 25, 1993 i

2. Fine H.V. -- midrange. ]

3. On/ Standby -- Standby. ] ,

3. Switch power to on. )

4. Switch on/ standby to on. -) ,

Place calibration source under detector: Pu-239 for

5. )

alpha counting or SrY-90 for beta or alpha + beta ] counting. J' , 6. Press the start button. ']

7. Increase high voltage stepwise until scaler shows a ]

count rate. ] ,

8. Decrease high voltage one step. )

9. Press stop button. )

10. Switch off/drm to off. )

11. Set time base to 0.1 minute. )

12. Press start button. Perform one minute _ counts )

increasing the.high voltage 100 volts after each- ') count:until a plateau is reached and counts begin ] to increase again. Plot a curve of high voltage vs ] , counts per minute. ) l Adjust the high voltage to be about'50 volts above.

13. ]

the knee of the-curve plotted in 12 above. Record ] this value in the instrument log book. ]- B. Scaler test function: ). ,

1. Adjust switches as described in A.2-. with the ]

modifications in A.10. and.A.11. ]

7

2. Press etart. -)

.i

3. After one minute, scaler reading should be ] ,

l 1 i a r Y 'Y'9

SOP HP-27 Rev. 4 Page 14 of 19 Appr'd F5wsb Date Aucust 25. 1993 approximately 7200. Record value in the instrument ') , log book. '). j i C. Computer System Start-up: )

l. Place-the computer power switch to the on position. ]- )

The computer will go through its start-up-routine. )

2. At the DOS prompt type "DATE". Type the date )

MM-DD-YY and hit enter. ]

3. Type " TIME". Type the time 00:00 and hit enter. ')

l

4. At the DOS prompt type " SWIPE". .

This will initiate ) the swipe counting program and arrive at the main ] menu. ] l D. Chi-square test: ) 'l l

1. Place a SrY-90 source in the planchet. ). H l

2. From the main menu screen press "4" then hit enter. ) !

3. It will ask you to enter the count time per trial )

in seconds. Type 60 then hit. enter. .)

4. It will then prompt you to enter the number off ")

trials. Type 21 and hit enter. -)- ,

5. The system will now automatically perform the ]

chi-square test.. Once the test is completed the ) . chi-square value will be displayed on the screen. '-) Press shift and print screen button to obtain a ) printout of-this value. A normalized chi-square' J-value of 0.6 to 1.6 is necessary. If.the value is -) repeatedly outside of this range, tag the equipment ). 5

                     -for repair.                                                                  J'
                                                                           ~

E. Determining efficiencies: )

1. From the main menu type'2 to determine background. -).

It will prompt you for the count time. Type 300 ) . and hit enter. ) .

SOP HP-27 Rev. 4 Page 15 of 19 Appr' d bnsf Date Auaust 25. 1993 __ ,

2. After background is completed enter the counts per ] '

minute value in the instrument log book. )

3. Place a SrY-90 source in the planchet. ]

4. Hit enter once to return to main menu. Type 3 to )

determine efficiency. It will prompt you to enter ) count time in seconds. Type 300 and hit enter. )

5. The system will then count the source for the 300 -)

seconds. When the count is finished it will prompt ) a- you to enter the source activity in dpm. Type the ) activity for the most recent calibration of.the ) source being used and hit enter. ) t

6. The computer will automatically calculate the )

efficiency based on this activity. Record this ] efficiency value in the instrument log book. ) 1

7. To determine alpha efficiency, place =the alpha ]

source in the planchet. Press start on the sample ) changer. Wait for the sample changer to.stop. )

8. Set timer to preset time to 50. Press the start ]

button. )

9. After'the 5 minute count, record.the value in )

counts per minute in the log book. )

                                                                                                 ]-              !

10. Calculate the efficiency by taking (cpm-bkg) / source dpm. Record this value in the log book. )

11. If the efficiency value differs from the previous .)

value by greater than 10%, contact the Health

Physics group. Previous values can- be found in the . ) instrument log book. }- F. See HP SOP 33 for sample counting instructions. ); VII. Procedure -- Tennelec LB-5100 Aloha / Beta ) Note: For any of the following. steps, the key must be used ) , in the control panel tua place the ' panel in the PROGRAM ) position. Also, it is assumed that the unit has no samples on. ) it and you have removed the Group A sample carrier. )

                                                     . . _ - .           .            ~ . .             __.                                 _     _.    -_.

l l l 1 i SOP HP-27 . Rev. 4 Page 16 of 19 Appr' d #4 Date Auoust 25, 1993 , A. Determining the operating voltage. )

1. Use Pu-239 calibration source for alpha counting ]'

only.. -]

2. Use SrY-90 calibration source for beta counting )

only. ) .-

3. Place Group D planchet in the elevator magazine. ] ;

4. Place the' proper calibration source in an empty ]

sample planchet and load into elevator magazine. ]

5. Place the end planchet on top of the source -)

planchet in the elevator magazine. J-

6. Verify the switch and dial settings on the.TC 264A ]-

                                                                        -as follows:                                                                         )

Gain----64 Line Noise Discr.----Fully CCW ]

7. Verify the switch and dial settings on the TC 265A -)

as follows: )

Gain----16 Alpha Discr.----Fully CW. -) A+B Discr----Fully CCW .)

8. Press "Q" on the keyboard. This will initiate the-- ;]-

plateau program. ).

9. Enter 1 for the number of' samples. )

10. Enter D'for the group letter to be used. Ensure. J-that group D is set up to yield approximately ;)

10,000 counts in the plateau. (5.4 minutes for ] , 5460 dpm source) J-

11. Enter the starting voltage: 900 for beta 420 for ]

alpha. ]

12. Enter the ending voltage: 1800 for beta and 1080 ]'

for alpha. ) ,

13. Enter the step voltage: 30 volts for either alpha )

or beta. )~

                                                                            +m_____-.       - _ - - - -     .-n   - = - . , - ,     y         +-4

t SOP HP-27 - Rev. 4 Page 17'of'19 ; Appr' d bh Date Auaust 25. 1993 ;

14. The system will now automatically perform the ] .

plateau and print the.results. The results need to ] be graphed so that the knee of the curve can be J- l determined. The correct operating voltage is 50 ) volts above the knee of the curve. -]

15. To edit the high voltage, press V from the main ]

i menu. ]

16. Enter the new alpha high voltage and press enter. .]

17. Enter the new beta high voltage and press enter. ]

18. Press enter once again to complete editing. ] l Setting the Alpha Discriminator: } ,

B.

1. Place the SrY-90 source in position under the J-detector and perform a count. Reduce the Alpha. ]

Discriminator on the TC 26SA until 1% of the gross ] , beta counts are occurring in the alpha channel. ]

2. Perform ten one minute counts of the alpha source ]

and average the results. The crosstalk should'be ] less than.9% for Pu-239. ] l C. Chi-squared test: '] I i

1. Use a combination alpha / beta calibration source or ]

repeat these steps with an alpha-and/or a beta ] calibration source as needed. ] I

2. Place the Group B planchet into the' elevator' ..]

magazine. ] l

3. Place ~the proper calibration source into a planchet ']-

and place into the elevator magazine followed by ] > the END planchet. - ) .,

                                                                                                        ]    ;

4. Press B to begin.

5. It will ask you whether to use the first sample as ]

background. Enter N for no. ] a-

 .          -                                          . . . ~.           .

SOP HP-27 Rev. 4 Page 18 of 19 Appr'd bH'2N ; Date Auaust 25, 1993T

6. It will then ask you whether to print chi-square or ] y not. Enter Y for yes. ]L

7. The system will now perform a' chi-squared test and~

-)

print the results for 21 sample counts, one minute ) each. The print out will give you three numbers at. ]' the end of the last count. The first one is for. )- alpha, the second is for beta, and the third one . )- should be disregarded. }l

8. For the system to be operating properly the .)

chi-squared values for both alpha.and beta should ]' fall between 11.and 27. If the value of the -) chi-squared repeatedly falls outside~of this -) region, contact Health Physics and tag the unit-as ] OOC and do not use this unit for any sample assay. -) D. Determining efficiencies: )

1. Use alpha calibration source for alpha efficiency- )

determination. ] l

2. Use SrY-90 calibration source'for beta efficiency .)-

determination. ]

3. Place the Group C planchet in the elevator ..)'

magazine. -) l i

4. Place the alpha calibration source in a planchet l' and place into elevator. magazine-followed by the ) '

~ beta calibration source.followed by the background ] planchet and finally the.END planchet. ]

5. Press ADVANCE on the control panel. ')

6. The system will now automatically count each sample )

5 minutes for determining efficiencies. -)-

7. Efficiencies are calculated from the following. ')

equation: ]- Efficiency = (Gross cpm-bkgd cpm) /4 Pi Source dpm ) l

y.

SOP HP-27 t Rev. 4 Page 19 of 19 App r' d - b' M f Date Auaust 25, 1993

8. If the efficiency differs from the previous value l' i by greater than 10%, contact the Health Physics ]

Group. Previous values can be found in the ] instrument data book. ] , E. Editing counting program: -]

1. Once the background and efficiency information l's ]

determined, the results need to be entered into the ] : counting program. Press G for Group. ]. ;

2. The normal simultaneous counting program is ]

assigned to Group A. Press A for Group A. ] s;

3. To edit the alpha efficiency (Ka) enter 9. ]

4. Enter the new alpha efficiency in decimal form. -]-

i.e. 35% as 0.35. ] .

5. To edit the beta efficiency (Kb) enter 10. ]

6. Enter the new beta efficiency in decimal form. ]

7. To edit the alpha background enter 6. ]

4

8. Enter the new alpha background in cpm. ]

9. To edit the beta background enter 7. ']

10. Enter the new beta background in cpm. ]. l s

11. Once finished with all editing, hit. enter one'more ]

time. .This completes the editing'section and ]i

                           -stores.all'of the'information.N,                                                 ]

Once'all operations are completed for any section of

NOTE: ] this procedure the key on the contro1~ panel must'be placed in ) the PROTECT position and removed from the control panel. ~ The -] key will be stored in the lock' box in the Health' Physics ] office. -]. ; F. See HP SCP 33 for sample counting instructions. ) a t

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

l MURR SHIPPING PROCEDURES l 1 Procedure Date Issued MURR-SAS-00000 4/13/93 > MURR-SAS 00002 4/15/93 MURR-SAS 00003 4/15/93 MURR-SAS-00004 2/17/93 MURR-SAS-00005 5/17/93 i i t II-7

l 1 MURR-SAS-00000 Service Applications Departmental Administrative: Shipping ' Procedure Cover Sheet MURR-SAS-00000 0 13 Acril 1993 (Procedure) (Revision) (Date) Service Annlications Decartmental Administrative: Shioning (Procedure Title) Prepared By (U' MT4v (Sigr(ature)

                                 !                 L Reviewed By           -  ti, + 8 4-4       ! A1 - NM              '

N ' (Signature) Revision Summarv Rev.# Dme Significant Summarv 0 13 April 93 Yes Original i

                                                                                    'l
                                                                                   .{

l Rev. O' SA / HP M Date 13 Anril 1993 MURR-SAS-00000 page 1 of 9 4 u

I

           . MURR-SAS-00000     Service Applications Departmental Administrative: Shipping TABLE OF CONTENTS SFCTION                                               PAGE NUMBER

1.0 Purpose and Scope

3 2.0 Precautions and Limitations 4 3.0 Definitions 5 4.0 Responsibilities 6 , 4.1 Reactor Services Engineer 6 4.2 Supervisor, Reactor Services 7 4.3 Shipping Technician (Shipper) 7 4.4 Shipper, Certified 7 , 4.5 Shipper, Qualified 7 4.6 Shipper, Trainee 7 4.7 Health Physics Manger 7 - 5.0 Procedure 8 References 9 f 1 1 4 4 4 r i 4 Rev. O SA II! HP Date 13 Aoril 1993 MURR-SAS-00000 page 2 of 9 ; 1 l

MURR-SAS-00000 Service Applications Departmental Administrative: Shipping ' SERVICE APPLICATIONS DEPARTMENTAL ADMINISTRATIVE: SHIPPING 1.0 PITRPOSE AND SCOPE The purpose of this Procedure is to delineate the responsibilities and to establish policies for radioactive material shipments entering or leaving the Service Applications Department, Shipping, Missouri University Research Reactor (MURR). To ensure Compliance with applicable Regulations of Code of Federal Regulations (CFR),10CFR,49CFR, and International Air Transport Association (IATA). Service Applications Department, Shipping's principal objective is to ship without error. 1.1 This Procedure applies to all permanent, part-time or student . personnel associated with Service Applications Department, Shipping. 1.2 All personnel assigned to Service Applications Department, Shipping, must abide by all associated Procedures, to include:

1.2.1 MURR-SAS-00000

Service Applications Departmental Administrative, Shipping.

1.2.2 MURR-SAS-00001

Not assigned, to be developed later.

1.2.3 MURR-SAS-00002

Hot Cell Preparation of Radioactive Material for Shipment.

1.2.4 MURR-SAS-00003

Hot Laboratory Preparation of Radioactive Material for Shipment.

1.2.5 MURR-SAS-OOOO4

Shipment of Radioactive Materials.

1.2.6 MURR-SAS-00005

Reload Radioactive Material. Rev. O SA db HP Date 13 Antil 1993 MURR-SAS-OOOOO page 3 of 9

n , MURR-SAS-00000 Service Applications Departmental Administrative: Shipping - 2.0 PRECAUTIONS AND LIMITATIONS 4 2.1 The non-fixed contamination on any external surface of the transfer cask, work tables or, tools must be kept as low as , practical. 2.1.1 The level of non-fixed radioactive contamination may be determined by wiping an area of the surface concerned with an absorbent material, using moderate pressure, and measuring the activity on the wiping material. 2.2 Ensure that all beta-gamma dose rate survey, contamination counting, and gamma radioisotope equipment calibration stickers have not passed the calibration due date prior to use. 2.3 Ensure that upon leaving the hot cell or hot laboratory area you measure for personal external contamination by use of' Hand-foot monitors or equivalent device. 2.3.1 When the Hand-foot monitor alarms indicating external contamination, call Health Physics immediately at extension

                         # 882-5217.

2.3.2 After 5:00 P.M. or Weekends call the Control Room ' at extension # 882-5213. 2.4 Maintain radiation exposure As Low As Reasonably Achievable (ALARA) by use of Time, Distance, and Shielding, e g: Do not ride down the elevator with the cask containing the samples removed from the Reactor pool. 2.5 Ensure that the transfer cask used to transfer the samples : from the Reactor pool to the hot cell is wiped and bagged to prevent contamination during its movement. 2.5.1 Examine poly bag for holes or tears. 2.5.2 Use Extreme Caution when removing the bag from the cask prior to placing the cask into the hot cell to prevent spread-of contamination. 2.5.3 Use Extreme Caution when placing the bag on the cask prior to moving the cask to a storage area' to prevent spread of contamination. Rev. O SA HP Date 13 Anril 1993 MURR-SAS-00000 page 4 of 9

L MURR-SAS-00000 Service Applications Departmental Administrative: Shipping 2.6 Use protective clothing:

Laboratory Coat
Rubber / Latex Gloves
Breathing Mask: Type to minimize ingestion / inhalation of particulate matter.
Safety Glasses or Face Shield.

2.7 In the event of a broken vial or stuck sample, the Reactor Services Engineer or Designee must be notified immediately to resolve the problem. 2.8 A package of radioactive material shall not be transported unless it is properly described, classed, marked, packaged and labeled. 2.9 if the Radioactive Material exceeds any of the applicable limits. of 49CFR or IATA Manual, the Reactor Services Engineer or Designee must be notified inunediately. 2.9.1 The Radioactive Material shall not leave MURR until the problem has been resolved. 3.0 DEFINITIONS

3.1 Activity

Is a measure of the quantity of radioactivity emitted by a radioisotope and is used to determine the amount of radioactive material which may be transported in various types of packaging. 3.2 Hot Cell: A sealed, shielded controlled area to process radioactive materials containing:

Manipulators to process radioactive materials.
A crane to move heavy objects.
A radioactive waste storage area.
Negative air pressure which exhausts to the Reactor Air Plenum.
A drain for liquid hot waste.
Can opener.
A welding unit.

3.3 Hot Laboratorv: A controlled area to process radioactive materials containing a hood which exhausts to the Reactor Air exhausts and a drain for liquids to hot waste. Rev. 0 . SA HP Date 13 Anril 1993 MURR SAS@0OO page 5 of 9

n , MURR-SAS-00000 Service Applications Departmental Administrative: Shipping'. 3.4 Observed An Independent Verifier who observes critical _' points of the processing steps and documents the performance of these steps by legibly initialing the steps as they are performed.

3.5 Performer

The individual who performs the critical step of the process and documents the performance of these steps by legibly initialing the steps as they are performed. 3.6 Radioactive Contents: The radioactive material together with any contaminated solids, liquids and gases within the package. 3.7 Radioactive material: Any material having a specific activity ' greater than 70 KBq/kg (0.002 uC1/g). 3.8 Shall. Must. Should:

3.8.1 Shall

Regulatory Commitment to Code of Regulations, 10CFR, 49CFR and IATA Dangerous Goods Regulations. 3.8.2 Musi: MURR Internal Commitment to 10CFR,49CFR and : IATA Regulations.

3.3.3 Should

Should be accomplished; not required. ; 3.9 Transfer Cask: Used to transport samples within the facility. 3.9.1 Orange Roll Up cask is included as a transfer cask. 4.0 RESPONSIBILITIES 4.1 Reactor Services Engineer: As Manager of the Service Applications Group, Shipping, is responsible for the overall administration of the Shipping Department.- Ensures that all Post-Irradiation handling of in-pool samples and all radioactive material shipments are performed in-accordance with Approved Procedures meeting all applicable Regulations by: , 4.1.2 Review and Approval of Shipping Procedures. 4.1.3 Ensuring Compliance with Shipping Procedures. 4.1.4 Ensuring training is conducted for Shipping Personnel on Shipping Procedures. 4.1.5 Ensuring maintenance of training records of Shipping Personnel. Rev. O SA [ HP Date 13 Acril 1993 MURR-SAS-00000 page 6 of 9

                              ,--w       y,-                                         ,

MURR-SAS-00000 Service Applications Departmental Administrative: Shipping 4.2 Service Acolications Section Leader- Shinoinc: As Supervisor of the Service Applications Group Shipping,is responsible for the overall supervision of the Shipping Department personnel.

To ensure that all Post-irradiation handling of in-pool samples and all radioactive material shipments are performed in accordance with Approved Procedures meeting all applicable Regulations by: 4.2.1 Review of Shipping Procedures. 4.2.2 Scheduling and implemetation of training of Shipping Procedures. 4.2.3 Identifying initial training and retraining. 4.2.4 Maintaining Documented training records. 4.3 Shipoine Technician (Shicoerk Defined to be any person in the Shipping Group. 4.4 Shioner. Certified: Is Qualified to perform the tasks required in all aspects of shipping as Documented by Training and is Qualified to sign Certifications for MURR. 4.5 Shioner. Quallffed: An individual who has completed the Required Documented Training to perform specific Tasks. 4.6 Shicoer. Trainee: Can neither Perform or Inspect a Task. 4.7 Health Physics Manacer: Is responsible for the overall administration of the Health Physics Group and to provide Health Physics support as required to the Service Applications Group, Shipping, in preparation of radioactive , shipments by: 4.7.1 Survey of recieved radioactive material. 4.7.2 Supervising opening of packages containing radioactive material. 4.7.3 Review and Approval of Radioactive Material Shipping Procedures. 4.7.4 Maintaining radiological control of the shipping process. Rev. O SA kl HP M Date 13 Anril 1993 MURR-SAS-00000 page 7 of 9 s - + , - , , -u -

j MURR-SAS 00000 Service Applications Dcpartmental Administrative: Shipping-5.0 PROCFDURE 5.1 Ensure that Consignees (Receivers) for MURR Shipments of radioactive materials are properly authorized to receive the Type, Form, and Quantity of such material in accordance with Provisions of 10CFR. 5.2 The following unique characteristics of each shipment Shall be maintained throughout Receipt, Safety Analysis, Preparation for Irradiation, Irradiation, Post Irradiation Processing, Packaging, and Documentation: 5.2.1 Material Description, 5.2.2 Amount (Mass), 5.2.3 Isotopes, 5.2.4 Activity, 5.2.5 Destination, 5.2.6 Recipient's License Number, Amendment Number and Expiration Date or certificate in accordance with 10CFR. . 5.2.7 MURR Identification Number. , 5.3 Data integrity must be maintained by Documented Control . Sheets of the Performer's action with an Observer Verification at critical points in the process, i 1 5.3.1 The " Performer" of a shipping process and " Observer" must not be the same individual. 5.3.2 The Observer must also be Qualified to perform the specific task. 5.4 The Procedure Flow Charts utilized for the Service Applications Departmental Shipping Procedures involves series and parallel-- Steps labeled in accordance with the Procedure Step numbers and must be adhered to by the Shipping Department Personnel unless othenvise noted. t 5.4.1 Series Steps of the flow chart must be accomplished in sequential order. , 5.4.2 Some parallel Steps are alternatives. Parallel Steps of the flow 9 chart may be accomplished in sequential order or at the same time, whichever is the most efficient. N a Rev. O SA HP Date 13 Acril 1493 MURR-SAS40000 page 8 of 9 l d i

.]

MURR-SAS-00000 Service Applications Departmental Administrative: Shipping ? 5.5 MURR Personnel involved in any Task within the scope ; of the Service Applications Departmental Shipping Procedures will receive Documented Inidal and Annual Refresher Training applicable to that task in accordance with -i 49CFR172 Subpart H- Training. 5.6 All employees who perform any task subject to the requirements of DOT Hazardous Material Regulations will receive applicable training as described in 49CFR172 in compliance with NRC Information Notice 92-72. . REFERENCES A. Code of Federal Regulations,10CFR. B. Code of Federal Regulations,49CFR. C. International Air Transport Association (IATA) Dangerous Goods Regulation. D. MURR Health Physics Standard Operating Procedures:

HP-3: Receiving and Opening Packages of Radioactive Material.
HP-4: Handling Radioactive Material in MURR Pool.
HP-12: Transfer of Radioactive Material within MURR Building.
HP-13: MURR Hot Cell Operation.
HP-16: Surveying Containers of Radioactive Material for Transport, 1

I Rev. O SA NA HP Date 13 Acril 1993 MURR-SAS-00000 page 9 of 9 l 1

MURR-SAS-00002 Hot Cell Preparation of Radioactive Material for Shipment Procedure Cover Sheet MURR-SAS-00002 0 15 Acril 1943 (Procedure) (Revision) (Date) Hot Cell Precaration of Radioactive Material for Shioment (Procedure Title) ! Prepared By - A/ (Signature)(/ Reviewed By UL $UYft . ASONEh (Signature) l Revision Summarv Rev.3 Date Significant Summarv 1 O 15 Apr. 93 Yes Original l l Rev. L SA IIP Date 15 Aor.1093 MURR-SAS-00002 page 1 of 22 W

MURR-SAS-00002 Hot Cell Preparation of Radioactive 6taterial for Shipment TABLE OF CONTENTS < SECTION - PAGE NUMBER

1.0 Purpose and Scope

3 2.0 Precautions and 1. imitations 3 3.0 Materials and Equipment 5 j 4.0 Definitions 6 5.0 Responsibilities 7 6.0 Procedure 7 7.0 Hot cell processing Dow path 8 7.1 Deterndne shipment type and prioritize 9 7.2 Preparation for sample removal from pool 9 7.3 Remove sample (s) from pool 10 - 7.4 Transport sample (s) to hot cell 10 7.5 Prepare shipping containers to receive sample (s) 11 7.6 Hot cell entry 11-7.7 Remove can from transfer cask 12' 7.8 Open can and process ~13 7.8.4 Process sample 14 7.8.7 Process capsule 15

       ' 7.9    Storage                                                     16 7.10 Open capsule and process                                      16 7.11   Reload                                                      17
        -7.12   Load into shipping container                                18                   t 7.13 Remove casks from hot cell                                   .19 i

7.14 Prepve transfer cask for reuse 20 t 7.15 Complete paper work 21 Attachments 22 References 22 ; Rev. L SA M . HP Date is Anr.1993 MURR-SAS-00002. page 2 of 22 I

MURR-SAS-00002 Hot Cell Preparation of Radioactive Material for Shipment HOT CFil PREPARATION OF RADIOACTIVE MATERIAL FOR SHIPMENT 4 1.0 PURPOSE AND SCOPE This procedure provides instructions for the hot cell ., preparation of radioactive material to be-packaged and , shipped by the Service Application Department to ensure Compliance with applicable Regulations of Code of Federal Regulations (CFR),10CFR. 49CFR and International Air-Transport Association (IATA). , 1.1 This procedure incorporates:

Positive identification of sample (s) to be removed from the Reactor pool. - ,
Loading of irradiated sample (s) into a transfer cask,
Conveyance of transfer cask to the hot cell,
Transfer of samples into hot cell, ;
Removal of sample (s) from the transfer cask,
Placement of sample (s) into shipping container / cask,

Preparation of transfer cask for reuse,
Transfer of shipping container (s) to packaging area or for In-house processing.

2.0 PRECAUTIONS AND LIMITATIONS , 2.1 The non-fixed contamination on any external surface of the transfer cask must be kept as low as practical. 2.1.1 The level of non-fixed radioactive contamination may be determined by wiping an area of the surface concerned with an absorbent material, using moderate pressure, and measuring the activity on the wiping material. 2.2 Ensure that all beta-gamma dose rate survey, contamination

               - counting, and gamma radioisotope equipment calibration stickers have not passed the calibration due date prior to use.

l Rev. L SA M HP Date 15 Aor.1993 MURR-SAS-00002 page 3 of 22 i

MURR-SAS-00002 Hot Cell Preparation of Radioactive Material for Shipment 2.3 Ensure that upon leaving the hot cell area you measure for _ personal external contamination by use of the Hand-foot monitor (located at the top of the stairs exiting the basement area) or equivalent device. 2.3.1 When the Hand-foot monitor alarms indicating external contamination, call Health Physics immediately at extension

                   #2-5217.

2.3.2 After 5:00 P.M. or Weekends call the Control Room at extension # 2-5213. 2.4 Maintain radiation exposure As Low As Reasonably ~ Achievable ( ALARA) by use of Time, Distance, and Shielding, e.g: . Do not ride down the elevator with the cask containing the samples removed from the Reactor pool. 2.5 Ensure that the transfer cask used to transfer the samples from the Reactor pool to the hot cell is wiped and bagged to prevent contamination during its movement. 2.5.1 Examine poly bag for holes or tears. 2.5.2 Use Extreme Caution when removing the bag from the cask prior to placing the cask into the hot cell to prevent spread of contamination. 2.5.3 Use Extreme Caution when placing the bag on the cask prior - to moving the cask to a storage area to prevent spread of contamination. 2.6 Use protective clothing:

Laboratory Coats ,

a Rubber / Latex Gloves

Breathing Masks: Type to minimize ingestion / inhalation of particulate matter.
Safety Glasses 2.7 In the event of a broken vial or stuck sample, the Reactor Services Engineer or Designee must be notified immediately to resolve the problem.

k t

     'Rev. L SA lh . HP            Date 15 Acr.1993        MURR-SAS-00002 page 4 of 22 1

B

                                                                             -          , 4

MURR-SAS-00002 Hot Cell Preparation of Radioactive Material for Shipment -. 3.0 MATERIALS AND EOUIPMENT j 3.1 Capintec Radioisotope Calibrator, CRC-5RH or equivalent. 3.2 Calibrated gross contamination counting equipment Eberline, Model RM-19 or equivalent. 3.3 Calibrated Beta counter Eberline, Model BC-4 or equivalent. 3.4 Calibrated Radiation Detector Xetex Model 302B or equivalent. 3.5 Smear papers. 3.6 Cask handling tools and equipment. 3.7 Fork lift. 3.8 Clean, uncontaminated shipping container (s): 3.8.1 Type, size, and quantity predetermined by shipping requirements for that day. 3.9 Protective clothing, to include: , 3.9.1 Rubber / latex gloves 3.9.2 1.aboratory coats 3.9.3 Breathing masks, type to minimize ingestion / inhalation of particulate. > 3.9.4 Safety Glasses 3.10 Bron yellow tape, one inch ~ wide. 3.11 Sample Pull Sheet, Attachment 2 Sample Sheet, Attachment 3 3.12 : 3.13 Sample Shipment Information Sheet, Attachments 4, S,6, and 8. 1 3.14 Existing Loading Sheet, Attachments 7 and 9. 3.1 S Permanent marker (black ink). , 3.16 Ball point pen (black ink). . Rev. L SA \6. HP d- Date 15 Anr.1993 MURR-SAS-00002 page 5 of 22 -i

  ,.           n    ,,            s,.--                                  , . , -   , - - ,,

MURR-SAS.00002 Hot Cell Preparation of Radioactive Material for Shipment 4.0 DEFINITIONS

4.1 Activity

Is a measure of the quantity of radioactivity emitted , by a radioisotope and is used to determine the amount of ) radioactive material which may be transported in various i types of packaging. 4.2 Radioactive Contents: The radioactive material together , with any contaminated solids, liquids and gases within the package. 4.3 Radioactive material: Any material having a specific activity greater than 70 KBq/kg (0,002 uC1/g). 4.4 Samole Log Books: These log books (two) are located in tne Control Room and designated as the:

Flux Trap, H1, and BPLS (Bulk Pool Lead Shield)

Book and,

Silicon Book.

The log books are broken down into sections designated to correspond with the reactor irradiation and in-pool storage area. 4.4.1 " Sample Run Sheets" are placed in the appropriate Section of the log books during irradiation of the sample, after which,'

  .                 they are moved to the Storage Section.

4.4.2 The stored position is recorded on the Sample Run Sheet. 4.4.3 The Flux Trap, H1, and BPLS Book consists of the following sections: Flux Tray Loading Sheet, Tube A Tube B. Tube C, H1, BPLS (Bulk Pool Lead Shield),. Bisco, Storage, Reuter Stokes, and Samples in use. 4.4.4 The Silicon Book consists of: J-1, K-2, R (Red, also known as "J") LL3, L positions, N positions, B (Blue, also known as 1), Y (Yellsw, also known as H), G (Green also know as G), Bin. Storage, and Sample Storage. 4.S Shall Must. Should: 4.S.1 Shall: Regulatory Commitment to Code of Regulations, 10CFR,49CFR and IATA Dangerous Goods Regulations. 4.5.2 Must: MURR Internal Commitment to 10CFR,49CFR and IATA Regulations.

4.5.3 Should

Should be accomplished; not required. 4.6 Shionine container: To contain the sample (s) during transport: Can be a lead pig (2 LB. to 30 LB), or a depleted uranium shield. Rev. L SA A HP _Date 15 Aor.1943 MURR-SAS-00002 page 6 of 22

T MURR-SAS-00002 Hot Cell Preparation of Radioactive Material for Shipment 4.7 Soecific Activity: The activity of the radionuclide per unit weight of that nuclide. 4.8 Transfer Cask: Used to transport samples within the facility. 5.0 RESPONSIBILITIES 5.1 Reactor Services Encineer: Ensure that all shipments of radioactive material conform to applicable Regulations of-10CFR, 49CFR, and IATA. Provide properly certified packages for shipment of radioactive materials. 5.2 Health Phvsics Manacer: Provide Health Physics (HP) support as required to Service Applications Group for preparation of radioactive material shipments. 5.3 Reactor Ooerations Manacer: Provide round the clock Operations support as required to Service Applications , Group for irradiation of samples received. 6.0 PROCEDURE 6.1 Ensure that Consignees (Receivers) for MURR Shipments of radioactive materials are properly authorized to receive the Type, Form, and Quantity of such material in accordance with Provisions of 10CFR. 6.2 The following unique characteristics of each shipment Shall be maintained throughout Receipt Safety. Analysis, Preparation for Irradiation, Irradiation, Post Irradiation Processing, Packaging, and Documentation: 6.2.1 Material Description, 6.2.2 Amount (Mass), 6.2.3 Isotopes, . l 6.2.4 Activity, -- 6.2.5 Destination, 6.2.6 Recipient's License Number, Amendment Number and .i Expiration Date or certificate in accordance with 10CFR. 6.2.7 MURR Identification Number. 1 I I

                                                                                             'I Rev. L SA M HP 3 Date 15 Aor.1903                   MURR-SAS-00002 page 7 of 22

I MURR-SAS-OOOO2 Hot Cell Preparation of Radioactive Material for Shipment - 6.3 Data integrity must be maintained by documented Control

     .              Check Sheets with Independent Verification at critical points                   )

in the process. -l l 6.3.1 The " Performer" of a shipping process and " Independent i Redundant Verifier" must not be the same individual. l 1 6.3.2 The Independent Verifier must also be Qualified to perform the Task. . 6.4 MURR Personnel involved in any Task within the scope of this Procedure will receive Documented Initial and Annual Refresher Training applicable to that Task in , accordance with 49CPR172 Subpart H- Training. 7.0 HOT CFII PROCESSING FLOW PATH 7.0.1 The Hot Cell Plow Path Chart (attachment 1) involves series and parallel steps labeled in accordance with the Procedure step numbers and must be adhered to by the Shipping Department Personnel unless otherwise noted.

          ?.0.2     Series steps of the flow chart must be accomplished in                        -

sequential order. 7.0.3 Some parallel steps are alternative parallel step:: of the flow chart and may be accomplished in sequential order or at the , same time, whichever is the most efficient. for example: 7.0.3.1 Step 7.5 (Prepare Shipping Containers to receive sample (s)) does not have to be completed immediately after Step 7.1 (Determine-Shipment Type and Prioritize) but must be i completed prior to Step 7.6 (Hot Cell Entry). 7.0.4 Processing of the radioisotopes prior to packaging for ! shipment is accomplished in cooperation with MURR Operations (OPS), Health Physics (HP) and Service Applications (SA) Departments. F t t

                                                                                                .i i

Rev.L SA "3 HP d Date 15 Anr.1993 MURR-SAS-00002 page 8 of 22

MURR-SAS-OOOO2 Hot Cell Preparation of Radioactive Material for Shipment 7.1 DETERMINE SHIPMENT TYPE AND PRIORITIZE Use the Samnie Pull Sheet (Attachment 2) and Samnie Shinment information Sheet (Attachment 4): Review specified ) shipping container to determine if appropriate and prioritize the shipping orders set for the day. 7.1.1 The Service Applications Section Leader-Shipping or Authorized Individual will determine priority based on prior knowledge and/or discussion with consignees. 7.1.2 General Guidelines to determine shipping priority: ,

1. In general, " Human Use" will have the highest priority.

2. Samples which have been retained beyond their requested ship date will have the next highest priority.

3. Others are:

Long lived isotopes, '

                                     . Standard Air (two day delivery service) 7.1.3     "A" Priority samples are high-lighted in pink on the Sample Pull Sheet (attachment 2 ;.                                       ,

7.1.4 "B" Priority samples are high-lighted in blue on the Sample Pull Sheet (attachment 2,. , 7.2 PREPARATION FOR SAMPIE REMOVAL FROM POOL . 7.2.1 Transport Transfer Cask and Samnie Pull Sheet (Attachment 2) to the Control Room. 7.2.2 Remove the Samnle Sheet.(Attachment 3) from the Control Room Samnie Loc Book in accordance with the information provided by the Samnie Pull Sheet (Attachment 2). 7.2.3 Verify the following Information from the Samnle Pull Sheet: (Attachment 2) and Samnle Sheet (Attachment 3):

Can number
Company (destination)
Proper decay time 1

Rev. L SA A HP _:df. Date 1S Anr 1493 MURR-SAS-00002 page 9 of 22

rc44.J.- d d * ' " ' < h , l MURR-SAS-00002 . Hot Cell Preparation of Radioactive Material for Shipment 7.3 REMOVE SA.MPLE(S) FROM POOL - ! 7.3.1 Qualified Shipper ensures can ID number corresponds to Samole Pull Sheet (Attachment 2). , 7.3.2 Operators assisted by Health Physics: 7.3.2.1 Load samples into transfer cask. 7.3.2.2 Install lid on transfer cask. 7.3.2.3 Raise transfer cask from pool 7.3.2.4 H.P. monitor transfer cask for dose rate. 7.3.2.5 Insert drain plug into transfer cask when cask is drained. 7.3.2.6 Rinse transfer cask with distilled water. l 7.3.2.7 Wipe down outside of transfer cask. 7.3.3 Inspect the plastic bag to be used to insert transfer cask into for holes or tears. 7.3.4 Install safety bar and pin in cask. 7.3.5 . Place transfer cask into the plastic bag. 7.3.6 Assure proper orientation of u..rt to accommodate cask. 7.3.7 Place transfer cask on a cart.- - 7.4 TRANSPORT SAMPLE (S) TO HOT CELL

                                   ** CAUTION **

Personnel transporting cask to hot cell must practice ALARA , (TIME, DISTANCE, SHIELDING) . DO NOT RIDE ELEVATOR WITH CASK. 7.4.1 Transfer cask is transported to the hot cell via the Containment and Freight elevators or door 101 when available. 7.4.2 Occasionally, two transfer casks are used. Second transfer cask is stored in the " hot closet" located in the basement at the foot of the stairs. Rev. Q_ SA Y HP g- Date 15 Anr.1493 MURR-SAS-00002 page 10 of 22

l

                                                                                          .I i
     ~ MURR-SAS-00002           Hot Cell Preparation of Radioactive Material for Shipment   !

7.5 . PREPARE SHIPPING CONTAINERS TO RECEIVE SAMPI_E(S) 7.5.1 Ensure shipping container is clean of all previous identifiers:

If the shipping container has previously been used, remove all orior markings.

7.5.2 Use the Samole Shioment Information Sheet (Attachment 4, Step 1) and permanent marker (black) to legibly mark and identify the shipping container with the following . information: A. Sample can number or capsule number, B. Company, C. Isotope, D. MURR Identification number. 7.5.2.1 In-house samples are taped with three inch wide yellow tape and then the above information is written on the tape. 7.5.3 Verify the information of Step 7.5.2 on the shipping shield before placing in processing area. 7.5.4 Performer and Independent Observer initial Step 1 completion, (Attachment 4). 7.6 HOT CFI I. ENTRY 7.6.1 Qualified Shipper dons protective clothing:

Laboratory coat
Rubber / latex gloves a Breathing mask, type to minimize ingestion / inhalation of particulate matter for personnel who approach the hot cell door.

Safety Glasses / face shield 7.6.2 Move transfer table to North end of hot cell.

7.6.3 Health Physics: 7.6.3.1 Ensure air monitor is functional. 7.6.3.2 Ensure hot cell blower is "ON". I 7.6.3.3 Open concrete shield outer door to hot cell and survey inner door of hot cell while outer door is opening. Rev. L SA A HP Date 15 Anr.1903 MURR-SAS-00002 page 11 of 22

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

1 MURR-SAS-00002 Ho't Cell Preparation of Radioactive Material for Shipment' 7.6.4 Q.ualified Shipper: 7.6.4.1 Open aluminum inner wall door. 7.6.4.2 Place clean absorbent paper on Pig Tray in hot cell.-

                                                                                                          .i 7.6.4.3    Load the clean, identified shipping containers on the                               ;

pig tray in the hot cell with the identifying markings facing i the South window at approximately a 45 degree angle, 7.6.4.4 Move the transfer cask to the front of the hot cell door by a fork lift. 7.6.4.5 Remove safety pin and bar from cask. ,

                                                                                                         -t 7.6.4.6    Remove the plastic bag from the transfer cask at the hot cell                       >

door. l - 7.6.5 Health Physics: Insert transfer cask into hot cell with fork lift. 7.6.5.1 7.6.5.2 Close inner hot cell aluminum door. 7.6.5.3 Swipe floor outside of hot cell and read for contamination. 7.6.5.4 Close outer concrete door. i 7.6.5.5 Turn hot cell blower "OFF". o, 7.7 REMOVE CAN FROM TRANSFER CASK 7.7.1 Lift lid from transfer cask using the crane. ,; 7.7.2 Remove transfer cask basket and place on upper work table. i 7.7.3 Manipulate sample can from the transfer cask basket and place can in holding area. NOTE-WHEN PROCESSING HOST CANS (Mondays), DO NOT REPLACE BASKET IN LAST TRANSFER CASK. ' l i l 7.7.4 Place basket into transfer cask. r 7.7.5 Set transfer cask lid in place. 7.7.6 Unhook lid from crane. i Rev. L SA HP $ Date 15 Aor.1043 MURR-SAS-00002 page 12'of 22 . i.' i

MURR-SAS-00002 Hot Cell Preparation of Radioactive Material for Shipment 7.7.7 Identify and verify the can by comparing the can with the a Samole Shioment Information Sheet (Attachment 4), Step 2, when applicable. 747.8 Performer and Observer initial to verify sample can is correct (Attachment 4) Step 2.

NOTE: AT THIS POINTIN THE HOT CELL PROCESSING, THE SAMPLE CAN MAY TAKE ONE OF TWO PATHS:

1. The Sample Can is to be Loaded into a Shipping Container for Shipment: Proceed to Procedure Sten 7.12 or,

2. The Sample Can is to be opened and contents processed: Proceed to Procedure Sten 7.8.

1 7.7.9 The transfer cask will be removed from the hot cell in Step 7.13. 7.8 OPEN CAN AND PROCESS

NOTE: The term " Process" in Steps 7.8.4 and 7.8.S means either processing a sample or removing a capsule without opening the capsule.

To process a sample, go from Steo 7.8.3 to 7.8.4. To remove a capsule, go from Steo 7.8.3 to 7.8.7. 7.8.1 Sample can is identified and verified by comparing the can inscription with Samole Shinment Information Sheet. (Attachment S) Step 2. 7.8.2 Performer and Observer initial Samole Shioment Information Sheet (Attachment S), Step 2 verifying sample can is correct. 7.8.3 Cut top off of sample can and place top into hot waste storage area of hot cell. Rev. L SA '4 HP I Date 15 Acr 1993 MURR-SAS-00002 page 13 of 22 -

  - -                .                             .                                   . ~.

l MURR-SAS-00002 Hot Cell Preparation of Radioactive Material for Shipment 7.8.4 Process Samolg 7.8.4.1 _ Remove sample from sample can and place on clean absorbent paper. 7.8.4.2 Perform a visual inspection of the sample after it is de-canned as shown in example on Samole Shioment Information Sheet (Attachment 5), upper right corner:

              = OPEN 4" CaN.

THREE VIA1.S 7.8.4.3 Performer and Observer initial Step 3 of Samole Shioment Information Sheet (Attachment 5). 7.8.5 If sample activity is to be measured in the Capintec: 7.8.5.1 The lid of the Calibrator cask is raised by the crane, exposing the CRC-5RH Detector. 7.8.5.2 The scale of the Calibrator, CRC-5RH detector is adjusted for the specific isotope setting (window). 7.8.5.3 Record the Date, Time, and Capintec Setting on Samole Shioment information Sheet ( Attachment 5), Step 4. 7.8.5.4 The sample is manipulated into the detector in a plastic holder. 7.8.5.5 Activity of the sample is measured by the CRC-5RH Calibrator. 7.8.5.6 Record the Capintec readings on Samole Shioment Information Sheet. (Attachment 5) Step 4. 7.8.5.7 Performer and Observer initial (Step 4) of Samole Shioment Information Sheet (Attachment 5). 7.8.6 To load processed sample into shipping container: Proceed to Procedure Steo 7.12. Rev.L SA 1 HP d Date 15 Anr.1993 MURR-SAS-00002 page 14 of 22

                                                                 ,w- - -

MURR-SAS-OOOO2 Hot Cell Preparation of Radioactive Material for Shipment 7.3.7 Process caosule 7.8.7.1 Identify and verify capsule inscription by comparing the inscription and capsule design on Samole Shioment Information Sheet (Attachment 6), and Existine Loadine Sheet (Attachment 7). 7.8.7.2 Performer and Observer initial Step 2 of Samole Shioment Information Sheet (Attachment 6). 7.3.7.3 Perform a visual inspection of the capsule as shown in wording description box in the upper right hand corner of Attachment 6: DO NOT OPEN CAPSULE 1 7.S.7.4 Performer and Observer initial Samole Shioment Information Shes (Attachment 6), Step 3. 7.8.8 If capsule activity is to be measured in the Capintec: 7.3.3.1 The lid of the calibrator cask is raised by the crane, exposing the CRC-5RH detector. 7.8.3.2 The scale of the calibrator CRC-5RH detector is adjusted for the specific isotope setting (window). 7.8.8.3 Record the Date, Time, and Capintec setting On Samole t Shipment Information Sheet (Attachment 6) Step. l 7.8.8.4 The capsule is manipulated into the detector in a plastic holder. 7.8.8.5 Activity of the capsule is measured by the CRC-5RH Calibrator. 7.S.3.6 Record the Capintec readings on the Samole Shioment Information Sheet. ( Attachment 6) Step 4. 7.8.8.7 Performer and Observer initial (Step 4) of the Samole Shioment Information Sheet (Attachment 6).

                   = NOTE:

l AT THIS POINT IN THE HOT CEIL PROCESS THE CAPSULE MAY TAKE ONE OF FOUR PATHS: l 1. Capsule is to be placed in Storage: Proceed to Steo 7.9. l

2. Capsule is to be Opened and Processed: Proceed to Steo 7.10.

t

3. Capsule is to be Reloaded: Proceed to Steo 7.11 or,

4. Capsule is to be loaded into shipping container: Proceed to Steo 7.12.

t Rev. SL. SA U HP $ Date is Aor.19o3 MURR-SAS-00002 page 15 of 22

_ . m _ , _ _ .- . - - _ _ 1 MURR-SAS-00002 Hot Cell Preparation of Radioactive Material for Shipment. 7.9 STORAGE 7.9.1 When capsules are placed into or removed from the hot cell storage area, the following information must be written into the Hot Cell Storage Log Book: ,

Date in and Out as applicable
MURR Identification Number
Capsule Number
Capsule Design
Position Stored a "In" initials '

                         * "Out" Initials                                                                 ,

i

Remarks 7.9.2 The capsule (s) unloaded in Procedure Step 7.8 (Open Can and Process) may be placed in storage for one of these later actions:

1. If it is to be opened and processed: Proceed to Steo 7.10, ;

2. If it is to be reloaded: Proceed to Sten 7.11 or,

3. If it is to be loaded into a shipping container: Proceed to .

Steo 7.12. 7.10 OPEN CAPSTILE AND PROCESS , 7.10.1 Place capsule in bucket and transfer to South work station. , 7.10.2 Place capsule on clean absorbent paper. 7.10.3 Identify and verify capsule inscription by comparing the inscription on Sample Shloment Information Sheet ' (Attachment 8), and Existine Loadinn Sheet (Attachment 9). 7.10.4 Performer and Observer initial Step 2, of Samole Shloment Information Sheet (Attachment 8). r

                                                               . MURR-SAS-00002 page 16 of 22 Rev.L SA 1 HP d Date 15 Aor 1493

MURR-SAS-00002 Hot Cell Preparation of Radioactive Material for Shipment i-7.10.5 - Perform a visual inspection of the capsule as shown in the -. upper right hand corner of Sample Shipment Information Sheet (Attachment 8) :

ONE VIAL OPEN CAPSUI.E 1 7.10.6 - Performer and Observer initial Samole Shioment Information Sheet (Attachment 8), Step 3.

7.10.7 Open the capsule and remove sample. 7.10.8 If sample activity is to be measured in the Capintec: 7.10.8.1- The lid of the calibrator is raised by the crane, exposing the CRC-5RH Detector. 7.10.8 2 The scale of the calibrator CRC-5RH detector is adjusted for the specific isotope setting (window). 7.10.8.3 Record the Date, Time, and Capintec Setting on Sample Shipment Information Sheet (Attachment 8) Step 4. 7.10.8.4 The sample is manipulated into the detector in a plastic holder. 7.10.8.5 Activity of the sample is measured by the CRC-5RH Calibrator. 7.10.8.6 Record the Capintec readings on ,Samnle Shinment Information Sheet. (Attachment 8) Step 4. 7.10.8.7 Performer and Observer initial (Step 4) of Samole Shinment Information Sheet (Attachment 4). 7.10.9 To load sample removed from capsule into shipping container: Proceed to Procedure Steo 7.12. 7.11 RELOAD i 7.11.1 Capsules to be reloaded will be received from:

1. Open Can and Process: Procedure Step 7.8

2. Storage: Procedure Step 7.9 7.11.2 To reload: Use MURR-SAS-00005. ,

I j Rev._D_. SA 'D . HP [ Date 15 Aor.1943 MURR-SAS-00002 page 17 of 22 1

MURR-SAS-00002 Hot Cell Preparation of Radioactive Material for Shipment 7.12 LOAD INTO SHIPPING CONTAINER The loading of the shipping container may occur from one or as many as five different sources:

An un-opened, un-processed can from Step 7.7, '
A processed sample from Step 7.8., ,
A processed capsule from Step 7.8.2,
A stored capsule from Step 7.9.
A capsule which has been opened and processed from Step 7.10 or, 7.12.1 Identify correct shipping container.

7.12.2 Load identified can/ sample / capsule into appropriate shipping container. 7.12.3 Performer and Observer initial Samole Shioment Information Sheet. Step 5 ( Attachment 4, 5, 6, or 8), indicating can/ sample / capsule is loaded into correct vial container, shipping > pig or depleted uranium shield. NOTE: Replacement of lids on some depleted uranium shields require the use of the-crane. 7.12.3.1 Replace lid on depleted uranium shield with crane if appropriate. i l r l i Rev. O SA 1 HP d Date 15 Anr.1943 MURR-SAS-00002 page 18 of 22

MURR-SAS-00002 Hot Cell Preparation of Radioactive Material for Shipment 7.13 REMOVE CASKS FROM HOT GI L NOTES: PERFORM A VISUAL INSPECTION OF THE HOT CELL TO ENSURE THAT ALL WORKING AREAS ARE SECURED AND THAT DOORS CAN BE OPENED. MOVE TRANSFER TABLE TO NORTH END OF HOT CELL AND ADJUST TO CORRECT LEVEL FOR FORK LIFT ENTRY. 7.13.1 Health Physics: 7.13.1,1 Turn hot cell blower "ON". l 7.13.1.2 Open concrete shield outer door to hot cell and survey inner door of hot cell while door is opening. 7.13.1.3 Open aluminum inner wall door. 7.13.2 Qualified Shipper: , 7.13.2.1 Place lid (s) on shipping container (s) by hand. 7.13.2.2 Swipe all shipping containers and transfer cask (s). 7.13.2.3 Remove shipping container (s) from hot cell. 7.13.2.4 Place shipping containers on absorbent paper covered work table. 7.13.3 Health Physics: 7.13.3.1 Perform dose rate measurements of shipping container (s) and transfer cask (s) using Ion Chamber, Eberline model RO-2A or equivalent 7.13.4 Qpalified Shipper / Health Physics: 7.13.4.1 Inspect poly bag to be used to bag the transfer cask for holes or tears. 7.13.4.2 Remove transfer cask from hot cell using fork lift. 7.13.4.3 Bag the transfer cask. 7.13.4.4 Replace safety bar and pin. Rev. L SA VA. HP I Date 15 Aor.1o93 MURR-SAS-00002 page 19 of 22 l

MURR-SAS-00002 Hot Cell Preparation of Radioactive Material for Shipment 7.13.5 Health Physics: 7.13.5.1 Close the inner hot cell door.

7.13.5.2 Close outer hot cell door. 7.13.5.3 Turn hot cell blower "OFF" 7.13.5.4 Swipe and read floor outside of the hot cell door using Baird Polyspec Research Spectrometer or equivalent to count the swipes. 7.13.6 On approval by Health Physics, indicating containers are clean to ship, tape shipping container lid to the the shipping container with Bron one inch wide yellow tape. 7.13.7 After the shipping containers are swiped, read and approved by Health Physics, the yellow taped shipping containers are loaded onto a cart and may be dispatched to:

The packaging area for packaging: Use MURR-SAS-00004, Shipping Procedure or.
In-house processing.

7.14 PREPARE TRANSFER CASK FOR REUSE 7.14.1 Clean transfer cask if required in preparation fo'r future - sample removal from the pool.

-)

P i Rev. L SA - HP % Date 15 At3r.1993 MURR-SAS-00002 page 20 of 22

MURR-SAS-00002 Hot Cell Preparation of Radioactive Material for Shipment 7.15 COMPLETE PAPER WORK 7.15.1 The following paper work is transferred between Service Aeolications-Shionine and Servce Aeolications-Isotones:

Sample Pull Sheet, Attachment 2.
Sample Sheet, Attachment 3.
Sample Shipment Information Sheets, Attachments 4, 5,6, and 8.
Existing Loading Sheets, Attachments 7 and 9. (Mondays only for host can loading).

7.15.2 Originally, the above paper work is generated by Service : Apolications-Isotones and transferred to Service Acolications-Shioning. 7.15.3 Prior to when the Shippers go to the hot cell the Samole Sheet is returned to Isotopes. 7.15.3.1 Isotopes enters the information of the Samole Sheet into the Data Base. 7.15.3.2 The Samole Sheet is returned to Shipping.

7.15.4 After the package is shipped the Documentation . Packet, which includes, the Samole Sheet and Samole Shioment Information Sheet is returned to Isotopes where it remains until Billing.

7.15.4.1 The Samole Pull Sheet is filed by the Shipping Department. 7.15.4.2 On Mondays (host can loading) the Existine Loadine Sheet is returned by placing it into the "In-basket" ofIsotopes. 7.15.5 After the Billing, the paper work is transferred to Service Applications Section Leader- Shipping. 7.15.6 The Service Applications Section Leader- Shipping:

Files the paper work in numerical order and maintains this paper work for a period of three years.
Performs sampling of the documents for accuracy.

7.15.7 After a three year period, this paper work is sent to the University of Missouri Storage. Rev. _Q SA b HP $ Date 15 Aor.1993 MURR-SAS-00002 page 21 of 22

MURR-SAS-00002 Hot Cell Preparation of Radioactive Material for Shipment ATTACHMENTS A. Hot Cell Sample Flow sheet. Attachment 1. B. Sample Pull sheet, Attachment 2. C. Sample sheet, Attachment 3. D. Sample Shipment Information Sheet, / tachments 4, 5, 6, and 8. E. Existing Loading Sheet, Attachments 7 and 9. REFERENCES A. Health Physics Standard Operating Procedures:

1. HP-4: Handling Radioactive Material in MURR Pool.

2. HP-12: Transfer of Radioactive Material within MURR building.

3. HP- 13: MURR Hot Cell Operation 5

L l

                                                                                                      'I I

l 4 Rev. L SA U . HP Date 15 Anr.1993 MURR-SAS-00002 page 22 of 22 i e .

       "                                                           .a.

MURR-SAS4)0003 Hot Laboratory Preparation of Radioactive Material for Shipment Procedure Cover Sheet

     ,       MURR-SAS-00003                 0           IS Aoril 1993 (Procedure)           (Revision)          (Date)

Hot Laboratorv Preoaration of Radioactive Material for Shioment (Procedure Title) Prepared By ![XM _ Wo - , (Signatpfe) Reviewed By AA)/ Lt/h4 kBY0k) (Signature) Revision Summarv Fev. # ' Dine Sinnificant Summarv 0 15 Apr.1993 Yes Original a 5 4 Rev. _Q SA I HP -d Date 15 Anr.1003 MURR-SAS-00003 page 1 of 18 7 7 Y

MURR-SAS-00003 Hot Laboratory Preparation of Radioactive Material for Shipraent

 ^'                                      TABLE OF CONTENTS SECTION                                                   PAGE NUMBER

1.0 Purpose and Scope

3 2.0 Precautions and Linutations 3 3.0 Materials and Equipment 5 4.0 Definitions 6' 5.0 Responsibilities 7 6.0 Procedure 8 7.0 Hot laboratory flow chart 9 7.1 Determine shipment type and prioritize 9 7.2 Preparadon for sample removal from pool 10 7.3 Remove sample (s) from pool 10 7.4 Transport sample (s) to hot laboratory 11 7.5 Prepare shipping containers and hot laboratory 11 7.6 Remove can from cask 12 7.7 Identify can 12 7.8 Open can 13. 7.9 Process sample 13 7.10 Load into shipping container 14-7.11 Shipping container to in-house user 15 7.12 Shipping container to packaging area 15 7.13 Prepare transfer cask for reuse 15 7.14 Hot laboratory cleanup 15 7.15 Complete paper work 17 Attachments 18 References 18 Rev.S SA M HP I Date 15 Aor.1993 MURR-SAS-00003 page 2 of 18

l MURR-SAS-00003 Hot L.aboratorf Preparation of Radioactive Material for Shipment

,. HOT LABORATORY PREPARATION OF RADIOACTIVE MATERIAL FOR SHIPMENT 1.0 PURPOSE AND' SCOPE This procedure provides instructions for the hot laboratory ' preparation of radioactive material to be packaged and shipped by the Service Application Department to ensure Compliance with applicable Regulations of Code of Federal , Regulations (CFR),10CFR,49CFR and International Air Transport Association (IATA). 1.1 This procedure incorporates:

Positive identification of sample (s) to be removed from the Reactor pool,
Loading of irradiated sample (s) into a Transfer Cask,
Conveyance of Transfer Cask to the hot laboratory,
Transfer of samples into hot laboratory hood,
Process of sample (s) into shipping container,
Preparation of transfer cask for reuse, ,
Transfer of shipping container (s) to packaging area or for In-house processing.

2.0 PRECAUTIONS AND UMITATIONS 2.1 The non-fixed contamination on any external surface of the transfer cask must be kept as low as practical. .! 2.1.1 The level of non-fixed radioactive contamination may be , determined by wiping an area of the surface concerned 1 with an absorbent material, using moderate pressure, and 1 measuring the activity on the wiping material. . 2.2 Ensure that all beta-gamma dose rate survey, contamination counting, and gamma radioisotope equipment calibration stickers have not passed the calibration due date prior to use. i ! i Rev.SL SA lh HP Date 15 Atm 1993 MURR-SAS4)0003 page 3 of 18

l q MURR SAS-00003 Hot Laboratory Preparation of Radioactive Material for Shipment

 .       2.3       Ensure that upon leaving the hot laboratory area you measure for personal external contamination by use of the Hand-foot monitor or equivalent device.

2.3.1 When the Hand foot monitor alarms-indicating external contamination, call Health Physics immediately at extension

                  #2-5217.

2.3.2 After 5:00 P.M. or Weekends call the Control Room at extension # 2-5213. t 2.4 Maintain radiation exposure As Low As Reasonably Achievable (ALARA) by use of Time, Distance, and Shielding, e g: Do not ride down the elevator with the cask containing the samples removed from the Reactor pool. 2.5 Use protective clothing:

                       . Laboratory Coats
                       . Rubber / Latex Gloves and long sleeve plastic gloves.

Safety glasses and/or Face Shield. -

2.5 ' In the event of a stuck sample or broken vial, the Reactor

                 - Services Engineer or designee must be notified immediately.                             ,

l t

                                                                                                           'I
                                                                                                       .t a

Rev. _Q SA M HP d Date 15 Anr.1943 MURR-SAS-00003 page 4 of 18 i u l

MURR-SAS-00003 . Hot Laboratory Preparation of Radioactive Material for Shipment

%       3.0 -        MATERIALS AND EOUTPMENT 3.1          Calibrated gross contamination counting equipment.

3.2 Calibrated Beta counter. 3.3 Smear papers. 3.4 Cask handling tools and equipment.

      . 3.5          Clean, uncontaminated shipping container (s):
      -3.5.1         Type, size, and quantity predetermined by shipping requirements for that day.

3.6 Protective clothing, to include: 3.6.1 Rubber / latex gloves and long sleeve plasdc gloves. 3.6.2 Laboratory coats. 3.6.3 Safety glasses or face shield. 3.7 Bron yellow tape, one inch wide. 3.8 Sample Pull Sheet, Attachment 2 3.9 - Sample Sheet. Attachment 3 ! 3.10 Sample Shipment Information Sheet, Attachment 4 3.11 Permanent marking pen (black ink). 3.12 Kay Dries 3 Rev._Q_ SA @) HP d Date 15 Anr.1993 MURR-SAS40003 page S of 18 -

              +e,- =             =    v

MURR-SAS-00003 Hot Laboratory Preparation of Radioactive Material for Shipment. 4.0 DEFINITIONS 4.1- Activity: Is a measure of the quantity of radioactivity emitted by a radioisotope and is used to determine the amount of radioactive material which may be transported in various , types of packaging. , 4.2 Hot Laboratory: A controlled area to process radioactive materials containing the following: ; 4.2.1 A hood which exhausts to the Reactor air exhausts and a drain - for liquids to hot waste. 4.3 Radioactive Contents: The radioactive material together with any contaminated solids, liquids and gases within the package. 4.4 Radioactive material: Any material having a specific activity , greater than 70 KBq/kg (0.002 uC1/g). ; 4.5 Samole Loc Books: These log books (two) are located in the ' Control Room and designated as the:

Flux Trap, H1, and BPLS (Bulk Pool Lead Shield). .

Book and,

Silicon Book.

The log books are broken down into sections designated to , correspond with the reactor irradiation and in-pool' storage area. j 4.5.1 " Sample Run Sheets" are placed in the appropriate Section i of the log books during irradiation of the sample, after which, they are moved to the Storage Section. 4.5.2 The stored position is recorded on the Sample Run Sheet. 4.5.3 The Flux Trap, H1, and BPLS Book consists of the following . sections: Flux Tray Loading Sheet, Tube A. Tube B, Tube C, H1, BPLS (Bulk Pool Lead Shield), Bisco, Storage, Reuter , Stokes, and Samples in use. 4.S.4 The Silicon Book consists of: J-1, K-2, R (Red, also known ., as "J") LL3, L positions, N positions, B (Blue, also known as 1), Y (Yellow, also known as H), G (Green also know as G), Bin Storage, and Sample Storage. Rev. .Q SA b HP M Date 15 Aor.1943 MURR-SAS-00003 page 6 of IS' , 1 i

.)

1

MURR-SAS-00003 Hot Laboratory Preparation of Radioactive Material for Shipment 4.5 Shall. Must. Should: 4.5.1 Sha,it Regulatory Commitment to Code of Regulations, 10CFR,49CFR and 1ATA Dangerous Goods Regulations. 4.5.2 Must: MURR Internal Commitment to 10CFR, 49CFR and IATA Regulations.

4.5.3 Should

Should be accomplished; not required. 4.6 Shinoine container: To contain the sample (s) during transport: Can be a lead pig (2 LB. to 30 LB), or a depleted uranium shield. 4.7 Soecific Activf tv: The activity of the radionuclide per unit weight of that nuclide. 4.8 Transfer Cask: Used to transport samples within the facility. 4.8.1 The Orange Roll Up Cask is included as a transfer cask.

5.0 RESPONSIBILITIES

5.1 Reactor Services Encineer: Ensure that all shipments of radioactive material conform to applicable Regulations of 10CFR,49CFR, and IATA. Provide properly certified packages for shipment of radioactive materials. , 5.2 Health Physics Manager: Provide Health Physics (HP) support as required to Service Applications Group for preparation of radioactive material shipments. 5.3 Reactor Onerations Manager Provide round the clock Operations support as required to Service Applications . Group for irradiation of samples received. Rev. S_. SA !b HP b Date I S Anr.1993 MURR-SAS-00003 page 7 of 18

1 MURR-SAS-00003 Hot Laboratory Preparation of Radioactive Material for Shipment 6.0 PROCEDURE ; i 6.1 Ensure that Consignees (Receivers) for MURR Shipments of radioactive materials are properly authorized to receive ; the Type, Form, and Quantity of such material in accordance l with Provisions of 10CFR. 6.2 The following unique characteristics of each shipment Shall be maintained throughout Receipt, Safety Analysis, ' Preparation for Irradiation, Irradiation, Post Irradiation Processing, Packaging, and Documentation: 6.2.1 Material Description, ! 6.2.2 Amount (Mass), , 6.2.3 isotopes, ! 6.2.4 Activity, . 6.2.5 Destination, 6.2.6 Recipient's License Number, Amendment Number and Expiration Date or certificate in accordance with 10CFR. 6.2.7 MURR Identification Number. 6.3 Data integrity must be maintained by documented Control ' Check sheets with Independent Verification at critical points in the process. i 6.3.1 The " Performer" of a shipping process and " Independent

Redundant Verifier" must not be the same individual.

7 6.3.2 The Independent Verifier must also be Qualified to perform the Task. 6.4 MURR Personnel involved in any Task within the scope of this Procedure will receive Documented Initial and Annual Refresher Training applicable to that Task in accordance with 49CFR172 Subpart H- Training. > a i Rev. _Q SA D - HP I- Date 15 Anr.1993 MURR-SAS-00003 page 8 of 18 - ,

       - - .                   _ ~ _ - -                         .c                   ,

I J MURR-SAS-00003 Hot Laboratory Preparation of Radioactive Material for Shipment HOT LABORATORY FLOW CHART l a 7.0 I 7.0.1 The Hot Laboratory Flow Chart (Attachment 1) involves series and parallel steps labeled in accordance with the Procedure 1 Step numbers and must be adhered to by the Shipping ; Department Personnel unless otherwise noted. i 7.0.2 Series steps of the flow chart must be accomplished in ; sequential order. 7.0.3 Some parallel steps are alternatives. Parallel steps of the flow l chart may be accomplished in sequential order or at the same l time, whichever is the most efficient, for example: ! 7.0.3.1 Step 7.5 ( Prepare Shipping Containers and Hot Laboratory) does not have to be completed immediately after Step 7.1 ; (Determine Shipment Type and Prioritize) but must be completed prior to Step 7.6 (Remove Can from Cask). 7.0.4 Processing of the radioisotopes prior to packaging for shipment is accomplished in cooperation with MURR ! t Operations (OPS),- Health Physics (HP) and Service Applications (SA) Departments. j 7.1 DETERMINE SHIPMENT TYPE AND PRIORITIZE Use the Samole Pull Sheet (Attachment 2): Review specified . shipping container to determine if appropriate and prioritize the shipping orders set for the day. 7.1.1 The Service Applications Section Leader-Shipping or Designee will determine priority based on prior knowledge and/or discussion with consignees. 7.1.2 General Guidelines to determine shipping priority:

1. In general, " Human Use" will have the highest priority.

2. Samples which have been retained beyond their requested ship date will have the next highest priority.

3. Others are:

Long lived isotopes,
Standard Air (two day delivery service) 7.1.3 "A" Priority samples are high-lighted in pink on the Samole Pull Sheet (Attachment 2).

7.1.4 "B" Priority samples are high-lighted in blue on the Samole Pull Sheet (Attachment 2). Rev.1 SA Nf HP Date 15 At'r.1993 MURR-SAS-OOOO3 page 9 of 18

MURR-SAS-00003. Hot Laboratory Preparation of Radioactive Material for Shipment 7.2 PREPARATION FOR SAMPLE REMOVAL FROM POOL 7.2.1 Procure cask and check for:

Safety rod and safety pin are in place.
Proper operation of the lid and cable.

7.2.2 Transport Transfer Cask and Samole Pull Sheet (Attachment 2) to the Control Room. 7.2.3 Remove the Samole Sheet.(Attachment 3) from the Control Room Samole Loc Book in accordance with the-information provided by the Samole Pull Sheet (Attachment 2). 7.2.4 Verify the following information from the Samole Pull Sheet: (Attachment 2) and Sample Sheet (Attachment 3): [

Can number
Company / Destination 7.3 REMOVE SAMPLE (S) FROM POOL 7.3.1 Qualified Shipper ensures can ID number corresponds to Samole Pull Sheet (Attachment 2) and Samole Shioment Information Sheet (Attachment 4).

NOTE: Sample (s) pulled from pool must read 10R/hr or less. , 7.3.2 Operators assisted by Quallfled Shippers and Health Physics: 7.3.2.1 Monitor sample as it is being pulled. 7.3.2.2 Load sample (s) into transfer cask. 7.3.2.3 Install lid on cask. 7.3.2.4 Secure lid on cask with safety rod and safety pin. 7.3.2.3 Health Physics monitor cask for dose rate. Rev.3_ SA M HP Date 15 Anr.1993 MURR-SAS-00003 page 10 of 18

MURR-SAS-00003 ' Hot Laboratory Preparation of Radioactive Material for Shipment 7.4 IRANSPORT SAMPLE (S) TO HOT LABORATORY

                        ** CAUTION **

Personnel transpordng cask to hot laboratory must practice ALARA , (TIME, DISTANCE, SHIELDING)

DO NOT RIDE ELEVATOR WITH CASK. 7.4.1 Transfer cask is transported to the hot laboratory via the Containment elevator. 7.5 PREPARE SHIPPING CONTAINERS AND HOT LABORATORY 7.5.1 Ensure shipping container is clean of all previous ' identifiers:

If the shipping container has previously been used, remove all orior markines.

7.5.2 Use the Samole Shloment Information Sheet (Attachment 4), Step 1, and permanent marking ink pen to mark and identify the shipping container with the following information: A. Sample can number, B. Company, C. Isotope and, , D. MURR Identification number. 7.3.2.1 If a vial pig is used for an in-house sample the above information is written on 3" wide tape and then applied to the vial pig. 7.5.3 Verify the information of Step 7.5.2 on the shipping shield before placing in processing area. 7.5.4 Performer and Observer initial Step 1 completion, ( Attachment 4). 7.5.5 Qualified Shipper dons protective clothing:

Safety glasses and/or face shield
Laboratory coat.
Rubber / latex gloves and long sleeve plastic gloves.

Rev. _Q_ SA _.lld HP Date 15 Acr.1093 MURR-SAS-00003 page 11 of 18

I MURR-SAS-00003 Hot Laboratory Preparation of Radioactive . Material for Shipment 7.5.6 Prepare laboratory table to receive samples for processing: ~. 7.5.6.1 Cover table area with Kay Dries @. 7.5.6.2 Place radiation meter on table. 7.5.6.3 Turn radiation meter "ON" and set meter to 10 R/hr. scale. 7.5.7 Turn hood light "ON". 7.5.8 Check battery to audible dosimeter, type ACCU-CHIRP or equivalent, located to the right of hood opening. 7.5.9 Verify operation of audible dosimeter. 7.5.10 Verify sample can size from description in the Sample Description Block of Samole Shloment Information Sheet (Attachment 4), for example: OPEN 2X5" FLOODED CAN, TWO BUNDLES OF VIALS IN FOIL 7.5.11 Adjust can opener to accommodate correct sample can size. . 7.6 REMOVE CAN FROM CASK CAUTIONS:

BEFORE UNLOADING THE SAMPLE, CLEAR THE ROOM OF ALL UNNECESSARY PERSONNEL.
DO NOT DRIP WATER FROM TRANSFER CASK ON THE CASK, FLOOR, TABLE, etc.

7.6.1 Remove the can from the transfer cask. 7.6.L1 Put th'e removed can in the hood behind the lead wall. 7.6.2 For preparation of the transfer cask for reuse: Proceed to Sten 7.13 7.7 IDENTIFY CAN 7.7.1 Identify and verify the can by comparing the can inscription with Samole Shinment information Sheet. (Attachment 4), Step 2, when applicable. 7.7.2 Performer and Observer initial to verify sample can is correct (Attachment 4) Step 2. Rev.1 SA N HP Date 15 Anr.1943 MURR-SAS-00003 page 12 of 18 9

     , .                    .-.        --. =-

MURR-SAS-00003 Hot Laboratory Preparation of Radioactive Material for Shipment 7.8 OPEN CAN NOTE IF THE CAN IS A FLOODED RUN, FIRST DRA1N WATER INTO FUNNEL ON LEFT SIDE OF HOOD. 7.8.1 Load the can to be opened in the can opener. 7.3.2 Tighten the base of the can opener on the can. - 7.8.3 Turn "on" the can opener. CAUTION: BE CAREFUL NOT TO FORCE THE BLADE OF CAN OPENER. THIS MAY CA USE THE CAN TO DENT OR BEND AND WILL MAKEIT DIFFICULT TO REMOVE THE SAMPLE. 7.8.4 Slowly move the blade in on the can. 7.8.5 Shut ."off" the can opener when can is opened. 7.8.6 Place the lid in the " hot waste" large can for disposal. 7.3.7 Move the cutting edge of the can opener away from the can. 7.9 PROCESS SAMPLE NOTE: FLOODED SAMPLES ARE TO BE PLACE IN PLASTIC-ZIP LOCK BAGS AND SEALED. 7.9.1 View the sample in the mirror at the top of the hood. 7.9.1.1 .If sample does not appear to be intact. stop and contact the Service Applications Section Leader-Shipping or Designee before proceeding. NOTE ENSURE SHIPPING CONTAINER IS READY TO RECEIVE THE SAMPLE per Step 7.S (Preparation) WORK QUICKLY TO MAINTAIN ALARA. 7.9.2 Using tweezers, remove sample from can. 7,9.3 Identify and verify the sample by comparing the sample with the descripdon shown in the Sample Description Block located in the upper right hand corner of Samole Shinmeru Information Sheet (Attachment 4), e.g.: OPEN 2X5" FLOODED CAN, TWO BUNDLES OF VIALS IN FOIL , 7.9.4 Performer and Observer initial Samnle Shinment information Sheet (Attachment 4), Step 3. Rev.S SA HP h Date 15 Aor.1993 - MURR-SAS-00003 page 13 of 18 t r w v

MURR-SAS-00003 Hot Laboratory Preparation of Radioactive Material for Shipraent 7.10 LOAD INTO SHIPPING CONTAINER 7.10.1 Identify correct shipping container. I 7.10.2 Load identified sample into appropriate shipping container. 7.10.3 Performer and Observer initial Samole Shinment Information Sheet (Attachment 4), Step 5, indicating sample is loaded into correct shipping container. 7.10.4 Perform dose measurements on shipping container. 7.10.4.1 Record dose reading in top, right hand corner (above Description Block) on Samole Shinment Information Sheet (Attachment 4). I 7.10.4.2 If container is for in- house, put dose measurement on container, e.g., zip lock bag or lead pig. 1 7.10.5 Remove gloves. 1 7.10.6 Put on fresh gloves. l I 7.10.7 Swipe shipping container. l 7.10.7.1 Use Hand; Foot Monitor for personal contamination check on l way to reading swipe of container. ')l 7.10.7.2 Read swipe to monitor for gross contamination. 7.10.7.3 If swipe indicates contamination: decontaminate with masaline until further swiping indicates free of contamination. 4 1 7.10.8 After the swipe is read, indicating container is free of ) contamination: ! 7.10.8.1 Tape only rigid shipping container (s) with Bron one inch ] wide yeMow tape. I 1 v' Rev. Q__' SA HP Date 15 Anr.1993 MURR-SAS-00003 page 14 of 18

                                                                                              'l    ,

MURR-SAS-00003 Hot Laboratory Preparation of Radioactive Material for Shipment . 7.10.9 The shipping container may go to:

1. In-house User: Proceed to Step 7.11 or, -l

2. Packaging Area: Procaed to Step 7.12. ,

      .7.11       SIIIPPING CONTAINER TO IN-HOUSE USER                                           >

7.11.1 If sample is in a bag for in-house user, place sample in the I' cavs by the hood. 7.11.1.1 If a lead pig is used, place in holding area. i 7.12 SHIPPING CONTAINER TO PACKAGING AREA : 7.12.1 If sample is in a lead pig or poly vial: I 7.12.1.1 Tape top of container, twice around, with 1" Bron yellow tape. i 7.12.2 Place container in the shipping area cave. 7.12.3 Remove gloves and dispose of in proper Hot Waste receptacle. 7.13 PREPARE TRANSFER CASK FOR REUSE 7.13.1 Clean transfer cask if required in preparation for future samples. 7.14 HOT IABORATORY CLEANUP 7.14.1 Put on fresh gloves. 7.14.2 Remove can from can opener. , 7.14.3 Place removed can into " hot waste" storage area in hood. j 7.14.4 Remove gloves and dispose ofin proper Hot Waste receptacle. 7.14.5 Put on fresh gloves. I

                                                                                              'i i                                                                                            .

- + Rev. S_. SA b HP d Date 15 Aor.1993 MURR-SAS-00003 page IS of 18 3 i

I MURR-SAS-00003 Hot Laboratory Preparation of Radioactive Material for Shipment , 1 7.14.6 Decontaminate the following with masaline: 7.14.6.1 Floor from end of table toward the hood. 7.14.6.2 Hood handles and, 7.14.6.3 Tools. 7.14.7 Wipe hood lid. 7.14.8 Swipe hood lip and floor in work area to check for contamination. 7.14.9 Use Hand. Foot Monitor for personal contamination check on l way to reading swipes. 7.14.10 Read swipe to monitor for gross contamination. , 7.14.11 If swipe indicates contamination: Repeat decontamination-with masaline until further swiping indicates free of contammation. 7.14.11.1 Floor from end of table toward the hood, 7.14.11.2 Hood handles and, 7.14.11.3 Tools. 7.14.12 Wipe hood lid.- J 7.14.13 Swipe hood lip and floor in work area to check for i contamination. 7.14.14 Use Hand, Foot Monitor for personal contamination check on way to reading swipes. f b o I de Rev. _0_. SA b HP Date 15 Anr.1903 MURR-SAS-00003 page 16 of 18 , i l l

MURR-SAS-00003 Hot Laboratory Preparation of Radioactive Material for Shipment 7.15 COMPLETE PAPER WORK 7.15.1 The following paper work is transferred between Service Acolications-Shioninn and Service Acclications-Isotooes:

Sample Pull Sheet Attachment 2.
Sample Sheet, Attachment 3.
Sample Shipment Information Sheet. Attachments 4.

7.15.2 Originally, the above paper work is generated by Service Aeolications-Isotones and transferred to Service Acclications-Shinoinn. 7.15.3 Prior to when the Shippers go to the hot cell the Samole Sheet is returned to Isotopes. 7.15.3.1 Isotopes enters the information of the Samole Sheet into the Data Base. 7.15.3.2 The Samole Sheet is returned to Shipping. 7.15.4 After the package is shipped the Documentation Packet, which includes, the Samole Sheet and Samole Shioment Information Sheet is returned to Isotopes where it remains until Billing. 7.15.4.1 The Samole Pull Sheet is filed by the Shipping Department. 7.15.5 After the Billing, the paper work is transferred to Service Applications Section Leader- Shipping. 7.15.6 The Service Applications Section Leader- Shipping:

Files the paper work in numerical order and maintains this :

paper work for a period of three years.

Performs sampling of the documents for accuracy.

7.15.7 After a three year period, this paper work is sent to the University of Missouri Storage. l Rev. _Q SA N HP Date 15 Aor.1943 MURR-SAS-00003 page 17 of 18

MURR-SAS-00003 Hot Laboratory Preparation of Radioactive Material for Shipment ATTACHMENTS ~ s ; A. Hot Laboratory Flow Chart, (Attachment 1). B. Sample Pull Sheet, ( Attachment 2). . C. Sample Sheet, (Attachment 3). D. Sample Shipment Information Sheet, (Attachment 4). REFERENCES j A Health Physics Standard Operating Procedures:

1. HP-4: Handling Radioactive Materialin MURR Pool.

2. HP-12: Transfer of Radioactive Material within MURR building. l t

f 9 a f l i e i Rev. .,0 SA HP Date 15 Anr.1993 MURR-SAS-00003 page 18 of 18 l

-)

i

MURR-SAS-00004 Shipment of Radioactive Materials 1 a t Procedure Cover Sheet , 1 Sf0RR-SAS-00004 0 17 February 1993 (Procedure) (Revision) (Date) -i Shinment of Radioactive Nf aterials - (Procedure Title) Prepared By bdd< L ; (Sig?iature) Reviewed By b6 JAAfY315@d83v ] (Signature) Revision Summarv I Fev..

Date sienificant summarv .

0 17 Feb. 93 Yes Original l l i i l l 1 Rev. D_. SA HP Date 17 Feb.1993 blURR-SAS-00004 page 1 of 29.

                  .,r-. .e

MURR-SAS-00004 Shipment of Radioactive Materials TABLE OF CONTENJS SECTION PAGE NUMBER

1.0 Purpose and Scope

4 2.0 Precautions and Limitations 4 3.0 Materials and Equipment 6 4.0 Definitions 7 5.0 Responsibilities 19 6.0 Procedure 20 , t 7.0 Packaging Flow Chart, Type A 21 7.1 Qpalified Shipper Check-in 21 7.2 Receipt "In-box" 22 7.3 Prepare Package Packet 22 , 7.4 Package Packet "In-box" 22 7.5 Package Preparation 23 l 7.6 Package Placed in Storage 25 7.7 Prepare Shipping Papers 25 7.8 Documentation Package "In-box" 25 7.9 Shipping Paper Packet "In-box" 25 7.10 Complete Shipping Papers 26 7.11 Final Packaging Checkout "In-box" 27 l 7.12 Final Packaging ~. 27 7.13 Final Verification "In-box" 28 7.14 Final Verification 28 I I Rev. O_ SA/ HP Date 17 Feb.1993 MURR-SAS-00004 page 2 of 29.

MURR-SAS-00004 ~ Shipment of Radioactive Materials 7.15 Shipping Summary Form 28 3 7.16 Release to Courier 28 7.17 Emergency Response Information 29 7.18 Notification of a Shipment. '29 References 29 d 9 h i N 1 J 1 Rev.IL S HP Date 17 Feb.1993 MURR-SAS-00004 page 3 of 29. a-,- -----t - e- - . _ . - . . g g ,

h!URR-SAS-00004 Shipment of Radioactive biaterials 1 SillPhf ENT OF RADIOACTIVE hfATERIAL ! i 1.0 PURPOSE AND SCOPE This Procedure provides instructions for the Packaging and Final Shipment as specified in Section 4.0 of this Procedure of Type A, non-waste radioactive materials received at Reactor Services for Shipment: To ensure Compliance with applicable 1 Regulations of Code of Federal Regulations (CFR),10 CFR, l 49CFR and International Air Transport Association (IATA). 2.0 PRECAUTIONS AND LibilTATIONS l 2.1 Each container or cask used for the Shipment of Radioactive hfaterials Shall be approved for use and shall conform to f

                    - Department of Transportation (DOT) Specifications contained .

in 49CFR and International Air Transport Association (IATA), 2.1.1 Certificates of Compliance shall be maintained on file for each container or cask. 2.2 Applicable container specifications must be specified by purchase order. 2.2.1 Purchase orders must stipulate that all containers to be used for shipment of Radioactive biaterials bear a marking or label to show conformance to the applicable Specification, e.g., i TYPE A. 2.3 Prior to any shipment of Radioactive biaterial, it shall be determined that the consignec (receiver) is licensed to receive that material. 2.4 A package of Radioactive hfaterial shall not be transported unless it is properly described, classed, marked, packaged and labeled. 2.5 If the Radioactive biaterial exceeds any of the applicable limits in of 49CFR or IATA hianual, the Reactor Services 1 . Engineer or designee must be notified immediately. 2.5.1 - The Radioactive hf aterial shall not leave h1URR until the problem has been resolved. . 2.6 Air freight shipments of " Excepted Quantitle-s" and "hfedical". Radioactive hfaterials may be consigned to Passenger Aircraft

in accordance to 49CFR. =i 2.6.1 All other Radioactive blaterial shipments by Air shall be -- consigned to " Cargo Only" Air Transportation. Rev D_, SA k HP Date 17 Feb.1993 blURR-SAS-00004 page 4 of 29.

+,

q

                                                                                                                .l
                                                                                                                   +

h!URR-SAS-00004 Shipment of Radioactive biaterials t 2.7 Air Freight Shipment quantity limits shall be in accordance i with the Requirements of 49CFR and IATA Regulations. 2.8 The non-fixed contamination on any external surface of any package shall be kept as low as practical and, under normal .. conditions of transport, must not exceed the levels specified in 49CFR and 1ATA Regulations. . 2.8.1 The level of non-fixed Radioactive contamination may be determined by wiping an area of 300 square centimeters of the surface concerned with an absorbent ma'terial, using : moderate pressure, and measuring the activity on the wiping 'i material. 2.9 Radioactive bfaterials having other hazardous characteristics shall be allocated packing groups I, II, or 111, as appropriate, by application of the grouping criteria in accordance with 49CFR and IATA Regulations. 2.10 Ensure that all beta-gamma dose rate survey equipment and meter stick calibration stickers have not passed the calibration due date prior to use.

         '2.11      The requirements for each package containing fissile material shall comply in accordane t with 49CFR.                                               ,
                                                                                                                'i P

Rev.LL SA . IIP Date 17 Feb.1993 MURR-SAS-00004 page 5 of 29. u

          - -        - -      -.         . . - .   -         ..          .              -    ~     . ..    .

4 . j i l l h!llRR-SAS-00004 Shipment of Radioactive hfaterials )

 ^.                 3.0      h1ATERIAIS AND EOUIPh1ENT 3.1      Capintec Radioisotope Calibrator, CRC-5Ril or equivalent.

3.2 Eberline, blodel Rht-19 or equivalent.

3.3 Eberline , blodel BC-4 or equivalent. 3.4 lon Chamber Survey meter. 3.5 Radioactive Placards meeting the requirements of 49CFR and ' IATA.

3.6 Labels

3.6.1 Radioactive White I 3.6.2 Radioactive Yellow 11 3.6.3 Radioactive Yellow 111 3.6.4 Empty j 3.6.5 Cargo Aircraft Only 3.6.6 Package orientation Label (This Way Up Arrows') , 3.6.7 Subsidiary risks labels i 3.6.8 h1URR blodels labels 3,7 Smear papers 3.8 Cask handling tools and equipment 3.9 Seals 3.10 Shipping papers: l 3.10.1 Air freight .[ 3.10.2 Ground freight 3.11 Calibrated meter stick , 1

                                                                                                             ?
                                                                                                             ?

( Rev. D_. SA llP ' ' Date 17 Feb.1993 blURR-SAS-00004 page 6 of 29. ;

   ._ 1               . ._.           _                    ._     -    ..                             _

h!URR SAS-00004 Shipment of Radioactive hfaterials

~'

3.12 DOT- 12B40 boxes with the following information: 3.12.1 Label: USA DOT Type A Radioactive hfaterial Specification Certified by University of blissouri Research Reactor Columbia, bio. 65211 3.12.2 label: RADIOACTIVE b1ATERIAL N.O.S. UN2982 , 3.13 Expanded Polystyrene packing for 40-UN151313 box 3.14 Ellisco Tear strip bright tinplate can to accept " Shipping Pig"

                            / container (can) marked with Radioactive (yellow / magenta)                ,

tape.

4.0 DEFINITIONS

4.1 M The maximum activity of " SPECIAL FORht" Radioactive material permitted in a Type A package. 4.1.1 Values of Al for most Radionuclides are given in 49CFR and IATA Regulations. 4.2 2 The maximum activity of Radioactive material, other than "Special Form" Radioactive material, permitted in type A package. 4.2.1 Values of A2 for most Radionuclides are given in Tables of 49CFR and IATA Regulations. 4.3 Recouerel (Ba): Is the standard unit of measure for the Radioactivity of a Radionuclide used in IATA, Dangerous Goods . Regulations. One Bq equals one decay per second. 4.3.1 Gicabecouerel (GBa) : One GBq = 1,000,000,000 Bq or IE9 Bq. 4.3.2 Terabecouerel (TBa) : One TBq - 1,000,000.000.000 Bq or - 1E12 Bq. 4.3.3 The Bq replaces the older unit for activity, the Curie (Ci). . 4.3.3.1 One ci is equal to 37 GBq. B Rev. IL SA IIP Date 17 Feb.1993 MURR-SAS-00004 page 7 of 29.

        - -     m   ,       +-

                                                          , - _ ~      _- _-               - - . .     . . -
                                                                                                              .i h!URR-SAS-00004                                    Shipment of Radioactive blaterials
  ~J 4.4       Conversion Factors: Table shows conversion factors to four significant figures.

4.4.1 To convert To hfultiniv by: Ci GBq 37.00 TBq Ci 27.03 4.5 External' Contamination: Is the non-fixed Radioactive ' contamination on any external surface of any package.it shall be kept as low as practical and, under normal conditions of transport, shall not exceed the levels specified in' 49CFR and IATA Regulations. 4.6 Fissile material: means any material consisting of or containing one or more fissile Radionuclides. Fissile materials are plutonium-238, plutonium-239, plutonium-241, uranium-233, and uranium-235. Neither natural nor depleted uranium are fissile material. Fissile matedals are classified according to the controls to provide nuclear criticality safety during transportation, as provided in 49CFR. ! 4.7 1.ow snerific activitv material HSA) means any of the , following: 4.7.1 Uranium or thorium ores and physical or chemical concentrates of those ores. ' 4.7.2 Unirradiated natural or depleted uranium or unirradiated ; natural thorium. 4.7.3 Tritium oxide in aqueous solutions provided the concentration ., does not exceed 5.0 millicuries per milliliter. ! 4.7.4 blaterial in which the radioactivity is essentially uniformly distributed and in which the estimated average concentration - of contents does not exceed:

4.7.4.1 0.0001 millicurie per gram of Radionuclides for which the A2 quantity is not more than .05 curie; 4.7.4.2 0.005 millicurie per gram of Radionuclides for which the A2 is more than .05 curie, but not more than.1 curie; or 4.7.4.3 0.3 millicurie per gram of Radionuclides for which the A2 quantity is more than 1 curie. !

I= l_ l Rev.D SA$h2 ilP - Date 17 Feb.1993 MURR-SAS-00004 page 8 of 29. -

                                                                                                              'l o

I h!URR-SAS-00004 Shipment of Radioactive hfaterials 4.7.5 Objects of non-radioactive material externally contaminated with radioactive material, provided that the radioactive material is not readily dispersible and the surface contamination, when averaged over an area of I square meter, does not exceed 0.0001 millicurie (220,000 disintegration's per minute) per square centimeter of Radionuclides for which the A2 quantity is not more than .05 curie, or 0.001 millicurie (2,200,000 disintegration's per minute) per square centimeter for other Radionuclides. 4.8 Non-fixed Radioactive hfaterial: Radioactive contamination that can be removed from a surface by wiping with a dry smear. t 4.9 Normal Form Radioactive Materiah Radioactive biaterial which has not been Qpalified as " Special Form" Radioactive hfaterial, , 4.10 Shinnine Technician (Shinner) is defined to be any person in the Shipping Group: 4.10.1 Shipper, Trainee: Can neither Perform or inspect a Task. 4.10.2 Shipper, qualified: Is an individual who has completed the Required Doc 6mented Training to perform a specific Task. 4.1-0.3 Shipper, Certified: Is Qpalified to perform all aspects of Shipping as documented by Training. 4.11 Snecial Form Radioactive Sfaterial: Radioactive blaterial is either an in-dispersible solid Radioactive hfaterial or a sealed capsule containing Radioactive blaterial. 4.11.1 Special Form Radioactive hfaterial shall meet the requirements of 49CFR and IATA regulations. 4.11.1.1 Ifit is in a sealed capsule, that capsule shall be so constructed that it can only be opened by destroying. 4.11.1.2 The Special Form Radioactive h!aterial shall have at least one dimension not less than 5 mm. 4.11.1.3 The Special Form design shall have received unilateral approval. r 9

s. r Rev. f.l_ SA - 0 4 llP Date' 17 Feb.1993 MURR-SAS-00004 page 9 of 29.

htURR-SAS-00004 Shipment of Radioactive htaterials , 4.12 Shall. Must. Should i 4.12.1 Shall : Regulatory Commitment to Code of Federal Regulations, 10CFR,49CFR and IATA Dangerous Goods Regulations. 4.12.2 Mun : blURR Internal Commitment to 10CFR,49CFR and IATA Regulations. 4.12.3 Should: Recommended; not required. 4.13 Snerific Activitv: The Activity of the Radionuclide per unit mass of that nuclide. 4.14 Iransnort Index Number (Tit Radioactive hfaterial Ontv: The dimensionless number (rounded up to the first decimal place)- placed on the label of a package to designate the degree of control to be exercised by the carrier during transportation. 4.14.1 The TI number is determined in accordance 49CFR and IATA Regulations. 4.14.2 The transport index is determined as follows: 4.14.2.1 The number expressing the maximum radiation level in millirem per hour at one meter (3.3 feet) from the external - surface of the packaging; or 4.14.2.2 For fissile class !! packages or packages in a fissile 111 shipment, the number expressing the maximum radiation , level at one meter (3.3 feet) from the external surface of the ; package, or the number obtained by dividing 50 by the _ allowable number of packages, which may be transported ' together, whichever is larger. 4.15 Tvne A Packacinm A type "A" package shall not contain activities greater than the following: 4.15.1 For "Special Form" Radioactive Material the value of Al is listed in Tables of 49CFR and IATA Regulations. 4.15.2 For other Radioactive blaterial the value of A2 is listed in . Tables of 49CFR and IATA Regulations. 1 4.16 Tvne B Packacine The only limits on the activities contained . . In type B packages are those prescribed on their approval certificates in accordance with the Code of Federal Regulations,10CFR and 49CFR. - Rev.lL SA ilP r Date 17 Feb.1993 blURR-SAS-00004 page 10 of 29. T - y , .e- - e 4,+ .w..+...~ w y

                                                                                      ~~         . -      -....       .  ,

t billRR-SAS-00004 Shipment of Radioactive hfaterials ~ 4.17 Primary Hazard label: Identifies governing hazard for a package. Radioactivity is normally the governing hazard for packages shipped by 51URR. Radioactive material shall be labeled in accordance with the guidelines of the following categories: 4.17.1 White ! - The maximum radiation level at any point on the external surface is 0.5 mrem /hr. The Transport Index is not applicable. 4.17.2 Yellow 11 - The maximum radiation level on any point on the external surface is more than 0.5 mrem /hr but not more than 50 mrem /hr. The Transport Index is more than 0 but not more than 1. 4.17.3 Yellow III - The maximum radiation level at any point on the ' external surface is more than 50 mrem /hr. but not more than 200 mrem /hr. The Transport Index is more than 1 but not more than 10. , 4.17.3.1 Packages with contact dose rates greater than 200 mrem /hr or with a Tl greater than 10 shall be shipped as an Exclusive Use Shipment. 4.17.4 Packages and overpacks shall be assigned to Category White I, . Yellow II, or Yellow 111in accordance with 49CFR and IATA Dangerous Goods Regulations. : 4.17.5 Shipper's Declaration for Dangerous Goods: Will be completed for each and every shipment containing Dangerous Goods so defined or Classified in 49CFR and IATA, unless it is stated that one is not required (Limited Quantities). i 1 L: Rev.R_- SA A llP Date 17 Feb.1993 ' blURR-SAS-00004 page 11 of 29. l c i ymnw- , y n y . , - - -

                                                                            - . - - -         w=        -       ,   e-.

1 l l MURR SAS-00004 Shipment of Radioactive Materials - l l 4.18 PACKAGING PROCEDURE USED FOR TEST CERTIFICATION OF11SA DOT MURR Sfodel 1000 Shiocine Container. 4.18.1 Authorized contents for package identification of MURR 1000 is Solid Normal Form Type A Radioactive Material. 4.I8.2 Description of package:

Sample is shielded by a MURR lead pig No.1288 with hole diameter between 0.5" and 3".
MURR lead pig is sealed with Bron 1 " yellow vinyl tape.
The primaty containment is an Blisco round tearstrip bright tinplate 404 x 7" can.
Bilsco can is inserted in two expanded polystyrene # 1 density modified bead packing inserts (MURR dwg No.1160) with Wunderlich 15.5" x 13.5" x 0.188 " fiberboard endcaps.
The polystyrene is strapped with Miller-Bevco 9 mm strapping # 06MG0912998WH.
The polystyrene is inserted in a Wunderlich box # 151313.
The Wunderlich box is sealed with 3" Scotch brand tape type 3 M-355.

4.18.3 Packaging Procedure:

Sample is placed in the lead pig. I
The lead pig is sealed by Bron 1" yellow tape.
The lead pig is sealed in the Blisco can.
The Blisco can is placed in two ' expanded polystyrene # 1 packing inserts with fiberboard endcaps.
The polystyrene is secured by four crossing Miller-Bevco 9 mm straps.
The strapped polystyrene is placed in the Wunderlich fiberboard box.
The box is secured by applying 3" Scotch brand tape type 3M-355 to all sears.

Rev. !L SA HP Date '17 Feb.1493 MURR-SAS-00004 page 12 of 29. T

_~ . . - - - . - . - , ._. . . .- .- . .- - l MURR-SAS-00004 - Shipment of Radioactive hfaterials

4.19 PACKAGING PROCEDURE USED FOR TEST CERTIFICATION OF. USA DOT hlDRR Model 1100 Shinnine Contajngt 4.19.1 The authorized contents for package identification of MURR 1100 is Solid and Liquid Normal Form Type A Radioactive blaterial. 4.19.2 Description of Package:

Sample contained in a Secondary containment.
Secondary containment is scaled by Bron 1" yellow vinyl tape or crimp seal.
Kimpak = 64290-00 is used to absorb twice the liquid contained.
Shielding is a MURRlead pig a 1288 with a hole diameter between 1.25" and 3.0 ".
MURR lead pig # 1288 is sealed with Bron 1" yellow vinyl tape.
The primary containment is an Ellisco round tearstrip bright tinplate 404 x 7" can.
Ellisco can is inserted in two expanded polystyrene # 2 l density modified bead packing inserts (NURR dwg. # 1180) I with Wunderlich 15.5" x 13.5" x 0.188" fiberboard endcaps.
The polystyrene is strapped with Miller-Bevco 9 mm >

strapping = 06MG0912998WH.

The polystyrene is inserted in a Wunderlich box

                                    #40UN151313.

The Wunderlich box is sealed with 3" Scotch brand tape type .,

3 M-3 5 5. , l 1

                                                                                                               -i i

i Rev.0 SA M llP Date 17 Feb.1993 51URR-SAS-00004 page 13 of 29. 4 w . -_ _ _ _ . . _ < . - . . ,

 .     .=     .      ,      -..     .-                      .            _--               . ._

blURR-SAS-00004 Shipment of Radioactive blaterials 4.19.3 Packaging Procedure:

Sample is placed in secondary containment.
The secondary containment is sealed by Bron 1"_or crimp seal.
The secondary containment is placed in the lead pig with sufficient Kimpak to absorb twice the liquid contained in the sample.
The lead pig is sealed by Bron 1" yellow tape.
The lead pig is sealed in the Ellisco can. .
The Ellisco can is placed in two expanded polystyrene

                   -v 2 packing inserts with fiberboard endcaps.

The polystyrene is secured by four crossing bliller-Bevco 9 mm straps.
The strapped polystyrene is placed in the Wunderlich fiberboard box.

F

The box is secured by applying 3" Scotch tape type 3bt-355 '

to all seams. i t I i

Rev.H_ SA A llP Date 17 Feb.1993 MURR-SAS-00004 page 14 of 29. 1

                                                                  ~ ~ ~

blURR-SAS-00004 - - Shipment of Radioactive hfaterials 4.20 PACKAGING PROCEDliRE USED FOR TEST CERTIFICATION OFl!SA l

                     ' DOT hIliRR 51odel 1?20 Shinnine Container.

4.20.1 The authorized contents for package identification of h!URR r 1220 is Solid and Liquid Form T3 pe A Radioactive blaterial. 4.20.2 Description of Package:

Sample contained in secondary containment.
Secondary containment is scaled by Bron 1" yellow \ inyl tape or crimp seal.
Shielding is a blallinckrodt Screw Top white shipping pig-No.2.
The blallinckrodt shipping pig No. 2 is sealed by Bron 1" yellow vinyl tape.
Kimpak No. 64290-00 is used to absorb at twice the liquid contained. #
The primary containment is an Ellisco round tearstrip bright tinplate 404 x 7" can.

                     ~* Ellisco can is inserted in two expanded polystyrene # 1 density modified bead packing inserts (h1URR dwg No.1180) with Wunderlich 15.5" x 13.5" x 0.188" fiberboard endcaps.

The polystyrene is strupped with h! iller-Bevco 9 mm strapping
06htG0912998WII. j
The polystyrene is inserted in a Wunderlich box # UN151313. .
The ivunderlich box is sealed with 3" Scotch brand tape type 3bi-355.

J 1 Rev.Q_ SA /S$ llP[ Date 17 Feb.1993 M URR-SAS-00004 page 15 of 29. 1 I

                                                 .                                            \

MURR-SAS-00004. - Shipment of Radioactive Materials

              -4.20.3 Packaging Procedure:

Sample is placed in secondary containment. )
The secondary containment is sealed by Bron 1" yellow tape or crimp seal.
The secondary containment is placed in the Mallinckrodt lead pig.
The lead pig is sealed by Bron 1" yellow tape.
The lead pig is sealed in the Blisco can with sufficient Kimpack to absorb twice the liquid contained.
The Blisco can is placed in two expanded polyse.,tene #1 packing inserts with fiberboard endcapt
The polystyrene is secured by four crossing Miller- Bevco 9 mm straps.
The strapped polystyrene is placed in the Wunderlich fiberboard box.
The box is secured by applying 3" Scotch brand tape Type !

3M- 355 to all seams. 6

            .                                  m                                        .

4 hfURR-SAS-00004 Shipment of Radioactive hfaterials 4.21 PACKAGING PROCEDliRE USED FOR TEST CERTIFICATION OF L1E6 DOT SIURR hiodel 1300 Shinnine Container. 4.21.1 The authorized contents for package identification of blURR' - 1300 is Solid and Liquid Normal Form Type A Radioactive hfaterial. , 4.21.2 Description of Package:

Sample contained in secondary containment.
Secondary containment is sealed by Bron 1" yellow vinyl tape or crimp seal. >
There is no lead shielding.
Kimpak = 64290-00 is used to absorb twice the liquid contained.
The primary containment is an Blisco round tearstrip bright tinplate 404 x 7" can.
Blisco can is inserted in two expanded polystyrene
1 density modified bead packing inserts (51URR dwg No.1180) with Wunderlich 15.5" x 13.5" x 0.188" fiberboard endcaps.
The polystyrene is strapped with hiiller-Bevco 9 mm strapping F 06h!G0912998WH.
The polystyrene is inserted in Wunderlich box w UN151313.
The Wunderlich box is sealed with 3" Scotch brand tape type 3 bl-3 5 5.

1 I c l Rev.D._ SA IIP Date 17 Feb.1993 blURR-SAS-00004 page 17 of 29.

i i i MURR-SAS-00004 Shipment of Radioactive Materials

                                                                                           ] i 4.21.3   Packaging Procedure:                                                .

Sample is placed in secondary containment.
The secondary containment is sealed by Bron 1" yellow tape or crimp seal.
The secondary containment is sealed in the Elisco can with

                       -sufficient Kimpak to absorb twice the liquid contained.

The Blisco can is placed in two expanded polystyrene #1 packing inserts with fiberboard endcaps.
The polystyrene is secured by four crossing Miller-Bevco 9mm straps.
The strapped polystyrene is placed in the Wunderlich fiberboard box.
The box is secured by applying 3" Scotch brand tape type 3M-355 to all seams e

P Rev. Q SA .

                          }!P       Date 17 Feb.1993    MURR-SAS-00004      page 18 of 29.

6

I h!URR-SAS-00004 Shipment of Radioactive blaterials ; a.0 RFSPONSIBILITIES 5.1 Reactor Services Encineer Ensure that all shipments of Radioactive biaterial conform to applicable Regulations of ! 10CFR,49CFR, and IATA. Provide properly certified packages for shipment of Radioactive blaterials. 5.2 Health Phv<ics Niancer: Provide Health Physics (H.P.) support as required to Service Applications Group for preparation of Radioactive h!aterial Shipments. ; 5.3 Reactnr Onerations hfanacer Provide around the clock I Emergency Response Information concerning Radioactive ' Staterial shipments from biURR. 5.3.1 Emergency Response Information Required by Operations Control Room Operators: ;

Shipment Destination
Shipment Isotope
Shipment Activity
51URR Shipment I.D. Number
Emergency Call List.

l l Rev. D SA M IIP ' Date 17 Feb.1993 h!URR-SAS-00004 page 19 of 29. -; i

NURR-SAS-00004 Shipment of Radioactive Materials 6.0 PROCEDlJEE ~. 6.1 Ensure thz t Consignees (Receivers) of MURR Shipments of Radioactive Materials are properly authorized to receive the Type, Form, and Q antity of such materialin accordance with Provisions of 10CFR. 6.2 Ensure that proper shipping classification (i.e..) Type "A" or B, Packaging, Shipping Papers, Marking, Labeling, and Macarding are identified and maintained as the preparation for shipping proceeds. 6.3 The following unique characteristics of each shipment must be maintained throughout Receipt, Safety Analysis, Preparation for Irradiation, Irradiation, Post Irradiation Processing, Packaging, and Shipment: 6.3.1 Material Description 6.3.2 Amount (Mass) 6.3.3 Isotopes 6.3.4 Activity 6.3.5 Destination 6.3.6 MURR ID Number 6.3.7 License Number, Amendment Number and Expiration Date or DOE authorization or Certification as specified in 10CFR. 6.4 All shipments shall conform with Provisions of 49CFR,10CFR and IATA, Dangerous Goods Regulations. 6.5 Packaging performance and environmental testing or evaluation for type A Packaging used for radioactive shipments Shall meet DOT 7A Requirements. 6.5.1 Such testing or evaluation shall be documented and maintained on file. 6.6 Type B Packaging Shall meet the Requirements of MURR Quality Assurance (QA) program for shipping as required by. 10CFR. , Rev. !L. SA HP - Date 17 Feb.1993 MURR-SAS-00004 page 20 of 29. I

MURR-SAS-00004 Shipment of Radioactive biaterials 5 6.7 Data Integrity will be maintained by Documented Control Check Sheets for IISA DOT MURR models 1000,1100,1220, and 1300 shipping containers with Independent Verification at critical points in the shipping process (Pages 1 through 4, Attachment 4.) 6.7.1 The " Performer" of a Shipping Process and " Independent Redundant Verifier" must not be the same individual. 6.7.2 The Independent Verifier must also be a Qualified Shipper for that task. 6.8 MURR Shipping Personnel involved in any Task within the scope of this Procedure will receive Documented Initial and ' Annual Refresher Training applicable to that task of shipping Radioactive Material in accordance with 49CFR - Training. 7.0 PACKAGING FIOW CHART. TYPE A 7.0.1 The Packaging Flow Chart (Attachment 1) involves series and paralle! steps labeled in accordance with the Procedure steps. 7.0.2 Series steps of the flow chart must be accomplished in sequential order. 7.0.3 Parallel steps of the flow chart may be accomplished in sequential order or at the same time, whichever is the most efficient. 7.1 OUAIJFIED SHIPPER CHECK-IN The qualified Shipper performs the Verification that the Shipping Container and Shipping Request agree and perform the following: 7.1.1 Verification that *In-house Radioactive Shinnine Reouest Form" (Attachment 2) matches data on the shipping container by completing item 4 prior to acceptance of Radioactive Material. 7.1.2 Verification that "Recuest for Radioisotone Shinment Form" (Attachment 3) matches the "In-house Radioactive Shinninc Reauest Form (Attachment 2) by comparing the data and completing Item 5 .of the in-house Radioactive Shinnine Reauest Form.(Attachment 2) 7.1.3 Place the "Shinninn Container " containing the Radioisotope into the Shielded Storace. 7.1.4 Staple " Customer Reauest for Radioisotone Shioment" and "In-house Radioactive Shinnine Reaue.u" forms

 -'                 together and place into the Receint "In-box" Rev. IL SA.I     IIP        Date 17 Feb.1993     MURR-SAS-00004    page 21 of 29.

l MURR-SAS-00004 Shipment of Radioactive Materials l l 7.2 RECEII7T " IN-BOX" 7.2.1 A Qpalified Shipper will process Check-in paperwork. 7.3 PREPARE PACKAGE PACKET A Qualified Shipper will prepare the Packace Packet: 7.3.1 Determine the proper Shipping Container %ased on information from Sections 4.18, 4.19, 4.20 or 4.21 ( Attachment 4). 7.3.2 Prepare labels:

      .7.3.2.1    Two each: MURR package Model Number, e.g., MURR 1000, etc.

7.3.2.2 Six each: Shipping Label with Shipment Destination, Isotope, MURR ID number, and Activity. 7.3.2.3 Two each: USA DOT 7A Type A Radioactive Material Specification Certified by University of Missouri

                                       .              Research Reactor Columbia, Mo. 65211 7.3.2.3   'Two each:                           RADIOATIVE MATERIAL N.O.S.~ UN2982 7.3.3      Prepare " control Check Sheet" for proper USA DOT MURR Model Number Package, Model 1000,1100,1220, or 1300.

(Attachment 4). 7.3.4 Place the prepared Packace Packet in the Packace Packet "In-Bos". 7.4 PACKAGE PACKFF "IN-ROX" Qualified Shipper will remove Eadace Packet from Packace Packet " In-Roy " E Rev. IL. SA N. IIP Date 17 Feb.1943 MURR-SAS-00004 page 22 of 29.

1 I i 1 MURR-SAS-00004 Shipment of Radioactive Materials

 .          7.5      PACKAGE PREPARATION Qualified Shipper must prepare the package in accordance -

with the enclosed Control Check Sheet (Attachment 4). NOTE: Only one box must be in the immediate work area and packaging must be accomplished in a clear work area with no other packages (package components) within five feet. The Control Check Sheet must be used as verification of Performer's activities completed and Inspector's Independent Verification of same by initialing the steps required. Initials are to be entered after steps marked (*) are completed.- 7.5.1 Ensure accuracy oflabel on Control Check Sheet (Attachment 4)_as to shipment destination, isotope, MURR I.D number, and activity: steps one through four. Ensure that all labels contain the same information. 7.5.2 Identify and install label with shipment destination, isotope, MURR ID number and activity on the lid of the Shipping Can. 7.5.3 Identify and install label with shipment destination, isotope, MURR ID number and activity on side 1 (top outside flap) of the 7A container. 7.5.4 Identify and install label with shipment destination, isotope,- MURR ID number and activity to the top of the polystyrene insert. 7.5.5 Ensure Control Check Sheet (Attachment 4) agrees with_the two labels indicating MURR Model Number and place labels on type 7A container directly under certification labels. 7.5.6

Ensure lead shipping container and inner shipping can identification labels agree.

7.5.7

Seal inner shipping can with sealing machine.

7.5.8

Verify radioactive labels are on inner can.

7.5.9 Insert inner shipping can into polystyrene. 7.5.10

Place polystyrene top with identifying label over shipping can.

- L Rev.f) SA M llP Date 17 Feb.1903 MURR-SAS-00004 page 23 of 29. 9

+-

h!URR-SAS-00004 Shipment of Radioactive blaterials 1 7.5.11 Strap polystyrene insert by strapping machine with: 7.5.11.1 Two straps centered over polystyrene cardboard cover. 7.5.11.2 Rotate polystyrene ninety degrees. 7.5.11.3

Apply two additional straps centered over polystyrene cardboard cover.

7.5.12 Insert polystyrene into type 7A container with Ldentification lithel on top for viewing when container flaps are opened. 7.5.13 Tape inner flap at least 75 percent oflength. _ 7.5.14 Tape loose edges of container with three inch clear tape with a minimum of two inches down on the sides of 7A container. 7.5.15 *Use the strapping machine to strap each container approximately two inches from both sides and ninety degrees with respect to container center flaps over sides 1 and 3. 7.5.16

Install security labels on the center edge of container on top and bottom.

7.5.17

Ensure Certification label is on the 7A container.

7.5.18

Ensure proper shipping name and UN number label is on 7A container.

7.5.19 Number type 7A container sides 1,2,3,4. 7.5.20 Identify swipe (filter paper,4.25 cm diameter) with: 7.5.20.1 Shipment blURR I.D. number. 7.5.20.2 Abbreviated customer name. 7.5.21 Swipe four sides, top and bottom of'7A container. 7.5.22 Ensure no contamination ( greater than 20 dpm per 300 cm2 ) exists on outside of container by reading swipe on swipe counter. 7.5.23 The dose rate (mrem /hr) must be measured at contact of the extemal surface of the containers' four numbered sides, top and bottom. 7.5.23.1 Obtained readings must be recorded on the control check sheet by performer and independently verified by inspector. Rev.IL SA - IIP Date 17 Feb.1993 MURR-SAS-00004 page 24 of 29, i

MURR-SAS-00004 Shipment of Radioactive Materials 7.5.24 The transport index (TI) dose rate (mrem /hr) shall be measured at a distance of one meter from the package face " with the maximum contact reading. 7.5.24.1 *Obtained reading must be recorded on the control sheet by performer and independently verified by inspector. 7.6 PACKAGE PLACED IN STORAGE ou c: rusi Anna wiin uuse ><ain iu WARNOTiiER WORKERS IN THEAREA. 7.6.1 The package is placed in storage awaiting the completed Shipping Papers from Final Packaeine Checkout "In-box" 7.6.2 The applicable Control Check Sheet.1 Attachment 4) is placed in the Documentation Packet "In-box" 7.7 PREPARE SHIPPING PAPERS 7.7.1 A Q alified Shipper will process paperwork from Receint "In-hD.5" 7.7.2 A Qpalified Shipper will: 7.7.2.1 Determine proper Carrier routing. 7.7.2.2 Prepare the Address Label (attachment 5 ) 7.7.2.3 Prepare the Material Transfer Form (attachment 6 ) 7.7.2.4 Prepare the Shippers Declamtion Form (attachment 7) 7.7.3 Place all of the above in a packet and put into the i Documentation Packet "In-box" (This material is defined as the Documentation Packet) 7.8 DOCUMENTATION PACKET " IN-BOX" 7.8.1 The Documentation Packet and the Packace Packet are combined in the Documentation Packet "In-box". 7.9 SHIPPING PAPER PACKET "IN-BOX" 7.9.1 The Packace Packet is combined with the Documentation Packet to forTn the Shionine Pacer Packet. 7.9.2 The Shinnine Paner Packet is then placed into Shinnine Paner Packet "in-Box" where it remains until a Certliied Shipper is ready to complete the documentation. ~ Rev.Q._ SA HP / Date 17 Feb.1993 MURR-SAS-00004 page 25 of 29.

hfURR-SAS-00004 Shipment of Radioactive blaterials , 7.10 COMPIRE SHIPPING PAPERS 7.10.1 A Certified Shipper will complete shipping papers ob'tained , from Shinnine Paner Packet "in-Box" and perform the following: 'I a 7.10.1.1 Determine the proper radioactive label White I, Yellow II, or Yellow 111 in accordance with 49CFR, or IATA Regulations. - 7.10.1.2 Fill out the radioactive label. 7.10.1.3 Determine the label (s) required for subsidiary risk by use of 'I Label Specifications) of IATA Dangerous Goods Regulations. 7.10.1.4 Provide label (s) for subsidiary risk (s). 7.10.1.5 Determine other hazardous label (s) required by use of Section ' 7.3 ofIATA Dangerous Goods Regulations. 7,10.1.6 Add transport index to shipping papers, category of radioactive label (White I, Yellow II, Yellow Ill), and : Subsidiary Risks labels from the Control Check Sheet. i 7.10.1.7 Add swipe information to shipping papers. 7.10.2 Complete the appropriate documentation section of the Con' trol Check Sheet. i 7.10.3 Ensure Information specified on the In-House Radioactive I Shinnine Reouest Form (Attachment 2) or the Reauest for : Radioisotone Shinment Form (Attachment 3) is within the , license restrictions: , 7.10.3.1

License number, amendment number and expiration date ;

agree. 7.10.3.2 -* Isotope and activity is within acceptable limits and I possession : limits. 7.10.3.3 *The shipping address is correct. ; 7.10.3.4

Transfer Form is in packing mclosure. !

i 7.10.3.5

Ensure that Shipment Waybill (s), address label, container identification agree. l 7.10.4 Place completed shipping papers in the Final Packaging -

Checkout "In-Box". ;

 +-                                                                                                 ,

Rev. L SA llP Date 17 Feb.1993 MUltR-SAS-00004 page 26 of .'9. u

                                                                                                  }
                                                                                            .   . 1

MURR-SAS-00004 Shipment of Radioactive Materials 7.11 FINAL PACKAGING CHECKOUT "IN-BOX"

b. 7.11.1 Package is ready for final attachment oflabels and checkout.

7.12 FINAI PACKAGING A Qualified Shipper will locate the specific Packace Packet in the Final Packacine Checkout "In-Box". 7.12.1 Perform the following for Air Freight: 7.12.1.1 Affix address. ! l 7.12.1.2 Affix packing list envelope, i 7.12.1.3 Affix Shippers Declaration (Attachment 7a). 7.12.1.4 Affix appropriate Primary Hazard label: White I, Yellow II, or Yellow Ill. 7.12.1.5 Affix subsidiary risk (s) label. ! l 7.12.1.6 Affix " Cargo Aircraft Only" label. l

                  # Exception for passenger aircraft is for medical use and if TI is equal to or less than 3.0.

7.12.1.7 Affix "This Way Up" arrow, if appropriate. . 7.12.1.8 Certified Shipper signs and dates Control Check Sheet (Attachment 4). 7.12.2 Perform the following for Ground Freight: 7.12.2.1 Affix address. 7.12.2.2 Affix Straight Bill of Lading (Attachment 7b). 7.12.2.3 Affix packing list. 7.12.2.4 Affix appropriate Primary Hazard label: White I Yellow II, or Yellow III. 7.12.2.5 Affix Subsidiary Risk Inbel. 7.12.3 Certified Shipper signs and dates Co'ntrol Check Sheet (attachment 4). Rev. IL. SA IIP Date 17 Feb.1943 MURR-SAS-00004 page 27 of 29.

MURR-SAS-OOOO4 Shipment of Radioactive Materials 7.13 FINAL VERIFICATION "IN-BOX" 7.13.1 . Package is ready for final verification by Health Physics ( H.P.) 7.13.2 Notify H.P. independent verification is required. 7.14 FINAL VERIFICATION 7.14.1 Will be conducted by an assigned Health Physics Personnel to verify: 7.14.1.1 Isotope and activity is within acceptable limits and possession ! limits as listed on Shipping Summary Form (Attachment 8). 7.14.1.2 Ensure that waybill (s), address label, container identification agree. 7.14.2 Ensure following labels are affixed : 7.14.2.1 Address 7.14.2.2 Appropriate White I, Yellow II or Yellow III. , 7.14.2.3 Verify Reportable Qpantity.

                         ~                                                             '

7.14.2.4 Subsidiary risk (s). g 7.14.2.5 Cargo Aircraft Only. 7.14.2.6 "This Way Up" arrow. 7.14.2.7 Verify Transport Index and Activity. 7.15 SHIPPING

SUMMARY

FORM The Shipping Summary Form (Attachment 8) is used for Qpality Cor} trol as a final review of the package and Shipper's . Declaration before releasing the package to the courier. The Shipping Summary Form is prepared by the Shipping Section Leader or authorized individual. It is prepared by use of independent projected shipping schedules and the Sample Folders. i Once prepared, a Q.palified Shipper vill review the l information for accuracy after which, will initial each line. l 7.16 RFMASE TO COURIER Package is picked up and signed for by a Courier only if the package is a yellow 111. Rev..Q_ S IIP d Date 17 Feb.1993 MURR-SAS-00004 page 28 of 29.

i MURR-SAS-00004 Shipment of Radioactive Materials 7.17 EMERGENCY RESPONSE INFORMATION , A copy of the Dangerous Goods Declaration is placed in the , Control Room Emergency Response Book. 7.18 NOTIFICATION OF A SHIPMENT , Notification of a shipment may take place anytime after the package has be.en signed-off by a Certified Shipper. s 7.18.1 Notification of the radioactive shipment should be made by a Qualified Shipper using Telephone calls, Fax or Mail. - 7.18.2 The Control Check Sheet (attachment 4 ) should be initialed and method of notification noted. ' REFERENCES A. Federal Code of Regulations 49CFR. B. Federal Code of Regulations 10CFR. C. International Air Transport Association Dangerous Goods Regulations. D. Packaging Flow Chart (Attachment 1). , E. In- House Radioactive Shipping Request Form (Attachment 2). F. Request for Radioisotope Shipment Form (Attachment 3). . G. Control Check Sheets for USA DOT MURR Models (Attachment 4). H. Address I;tbel Examples (Attachment 5). I. Material Transfer Form (Attachment 6). J. Shippers Declaration For Dangerous Goods Form (Attachment 7a). ; K. Straight Bill of lading (Attachment 7b). L Shipping Summary Form (Attachment 8). I Rev.IL SA, LIP Date 17 Feb.1993 MURR-SAS-00004 page 29 of 29.

MURR-SAS-0000S Hot Cell Loading of Host Cans , w., Procedure Cover Sheet MURR-SAS-00005 0 17 May 1993 (Procedure) (Revision) (Date) I ' Hot Cell Loadine of Host Cans - (Procedure Title) Prepared By ' ' (Signa (tire) Reviewed By d6 Ilc[AOG eMRI

                          '               (Signature) h Revision Summarv.

Rev.# Dale Sienificant Summarv 0 17 May 93 Yes Original Rev. O SA M HP Date 17 May 1993 MURR-SAS-0000S page 1 of 21

i l Hot Cell Loading of Host Cans l MURR-SAS-00005 3- TABI E OF CONTENTS SECTION . PAGE NUMBER-

1.0 Purpose and Scope

3 , 2.0 Precautions and Limitations 4 3.0 Materials and Equipment 5 - 4.0 Definitions 6 5.0 Responsibilities 8 - 6.0 Procedure 8 7.0 Hot cell loading of host cans 9 7.1 Prepare paper work 10 7.2 Prepare new samples 10 7.3 Prepare host capsules and host can 11 7.4 Load hot cell 11 7.5 Open host can'#1 (Example used: Can #35) 13

                                                                                                              'l l

7.6 Open host can #2 (Example used: Can #88) '14 7.7 Load new host can for flux trap 15 7.8 Weld new host can 15 7.9 Size new host can 15 , i. 7.10 Leak test host can 16 7.11 Unload hot cell 17 ~i 7.12 Transfer to pool for reload 18 7.13 Complete paper work 19 7.14 Open leaky host can and dry 20

        . Attachments                                                                                21          i l

References 21 l Rev. O SA N HP b Date 17 May 1993 MURR-SAS-00005 page 2 of 21_ .I I l

MURR-SAS-00005 Hot Cell Loading of Host Cans

 %        1.0         PURPOSE AND SCOPE This procedure provides instructions for hot cell loading of host cans to be irradiated in the Reactor Flux Trap.                  ,

The purpose is to ensure Compliance with applicable Regulations of Code of Federal Regulations (CFR),10CFR,49CFR and International Air Transport Association (IATA). 1.1 This activity is scheduled during the normal ." shutdown". periods of the reactor and is completed prior to "startup" of the reactor. 1.2 This operation of loading a host can for irradiation starts after the previously irradiated capsules have been removed from the transfer cask and/or removed from storage in the hot cell as depicted in the Procedure MURR-SAS-00002, Hot Cell Preparation of Radioactive Material for Shipment. New capsule (s) may also be inserted into the host can. . 1.3 This procedure incorporates:

Positive identification of host can(s),
Positive identification of capsule (s) removed from an opened. host can, capsule (s) from hot cell storage or new capsule (s),
Reloading capsule (s) into a different host can, ,
Loading new capsules in a host can, >
Placement and welding oflid on the new host can and,
Testing performed on the host can after welding to ensure correct size and water tight integrity.

1.4 This Procedure duplicates some Steps of MURR-SAS-00002, 1.5 Specific details are used as examples in this Procedure to illustrate the process flow, i.e., using the host can numbers, etc. of the Attachments.

                                                                                             )
                                                                                           -l1 l

1 Rev. O SA db HP db Date 17 May 1993 MURR-SAS-00005 page 3 of 21

i i MURR-SAS-00005 Hot Cell Loading of Host Cans 2.0 PRECAUTIONS AND LIMITATIONS 3 2.1 The non-fixed contamination on any external surface of the transfer cask must be kept as low as practical. 2.1.1 The level of non-fixed radioactive contamination may be determined by wiping an area of the surface concerned with an absorbent material, using moderate pressure, and measuring the activity on the wiping material. 2.2 Ensure that all beta-gamma dose rate survey, contamination counting, and gamma radioisotope equipment calibration stickers have not passed the calibration due date prior to use. 2.3 Ensure that upon leaving the hot cell area you measure for personal external contamination by use of the Hand-foot monitor or equivalent device. 2.3.1 When the Hand-foot monitor alarms indicating external contamination, call Health Physics immediately at extension

                    #2-5217.

2.3.2 After 5:00 P.M. or Weekends call the Control Room at extension # 2-5213. 2.4 Maintain radiation exposure As Low A's Reasonably Achievable (ALARA) by use of Time, Distance, and Shielding. 2.5 Use protective clothing:

Laboratory Coats
Rubber / Latex Gloves
Safety glasses and/or Face Shield.

2.6 In the event of a stuck capsule or broken vial, the Reactor Services Engineer or Designee must be notified immediately. L k i Rev. 0 SA M HP b Date 17 May 1993 MURR-SAS-00005 page 4 of 21

      '. MURR-SAS-00005                                    Hot Cell Loading of Host Cans mj           3.0       MATERIALS AND EOUIPMENT 3.1       Calibrated gross contamination counting equipment.

3.2 Calibrated Beta counter. 3.3 Smear papers. 3.4 Cask handling tools and equipment. 3.5 Protective clothing, to include: 3.5.1 Rubber / latex gloves. 3.5.2 Laboratory coats. 3.5.3 Safety glasses and/or face shield. 3.6 Loading of radioactive material chart, Attachment 1. 3.7 Sample Pull Sheet, Attachment 2. 3.8 Sample Shipment Information Sheet, Attachments 4 and 6. 3.9 Existing Loading Sheets, Attachments 5 and 7. 3.10 Welding unit, Miller 330A/BP or equivalent. 3.11 Tec Torch Model 308 or equivalent. Rev. O SA HP Y Date 17 May 1493 MURR-SAS-00005 ' page 5 of 21

l MURR-SAS-00005 . Hot Cell Loading of Host Cans I

   -.      4.0       DEFINITIONS

4.1 Activity

Is a measure of the quantity of radioactivity emitted , by a radioisotope and is used to determine the amount of . radioactive material which may be transported in various types of packaging. 4.2 Host Can: Is a multi-carrier of capsules, with spacers, if ' required, which may contain capsules from:

Prior Host cans p.reviously irradiated, I
Storage which have been previously irradiated and placed in Storage or,
New capsules to be irradiated.

4.3 Host Cansule Change Sheet: This term is used in the Description Section of the Samole Shioment Information Sheet (Attachments 4 and 6). It is an interchangeable title for ; the Existing Loading Sheet (Attachments 5 and 7).

4.4 Observer

An Independent Verifier who observes critical points of the processing steps and documents the performance of these steps by legibly initialing the steps as they are performed.

4.5 Performer

The individual who performs the critical step of the process and documents the performance of these steps by legibly initialing the steps as they are performed. 4.6 Radioactive Contents: The radioactive material together . with any contaminated solids, liquids and gases within the package. 4.7 Radioactive material: Any material having a specific activity greater than 0.002 micro curies per gram (uCi/g). , 4.8 Shall. Must. Should: 4.8.1 Shall. Regulatory Commitment to Code of Regulations, 10CFR,49CFR and 1ATA Dangerous Goods Regulations.

4.8.2 hht11

MURR Internal Commitment to 10CFR,49CFR and 1ATA Regulations.

4.8.3 Should

Should be accomplished; not required. Rev. O SA M HP d Date 17 May 1993 MURR-SAS-00005 page 6 of 21

MURR-SAS-00005 Hot Cell Loading of Host Cans 4,9 Snacer: Used to take up space in the host can to minimize

                 capsule movement.

4.10 Snecific Activity: The activity of the radionuclide per unit weight of that nuclide. 4.11 Transfer Cask: Used to transport samples within the facility. I Rev, O SA IIP b Date 17 May 1993 MURR-SAS-00005 page 7 of 21

MURR-SAS-00005 Hot Cell Loading of Host Cans S.O RESPONSIBILITIES 5.1 Ecaclor Services Engineer: Ensure that all host cans loaded for insertion into the reactor are prepared in accordance with Reactor Technical Specifications, Reactor Utilization Request (RUR) Control Sheet and appropriate Procedures. 5.2 Health Physics Manager: Provide Health Physics (HP). support as required to Service Applications Group for-preparation of radioactive material shipments. , 5.3 Reactor Ooerations Manacer: Ensure that all host cans loaded for insertion into the reactor are prepared in accordance with Reactor Technical Specifications, RUR's and appropriate Procedures. 6.0 PROCEDURE 6.1 Ensure that host cans are prepared in accordance with Reactor Technical Specifications, RUR's and appropriate Procedures. 6.2 The following unique characteristics of each shipment Shall be maintained throughout Receipt, Safety Analysis, Preparation for Irradiation, Irradiation, Post Irradiation Processing, Packaging, and Documentation: 6.2.1 Material Description, 6.2.2 Amount (Mass), 6.2.3 Isotopes, 6.2.4 Activity, 6.2.5 Destination, 6.2.6 Recipient's License Number, Amendment Number and Expiration Date or certificate in accordance with 10CFR. 6.2.7 MURR Identification Number. r Rev. O SA M HP I Date 17 May 1993 MURR-SAS-00005 . page 8 of 21 l

               ,--n..

MURR-SAS-00005 Hot Cell Loading of Host Cans x 6.3 Data integrity must be maintained by documented Control Check sheets with Independent Verification at critical points in the process. 6.3.1 The " Performer" of a shipping process and " Observer" must not be the same individual. 6.3.2 The Observer must also be Qualified to perform the Task. 7.0 HOT CELL LOADING OF HOST CANS 7.0.1 The Loading of Radioactive Material Flow Chart (Attachment 1) involves series and parallel steps labeled in accordance with the Procedure step numbers and must be adhered to by the Shipping Department Personnel unless otherwise noted. 7.0.2 Series steps of the flow chart must be accomplished in sequential order. 7.0.3 Some parallel steps are alternative parallel steps of the flow chart and may be accomplished in sequential order or at the same time, whichever is the most efficient.

7.0.4 Processing of the radioisotopes prior to packaging for shipment is accomplished in cooperation with MURR Operations (OPS), Health Physics (HP) and Service Applications (SA) Departments. 7.0.5 The Sample Pull Sheet (Attachment 2) designates the host can(s) by their can numbers and provides instructions for the movements of specific capsules. 7.0.6 The Samnle Shinment Information Sheet (Attachments 4 and 6) used for loading are differentiated from other Samnle Shinment Information Sheets by being identified with a pink edge around the sheet or copied on different colored paper. 7.0.7 - The Existine Loadine Sheet (Attachment 5) instructs Qualified Shippers the specific capsules to be pulled from an Identified Host can, pull date and transfer to another identified Host can. , 7.0.7.1 In Attachment 5, capsules M2101 and SEP4 are to be pulled from host can #35 on 4/5/93 and transferred to host can #88. 7.0.7.2 Remaining capsules (Attachment 5) are shipped or stored. Note: No new loading is indicated for the New Loadine section (Attachment 5). ! P Rev. O SA M HP [ Date 17 Mav 1993 MURR-SAS-00005 page 9 of 21 l

4 MURR-SAS-00005 Hot Cell Loading of Host Cans

 %      7.0.8      The Existine Loading Sheet (Attachment 7) instructs Qualified Shippers the specific capsules to be pulled from an Identified host can, pull date, ship date, and their disposition.

7.0.8.1 The New Loading section (Attachment 7) indicates the transfer of Capsules (M2101 and SEP4) from another host can (#35) into host can (#88). 7.0.8.2 A new and different host can is assembled; this new host can number remains the same as before(#88). . NOTES: THE FOLLOWING STEPS FOR LOADING WILL BE ACCOMPI1SHED USING THE ATTACHMENTS 1 THROUGH 7 OF THIS PROCEDURE AS AN AfD AND THE HOST CAN NUMBERS WILL BE USED THROUGHOUT. STEPS 7.1, 7.2, AND 7.3 AREPERFORMED BYSERVICE APPLICATIONS-ISOTOPES GROUP . APPROVED TRACKING AND HOST CAN INFORMATION SHFFTS MENTIONED IN THE ABOVE STEPS ARE FOR INFORMATION ONLY TO INDICATE THE PAPER TRACK AND DO NOT PERTAIN TO SERVICE APPLICATIONS -SHIPPING. 7.1 PREPARE PAPER WORK 7.1.1 Service Applications-Isotope Group, on receipt of MURR Irradiation Reauest Form assembles paperwork consisting of:

Sample Pull Sheet, Attachment 2.
Sample Shipment Information Sheets, Attachments 4 and 6.
Existing Loading Sheets, Attachments 5 and 7.

7.1.2 The prepared paperwork is transferred to the Service Applications Section Leader- Shipping. 7.2 PREPARE NEW SAMPLES 7.2.1 Service Applica%as-Isotopes prepares new samples scheduled for irradiation by an Aporoved Tracking Sheet. 7.2.1.1 Sample preparation is initialed by Performer and Observer of the process. l Rev. O- SA b HP ._:.h Date 17 May 1993 MURR-SAS-00005 page 10 of 21 l

 . MURR-SAS-00005                                     .ilot Cell Loading of Host Cans 7.3      FREPARE HOST CAPSULE AND HOST CAN -

7.3.1 Service Applications-Isotope prepares new host cans and host capsules for irradiation by an approved Host Can Information Sheet. 7.3.1.1 Capsules are engraved with distinctive identification markings as indicated by Existine Loading Sheets . 7.3.1.2 Host cans are engraved with the host can number assigned by the Host Can Information Sheet and are indicated also on the Samnle Shinment Information Sheet. 7.4 LOAD HOT CELL NOTE: THIS 15 SIMIIAR TO STEP 7.6 OF MURR-SAS-00002. 7.4.1 Move the transfer cask to the immediate area of the hot cell. 7.4.2 Qualified Shipper dons protective clothing:

Laboratory coat
Rubber / latex gloves
Breathing mask; type to minimize ingestion / inhalation of particulate matter for personnel who approach the hot cell door.
Safety Glasses and /or face shield.

7.4.3 Move work table to North end of hot cell. 7.4.4 Health Physics: 7.4.4.1 Ensure air monitor is functional. 7.4.4.2 Turn hot cell blower "ON". 7.4.4.3 Open concrete shield outer door to hot cell and survey inner door of hot cell while outer door is opening. Rev. O SA M . HP M. Date 17 Mav 1993 MURR-SAS-00005 page 11 of 21

i MURR-SAS-00005 Hot Cell Loading of Host Cans c 7.4.5 Health Physics /Quallfled Shipper: 7.4.5.1 Open aluminum inner wall door. i 7.4.5.2 Place clean absorbent paper on the South work table in hot cell. 7.4.5.3 Load the new host cans and host capsules in the hot cell. 7.4.5.4 Move the transfer cask to the front of the hot cell door,by a fork lift. 7.4.5.5 Remove safety pin and bar from the transfer cask. ; 7.4.5.6 Remove the plastic bag from the transfer cask at the hot cell door. 7.4.5.7 Insert transfer cask into hot cell with fork lift. 7.4.5.8 Close inner hot cell aluminum door. 7.4.5.9 Swipe floor outside of hot cell and read for contamination. 7.4.5.10 Close outer concrete door. 7.4.5.11 Turn hot cell blower "OFF". 7.4.5.12 Lift lid from transfer cask using the crane. 7.4.5.13 Remove transfer cask basket and place on upper work table. 7.4.5.14 Manipulate host can #35 from the basket. 7.4.5.15 Manipulate host can "88 from the basket. 7.4.5.16 Replace basket into transfer cask or appropriate storage area for returning host cans to pool. , 7.4.5.17 Set transfer cask lid onto the transfer cask. 7.4.5.18 Unhook lid from crane. Rev.. O SA OA HP [ Date 17 May 1993 MURR-SAS-OOOOS page 12 of 21

MURR-SAS-00005 Hot Cell Loading of Host Cans 7.5 OPEN HOST CAN #1 (Examole used: Can # 3S) NOTE: THIS STEP 7.8 OF MURR-SAS-00002, 7.5.1 Host can #35 is identified and verified by comparing the can inscription with Sample Shloment Information Sheet. (Attachment 4) Step 2, as can #35. 7.5.2 Performer and Observer initial Samole Shloment Information Sheet (Attachment 4), Step 2, verifying host can to be ' opened is correct (#35). 7.5.3 Cut top off of host can and place top into hot waste storage area of hot cell. 7.5.4 Remove capsule (s) from host can and place on clean absorbent paper. 7.5.5 Perform a visual inspection of the capsule after it is de-canned as shown in example on Samole Shloment 'nformation Sheet (Attachment 4) description (upper right corner): THIS IS A HOST CAN. PULL AND LOAD ACCORDING TO HOST CAPSULE CHANGE SHEET. 7.5.6 Identify and verify capsule (s) description by comparing the description on Samole Shloment Information Sheet (Attachment 4), and inscription on Existing Loading Sheet (Attachment 5). . 7.5.7 Performer and Observer initial Step 4 of Samole Shioment Information Sheet (Attachment 4). 7.5.8 Place Identified capsules (#M2101 and SEP4) into a plastic cup and place in the hold'ng area on the hot cell West work table. Rev. O SA d$) HP Date 17 Mav 1993 MURR-SAS-00005 page 13 of 21

MURR-SAS-00005 Hot CellIoading of Host Cans 7.6 OPEN HOST CAN #2 (Example used: Can #88) 7.6.1 Host can is identified and verified by comparing the can description with Sample Shipment Information Sheet. (A'ttachment 6) Step 2, as can #88. 7.6.2 Performer and Observer initial Samole Shinment h formation Sheet (Attachment 6), Step 2, verifying host can to be opened is correct (#88). 7.6.3 Cut top off of host can and place top into hot waste storage area of hot cell. 7.6.4 Remove capsule (s) from host can and place on clean absorbent paper, 7.6.5 Perform a visual inspection of the capsule (s) after it is de-canned as shown in example on Samole Shloment Informatial Sheet (Attachment 6) description (upper right corner): THIS IS A HOST CAN. Pull AND LOAD ACCORDING TO HOST CAPSUI.E CHANGE SHEET.

7.6.6 Identify and verify capsule (s) description by comparing the inscription (s) on Existine Loading Sheet (Attachment 7). J 7.6.7 Performer and Observer inidal Step 3 of Samole Shioment , Information Sheet (Attachment 6). ! I Rev. O SA MU HP Date 17 May 1993 MURR-SAS-00005 page 14 of 21 4

x MURR-SAS-00005 Hot Cell Loading of Host Cans

a. 7.7 LOAD NEW HOST CAN FOR FLUX TRAP NOTE:

FOR OTHER LOADING, CAPSULES, MAY COME PROM:

STORAGE (STEP 7.11 OF MURR-SAS-00002)
HOST CAN (STEP 7.11 OF MUl%SAS-00002) .
SERVICE APPLICATIONS-ISOTOPES (NEW) .

7.7.1 Identify and put capsules 9550, MAR 2, ABA, and 816 from the , Orininal host can 388 into the New host can #88. 7.7.2 Identify and install capsules M2101 and SEP4 transferred from host can #35 also into the new host can #88. 7.7.3 Performer and Observer initial Existinn Loadine Sheet in the New Loadine Section (Attachment 7). 7.7.4 Place lid onto the new host can #88. 7.7.5 Place the new host can (# 88) into hot cell storage area. NOTE: MACHINESHOP PERSONNEL DO NOT USE THE . MANIPULATORS EXCEPT TO INSERT / REMOVE HOST CANS TO WELDING RIG. 7.8 WFI D NEW HOST CAN 7.8.1 Machine Shop personnel weld the lid onto the host can using:

Welding unit. Miller 330A/BP or equivalent.
Tec Torch Model 308 or equivalent. .

7.9 SIZE NEW HOST CAN , 7.9.1 Manipulate the host can through the sizing tube to verify host can is of correct size to be accepted into the flux trap. NOTE: 1 The host can must be able to pass through the - sizing tube freely 1 7.9.1.1 If the host can is too large to pass through the sizing tube, use the manipulators and a file to size the host can. Repeat Step 7.9.1. Rev. O SA HP Date 17 Mav 1993 MURR-SAS-00005 page 15 of 21 -

m MURR-SAS-00005 Hot CellIoading of Host Cans. g 7.10 LEAK TEST HOST CAN 7.10.1 Remove the lid from the Leak Test jar. 7.10.2. Insert host can into Leak Test jar. 7.10.3 Install the lid onto the Leak Test jar. , NOTES: The Vent and Vacuum valve handles for the following test are located on a panelin the upper - right hand corner of the West hot cell window. ' The vent and vacuum valves handles are moved to the "IN" position to "CLOSE" the valves and moved to the "OUT" position to "OPEN" the valves. ' Watch for bubbles at all times when placed in alcohol. 7.10.4 Verify that the Vent and Vacuum valves are both " CLOSED" 7.10.5 "OPEN" the Vacuum valve and observe if any bubbles are ! coming from the host can. NOTD This next Step assures that vacuum is operational 7.10.6 Raise the Leak Test jar approximately~one inch off the work table by the lid of the jar. t 7.10.7 Carefully lower the Leak Test jar to the work table. 7.10.8 Observe for bubbles leaking from the host can for approximately 30 seconds. 7.10.8.1 Bubbles indicates a leaky host can: Proceed to Sten 7.14. 7.10.8.2 No bubbles indicates the host can has integrity. ) 7.10.9 Close the vacuum valve. 7.10.10 Open the vent valve. 7.10.11 Close the vent valve when the vacuum has been vented. l Rev. O SA $N HP h Date 17 May 1993 MURR SAS-00005 page 16 of 21:-

                                                                                           ..g 0 -       ,     -

           . , . . .                         ,            - -                 . _ _ - . _ - . =                                .-   - - . -

J i MURR-SAS-00005 Hot Cell Loading of Host Cans I . 7.10.12 Remove the lid from the Leak Test jar. ; 4 3 7.10.13 Remove the Host can from the Leak Test jar. 7.10.14 Load host can into transfer cask basket. l 7.10.15 Load basket into transfer cask arter all host cans have been l leaked checked. 7.10.16 Replace transfer cask lid onto the transfer cask. , 7.11 UNLOAD HOT CELL NOTES: .; PERFORM A VISUAL INSPECTION OF THE HOT l CEIL TO ENSURE THAT ALL WORKING AREAS ARESECURED AND THAT DOORS CANBE OPENED. MOVE TRANSFER TABLE TO NORTH END OF HOT g CBL AND ADJUST TO CORRECTLEVEL FOR ' l FORK LIFT ENTRY. l

THISIS SIMILAR TO STEP 7.13 OF MURR-SAS-00002. 7.11.1 Health Physics / Qualified Shipper: , 7.11.1.1 Turn hot cell blower "ON." l 7.11.1.2 Open concrete outer door to hot cell and survey inner door of hot. cell while door is opening. 7.11.1.3 Open aluminum inner wall door. i 7.11.1 A Swipe and read transfer cask. 7.11.1.5 Inspect poly bag to be used to bag the transfer cask for holes or tears. 7.11.1.6 Remove transfer cask from hot cell using fork lift. > 7.11.1.7 Bag the transfer cask. .; 7.11.1.8 Place transfer cask on a cart. > 7.11.1.9 Replace safety bar and pin. 7.11.1.10 Survey transfer cask on cart. Rev. O- SA N-HP Date 17 May 1993 MURR-SAS-00005 _ page 17 of 21 f _- - - - .. _ -__ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

i i MURR-SAS-00005 Hot Cell Loading of Host Cans 7.11.1.11 Close the inner hot cell door. i 7.11.1.12 Close outer hot cell door. ) i 7.11.1.13 Turn hot cell blower "OFF" j

                                                                                        .J 7.11.1.14 Swipe and read floor outside of the hot cell door using Baird           ;

Polyspec Research Spectrometer or equivalent to count the , swipes. 7.12 TRANSFER TO POOL FOR RELOAD l CAUTION: Personnel transporting transfer cask to the pool must practice AIARA, (TIME, DISTANCE, SHIELDING). DO NOT RIDE ELEVATOR WITH CASK. 7.12.1 Transport cask is transported to the pool by way of Containment and Freight elevators or door 101 when available. i I,

                                                                                        ,t e

Rev. O SA HP Date 17 May 1993 MURR-SAS-00005 page 18 of 21

I l MURR-SAS-0000S Hot Cellloading of Host Cans

~.-

7.13 COMPLETE PAPER WORK 7.13.1 The following paper work is transferred between Service Acolications-Shioning and Service Acolications-Isotones: !

Sample Pull Sheet, Attachment 2.
Sample Sheet, Attachment 3.
Sample Shipment Information Sheets, Attachments 4 and 6.
Existing Loading Sheets, Attachments 5 and 7. (Mondays only) for host can loading. i 7.13.2 Originally, the above paper work is generated by Service Applications-Isotopes and transferred to Service Aoplications-Shionine.

7.13.3 Prior to when the Shippers go to the hot cell the Samole Sheet is returned to Isotopes. , 7.13.3.1 Isotopes enters the information of the Samole Sheet into the Data Base. 7.13.3.2 The Samole Sheet is returned to Shipping. 7.13.4 After the package is shipped the Documentation Packet, which includes, the Sample Sheet and Samole Shipment Information Sheet is returned to Isotopes where it remains until Billing. 7.13.4.1 The Samole Pull Sheet is filed by the Shipping Department. 7.13.4.2 On routine reactor shutdown days (host can loading) the Existing Loading Sheet is returned by placing it into the "In-basket" ofIsotopes. 7.13.5 After the Billing, the paper work is transferred to Service Applications Section Leader- Shipping. 7.13.6 The Service Applications Section Leader- Shipping:

Files the paper work in numerical order and maintains this paper work at MURR for a period of three years.
Performs sampling of the documents for accuracy.

7.13.7 After a three year period, this paper work is sent to the University of Missouri Records Retirement Storage. b _

MURR-SAS-00005 - Hot Cell Loading of Host Cans 7.14 OPEN LEAKY HOST CAN AND DRY NOTE: - IF HOST CAN LEAKS, CUT HOST CAN OPEN, REMOVE CAPSULES AND ALLOW CAPSULES TO DRY FOR 30 MINUTES. 7.14.1 Host can is identified and verified by comparing the can inscription with Samole Shloment Ynformation Sheet.- (Attachment 6) Step 2, as can # 88. > 7.14.2 Performer indicates that the host can leaked, by making a note on Existine Loading Sheet (Attachment 7). 7.14.3 Cut top off of host can and place top into hot waste storage area of hot cell. 7.14.4 Remove capsule (s) from leaky host can and place on clean absorbent paper. 7.14.5 Allow removed capsules to dry for 30 minutes prior to loading , into a new host can. o 7.14.6 Place capsules into temporary, storage. 7.14.7 If new host can leaks: Repeat Procedure Steps 7.7, 7.8, 7.9 and 7.10. 6 I Rev. O SA NM HP Date 17 May 1993 MURR-SAS-0000S page 20 of 21 I

1 MURR-SAS-00005 Hot Cell Loading of Host Cans y ATTACHMENTS A. Hot Cell Loading of Host Cans, Attachment 1. i B. Sample Pull Sheet, Attachment 2. C. Sample Sheet, Attachment 3. B. Sample Shipment Information Sheets, Attachments 4 and 6. C. Existing Loading Sheets, Attachments S and 7. REFERENCE A. Federal Code of Regulations 10CFR. B. Federal Code of Regulations 49CFR. C. International Air Transport Association, Dangerous Goods Regulations. D. MURR, Reactor Technical Specifications. E. Hot Cell Preparation'of Radioactive Material for Shipment, MURR-SAS-00002. F. Shipment of Radioactive Materials, MURR-SAS-00004. Rev. O SA kN HP M Date 17 May 1993 MURR-SAS-00005 page 21 of 21

I I I 1 SECTION III REVISIONS TO THE HAZARDS

SUMMARY

REPORT l 1 July 1993 through 31 December 1993 HAZARDS

SUMMARY

REPORT (Original July 1,1965) Original Hazard Summary Report, Section 7.2.2, page 7-16,line 7: Delete: "as well as the supply of demineralized water to various laboratories." Original Hazard Summary Report, Section 7.2.2, page 7-16, Paragraph 3 is changed to read:

      "The two tanks are isolated from the facility demineralized water system. The two tanks can be cmss-connected by a gate valve between the tanks."

Original Hazard Summary Report, Section 7.2.2, page 7-17, new paragraph:

      "Three 420 gallon, 304 stainless steel demineralized water tanks are located in the north tower of the mactor building. The tanks are used for supplying demineralized water to the facility. The tanks are connected with PVCpipe to the laboratory demineralized water distribution system. The tanks have high and low level alarms which annunciate in the control room. They also have a " tank full" cutout switch associated with them so that when the tank is full the muerse osmosis (RO) unit used to fill them is shutdown automatically."

III-1 . l l

SECTION IV

r l

PLANT AND SYSTEM MODIFICATIONS r 1 July 1993 through 31 December 1993 I Modification 93-1: The installation of three new demineralized water tanks in .; north tower This modification adds three (3) 420 gallon,304 stainless steel tanks with a repressurization system to the facility demineralized water system for non- i reactor system use. The original 7,000 gallon DI tank (T-300) has been ; physically separated from the facility domineralized water system and will supply pool and primary system make-up water needs. The safety evaluation for this modification documents that it does not present an unreviewed safety question as per 10CFR50.59. i J l i

                                                                                       'i IV-1
                                                                                          )

1 SECTION V NEW TESTS AND EXPERIMENTS 1 July 1993 through 31 December 1993 New experimental programs during this period are as follows: RUR-305, Ruthenium Metal: Experimenter: S. Gunn

Description:

This RUR authorized irradiation of rutheniunimetal for medical use. RUR-315, Rubidium Carbonate: Experimenter: S. Gunn

Description:

This RUR authorized irradiation of rubidium carbonate for medical research use. Each of these experiments has a written safety evaluation on file which provides the ( basis for the determination that it does not involve an unreviewed safety question as per 10 CFR 50.59. l l l t I I 1 1

V-1 l 4

{

                        --- _ _ _ _ _ - -__-----_--_----__-_----------------------__---_ _-----__ _--___---_J

SECTION VI SPECIAL NUCLEAR MATERIAL ACTIVITIES 1 July 1993 through 31 December 1993

1. SNM Receipts: A total of16 new fuel elements were received from Babcock and Wilcox (B & W), Lynchburg, Virginia.

Grams Grams Shipper Elements U U-235 B&W MO-385, MO-386, MO 387, MO-388, MO-389, MO-390, 13,294 12,374 l MO-391, MO-392, MO-393, MO-394, MO-395, MO-396, MO-397, MO-398, MO-399, MO-400

2. SNM Shipments: A total of 24 spent fuel elements were shipped to DOE facilities at Savannah River Plant, Aiken, South Carolina.

Grams Grams Shipper Elements U U-235 i MURR MO-316, MO-318, MO-319, MO-320, MO-323, MO-324, 16,177 14,115 l MO-325, MO-326, MO-327, MO-328, MO-329, MO-330, MO 331, MO-332, MO-333, MO 334, MO-335, MO-336, MO-337, MO-338, MO 339, MO-340, MO-341, MO-342

3. Inspections: Physical Security and Material Control and Accountability inspections were conducted by the . Nuclear Regulatory Commission during the time period July 14-16,1993. No violations of NRC requirements I were identified during the course of these inspections.

4. SNM Inventory: As of 31 December 1993, MURR was financially responsible for the following DOE-owned amounts:

Total U = 44,192 grams Total U-235 = 39,688 grams Included in these totals are 36 grams of U and 34 grams of U-235 in DOE-owned non-fuel. In addition to these totals, MURR owns 177 grams of U and 96 grams of U-235. All of this materialis physically located at the MURR. VI-1 1 1 i

The fuel elements on hand have accumulated the following burn-ups as of 31 December 1993: Burned un Elements (16) Element No, Element No. MWD Element No. MWD MWD MO-321 126.29 MO-347 137.81 MO-353 147.50 =j MO-322 126.29 MO-348 145.31 MO-354 136.11 i MO-343 146.30 MO-349 137.81 MO 359 135.08 MO-344 146.07 MO-350 145.31 MO-360 135.08 MO-345 146.30 M O-351 147,50 MO-346 146.07 MO-352 136.11 j Elements in Service (41) l l MO-355 MO-372 MO-387 42.12 108.48 104.63 MO-356 108.48 MO 373 100.82 MO-388 50.17 MO-357 92.92 M O-374 104.65 MO-389 46.37

MO 358 02.92 M O-375 100.82 MO-390 ' 2.73 '

4 MO361 116.99 M O-376 104.65 MO-391 46.37 MO 362 103.37 MO-377 81.03 MO-392 42.73 MO-363 116.99 MO-378 77.21 MO-393 33.11 l MO-364 103.37 M O-379 81.03 MO-394 0.00 -{ I M O-365 103.78 MO.380 77.21 MO-395' 33.11 M O-366 122.96 MO-381 68.15 MO-396 0.00 M O-367 103.78 MO-382 71.28 MO-397 0.00 MO-368 122.96 MO-383 68.15 MO-398 - 0.00 MO-369 88.22 MO-384 71.28 MO-399 0.00 . MO-370 104.63 MO-385 42.12 MO-400 0.00 MO-371 88.22 MO 386 50.17 Average Burn-up (all elements): 89.32 MWD J VI 2

SECTION VII REACTOR PHYSICS ACTIVITIES 1 July 1993 through 31 December 1993

1. Fuel Utilization: During the period 1 July 1993 through 31 December 1993, the following elements reached licensed or feasible burn-up and were retired:

F'erini Number Final Core Date Lnst Used MWD MO-321 93-56 11 01-93 126.29 MO-322 93-56 11-01-93 126.29 MO-347 93-40 07-26-93 137.81 MO-349 93-40 07-26-93 137.81 MO-352 93-49 09-27-93 136.11 MO-354 93-49 09-27 93 136.11 MO-359 93-64 12-20-93 135.08 MO-360 93-64 12 20-93 135.08 Due to the requirement of having less than 5 kg of unirradiated fuel in possession, initial criticalities are obtained with four new elements or fewer as conditions dictate. A core designation consists of eight fuel elements of which only the initial critical fuel element serial numbers are listed in the following table of elements in service 31 December 1993. To increase operating efliciency, fuel elements are used in mixed core loadings. Therefore, a fuel element fabrication core number is different from its core load number. Fabrication Initial Core Initial Serial Number Core Number Load Number Ooernting Date MO-381 63 93-40 07 19 93 510-382 63 93-41 07-26-93 MO-383 64 93-40 07-19-93

       . MO-384                                                    64                   93-41            07-26-93 MO-385                                                    64                   93-48            09 13-93 MO-386                                                    64                   93-49            09-20 93 MO-387                                                    64                   93-48            09-13-93      ;

MO-388 64 93 49 09-20-93 ! MO-389 64 93 51 10-04-93 '! MO-390 64 93-56 10-25-93 MO-391 65 93-51 10-04-93 i MO-392 65 93-56 10-25-93 MO-393 65 93-62 11-29-93 MO-395 65 93-62 11-29-93 ) - 2. Fuel Shipments: Twenty-four spent fuel elements were shipped from MURR to Savannah River Plant, Aiken, South Carolina. The identification numbers of these elements are: MO-316 MO-325 MO-331 MO-337 . MO-318 MO-326 MO-332 MO-338 MO 319 MO-327 MO-333 MO-339 MO-320 MO-328 MO-334 MO-340 M O-323 MO-329 MO-335 MO-341 MO-324 MO-330 MO-336 MO-342 VII-1

3. Fuel Procurement: Babcock and Wilcox, Lynchburg, Virginia, is MURR's fuel assembly fabricator. This work is contracted with the U. S. Department of Energy and administered by EG&G Idaho Inc., Idaho Falls, Idaho. As of 31 December 1993,201 fuel assemblies fab'ricated by B & W had been received and 195 used in cores at 10 MW.

4. Licensing Activities: On July 21,1993, the Nuclear Regulatory Commission approved Amendment No. 24 to the facility operating license R-103. This amendment temporarily increased the Special Nuclear Material inventory limit to 60 kg U-235 pending the completion of spent fuel shipments.

This amendment requires that this annual report include the status of these shipments. Twenty-four spcnt fuel elements were shipped in the period of this ' i report, and one shipment of eight elements is scheduled in 1994. After the 1994 i shipment, the MURR fuel and non-fuel U-235 inventory will be 37,600 grams. A request for a unique purpose exemption as defined in 10CFR50.2 was submitted September 26,1986, and is pending.

5. Reactor Characteristic Measurements: Thirty refueling evolutions were completed. An excess reactivity verification was performed for each refueling and the average excess reactivity was 1.97%. The largest excess reactivity was ,

2.59%. MURR Technical Specification 3.1(0 requires that the excess reactivity .! be less than 9.8%. Reactivity measurements were performed for two evolutions to verify reactivity l parameters for the flux trap. Differential and total worth measurements were made on blade C. l 1 VII-2

SECTION VIII ,

SUMMARY

OF RADIOACTIVE EFFLUENT RELEASED TO THE ENVIRONMENT The stack and sewer efIluent fer the first half of 1993 was reported in our fiscal year 92/93 Annual Report. The data for the second half of 1993 is reported in Table 1 and Table 2. Table 3 and Table 4 show the effluents for the entire calendar year of 1993. The information in the 92/93 Annual Report and these tables demonstrate compliance with efIluent release limits for both Fiscal Year 92/93 and Calendar Year 1993. Table 1. Sanitary Sewer EfIluent 1 July 1993 through 31 December 1993 Descending Order of Activity Released fbr Isotope Totals > 1.00 E-5 Ci: Nuclide Amount (Ci) Nuclide Amount (Ci)

                                           .H -3                          8.627E-02                          Sc-4 6           4.987E-05 S-35                            6.915E-03                          Pd-109           4.911E-05 As-77                           3.322E-03                          Na-24            4.674 E-05 Ca-45                           2.825E-03                          Sb-125           2.558E-05 Co-58                           6.089E-04                          Re-186           2.227E-05 Cr-51                          4.753E-04                           Co-60            2.175E-05 Te-125m                          3.340E-04                          Eu-152           1.880E-05 Eu-154                         1.149E-04                          Se-75            1.848E-05 Zn-65                           5.287E-05                          Co-57            1.613E-05 VIII-1

Table 2. Stack Effluent 1 July 1993 through 31 December 1993 Ordered by % Technical Specification (TS) Limit g Average Total Release Concentration 6/93 - 12/93 TS Limit Isotope (uCi/ml) (Ci) x MPC % TS* Ar-41 5.56E-07 1.4 E + 02 350 3.9714 W-188 2.78E-12 2.6E-05 1 2.7840 I-131 7.88E-13 2.0E 04 1 0.7875 Pd-103 2.21E-10 1.9E-03 1 0.7352 K-40 7.17E-13 1.9E-05 1 0.7169 Cd-109 2.11E-12 9.9E-05 1 0.1053 Lla 133 9.47E-14 1.9E-06 1 0.0947 Eu 152 3.02 E-13 3.3E-06 1 0.0755 II-3 3.76E-08 9.4 E+ 00 350 0.0537 11f-181 4.22E-13 2.0E-06 1 0.0422 Ce-144 7.88E-14 3.6E-06 1 0.0394 Tm-170 2.86 E-13 2.3E-06 1 0.0286 Ce-139 2.80E-14 8.4 E-07 1 0.0280 Co-60 5.68E-14 4.9E-06 1 0.0189 Cd 115 1.86E-13 1.3E-06 1 0.0186 Te-123m 1.79E-14 3.9E-07 1 0.0179 Cs 137 4.78E-14 1.6E-06 1 0.0096 Na-22 2.22E-14 2.5E-07 1 0.0074 Ir-192 5.13E-14 8.3E-07 1 0.0057 Zr-95 5.54E-14 4.5E-07 1 0.0055 Sc-46 4.42E 14 3.6E-07 1 0.0055 Se-75 2.09E-13 4.5E-05 1 0.0052 l-135 1.55E-11 3.5E-03 350 0.0044 l 1133 6.18E-12 1.7E-03 350 0.0044 Pt 195m 1.17 E-12 7.5E-06 350 0.0033 Re-188 6.56E-11 1.GE-04 350 0.0031 Mn 54 3.03E-14 4.8E-07 1 0.0030 1-134 4.49E-11 1.1E-02 350 0.0021 Xe-135m 2.23 E-10 6.4 E-03 350 0.0021 1-128 1.91E-10 1.2E 02 350 0.0018 Ilg 203 6.19E-14 1.6E-05 1 0.0015 Au-196 1.07E-10 1.0E-03 350 0.0015 Ta 182 1.48E-14 1.4 E-07 1 0.0015

                              ' Isotopes observed at < 0.0001% TS limit are not listed.

VIII-2

Table 2. Stack Efiluent (Cont'd) 1 July 1993 through 31 December 1993 - Average Total Release Concentration 6/93 - 12/93 TS Limit Isotope (uCi/ml) (Ci) x MPC % TS* l- Pa-233 7.81E-14 1.4E-06 1 0.0013 I-132 -1.35E 3.2E-03 350 0.0013 Eu-155 3.25E-14 1.4 E-06 1 0.0011 ! Ba 133m 3.19E-13 5.4E-06 350 0.0009 Sb.125 1.76E-13 1.0E-06 .1 0.0009 As-77 2.54 E-11 3.4E-03 350 0.0007 ' Cc-141 3.23E-14 1.8E-06 1 0.0006 Os-191 5.02E-14 2.2E-06 1 0.0005 Sn-113 9.00E-15 9.5E-08 1- 0.0004 Gd-153 3.31E-14 2.7E-07 1 0.0004 Tc-101 3.13E-11 1.3E-03 350 0.0003 Cu 67 1.03 E-13 3.8E-06 350 0.0003 Pd-109 8.93E-12 4.7E-04 350 0.0003 Ta-183 8.02E-14 7.8E-07 350 0.0002 q Cs-138 2.35E-11 6.2E-04 350 0.0002 .! Xe-131m 6.00E-13 1.1E-05 1 0.0001 Ba-139 1.25E-11 6.0E-04 350 0.0001 In-114 m 2.70E-13 5.2E-06 350 0.0001 Kr 87 4.27E-12 1.4 E-04 350 0.0001 l Total 9.5952 . i

Isotopes observed at < 0.0001% TS limit are not listed. I l

l Stack flow rate 33,500 cfm , I. ! 1 i VIII-3

Table 3. Sanitary Sewer EfIluent 1 January 1993 through 31 December 1993

Descending Order of Activity Released for Isotope Totals > 1.00 E 5 Ci:

1 Nuclide Amount (Ci) Nuclide . Amount (Ci) H-3 2.574 E-01 Na 24 3.013E-04 Eu-154 3.012E-02 Se-75 2.151E 04 S-35 1.184E-02 W 188 1.501E-04 As-77 8.293E-03 Sc46 1.169E-04 Ca 45 3.335E-03 Pd-109 - 7.775E 05 1 Te-125m 1.156E-03 Ba-131 7.571E-05 ' Re-186 9.153E-04 Eu-152 6.974E-05 Co-58 6.595E 04 Cd-109 5.192E-05 Cr-51 5.182E-04 Sb-125 4.084E-05 Co 60 4.142E-04 Co-57 3.305E 05 Zn 65 3.083E-04 Ce-144 2.433E 05 i Total H 3 2.574E-01 Total Other 5.871E 02 , i i

                                                                                                                 -1 i

VIII-4 y

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

Table 4. Stack EP 'ent 1 January 1993 through ' ' acernber 1993 Ordered by % Technical Specification (TS) Limit Average Total Release Concentration 1993 MPC TS Limit Isotope (uCi/ml) (Ci) (uCi/ml) x MPC % TS * ' ' F Ar.41 8.20E-07 4.09E+02 4E-08 350 5.8571 W.188 2.78E-12 2.57E-05 1E-10 1 2.7840 I-131 7.73E 13 3.80E-04 1E-10 1 0.7727 K 40 5.89E-13 2.14E-05 1E-10 1 0.5885 Pd-103 1.35E-10. 2.92E-03 3E-08 1 0.4512

    - Eu-152                  3.02E-13               3.34 E-06        4E-10                1    0.0755 Cd-109                  1.26E-12               1.26E 04         2E-09                1    0.0632 11-3                    3.12E-08              1.56E+01          2E-07              350    0.0446
     .11f-181                 4.22E-13               2.00E-06         1E-09                1    0.0422 Pt-195m                 1.17E-12               7.48E-06         3E-09                1    0.0389 Ce 144                  7.49E-14               4.22E-06         2E-10                1    0.0374 Tm-170                  2.86E 13               2.27E-06         1E-09                1    0.0286 Cc 139                  2.16E-14               1.49E-06         1E-10                1    0.0216 Te-123m                 1.79E-14               3.86E-07         1E 10                1    0.0179-Co 60                   5.26E-14               6.72E-06         3E-10                1    0.0175 Ba-140                  1.46E 13               3.34E-06         1E-09               -1    0.0146 Cd-115                  1.34 E-13              2.11E-06         1E-09                1    0.0134 Cs-137                  4.12E-14               2.33E-06         5E-10                1    0.0082 Na-22                   2.22E-14               2.45E-07         3E-10                1   0.0074 Cs 134                  6.10E-14               7.47E-07         IE-09                1    0.0061 Ir-192                  5.13E-14               8.35E-07         9E 10                1   0.0057 Sc-46                   4.42E-14               3.59E-07         8E-10                1    0.0055 Se-75                   2.01 E-13              7.59E-05         4 E-09               1    0.0050 Zr-95                   4.47F 14               8.13E 07         1E-09                1    0.0045 1-133                   6.24E-12               3.23E-03         4E-10              350   0.0045-I-135                   1.55E-11               7,11E-03         1E-09              350   0.0044 Ba 133                  9.47E-14               1.86E-06         3E-09                1   0.0032 Mn-54                   3.03E-14               4.84E-07         1E-09                1   0.0030 Xe-135m                 3.15E-10               1.70E-02         3E-08              350   0.0030 11D                     4.67E-11               2.23E-02         6E-09              350   0.0022 IIg-203 -               7.50E-14               3.66E-05         4 E-09               1   0.0019 Re-188 -                3.30E-11               1.64E-04         GE-09              350   0.0016 Au-196                  1.07E 10               1.02E-03         2E-08             .350   0.0015 Ta 182                  1.48E 14               1.41E.07         1E-09                1   0.0015-
      ' Isotopes observed at < 0.0001% TS limit are not listed.

VIII 5

Table 4. Stack Emuent (Cont'd) 1 January 1993 through 31 December 1993 Average - Total Release > Concentration 6/93 - 12/93 MPC TS Limit Isotope (uCi/ml) (Ci) (uCi/ml) x MPC % TS* Zn-65 2.90E-14 6.38E-07 2E-09 1 0.0015 1 128 1.40E 10 1.49E-02 3E-08 350 0.0013-1132 1.37E-11 6.46E-03 3E-09 350 0.0013 ! Eu-155 3.25E-14 1.35 E-06 3E 09 1 0.0011 I Pa 233 6.26E-14 1.91E-06 6E 09 1 0.0010 Sb-125 1.76E-13 1.02E-06 2 E 1 0.0009 Nb-95 2.39E-14 5.34 E-07 3E-09 1 0.0008 Ba-133m 2.68E-13 6.50E-06 IE-10 350 0.0008 Ce-141 3.23E-14 1.77E-06 5E-09 1 0.0006 Sn 113 1.29E-14 5.00E-07 2E-09 1 0.0006 Sr-85 2.00E 14 1.56E-07 4E-09 1 0.0005 As-77 1.73E-11 4.79E-03 1E-08 350 0.0005 Ru 103 1.31E-14 2.60E-07 3E-09 1 0.0004 Os-191 3.61E-14 4.08E-06 IE-08 1 0.0004 Tc-101 3.13E-11 1.26E-03 3E-08 350 0.0003 Gd-153 2.26E 14 6.19E-07 8E-09 1 0.0003 Ta-183 8.02E-14 7.80E-07 1E-10 350 0.0002 Cr-51 1.83E-13 4.16E.06 8E-08 1 0.0002 , Cu-67 7.95E-14 8.95E-06 1E-10 350 0.0002 Pd 109 6.62 E-12 5.53E-04 1E-08 350 0.0002 Cs-138 1.76E 11 6.24E-04 3E-08 350 0.0002 >. Kr-87 1.08E-11 6.63E-04 2E-08 350 0.0002 ) Xe-131m 6.00E 13 1.12E-05 4E-07 1 0.0001 Co-57 5.66E-15 5.55E-08 6E-09 1 0.0001 ~ In 114m 2.18E-13 5.85E-06 7E-10 350 0.0001 I Ba-139 9.31E-12 1.04 E-03 3E 08 350 0.0001 ! Total 10.9520

Isotopes observed at < 0.0001% TS limit are not listed.

l Stack Dow rate 33,500 efm j { VIII-6 i

                                .                  ..                _                    .         , . ~

                                                                                                       'l l

1 SECTION IX 1

SUMMARY

OF ENVIRONMENTAL SURVEYS 1 1 July 1993 through 31 December 1993 Environmental samples are collected two times per year at eight locations (HP-11: " Environmental Sampling") and analyzed for radioactivity. These locations are shown in Figure 1. Soil and vegetation samples are taken at each location. Water samples are taken at three of the eight locations. Results of the samples are shown in the following tables.

1. Sampled during December 1993.

Detection Limits

Matrix Aloha Beta Gamma Tritium Water 0.5 pCi/l 2.7 pCi/l 200.5 pCi/l 13.6 pCi/ml ofsample Soil 0.5 pCi/g 2.7 pCi/g 0.4 pCi/g N/A Vegetation 1.0 pCi/g 5.4 pCi/g 1.4 pCi/g 13.6 pCi/ml ofdistillate
Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights.

Determined Radioactivity Levels Vecetation Samules Alpha Beta Oamma H-3 Samnle (nCi/c) (oCi/c) (pCi/c) (nCi/c) 1-V-44 < 1.0 18.3 < 1.4 < 13.6 2-V-44 < 1.0 27.3 < 1.4 < 13.6 3-V-44 < 1.0 24.4 < 1.4 < 13.6 4-V-44 < 1.0 24.6 < 1.4 < 13.6 5-V-44 < 1.0 26.8 < 1.4 < 13.6 6-V-44 < 1.0 20.6 < 1.4 < 13.6 7-V-44 < 1.0 27.2 < 1.4 < 13.6 10-V-44 < 1.0 33.8 < 1.4 < 13.6 : i IX-1 ; y -,9---

I g ._.. \ n. ~ --_a, \ 0) l. f

                                                                                          ,_                                 y

_ __. __/ if ' i men.e 1 's,

              -c= '           ~                                                                                                                                                               i
                                                                                                                                                                                                          ",L 8

t s ! !% mf ; i ,! i) ' ' q-- , f f/ s. / s ~ _ m

                                                     ';       m                                                         F                                                                       f
                                                                                                               ,)                                -e       ea             h                  it =

4

                                                                                                                                                   "[        v j                            .q -

p, _2 __ ff\m+ k + - a n : L 8 e

                                                                                                                                                                    .                         \ j'fr,w y ,y;,,,g-m __                                     /-
                                                                                    ~T~ _ /e)1___._

hD a J

                                          \ %m E                                                                     l r                     " ~ ~ "
                                                                                        ,.                           't
                                                ,1 , .. . ../

Qq ' Oq O Y t w [ i

                                                                                                                                            \ MURR \

i

                                                                                                               . \;\

t i

                                                                                                                             ' '   L.--      -
                                                                                                                                                                   \                                  a
                                                                                                                                                                      \                      5 s                                                                < -
                                                                                .....                           /                                                       s                   '~'~

p ~ g l e s - j g r_ _ i : c' 1

                                                             .T - ' g,/-
                                                                                                                    -u==={         .____ ..___ _____

f; x Figure 1. MURR Environmenta1 Program Sample Stations HOTE: September 1983 City sewerage plants at stations 8 and 9 closed. All waste water now processed at City Waste Treatment Fact 11ty at station 10.

Determined Radioactivity Levels Soil Samnles Alpha Beta Gamma l Sample (nCi/e) (nCiM (pCi/c) 1-S-44 < 0.5 18.6 6.1 , 2-S-44 < 0.5 19.6 5.8 3-S-44 0.7 13.4 5.1 4-S-44 0.6 5.8 3.4 5-S-44 0.7 12.7 5.0 6-S-44 < 0.5 12.0 5.5 7-S-44 < 0.5 14.6 5.7 .j 10-S-44 < 0.5 18.1 6.0

                                                                                               -l Determined Radioactivity Levels Water Samples Alpha                               Beta      Gamma                 H-3 Samnle   (nCiA)                     (pCiA)               (nCi/l)            (nCi/ml)           ]I 4 W-44    0.6                               12.6       < 200.5             < 13.6 6-W-44  < 0.5                                 7.2      < 200.5             < 13.6 10-W-44  < 0.5                                16.3      < 200.5             < 13.6             )

l IX-3

ENVIRONMENTAL TLDs l The MURR Health Physics staff have continued to work with Landauer, Inc. in i the development of a TLD monitoring program to monitor external doses around the MURR Facility. The table on the following page lists the results of monitors as they I were deployed in 1993. A design for the monitors has been determined, but their placement is still under development. All totals remained below 100 mrem / year, except monitor number 9. L This monitor is located on the side of the MURR building near the loading dock where radioactive shipments are made. This monitor, along with the other five monitors that had readings greater than 25 mrem / year, were alllocated on the brick exterior of the building. A test during the first quarter in 1993 showed that a monitor mounted on a brick structure 65 meters from the reactor building recorded 15.1 mrem where its counterpart equidistant, but deployed in a tree, was 4.6 mrem. , Shipping and deployment controls are carried with each set and stored at a distant site. These are used to determine background which is subtrated from each of the monitors. This normalizes all of the monitors and compensates for any exposure I they may experience in transit. Negative numbers on some of the monitors indicate that dose levels at the deployment site are not significantly different than background. 1 l l I I IX-4 i _ _ _ _ _ _ _ _ - _ - _ - - _ . _ _ _ _ _ _ _ - _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ - _ - _ = _____ ___ ___ - _ _ _ _ _ - _ _ - _ _ _ _ -

Environmental TLD Summary January through December 1993 Map Distance from- 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Total Badge ' Direction MURR Stack 1993 1993 1993 1993 1993 Number From MURR (meters) Net mR Net mR Net mR Net mR Net mR 1 Control N/A 1.6 -1 -0.7 0 -3.3 2 Control N/A -1.4 1.4 -0.9 1.1 -2.6 3 Control N/A -1.2 -0.8 -0.8 4.6 1.8 4 Control N/A -1.1 -1 1.8 3 -0.9 5 Control N/A -1.1 -1.7 -0.3 1.2 -1.9 6 NNE 34 7.5 10.9 9.8 28.2 7 ESE 57 14.7 22.2 20.6 22.2 79.7 8 WSW 27 16.4 19.6 19.9 39.1 95 9 SSE 27 61.8 86.2 70.6 56.8 275.4 10 NE 149 0.8 2.5 0.5 -0.1 3.7 11 N 149 2.8 4.4 3.5 4.8 15.5 12 ENE 301 3.9 6.2 6 9.9 26 13 NNE 316 2.3 3.3 -4 2.7 4.3 14 S 156 4.3 6.9 2.7 4.4 18.3 15 S 65 15.1 26.6 18 18.7 78.4 16 SE 107 3.1 8.8 4.1 1.4 17.4 17 E 293 2.5 5.3 1.5 0.1 9.4 18 NE 476 5.8 3.1 0.3 9.2 19 NNE 606 3 4.1 1.3 8.4 20 NE 907 1.4 4 2.7 1.3 9.4 21 SE 236 1.2 7.4 2.6 1.2 12.4 22 ESE 168 -1.6 0.6 -0.8 -3.7 5.5 23 NW 110 0.7 2 2 -0.1 4.6 24 SSW 328 -1.8 0.6 2 0.1 0.9 25 SSW 480 1.4 4.5 2.9 1.4 10.2 26 SW 301 3.7 5.5 4.1 3.4 16.7 27 WSW 141 -1.3 -0.5 -0.4 -1.6 -3.8 28 WNW 210 3.4 5.4 4.1 4.5 17.4 29 NW 255 3.3 4.7 3.6 5 16.6 30 NNW 328 0.4 3.9 3.4 2.6 10.3 31 NNE 671 3.9 2.9 3.5 5.1 15.4 32 NNW 724 2.6 9.9 4.6 2 19.1 33 E 671 -0.5 6.7 -1.3 4.9 34 ENE 587 -0.7 1.7 1.7 -0.1 2.6 35 SSE 499 2.3 2.2 1.5 2.9 8.9 36 SE 419 2.2 7.4 5.5 3.4 18.5 37 NE 690 -0.9 0 -0.4 -3.1 -4.4 38 NW 556 3.9 9.1 5.8 2.6 21.4 39 W 491 4.1 7.1 3.5 14.7 40 N 514 1.6 7.4 5.4 2.5 16.9 41 ENE 137 3.4 8.1 4.3 3.3 19.1 42 In lluilding N/A 15.8 10.5 10.6 6.2 43.1 43 In Building N/A 7.2 9.1 -4.7 11.5 23.1 44 Distant Site N/A -0.9 0 -1.1 -2 45 Distant Site N/A 4.6 6.8 5.3 5.2 21.9 IX-5

NUMBER OF FACILITY RADIATION AND CONTAMINATION SURVEYS Surface Air Radiation Contamination

Samules RWP 1993 l July 32 32 32 7 I

! August 27 27 30 7 September 12 10 29 7 October 36 34 28 9 i November 36 36 30 11 December 51 _4fi _l33 8 TOTALS 194 185 182 49 1 ! *Eqts: In addition, general building contamination surveys are conducted each l normal work day. Miscellaneous Items In January 1993 Dr. Susan M. Langhorst, Manager Reactor Health Physics, began a one year sabbatical with the Committee on Interagency Radiation Research and Policy Coordination (CIRRPC)in Washington, DC. CIRRPC is a research committee responsible for advising Federal Agencies on Health Physics policy. Dr. Langhorst will return to MURR the first of March,1994. Mr. John Ernst is Acting Health Physics Manager in her absence. September 1,1993, Mr. F. Scott i Keithlyjoined the group as a Health Physics Technician. Scott has over ten years l experience as a Health Physics Technician in nuclear power plants and naval ship yards. The University made application to the NRC for renewal ofit Broad Scope Materials License on February 27,1992. The renewal application asked for separate licenses for each of the four university campuses and for MURR. The NRC ismed MURR a Broad Scope Materials License effective July 7,1993. ADCO Services continues to function as radioactive waste broker for MURR. Through ADCO we disposed of 270 cubic feet of LSA material during the second half-of 1993. The ALARA program implemented to document efforts to reduce personnel exposure continues to function. MURR personnel and other users of the Center are assigned to research or operational groups for the purpose of ALARA review. The average monthly whole body deep dose to individuals in each group are shown in the following table: IX-6

l 1 Groun Name Averace Monthly Dose Actinide Chemistry 10 mrem Computer Development minimal Electronic and Mechanical Properties minimal j Director's Office minimal J Facilities Operations 10 mrom ; Gamma Ray Scattering 10' mrom ] Health Physics 40 mrem i Instrument Development minimal ' i Magnetic and Crystal Structure minimal Nanostructures and Excitations 10 mrem Neutron - Optics 10 mrem Nuclear Analysis Program minimal Nuclear Archaeology and Geochemistry minimal Nuclear Engineering minimal Operations 80 mrem Radiobiochemistry 10 mrem Radiopharmaceutical 10 mrem Services Applications 20 mrem t f f i b i IX-7 3

                    ,        r , -         -

m

SECTION X

SUMMARY

OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS, AND VISITORS 1 July 1993 through 31 December 1993

1. Largest single exposure and average exposure are expressed in millirem.

2. Minimal exposure is defined to be gamma <10 mrem; beta < 40 mrem; neutron < 20 mrem.

3. ME = Number of monthly units reported with minimal exposure.

4. AME = Nmnber of monthly units reported with exposure above minimal.

5. AE = Average mrem reported for all units above minimal.

6. HE = Highest mrem reported for a single unit for the month.

7. Dosimetry services except for "Self Reading Dosimeters" are provided by R. S. Landauer, Jr. & Co.

Dosimeter Types: "C" - X, Gamma, Beta, Fast Neutron (Neutrak 144), Thermal Neutron; "G" - X, Gamma, Beta; "U" -TLD (1 Chip Ring). PERMANENTISSUE BADGES "C" Whole Body Badges (Deep Dose): ~ JUL AUG SEP OCT NOV DEC ME 149 154 144 112 132 152 AME 58 51 55 98 73 54 AE 59 63 61 47 63 83 HE 160 210 180 210 190 250 "G" Whole Body Badges (Deep Dose): JUL AUG SEP OCT NOV DEC ME 79 79 74 79 81 80 AME 3 3 5 7 2 4 AE 20 30 20 14 15 20 HE 30 50 50 30 20 30 "U" TLD Finger Rings: JUL AUG SEP OCT NOV DEC ME 160 160 148 178 158 166 AME 84 74 89 72 86 79 AE 138 115 111 124 136 147 HE 570 510 490 420 710 600 ; 1 X-1

SECTION X

SUMMARY

OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS, AND VISITORS (CONT'D) Self Reading Dosimeters: JUL AUG SEP OCT NOV DEC ME 4 10 18 8 11 13 AME 111 117 93 104 105 109 AE 44 27 44 46 44 50 HE 214 207 183 222 186 279 SPARE ISSUE BADGES "C" Whole Body Badges (Deep Dose): JUL AUG SEP OCT NOV DEC ME 60 71 72 64 66 69 AME 60 3 2 10 9 3 AE 150 10 180 25 26 47 HE 170 10 180 60 120 80 "G" Whole Body Badges (Deep Dose): JUL AUG SEP OCT NOV DEC ' ME 61 61 62 61 61 61 AME O O 1 0 0 0 AE O 0 60 0 0 0 HE O O 60 0 0 0 'U' TLD Finger Rings: JUL AUG SEP OCT NOV DEC ME 32 37 32 35 30 35 AME 16 10 6 3 8 3 AE 113 164 110 43 90 63 HE 250 340 250 60 190 70 7 X-2 l

!}}

@@ Line 2: / Line 2: @@
 | number = ML20063M204
 | issue date = 12/31/1993
-| title = Operations Semiannual Rept Jul-Dec 1993. W/940303 Ltr
+| title = Operations Semiannual Rept Jul-Dec 1993
 | author name = Meyer W
 | author affiliation = MISSOURI, UNIV. OF, COLUMBIA, MO

ML20063M204: Difference between revisions

Latest revision as of 16:56, 6 January 2021

Text

REFERENCE:

SUMMARY

1.0 Purpose and Scope

1.2.1 MURR-SAS-00000

1.2.2 MURR-SAS-00001

1.2.3 MURR-SAS-00002

1.2.4 MURR-SAS-00003

1.2.5 MURR-SAS-OOOO4

1.2.6 MURR-SAS-00005

3.1 Activity

3.5 Performer

3.8.1 Shall

3.3.3 Should

1.0 Purpose and Scope

4.1 Activity

4.5.3 Should

1.0 Purpose and Scope

4.5.3 Should

5.0 RESPONSIBILITIES

1.0 Purpose and Scope

3.6 Labels

4.0 DEFINITIONS

SUMMARY

1.0 Purpose and Scope

4.1 Activity

4.4 Observer

4.5 Performer

4.8.2 hht11

4.8.3 Should

SUMMARY

SUMMARY

Description:

Description:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

Search