ML20080M428
| ML20080M428 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 12/31/1994 |
| From: | Meyer W MISSOURI, UNIV. OF, COLUMBIA, MO |
| To: | Weiss S NRC |
| References | |
| NUDOCS 9503030208 | |
| Download: ML20080M428 (192) | |
Text
{{#Wiki_filter:._- . - - - lJ A I Res~earch Reactor Center II Research Park Cdumbia, Missouri 65211
; UNIVERSITY OF MISSOURI-COLUMBIA we%gfg2fg February 28,1995 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 Enclosed are two copies of the Reactor Operations Annual Report for the University of Missouri Research Reactor. The reporting period covers 1 January 1994 through 31 December 1994. If you have any questions, please feel free to call. Sincerely, I h Walt A. Meyer Jr. Reactor Manager bjb 000089 enclosures xc: Document Control Desk, USNRC / 9503oso20s 941231
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UNIVERSITY OF MISSOURIL a l UNIVERSITY OF MISSOURI- 1
. q
. RESEARCH REACTOR 1 1 t 4 , 2
.)
- :l REACTOR OPERATIONS- 1 i
f- ' . A1NNUAL REPORT 1
.. -j 1
1 January 1994 - 31 December 1994- j
- . j
! a 1-l l i , ^! RESEARCH REACTOR FACILITY l l !
t i UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY ! s l l i REACTOR OPERATIONS , i ANNUAL REPORT 1 January 1994 - 31 December 1994 j l i Compiled by the Reactor Staff l Submitted February 1995 by Walt A. Meye , Jr. : Reactor Manager , Reviewed and Approved J. Charles McKibben Associate Director j
r. o t TABLE OF CONTENTS i Section Eaga L Reactor Operations Summary I-1 through 8 IA. Changes to the Technical Specifications IA-1 through 2 ; II. MURRProcedures II-I through 10 l A.~ Changes to Standard Operating Procedums B. Changes to MURR Site Emergency Procedures and Facility Emergency Procedures l C. Changes to Health Physics Standard Operating Procedures D. Changes to MURR Shipping Procedums III. Revisions to the Hazards Summary Report III-1 through 11 IV. Plant and System Modifications IV-1 through 2 V. New Tests and Experiments V-1 : VI. Special Nuclear Material Activities VI-1 through 2 VII. Reactor Physics Activities VII-1 thmugh 3 i VIII. Summary of Radioactive Efiluent Released to the . Environment VIII-1 through 2 ; i IL Summary ofEnvironmental Surveys IX-1 through 8 : X. Summary of Radiation Exposures to Facility Staff, Experimenters and Visitors X-1 through 2
+
p 3.
. SECTION I t 3 t N REACTOR OPERATIONS SUlOIARY !
~ 1 January 1994 through 31 December 1994 l The following table and discussion summarizes teactor operations in the period i 1 January 1994 through 31 December 1994.
Full Power Percent - Data Full Power Hours MeFawatt Days of Total Time ofSchedule* ; Jan. 1994 669.63 279.24 90.00 '100.80 $
'Feb. 1994 583.22 243.09 86.79 97.20 i Mar. 1994 673.99 281.01 90.59 101.46 i Apr. 1994 648.15 270.20 90.02- 100.82 l May 1994 656.34 ,273.65 88.22 98.80 .
Jun. 1994 649.24 270.64 90.17 100.99 +
. Jul. 1994 671.99 280.14 90.32 101.16 Aug. 1994 674.31 281.10 90.63 101.51 i t
Sep. 1994 659.49 275.01 91.60 102.59 Oct. 1994 668.91 278.97 -89.91 100.70 Nov. 1994 660.62 275.37 91.75 102.76
- Dec. 1994 675.48 281.62 9.QJJt 101.69
?
Total for one 7,891.37 3,290.04 90.08% of 100.89% of - year period time for 12 mos. sched. time for ; at 10 MW 12 mos. at 10 MW r
- 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 year. )
)
'l There wem fourteen unscheduled shutdowns recorded during the period 1 January 1994 through 31 December 1994. Of these unscheduled shutdowns, seven were !
scrams and seven were rod run-ins (RRIs).- ( I Five of the unscheduled shutdowns were manually initiated scram or rod run-in to allow investigation and/or repair ofvarious reactor equipment. The remaining nine unscheduled shutdowns were spurious in nature. Four spurious rod run-ins were associated with closing the Channel 4 (wide range) nuclear instrument drawer. Electmnics technicians have investigated each case, but the source of the spurious RRIs is uncertain. Two spurious scrams early in 1994 were attributed to the Trip Actuator Amplifier (TAA) associated with the reactor scram and rod run-in circuits. Since the - l trip point on each TAA was set to the same value in Manh 1994, no unscheduled shutdowns associated with the TAAs have occurred. There were two Licensee Event Reports (LERs) submitted to the NRC in 1994. One in April regarding the regulating blade being inoperable for a period of 6 te 7 minutes and one in September regarding an airlock door failum msulting in a momentary loss of containment integrity. Neither of the events detailed in the LERs represented a safety concern to the reactor or the public. 1-1
' =
The University of Missouri Research Reactor received two notices of violation by the NRC in 1994. One Notice of Violation was for apparent violation o# 10CFR50.7, Employee Protection from Discrimination. A second Notice ofViolation involved violation of 10CFR71.5(a) and applicable Department of Transportation regulations associated with radioactive material shipments. MURR sent a reply to the NRC for each violation describing the mrrective actions being implemented to ensure these violations will not recur. January 1994 The reactor operated continuously in January with the following exceptions: five - shutdowns for scheduled maintenance and refueling; one unscheduled shutdown. On January 18, a spurious reactor scram oc;urred during a normal startup when the safety system green leg TAA (serial #135) tripped, dropping control blades "C" and "D". This action initiated a " rod notin contact with magnet" rod run-in, causing control blades "A" and "B" to drive in. The yellow leg TAA (serial #137) did not trip. Both yellow and green leg TAAs were able to be reset, indicating that a true scram signal had not occurred in either leg. A valid scram signal will trip both TAAs because of the non-coincidence logic units (NCLU) that precede them. These NCLUs were tested to verify that a valid trip from either the yellow or green leg would initiate a scram from both TAAs. This was done by opening the contacts of the power level interlock relays in eachleg. The electronics technicians investigating this type of spurious scram found that the trip setting on the green leg TAA (sedal #135) was about 1.2 volts higher than the yellow leg TAA (serial #137). They concluded that a high resistance in the series of contacts that comprise the green and yellow leg could result in an intermediate voltage level being applied to the TAA input [the input is normally full voltage (non-tripped) or zero voltage (tripped)) which could cause only the TAA with the higher trip point to trip. This determination was further supported by additional investigation after a similar unscheduled shutdown in March 1994. In order to gain additional information to isolate the source of the spurious scram, TAA (serial #135) was placed in the yellow leg of the safety system and a spare TAA (serial #138) was installed in the greenleg of the safety system. Major maintenance items for the month included: replacing the reliefvalve on the anti-siphon tank; replacing valve 527F (primary demineralizer isolation) air diaphragm and valve 527A (pressurizer drain) o-ring and valve diaphragm; and installing a spare TAA in the yellow leg of the safety system. I-2
- t. <
x . . l I February 1994 Ihe reactr,r operated continuously in February with the following exceptions: four shutdowns for scheduled maintenance and refueling. There were no unscheduled shutdowns this month. Mador maintenance items for the month included: performing Special Maintenance Pmcedum, SMP-31, removing the originally installed graphite reflector elements 2 and 3-through which beamports "B" and "C" extend, and replacing them j
- with new reflector elements; removing the experimental cans from beamports "B" j and "C" per modification package 94-1; removing the collimator in beamport "C";
replacing valve 565A (drain collection tank outlet) air operated diaphragm; and j installing a bag-filter housing on the air pump inlet of the pneumatic tube operation j system. ; t i March 1994 ; The reactor operated continuously in March with the following exceptions: four : shutdowns for scheduled maintenance and refueling; two unscheduled shutdowns. l On March 9, a spurious reactor scram occurred when the safety system yellow t leg TAA (serial #135) tdpped, dropping control blades "A" and "B". This action : initiated a " rod not in contact with magnet" rod run-in, causing control blades "C" and "D" to drive in. The green leg TAA (sedal #138) did not trip, indicating that a valid trip .l signal had not occurred on either safety leg. The yellow leg TAA (serial #135) was replaced by a spare TAA (serial #137). TAA (serial #135) was bench tested and ; found to have a trip setpoint 1 to 2 volts higher than the other TAAs. The non- l coincidence logic units (NCLU) were antisfactorily tested to verify that a valid trip .l from either the yellow or green leg would initiate a scram from both TAAs. j The spurious scram was caused by higher than normal resistance in the senes . mechanical relays that comprise a voltage divider at the input to the NCLUs. A' ! change in the series resistance of a number of relay contacts is not uncommon and [ depends on relay contact surface condition and spring tension, which can vary. A . ! higher than usual resistance in the series contacts in this leg resulted in a voltage level applied to the input to both TAAs that was lower than the yellow leg TAA (serial l
#135) trip point but higher than the green leg TAA (serial #138) trip point. j Electronics technicians installed a spare TAA module in t' e yellow leg of the :
safety system and set the trip setpoint to match the green leg TAA. No further '!
' spurious scrams of this nature have occurred since that tune.
l I-3
1 4 On March 29, a epurious reactor isolation occurred when one of the two area radiation monitor mcdules for the air plenum did not dete::t a threshold number of
- input pulses fmm its detector. This automatically initiated a scram trip and reactor containment isolation. The Eberline area radiation monitors in use are designed to initiate an automatic alarm or trip (a protective feature in the event of detector failure)if the background radiation drops below the detectable range for a specified period of time (approximately one minute between input pulses). After conferring ,
with Health Physics personnel, stronger background sources were placed inside the 1 ARMS monitor boxes to ensure that the background radiation at the detectors remained in the detectable range. All personnel had exited the reactor cantainment building as required by procedure when the reactor isolation occurred. The reactor ' was subsequently restarted and no further problems of this type have occurred. Major maintenance items for the month included: replacing solenoid valve 529D actuator for valve 527B (pressurizer charging); replacing the yellow leg TAA with a spare; installing a new breaker in the 120/240 V power distribution center dedicated to the electric forklift charger; replacing the scram trip lamps on pressure transmitters 944 A & B (core discharge) and 943 (primary). Anril 1994 l The reactor operated continuouslyin April with the following exceptions: four l shutdowns for scheduled maintenance and refueling. There were no unscheduled , i shutdowns this month. On April 26,1994, the regulating blade drive mechanism was inoperable for a period of six to seven minutes. Operation of the reactor during this time deviates ! from Technical Specification 3.2.a. which states, "All control blades, including the regulating blade, shall be operable during reactor operation." A Licensee Event l Report detailing this deviation from Technical Specifications and the corrective ! actions was sent to the NRC on May 26,1994. Major maintenance items for the month included: biennial change-out of control blade offset "B"; installing a new silicon wedge (with detectors) in the I/J position; replacing Beamport "A" liner; and replacing Beamport "F" centertube. ) May 1994 ; i The reactor operated continuously in May with the following exceptions: five . ' shutdowns for scheduled maintenance and refueling and one shutdown for flux trap sample changes. The biennial emergency preparedness drillinvolving outside emergency support organizations was completed May 16,1994. l I-4 l
i i , , 1%or maintenance items for the month included: mplacing the outer personnel airlock door motor; replacing the primary Te MV/I millivolt transmitter; a4usting the . ctop for the closed position indication for valve 543A (anti-siphon); modifying the agnidng blade drive motor coupling by drilling a hole thmugh one allen set screw and shaft and inserting a cotter pin; installing new exerciser timer in the emergency diesel generator; and replacing the primary demineralizer inlet conductivity meter. June 1994 The reactor operated continuously in June with the following exceptions: four shutdowns for scheduled maintenance and refueling; one unscheduled rod mn-in. On June 13, a channel #4 high power rod run-in occurred when the channel #4 ; drawer chassis contacted the drawer stop while being pushed back into the instrument cabinet after a@usting the gain potentiometer. No actual high power was , indicated on any instruments. - Attempts to duplicate this event were unsuccessful. l The rod run-in was subsequently reset and the reactor was returned to normal . cperation. Electronics technicians examined and tested the drawer on the next i scheduled maintenance day and were not able to duplicate the problem. This problem recurred several additional times (July, October and December)in 1994. On June 6, a waste shipment ofirradiated metal hardware was shipped to and eccepted by the facility at Barnwell, South Carolina. i Major maintenance items for the month included: replacing the regulating blade shaft coupling; replacing pool loop "B" GE type flow transmitter with a new Rosemount transmitter; repairing the diesel generator emergency shutdown switch; and replacing the scram trip light for primary pressure transmitter 943 meter relay trip unit. July 1994 The reactor operated continuously in July with the following exceptions: five shutdowns for maintenance and refueling or flux trap changes; three unscheduled shutdowns. On July 1, a manual scram was initiated when a small air leak was discovered in the inflatable sealing gasket of the outer personnel airlock door. The leak was not on the seating surface of the gasket and was so small that sealing pressure stayed within its normal operating limit and containment integrity was not compromised. The gasket was replaced and tested satisfactorily and the reactor was refueled and returned to normal operation. I-5
i 4 . 4 On July 29, a manual scram was initiated when the leading edge hanger bolt on the inner personnel airlock door shoud, rendering the door inoperable. As part of the .- normal operating sequence, the outer personnel airlock door was closed and sealed at the time the inner door hanger bolt failed. Containment isolation was not lost while the reactor was operating. The bolt was replaced and the door was tested ' satisfactorily. The reactor was then ufueled and returned to normal operation. On July 30, a spurious md run-in occurred simultaneously with pushing the NI ; channel #4 drawer back into the instrument cabinet after adjusting the gain potentiometer. There were no unusual or abnormal madings indicated on any instrumentation prior to or aftar this occurrence. 'Ihe rod run-in was reset and, while suberitical, an attempt to duplicate the rod run-in by opening and closing the channel
#4 drawer was unsuccessful. The cause was determined to be spurious, but coincident with the physical movement of the channel #4 drawer. Electmnics ,
technicians investigated this problem during the following maintenance day, August 1, but could not repmduce the spurious rod run-in. MWor maintenance items for the month included: replacing the inflatable sealing gasket on the outer personnel airlock door; replacing the pressurizer high pressure , i alarm switch (PS 946); installing a new evacuation horn and light in laboratory #215; , replacing the diaphragm and inlet and outlet flexitallic gaskets on primary valve 540A; and replacing the leading edge hanger bolt on the inner personnel airlock door. August 1994 i The reactor operated continuously in August with the following exceptions: five - shutdowns for scheduled maintenance and refueling. There wem no unscheduled t shutdowns this month. MWor maintenance items for the month included: replacing one of the two lower guide springs on the inner personnel airlock door; removing the Nuclepore irradiator case to shielded storage; and replacing the resin in the fission pmduct monitor. Sentember 1994 The reactor operated continuously in September with the following exceptions: four shutdowns for scheduled maintenance and refueling; thme unscheduled ; shutdowns. On September 2, a manual scram was immediately initiated upon the discovery i of the failure of the inner personnel airlock door drive mechanism. The door drive ' chain became detached from the door when the coupling that attaches it to a shock l
. I-6 i 1
1
e 3 absorber Wa== unthreaded, rendering the door inoperable, and ultimately causing a momentary loss of containment. The chain coupling was rethreaded and j subsequently has been modified to include a 1/8" roll pin to prevent a acurrence of j this type of failure. A letter to the Director of Nuclear Reactor Regulation was sent on September 30 describing this incident and corrective actions taken. On September 12, a manual rod run-in was initiated during a normal startup when erratic indications were noted on NI channel #2 (intermediate range monitor). I Electmnics technicians investigated and isolated the problem to the signal connector within the drawer. The suspected connector was cleaned and the drawer was placed l back in service and tested satisfactorily. The startup was completed and no further problems of this type have recurred. On September 27, a spurious rod run-in occurred with no abnormal or unusual indications on any instrumentation. The rod run-in was reset and the rod run-in trip ectuator amplifier (TAA) was manually tripped and reset satisfactorily to test its cperation. Reactor power was subsequently recovered. On the next scheduled maintenance shutdown (October 3), electronics technicians replaced the rod run-in TAA with a spare to help isolate the source of the spurious rod run-in should it recur. Major maintenance items: removed the south side pneumatic tube biological shield penetration section, and blank flanged or sealed off the open sections; and l mpaimd inner personnel airlock door drive chain. October 1994 The reactor operated continuously in October with the following exceptions: four shutdowns for scheduled maintenance and refueling; one unscheduled shutdown. On October 18, a spurious rod run in occurred coincident with closing the wide range (channel #4) monitor drawer after completing a routine gain potentiometer change. No abnormal or unusual indications were noted on any instrumentation-other than the 95% downscale alarm on the annunciator. The rod run in was subsequently reset and the reactor was returned to normal operation. On the following maintenance day (October 24), electronice technicians thoroughly inspected the wide range monitor drawer components and cable connections. Any suspect cable or lead connection was re-soldemd. Major maintenance items for the month included: installing a spare rod run-in trip actuator ampli6er; replacing the inner personnel air-lock door gear box; correcting a mismatch in air flow between the dispatch and return modes of the pneumatic tube cperating system; completing the biennial preventive maintenance replacement of control blade offset mechanism "D".
, I-7
f i November 1994 The reactor operated centinuously in November with the following exceptions: five shutdowns for scheduled refueling and/or maintenance; one nn-haduled i
- shutdown.
On November 21, a spurious md run-in occurred fmm nuclear instrument channel #4 (wide range monitor) coincident with mamantadly turning offits chart reconfer. The chart reconter was im= 'intely turned back on and the rod run-in was meet and reactor power was quickly motored. No actual high power condition occurred. Major maintenance items for the month included: mplacing an alann relay on the Uninterruptible Power Supply; in=+=11ing a new isolation valve on the secondary P-4 line; replacing a piping elbow on 10" secondary line to pdmary heat exchanger 503B; replacing o-rings in the actuator for the primary outlet isolation valve, 507B;
. replacing the microswitch for the wide range monitor (channel #4) reearder " greater than red set point" in the regulating blade automatic contml prohibit circuit; and unloading depleted pool deionization resin bed "R"-loading new pool main bed "E".
December 1994 3 The reactor operated continuously in December with the following exceptians: four shutdowns for scheduled maintenance and refueling; two unscheduled shutdowns. j On December 18, a manual scram was initiated when the inner personnel airlock I door closed on a transfer cart, wedging the cart between the door and the door frame, i and temporarily rendering the doorinoperable. 'Ihe outer airlock door remained closed with its seal inflated to maintain containment integrity until after the reactor was shutdown and secured. The inner airlock door was subsequently opened manually and the cart was i removed. The inner airlock door and its safety edge were inspected and tested for operability and were determined to be operating satisfactorily. The reactor was then ufueled and returned to normal operation. On December 12, a spurious rod run-in occurred coincident with closing the wide range monitor (channel #4) drawer after completing a routine gain potentiometer change. No abnormal or unusual indications were noted on any instrumentation. The f rod run-in was subsequently reset and the reactor was aturned to normal operation. The precise cause for the rod run-in has not been determined. Electronics technicians have continued to investigate this type of spurious rod run-in. Major maintenance items for the month included: replacing bearings and machanie=1 seal on pool demineralizer pump 513B; replacing inboani and outboani moty bearings on pump 513B; and replacing the room 114 exhaust absolute filters. I-8
s t SECTION IA CHANGES TO THE TECHNICAL SPECIFICATIONS 1 January 1994 through 31 December 1994 MURR TECHNICAL SPECIFICATIONS (Manualissued 7/9/74) l Revision Number 8 Amendment Number 25 AmendmentDate: 3/2/94 i Section Page Number Number 6.1 6 of 8 IA-1
m TECHNICAL SPECIFICATION ' , I d 7g UNIVERSITY GF MISSOURI (\ k RESEARCH REACTOR FACILITY Number 6.1 Page 6 of 8 Dato 3/2/94
SUBJECT:
Administrution (continued) reactor safety system from performing its safety function as described in the Technical Specifications. For each such occurrence, the University of Missouri shall notify within 24 hours, by telephone or telegraph, the Director of Regulatory Operations and shall submit within ten (10) days a report in writing to the Directorate of Licensing, with a copy to the Directorate of Regulatory Operations. (2) The Directorate of Licensing shall be informed in writing within thirty (30) days of its observed occurrence any substantial variance disclosed by operation of the reactor from performance specifications contained in the Hazards Summary Report or the Technical Specifications. (3) The Directorate of Licensing shall be informed in writing within thirty (30) days of its occurrence any significant changes in transient or accident analysis as described in the Hazards Summary Report. (4) An annual report on reactor operation due 60 days following each calendar ] year to include: (a) A brief narrative summary of (1) operating experience (including operations designed to measure reactor characteristics), (2) changes in facility design, performance characteristics and Amendment No. 25
- - - - - ~ . __
8 MURR TECHNICAL SPECIFICATIONS (Manualissued 7/9/74) Revision Number 9 Amendment Number 27 Amendment Date: 11/4/94 Section Page Number Number 3.3 2 of 5 3.3 S of 5 4.4 1of3 1A-2
9 TECHNICALSPECIFICATION , UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY Number 3.3 Page _.2 _ of 5 DateNovember 4,1994
SUBJECT:
Reactor Safety System (continued) 2 1 0 425(4) gpm (Min) for each 50% Pool Coolant Flow capacity heat exchanger leg or 2 2 0 850(4) gpm (Min) for one 100% capacity heat exchanger 2.52 psi (Min) Differential Pressure Across 8.00 psi (Max) 1 0 0 Reflector 0,63 psi (Min) Differential Pressure Across 0 1 0 2,00 psi (Max) Reflector Differential Pressure 3200(5) gpm (Min) 1 0 0 Across Core DifTerential Pressure 1600(5) gpm (Min) 0 1 1(2) Across Core Pressurizer High Pressure 1 1 1(2) 95 psia (Max) 1 1 1(2) 16 inches below centerline (Min) Pressurizer Low Level 0 0 1 23 feet (Min) Pool Level Primary Coolant Isolation Valves 507A/B Off Open Either valve 1 1 1(2) Off Open Position Position Pool Coolant Isolation Valve 509 Off Open Valve 509 Off Open 1 1 0 Position Position 1 1 1 Scram as a result ofincorrect Power Level Interlock selection of operating mode 1 1 Scram as a result of actuating Facility Evacuation 1 facility evacuation system 1 1 1 Scram as a result of actuating Reactor Isolation reactor isolation system Amendnent No. 27
-~,:----- _ , _ _ _ ,
e TECHNICALSPECIFICATION 0 UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY Number 3.3 Page 3 of 5 Date November 4,1994
SUBJECT:
Reactor Safety System (continued) Manual Scram 1 1 .1 Push Button at Control Console (1) Flow orifice or heat exchanger AP (psi)in each operating heat exchanger leg l corresponding to the flow value in the table. (2) Not required below 50 KW operation if natural convection flange and pressure 1 l l vessel cover are removed or in operation with the reactor suberitical by a margin of atleast 0.015 AK. (3) Trip pressure is that which corresponds to the pressurizer pressure indicated l , { in the table with normal primary coolant flow. (4) Flow orifice AP (psi) corresponding to the flow value in the table. (5) Core AP (psi) corresponding to the core flow value in the table. Bases
- a. The specifications on high power, primary coolant flow, primary coolant pressure, and reactor inlet temperature provide for the safety system settings outlined in I specifications 2.2.a,2.2.b, and 2.2.c. In Mode I and II operation the core j differential temperature is approximately 17 F i
l l 1 Anendnent No. 27 [ ------- -
9 TECHNICALSPECIFICATION UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY , Number 4.4 Page 1 of 3 November 4, 1994 Date l
SUBJECT:
Reactor Coolant System Annlicability This specification shall apply to the reactor coolant systems. Obiective Itis the objective of this specification to assure proper coolant for safe operation. i Snecification I
- a. The reactor coolant system shall consist of not less than a reactor pressure vessel, two primary system pumps, primary pressurirer, two primary heat ;
exchangers, two pool system pumps, one 100% capacity or two 50% capacity ! I pool system heat exchanger (s), and one pool system hold up tank plus all associated piping and valves.
- b. The reactor coolant system shall have one secondary coolant system capable of continuous discharge of heat generated at the operating power of the reactor,
- c. The pumps and heat exchangers in the primary system shall constitute two parallel systems separately instrumented to permit safe operation at five megawatts on either system or ten megawatts with both systems operating simultaneously, Amenitent No. 27
..i p .--
SECTION II. MURR PROCEDURES 1 January 1994 through 31 December 1994 A. CHANGES TO THE STANDARD OPERATING PROCEDURES 2nd edition, Effective Date: 5/2/89 L (Revisions #1 through #24 to the October 1981 printing were incorporated.) As required by the MURR Technia=1 Speci6 cations, %e Reactor Manager myiewed and approved the following: Revision No.12, dated 1/6/94 Revision No.13, dated 10/20/94 B. CHANGES TO THE MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES (Dated January 1985; Revised and reprinted May 13,1988) As required by the MURR Technical Speci6 cations, the Reactor Manager myiewed and approved the following: Revision No.15, dated 4/4/94 Revision No.16, dated 7/29/94 Revision No.17, dated 8/25/94 Revision No.18, dated 12/20/94 l l L C. CHANGES TO HEALTH PHYSICS STANDARD OPERATING PROCEDURES Hola: New manualissues 10/29/90 HP-6, Revision No.1, dated 6/2/94 HP-5, Revision No.1, deleted 6/2/94 HP-13, Revision No.1, dated 6/2/94 HP-16, Revision No.12, deleted 6/2/94 HP-17, Revision No. 4, dated 6/2/94 HP-23, Revision No. 2, deleted 6/2/94 HP-35, Revision No.1, dated 6/2/94 HP-26, Revision No.1, deleted 6/2/94 HP-28, Revision No. 2, dated 6/8/94 I HP-39, Revision No. O, dated 6/10/94 HP-28, Revision No. 3, dated 8/12/94 HP-39, Revision No.1, dated 8/12/94 HP-14, Revision No. 2, dated 11/29/94 II-1 1
s D. . CHANGES TO MURR SHIPPING PROCEDURES: SAS-0, Revision No.1, dated 27 Sep 94 SAS-4, Revision No.1, dated 14 Apr 94 SAS-4, Revision No. 2, dated 27 Sep 94 SAS-4, Revision No. 3, dated 4 Nov 94 r U II-2
- - . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _m
i e STANDARD OPERATING PROCEDURES 2nd Edition, Efrective Date: 5/2/89 (Revisions #1 through #24 to the October 1981 printing were incorporated.) Revision Number 12 Revision Date: 1/6/94 Pace Nitmber Pace Number SOP /I-10 REP-21-1 SOP /II-2 REP-21-2 SOPNI-6 SOPNI-7 SOP /A-la SOPNII-19 SOP /A-1c SOPNII-21 80P/A-11a a SOPNII-22 SOP /A-19e SOPNII-23 SOP /A-19d SOPNII-24 SOPN11-25 SOPNII-26 SOPNII-27 SOPNIII-23 > 11-3
I.4A Normal Operation (cont'd) ] i calculation will normally be used to establish the 10 MW power level, however, the nominal steady state power level shall not exceed 10 MW. The reactor shall not be operated at a power level which causes the steady state secondary calorimetric to exceed 10.5 MW unless it is confirmed that the secondary calorimetric is in error or out of Commission. The primary system DI Dow bypasses the core and yetit flows through the primary flow orifice. Therefore, the primary flow as read on the recorder should be decreased by the primary DI Dow before the value is used in calculating the powerlevel. The recorder values should be logged on the log sheets without correction. I. Steady state reactor powers of1 MW and greater will be determined by the method stated above. The power indicated by Channels 4,5, and 6 shall be maintained greater than 100% (and typically less than 105%) ] during steady state full power operation. Channels 4,5, and 6 are adjusted by proper positioning of the drawer amplifier feedback potentiometers. After adjustment of a potentiometer, the change in indicated power shall be logged in the console log and the new pot setting logged on the Startup Nuclear Data Sheet. The Shift Super;" or's approval must be obtained before adjustment of any Power Range Monitor. Adjustments shall be made after a determination of the power level by heat balance, with one exception. During or shortly after a normal reacter startup, and at the Shift Supervisor's discretion, the pot adjustments may be made when an accurate heat balance is not yet possible due to changing temperatures. In all cases, the Shift Supervisor must ensure that the pots are adjusted nulyin the conservative direction, that is, in a direction that over estimates actual power. J. Minimum nuclear instrumentation for normal operation shall be two (2) intermediate range channels with penod trip, two (2) power range channels each with high flux trips, and one (1) wide range channel with high flux trip. Rev. 1/694 App'd M SOP /I-10
e.
- ILL1 ' Procedure f:r Recctor Startup (cont'd) ]
K. Bring the reactor critical at a steady state power level of approximately 50 kW unless a lower power level is desired for tests, calibration runs, etc. The lowest steady state power level reached, and any ensuing steady state power, will be logged on the Startup Nuclear Data Sheet for a record of reactor operating time. L. Withdraw the fission chamber to full out. M. Verify that all nuclear instrumentation is responding normally. N. Take a complete set of nuclear data on the Startup Nuclear Data Sheet. Indicate on this sheet the critical control and reg blade positions and the primary and pool temperatures. O. Continue the startup, withdrawing only one blade at a time until the reactor poweris increasing at no less than a 30 second perici At power levels greater than 100 kW, maintain the control blades such that the maximum difference in position between any two blades always remains less than 1 inch. P. As the reactor power level approaches 1 MW, increase the period until a stable period remains that is no less than 100 seconds for all power increases greater than 1 MW. Q. Bring the reactor critical at a steady state power level of 5.0 MW for mode I(10 MW) operation. At this powerlevel:
- 1. Verify that the nuclear instrumentation is in essential agreement with the actual powerlevel which can be read out directly from the digital calorimetric meter. Ensure that the steady state powerlevelis maintained long enough for the digital calorimetric meter indication to stabilize (atleast five (5) minutes). Note the actual power levelin the operations console log book. In the case of the calorimetric meter being out of commission during a startup, the power level should be ]
determined by manual calculation.
- 2. Note the time of arrival and departure from this power level on the Nuclear Startup Data Sheet.
R. Continue the reactor power increase by withdrawing only one control blade at a time, maintaining the reactor period at naless than 100 seconds. Rev.1/6Si App'd M SOP /II-2
VI.3.3 W' ter m Operations (Temperatures Expected Below Freezing) Due to the potential forice to significantly damage the plastic fill, every precaution must be exercised to prevent ice build up on the wooden louvers andin the plastic fill. When the cooling tower is to be left unattended for an extended period of time and there is a possibility of significantice build-up, perform the following steps to prevent ice build-up in the plastic fill: 1 Open or verify open the basin steam supply valve.
- 2. Verify the steam solenoid valve operable.
- 3. Secure CT makeup automatic valve.
- 4. Prop open CT basin float valve to drain water between automatic valve and float valve.
- 5. Verify the CT makeup line heat tape is attached and operable.
- 6. Secure air conditioning unit and tag.
- 7. Secure P-4 and tag.
In certain instances, some of these steps may be omitted at the discretion of the shift supervisor. VI.3.4 Cold Weather Operation of P 4 Flow Distribution ] If the reactor is shutdown when the outside temperature is below ] 40*F and P-4 is in operation, the P-4 flow distribution should be ] rerouted to the south bay of C.T. cell #1, This should be ] accomplished as soon as possible after shutdown. ] This will help prevent both ice build-up within the cooling tower ] and a cold temperature shutdown of the LiBr air conditioner. The ] LiBr air conditioner initiates an automatic shutdown on chill water ] temperature of 36 F. ]
~
]
To reroute the flow:
]
- 1. Open valve S-47A
]
- 2. Shut valve S-47B After a reactor startup, to restore normal flow distributiom ]
Open valve S-47B . ] 1.
]
- 2. Shut valve S-47A Rev.1/G94 App'd W SOPNI-6
g.. a
]
VI.S.4 Cold Weather Operation cf P-4 Flow Distributi:n (cont'd) Normal flow distribution should be restored as soon as possible ] after a startup to restore flow past the conductivity probe. After ] restoring normal flow distribution, open the line drain valve (S-196) ]
]
enough to prohibit freezing (valve located in bay 1). VI.4 Shutdown of the Secondary System Upon completion of shutdown of the reactor, reactor primary and poolloop cooling systems. the secondary cooling loop can be shutdown as follows:
}
A. Shutdown secondary pump or pumps. If more than one secondary pump l l is operating, they should be secured simultaneously to minimize check valve slam. This is done from the control room instrument panel. B. Verify that system flow recorder indicates no flow and that the chiller f pump, P-4, has automatically started to provide coolant flow to the chiller unit. I 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. l 1 VI.6 Secondary Water Treatment Procedures VI.6.1 Secondary Water System Responsibility The responsibility of the secondary water treatmentis 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 and pH Control
]
]
Descriptions of these systems are in the MURR Training Manual VI.7 Secondary System Operation on Maintenance / Refueling Days Start either P-1, P-2, or F-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. SOP /VI-7 Rev.1/fa4 App'd lJM(
.j + b- ? .
#lf' # .u.'.3
~
yf' . b* < ?VII.6.31 System Startup-- . J ' The primary / pool drain collection system should be in. operation anytime evolutions involving operation of reactor or pool wateE systems are being
. performed. The following steps will prepare the s.O.em for operation: ' .,
L A. Turn on the panel control power located behind the instrument cubical. ~
]q, B. Place the valve operating system (air /N2)in-service as per Section VIL10.1. ]
. C. - Verify that the poollevel is sufBeiently below the overflow so that water ' J from the collection tank will not overflow the pool when pumped.-
VII.6.4 System Shutdown
~
After all systems have been secured and the building shutdown check is in . progress: A. Verify that the level of the pool is low enough to accept water for the collection tank. If the pool level must be lowered, do so in accordance with Section VII.5.2. _ B. Manually pump the water in the collection tank to its low level cutout as per Section VII.6.2. C. Secure the valve operating system as per Section VII.10.1. -]
- j. D. Secure the electrical power to the control power panel by opening the switch behind the instrumentpanel.
l VII.7 Primary and Pool Sample Station VII.7.1 Sampling Frequency Both the primary and poolinfluent waters are sampled on a weekly basis, and an activation analysis is conducted by the laboratory section for ' evidence of fission products and any activation products. Rev.1/6S4 App'd kJkwQ SOP /VII-19
' ' V .8.1 Liquid Waste Disposal System Descriptien (cont'd) ].
B. The WT system consists of two collection sumps, two sump pumps in ] each sump, one "T' strainer, three waste tanks, two waste tank pumps, , a filter bank and associated piping, valves and fittings. . C. Each WT has valved drains which connect via a common suction header to the waste tank pumps. This header also has connections for chemical addition, DCW, and LP air. D. The waste pumps should always discharge through the Cuno filters to any waste tank or to the sanitary sewer system. The discharge header has a pressure gauge on both sides of the filter, a sample line, and a ] l I low pressure pump cutout switch (set at 5 psig). The low discharge pressure cutout switch automatically shuts off the running pump upon low discharge pressure. E. Each tank has a sight glass forlevel readings. An air sparge line is ] installed along the entire length of WT1 and 2. Each tank has an unvalved vent to atmosphere. WT3 (and WTI, if needed) can ] receive waste directly from the hot waste sumps, depending on the valve line-up. Each tank has sludge settlement standpipes, but the ] normal sump discharge is to WT3. WT2 receives efiluent directly from the DI200 regeneration system. VII.8.2 Dry Active Waste We must make every effort to remove as much waste as possible in the form of dry active waste. We have three methods: (1) Sludge Settlement (2) CunoFilters (3) ChemicalPrecipitantTreatment A. Sludge Settlement WT1 and WT3 are fitted with gravity drains to WT2 thrcugh 18" standpipes. This can allow WT1 or WT3 to act as settling tanks, ] although only WT3 is currently used as a settling tank. When ] the sludge buildup warrants, the sludge is dumped via a 3" drain line at i the south end of WT3 (or the north end ofWTI)into barrels or dr3 ng ] troughs. This sludge is dried and removed as dry active waste. App'd hW'V\ SOPNII-21 Rev.1/6/94
1 VII.8.2 Dry Activo Waste (cont'd) , B. Cuno Filters The waste water will normally be pumped through a waste system filter bank. When the AP is high across them, they are replaced with new - filters, and the old ones are disposed of as dry active waste. See Section VII.8.11. C. Chemical Precipitant Treatment Radioactive particulates will attach themselves to carriers which can then be readily filtered out of the WT water. Without these carriers, even the most efficient filters could not remove this radioactive particulate. Afkr filtering, the filters are shipped as dry radioactive
]
waste. See SMP 33. l VII.8.3 Dumping Cnteria A. The liquid waste is collected and held until an analysis is made to determine that the specific activity of all radioactive isotopes in the waste is less than the limit specified in the Code of Federal Regulations, Title 10, Part 20 (10CFR20) for' dumping liquid waste to the sanitary sewer. In addition to the dumpinglimit on eachisotope, 10CFR20.2003 also limits the total activity which the MURR can ] dump to the sanitary sewer to 1 curie per year for carbon-14,5 curies per year for H 3 (tritium), and 1 curie per year for other radioactive material, excluding C-14 and H 3. MURR will continue to use 80% ] of the totallimit as an administrative limit,i.e.,800 millicuries per ] year for carbon 14,4 curies per year for H-3 (tritium), and 800 milli-curies per year of other radioactive material. This latter limit, and a general desire to minimize the activity dumped to our environment, dictates that the waste be retained as long as possible to permit the activity to decay off prior to discharge. If the 10CFR20 limits are not exceeded and the total activity of radionuclides does not exceed 10 mci of tritium of 2 mci of other nuclides, the Shift Supervisor may authorize the water to be pumped to the sanitary sewer. Any tank containing water with an activity greater than 10 mci of tritium or 2 mci of other nuclides will be discharged only with the approval of the Reactor Manager. SOP /VII-22 Rev.1/6S4 App'd W MY\
- , -. --. .~. . - ..
4 ;]. l % VII.8.8 DumpingCriteria(cont'd). o
~
' B.' When the liquid waste exceeds the limits of 10CFR20 for dumpmg, one
- of two methods will usually be utilized to dispose of the waste. The most . i desirable option is to retain the water until the activity has decayed off'
~
to permit dumping. The second option is to chemically treat'the waste with a carrier solution that causes the radionuclides to precipitate { which facilitates them being filtered out (see SMP-33). Precipitates ];
'will then be removed either by pumping from one tank to another or .
recirculating the tank through the WT filters. As the filtenng process ' s 1 j proceeds,it may be necessary to change the filters to a smaller mesh [ '
~s ize and continue the filtration until the desired activity reductionis achieved.
C. It shall be standard procedure to hold allliquid waste as long as practical to minimize the total activity released. A sample of the tank is taken . and delivered to Reactor Chemistry Group. Results of the analysis am ; recorded on the Waste Tank Sample Form and the form is sent to the l Shift Supervisor. The Shift Supervisor reviews the sample results and makes the decision of what to do with the tank. - If the Shift Supervisor g decides to' dump the tank, he sends the form to Health Physics for their j concurrence. If Health Physics concurs that the tank can be dumped, 'l the tank is pumped to the sanitary sewer as per Section VII.8.7. After 'l the operator has completed pumping the tank, he enters the final . volume pumped on the sample form and sends the form to Health .i Physics Department. ! l D. If the analysis ofWT2 exceeds the 10CFRlimits, orif the Shift Supervisor wishes to hold the tank for further decay, WT2 can be :
; pumped to WT1 via the filters, utilizing a vigorous air sparge. Then 1 WT1 shall be sampled at alater date and re-evaluated to determine j where it should be dumped.
VII.8.4 Draining WT1 and WT2 (not currently done; procedure moved to ] j SMP 33) ..
]
Rev.1/6S4 App'd M SOPNII-23 1 l
- . ._ a
,W r #
v
+ c VIIl8.5 ; Transferring WT3 to WT2 (by Draining or Pumping if Necessary) f- _
NOTE:! '11:e new 10CFR30 pmbibits visible settled solids in any ]' l sasaple, therefore, all wasta tanks will be filtered thmugh ] .!
]f '
~
- (5 micron) filters prior to sampling as reflected in this procedure.
]l l . z When WT8 is nearly full, transfer it to WT2 via the standpipe. ]' l A. Check valves WD1 and WD2 and valves W1A,1B,2A,2B,3Bl 5, '] i and 9 shut. ]. l 7
B. Open valves 3A,9,16,18, and 24.- ] l C. Start pump #1,if necessary. ]. D. Upon completion, close valves SA,9,16,18, and 24. ] ] E. Record the evolution in the Reactor Log. ] l VII.8.6 Recirculating and Sampling of Waste Tanks l NOTE 1: Notify Reactor Chemistry group before obtaining a sample. l NOTE 2: Always pump through the filters by opening valves W16 and W18, ensuring W5 is closed. Before recirculating any tank, check the followingvalves closed: W1A, IB,2A,2B,3A,3B,5,7,8,9, i 22, 23, 24, 25, 26, 27,38, WDI, WD2, WD3, WD4, .WD5. IfWP2 is used instead of WP1, open W7 and W8 instead of W9. i ^ A.~ SamplingWT2 a
- 1. Open W2A,2B,9,16,18, 24.
- 2. Start waste pump (WP1) and verify flow. ] l
- 3. Commence a vigorous air sparge through W20. j 7
- 4. Recirculate for 30 minutes prior to sampling. -
] ]
i Draw off a sample through W22 and discard to liquid waste drain. ;
- 5. i
- 6. Draw ofra second sample through W22 for analysis.
~
NOTE: If sample shows indication of suspended solids or ] l settled solids, additional recirculation and sampling ] I is required. ] Rev.1/6S4 App'd M SOPNII-24 f 1 f r
e-b '9 VB.8.6 A. Sampling WT2 (cont'd) ] l r
- 7. Shut W22 and secure the waste pump.
- 8. Close W2A, 2B, 20,9,16,18,24.
- 9. Deliver the sample and completed sample form to the Reactor Chemistry Group for analysis.
- 10. Record taking of sample in the Reactor Log.
B. Sampling WT1 (not currently done; procedure moved to SMP 33)] VII.8.7 Pumping to Sanitary Sewer NOTE: Can be done only with Shift Supervisor's or Reactor Manager's authorization. Check the following valves closed: W1A, IB,2A,2B, 3A, 3B, 5, 22, 23, 24, 25, 26, 27, 38. Ifpumping with WP2, open W7 and 8 instead of W9. i A. Pumping WT1 to Sewer (not currently done; procedure moved to ] SMP-33) B. Pumping WT2 to Sewer
- 1. Open W2B,9,16,18, WDI, WD2.
- 2. Conunence a vigorous air sparge through W20.
- 3. Start the waste pump (WP1) and verify flow. ]
- 4. Check waste tank periodically until tank is empty. When empty, secure waste pump, t
- 5. Shut W2B,20,9,16,18, WDI, WD2. ,
- 6. Record the volume pumped on the Waste Tank Sample Form and returnit to Health Physics Office.
Record the pumping evolution in the Reactor Log.
- 7. :
VII.8.8 Pumping Waste System to Secondary System (moved to SMP-15) Rev.1/G94 App'd )h SOP /VII-25
n; ,
. 1 J
- (VII.8.9 - Pumping Waste from One Wasta Tank to Another , a a ~
.,, o
' A; PumpingWT2 to WT3 1.' .. Check closed valves W1A, IB,2A,2B,'3A,3B,' 5,23,24,25,26,38. :
1
'2. Check WT3 to ensure that it has enough room to accept the ]
4 volume of WT2. i
- 3. Open W2A to pump via the standpipe or W2B to pump the entire "
contents of the waste tank. Open W9,16,18,27. f Start the waste pump (WP1) and verify flow. ] I; 4.
- 5. Commence a vigorous air sparge through W20. (Except if via f standpipe).
t t
- 6. When the waste tank is empty, shut W2C, 9,16,18, 27.
- 7. Record the pumping evolution in the Reactor Log. ] j B. Pumping Waste Tank 2 to Waste Tank 1 (not currently done; ]. i procedure moved to SMP 33) ] l j
VII.8.10 Dumping Sludge from a Waste Tank Sludge will be dumped from WT1 through valve W44 (WT2 through sludge j plug, and WT3 through WSD)into barrels or troughs by a procedure ] ~! i approved by the Shift Supervisor. This sludge will be dried and disposed of as Dry Active Waste. ; VII.8.11 Changing Waste Tank Filters A. Obtain Shift Supervisor's permission. j B. Wear gloves, lab coat, and shoe covers. .]- C. Ensure all normally closed WT valves are closed. ] D. Place the filter drainline hoses in the floor drain. Open drain valve 51 ] and open the vent valve on housing. E. When water quits running, remove' filter canister and place old filters ] in bucket. ( l F. Replace filters and hardware, reassemble canister, and close valve' 51.] l I SOP /VII-26 ! Rev.1/6S4 App'd i
. 1
].
' iVIL8.11" Changing Waste Tank Filters (cont'd)
G. Open DCW valve 38 and valves 9 and 16 to fill and vent filter
]
canister. Close vent valve.
]: l 3
- H. Secure valves 9,16, and 38.
Wash down area, dispose of collected filters in the drying rack. ] I. J. Check self on portal monitor. ] K. Notify Health Physics to survey area. ] VII.8.12 Chemical Precipitate Treatment (moved to SMP-33) ] VII.9 Nitrogen System VII.9.1 Purpose i l The primary function of the Nitrogen System (N2)is to provide pressurized N 2to the pressurizer to maintain primary pressure. I VII.9.2.1 Ng System Startup Before the reactor is made operational, light off the N2 system by the following procedure: i A. Verify that the regulator is set at 140 psig and the average gauge pressure of the two N2 banks is at least 500 psig before placing the lt s rstemin operation. B. C'ose the switch which energizes the electrical controls for the system. O. Open the N2 cut out valve N15 in room 114, and verify a N2 pressure of 90 to 95 psig to the pressurizer. 1 The N2 system is now ready for operation. t l
-[
i l 1 i Rev. V6/94 App'd M SOP /VII-27 , t i t
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*e Post r OvenFLow 6P- Si l EXP. CAM SUR(s0 TA8Js VC#T Q To P PE TREMCH BP- BB EXP.CAN . SURGE TAust 150L AT10m H M N R 7 Moti . e P s*J Cr A5 oF 11l 7 3 93 a m
" ' DRAW E x p. C AN A b o ct. -
REP- 21 HIGH STACK MONITOR INDICATIONS IMMEDIATE ACTIONS: 2 l
- 1. Notify the Shift Supenisor.
1
- 2. Notify the Manager of Health Physics. After working hours contact:
HEALTH PHYSICS CALL LIST. , SUBSEQUENT ACTIONS: i Evaluate the extent of iodine, particulate, and gas with overlays. If the extent ] ; of radioactivity is great enough to enter event classifications, the highest category of eventindicated by gas, iodine or particulate reading will be used to classify the event. j 6 The overlay thresholds assume the present release rates will be constant for a 24 l hour period. They are conservative, since the present release rate may exist for less than 24 hours. The emergency action levels are: ] , UNUSUAL EVENTS - 20,000 AEC* averaged over 24 hours ] ALERT EVENTS - 100,000 AEC averaged over 24 hours ] SITE AREA EMERGENCY - 600,000 AEC averaged over 24 hours ] , I t These overlays are to graphically assist the operator's judgement as to the extent of release.
*AEC-Air Effluent Concentration,10CFR20, Appendix B, Table 2, Column 1. ]
Rev.1/694 App'd h% REP-21-1 ,
.i i- . l l
i HIGH STACK MONITOR INDICATIONS (Cont'd) , A. IODINE and PARTICULATE: .)- l Check the stack monitor reading using appropriate overlay. The ranges ] of values represented on the overlay are the threshold levels of concen- . trations corresponding to speciSc emergency events in excess of Technical Specification limits. f i NOTE: For particulate release, if the nuclide cannot be identi5ed - ] } the AEC is 1E 12 pCi/ml. This makes timely identification of ] ; the particulate (s) ofinterest extremely important (e.g., if ] [ particulate were identified as Rubidium-88 the AEC is ] ! 9E 8 Ci/ml, a concentration 90,000 times greater than for ] [ an unkaawn particulate). ] : t B. GAS (use gas overlay) ;.] f
- 1. E gas concentration exceeds 8.8 x 103 CPM (20,000 AEC*) but less ]
than 4.2 x 104 CPM (100,000 AEC), and remains between these levels ] ! i for 1 hour with no evidence of darlining, the event shall be classified as an UNUSUAL EVENT. l
- 2. E gas concentration exceeds 4.2 x 104 (100,000 AEC) but less than ]
2.1 x 105 CPM (500,000 AEC) and remains between these levels for ] 1 hour with no evidence of declining, the event shall be classified as an ALERT.
- 3. E gas concentration exceeds 2.1 x 10s CPM (500,000 AEC) and ]
remains above this level for 1 hour with no evidence of declining, the ] event shall be classified as a SITE AREA EMERGENCY. ,
'AEC Air Effluent Concentration,10CFR20, Appendix B, Table 2, Column 1. ] ;
Rev.1/f44 App'd M REP-21-2
I i Js ! Date: ; . REAC7OR STAR'IUP CHECKSHEET ' Time (Started): FULLPOWER OPERATION BUILDING AND MECHANICAL EQUIPMENT CHECKLIST l l 1. Emergency air compressor (load test for 30 minutes after maintenance day).
- 2. Beamport Floor:
- a. Beamport radiation shielding (as required).
- b. Beamport status checked / updated.
- c. Seal trench low level alarm tested (after maintenance day).
- d. Check closed beamport floor access gates.-
- 3. a. Check operation of fan failure buzzer and warning light. Notify Alpha Lab of momentary ,
ventilation loss. (Reg'd if shutdown longer than 4 hours.) ,
- b. Test stack monitor and low flow alarm per SOP while in west tower.
- c. Test UPS alann canel.
- 4. Emergency generat ailability checked as per Sect. I.A. and III. of D.G. checklist.
(If shutdown for gn ar than 24 hours, run emergency generator for 30 minutes.) l l 5. Emergency pool fit Check valves PIV 1 and PIV 2 locked open.)
- 6. Visual check of CT and secondary equipment:
- a. Oil level in CT fans r.ormal (after maintenance day).
- b. Secondary makeup isolation valve power switch closed, valve cycled to verify operation and placed in auto mode.
- 7. Visual check of room 114 equipment:
- a. Valve Op Air compressor oil level normal and cutout switch in auto.
- b. Main air back up valve VOP 33 open.
- c. Air valve for valve operating header (VOP 31) open. '
- d. P501A and P501B coolant water valves open.
- e. Check valves 599A and 599B open.
- f. Pump controllers unlocked to start (as required).
- g. S1 hydraulic pump on (oil level normal). ]
- h. Valve Si cycled in manual mode and positioned as required. ] l
- i. Vent the pool hold-up tank.
Vent the pool skimmer system pump. l J. i
- k. Check the pipe trench free of water. Check the four pipe annulus drain valves for water leakage after maintenance days. ;
Add DI water to beamport and pool overflow loop seals. i 1.
- m. Check oil reservoir for pumps 501A,501B, and 533 for adequate supply. Add if necessary. l
- n. Visually check room 114 and DI area after all systems are in operation.
- 8. Reactor Pool: .
- a. Reflector experimentalloadings verified and secured for start-up.
l
- b. Flux trap experimentalloading verified and secured for start-up, or strainerin place.
- c. Check power on and reset, as necessary, silicon integrator, totalizer setting, silicon rotator, and alarm system. ]
I i I SOP /A la Rev.1/6/94 App'd: M
e e e i s -g. REACTOR STARTUP CHECKSHEET FULL POWER OPERATION (cont'd) -
; Page 3 -
;j
.I 1' . d. ARMS trip setpoints checked and tripped, check buzzer operational locally for all channels and remotely for chann'lse 6 and 7.
Channel 4 ExhaustPlenum- ; Channel 6 -Bridge ALARA l Channel 7 -ReactorBridge : Channel 11- Exhaust Plenum #2 (B/U) .
?- e. Reactor isolation horns switch in ** Isolation Horns On" position. Valves and doors open.
- f. All ARMS trips set per SOP.
i
- g. Check ventilation fans, containment and backup doors. -
- h. Announce completion of test to facility evacuation isolation system. ]
g (Reset secur.'*v cabinet alarm at keypad and notify police.) ]
- 20. Operate reg blade from full-out to full in and set at 10" + .05".
- a. Check rod run-in function at 10% withdrawn and annunciator at rod bottomed.
- 21. Raise blade A to 2" and manually scram.
- 22. Raise blade B to 2" and trip manual rod run in. !
- 23. Raise blade C to 2" and scram by WRM trip.
- 24. Raise blade D to 2" and scram by IRM trip. -!
- 25. Annunciator board energized; horn on.
- 26. Jumper and tag log cleared or updated.
- 27. IRM recorder in fast speed. j
- 28. Check magnet current for 90 ma on each magnet.
- 29. Cycle WRM range switch.
- 30. Reset " white rat" scram monitor. ,
- 31. Estimated critical blade position (corrected); inches.
- 32. Pre startup process data taken.
- 33. Routine patrol completed.
- 34. All reactor and license related systems upon which maintenance was performed have been reviewed and are operable.
~l l 35. Reactor ready for startup.
Time (Completed): Shift Supervisor / Lead Senior Operator ( 1 Y l SOP /A le Rev.1/6/94 App'd
d
.. j t-Nr.
J Z ARICINAL'IO Mr Af 'Mt PHYRica OFFICE
,A.:
WARTE TANK EAMPLE REPORT TANK LEVEL (Liters) ., ETANKNO. i DATE j ' TIME SAMPLER - i
- 1. Analvain Results Physical Form Concentration WZC* Activity ]
Nuclide Halflife
- c. H.3 12.3Y l l.
b. I 1 FRACTION OF WEC ] pH (Note: pH must ue between 5.5 - 9.5 for release) TIME DATE Analysis by Total Volume Gitars) Activity (mci) ] Concentration ( M.Calml} (a) (b) ,, _
- 2. Annrovals Reauired fan Any Dis charge . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Shift Supervisor Discharge of > 10 mei of H-3, > 2 mei of other activity, or to Secondary System Reactor Manager
. Discharge Limit Approved . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Health Physics
- 3. Action Taken Time Discharged Volume Discharged (Liters)
Date Discharged _ O Sanitary Sewer 0 Secondary System 0Not Discharmed Tank Discharged to (check one): REMARKS
] I
*Wcter Emuent Concentration,10CFR20, Appendix B, Table 2, Column 2.
SOP /A 11a Rev.1/6S4 App'd uBlvi
1 5 MURR OPERA'!OR ACTIVE STATUS IDG (cont'd) OPERATORNAME: . i YEAR:
. NOTE: 'Ihis form is for documenting active status oflicense doperators ass igned to rotating shifts.
QUARTER 1 Shift SupervisorInitial -
] Active status needs to be documented to meet minimum requirements (4 hours)
] Active status lapsed, documentation required
- for return to active status (6 hours)
Shift Supervisor Initial (for SROs) Total Time Activity SRO Initial (for ROs) Date QUARTER 2 Active status needs to be documented Shift Supervisor Initial to meet minimum requirements (4 hours)
] Active status lapsed, documentation required for return to active status (6 hours)
Shift SupervisorInitial(for SROs) Date Total Time Activity - SRO I_nitial(for ROs) M SOP /A-19c New 14/94 App'd l
. .. . . . - .. .. . ..~ -. . - -
t i
.b ^ ,
yA. l MURE OPERA'!OR ACTIVE STAWS LOG (cont'd) .- i F OPERA'IOR NAME: i
' ~ YEAR: -l i
J NOTE: Ihis form is for documendng active status oflicensed operators assigned to rotating shifts. j QUARTER 3 ' I Active status needs to be documented Shift Supervisor Initial to meet minimum requirements (4 hours)- - l
] Active status lapsed, documentation required {
for return to active status (6 hours) . l
'E Shift Supervisor Initial (for SROs) i Date Total Time Activity SRO Initial (for Ros) .i
- i r
t i i QUARTER 4 > Active status needs to be documented Shift Supervisor Initial [ to meet minimum requirements (4 hours) l I Active status lapsed, documentation required i l for return to active status (6 hours) l Shift SupervisorInitial(for SROs) ! Date Total Time Activity SROlnitial(for ROs) l l l t
~ - '
- l i
i
-I
'I I
i New U6/94 App'd A SOP /A-19d
tc. .
-t
- i STANDARD OPERATING PROCEDURES f 2nd Edition, Effective Date: 5/2/89 i (Revisions #1 through #24 to the October 1981 l
, printing wereincorporated.) _
Revision Number 13 t Revision Date: 10/20/94 ; f Pare Number Pace Number SOPNIII-21 SOP /A-8a . SOPNIII-22 SOP /A-8b t SOPNIII-23 SOP /A-11a : SOPNIII-24 l SOPNIII-25 SOPNIII-26 , SOPNIII-27 : SOPNIII-34 SOPNIII-35 i r i h
?
k l i i II-4 )l
y n .
.. _ _ . . - .. - ~. . - - ~ ~
t 4 -
,. ( 'f . $ i c ~
j 3 VIII.'4.2 Beamport "A" Pmeedums'. . j
' i CAUTION: 'Ihe mactor shall be shutdown before any drain or fill
- operationis performed.
*' HQIK: All valve manipulations shall be made by Reactor Operations .i personnel. A health physicist shall be pasent for any t-Q or ,-l flDingevolution. .
A. Flooding / Filling Beamport "A" with DI Water :
. 1. Check the beamport DI supply valve open (above the sample . q station at room 114 entrance). j
- 2. Check closed BP-1, BP-11, BP-B13, BP-CIS, BP-A16, BP-5, .]
BP-3, BP-4, and BP-2. j
- 3. Open BP-A17'(beamport "A" vent).
- 4. Slowly open BP-8 to bleed helium pressure off. .
- 5. Close BP-8 and BP-A17. .;
- 6. Open BP-A14 and BP-A15 (surge tank isolations).
- 7. Open BP-A13 Gocated in trench).
~ 8. Slowly open BP-2.(should feel and hear water flow). i
- 9. - When surge tank is halffull shut BP-2. .;
- 10. Shut BP-A13.
j
- 11. Log in console log beamport "A" flooded, and update Fuel Inventory Sheet. !
B. Flooding / Filling Beamport "A" with Super Water l
- 1. Check closed BP-1, BP 2, BP-11, BP-B13, BP-CIS, BP-A16, 1 BP-5, BP-3, and BP-4. !
- 2. Open BP-A17 (beamport "A" vent). l
- 3. Slowly open BP-8 to bleed helium pressure off. ';
- 4. Close BP-8 and BP-A17. -l
- 5. Open BP-A14 and BP-A15 (surge tank isolations).
l
- 6. Open BP-A13 Gocated in trench).
- 7. Open BP-1 and start adding super water to funnel located on mezzanine (takes = 10 gallons of water). l
- 8. When surge tank is half full, shut BP-1.
- 9. Shut BP-A13. . }
- 10. Log in console log beamport "A" flooded with super water, and - !
update Fuel Inventory Sheet. l New 10/20/94 App'd W SOPNIII-21 ! I
- . _ _ ._ .__ _ _ _ _ _ _ _ _ . . _ . ._, . . _ _ _ - _ . ., a
e . j is. ' l n ! C. Adding DIWater to Beamport "A" CAUTION: Use this procedure only when water level is visible in the surge tank or plastic hose connecting to the surge tank. NOTE: Inform shift supervisor that the surge tank is low and request I permis:: ion to refill the surge tank.
- 1. Check closed BP-5, BP-1, BP-3, BP-4, BP-11, BP-B13, BP-CI3, ;
and BP-2.
- 2. Open BP-A13 Gocated in seal trench). ,
- 3. ' Slowly open BP-2.
- 4. When surge tank is half full, shut BP-2 and BP-A13.
D. Draining Beamport"A" : CAUTION: All drained wateris highly tritiated and should, whenever possible, be collected in containers rather than be allowed , i to drain to pipe trench. The only time BP-5 should be open is to drain the leg between BP-3, BP-4, and BP-5. ,
- 1. Connect helium bottle with regulator to the line on biological ,
shield manifold. s
- 2. Set regulator to 5 psig. ,
l
- 3. Place tygon hose from BP-4 into 5 gallon poly jug.
NOTE: Have H.P. present before beginning to drain. l
- 4. Check closed BP-AIS, BP-B13, BP-CIS, BP-5, BP-1, BP-2, BP-7, BP-10, BP-11, BP-9, BP-8, BP-12, BP-A16, and BP-A17.
- 5. Check open BP-A14 and BP-A15. j
- 6. Open BP-A13 and BP-4.
j
- 7. When surge tank is empty, shut BP-A14 and BP-A15 (surge tank -
i
, isolations).
- 8. Open BP-A16 (beamport "A" helium fill). i
- 9. Slowly open BP-7 to get steady drain rate into the poly jug l through BP-4.
- 10. When completely drained, flow helium through beamport for 30 l t
minutes to dry out beamport.
- 11. Shut BP-A13 and BP-4.
12.' Shut BP-A16 and BP-7.
- 13. Disconnect helium bottle from manifold and log in console log that !
beamport "A" has been backfilled with helium, and update Fuel Inventory Sheet. Dispose of the tritiated water as directed by 4 Health Physics. ( App'd Wem SOPNIII-22 l New 1&20/94 1
,~+ , , s Beamport"B" Procedures VIII.4.3 ! i
~
CAUTIONi The reactor shall be shutdown before any drain or fill operationis performed. : HQ3E: All valve manipulations shall be made by Reactor Operations . l l personnel. ' A health physicist shall be present for any draining' or - :
- fillingevolution. q
. A. Flooding / Filling Beamport "B" with DI Water l i 1. Check the beamport DI supply valve open (above the sample*
station at room 114 entrance).
- 2. Check closed BP-1, BP-11, BP-A13, BP-C13, BP-B16, BP-5, BP-3, BP-4, and BP-2.
i
- 3. Open BP-B17 (beamport "B"_ kent).'
1
- 4. Slowly open BP-8 to bleed helium pressure off.
- 5. Close BP-8 and BP-B17. _
- 6. - Open BP-B14_ and BP-B15 (surge tank isolations).
- 7. Open BP-B13 Gocated in trench).
-[
- 8. Slowly open BP-2 (should feel and hear water flow).
- 9. When surge tank is half full shut BP-2. j
- 10. Shut BP-B13.
i
- 11. Log in console log beamport "B" flooded, and update Fuel Inventory Sheet. j i
B. Flooding /Fdling Beamport "B" with Super Water .
- 1. Check closed BP-1, BP-2, BP-11, BP-A13, BP-013. BP-B16, l BP-5, BP-3, and BP-4.
- 2. Open BP-B17 (beamport "B" vent).
j
- 3. Slowly open BP-8 to bleed helium pressure off.
-4. Close BP-8 and BP-B17. .
- 5. Open BP-B14 and BP-B15 (surge tank isolations).
- 6. Open BP-B13 Gocated in trench).
- 7. Open BP-1 and start adding super water to funnellocated on' '
mezzanine (takes = 10 gallons of water).
- 8. When surge tank is half full, shut BP-1.
- 9. Shut BP-B13. .
i l
- 10. Log in console log beamport "B" flooded with super water, ard update FuelInventory Sheet. 1 I
SOPNIII-23 $ Rev.10/20/94 App'd _ N ] l Section VIII.4.3 renumbered and revised in its entirety.
)
l t--_ _ _ . _ _ _ _ _ _ _ ___________ . _ _ _ _ _ _ . - _ _ -~_-
g.
-c C. Adding DIWater to Beamport"B" CAUTION: Use this procedure only when water level is visible in the surge tank or plastic hose connecting to the surge tank.
M: Inform shift supervisor that the surge tank is low and request permission to refill the surge tank.
- 1. Check closed BP-5, BP-1, BP-3, BP-4, BP-11, BP-A13, BP-C13, and BP-2.
- 2. Open BP-B13 Gocated in seal trench).
- 3. Slowly open BP-2.
- 4. When surge tank is half full, shut BP-2 and BP-B13.
D. Draining Beamport "B" CAUTION: All drained wateris highly tritiated and should, whenever possible, be collected in containers rather than be allowed to drain to pipe trench. The only time BP-5 should be open is to drain the leg between BP-3, BP-4, and BP-5.
- 1. Connect helium bottle with regulator to the line on biological shield manifold.
- 2. Set regulator to 5 psig.
- 3. Place tygon hose from BP-4 into 5 gallon polyjug.
NOTE: Have H.P. present before beginning to drain. l 4. Check closed BP-A13, BP-B13, BP-C13, BP-5, BP-1, BP-2, BP-7, BP-10, BP-11, BP-9, BP-8, BP-12, BP-B16, and BP-B17.
- 5. Check open BP-B14 and BP-B15.
6., Open BP-BIS and BP-4.
- 7. When surge tank is empty, shut BP-B14 and BP-B15 (surge tank l
l isolations).
- 8. Open BP-B16 (beamport "B" helium fill).
l
- 1. -> 9. Slowly open BP-7 to get steady drain rate into the poly jug through BP-4.-
- 10. When completely drained, flow helium through beamport for 30 minutes to dry out beamport.
- 11. Shut BP-B13 and BP-4.
- 12. Shut BP-B16 and BP-7.
- 13. Disconnect helium bottle from manifold and log in console log that beamport "B" has been backfilled with helium, and update Fuel Inventory Sheet. Dispose of the tritiated water as directed by Health Physics.
Rev.10/20/94 App'd h SOPNIII-24 Section VIH.4.3 anumbered and revised in its entirety. ]
5 VIII.4.4 Beamport"C" Procedures j CAUTION: The reactor shall be shutdown before any drain or fill ' ', operationis performed.' l l l HQ21: All valve manipulations shall be made by Reactor Operations ~ :l personnel. A health physicist shall be present for any J..hd. g or filling evolution. l l A. Fla-Ung/FillingBeamport"C"withDIWater _ ,
- 1. Check the beamport. DI supply valve open (above the sample -l station at room 114 entrance).-
- 2. Check closed BP-1, BP-11, BP-AIS, BP-B13, BP-C16, BP-5, i BP-3, BP-4, and BP-2. y
- 3. Open BP-C17 (beamport "C" vent).
- 4. Slowly open BP-8 to bleed helium pressure off. ]
- 5. Close BP-8 and BP-C17.
- 6. Open BP-C14 and BP-CIS (surge tank isolations). l
- 7. Open BP-CIS Gocatedin trench).
- 8. Slowly open BP-2 (should feel and hear water flow). l
- 9. When surge tank is half full, shut BP-2.
- 10. Shut BP-CIS.
j
- 11. Log in console log beamport "C" flooded.
B. Fla-Hng/Fdling the Beamport with Super Water .
- 1. Check closed BP-1, BP-2, BP-11, BP-A13, BP-B13, BP-C16, BP-5, BP-3, and BP-4.
- 2. Open BP-C17 (beamport "C" vent). -
- 3. Slowly open BP-8 to bleed helium pressure off. j
- 4. Close BP-8 and BP-C17.
- 5. Open BP-C14 and BP-C15 (surge tank isolations). l
- 6. Open BP-C13 Gocatedin trench).
i
- 7. Open BP-1 and start adding super water to funnellocated on mezzanine (takes - 10 gallons of water) . ;
t
- 8. When surge tank is nalf full, shut BP-1.
- 9. Shut BP-C13.
- 10. Log in console log beamport "C" flooded with super water, and {
update FuelInventory Sheet.
-)
4 Rev.10/20S4 App'd # SOPNIII-25 l Section VIII.4.4 renumbered and revised in its entirety. ] l
"' ~ r , - - - , - - - , , , . . _ _ .
S J lh, C. Adding DIWater to Beamport "C" CAUTION: Use this procedure only when waterlevel is visible in the surge tank or plastic hose connecting to the surge tank. HQ'E: Inform shift supervisor that the surge tank is low and request permission to refill the surge tank.
- 1. Check closed BP-5, BP-1, BP-3, BP-4, BP-11, BP-A13, BP-B13, and BP-2.
- 2. Open BP-C13 Gocatedin seal trench).
- 3. Slowly open BP-2. ,
- 4. When surge tank is half full, shut BP-2 and BP-C13.
D. Draining Beamport"C" CAUTION: All drained water is highly tritiated and should, whenever possible, be collected in containers rather than be allowed to drain to pipe trench. The only time BP-5 should be open is to drain the leg between BP-3, BP-4, and BP-5.
- 1. Connect helium bottle with regulator to the line on biological shield manifold.
- 2. Set regulator to 5 psig.
- 3. Place tygon hose from BP-4 into 5 gallon polyjug.
NOTE: Have H.P. present before beginning to drain.
- 4. Check closed BP-AIS, BP-B13, BP-CI3, BP-5, BP-1, BP-2, BP-7, BP-10, BP-11, BP-9, BP-8, BP-12, BP-C16, and BP-C17.
- 5. Check open BP-C14 and BP-C15.
- 6. Open BP-C13 and BP-4.
- 7. When surge tank is empty, shut BP-C14 and BP-C15 (surge tank l
,- isolations).
i
- 8. Open BP-C16 (beamport "C" helium fill).
- 9. Slowly open BP-7 to get steady drain rate into the poly jug _
i through BP-4. ;
- 10. When completely drained, flow helium through beamport for 30 -
minutes to dry out beamport.
- 11. Shut BP-CI3 and BP-4.
- 12. Shut BP-C16 and BP-7.
- 13. Disconnect helium bottle from manifold and log in console log that l i
beamport"C" has been backfilled with helium. Dispose of the ' tritiated water as directed by Health Physics. App'd _ h SOPNIII-26 Rev.10/20/94 Section VIH.4.4 renumbered and mvised in its entirety. ]
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1 l i 9, ; o -E. _ . _%. _*a. _ . _ . _ . _ . _ . _ . _ . _ , _ .. . ; I l l._._.... .8a "s O d i i App'd h SOP /VIII-27 l New 10/20/94
__' - O
~-.
'ti 4
VIII.4.7 L Operating Procedures' for Beamport "F" ' -] The following procedures shall be used for operation of Beamport "F". All - valve and tube chan=as shall be.made byReactor Operations personnel. i Major shielding movements and all center tube a4ustments or changes l shall be coordinated with Health Physics and Reactor Operations ! personnel. A copy of this procedure shall be posted near Beamport "F" - -l and a copy shall be put in the Beamport "F" log book. l ~ CAUTIONS:
- Ensure center tube is not left fully inserted; allow at least 1/4 inch for ] - ;
thermal expansion.
- After the' center tube is inserted, verify drain and vent valves are' shut.' -l
- To prevent a partially filled beam tube leaving a crack for radiation, be sure the vent tank has waterin it. l 1
- To limit handling of a very radioactive filter tube, pull the tube back four feet and let it decay for > 2 days before withdrawing it. Have i
~
Health Physics coverage.
- To limit tritium release, limit leakage of water. l j
- To prevent excessive personnel exposure, make sure filter parts are in tube and pushed forward to reactor end of filter tube. Apply vacuum i slowly so that filter parts are not sucked back. Have Health Physics f coverage on startup. ,
- After startep, check radiation survey readings against previous readings with similar filters. ]
- Make it a habit to stay out of beams, whether they are open or " closed." :
HCZII: The experimental can may be flooded or drained only when the .j reactoris shutdown ~ The water levelin the surge tank shall be checked and maintained by i Operations. Makeup water should be " super" water. q j The principal experimenter should send a not to Operations asking for a]
-I change in filters and tubes. The note should reach Operations before the.
shutdown. The principal experimenter is responsible for verifying the ] desired filtering material is in a center tube before it is inserted and that it ] is covered in his RUR. To facilitate in verifying materials, all filter parts ! should be marked and their storage should be controlled because of their - l l
. activation and potential contamination. j l
App'd W SOPNIII-34 Rev. ~ 10/20S4
,Es . ,
1 g, t. y
'
- _ A. Installing Center Tubes in Beamport "F" _
'1. Center tubes shall be installed into Beamport "F" only with the : .l !
reactor shutdown.
- 2. Verify the Beamport "F" center tube sealing "O"-ring is in place . ;
andin good condition. . : i 3. . With Health Physics coverage, transfer the desired center tube - from storage to Beamport "F" and insert it until contact is made -l with the ball valve. Note the change in the Beamport Storage ! Log-j
- 4. Lightly tighten the center tube "O"-ring packing nut; check the drain valve and vent valve closed and open the surge tank line i valve. ;;
1
- 5. Open the center tube ball valve and insert the center tube. The -
center tube packing nut may need to be a4usted so the tube can ] be inserted with minimal water leakage. {
- 6. With the center tube fully inserted, pull the tube out the distance desired by the experimenter. It must be pulled out atleast j
1/4 inch to allow for thermal expansion. .] i
-l
- 7. The center tube end plate shall be amoved and a md inserted in j the tube to verify the filter slugs are at the end of the tube closest :
> to the reactor core. '
- 8. The vacuum pump shall be hooked up and started before the reactor is taken critical. The vacuum should be applied slowly so that suction will not pull back the filter parts. ;
R 9. A beamport radiation survey shall be completed after the reactor - is started up at 10 MW. B. A4ustments to Beamport "F" Center Tube -- The center tube shall only be a4usted with the reactor suberitical. l A4ustments including changing the distance the center tube is fmm the core and pulling or adding parts from the center tube. l I
- 1. Take the reactor suberitical before a$usting the center tube.
- 2. If the center tube is moved, ensure it is not closer than 1/4 inch ]
j L l from being fullyinserted.
- 3. After adjustments are made and vacuum restored, return reactor ' -
to normal operations, and perform a Beamport "F" radiation ; survey. t ! !. SOPNIII-35 I l Rev.10/20/94 App'd W ( i 1 !
)
g .a A--e&,a J e , J,& .+h- am a4 .-a..i., e m- 4- - s. DATE- ! t 1 REACTOR ROUTINE PATROL 1
\
1; Time of start of patrol 1
- 2. Time and date all charts
- 3. Visual check of entire E+:'
- 4. Anti siphon tank pressure 36 psic 3 psi
- 5. North iso door seal pressure 18-28 psio ;
- 6. South it.o door seal pressure 18-28 psia -
open ,
' 7. 5th level backup doors ;
8.16" iso viv A air pressure 45-55 psia i 9.16" iso viv B air pressure > 80 psio l
- 10. Emerg air compress on standby Skr closed, viv open, i cage 2 80 psia I
- 11. Containment hot sump pumps Operable ;
- 12. Door 101 seal pressure 18 28 psia ,
- 13. BP floor Conditions normal
- 14. Fuel vault Locked i
- 15. Inner airlock door seal pressure 18 28 psia .
- 16. Outer airlock door seal pressure 18 28 psia j
- 17. Cold deck temperature 45-65'F !
- 18. Argon bank pressure > 200 psio
- 19. Full N2 bottles Total > 3 I A or B ]
- 20. Bank on service l
> 250 pslo ]
- 21. Bank A bottle pressure
>250 psig ] l 22.' BanR B bottle pressure !
135145 psi ]
- 23. N2 header pressure !
> 2100 cal ] -l
- 24. T-300 level
< 6000 cal ]
- 25. T-301 level l
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 significantly, return to the middle of the band (36 psig) and record the pressure here, if a condition or reading is normal, enter a "V" (for conditio 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.10/20/94 App'd W SOP /A 8a
. - . - w!
DATE: , REACTOR ROUTINE PATROL j
- 26. Labyrinth sump Level < Alarm Pt.
j Condition normal j
- 27. RO Unit No alarms indicated
- 28. UPS room Temp. 60*-80*F Thermostat >55'F j ,
- 29. T-300, T 301 Room !
Temp. > 40 *F
< 3.5* water j
- 30. Rm 114 particulate filter AP j
- 31. EG. Rm (Perform complete Thermostat > 60*F checklist on Sunday) Temp. > 50 *F
< 1 amp j
- 32. Battery charging current j
- 33. Battery voltage > 28 V Alllocked except east j
- 34. External doors when sec. on duty 5 - 10* ]
- 35. CT basin water level j ,
- 36. Automatic secondary makeup vis Auto or open
- 37. Acid dry tank level (Perform Visible weekly level check on Friday on storage tank)
- 38. Acid control and pH Range as posted Range as posted ,
- 39. Blowdown control /cond. !
- 40. CT sump pumps Operable
- 41. P pump (s) running
- 42. Pump strainer AP O - 7.0 psi
- 43. Discharge pressure
- 44. Pump strainer AP O - 7.0 psi
- 45. Discharge pressure i
- 46. ' Tunrtel sump pumps Operable !
Running
- 47. WT booster fan
- 48. Fission product monitor flow 95 - 105 cc/ min
- 49. Viv control header pressure 90 - 125 psig ,
- 50. Pressurizer N2 supply press 90 - 100 psia ,
I
- 51. Check rm 114 from door
- 52. Deltech oil filters
- red level * < 75% dark red and blow down i
i I SOP /A 8b Rev.10/20/94 App'd M i 1
t
. g l t; ,
i No. ammer naimwwm HERTH PHvnts arricE WARTE TANK RAMPLE BRPORT i
. TANK LEVEL (Liters) !
- TANKNO.' .
TIME DATE-SAMPLER' - 1; Analvais Resuh !
)'
Physical Form _ Concentration RTS* Activity Nuclide . H alf Life !
. c. ' N.3 12.3Y b.
F
-l i
.t i
FRACTION OF RTS ] pH l (Note: pH must be between 5.5 9.5 for release) ! TIME DATE Analysis by Activity (mci) Concentration (p Ci/ml) Total Volume diters) i (a) ,_ (b) _
- 2. Anorovals Renuired for:
\
i Any Disch arge . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Shift Supervisor . i
'Disch"arge of > 10 mei of H.3, > 2 mei of other activity, or to Secondary System Reactor Manager i
Discharge Limit Approved . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Health Physics i l
.3. - Action Taken ,
Time Discharged Volume Discharged ' (Liters) l Date Discharged l Sanitary Sewer O Secondary System 0Not Discharged l Tank Discharged to (check one): !
\
J REMARKS l
] ]
' ' Releases to Sewer,10CFR20, Appendis B Table 3. 1 SOP /A.11a l Rev.10/205M - App'd VM
MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES Revision Number 15 Revision Date: 4/4/94 Section Page Number Nismher . - SEP-8 1of3 SEP 2 of 3 SEP-8 3 of 3 Emergency Call List II-5
Page 1of>3- l t 1 SEP ) EMERGENCY EQUIPMENT MAINTENANCE PROCEDURE ,
Purpose:
This procedure states how the operational readiness of emergency equipment and - l supplies required by the Emergency Procedures is to be maintained, calibrated, l tested, and pedodically inventoried. . i Hamith Physics' Emerannev Eauinment. I Health Physics' Emergency Equipment and supplies required by the Site Emergency Procedums shall be maintained in two designated readily accessible locations. The - two locations are the MURR Emergency Equipment Cabinets in the copy machine j room and the Backup Emergency Equipment Cabinet at RPDB in room 10. The ! inventory checklists for each location are attached to this procedure and shall be used l to verify quarterly that the contents of the cabinet meet at least the required levels. All maintenance and inventory records on emergency equipment shall be maintained ; in the Health Physics Office. ; The civil defense kits stored at each location contain a G-M survey meter, an ion [ chamber meter (500 R/hr range), and a set of self-reading pocket dosimeters. These kits are exchanged routinely by Missouri SEMA for updated kits of l instruments which have been calibrated by SEMA. The emergency Health Physics' ] , equipment is supplemented by the Health Physics' instruments and equipment used i for daily routine evaluations and is maintained and calibrated by the Operational i Health Physics' Program. Off-Gas Monitorina Eauinment: I i The off-gas stack monitor has three channels: gas, particulate, and iodine. The three , channels shall be calibrated semiannually by the Health Physics / Reactor Chemistry group using Reactor Chemistry Standard Operating Procedures: RC/III 2 Calibration of Stack Particulate Monitor RC/III-3 Calibration of Stack Iodine Monitor RC/III-4 Calibration of Stack Gas Monitor - ji The operability of the off-gas monitor is checked as part of the start-up checklist for normal reactor start-ups. l l Fire Fiahtine Eauinment: . The fire hydrant in the reactor site is checked operable routinely by the Columbia ! Fire Department. The fire extinguishers shall be checked annually by the University l ofMissoud Physical Plant. ! Rev. 4/4/94 App'd M I L .. ! i
- ,s i
.w
- 7 9tl 8EP-8 ~ (Cont'd)-. Page 2 of3 j
~
EMERGENCYLOCKERINVENTORY l r r MURR COPYROOM l
, i i
Date-i By ! Number- ' Number - '!
- Required Desired l Y 1 () 2 flashlights - new batteries installed every 6 months. ,
Date batteries when installing in flashlights. .l 1 () 1 first aid kit { 5 () 5 "D" cell batteries replaced with new battenes every ; 6 months. Date batteries when placing in locker. l 3 (- ) 5 boxes swipes 0 () 1 box paper towels jl
-0 () Ibox absorbent paper 2 () 4 bars face soap [
-3. () 6 " Radioactive Material" tags j 0 () 2 rolls tape j 0 () 1 roll - " Radioactive Material" tape t 2 () 2 full face respirators l 2 () 5 half face respirators l
8 () 10 spare filters for respirators j 0 () assorted plastic bags j i 2 () 4 NuCon permasigns ; O () NuCon permasigninsets j 1 () 1 box rubber gloves l 4- () 7 sets protective clothing Li 0 () 20 ft. yellow and magenta rope - l
.1 () 1 Civil Defense instrument kit - l date kit placed in cabinet j i
b b. l i i
.h Rev. 4/4/94 App'd M l i
l
i r
. SEP-8 (Cont'd) ._ Page 3 o'f 3 s ;
EMERGENCY LOCKERINVENTORY l l RESEARCH PARKDEVELOPMENT BUILDING i (RPDB) Date' By [ i- - Number Number i
- Required Desired j
1 () 2 flashlights - new batteries installed every 6 months. r Date batteries when installing in Dashlights. I 1 () 1 first aid kit _j 5 () 5 "D" cell batteries replaced with new batteries every 6 months. Date batteries when placingin locker. ; 3 () 5 boxes swipes 0 () 1 box paper towels t 0 () 1 box absorbent paper : 2 () 4 bars - face soap , 3 () 6 " Radioactive Material" tags { 0 () 2 rolls tape l 0 () 1 roll " Radioactive Material" tape l () 2 2 full face respirators l 2 () 3 half face respirators 8 () 10 spare Hlters for respirators ; , 0 ( )- assorted plastic bags 2 () 4 NuCon permasigns 0 () NuCon permasigninsets 1 () 1 box rubber gloves () 2 2 sets protective clothing 0 () 20 ft. yellow and magenta rope t 1 () 1 Civil Defense instrument kit- ' date kit placed in cabinet t REMARKS: i 4 i
?
.Rev. 4/4/94 App'd M !
y,
~
~
;; 6 :y '
; .c ; ,
EnERGENCYCAU.USE j.- Director's OfNeo Faclittles C;i. ^^; .; Emergency Support Orgenlastions hh Phone. k hh iW' J. Rhyne 442 4967 _ C. Edwards 443-7529 UMC Polion 882 7201.
"3 '
J. C. McKhbon 442 8728 D. Pooler 816-848-2471 i K. Beamer 682 5499 i Reector C;;._^.:x.; R. Kitch 875-2045 ) Columbia F're Department '9 911 ! Phona.No. C. Kribbs 682-3980 W. Meyer 442-7675 - T. Seeger 474-3891 T.Schoone 443 8862 J. Baskett 474-2046 UM Hospital & Chrucs i R. Hulloch 442 6653 M. Richardson 446-1014 Emergency Services 882-8003 ! C. Anderson 696 5506 Ambulance 882-6128 or 9-911 ~~ B.Beannok 445 5680' Staff Resource Personnel Wak-in (Emergency Center) 882 8091 G.Gunn 875 1162- Phona.No. l N. Tritschler 474 9388 S. Moms 445-4217 .. L Foyto 446 0491 V. Speto 657-9450 UMC Health Physics (Office) 882-7221'
- j. J. Fruits 474-0774 C. Baskett 474 2046 Sue Langlierst (Home) 442-3534 ] ~
A. Hartweg 474-7882] M. Glascock 443 4172 Jamieson Shotts (Home) 474 2194-R. Hudson 445 6769- B. McCrachen 449 7731 Daried Spate (Home) 657-9450 V. Jones 445 2543 W. Oladiran 443 5658-
- P. Muren 874 0219 D. Nidolaus 443 0502-
~ P. Noel 442 8693 G. Ehrhardt 445-3570' MU News Bureau . 882 6211 W. Oldham 474 0987 - A. Kotring 657-9614 See Public Information Procedure for other 882 6214 or -882-6217.. i R. Walker - 443 0970 ~ B. Yelon 445-8147 phone numbers (SEP-7). 4 M. Wallis 387 4859 M. Kilfoil 449-2524 443 2125- ! T. Wamer 816-882 6740 S.Gunn L Krueger 442-0740 State Emergency Mananoment Agency (SEMA) 314 7512rG l 445 4038 - t
- Health Physics /Rx. Chemistry T. Storvick '
t Phone No. l R Dinger 449-C992]. J. Ernst 445-5621. NRC Washington. DC 301 951 0550 i R. Stevens 442 2539- I 8 J.Schuh 449 0992-i R. Ayers 445-0340 PEC Region El 708-829 9500 e W. D. Pickett 474-0709 A. Shipp .442 4304 j
- - American Nuclear Insurers 203-561-3433 i
2 Rev. 4/4/94 App'd _ _ _ _ _ _ _ _ . _ _ _ _ _ _ ____.__.m_ _ _ _ . , . _ . _ . - . - . . . ~ . _ .. .... _
..-..;..._._m.a.,......_.._..._,.._._,__.L...._.._..i
.L,'-
. .s
. ) :'
MURR SITE EMERGENCY PROCEDURES AND
- FACILITY EMERGENCY PROCEDURES Revision Number 16 Revision Date
- 7/29/94 e
Section Page Number Number SEP-2 S of 5 SEP-2 5 of 5 SEP-3 S of 6 SEP-3 6 of 6 - SEP-4 3 of 6 SEP-4 6 of 6 SEP-5 1of2 SEP-5 2 of 2 SEP-7 1of4 E,mergency Call List Worksheet C FEP-1 3 of 7 FEP-3 1 of1 FEP-4 1 of 5 FEP-4 2 of 5 FEP-4 3 of 5 FEP-4 4 of 5 FEP-4 5 of 5 University ofMissouri Hospital & Clinics Emergency Action Plan 59 - 68 II-6 i
J- l , ' - * * '
'd ' Page 3ef5 Si2lP-2 (Cont'd) _ 5 .
TABLE II.
.: EMERGENCY SUPPORT ORGANIZATIONS ,
6 'a'.o UMC HEALTH PHYSICS RERVICRR In the event of a radiological emergency, the.UMC Health Physics Services may ~ -t
' " be contacted to assist in checking facility personnel for contamination. L After hours the UMC Police may be contacted to open the Research Park Development -.
. Building (backup emergency control center). - One of the persons listed below will j
man the backup control center, i CONTACT OfHe Home j 442 3534 ~). Dr. Sue M. Langhorst 882-7221- ; Jamieson Shotts 882-7221 474-2194 J David Spate 882-7221 657-9450
- b. UMC POLICE '
24 hours . .l The UMC Police may be called to restrict entry to the facility. 882-7201 i N 1
- c. UNIVERSITY OF MISSOURI HOSPITAL & CLINICS iUMH&C) i Emergency Services 882-6003 :
Ambulance 882-6128 or 9 911 - Walk-In (Emerg. Center) 882-8091 .]
}
The UMH&C should be contacted in the event of personal injury. In the event + of personal contamination or radiation exposure without injury, see FEP-4, - ] [ l MEDICAL EMERGENCY PROCEDURES. 3 MU NEWS BURRAU - See SEP-7, PUBLIC INFORMATION PROCEDURE i d.
/
This office will initially deal with questions from off' site. Direct any questions j from media to this office. They will release statements only by EMERGENCY DIRECTOR authorization. j r COLUMBIA FIRE DEPARTMENT 1 e. 24 hours -l The Columbia Fire Department shall be notified in the event 9-911 l of fire or need of emergency rescue capability.- .' l i E Ensure Office of University Relations is also called. (Hage: Research Reactor street address is ] -l 1513 South Providence Road). ] ! 1l I i i i Rev. 7/29S4 App'd (M i i l
. , . . . ~_ u __ _. . .~ ._ __._ x . _ _ ._ _ J
to Page 5 ef 5 ' F SEP-2 (Cont'd) CORRECTIVE ACTIONS: (Cont'd)
- d. LABORATORIES (1) Determine which laboratory is the source of release by checking radiation levels in quadrant exhaust ducting.
(a) SouthwestQuadrant (b) Northwest Quadrant (c) Northeast Quadrant Actions to Consider: (.') Throttle flow from laboratory quadrant to reduce release rate to less t than Technical Specification limits. (2) Area Evacuations , t 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. l
- 3. Keep record of actions and evaluations and time they were done for documentation. Use procedure worksheets.
1
- 4. . Notify NRC, Headquarters Operations Officer, Washington, DC
[301-816 5100] that an UNUSUAL EVENT has occurred within one hour ] . 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. l 2. Procedures shall be written and approved for handling significant recovery evolutions. l . NOTE: During recovery operations, personnel exposures to radiation should be maintained with 10CFR20 limits. Rev. 7/29/94 App'd _ M __ _ _ ___-m-____ _______-__ _ --_-m_ ._ _-_._____m--_____.____ _____.__ __ _ _ _ _ - - - - . _ - . _
< __ w :
, . 1
. Page 3 df'6 " _g R [SEP-3'(Cont'd)) .-- _;
TABLE IIL .; N EMERGENCY SUPPORT ORGANIZATIONS .l
^
., a.T UMC HEALTH PHYSICS SERVICER
~
'~ In the event of an ALERT condition, the UMC Health Physics Services may be !
L contacted to man the backup emergency. control center. After hours, call the i E UMC Police to open the Research Park Development Building. -]- t CONTACT OfHee Hame Dr. Sue M. Langhorst 882-7221 442 8534 ] i~ Jamieson Shotts' 882-7221 474-2194. David Spate 882-7221 657-9450 ;, {
- b. UMC POLICE 24 hours !
The UMC Police may be called to restrict entry to the facility. 882 7201 j
- c. UNIVERSITY OF MISSOURI HOSPITAL & CLINICS (UMH&C) j j
Emergency Services 882-6003 . ' Ambulance 882-6128 or 9-911 Walk-In (Emerg. Center) . 882-8091 ] The UMH&C should be contacted in the event of personal injury. In the event' ! of personal contamination or radiation exposure without injury, see FEP-4, ] }' MEDICAL EMERGENCY PROCEDURES. l MU NEWS BURE AU - See SEP-7, PUBLIC INFORMATION PROCEDURE : d. This office will initially deal with questions from off-site. Direct any questions : L from media to this office. They will release statements only by EMERGENCY j . DIRECTOR authorization. y
- e. COLUMBIA FIRE DEPARTMENT !
L 24 hours ; The Columbia Fire Department shall be notified in the event 9-911 -l of fire or need of emergency rescue capability.- , Ensure Office of University Relations is also called. (Neig: Research Reactor street address is ] ; g 1513 South Providence Road). ] l i a l : l' i l- ) Rev. 7/29/94 App'd M l l k l
e 88P-3' (Cont'd); PJge 6 cf 6 t
~SUR.EIRQUENT ACTIONS: ,
I 1; Evaluate results of corrections and subsequent actions to determine need to 1 escalate /de-escalate the emergency classification.
- 2. Keep record of actions and evaluations for documentation. Use procedures and worksheets.
a
- 3. Notify NRC, Headquarters Operations Officer, Washington, DC
[301816 5100] 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 l condition has occurred. (Use information in Worksheet C) ;
- 5. Nctify State Emergency Management Agency (SEMA) [314-751-2748] that ;
4 an ALERT condition has occurred. (Use information in Worksheet C)' , f 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. 3 NOTE: During recovery operations, personnel exposures to radiation should be
- maintained within 10CFR20 limits.
i k
?
6
-- ~ . . _ _-- ., _ . _ . . ._ . - , - , - .-, ,+4 y
y - y _1 . j Page 3 cf'6 3 SSEP-4 (Cor t'd) -
- TABLE IV. ,
q EMERGENCY SUPPORT ORGANIZATIONS
'a. UMC HEALTH PHYSICS SERVICER z j
;; 1
' In the event of a SITE AREA EMERGENCY, the UMC Health Physics Services may be contacted to man the backup emergency control center. After hours, call the UMC Police to open the Research Park Development Building.-
- ]' jn CONTACT Office Home 882-7221 .442 3534' -] 9 Dr. Sue M. Langhorst -
~
Jamieson Shotts '882-7221 474-2194 . David Spate _ 882-7221 657-9450
. i
- b. UMC POLICE
- 24 hours - l The UMC Police may be called to restrict entry to the facility. 882-7201 ;
- c. UNIVERSITY OF MISSOURI HOSPITAL & CLINICS (UMH&C) - 'l Emergency Services 882-6003
-882-6128 or 9 911 i Ambulance
- ]
Walk-In (Emerg. Center) 882-8091 :. The UMH&C should be contacted in the event of personal injury. In the event of personal contamination or radiation exposure without injury, see FEP-4, -] j MEDICAL EMERGENCY PROCEDURES. i
- d. MU NEWS BURRAU - See SEP-7, PUBLIC INFORMATION PROCEDURE j
~
i This office willinitially deal with questions from off-site. Direct any questions i from media to this office. They will release statements only by EMERGENCY DIRECTOR authorization, q
- e. COLUMBIA FIRE DEPARTMENT -
24 hours The Columbia Fire Department shall be notified in the event 9-911-of fire or need of emergency rescue capability. Ensure Office of University Relations is also called. ::
-] d (No.te: Research Reactor street address is 1513 South Providence Road). ] ]
d y
)
L :j , i I Rev. 7/29/94 - App'd k i
gg , 37
;[ _
SEP-4 '(Cont'd): Page 6 cf 6 1 f - _j w e
, SURREQUENT ACTIONSi .
"- Evaluate results of corrections and subsequent actions to determine need to - 1
- 1..
i N ' 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 1
[301-216 5100] that a SITE AREA EMERGENCY condition has occurred ~ ] ' 0 within one hour after eventis classified or reclassified. (Use Work' sheet C) 1 , 4. Notify American Nuclear Insurers (ANI)[203-561-3433] that a SITE AREA i EMERGENCY condition has occurred. (Use information in Worksheet C) 1
- 5. Notify State Emergency Management Agency (SEMA) [314-751-2748] that 3 a SITE AREA EMERGENCY condition has occurred. (Use information in j Worksheet C) l 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 j maintained within 100FR20 limits. 3 i 1 5 i
\
Rev. 7/29/94 App'd M : i
I : s . , . Page 1 of 2 i SEE:A - i m H PARTIAL SITE ARRA EVACUATION PROCEDURE l , (SEE ATTACHED SITE MAP)
- 1. When a PARTIAL SITE AREA EVACUATION is deemed necessary, the EMERGENCY DIRECTOR shall contact the UMC Police Department to have
~ their personnel notify the affected laboratory and office spaces of the need to evacuate to the Research Park Development Building (RPDB).
b
- a. All personnel within the Golf Course Greenskeeper buildihg, the Cisil .
Engineering Freight Pipeline Research Laboratory building, the Laboratory Animal Center, and the Animal Psychology Laboratory in the Melvin H. Marx Research Laboratory building will proceed to the RPDB.
- b. All personnel within the Dalton Cardiovascular Research Center and USDA Biological Control ofInsects Research Laboratory will proceed north to the RPDB.
- c. All personnel within the Blood Center will proceed north on Providence Road to the RPDB.
- d. All personnel who have evacuated the reactor building will proceed to the RPDB.
- e. All personnel in the Greenhouse and Science Instrument Shop will proceed to the RPDB.
Building Number (s) Golf Course Greenskeeper building . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-6226 Civil Engineering Freight Pipeline Research Lab building . . . . . . . 2-3081 ,* Laboratory Animal Center . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-4123 or 2-4122 Animal Psychology Laboratory . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-3811 or 2-4123 2-7586 . Dalton Cardiovascular Research Center . . . . . . . . . . . . . . . . . . . . . .
- USDA Biological Control ofInsects Research Lab . . . . . . . . . . . . . . 875-5361 American Red Cross Blood Center . . . . . . . . . . . . . . . . . . . . . . . . . . . .
449-2656 2- 627 6 Greenhouse . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Science Instrument Shop . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-3711 or 2-3712 - 1 1 Rev. 7/29/94 App'd M Revised inits entirety ]
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AREA EVACUATION' R3v. 7/29/94 App'd NP _
/, PROCEDURE
./ _ _ _ _ _ _ - - _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ - - - _ .
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PUBLIC INFORMATION PROCEDURE - Y NOTE: - The MU News Bureau shall be activated to handle the release of public .; information as required in the ALERT or SITE AREA EMERGENCY - -l
- procedures; whenever off-site emergency assistance is requested via 911; or. j whenever deemed appropriate by the Emergency Director. j I
A. INITIAL RELEASE OF PUBLIC INFORMATION I
' 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-
]l Bureau.) ;
l
. 2a. During normal University office hours, activate the MU News Bureau by .
j calling 882-6211 (Rhona Williams), or 882 9143 (Jill Scoggins) or - .
.] -l 882 9144 (Connie Mitchell) or 882-6217 (Teresa Walker). ]. J 2b. At other times, call the followinglist of MU News Bureau staffin order until-one of the individuals listed is reached (HQI their spouse, children, etc.).' i t
h
- 1) Rhona Williams 449-1586. .6
]. j
- 2) JulScoggins 874 9015
- 3) Connie Mitchell 442-6166 ) l
- 4) Teresa Walker 446-0006 ] j
.f
- 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. q j
- 4. Record other questions that the MU News Bureau staff member may have.
Enter the name of the MU News Bureau staff member contacted and give j the completed report to the Emergency Coordinator to be kept with the records of the emergency. ]
.k l
-t Rev. 7/29/94 App'd _ M l l
1
~. _ $
NN *-- EMERGENCY CALLUST Director's Office Facilities Operations Emergency Support Organlastions , Phone.No. Phone.No .. Phone No. 443-7529 UMC Polce 882-7201 J.Rhyne 442 4967 C. Edwards J. C. McKibben 442 6728 D. Peeler 816-848-2471 K. Beamer 682-5499 ' 875'-2045 Columbia Fire Denartment 9-911 Reactor Operations R. Kitch Phone.No. C. Knbbs 682-3980 W. Meyer 442-7675 T. Seeger 474-3891 T. Schoone 443-8862 J. Baskett 474-2046 UM Hosoital & Clinics 446-1014 Emergency Services 882-6003 R. Hultsch 442-6653 M. Richardson Ambulance 682-6128 or 9-911 C. Anderson 696-5506 882 8091 445-5680 Staff Resource Personnel Walk.In (Emergency Center) B. Bezenek G.Gunn 875-1162 Phone.No. N. Tritschler 474 9388 S. Moms 445-4217 , 657-9450 UMC Health Physics (Officel 882 7221-L Foyto 446-0491 V. Spate 474-2046 Sue langhorst (Home) 442 3534 J. Fruits 474-0774 C. Baskett 443-4172 Jamieson Shotts (Home) 474-2194 A. Hartweg 474-7882 M. Glascock 449 7731 David Spate (Home) 657-9450 R Hudson 44F 6769 B. McCracken V. Jones 445 2543 W. Oladiran 443-5658 P. Muren 874-0219 D. Nickolaus 443-0502 445-3570 MU News Bureau '882-6211 P.Neel 442-8693 G. Ehrhardt A. Ketring 657 9614 See Public Information Procedure for other 882-9143 ] W. Oldham 474-0987 443-0970 B. Yelon 445-8147 phone numbers (SEP-7). 882-9144 ] R Walker M. Wallis 387-4859 M. Kilfoil 449-2524 T. Wamer 816-882-6740 S.Gunn 443 2125 L Krueger 442 0740 State Eiriessericv Manaaement Aaency (SEMA) 314-751 2748 l l Health Physics /Rx. Chemistry T. Storvick 445-4038 Phone No. R Dinger 449 0992 445-5621 NRC Wr.slaima.L DC 301-818-5100 ] J. Ernst i R. Stevens 442 2539 J.Schuh 449-0992 NRC Regen 111 708-829-9500 R Ayers 445-0340 W. D. Pickett 474-0709 A. Shipp 442 4304 American Nudear insurerp 203-561-3433 Rev. 7/29/94 App'd M" t
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% l WORKSHEET C ,
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+
[- CONTENTS OF INITIAUFOT T AWUP EMERGENCY MRRR AGES TO - i
" HEADQUARTERS OPERATIONS OFFICER" WASHINGTON, D.C. 301 816 5100 ]
- 1. Provide name, title, telephone number of caller.
, i L
L 2. Location of emergency event. F 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 I l 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) ,
Has the release been terminated? r
- 7. What protective actions taken? e.g. evacuation of facility, site area evacuation s
(
- 8. What outside assistance is required? e.g. SEMA, Fire Department, Medical Facilities
- 9. Are there any injuries? Are the injured contaminated?
l
- 10. Estimate impact of release? e.g.,is general public expected to be affected?
EMERGENCY DIRECTOR-AUTHORIZATION TO CALL L 1 f Rev. 7/29/94 App'd iklGM i l
( . j FEP 1(Cont'd) Pago 3 of 7
/ ,
- D. Ensure all personnel are cleamd fmm alllevels of the containment building
- and exit via personnel airlock doors. l The DUTY OPERATOR 'shall report to the EMERGENCY COORDINATOR . ] >
' and advise him of the status of the mactor. [
}
MANAGER OF HEALTH PHYSICS / REACTOR CHEMISTRY shall proceed to l the lobby control center and establish the radiation-safe condition of the area. -[ i L Immediate actions may require the Manager of H.PJR.C. to: j
- 1) establish a hot-cold change ama; j
- 2) - assemble and prepare for use, special Health Physics equipment; j
- 3) perform radiation and contamination surveys; !
i
- 4) evaluate the extent of radioactive contamination and/or radiation exposure received by personnel at the time of the incident; and/or [
- 5) advise the EMERGENCY DIRECTOR of measures to be taken to; j control radioactive contamination which may have resulted from the incident.
The EMERGENCY DIRECTOR shall appoint a COI4MUNICATOR to notify - i auxiliary organizations which have been made aware of these emergency procedures and perform other communicative functions required. The followmg telephone numbers may be of assistance in the performance of these duties: University Police / Watchman's Office, UMC 882-7201 ) Radiation Safety Office,UMC 882-7221 l Emergency Room, UM Hospital & Clinics, UMC - 882-8091 l 1 NOTE: When determined appropriate by the EMERGENCY DIRECTOR, the j evacuation horns may be silenced by opening breaker 15 on the j emergency lighting panellocated in the north inner corddor next to the emergency power transfer switch. jl I i i Rev. 7/29/94 App'd b l
)
i
p
~
~Page l ofi , ;
f' _ ,! 3 , FIRE PROCEDURE t. TMMEDIATE ACTIONS: f 1.H Any individual discovering a fire shall notify the Reactor Control Room (#13 j , [, or 2-5213) of the fire. [ If the fin'cannot be' extinguished with local fire extinguishers: 1 ks j
^
NOTE: This procedure is meant to serve as a guide to the EMERGENCY ' DIRECTOR. At his discretion any step may be altered or omitted as necessary. y The SHIFT SUPERVISOR will call 911 on the outside line (black phone) to ' ! 2. i notify the Columbia Fire Department. (Hata: Research Reactor stmet ] address is 1513 South Pmvidence Road.) :) ;
- 3. The SHIFT SUPERVISOR will initiate e Facility Evacuation. l
- 4. The EMERGENCY DIRECTOR will investigate the source of the fire and !
determine the steps to minimize hazards until the Fire Department arrives. !
- 5. Secure EF-13 and EF-14 if there is a potential for the fire spreading thmugh .{
the ventilation system. ;
- 6. Secure the ventilation supply fan SF-1, the north RTAH, the south RTAH, and close all fire doors. l
.(
i NOTE: The assessment of off site radiological consequences shall be determined. This assessment'may require escalating emergency response to a Site - Emergency Procedure (Unusual Event, Alert). SUPPLEMENTAL ACTIONS: l
- 1. The EMERGENCY DIRECTOR or EMERGENCY COORDINATOR should meet the Fire Department in the upwind parking lot. ,
'l
- 2. The EMERGENCY DIRECTOR will maintain contact with the INCIDENT j
-e COMMANDER at the Command Post.
- 3. The EMERGENCY DIRECTOR should contact the MU News Bureau to handle publicinformation. l
- 4. The EMERGENCY DIRECTOR will assist the INCIDENT COMMANDER in coordinating Sre fighting and lifesaving measures.
1
- 5. The EMERGENCY DIRECTOR will advise the INCIDENT COMMANDER of any proposed action that may violate the Facility NRC license.
i Rev. 7/29/94 App'd 1
w
$f l' Page1cfs:
s
<, > FEP-4 MEDICAL EMERGENCY PROCEDURE a
l Iqjuries which may or may not involve radiation exposure and/or radioactivity contamination are classified as follows by the UMH&C Emergency Action Plan - ] Radiation Response.: ]. b L 1. External Radiation - The individual who may have received a large external ] dose of radiation is of no risk to attendants, other patients or the environment.-] g his individualis no different than the x-ray patient. ] L , L 2. Inhalation or Incestion - Another type is the individual who may have received :) - internal contamination by inhalation or ingestion. his person is no ] l [ significant hazard to attendants, other patients or the environment. Following ] cleansing of any minor amount of contaminated material deposited on the body _ ] surface during airborne exposure, exposure is similar to the chemical poisoning ] case such as lead. Body wastes should be collected and saved for measurement'] - of the amount of nuclides to assistin determination of appropriate therapy. Persons attending those patients must wear gloves to avoid the ]- ; possibility of contamination. ]-
- l. 3. External Contamination - External contamination of body surface and/or clothing by liquids or by dirt particles containing radioactivity presents ]
]
the possibility of a radiation risk to attendants and the envimnment. Surgical isolation techniques should be followed to protect attendants from - ] - radioactive contamination. Decontamination must be performed, or- ]- the contamination fixed, to' avoid contamination of the area. J'
- 4. External Contamination comolicated bv a Wound - Care must be taken not to contaminate the wound fmm surrounding surfaces and vice versa. The ]
wound and surrounding surfaces are cleansed separately and sealed off when clean. When crushed dirty tissue is involved, early preliminary wet debridement following wound irrigation may be indicated. Further debridement and more
' definitive therapy can await sophisticated measurement and consultation guidance. j Rev. 7/29S4 App'd M
r; . ;"': .1 R&- ) ~l
- X; l
FEP-4 (Cont'd) Pag)2cf6 l 1 j 2 n:
' U=. ,H_. ..... . that an accident han accu. . d. the followine action is in be *= ken: 1 1 *
. ,I nl
- A. ' If the area in which the accident has occurred is a "high radiation area".with l
- an exposure dose rate of100 mR/hr or more, oris suspecte d tob e suc h an l l
area, move the victim quickly and carefully to a location at which the exposure dose rate is 5 mR/hr or less if the victim can be moved without : j l harm. Evacuate all personnel from the accident area and provide first aid to the victim. l B. Notify the Reactor Operator in the Control Room (2-5213). 1 o Accident Involvina Physical Iniury:
? A. Control Room Operator will notify the Emergency Room, UMH&C at .]- [
882-8091, and arrange for medical care either at the Facility or at UMH&C. ] t B. Control Room Operator will call Health Physics Man'ager at (2-5226) or by ] . l page. If the Health Physics Manager or health physics representative. j cannot be reached, call UMC Health Physics at 882-7221. Uoon arrival at the accident scene. Health Physics and/or Rhift Sunervisor will ]
- take the following action: :;
I A. Assess the severity of the radiation injury and classify the injury. B. If necessary, recommend to the Shift Supervisor to seal off the accident . ] 1 area and secure ventilation to that area. : i C. Ifinitial treatmentis to be administered at the Facility by a representative ] j of the UMH&C, attend the accident victim, keep him comfortable, and j render first aid as required. f i L D. Survey all personnel who may have been contaminated in the accident. ] : l Provide first aid as required. , i E. Provide decontamination of the accident victim,if possible, and all other ] persons found to be contaminated. ) l I 1 l l F. Save all samples of clothes, jewelry, etc. Label the samples with name, ] time and date. ; i l Rev. 7/29/94 App'd M. ) i
1, i?' - 'y < Pige 3 cf 5
% - FEP-4 (Cont'd) . , .
l l y
]
G. Notify the Facility Director and the Radiation Safety Officer. j H. Evaluate the radiation dose received by carefully reconstructing the '] f accident. This assessmentis more detailed than that required in item A l above and may be deferred until after the care of the accident victim is j g, transferred to the attending physician. Contamination and/or Radiation Exnosure Without Phvaical Iniurv: f r f
.. Contamination f;
Ifimmediate emergency cleaning of contaminated person's skin cannot , I reduce level to 1 mR/hr py or 1000 dpm a, they should be sent to the Research Park Development Building for further health physics evaluation l and/or decontamination. ; Ensure that one of the following persons will be at the Research Park l Development Building to assist in evaluating the need to move the person to j the UMH&C. (Health Physics Manager or UMC Health Physicist) :
'i Radiation If a person has an estimated 10 REM exposure to any part of the body or l
whole body, send to Research Park Development Building for further medical / health physics evaluation. t Transnortation Routes to the UMC Hosoital and Clinien. see Fisrure 1. FEP-4 .] l l A. University Hospital and Clinics: Accepts all Class I, Class II and ] I Class III trauma patients and provides necessary medical treatment ] and decontamination. Care will be provided in Emergency Center ] per routine disaster protocol. ] ! a ! B. VA Hospital: Accepts all overload Class III and non iglured patients ] (walking wounded) from University Hospital and Clinics and ] l provides first aid and decontamination. ] ) l [ i t
' Rev. 7/29/94 App'd M i
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Pcge 5 cf 5 ] , r FbP-4 (Cont'd)L 1 I RADIOLOGICAL CONTACTS I ASSISTANCE may be secured from the U.S. Department of Energy's REGIONAL COORDINATING OFFICES FOR RADIOLOGICAL EMERGENCY ASSISTANCE. Telephone and personal contacts with trained physician, specialist, technicians, laboratories, health physicists, public relations and information officer specialists are l cvailablein the following areas: ! Chicago Operations 'Omce Brookhaven Area Office Upton, NY 11973 9800 South Cass Avenue (516) 282-2200 Argonne, Illinois 60439 , (708)252-4800 duty hours ; Oak Ridge Operations Omce (708) 252-5731 off-duty hours , P.O. Box 2001 Oak Ridge, Tennessee 37831 Idaho Operations Office : (615) 576-1005 or 785 DOE Place 4 Idaho Falls, Idaho 83402 (615) 525-7885 i (208) 526-1515 Savannah River Operations Office P.O. Box A San Francisco Operations Office Aiken, South Carolina 29802 1301 Clay Street : Oakland, California 94612-5208 (803) 725 3333 i
- (510) 637-1794 Albuquerque Operations Office P.O. Box 5400 Richland Operations Office Albuquerque, New Mexico 87185-5400 P.O. Box 550 '
Richland, Washington 99352 (505) 845-4667 ' (509) 373-3800 References .
- 1. U.S. Department of Energy. Emergency Handling of Radiation Accident Cases:
Physicians (Prepared in cooperation with the American Medical Association) Washington, D.C. U.S. Government Printing Office,1979. .
- 2. Carol B. Jankowski, Radiation Emergency, American Journal of Nursing, Jan.
1982, pp. 90-97. Rev. 7/29/94 App'd Revised in its entirety ]
UNIVERSITY OF MISSOURI BOSFITAL & CLINICS EMERGENCY ACTION ,FIAN $ RADIATION RESPONSE .
- I. ~ GENERAL INFORMATION TYPES OF RADIATION ACCIDENTS Poses no hazard to hospital personnel External Radiation The individual who may have received a large external dose of radiation This is of no risk to attendants, other patients or the. environment.
individual is no different than the X-ray patient. Inhalation or Innestion Another type is the individual who may have received internal contamination by inhalation or ingestion. This person is no significant Following . hazard to attendants, other patients or the environment. cleansing of any minor amount of contaminated material deposited on the body surface during airborne exposure, exposure is similar to the chemical poisoning case such as lead. Body wastes should be collected and saved for measurement of the amount of nuclides to assis < determination of appropriate therapy. Persons attending those patients
- must wear gloves to avoid the possibility of contaminates.
Potentially poses a hazard to hospital personnel External Contamination ! External contamination of body surface and/or clothing by liquids or by dirt particles containing radioactivity presents the possibility of a radi risk to attendants and the environment. Surgical isolation techniques should be followed to protect attendants from radioactive contamination. Decontamination must be performed, or the contamination fixed, to avoid; contamination of the area. : i External Contamination Comolicated by a Wound Care must be taken not to contaminate the wound from surrounding The wound and surrounding surfaces are l surfaces and vice-versa. Emergency Action Plan ' 03/28/94 59
cleansed separately and sealed off when clean. When crushed dirty tissue is involved, early preliminary wet -debridement following wound-irrigation may be indicated. ' Further debridement and more definitive - therapy.can await sophisticated measurement and consultation guidance.' , i RADIATION PATIENT SEGREGATION ' ; i University Hospital and Clinics i Accepts all Class I, Class II and Class III trauma patients and provides necessary medical treatment and decontamination. Care will be provided j in Emergency Center per routine disaster protocol. VA Hospital j Accepts all overload Class III and non-injured patients (walking wounded) , from University Hospital and Clinics and provides first aid and decontamination. l VAH Command Center will contact UHC Command Center if addi- t tional staffing or equipment is needed, ; Patients are either discharged from VAH or directly admitted to UHC. j Admissions should be arranged through VAH Command Center, Transportation of patients from VAH to UHC will be made through the { UHC Command Center. I
'l l
i Emergency Action Plan l 03/28/94 60 l ! 1 I
)
.+ .
Y e s
, !IL- FACILITY RESPONSE- .
t-ER CHARGE NURSE OR SUPERVISOR I. Relay the information received about the reported disaster to the AOD, House Manager, ER Medical Director. and on-duty Attending
- Physician, Emergency Services Manager, Emergency Center Assistant -
Manager.
- 2. Assess actual number of victims and severity of injuries.
AOD ' Implement the Emergency Action Plan if situation warrants. l
- 1. i NOTE: Notify VA . hospital if the amount of victims cannot - be appropriately handled at the hospital. Only Class III patients ;
and non-injured will be treated at the VA. During office hours, contact the VA Hospital Associate Director; after hours, l contact the Medical Administrative Assistant.
- 2. Request from VA, if situation warrants, approval of transfer of Class III by EMS for treatment and decontamination by their facility. If approved by VA, notify ER at 2-8091 and inform them of VA approval to proceed.
i TELECOMMUNICATIONS '
- 1. Upon notification to initiate the Radiation Emergency Action Plan, announce " Radiation Emergency Action Plan is in effect" in the followmg j manner:
*Over the 0500 group pagers eBy calling divisional representatives requested by the AOD By calling the following critical areas:
- Health Physics ;;
- Radiology
- Admissions
- Distribution l
l SENIOR EMERGENCY CENTER RESPONSE PERSONNEL l
- 1. Activate the Emergency Action Plan if directed to do so by the AOD.'
Emergency Action Plan 03/28/94 61 t
A; ,-.. s , .
~
_(
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I2.' ;Upon receipt of call announcing momentary arrival of radiation exposure
^
victims supervise the following: .,
. ' a. ' Notify the Manager of Emergency Services -
- b. Open Radiation Emergency Kits I. '
- c. Establish treatment and decontamination at the Emergency Center. =
- d. . Don personal protective equipment and personal ' monitoring devices.
- e. Assist Housekeeping personnel in preparing the area for patient reception,- setting up the control area to hold- the anticipated-number of victims.
- f. To prevent tracking of contaminates, instruct House-keeping to cover floor areas. Floor covering will be applied from ambulance entrance into treatment areas.
- g. Establish a control line at entrance of decontamination area andi mark clearly with a wide strip' of. tape to differentiate' the contaminated from uncontaminated side.
- h. Instruct Security to establish control of treatment area.
.n 1
.i
' Assign a person to record radiological information and assist :l i.
Health Physics as needed.
- j. Check radiation monitors, cover probes with' rubber ' gloves or plastic bags and secure with tape and record background radiation levels in the decontamination room (s). .;
t j EMERGENCY MEDICAL SERVICE r ! t
.1. Put on personal protective equipment and dosimeters before entering the'
' radiation zone (record initial reading of dosimetry).~ l i j 2.. Prepare ambulance for receipt of patients by applying protective barrier covers. ! i Emergency Action Plan 03/28/94 62
K v , r Pick up radiationiaccident victims and decontaminate as appropriate. I, 3. Wrap with sheets, if possible, to control contamination. .
- 4. Report number of patients and nature of radiation accident to the ER.
- 5. Transport victims to designated hospital entrance (at VAH, east entrance to Animal Research Area), or as directed by the Emergency Center.
-t NOTE: Patients will be transported to either UHC or VAH based on . ,
the following criteria regardless of contamination status: l L Class I, II to UHC ' Class III to VAH ,
-i Non-injured to VAH i HEALTH PHYSICS SERVICE t 1.
Contact UM Radiation Safety Officer,2-3721 and if campus reactor is involved, notify the Reactor Health Physics Manager,2-4221. 7 i
- 2. Call Environmental Health and Safety and/or Business Office. ,
SECURITY l
- 1. Dispatch Security Officers to ER to monitor and secure entry and exit of l
personnel.
- 2. Assist Emergency Center in setting up restriction barricades and restrict public access to the area.
- 3. Direct patients to the ER.
HOUSEKEEPING l
- 1. Remove all hanging curtains from the treatment room.
- 2. Cut yellow herculite floor covering to fit the appropriate treatment room l
floor and secure with red duct tape.
- 3. Place brown paper on the floor half the widtn of the hall and 2 widths onto the ambulance unloading area. Tape the inside edges securely using the red duct tape and the outside edges with the yellow Radiation Tape. j
(' Emergency Action Plan 03/28/94 I 63 . t l t l
n; 4 ' 3 ;
.4. Place the stretcher in the treatment room and the splash tray on top of the
~ i stretcher with fluid collection container. '
- 5. After the patient is in the treatment room, place yellow herculite covering over the brown buffer zone paper and tape with yellow Radiation Tape.
- 6. Stand by for assistance in treatment room clean-up which will be directed 1 by the Health Physics officer.
RADIOLOGY Provide a radiologist-on-call in the absence of a Health Physicist to assist in the j interpretation of radiation level measurements and ensure staff's protection. Nuclear medicine technicians with survey meters may serve as monitoring technicians. Radiation Physicist serves as competent Health Physicist during emergencies. ADMISSIONS Report to ER, providing emergency charts and ID bracelets. PLANT ENGINEERING t Prepare to shut off air circulation system to prevent spread of contamination if directed to do so by the AOD or Command Center.
. i i
}
U. EQUIPMENT AND SUPPLY LIST EMERGENCY SERVICES A. Radiation Monitoring equipment (Barrels housed in Emergency Services area) s
- 1. Survey meters r
- 2. TLD badges
- 3. Pen dosimeters !
l
- 4. Plastic Bags I
i i
. Emergency Action Plan j 03/28/94 64
~
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-3 r
' 5. ' Signs /L,abels- !
l B. General Equipment - Normal patient care and medical items. ! HOUSEKEEPING , Usual housekeeping equipment and protective floor covering. SECURITY l Barriers to control contaminated area i P VA HOSPITAL Two large drums containing Radiation Disaster supplies are stored in the VA research area and the VA shall be responsible for maintenance of the contents.- i l SUPPLY DISTRIBUTION . When requested, couriers will deliver supplies and decontamination beds (s) . designated areas. t i P h t i
~- !
i i i i. Emergency Action Plan 03/28/94 , 65 M
- g. '
0 L@ q i ] q y kIIL PROCESS-o, j [9 ~ - HEALTH PHYSICIST, PARAMEDIC,- EC or FLIGHT NURSE: r A .' - Check patients, for contamination with survey meters (preferably as - _i
; patient is removed from the ambulance. ;
l
- .B. If seriously injured, give emergency lifesaving treatment immediately.
- j Handle contaminated patient with wound as one would a surgical t C.
procedure (i.e., gown, mask, cap, double gloves, etc).
] i 1
D. If external contamination is involvsd,- save all clothing and bedding from: j " ambulance, blood, urine, stool, vomitus, and all metal objects with name,
.I
' body location, time and date. Save each in appropriate containers; mark j-containers clearly, " Radioactive - Do Not Discard". Marking may be- 1 made with adhesive pasted to cloth bag or hamper inside of which is
-[
plastic disposable bag. Ambulance to be released by Health Physics ; before returning to service. 1 Decontamination should start, if medical status permits, with cleansing -f E. y and scrubbing the area of highest contamination first.- If an extremity alone is involved, clothing may serve as an effective barrier and the. ] Initial cleansing i affected limb alone may be scrubbed and cleansed. J should be done with soap or detergent and warm water. Wash water maE y be flushed into community sewnee system where dilution will obviate any !
. hazardous effect. if the body as a whole is involved and clothing is l
generally permeated by contaminated material, showering and scrubb, will be necessary. Pay special attention to hairy parts, body orifices, and l body folds. Decontamination of eyes, ears, nose, and mouth require- 1 irrigation with copious quantities of irrigation solution or. water. Remeasure and record measurement after each washing or showering. , j
'[
If a wound is involved, prepare and cover the wound with self-adhering l j disposable surgical drape. Cleanse neighboring surface of skin. 1S cleansed areas with self adhering disposable surgical drapes.' . Remove wound covering and irrigate wound withL sterile saline, catching the r j l irrigation 1 fluid in a basin, and handle as described in item D above. j Each step in the decontamination' processf should ~ be preceded and i followed by monitoring and recording.of the location and extent of q contamination. i t, eEmergency Action Plan ! 103/28/94 1 66
'I t
l
i % s i c ,
. F. Collect nurses', physicians', and attendants' scrubs or protective clothing, .
- 'i in plastic bags or waste barrels for monitoring by Health Physics. Nurses '!
.4.vtas. and ~ an=Amots must' follow the same manitorine and
'dua.tamination eivdures to maintain contaminatinn s,etrels.
G. Request for additional supplies, equipment, and staffing should be ~ ! arranged by the Emergency Center through the Command Center. . , H. . Admissions to floor beds, ICUs, OR. will be coordinated through the Command - Center, based on . . patient acuity not primarily on 1
~
contamination level. ! 1 J. If the physician in attendance in the Emergency Center is confronted with :i a grossly contaminated wound with dirt particles and crushed tissue,' he/she should be prepared to do a preliminary simple wet debridement. l An emergency minor surgical set would be used. Further measurements l t may necessitate sophisticated wound counting detection instruments supplied by a consultant who will advise if further definitive debridement .1 is necessary. 1 1
~
. NOTE: ~ ' Health Physics Service personnel will serve as consultants .
in the event that radiation victims are treated at UNC. Their expertise includes the areas of: j > e' the use of radiation monitoring equipment;-- ! i
- the bgistical direction of patients treated and area !
to be utilized-
- direc'ang the disposal of radioactive waste; .l
- directing the clean-up effort ' to ensure a. !
?
raidoactive. free environment. and -
- a: sessing radiation doses of attending personnel. l r
i
.I i
.l v
i t t i, Emergency Action Plan ! 03/28/94 l 67 : i i s
)
1
-g. l IV. MUTUAL AGREEMENT Mutual Agreement between Truman VA Hospital and University Hospital I
r
- 1. The VA Hospital Associate Director-on-Call or the VA Medical-Administrative Assistant is authorized to receive and act upon.
requests for aid from the AOD/ Command Center. Upon approval, the VA representative will activate the Radiation Disaster Plan.
- 2. Each facility will be responsible for staffimg their respective areas l and ensuring that appropriate equipment, supplies, personal
- protective devices, environmental barriers, and monitoring l equipment is available. 1
- 3. Each facility will store two, easily accessible, Radiation Disaster Response drums, properly maintained and labeled.
- 4. After decontamination, patients to be hospitalized will be transported through the VA/UHC tunnel to UHC. Patients l
requesting admission at the VA and fulfilling VA admission criteria will be admitted to the VA Hospital. All VA admissions will be communicated to the UHC Command Center.
- 5. Decontamination of each facility after victims have vacated the area will be supervised and directed by their respective Health Physics / Radiation Safety personnel who will then officially declare the area safe for resumption of routine activities.
- 6. Any victim that is dead on arrival or that expires during treatment will be transported to the VA Morgue.
VL ALL CLEAR AOD Instruct Telecommunications to announce, or otherwise announce, " Radiation Emergency Action Plan All Clear." Emergency Action Plan 03/28/94 68
1 ,
.a l c, MURR SITE EMERGENCY PROCEDURES'AND l FACILITY EMERGENCY PROCEDURES :
9 Revision Number 17 l Revision Date: 8/25/94 ; Section Page . Number Number t SEP-8 2 of 3 i SEP-8 3 of 3 t Emergency Call List i i e S k 9 Y l P e r{ 9 M II-7 :
SEP-8 (Cont'd) Page 2 d3. . EMERGENCY LOCKER INVENTORY MURR COPY ROOM Date By Number Number Required Desired 1 () 2 flashlights - new batteries installed every 6 months. I Date batteries when installing in flashlights. 1 () I first aid kit 5 () 5 "D" cell batteries replaced with new batteries every 6 months. Date batteries when placing in locker. 3 () 5 boxes swipes q 0 () 1 box paper towels i 0 () Ibox absorbent paper j 2 () 4sbars face soap l 3 () 6 " Radioactive Material" tags 0 () 2 rolls tape 0 () Iroll " Radioactive Material" tape 0 () assorted plastic bags 2- () 4 NuCon permasigns 0 () NuCon permasign insets 1 () Ibox rubber gloves 4 () 7 sets protective clothing 0 () 20 ft. yellow and magenta rope l 1 () 1 Civil Defense instrument kit - date kit placed in cabinet REMARKS: I Rev, 8/25/94 App'd M
+ 3, ; ,, , , y s ,- ; 4 b L iSEP-8 (Cont'd). Pdge 3 ef 3 ,
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l u' EMERGENCY LOCKER INVENTORY
^
IRESEARCH PARK DEVELOPMENT BUILDING p, (RPDB) Date By Number - 1 Number ' Required Desired l l 1 () 2 flashlights - new batteries installed every 6 months. Date batteries when installing in flashlights. 1 () I first aid kit 5 () 5 "D" cell batteries replaced with new batteries every 6 months. Date batteries when placingin locker.
'3 () 5 boxes swipes
'O () Ibox paper towels 0 () Ibox absorbent paper l 2 () 4 bars face soap . ,
3 () 6 " Radioactive Material" tags 0 () 2 rolls tape 0 () Iroll " Radioactive Material" tape 0 () assorted plastic bags () T 2 4 NuCon permasigns 0 () NuCon permasign insets 1 () Ibox rubber gloves 2 () 2 sets protective clothing 0 () 20 ft. yellow and magenta rope I 1 () 1 Civil Defense instrument kit - : date kit placed in cabinet ; REMARKS: I Rev. 8/25/94 App'd M l
, 3 mg ENERGENCY PROCEDURES EMERGENCY CALL LIST Director's Office Facilities Operations Emergency Support Organizations Phone No. Phone.No. Phone.No.
J.Rhyne 442-4967 C. Edwards 443-7529 UMC Polce 882-7201 J. C. McKibben 442-6728 D. Peeler 816-848-2471 K. Beamer 682-5499 Reactor Operations R. Kitch 875-2045 Columbia Fire Deoartment 9-911' Phone.No. C. Kribbs 682-3980 W. Meyer 442-7675 T. Seeger 474-3891 T.Schoone 443-8862 J. Baskett 474-2046 UM Hosoital & Clines 442-6653 M. Richardson 446-1014 Emergency Services 882-6003 R. Hultsch 696-5506 Ambulance 882-6128 or 9-911 C. Anderson 445-5680 Staff Resource Personnel Walk-in (Emergency Center) 882-8091 B.Dezenek G.Gunn 875-1162 Phone.No._ N. Tritschler 474 9388 S. Moms 445-4217 V. Spate 657-9450 UMC Health Physics (Officel 882-7221' J. Brake 446-3026 ] 446 0491 C. Baskett 474-2046 Sue Langhorst (Home) 442-3534 L Foyto 474-0774 M. Glascock 443-4172 Jamieson Shotts (Home) 474-2194c J. Fruits 474-7882 B. McCracken 449-7731 David Spate (Home) 657-9450 A. Hartweg R. Hudson 445-6769 W. Oladiran 443-5658 V. Jones 445-2543 D. Nickolaus 443-0502 874-0219 G. Ehrhardt 445-3570 MU News Bureau 882-6211 P. Muren 442-8693 A. Ketring 657-9614 See Public Information Procedure for other 882-9143 P. Neel 474-0987. B. Yelon ~445-8147 phone numbers (SEP-7). 882-9144 W. Oldham R. Waker 443-0970 M. Kilfoil 449-2524 M. Wallis 387-4859 S.Gunn 443-2125 L Krueger 442-0740 State Emeroency Manaaement Aaency (SEMA) 314 751-2748 T. Wamer 816-882-6740 T. Storvick 445-4038 Health Physics /Rx. Chemistry R. Dinger 449-0992 NRC Washinoton. DC . 301-816-5100, Phone No. R. Stevens 442-2539 ]. J. Ernst 445-5621 J.Schuh 449-0992 NRC Reason til 708-829-9500 R. Ayers '443-6328 ] W. D. Pickett 474-0709 A. Shipp 442 4304
.- American Nuclear insurers 203-561-3433 =
S. Keithley 443-1929 ] Rev. 8/25/94_. .
' App'd M_
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- /,1 MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES Revision Number 18 Revision Date: 12/20/94-Section Page Number Number SEP-2 2 of 5 -
SEP-3 2 of 6 SEP-4 2 of 6 SEP-9 1of2. Emergency Call List-FEP-1 2 of 7 FEP-2 2 of4 II-8
o
- n
. Page 2 ofd.
i SEP-2[(Cont'd) . L
- 5. Send operator to west' tower with radiation monitor to:
E M E: Communicate by intercom, since stack monitor is' affected by portable' radio RF.'
- a. Verify radiation background at stack monitor.
b.: . Verify control room readings.
- c. Write down the nadings on the analog display, with the time, for futum ]
analysis if the control room display becomes inaccessible.'
- d. Verify flow rate through monitor is 5
- i SCFM. If not, use Worksheet A to determine stack monitor values.
< 6. If nuclides which are being released are in doubt, pull stack filters and analyze. .
- 7. The Emergency Coordinator shall evaluate the need to evacuate specific portions of the facility. .
- 8. The Emergency Coordinator shall appoint and have a surveillance team check any areas evacuated in step 7, 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 forlifesaving, up i to 25 rem to prevent exposu-e to members of general public in excess of
'l rem whole body and 5 rem thymid.) _.
i
- 9. The Emergency Director shall determine the need for Emergency Support Organizations and,if needed, activate them or place them on standby. See Table II, Emergency Support Organizations. ,
NOTE: If 9-911 is called during any emergency, contact MU News Bureau. : l i Rev.12/20/94 App'd ibh
- w.. ,
- j y SEP-8 (Cont'd) -
- Page 2 of 6 j 3
l IMMEDIATE ACTIONS: (Cont'd) . 3 L! 1
,j 5. Send operator to west tower with radiation monitor to: ,
m;- .
'T M: Communicate by intercom, since the stack monitor is affected by i portable radio RF.
l
- a. . Verify radiation background at stack monitor. l 7.
- b. Verify controlroommedings. j
- c. Write down the readings on the analog display, with the time, for ] ]
future analysis if control room display becomes inaccessible. j
- d. Verify flow rate through monitor to 5 i 1 SCFM. If not, use Workaheet A l to determine stack monitor values.
1
- 6. Pull stack monitor filters and analyre. -!
- 7. After determining radionuclide responsible and verifying concentrations' l greater than 100,000 AEC* (a) secure EF-13 and EF-14;(b) secure RF2, j SF2, SF1; (c) secure all individual vent fans. ]
+
- 8. The Emergency Coordinator shall evaluate the need for a partial or total l evacuation of the facility. j NOTE: For facility evacuations or northeast quadrant evacuation, have .
sample counting instrumentation amoved 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. q NOTE: Emergency Director approval required for any voluntary radiation l exposure in excess of 10CFR20 limits. (Up to 75 rem for lifesaving, up to 25 rem to prevent exposum to members ofgeneral public in ' i excess of 1 mm whole body and 5 rem thyroid.) l
- 10. Determine the need for Ezrirgency Support Organizations and,ifneeded, activate them or place them on standby. See Table III, Emergency Support Organizations.
'AEC. Air Emuent Concentration as per 10CFR20, Appendix B, Table 2, Column L Rev.12/20S4 App'd M k_
1
- - , - , - - - * - - e ~a e- s .a ,a e ,,a,e >.-v-e a w m,---w -
s- ,-v--, -+,--- -e-wr.- -- w n ~*-,w-~ w
x > ~ Page 2 of 6.- SEP-4 (Cont'd) i IMMEDIATE ACTIONS: (Cont'd) , i
- 5. ' Send operator to west tower with radiation manitor to: ]
M: Communicate by intercom, since the stack monitor is affected by j portable radio RF. i j I
- a. Verify radiation background at stack monitor.
- b. Verifycontrolroomreadings. l
- c. Write down the rechags on the analog display, with the time, for ] l future analysis if control room display becomes inaccessible. .
1 Verify flow rate through monitor to 5 i 1 SCFM. If not, use Worksheet A j d. to determine stack monitorvalues. l
- 6. Pull stack monitor filten and analyre, ;
i
- 7. After determining radionuclide responsible and verifying concentrations L. greater than 500,000 AEC* (a) secure EF-13 and EF-14; (b) secure RF2, SF2, SF1; (c) secure all individual vent fans. ] l i
- 8. The Emergency Coordinator shall evaluate the need for a partial or total :
evacuation of the facility. t NOTE: For facility evacuations or nort.heast quadrant evacuation, have t sample counting instmmentation removed to RPDB. (Ge-Li detector and dewer; High Resolution Gamma Ray Spectrometer) i
- 9. The Emergency Coordinator shall appoint and have a surveillance team i check areas evacuated clear of personnel within 30 minutes.
I NOTE: Emergency Director approval required for any volunta.y radiation -i exposure in excess of 10CFR20 limits. (Up to 75 rem for lifesaving, , up to 25 rem to prevent exposum to members of general public in , excess of 1 rem whole body and 5 rem thyroid.) - l
- 10. Determine the need for Emergency Support Organir.ations and,ifneeded, activate them or place them on standby. See Table IV, Emergency Support l
)
l. Organir.ations.
- 1. l
*AEC-Air Effluent Concentration as per 10CFR20, Appendix B, Table 2, Column 1.
l Rev.12/20/94 App'd (M i i i I t
Page 1 of 2.- 1 ' SEE-3 TRAINING PROCRnURE OF EMERGENCY PREPAREDNRM - I. TRAINING OF EMERGENCY ORGANIZATIONS < j A. FACILITY EMERGENCY ORGANIZATION (FEO) TRAINING This organization consists of MURR staffin the Director's OfHee, Operations, , and Health Physics / Reactor Chemistry gmups. This organization will ! respond to bol,h General Facility Emergencies (Facility Evacuation, Reactor - ! Isolation, Fire, Medical, and Security emergencies) and Emergencies with i f Possible Off-Site Consequences (Unusual Event, Alert, Site Area
-i Emergency, Partial Site Area Evacuation). .
- 1. The members of the FEO will train initially and annually thereafter, by .
emergency plan and procedure review of each member's role in i emergency preparedness. This training will be documented by each [ member signing the Emergency Plan /Pmeedures Review Documentation j List.. j
- 2. An annual on-site emergency drill shall be conducted as an action .] ,
drill to test the training of FEO members to carry out their roles ] l under simulated emergency conditions. l i B. TRAINING OF FACILITY STAFF OTHER THAN FEO MEMBERS .
- 1. The members of MURR staff not assigned to the FEO shall initially, and i annually thereafter, be trained as to their respective actions for each site i and facility emergency classi6 cation. This training may be by seminar, ;
lecture, or video tape sessions. j
- 2. An annual on-site emergency drill will test these members' ability to ] !
properly respond to simulated emergency conditions. -
)
C. TRAINING OF EMERGENCY SUPPORT ORGANIZATIONS- !
- 1. The members of Emergency Support Organizations shall be trained i initially, and biennially thereafter, on their role in maintaining emergency preparedness. This will be performed by discussions between MURR staff and the members of each Support Organization, stressing familiarization with the facility or specinc changes to the Emergency ]
Plan or Procedures that may effect their msponse. This training ] . will be scheduled prior to each biennial ddll and will include ddll 9nning l and scenario development. l
- 2. On a biennial basis, the annual emergency drill shall be conducted ]
to test, as a minimum, the communication link and notification procedures with these Emergency Support Organizations. j
- i App'd UWW\ !
a Rev.12/2094 i *
,nw., , - - - . . , - - , . , . . , - , . - -- ,w--. . , , - - , , - . - ..n , , , - - - , - . . - - , ,,, , c-
NN . ENERGENCYCALLUST Director's Offlee Feellities Operemons Emergency Support Orgenlastions
- Phone Nn. Phone.No. Phona.No.
442-4967 C. Edwards 443-7529 UMC Paine 882-7201 J.Rhyne i J. C. Mclabben 442 6728 B. McCracken 449-7731 ] i W. Oladran 443 5658 ] Reector Operations D. Poeler 818-848-2471- Columbia Fire Department 9 911-Phona.No. K. Beamer 314-682 5499 } W. Meyer 442-7675 J. Evans 898 2127] ' T.Schoone 443-8862 R.Kitch 875-2045 UM Hannital & Clinics 442-6653 C. Kribbs 314 682 3980 ] Emergency Services - 882 6003 R. Hultech Ambulance 882-6123 or,9-911 C. Anderson 696-5506 S. Rinehert 314-682-2807 ]
'445 5680 T. Seeger 474-3891 Wak-in (Emergency Center) 882-8091-' ,
B.Bezonek G. Gunn 875-1162 J. Baskett 474-2046 N. Tritschler 474-9388 M. Richardson 446-1014 L Foyto 446 0491 UMC Health Physica f0f5cm) 882 7221 474 0774 Stoff Resource Personnel Sue Langhorst (Home) 442 3534 4 J. Fruits ' 474-7882 Phone.No. Jamieson Shotts (Home) 474-2194 A. Hartweg R. Hudson 445 6789 - S. Morris 445-4217 David Spate (Home) .657-9450 V. Jones 445-2543 V. Spate 657-9450 - t P. Muren 874-0219 C. Baskett 474-2046 ;
'442-8693 M. Glascock 443-4172 MU News Bureau 882-6211 P. Noel I
W 30 0 G. 45 5 rs SEP 2 14 M.Wallis 314-387-4859 ] A. Kotring -657-9614 T. Wamor 816-882-6740 B. Yelon 445 8147 . M. Kilfoil 449-2524- State Ernarpency Management Agency (SEMA) 314-751 2748 .[ Health PhyelceNtx. Chemistry S.Gunn 443-2125 . Phone No. L Krueger 442-0740 , J. Ernst 445-5621 T. Storvick 445-4038 NRC Washington. DC 301-816-5100 J.Schuh -449-0992 R. Dinger 449-0992-R. Ayers 443-6328 W. D. Plchett 474-0709 f5tC Reginn M 708-829-9500 , A. Shipp 442-4304 S. Keilhley 443-1929 Amadcan Nuclear insurers 203 561-3433 Rev. 12/20l94 App'd MY ..
. . - - - .-. --- . - . - . . - = - . - - - - - . . . - . - - - . _ _ . - - - . - - = - - - --
;,~ I j
-y 1 Page 2 of 7 l EEP.:1 (Cont'd) i I. M.ONNFL WITH PREARRIGNED TARKS i (Facility Emergency Organization Members) ! A. IMMEDIATE ACTIONS:
} i 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 Physica/ :] Reactor Chemistry, Machine and Electronics Shop Supervisors, and Duty j Shift Supervisor. ; The responsibility for Emergency Director shall be assumed. The Emergency j Director shall ascertain the availability of personnel required to execute the i emergency plan and shall appoint an Emergency Coordinator. He shall i investigate the cause of the alarm and the magnitude of the incident, and { shall direct those activities necessary to correct the emergency situation. ] : The Emergency Coordinator shall ascertain that the reactor containment - building, the Facility laboratories, and the mechanical equipment 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 l released from the site by the Emergency Director. He shall ensure a recorti ) l of the events following the emergency is maintained. j The Duty Operator shall perform or have performed the following tasks ! before leaving containment: (Do not attempt to correct any abnormalities at i this time.)
-i A. Verify that the reactor has scrammed as indicated by the instrumentation.
B. Verify that all shim rods have bottomed as indicated by the console lights. C. Verify that the containment has sealed as indicated by the ventilation I door and the exhaust valve lights. ; I Rev.12/20/94 App'd M 1 1 4 I i 1
' Page 2 of4-FEP-2 (Cont'd) :
L . PERSONNEL WITH PRE. ASSIGNED TASKS: (Facility Emergency Organization mamhers) - ,
=
1 The following shall report to the lobby contml center during normal working hours: - .l Reactor Manager, Reactor Operations Engineer, Shift Supervisor, Duty. . Operator, Plant Engineer, Manager of Health Physics, Machine and Electmnics Shop Supervisors. ..
-l i
The responsibilities of Emergency Dimetor shall be assumed. The Emergency Director shall ascertain the availability'of i , ad mquired to execute the 'i emergency plan. He shallinvestigate the cause of the alarm and the magnitude of the incident. He shall appoint an Emergency Coordinator. l 1 i j Ifin the opinion of the Emergency Director the extent of the emergency is sufBeient to warrant evacuation of the facility, he shall actuate the alarm and -l the facility evacuation plan shall be executed. ] The Emergency Coordinator shall establish that containment is vacatad and secured. He shall maintain a roster of all persons released from the site by the ' , Emergency Director. He shall assist the Emergency Director as mquired and - ] ! insure a record of the events following the emergency is maintained. The Duty Operator shall perform or have performed the following tasks before l leaving containment. (Do not attempt to correct any abnormalities at this time.) - .l
-1 A. Verify that the reactor has scrammed as indicated by the instrumentation. l B. Verify that all shim rods have bottomed as indicated by the console lights. l C. Vedfy that the containment has sealed as indicated by the ventilation door :i and the exhaustvalvelights.
D. Ensum all personnel are cleared from alllevels of the containment building and exit via personnel airlock door. l I I
.i i
f Rev.12/2W94 App'd b l I
't, ! i HEALTH PHYSICS STANDARD OPERATING PROCEDURES (New manualissued 10/29/90) l i l Sagiion Paqre Nos. Revision No. Revision Date , i
~ HP-6 1 1 5/31/94 l HP-13 1 1 5/31/94- 1 HP-14 1-2 2 11/29/94 HP-17 1-3 4 5/31/94 HP-28 1-6 3 8/12/94 :
HP-35 1-3 1 5/31/94 HP-39 1-6 1- 8/12/94 The following HP-SOP procedures were deleted &2/94: , HP-5, Revision No.1 e HP-16, Revision No.12 i HP-23, Revision No. 2 HP-26, Revision No.1 ; e i i i 6 h l l 1 i
)
i II-9
6 ,1 1 SOP MP-6 Rev. 1 Pa e__1 of 'Appr'd ns/ Date Sh31/94 Air Sampling During Reactor Emergency - _ 1.0 POLICY AND SCOPE l' 1.1 ' This procedure is used when the MURR Emergency Plan has been initiated and is performed to provide data for evaluations by the Emergency Director. Air samples will ) be collected and analyzed as per SEP-6. ) 1.2 This procedure may be used when air sampling is deemed ) , necessary by the Reactor Manager or'the Health Physics ] 1 Manager. ) j 2.0 PROCEDURE , 1 2.1 Evacuate air sample can, if one of the cans-is not currently evacuated, use Reactor Health Physics vacuum. pump or equivalent (10-4 torr vacuum range). 2.2 Collect sample as per SEP-6. 2.3 Select counting station as following priority depending on availability. A. Reactor Health Physics NaI counting well. B. NaI detector--MCA system at Research Park ) Development Building. 3 I .. f 2.4 Report analysis to Emergency Director.
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.- v SOP MP-13 Rev. 1 Page 1 of 1 u
Appr'd c bers c Date 5/31/94 MURR Hot Cell Operation L 1.0 POLICY Use of the Hot-Cell is restricted to persons who have received 4 appropriate operational training from Service Applications- ) -) Group and radiation protection instructions from Health ] l Physics Group. ) i 1 2.0 PURPOSE The MURR Hot Cell-is to be used to minimize radiation exposure to personnel. 3.0' RESPONSIBILITIES 3.1 Administrative responsibility for the Hot Cell is i l assigned to Manager, Reactor Health Physics. 3.2 The Manager, Reactor Health Physics is responsible for providing radiation protection as required for use of the Cell. 3.3 The Manager, Reactor Health Physics is responsible for determining that the exhaust filter system from the cell is adequate. 4.0 OPERATION OF TME CELL 4.1 Health Physics shall be informed prior to entry to the Cell. c A. Custody of the access door key shall remain with Health Physics. 4.2 The exhaust blower must be operating whenever the access door or pass-through are open. 4.3 Health Physics shall evaluate the airborne contamination
" hazard prior to entry to the cell.
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MP-14 f SOP Rev. 2 P ge 1 of 2 [ Appr' d #3 Date 11/29/94 ; CHANGING STACK MONITOR FTLTERS 4
1.0 Pureose
lJ. c To replace the currently collecting particulate and charcoal .) !' filters with new ones. The particulate, iodine and. gas . ) monitors are source checked at this time, and the iodine high ]- i voltage is checked. These checks are to ensure the stack J-monitor is performing reliably between ' calibrations. This ) -; procedure does not apply to emergency or special situations- ) involving.these filters. . ] .[
2.0 Precaration
) -{
r 2.1 Collect a new particulate filter, a charcoal filter, the :) l l filter change-out book, a small plastic bag, a small
)
envelope, and a volt meter. ] 2.2 Label the filters with the next consecutive number from ) , the filter change-out book. Record these new numbers. ] i 2.3 Ensure that no experimental or maintenance activities ] are being conducted which could likely result in the ] .i release of significant quantities of airborne ] ; radioactivity. The pneumatic tube system must not be in ] use during filter change. Call the control room and ask ) for their assistance in reading the control room ) recorder. ] [ J' I
3.0 Procedure
3.1 At the stack monitor, record the date, time and stack ) ' monitor pump flow rate in the filter change-out book. ] Ask for readings from the particulate, iodine and gas ) { recorder in-the control room. Record these values and ) { compare them to the stack monitor meter readings. ] l 3.2 Inform the operators that you are going to turn the pump ) > off. Turn it off and record the time. } l l 3.3 Remove the particulate filter holder from its housing. ] ; Place the particulate monitor standard (Cs-137) in its ] [ place. Remove-the used particulate filter from the
]
holder and place it in a small envelope giving care so } 7 that no particulate activity is lost. Replace the used } l [ h
w d SOP HP-14' Re v . _. 2 Page 2 of 2 Appr'd d* f Date 11/29/94 ; filter with a new, numbered filter, placing it rough -) side up on the holder. ) 3.4 Remove the charcoal (iodine) filter holder from its ] housing. Place the iodine monitor standard (Ba-133) in ] , its place. Remove the used charcoal filter ~from the ] holder and place it in a small plastic bag. Replace the ) used* filter with a new, numbered charcoal filter, ) placing it with the arrow on the side.of the filter ] : pointing into the holder. ] 3.5 When the particulate and iodine meter readings no longer ] ' seem to be increasing, call the control room for ] recorder readings. Compare these values'to the' values ] . from the previous weeks. If they are not within twenty ] > percent, inform the Manager of Health Physics. ] [ 3.6 Remove the particulate and iodine monitor standards and ) , replace them with their respective filter holders. ) j 3.7 Remove the plug to the gas monitor chamber and replace ) it with the gas monitor standard (Cs-137) . While the ] , i meter value is levelling out, determine the iodine high ) voltage using the volt meter. Compare this voltage to ) , the previous week's, inform the Manager of Health ) Physics if it has changed significantly. ) 3.8 Call the control room for the gas recorder reading. ) Compare this value to previous weeks. If it is not ) within twenty percent, inform the Manager of Health ] Physics. Remove the gas monitor stand'ard and replace ] the plug for the gas monitor chamber. J. 3.9 Inform the control room that you are going to turn the ) ; pump back on. Check the flow rate, it should be close ) , to the same value it was when the previous week's filter ) : was started, and must be between 4.0 and 6.0 cfm. If ) the flow seems too high, turn the pump off again and ) a check to make sure the particulate filter is secure in ) its holder. Record the time the pump was turned on and
)
the flow rate. Inform the operators that you are ] finished changing stack filters. ) 3.10 Proceed with the Analysis of Particulate and Charcoal ) Stack Filters. ]
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-sop MP-17 l
. I Rev. 4 Page 1 of 3~ l Appr' d e3 h M57 -
.Date 5/31/94 H-3 Air Samples
. l 1.0 POLTCY An air sample measuring tritium levels in the containment building will be taken daily on normal working. days or more often as. may be deemed necessary. ]
2.0 PURPOSE , Ensure airborne tritium levels in containment building remain below regulatory limits. ] 3.0 EOUTPMENT 3.1 Gelman bubbler system or equivalent ] 1 ml pipette Scintillation vials-Searle Delta 300 scintillation system or equivalent - Sample Bottle - (> 250 ml)
' 250 ml graduated cylinder Scintillation cocktail Approved H-3 Standard ,
4.0 PROCEDURE i 4.1 Place 250 ml distilled water in bubbler, secure top of , bubbler. , t 4.2. Turn on air pump noting exact time. i 4.3 Check air flow. q 4.4 If necessary adjust air flow with black knobs to obtain . . _. air flow of three (3) liters per minute. -) -l 4.5 Allow to run for 60 to 120 minutes. 4.6 Secure air pump noting exact time. , 4.7 Collect 250 m1 tritiated water. l 4.8 Add one (1) m1 sample to 10 m1 liquid scintillation cocktail in scintillation vial. i t
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l SOP HP-17 . Rev. 4 Page 2 of 3 : sjI vr D fW 5 f-Appr' d Date 5/31/94 l
'4iOL 2ROCEDURE (continued) 4.9 Swirl to mix until white precipitate dissolves.
4,10 Consecutively count sample mixture, prepared standard, t and prepared black (for background counts) on Searle Delta 300 Liquid Scintillation System, oor equivalent. 4.11 Delta 300 settings: A. " Power" - on B. "All samples" - green C. " CPM" - white D. "ESR" - white E. Time knob - 10 minutes F 2 Sigma Knob .25% G. Module 1 inserted (Caution--do not disturb if cour. ting of another sample is in progress.) , 5.0 CALCULATION Sample count - blank + l standard count - blank count X standard activity in pCi/cc X ] 250 (liquid sample volume in ml) + ! air volume (3000 ml/ min X number of minutes sample ran) +
.9 (efficiency) = pCi/cc H-3 in air )
Example: sample count 130 CPM , standard count 1450 CPM . blank count 30 CPM i time sample run 60 minutes I ve n , ,-
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.Rev. '4 Page 3 of 3
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' Appr' d r 10- 'd S/ ' -
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.l Date 5/31/94 .i i
5.0' catcDLATION '(continued) .) 1 I x (1. 64 x 10~3) x'(250) +~ (1.8 x 10'} + (. 9) -' 61420' ,
. - 1. 8 x 10-1 Ci/cc 3 Note: 1. 64 x 10-3 is and example of and H-3 standard >
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SOP MP-29 . Rev. 3 Page 1 of 6 Appr' d . -- IEY~ Date 8/12/94 ' 1 j ShipmentEof Radioactive Material, LSA' Waste 1.'O Purrese and S c,coe $ 1.1 This procedure establishes the requisements.fer. making- -) l exclusive use shipments of Low Specific Activity ) -;
)
radioactive waste. l 1.2 Individual responsible for making the waste shipment J i must have documented training meeting the requirements ) of 49 CFR 172 Subpart H. .)
] l 1.3 Person responsible for this waste shipment .) i t
l Date of this waste shipment . } 1.4 i procedure ) 2.0 i
]
2.1 Prerequisites. Notify MU Enviren= ental Health and Safety of the- .) i A. }- Radioactive Waste Shipment. t
- 3. Material must not exceed the limits for' a DOT Type-- A ) ;
) l Quantity.
Material must meet the definitien of Radioactive ] f C. ] Material - Low Specific Activity.
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D. Obtain a current copy of the recipients license and ) ., ensure that they are authorized to' receive the ) l quantity and-form of radioactive' material included ) in the shipment. ] Determine.if any Licenses or Permits are necessary- ) l E. ) to transport waste through or into any states en ; route. If state specific permits / licenses are ) { necessary ensure that they are obtained and valid ) ! for the intended shipment. ) . l f i
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r._ , SOP MP-28 Rev. 3 Page 2 of 6 Appr' d MSY Date 8/12/c4 2.0 procedure
)
2.1 Prerecuisites (centinured)- ) F. If h Broker or Brokerage Service is utilized ensure ) that all necessary permits and licenses are ] possessed by the 3roker. Ensure that the ) permits / licenses are valid and that the broker is ) authorized to utilire them. ] 2.2 Packace celection and tcadine: ) A. Radioactive - LSA materials may be shipped exclusive ] use in strong tight containers (STC's). These ] containers must not leak radioactive material under ) conditions normally incident to transportation. ) Initia111ng en this space indicates that the package ) has been evaluated by MURR and that MURR has ] determined that it meets the definition of a strong ) tight container. )
- 3. Load the radioactive material into the strong tight )
container. Survey the material as it is loaded to ) i ensure that package radiation levels will remain ) below the limits specified in 49 CFR 173.441. These ) limits specify that a package loaded in an exclusive ) use closed transport vehicle may exhibit a surface ) , radiation level of 1000 mrem /hr provided the ] folicwing conditions are met. The dose rate on the ) external surfaces of the vehicle may not exceed 200- ) , mrem /hr. The dose rate at 2 m from the outer ) ' lateral surfaces of the vehicle may net exceed 10 ) mrem /hr. The dose rate in any normally occupied ) region of the vehicle may not exceed 2 mrem /hr ) unless you have a private carrier with the exposed ) personnel wearing radiation dosimetry devices and ) the carrier operates under provisions of a State or ) Federally regulated radiation protection program. ) 1 If the package is leaded onto an exclusive use open ] top vehicle then the package may exhibit a surface ) radiation level of only 200 mrem /hr. The other dose ) rate limits in the previous paragraph continue to ] apply. )
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SOP MPkII 3 Page' 3 ef 6 Rev. Appr' d_ - I'n+b v[-T. p 9/12/94'
.Date .
)
_ 2;0' Precedure
).
2.2- Packaee 'S ele ct ion and Leadino (continuedi:
.)'
C. Ensure that the material'is biccked and braced orhat ]- ;
.ctherwise secured the lading will'not within the package to ensure tshift under) cenditions n
,CA ] l incident to transportation.
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D. C1cse the package using an apprcpriate closure ) device. ) QA no damage. .) E. Visually inspect package to ensure that Ensure the ) has occurred during loading evolutions. ) package still meets the requirements of a Strong ) Tight Container.
)
2.3 Packaen surveu:
)
A. Perform a contamination-survey on the package. -) contamination levels en the external surfaces cf the' ) package should be less than 6600' dpm/300 cm2 Beta / J-Gamma and less than 660 dpm/200 cm2 Alpha.
).
B. Perform a radiation level survey en a11' sides, ) including the top and bottom of the package. .) External radiation levels must comply with 49 CFR .
)
173.441. These limits specify that a package loaded CA
)
in an exclusive use closed transport vehicle may. J. ) exhibit a surface radiation level of 1000 mrem /hr d
).
provided the following conditions are met. .The dose ) rate en the external surfaces of the vehicle may.not ) exceed 200 mrem /hr. The-dose rats at-2 m from the ) outer lateral surfaces of the vehicle may not exceed ) 10 mrem /hr. The~ dose rate in any normally cccupied ] region of the vehicle may not' exceed 2 mrem /hr l' unless you have a private carrier with the exposed )~ personnel wearing radiation dosimetry devices and ) the carrier operates'under provisions of a State or ) Federally regulated radiation protection program.
i k' * -' L . SOP MP-28
" Rev. 3 Page 4 of 6 Appr'd Nm j Date 9/12/94 2.0 Procedure. ]
2.3 Packace survev fcentinued)- ) If 'he t package is loaded onto an. exclusive use open ] ; top vehicle then the package may: exhibit a surfaca' ] radiation level of only 200 mrem /hr. The other dose ] rate limits in the previous paragraph continue to ) apply. ] Document this survey on a MURR survey form. Measure ) the Transport Index (TI) of the package. ] ' 2.4 Packace Markine and Labelinet ) . A. Package shall be marked as " Radioactive LSA". .The 3 packages are excepted from all specification
)
labelling. ) ; B. Packages should have gross weight marked on the ) container. ) i 2.5 Leadine the Packace en to the convevance: ) r A. Package shall be loaded onto the vehicle by the 3 consignor. }- 1 B. Package shall be braced on the vehicle to prevent ] ; shifting during normal transportation conditions. ) C. There shall be no loose radioactive' material in.the ~ ) conveyance. ] D. Perform a vehicle Radiation Survey. The dose rate 3 on the external surfaces of the vehicle may not .) QA exceed 200 mrem /hr. The dose rate at 2 m from the ] outer lateral surfaces of the vehicle may not exceed ) l The dose rate in'any normally occupied .] 10 mrem /hr. region of the vehicle may not exceed 2 mrem /hr ) ' unless you have a private carrier with the exposed ) personnel wearing radiation dosimetry devices and ) ' the carrier operating under provisions of a State or ) Federally regulated radiation protection program. J' a f n
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'Rev. 3 Page: 5 ef 6 - ' Appr.' d' bnsE - ! ?
- Date B/12/94 1
P '2 0 - Procedure .) l t Leadine the Packaee~ en' re the cenvevance 'teentinued). 2.5 J' I. 'Per' form'a vehicle centaminatien survey. . J' , l Contamination lev'els on the vehicle-shuld be less ]
- than 660. dpm/300 cm2 Beta / Gamma and less than 66 )~
dpm/300 cm2 Alpha. ) .; t. I 2.6 Placard the Vehicle' ) l A. Transport vehicle'must bear the Radioactive Placards ] on all four sides. ] l i
.i 2.7 Shineine Pacers?
) l 1
A. Prepare a bill of lading and have it reviewed by.a ] i Certified Shipper. ) j D Certified Shippers Initials. ] l
- 3. The following reports shall accompany a11 shipments: ) !
Radioactive Shipment Manifest (RSM), Vehicle )~ j Radiation Survey, Bill of Lading, Emergency ) ! Response Guide and Exclusive Use Instructions. ) , r i
'2.8 shierent Release 3 A. Notify the-consignee that the radioactive material. ) l shipment is.taking place. This. notification may be ') ':
made by telephone call or by PAX. ] l Shipment approved for release by: ); f l 3: l Signature / Date l' j i B. Package released to carrier. ] l i i l
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i t SOP MP-2B ,
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Rev. 3 Page: 6 ~ef 6 , Appr'd b ,.. I
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Date 'B/12/94 t- : l
.2.0 Precedure icentinued) j j 2.9 'rmereenev Response-information- ;). :
A. Deliver a ecpy of the Bill of Lading, RSM and .)- Emergency Response Guide to the Control Room- .] Emergency Response Book. )=
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l) : SOP MP-35 Rev. 1 Pag 1 of 3 Appr' d _
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Date- 5/31/94 ' BEAMPORT AREA ACCESS' 1.0 POLICY i Unescorted entry'into the beamport area shall be limited to those individuals approved for access to.the area. All othe I
. individuals entering the beamport area shall be escorted by individuals with approved access. !
, 2.0 PURPOSE The purpose of controlling access to the beamport area is .to ensure compliance with 10 CFR 20.1601: " Control of access to ) , high radiation areas." ) ! 3.0 DEFINITIONS 3.1 Authorized Individual means any individual who is identified as having need of access to the beamport area, and who has successfully completed training and been approved for unescorted access. -; 3.2 Beamport Area is defined as that area around the ' biological shielding controlled by fencing'with key ECCess. L 3.3 High Radiation Area means an area, accessible to ) e individuals, in which radiation levels'could result in ) an individual receiving a dose equivalent in excess of ) , 0.1 rem (1 mSv) in 1 hour at 30 centimeters from the ) ; radiation source or from any surface that the radiation ) ' penetrates. ) 3.4 Radiation area means an area, accessible to ] l' ' individuals, in which radiation levels could result in ] an individual receiving a dose equivalent in excess of 1 ; 0.005 rem (0.05 mSv) in 1 hour at 30 centimeters from- ) .; the radiation source or from any surface that the ) -; radiation penetrates. 3 ( 4.0 RESPONSIBILITIES 4.1 Access Control A. Limited to authorized individuals. l l 0
SOP. MP-35' i t s I Rev. 1 Page 2 of 3 Appr'd - L f1 d~~'e 4J/ c Date 5/31/94 4.1 Access-Control (continued). . B.. Guests approved by Health Physics prior to escorted entry by an authorized individual. C. Access-control required during reactor operation. 4 D. List of authorized individuals' maintained at each access point. E. Authorized individuals responsible for ensuring positive control of each entry. 4.2 Training A. Initial request made to Health Physics by sponsor to complete training of individual to be authorized. B. Successful completion of training and approval for individual to be authorized as per TRAINING 2:
" General Information for Beamport Area Access -
Radiation Safety." _ 4.3 Door Control-A. During reactor operation, doors shall remain locked except during periods when access to the area is required, with positive control over each entry. B. During reactor shutdown, doors may be opened to individuals with containment access unless special maintenance procedures warrant limited access. C. Reactor Operations will ensure doors are closed prior to reactor startup. 4.4 Posting' A. Entry points to the beamport area shall be posted as per 10 CFR 20.1902 (b) with the phrase, "in the ) i' beam", added. B. High radiation areas shall be limited to in the neutron beams during normal operation.
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v j SOP' MP-35 , Rev. 1 Page 3 of"3 ! Appr' d I4 l u i Date 5/31/94 [
. 4.4 Posting (continued) t C. !
Neutron beams accessible to-personnel;shall.be conspicuously- marked with yellow plastic streamers. . 4.5- Radiation Surveys ,
.A. Beamport. area shall be included-in the monthly ,
survey of' the beamport floor performed by Health Physics B. Copies ofsthe' monthly area surveys are posted on the i beamport floor bulletin board and should be reviewed by_the authorized individuals. 4 C. Survey instruments'are available for authorized. l individuals to make radiation measurements. 1 D. Changes or movement of.the physical' arrangement of 1 the instruments, beam stops, and shielding lshallLbe. done-in cooperation with Health Physics;to monitor.
~
for changes in dose rates or contamination. 4 E. Items removed from the beamport area suspected to be '! activated and/or contaminated shall be monitored-by , Health Physics prior.to being released or stored. .r 1;
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f p - , p.< ' s SCP 'MP-39 b: o; Rev. _ L A? age 1 of 6 Appr ' r'. =f 'NMM 4 Cate 9/12/94 L t' l Shipment of Radicactive Materi!1 NCS Waste 1.0 Purocre and sceee t b 1.1 This procedure establishes the requirements for making' n exclusive use shipments of radicactive material, n.o.s., waste. I-1.2 Individual responsible for making the waste shipment must have documented training meeting the requirements-of 4 9 CFR 172 Subpart H. 1.3 Person responsible for this waste shipment 1.4 Date of this waste shipment . l.. 2.0 Precedure 2.1 Prerecuisitest j A. Notify MU Environmental Health and Safety cf the Radioactive Waste Shipment. B. Material must not exceed the limits for a DOT Type J. Quantity. Type B quantities must be covered by an l approved Quality Assurance Program Procedure. C. Obtain a current copy of the recipients license and i ensure that they are authorized to receive the quantity and form of ' radioactive material included j in the shipment. I l 1 D. Determine if any Licenses or Permits-are necessary ; to transport waste through or into any states en route. If state specific permits / licenses are necessary ensure that they are cbtained and valid for the intended shipment.
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I SOP MP-39 Rev. 1 Page 2 of 6 Appr' d f5 Date 9/12/94 , 12.0~ Procedure 2.1 Prerecuisites (continuedi-E. If h Broker or Brokerage Service is. utilized ensure that all.necessary permitsLand licenses are possessed by the Broker. Ensure that the permits / licenses are valid and that the broker.is authorized to utilize them. 2.2 Packace selection and Leadine: ; A. Type A Quantities of Radioactive material, n.o.s. may be shipped in DOT Specification 7A packaging. The performance ~and environmental testing or , evaluation shall meet DOT 7A requirements. Initia111ng on this space indicates that the package has been evaluated by MURR and that MURR has determined that it meets the definition of a DOT Specification 7A container. 3, Load the radioactive material into the container. Survey the material as it is loaded to ensure that package radiation levels will remain below the .! limits specified in 49 CFR 173.441. These limits : specify that a package loaded in an exclusive use closed transport vehicle may exhibit a surface : radiation level;of 1000 mrem /hr provided the l following conditions are met. The dose rate on the external surfaces of the vehicle may not exceed 200 mrem /hr. The dose rate at 2 m from the outer lateral surfaces of the vehicle may not exceed 10 mrem /hr. The dose rate in any normally occupied i region of the vehicle may not exceed 2 mrem /hr unless you have a private carrier.with the exposed personnel wearing radiation dosimetry devices and the carrier operates under provisions of a State or Federally regulated radiation protection program. 1 If the package is' loaded onto an exclusive use open top vehicle then the package may exhibit a surface j radiation level of only 200 mrem /hr. The other dose i rate limits in the previous paragraph continue to apply.
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'^ - SOP HP-39 f t '
- Rev. 1 Page- 3 of'6 Appr'd #6 f& '
a
' ' - Date s'/12/94 __.
t
- 0.0 . Proemdure 2.2 Packaen selection ' and Leadine teentinuedt: f sc C. Ensure L that the' material is blocked'and braced or, j l
otherwise. secured within the. package to ensure
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that the lading will not, shift-_under' conditions normally incident to transportation. D. Close the package using an appropriate closure , device. c k OA E. Visually inspect package to ensure.that no damage t e has occurred during. loading evolutions. 1 2.3 Packaee surveve Perform a contamination surveylon the package. _ . j A. ;
-Contamination levels on the external surfaces.of the "
. package. should be .less than 660_ dpm/300 cm2 - l Beta / Gamma and less than 66 dpm/300 cm2 Alpha.
1 B. Perform a radiation level survey.on'all sides, i including the top and bottom of the' package. i CA External radiation levels must. comply:with 49 CFR , !
.j 173.441. These limits specify thatta:packageuloaded:
in an exclusive use closed transport vehicle-may. : exhibit a surface. radiation level'of 1000 mrem /hr ' provided the.following conditions are met. nThe dose ~ rate on the- external surfaces .of the vehicle may not - exceed 200 mrem /hr. The dose' rate at 2 m from the outerslateral surfacesLof the vehicle may not exceed-10 mrem /hr'.- The. dose rate in any.normally occupied ~:' region of.the vehicle may not. exceed 2-mrem /hr' unless you have a private carrierfwith-the exposed- i
.J personnel-wearing radiation dosimetry devices and the carrier operates under provisions of'a.Stateior. 3 r-aFederally regulated radiation protection' program, j i
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SOP MP-39 Rev. 1 Page 4 of 6 , App r' d --- FM Date 9/12/94
<2 . 0 Procedure 2.3 Packaee survev fcontinued):
Ifkhepackage'is'leadedontoan.exclusiveuseopen top vehicle then the package may exhibit a surface ' radiation level of only 200 mrem /hr. The other dose rate limits in the previous paragraph continue to apply. Document this survey on a MURR survey form. Measure the Transport Index (TI) cf the package. 2.4 Packace Markine and Labeline: j A. Package shall be labelled in accordance with 49 CFR 172.403. B. Package shall be marked with the container certification (i.e. USA DOT 7A Type A). C *. ~ Packages shall have gross weight marked on the l container. D. Packages shall be marked with the proper shipping name and identification . (UN number) . 2.5 Leadino the Packmoe on to the conveyance: A. Package shall be leaded onto the vehicle by the- ; consignor. i B. Package shall be braced on the vehicle to prevent shifting during normal t:ansportation conditions. C. There shall be no loose radioactive material in the j conveyance.
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SOP' HP-39 ] Rev. I Pa e 5 ef 6-
- Appr' d heb j o
Date 9/12/94 i I
, _ 2.0- Procedure Leadine the Packaec en to the convevance-(centinuedi-2.5:
D. Per' form a vehicle radiation survey. ;The dose'rateL ' on the external surfaces of~the. vehicle may z QA not exceed 200 mrem /hr. 'The dose rate at 2'm from/ the outer lateral surfaces of the vehicle.may.not exceed 10 mrem /hr. The dose rate in any.normally : occupied region of the vehicle may not exceed 2 mrem /hr unless you have a private carrier with the' i exposed personnel wearing radiation dosimetry .i devices.and the carrier operating under provisions
~
of a: State or Federally regulated radiation. I t protection program,
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Document this survey on a MURR survey form. Be'sure to include the dose rate at 2m and the cab dose rate ( on survey form Perform a vehicle centamination survey. b E. a Contamination levels.on the vehicle should be less j than 660. dpm/300 cm2 Beta / Gamma and less than 66 dpm/300 cm2 Alpha ;;{ 2.6 Placard the Vehicle A. Transport vehicle must bear the Radioactive. Placards [ on.all four sides if the package required a Yellow ; c III. label. 2.7' shiccine Pacerst i A. Prepare a bill of lading and,have it reviewed by.a j' L L Certified Shipper. i " Certified Shippers Initials. B. The following reports shall accompany all shipments: ]
~ Radioactive ~ Shipment Manifest -(RSM) , Vehicle i i
Radiation Survey, Bill of Lading and Emergency ' Response Guide. Exclusive Use Instructions shall be provided to the driver if the load is shipped , i exclusive use. :
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' Appr' d b'n 6Y I
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Date- 8/12/94 L 2.0 Procedure (continued) ; 2,8 Shiement Felease t-A. Notify the-consignee that the radioactive material shipment is taking place. This not ification may be , made by telephone call or by FAX. . Shipment appreved for release by: L Signature / Date l B. Package released te carrier. . 2.1 Emercency Reseense Information ; A. Deliver a copy of the Bill of Lading, RSM and r Emergency Response Guide to the Control Room. Emergency Response Book. ;
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MURR SHIPPING PROCEDURES , q. MURR-SAS-00000 - Revision Number 1 RevisionDate: 9/27/94
- Pace Number -
4 of15 5 of15 i 6 of15 7 of15 ; Bof15 i S of15 ; 10 of15 1 11 of15 ! 12 of15 ; 13 of15 ; 14 of15 ,. i i ( j i i l 11-10 ) i I
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- MURR SAS4000 Service App!! cations Departmental Administretive: Shipping ;
2.0 SERVICE APPLICATIONS-SHIPPINC PRECAUTIONS AND LIMITATIONS 2.1 The non-fixed contamination on any external surface of the transfer cask, work tables, floors, 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 duc 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, follow directions on monitors and call Health Physics immediately. 2.3.2 After 5:00 P.M. or Weekends call the Control lioom 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. HP ob Date 27 Sept.1994 MURR-SAS-OOOOO page 4 of 15 Rev.n L SA.S d.
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p _.4- ! fy? > MURR-sAs.00000 ' Service Applica'tions Departmental Administrativ7.: Shipping j!
- 2.6 Use protective clothing: ' ~
b
- 1aboratory Coat . i w
- Rubber / latex Gloves !
- Safety Glasses or Face Shield. I l
' 2.7 l In the event of a broken vial or stuck sample,' the Reactor
- Services Engineer or Designee must be notified immediately to ;
resolve the problem. ; l 2.8 ' ' A package of radioactive material shall not be transported unless it is properly described, classed, marked., packaged and l labeled. i 2.9 'If the Radioactive Material exceeds any of the applicable limits of 49CFR or IATA Manual, the Reactor Services Engineer or i Designee must be notified immediately, .: 3
'2.9.1 . The Radioactive Material shall not leave MURR until the ;
problem has been resolved. ,I 2.10 in the event of a stuck capsule or broken vial, the Reactor .!
. Services Engineer or Designee must be notified immediately.
a, 2.11 Each container or cask used for the Shipment of Radioactive - Materials Shall be approved for use and shall conform to - l Department of Transportation (DOT) Specifications contained in 49CFR and International Air Transport Association (IATA). !
'i 2.11.1 , Certificates of Corapliance shall be maintained on file for cach container or cask. ^t 2.12 Applicable container specifications must be specified by t purchase order, j i
2.12.1 Purchase orders must stipulate that all containers to be used ' ! for shipment of Radioactive Materials bear a marking or label to show conformance to the applicable Specification, j! e.g., TYPE A. l 2.13 Prior to any shipment of Radioactive Material, it shall be ' determined that the consignee (receiver) is licensed to ! receive that material. 2.14 A package of Radioactive Material shall not be transported . unless it is properly described, classed, marked, packaged and labeled. i l r .! t f HP M Date 27 Sept.1994 MURR SAS-00000 page 5 of I5 Rev.QL SA M i
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. Service Applicadons Departmental Administradve: Shipping ' !
. MURR SAS40000 l 2.15. : If the Radioactive Material eveawin any of the applicable -
limits of 49CFR or IATA Manual, the Reactor Services ' : E'
~
' Engineer or designee must be notified immediately. . -j b
c' 2.15.1 The Radioactive Material'shall not leave MURR until the .6
" problem has been resolved. : $+
2.16, . Air freight shipments of " Excepted Qpantities" and " Medical" '
~ '
V- Radioactive Materials may be consigned to Passenger Aircraft { A- in accordance to 49CFR. ~ 2.16.1 All other Radioactive Material shipments by Air shall be - l consigned.to " Cargo Only" Air Transportation. ? l
~ 2.17 Air Freight Shipment quantity limits shall be in accordance j with the Requirements of 49CFR and IATA Regulations.~
i The non-fixed contamination on any external surface of any , i 2.18 package shall be kept as low as practical and, under normal [ conditions of transport, must not exceed the levels specified in 49CFR and IATA Regulations.- -j y 2.18.1 The level of non-fixed Radioactive contamination may bc . determined by wiping an area of 300 square centimeters of. l the surface concerned with an absorbent material, using 1 L i moderate pressure,'and measuring the activity on the wiping
~
l- material. 2,19 Radioactive Materials having other hazardous characteristics 1 ' shall be allocated packing groups I, II, or III, as appropriate, by application of the grouping criteria in accordance with-49CFR and IATA Regulations. ; L 2.20 Ensure that all beta-gamma dose rate survey equipment and - 1 L meter stick calibration stickers have not passed the , calibration due date prior to use. t 2.21 The requireme 1ts for each package containing fissile material shall cumply in accordance with 49CFR. , 7 i , i f I I I
'I i
r I i i HP d Date 27 Sept, t994 MURR-SAS-OOOOO page 6 of 15 i Rev.Q1 SA M i i f
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- MURR-SAS 00000 Service Applications Departmental Administrative: Shipping
-- ' 2.22 - Shipping activity: The Irradiation Project Specialist or his .
. designee is responsible for the activity listed on all shipments i and should report all radionuclides to the 90th percentile of-
- activity at the time of shipment. ~
2.22.1 .-In the absence of the Irradiation Project Specialist, the-following individuals are qualified to approve shipment activities;
- Processing Project Specialist
- Service Applications Engineer
- _ Manager Health Physics
- Project Specialist of Radio pharmaceuticals
-2.22.2 The Irradiation Project Specialist may designate a list of samples by company and target, whose activity may be derived by means of Capintec or equivalent measurement.
2.22.3 The Irradiation Project Specialist may designate a list of individuals who are authorized to approve shipment activity for secondary samples. HP Date 27 Sept.1994 MURR-SASN page 7 of IS Rev. QL_ SA
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;w ; MURR-SAS40000 yService Applications Departmental Administrative: Shipping i
[ 3.0 C5:RVICE APPIYATIONS CHIPPING: DEFINITIONS ~
~:
, ' 3.1 i R The maximum activity of " SPECIAL FORM" Radioactive g.
material permitted in a Type A package. i
,- 3.1.1 - Values of Al for most Radionuclides are given in 49CFR and ,
IATA Regulations.
" t E The maximum activity of Radioactive material, other than L fm 3.2 -
"Special Form" Radioactive material, permitted in type A [
~
package. ,
. Values of A2 for most Radionuclides are given in Tables of f 3.2.1 :
49CFR and IATA Regulations. , l
^
3.3 Activitv
Is a measure of the' quantity of radioactivity emitted.. r
. by a radioisotope and is used to determine the amount of radioactive material which may be transported in various. jp types of packaging.
3.4 Becoueret iBa): Is the standard unit of measure for the . .l Radioactivity of a Radionuclide used in'IATA. Dangerous Goods Regulations. One Bq equals one decay per second. 3.4.1 Gionherniserel (GBa): One GBq - 1,000,000,000 Bq or IE9 Bq. i 3.4.2 Ternheeniieral (TBa) : One' TBq - 1,000,000,000,000 Bq or IE12 -Bq. ~I qi 3.4.3 The Bq replaces the older unit for activity, the Curie (Cl). , 3.4.4- One Ci is equal to 37 GBq._ 3.5 ' Conversion Factorr Table shows conversion factors-to four significant figures. . L To convert To Multiolv hv: j 3.5.1 i Cl GBq 37.00 27.03 i TBq C1
]
' 3.6 Erneriment: Is any device or material which is exposed to :
l , significant radiation from the reactor and is not a normal part L of the reactor or any operation designed to measure or [ l monitor reactor characteristics or parameters. .j l l L ; o , i
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MURR-SAS-00000 page 8 of IS Rev.Q,1_ sad 11P - Date 27 Sept.1994 ; f
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. y MURR-$AS 00000 Service Applications Departmental Administr'.tiv;: Shipping 3.7 External Contamination: Is the non fixed Radioactive contamination on any external surface of any package.
It must be kept as low as practical and, under normal condition of transport, shall not exceed the levels specified in 49CFR and IATA Regulations. 3.8 Externally contaminated objects of non-radioactive material 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 i 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. 3.9 Fissile material: Means any material consisting of or ) containing one or more fissile Radionuclides. Fissile materials are plutonium-238, plutonium-239, plutonium-241, uranium-l ' 233, and uranium-235. Neither natural nor depleted uranium are fissile material. Fissile materials are classified according to the controls to provide nuclear criticality safety during transportation, as provided in 49CFR. 3.10 Host Can: Is a multi-carrier of capsules, with spacers, if l required, which may contain capsules from: } l I
- Prior Host cans previously irradiated,
,* Storage which have been previously irradiated and placed in Storage or,
- New capsules to be irradiated.
3.11 Host Cnnsule Chance Sheet: This term is used in the Description Section of the Samnle Shinment Information Sheet. It is an interchangeable title for the Existino Loadino Sheet. ( l [ V HP Y Date 27 Sept.1994 MURR-SAS-00000 page 9 of 15 Rev.01_ SA M $.
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i v *JMURR.SAS 00000 ! Service Applications Departmental AdministrClive: Shipping 1
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- v. 3.12; HoL4eu:' A sealed, shielded controlled area to process J radioactive materials containing: ,
(
- Mant'pulators to process radioactive materials.
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- A crane to move heavy objects.
I
- A radioactive waste storage area.
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- Negative air pressure which exhausts to the D Reactor Air Plenum. /
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- A drain for liquid hot waste.
- Can opener.
' :
- A welding unit.
3.13 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. 3.14 tow Snecific Activity Material (tSA) means any of the following: Uranium or thorium ores and physical or chemical . -l 3.14.1
. concentrates ofh t ose ores.
3.14.2- Unirradiated natural or depleted uranium or unirradiated natural thorium. 3.14.3- Tritium oxide in aqueous solutions provided the concentration-does not exceed 5.0 millicuries per milliliter.;.
.9.14.4 Material in which the radioactivity is essentially uniformly.
distributed and in which the estimated average concentration of contents does exceed: , 3.14.4.1 0.0001 millicurie per gram t,f Radionuclides for which the A2 quantity is not more than .05 curie; 3.14.4.2 0.005 millicurie per gram of Radionuclides for which the A2 is more than .05 curie, but not more than 1 curie; or 3.14.4.3 0.3 millicurie per gram of Radionuclides for which the A2 quantity is more than 1 curie. HP d Date 27 Sept.1994 MURR-SAS-00000 page iO of I5 Rev.Q L SA M .
1 a .- t : s' ' . 4 : MURR-SAS-00000 Service Applications Departmental Administrctive: Shipping 3.15 MCA: Multi-Channel Analyzer 3.16 Non-fixed R=dinactive Material: Radioactive contamination that can be removed from a surface by wiping with a dry . smear. Normal Form Radioactive Materf ah Radioactive Material which l 3.17 has not been Qualified as " Special Form" Radioactive Material. 3.18 Observer /Insoector: An independent Verifier who observes ; critical points of the processing steps and documents the performance of these steps by legibly initiating the steps as they are performed. 3.19 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. j 3.20 Primarv Hazard inbel: Identifies governing hazard for a 1 package. Radioactivity is normally the governing hazard for l packages shipped by MURR. - Radioactive material shall be labeled in accordance with the guidelines of the following categories: , 3.20.1 White ! - The maximum radiation level at any point on the ' external surface is 0.5 mrem /hr. The Transport index is not applicable. 3.20.2 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. 3.20.3 Yellow 111 - 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. i 3.20.3.1 Packages with contact dose rates greater than 200 mrem /hr or with a TI greater than 10 shall be shipped as an Exclusive Use Shipment 3.20.4 Packages and overpacks shall be assigned to Category White I, Yellow II, or Yellow III in accordance with 49CFR and IATA Dangerous Goods Regulations. 3.20.5 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 (1.imited Quantities). Rev. QL,, SA MM llP[ Date 27 Sept.1994 MURR SAS-00000 page 11 of 15 .
= MURR-SAS.00000 Se:vice Application's Departmental Administrative: Shipping 3.21 ' Primary Processed Limnles: Samples that have been under '
continuous SAS Control after removal from reactor. 3.22 Radioactive Contents: The radioactive material together with any contaminated solids, liquids and gases within the package. ' 3.23 R=dinmetive materinh 3.23.1 DD.T.: Any material having a snecific activity greater than 0.002 micro curies per gram (uCi/g). 3.23.2 MB.C: " Specific' activity" of a radionuclide, means the activity of the radionuclide per unit mass of that nuclide. . . The specific activity of a material in which the radionuclide is ' essentially uniformly distributed is the activity per unit mass of the material 3.24 Samole: Is a chemical or physical makeup of the target material or combination of target and encapsulation. i 3.25 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. 3.25.1 " 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. 3.2S.1.1 The stored position is recorded on the Sample Run Sheet. 3.25.1.2 The Flux Trap, H1, and BPLS Book consists of the following sections: Flux Tray Loading Sheet, Tube A. Tube B, Tube C, i H1, BPLS (Bulk Pool Lead Shield), Bisco, Storage, Reuter > i I Stokes, and Samples in use. 3.2S.1.3 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 I), Y (Yellow, also known as H), G (Green also know as G), Bin Storage, and Sample Storage. I. l Date 27 Sept.1994 MURR-SAS-00000 page 12 of 15 Rev.Q1 SA M HP
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Mb [NURR.SAS40000' Service 'Applicctions Departmental Administrativz: Shipping ~ 'l r . . _ i
/ lF 3.261 . heaadarv Prnemenad Camnime: Samples that are directlyf '
i
- submitted for shipping by RPG, NAP or HP.:
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/ 3.27 TChall Must shnuid-1
,? 3.27.1' Shalk Regulatory Commitment to Code'of Regulations,- 10CFR,49CFR and IATA Dangerous Goods Regulations. ! r i 3.27.2 Mug: MURR Internal Commitment to 10CFR,49CFR and l IATA Regulations. ! W 3.27.3 Should: Should be accomplished; not required. 3.28 Shinnine container: To contain the sample (s) during transport: i
' Can be a lead pig (2 LB. to 30 LB), or a depleted uranium shield.
3.29 Snmeer: Used to take up space in the host can to minimize capsule movement. 4 3.30 Snecial Form Radioactive Material: Radioactive Material is either an in-dispersible solid Radioactive Material or a sealed . capsule containing Radioactive Material. ..] 3.30.1 Special Form Radioactive Material shall meet the ~ requirements of 49CFR and IATA Regulations. 3.30.1.1 If it is in a sealed capsule, that capsule shall be so constructed ' .i that it can only be opened by destroying. 3.30.1.2 The Special Form Radioactive Material shall have at least one dimension not less than S mm.
-t 3.30.1.3 The Special Form design shall have received unilateral approval.
3.31 . Snecific ' Activitv: The activity of the radionuclide per-unit weight of that nuclide. 3.32 Transfer c ek. Used to transport samples within the facility. ;
-l 3.32.1 Orange Roll Up cask is included as a transfer cask.
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I i 1 Rev.D.l_.,SA' M HP d Date 27 Sept.1994 MURR-SASN page 13 of 15 i
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, I Service Applications Departmental Administrative: Shipping
-j MURR SAS40000
. 3.33 - Trantnort Inder Number iTI). pudinactive Material Ontv: The. "
dimensionless number (rounded up to the first decimal place) L - placed on the label of a package to designate the degree of. ' control to be exercised by the carrier during transportation. t 3.33.1- The Tl number is determined by 49CFR and IATA > Regulations.- 3.33.2 The transport index is determined as follows: , 3.33.2.1' The number expressing the maximum radiation levelin , millirem per hour at one meter (3.3 feet) from the external surface of the packaging; or, 3.33.2.2 For fissile class 11 packages or packages in a fissile III . , 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.
3.34 Tvoe A Packnoino A type "A" package must not contain activities greater than the following:
'3.34.1 For "Special Form" Radioactive Material the value of Al is listed in Tables of 49CFR and IATA Regulations.
3.34.2 For other Radioactive Material the value'of A2 is listed in - ' Tables of 49CFR and IATA Regulations. 3.35 Tvoe B Packmaine* 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, i s
-- Date 27 Sept.1994 MURR-SAS-00000 page 14 of 15 Rev.0.1_ SA_Ab HP ,
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i MURR SHIPPING PROCEDURES
- l MURR-SAS-00004 ;
I Revision Revision Page l Number Data Hughgg [ 2 -9/27/94 6 of 31 l 2 9/27/94 8 of 31 3 11/4/94 10 of 31 2 9/27/94 13 of 31 2 9/27/94' 14 of 31 2 9/27/94 15 of 31 2 9/27/94 16 of 31 2 9/27/94 17 of 31 2 9/27/94 18 of 31 2 9/27/94 19 of 31 ! 3 11/4/94 23 of 31 3' 11/4/94 25 of 31 2 9/27/94. 27 of 31 3 11/4/94 28 of 31 ! 2 9/27/94 30 of 31 ; 2 ' 9/27/94 31 of 31 3 11/4/94 MURR Model1000 Checksheet, pap 1 of 2 l 3 11/4/94 MURR Model 1000 Checksheet, page 2 of 2 ) 3 11/4/94 MURR Model 1100 Checksheet, page 1 of 2 ; 2 3 11/4/94 MURR Model 1100 Checksheet, page 2 of 2 3 11/4/94 MURR Model 1220 Checksheet, page 1 of 2 3 11/4/94 MURR Model 1220 Checksheet, page 2 of 2 { 3 11/4/94 MURR Model 1300 Checksheet, page 1 of 2 ! 3 11/4/94 MURR Model 1300 Checksheet, page 2 of 2 J CHea: Complete procedure is reissued with each revision, so all pertinent changes from each revision in 1994 have been copied from the latest revision. II-11 I
g+3 ,
~ ~ @o g MURR-SAS-00004 . Shipm:nt cf Radioactiva Materials -
2.7 ' Air Freight Shipment quantity limits'shall be in accordanci ' W(g 7 , i with the Requirenwnts of 49CPR 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
~
g' 149CFR and IATA Regulations. , 2.8.1 The level of non-fixed Radioactive contamination may be . . determined by wiping an area of 300 square centimeters of . s the surface concerned with an absorbent material, using moderate pressure, and measuring the activity on the. wiping . material. 2,9 Radioactive Materials having other hazardous characteristics shall be allocated packing groups I, II, or III, 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 accordance with 49CFR. I 2.12 Shipping activity: The Irradiation Section Leader or his .. designee is responsible for the activity listed on all shipments and should report all radionuclides to the 90th percentile of - activity at the time of shipment. In the absence of the Irradiation Section Leader, the I 2.12.1 following individuals are qualified to approve shipment
~
Activ.' ties; l .* Proce::ing Section leader
- Service Applications Engineer
- Manager Health Physics I
- Section leader of Radio pharmaceuticals 1 2.12.2 The Irradiation Section leader may designate a list of samples by company and target, whose activity may be derived by means of Capintee or equivalent measurement.
.I 2.12.3 The Irradiation Section Imader may designate a list of . ,
individuals who are authorized to approve shipment activity for measured secondary samples. - MURR-SAS-00004 page 6 of 31 Rev.03 SA HP d Date 04 Nov.1994 CONTROL CHECK SHEET USE PROCEDURE
ng ' ' q
- g s -l , " Shipment cf Radioactive Materials l
- e. MURR-SAS-00004 3.12- ' DOT- 12B40 boxes with the following information:
i 3.12.1- Label: ! USA DOT 7A Type A Radioactive Material Specification Certified by - i University of Missouri j Research Reactor Columbia, Mo. 65211 ; i 3.12.2 . label: Radioactive Material 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 All The maximum activity of " SPECIAI. FORM" Radioactive material permitted in a Type A package. -l 4.1.1 Values of Al for most Radionuclides are given in 49CFR and IATA Regulations. - 4.2 A2;The maximum activity of Radioactive material, other than
."Special Form" Radioactive material, permitted in type A i package. .;
4.2.1 Values of A2 for most Radionuclides are given in Tables of 49CFR and IATA Regulations, j 4.3 - Becouerel (Bo): 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 Gignbecauerel (GBo): 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). t One Ciis equal to 37 GBq. 4.3.3.1 } MURR-SAS-00004 page 8 of 31 Rev.03 SA M HP N Date 04 Nov.1994 CONTROLCHECK SHEET USE PROCEDURE
p ,, , ..ir.. o Shipment of Radioactive Materials . MURR-SAS-00004
'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 Material: Radioactive contamination that can be removed from a surface by wiping with a dry smear. 4.9 Normal Form Radioactive Materlah Radioactive Material which has not been Qpalified as " Special Form" Radioactive Material. 4.10 Primary Processed Samoles: Samples that have been under continuous SAS Control after removal from reactor. 4.11 secondarv Processed Samoles: Samples su'.,mitted for shipment 1 I by groups other than Service Applications. 4.12 Shionino Technician (Shionerlis defined to be any person in the Shipping Group: 4.12.1 Shipper, Trainee: Can neither Perform or Inspect a Task. 4.12.2 Shipper, Q alified: Is an individual who has completed the Required Documented Training to perform a specific Task. 4.12.3 Shipper, Certifled: Is Qualified to perform all aspects of Shipping as documented by Training. 4.13 Soecial Form Radioactive Material: Radioactive Materialis either an in-dispersible solid Radioactive Material or a sealed capsule containing Radioactive Material. 4.13.1 Special Form Radioactive Material shall meet the requirements of 49CFR and IATA Regulations. 4.13.1.1 If it is in a sealed capsule, that capsule shall be so constructed that it can only be opened by destroying. 4.13.1.2 The Special Form Radioactive Material shall have at least one dimension not less than S mm. . 4.13.1.3 The Special Form design shall have received unilateral approvat MURR-SAS-00004 page 10 of 31 Rev.03 SA M HP Date 04 Nov.1994 CONTROL CHECK SHEET USE PROCEDURE l
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4 i .~ MURR-SAS OOOO4 Shipment cf Radioactive Materials 4.20 PACKAGING PROFFDURE IIRFD FOR TEST OFRnMCATION'OF'IIRA DOT MtfRR Mevlet 1000 RhinnIna Container.
.4.20.1 Authorized contents for package identification of MURR 1000 -
is Solid Normal Form Type A Radioactive Material. 4.20.2 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 scaled 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 # 1 or #2 density modified bead packing inserts (MURR dwg. No.1180) 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 -
3M-355 or brown Safety Tape. 4.20.3 Packaging Procedure:
- Sample is placed in lead pig.
- 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 # 1 or #2 packing inserts with fiberboard endcaps. l
- The polystyrene is secured by four crossing Miller-Bevco 9 mm straps.
- The strapped polystyrene is placed in the Wunderlich fiberboard box.
6
- The box is secured by applying 3" Scotch brand tape type 3M-35E or brown Safety Tape to all seams.
i Date 04 Nov.1994 MURR-SAS-00004 page 13 of 31 Rev.03 SA _ HP CONTROL CHECK SHEET USE PROCEDURE
a J . o f MURR-SAS OOOO4 Shipment of Radioactive Materials 4.21 PACKACING PROrmIIRE TMm FOR TEST C+ximCAT10N'OF tit 4-
' DOT MifRR Mndal 1100 Chinnine enntainer. ,
- p. 5 4.21.1 . The authorized contents for package identification of MURR 1100 is Solid and Liquid Normal Form Type A Radioactive
. Material.
t 4.21.2 Description of Package:
- Sample contained in a Secondary containment. f
- Secondary containment is sealed by Bron 1" yellow vinyl tape or crimp seal. j e Kimpak # 64290-00 is used to absorb twice the liquid 1 contained.L l
- Shielding is a MURR lead pig # 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 polystyrene #1 or #2 j density modified bead packing inserts (MURR DWG. # 1180) with Wunderlich 15.5" x 13.5" x 0.188" fiberboard endcaps. l
- The polystyrene is strapped Miller-Bevco 9 mm strapping # 06MG0912998WH. l
- The polystyrene is inserted in a Wunderlich #40UN151313. l
- The Wunderlich box is sealed with 3" Scotch brand tape type 3M-355 or brown Safety Tape.
i I t l i i i l l HP Date 04 Nov.1994 MURR-SAS-OOOO4 page 14 of 31 Rev.03 SA CONTROL CHECK SHEET USE PROCEDURE i
~i
. Shipmentcf Radioactive Materials 7 MURR-SASN
~ 4,21.3 ' Packagias Procedure:
i
- Sample is placed in secondary containment. q
- The secondary containment is sealed by Bron 1" tape or - r 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.
i
- The Ellisco can is placed in two expanded polystyrene \
.i
#1 or # 2 packing inserts with fiberboard endcaps.
) r
- 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 tape type,3M-355 !
or brown Safety Tape to all seams. [ l ;
, j.
i i e i i J i MURR-SAS-00004 page 15 of 31 l Rev.03 SA S HP Date 04 Nov.1994 CONTROL CHECK SHEET USE PROCEDURE
o Shipment of Radioactive Materials '. M U R R-S N 4.22 PACKAGING PROrmIIRE URE FOR TEST < w i wiCATION 5F ORA DOT MITRR Mtviel 1220 Rhinnina enneminer. E 4.22.1 The authorized contents for package identification of MURR 1220 is Solid and I.iquid Form Type A Radioactive Material. 4.22.2 Description of Package:
- Sample contained in secondmy containment.
- Secondary containment is sealed by Bron 1" yellow vinyl tape or crimp seal.
- Shielding is a Mallinckrodt Screw Top white shipping pig No.2.
- The Mallinckrodt shipping pig No. 2 is sealed by Bron 1" yellow vinyl tape.
- Kimpak No. 64290-00 is used to absorb 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 or #2 density modified bead packing inserts (MURR DWG. No.1180) with Wunderlich 15.5" x 13.5" x 0.188" fiberboard endcaps.
- The polystyrene is strapped with Miller-Bevco 9mm strapping # 06MG0912998WH.
- The polystyrene is inserted in a Wunderlich box # 40UN151313.
- The Wunderlich box is sealed with 3" scotch brand tape type 3M-355 or brown Safety Tape.
l 1 MURR-SAS-00004 page 16 of 31 Rev.03 SA . / ). HP Date 04 Nov.1994 CONTROL CHECK SHEET USE PROCEDURE l i {
e.
~
MURR-SASM Shipment of Radioactive Materials
;. 4.22.3 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.
F
- The Icad 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 polystyrene #1 or #2 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 or brown Safety Tape to all seams.
L MURR-SAS-00004 page 17 of 31 Rev.03 SA M k HP M Date 04 Nov.1994 CONTROL CHECK SHFET USE PROCEDURE
e , l p
- MURR-SAS-00004 Shipment of Radioactive Materials .
n
' PACKAGING PROrmHRE INm FOR TITT nk i nHCATION 6F USA f 4.23 DOT MURR Mrwiel 1300 Rhinnine enntniner. l 4.23.1. The authorized contents for package identification of MURR .,
1300 is Solid and Liquid Normal Form Type A Radioactive : Material. ; 4.23.2 Description of Package:
- Sample is 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.
t
- The primary containment is an Ellisco round tearstrip bright tinplate 404 x 7" can.
- Ellisco can is inserted in two expanded polystyrene #1 or #2 ,
density modified bead packing inserts (MURR DWG. No.' 1180) 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 Wunderlich box # 40UN151313.
- The Wunderlich box is sealed with 3" Scotch tape type 3M-355 or brown Safety Tape.
l l l l l l l MURR-SAS-00004 page 18 of 31 Rev.03 SA M HP ' Date 04 Nov.1994 CONTROLCHECK SHEET USE PROCEDURE f l
1'I 1 t : 1 MURR-SASN - Shipment of Radioactive Materials
, 4.23.3 Packaging Procedure:
- Sample is placed in secondary containment.
- The secondary containment is sealed by Bron 1" yellow tape or crimp seat
- The secondary containment is sealed in the Blisco can with 1 sufficient Kimpak to absorb twice the liquid contained. i l
- The Blisco can is placed in two' expanded polystyrene #1 or #2 1
packing inserts with fiberboard endcaps.
- The polystyrene is secured by four crossing Miller 9mm straps.
i
- The strapped polystyrene is placed in the Wunderlich fiberboard box.
- The box is secured by applying 3" Scotch brand tape type 3M 355 or brown Safety Tape to all seams.
Rev.03 SA M HP Date 04 Nov.1994 MURR-SAS-00004 page 19 of 31 CONTROL CHECK SHEET USE PROCEDURE i
i. l a[ Shipment of Radioactive Materials i MURR-SAS-00004 b' 7.1.3 Place the "Rhinnino enneminer " cont =inino the Radioisotok " : into the Shialdad Stormee. 7.1.4 Staple ". Custnmer Reonest for Rndinisotone Shinment" and "In-house Partinnetive Shinnine Reonatt" forms together and place into the "Receint in-hox". 7.2 I!FCFIM " IN-BOX" l 7.2.1 A Q alified Shipper will process Check-in paperwork. ~ ! 7.3. PREPARE PACKAGE PACKET A Qualified Shipper will prepare the Packave Packet-7.3.1 Determine the proper Shipping Container based on information from Sections 4.20,4.21,4.22 or 4.23 (Attachment 4). . 7.3.2 Prepare labels: 7.3.2.1 Two each: MURR package Model Number, e.g., MURR 1000, etc. i 7.3.2.2 Six each: Shipping Label with Shipment Destination, Isotope, MURR ID number, and Activity. . Two each: USA DOT 7A Type A I 7.3.2.3 ! I
' Radioactive Material i
Specification Certified by ' University of Missourl i l Research Reactor Columbia, Mo. 65211 i 7.3.2.4 Two each: Radioactive Material ' N.O.S. UN2982 i 7.3.3 Prepare " Control Check Sheet" for proper USA DOT 7A MURR Model Number Package, Model 1000,1100,1220, or 1300. (Attachment 4). 7.3.4 Place the prepared Packane Packet in the " Packane Packet In-Box". : 7.4 PACKAGE PACKET "IN-BOX" Qualified Shipper will remove Packane Packet from
" Pneknoe Packet " In-Box "
MURR-SAS-OOOO4 page 23 of 31 Rev.03 SA M ... HP Date 04 Nov.1994 CONTROL CHECK SHEET USE PROCEDURE ,
-1
T }
' MURR-SAS40004 Shipment cf Radioactiva Materials- .
~
7.5.11 - l Strap polystyrene insert by strapping machine wlthi, 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 Identification Label on top for viewing when container flaps are opened. 7.5.13 Tape inner flap at least 75. percent of length. i 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.
I 7.5.18
- Ensure proper shipping name and UN number label is on opposite
- 1. sides of the 7A container.
I 7.5.18.1. Include "RQ" before or after if applicable. 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 MURR 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 external surface of the containers' four numbered sides, top l and bottom. 7.5.23.1 Obtained readings must be recorded on the control check sheet by performer and independently verified by inspector. ; Date 04 Nov.1994 MURR-SAS-00004 page 25 of 31 Rev.03 SA HP . CONTROL CHECK SHEET USE PROCEDURE
tR _ s
. MURR-SAS-00004 Shipment of Radioactiva Mat: rials 1 .-
7.10 COMPIFIT SHIPPING PAPERS 7.10.1 A Certified Shipper will complete shipping papers obtained from Shionine Paner Packet "In-Box" and perform the following: 7.10.1.1 Determine the proper radioactive label White I, Yellow II, or Yellow III in accordance with 49CFR, or IATA Regulations. T 7.10.1.2 Fill out the radioactive label. 7.10.1.3 Determine the label (s) required for subsidiary risk by use of (Label Specifications) ofIATA Dangerous Goods Regulations. 7.10.1.4 Provide label (s) for subsidiary risk (s). 7.10.1.S Determine other hazardous label (s) required by use of Section 7.3 of IATA Dangerous Goods Regulations. l 7.10.1.6 Add transport index to shipping papers, category of ' radioactive label (White I, Yellow II, Yellow III), and Subsidiary Risks labels from the Control Check Sheet. 7.10.1.7 Add swipe information to shipping papers. t 7.10.2 Complete the appropriate documentation section of the Control Check Sheet.
.- 7.10.3 Ensure Information specified on the In-House Fuelloactive Shinnine Reauest 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
- Verify that activity has been approved as per Precautions and Limitations of MURR-SAS-00004, Step 2.12.
7.10.3.3
- Isotope and activity is within acceptable limits
~
and possession limits. I 7.10.3.4
- The shipping address is correct.
7.10.3.S
- Transfer Form is in packing enclosure. ,
7.10.3.6
- Ensure that Shipment Waybill (s), address label, container identification agree.
.7.10.4 Place completed shipping papers in the Final Packaging Checkout "In-Box".
Date 04 Nov.1994 MURR-SAS-00004 page 27 of 31 Rev.03 SA HP , CONTROL CHECK SHEET USE PROCEDURE
. _ . . _ - - . ___2____-_-_-______-_-__-_____-___
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MURR-SAS-00004 / Shipment of Radioactive Materials
~ FINAL PACKACING CHW'KOITT "IN-BOX"
- ' s7.11- .
I .< , .. ,, , ,< .,j . J* 7.11.1i Package is ready for final attachment of labels a6d cheknut. , a 7.12' FINAL PACKAGING W
' A Qpalified Shipper will locate the specific Package Packet in 1 the Finni Parknoine Chuknut "In-Box". ,
j L ~ 7.12.1 - Perform the following for Air Freight: 7.12.1.1' Affix address. ' i N ,7.12.1.2 Affix packing list envelope. :
. 7.12.1.3 - Affix Shippers Declaration (Attachment 7a) - ,
1 7.12.1.4 Affix appropriate Primary Hazard label: , White I, Yellow II, or Yellow 111. i 7.12.1.S Affix subsidiary risk (s) labet .
~ 7.12.1.6. Affix " Cargo Aircraft Only" label. r
# Exception for passenger aircraft is for medical use and if T1 [
is equal to or less than 3.0. -l
' 7.12.1.7 Affix "This Way Up" arrow, if appropriate.
7.12.1.81Certified Shipper signs and dates Control Check Sheet . y (Attachment 4) indicating shipment is approved for release. l 7.12.2- Perform the following for Ground Freight: - , l
~
-7.12.2.1? Affix address. ;
7.12.2.2 Affix Straight Bill of Lading (Attachment 7b). I 7.12.2.3 Affix packing list. 7.12.2.4 Affix appropriate Primary Hazard label: White I Yellow II, or I Yellow 111. , I : 7.12.2.S Affix Subsidiary Risk label and Handling Label adjacent to the : I i Li- Primary Hazard Label. 1 1 7.12.2.6 Include "RQ" before or after if applicable. ] 7.12.3 Certified Shipper signs and dates Control Check Sheet - attachment 4) indicating shipment is approved for release.' .1 SA' HP Date 04 Nov.1994 - MURR-SAS-00004 page 28 of 31 Rev.03. y j CONTROL CHECK SHEET USE PROCEDURE l
m-y3 . ,
- ]
o. MURR-SAH)0004 , Shipment of Radlametive Materials , 7.16' REIRASE m COURIER -
, )
r
, 7.16.1 Mark the box below the Certified Shipper's Signature /Date i (Atrachrnant 4) only if the package is category Yellow III, and 'I requires vehicle placards. ~
j 4 - 7.16.2 Package is picked up and signed for by a Courier only'if the ' l package is a yellow III indicating an offer was made to the courier i for placards. ~ j a 7.17' EMERGENCY RF3PONSE INFORMATION I A copy of the Dangerous Goods Declaration is placed in the Control Room Emergency Response Book. . e 7.18 NOTIFICATION OF A SHIPMENT } Notification of a shipment may take place anytime after the ' ~' package has been signed-off by a Cartified Shipper.-
'l 7.18.1 Notification of the radioactive shipment should be made by a :
Qualified Shipper using Telephone calls, Fax or Mail. : t 7.18.2 The Control Check Sheet (attachment 4 ) will be initialed ' - and method of notification noted. ,.
.i i
i t i l P l
-l l
9 I
?
i Rev.03 SA HP Date 04 Nov.1994 MURR-SAS-00004 page 30 of 31 CONTROL CHECK SHEET USE PROCEDURE I I _ _ _ _ _ _ _ _ _ _ . . _ . __ .._ _ _ __ _ . - . . .. ._ . - . . _ ,, . ,. . . ~ ,
(+ ,' fQ " W'
;r :-
- l' MURR-SAS-00004 Shipment of Radioactive Materials ATTACHMENTS 4
- A. Packaging Flow Chart (Atenehment 1).
B. In-House Radioactive Shipping Request Form (Attachment 2). C. Request for Radioisotope Shipment Form (Attachment 3). D. Control Check Sheets for USA DOT MURR Models (Attachment 4). E. Address label Examples (Attachment S).'- F. Material Transfer Form (Attachment 6). G. Shippers Declaration For Dangerous Goods Form (Attachment 7a).
- H. Straight Bill of Lading (Attachment .'b).
I. Shipping Summary Form (Attachment b.N REFERENCES A. Federal Code of Regulations 49CFR. B. Federal Code of Regulations 10CFR. C. International Air Transport Association Dangerous Goods Regulations. i HP Date 04 Nov.1994 MURR-SAS-00004 page 31 of 31 Rev.03 SA CONTROL CHECK SHEET USE PROCEDURE b~-- - - - - + , - . , _ . . ,, .,
n j
- CONTROL CHECK SHEET FOR USA DOT 7A MURR MODEL1000 -
Perfomer and hupactor can not be the same induaktual. - l Affix shipment preprinted identification label here. 3, ,s,<a. ,ua.,ryr tue sorum.wa.uuu , a i i inspector Performer
- 1. Imad shipping pig and inner shipping can identification labels agree.
- 2. Inner shipping can sealed.
- 3. Radioactive labels on inner shipping can. l
- 4. Expanded polystyrene insert identified and strapped.
- 5. 7A container identified, sealed and strapped.
- 6. Security seals on 7A container.'
- 7. Certification label in place on 7A container.
-i
- 8. Proper shipping name and UN No. on opposite sides of the 7A container. (Include "RQ" before or after if applicable) ;
- 9. 7A container swipe <6600 dpm/300cm2 y & <660 dpm/300cm2 a. l
- 10. 7A container dose survey (mR/hr):
B: Sides: 1) 2)_ _3) 4) l
Contact:
T: 1 i TransportIndex: j
- 11. Verify the information for this shipment is specified in the MURR i
Irradiation / Shipment request form and is within the license i restrictions.
- a. License number, amendment number and expiration date agree. j l
- b. Verify that activity has been approved as per Precautions and Limitations of MURR-SAS-00004 (2.12).
- c. Isotope and activity is within acceptable limits and possession -
limits. ;
- d. The shipping address is correct. .l I
- 12. Transfer Form is in packing enclosure.
i SA HP - Date:04 %v.1994 MURR-SAS 00004 Atachment 4 Page l of 2 Rev. 0.1. l i
- n. . ,
1
)
- f. ' ,
1 Noen: perfernerin to liet '.;.. ':== from each label. t m perfenner shouM not be the sMpper releasing ete containerJ
, b z;
,Insymsor Performer l
- 13. Primary hazard labels verified and in place'on opposite sides of the 7A
<r container. !
p Category: ! Isotope (s): Activity: '
.t TI: ;
- 14. . Verify appropriate subsidiary risk and handling label (s) are adjacent toi; j I
the primary hazard labels (List). (Include "RQ" before or after if ; applicable) i
- 15. ' Shipment Waybill (s), address label and 7A container preprinted :
identificationlabelagree. i i
- 16. Sodium Iodide Spectrum completed. ;
- 17. Consignee notified of shipment.
i Shipment approved for release by: i i i Certified Shipper's Signature /Date ]
. O rwi. Packase 1. catesor: Yetiow Irr, and require'. vehicle pt. cards.
( I cccept this shipment and certify that I have been offered radioactive placar: the time it was offered for transport. t i Courier's Signature /1/ ate ! l i Rev._A1. SA M HP d Date:04 Nov.1994 MURR-SAS-00004 Atachment 4 Page2 of 2 - f f i
e t CONTROL CHECK SHEET FOR USA DOT 7A MURR MODEL1100 ' l Perprmer and Inspator can not be the same individus!. ' r I-Affix shipment preprinted identification label here. f%pment Destination.isosopr(s),MURR Identplostson Nu=6erfs),and Actndfyl 1. Inspector Perfonner
- 1. Kimpack8 materialin inner shipping can. (Igm /2ml) f No.of mis No.of grams of Kimpacke
- 2. Imad shipping pig and inner shipping can identification labels agree.
- 3. Inner shipping can sealed. .
- 4. Radioactive labels on inner shipping can. !
- 5. Expanded polystyrene insert identified and strapped.
- 6. 7A container identified, sealed and strapped.
t
- 7. Security seals on 7A container.-
- 8. Certification label in place on 7A container.
- 9. Proper shipping name and UN No. on opposite sides of the 7A l container. (Include "RQ" before or after if applicable) j
- 10. 7A container swipe <6600 dpm/300cm2 y & <660 dpm/300cm2 a. i
- 11. 7A container dose survey (mR/hr):
Contact:
T: B: Sides: 1) 2) 3) 4) i Transport Index:
- 12. Verify the information for this shipment is specified in the MURR ,
Irradiation / Shipment request form and is within the license restrictions. l
- a. License number, amendment number and expiration date agree.
- b. Verify that activity has been approved as per Precautions and i
Limitations of MURR-SAS-00004 (2.12).
- c. Isotope and activity is within acceptable limits and possession !
limits.
- d. The shipping address is correct. ,
- 13. Transfer Form is in packing enclosure.
Rev..EL SA h HP Date: 04 Nov.1994 MURR-SASG)004 Attachmmt 4 Page1 of 2 , i
,m ,.
*. -l Nees: Perforwar is to list deformationfrom each labet ( 71w pesfermeer'shemld not be the shipper releme6qg taw = -l a,, tag,ary .
i Inspector Performer
- 14. Primary hazard labels verified and in place on opposite sides of the 7A container. :-
s Category: Isotope (s): ]
' Activity:
t
?
TI: t
- 15. Verify appropriate subsidiary risk and handling label (s) are adjacent to - ]
I the primary hazard labels (List). (Include "RQ" before or after if - ; applicable) : t
- 16. Shipment Waybill (s), address label and 7A container preprinted f identification label agree. ;
17.' Sodium Iodide Spectrum completed.
- 18. Consignee notified of shipment.
Shipment approved for release by: , l
;i Certified Shipper's Signature /Date .
-l t
- O rwi. Packase 1. catesory veniow Irr, and requires vehicle P .t cards.
I secept this shipment and certify that I have been offered radioactive placards, for Yellow III, at'thl time it was offered for transport. I i I ! l .t Courier's Signatum/Date SA lb HP - Date: 04 Nov.1994 MURR-SAS40004 Attachment 4 Page 2 of 2 ' f Rev. 03._
l o CONTROL CHECK SHEET FOR USA DOT 7A MURR MODEL1220 . j Perfmner and Inspector enn not be the same individual. .l i i Affix shipment preprinted identification label here. (Slupnwn Detaistans,Isotopr(s).MURA Menf#ksim Mann6er(s). sad Actipey) Inspector Performer ,
- 1. Kimpack* 80 packet used in inner shipping can.
- 2. Lead shipping pig and inner shipping can identification labels agree.
- 3. Inner shipping can sealed.
- 4. Radioactive labels on inner shipping can.
- 5. Expanded polystyrene insert identified and strapped. r
- 6. 7A container identified, sealed and strapped.
- 7. Security seals on 7A container.
- 8. Certification label in place on 7A container.
- 9. Proper shipping name and UN No. on opposite sides of the 7A container. (Include "RQ" before or after if applicable)
- 10. 7A container swipe <6600 dpm/300cm2 py & <660 dpm/300cm2 a.
- 11. 7A container dose survey (mR/hr):
Contact:
T: B: Sides: 1) 2) 3) 4) Transport Index:
- 12. Verify the information for this shipment is specified in the MURR Irradiation /Slupment request form and is within the license 1 restrictions.
- a. License number, amendment number and expiration date agree. f
- b. Verify that activity has been approved as per Precautions and Limitations of MURR-SAS-00004 (2.12).
- c. Isotope and activity is within acceptable limits and possession limits.
- d. The shipping address is correct. ;
- 13. Transfer Form is in packing enclosure.
t Date: 04 Nov.1994 MURR-SAS-00004 Atachment 4 Page l of 2 Rev._03. SA ! HP
p
~
~ 2 1
5
- " -frene each label. (the perferneer should not be the shipper z'--
' ; the' l Netbr Perfenner is to list
- _l ,
s eene.iner.) . . ; 5 i Inspector Performer !
- 14. Primary hazard labels verified and in place on opposite sides of the 7A . !
container. ' Category: j Isotope (s):
~ Activity:
[ TI:
- 15. Verify appropriate subsidiary risk and handling label (s) are adjacent to the primary hazard labels (List). (Include "RQ" before or after if .
applicable) :
- 16. Shipment Waybill (s), address label and 7A container preprinted ;
' identification label agree. .
- 17. SodiumIodide Spectrum completed.
4
- 18. Consignee notified of shipment.
i Shipment approved f6r releaseby: ! l Certified Shipper's Signature /Date O ni p.ckase is a catesory veniow 111, and require. vehicie pi. cards. I cecept this shipment and certify that I have been offered radioactive placards, for Ye
' the time it was offered for transport. l l
i. d Courier's Signature /Date HP D.te:04 % v.1994 MURR-SAS40004 Atachment 4 Page 2 of 2
.Rev..gL SA o
l
s
, s 1; o g. -
m- > ;;. _ x _ ,
@ 1 CONTROL CHECK SHEET FOR USA DOT 7A - l MURR MODEL1300. . .
E, Amfonarr and faspasar een not er the same indioidmet. i
- j 1
~ Affix shipment preprinted identification label here. ;
3, .
' %am.=m.m ,vo.muuumpm u wco. ,uwe l
.l j
Inspect:r . Performer 1. Sample containment and inner shipping can identification labelsL' t agree.
- 2. Inner shipping can sealed.
- 3. Radioactive labels on inner shipping can.-
- 4. Expanded polystyrene insert identified and strapped.
-i
- 5. 7A container identified, sealed and strapped.
. 6. Security seals on 7A container, j
- 7. Certifiestion labelin place on 7A container. ;
j
- 8. Proper shipping name and UN No. on opposite sides of the 7A-container. (Include "RQ" before or after if applicable) i
- 9. 7A container swipe <6600 dpm/300cm2 py & <660 dpm/300cm2 a..
- i
- 10. 7A container dose survey (mR/hr): ;
Contact:
T: B: Sides: 1)- 2) ' 3) 4) ! Transport Index: }
- 11. Verify the information for this shipment is specified in the MURR - j Irradiation / Shipment request form and is within the license .;
restrictions. 4
- a. License number, amendment number and expiration date agree._ j
- b. Verify that activity has been approved as per Precautions and l 1
Limitations of MURR-SAS-00004 (2.12). j t
- c. Isotope and activity is within acceptable limits and possession .
limits. )
- d. The shipping address is correct. ,
.I
- 12. Transfer Form is in packing enclosure.
i
.i Date:04 Nov.1998 MURR-SAS@004 Attachment 4 Page 1 of 2 Rev. AL SA ~ 31A ~ HP ~
. I m _ . - . . _ _ _ _ _ ._ _ _ _ _ _ . _ _ _ _
p.
~ Note: Performer is to list informationfrom each label. (The performer should not be the shippe t releasing the container.) ' Inspector Performer
- 13. Primary hazard labels verified and in place on opposite sides of the 7A' container.
Category: Isotope (s): l Activity: : TI:
- 14. Verify appropriate subsidiary risk and handling label (s) are adjacent to the primary hazard labels (List). (Include "RQ" before or after if .
applicable)
- 15. Shipment Waybill (s), address label and 7A container preprinted identification label agree.
- 16. Sodium Iodide Spectrum completed.
- 17. Consignee notified of shipment.
9 Shipment approved for release by: ; Certified Shipper's Signature /Date ! 4 O This p.ck.ge is a category Yellow III, and requires vehicle placerds. I cecept this shipment and certify that I have been offered radioactive placards, for Yellow III only, at : the time it was offered for transport. i r Courier's Signature /Date i SA JN HP Date:04 Nov.1994 MURR-SAS-00004 Attachment 4 Page 2 of 2 Rev. 03_
E j SECTION III > REVISIONS TO THE HAZARDS
SUMMARY
REPORT ! 1 January 1994 through 31 December 1994 l t HAZARDS
SUMMARY
REPORT (ORIGINAL JULY 1,1965) ! l Original Hazards Summary Report, page 13, Section 1.1.3, paragraph 8; 198142 Annual l Report revision: Dalata: "(4) 4 pneumatic tube irradiation positions." ; Ramlaea with: "(4) Pneumatic tube irradiation positions." Original Hammeds Summary Report, page 1-11, Section I AJ, paragraph 2, last centence: Delata: "In final form two parallel electrically controlled, nitrogen operated valves have replaced the vacuum breaker valve." Henlace with: "In final form two parallel electrically controlled, air operated valves have replaced the vacuum breaker valve." l Original Hazards Summary Report, page 5 2, Section 5.2.1, paragraph 1, sentence 1: ! Dalgia "100 KW"; raniaca with "50 kW" f i Original Hazards Summary Report, page 5-3, Section 5.2.2, paragraph 3,line 2: ; t Delete: " Water is automatically discharged into the hot waste system when the pressurizer ! level becomes too high." ; Hanlace with: " Water is automatically discharged into the drain collection tank when the l pressurizer level becomes too high." j Original Hazards Summary Report, page 5-8, Section 5A.1, paragraph 2: . j Dalcia: " Components comprising the secondary cooling system include: the pool heat exchanger, the primary heat and temperature instrumentation, radiation monitoring instrumentation, chemical addition equipment, primary and pool automatic control : valves, . . . ." 1 Ranlace with: " Components comprising the secondary cooling system include: the pool heat exchanger, the primary heat exchanger and temperatum instrumentation,
]j radiation monitoring instrumentation, chemical addition equipment, primary ;
and pool heat exchanger automatic control valves, . . . ." l Original Hazards Summary Report, page 5 9, Section 5A.3, paragraph 2, sentence 2: i Dalcia: . ." . on the perimeter of the basin wall." Original Hazards Summary Report, page 5 9, Section 5AA, sentence 3: Delete "One standby pump in addition to the number required for normal cooling is installed and operable." Renlnee with: "One standby pump in addition to the number required for normal cooling is j installed." ) III-1 l 1
Original Hm==eds Summary Report, page 510, Section 5.4.5, paragraph 2, mentence 1: f Delsia: "A complete system to measure gross gamma activity of the secondary system is installed with the output displayed and recorded in the reactor control room." i Replace with: "A complete system to measure gross gamma activity of the secondary system is .; installed with the output displayed in the reactor control room." Original Hazards Summmey Report, Figure 5.1: Dalata Figum 5.1; renlace e updated Figure 5.1. , Original Hazards Summary Report, page 101, paragraph 1: . Dalata: " Maintenance on the reactor and systems will normally be performed by personnel ' permanently assigned to the Research Reactor Facility for this purpose. 'Ihe number ! of persons will be dependent upon work load. There will be at least one mechanical and one electrical technician permanently assigned at the facility. These people will . receive training on the reactor and systems equivalent to that of a reactor operator and t may become licensed reactor operators. They will be thortsughly indoctrinated with appropriate radiation health and safety practices." Bag] ace with: " Maintenance on the reactor and process systems will normally be performed by - i personnel permanently assigned to the Research Reactor Facility for this purpose. There will be at least one mechanical and one electrical technician > permanently assigned at the facility. These people will receive training on the ; reactor and process systems similar to that of a reactor operator. They will be , thoroughly indoctrinated with appropriate radiation health and safety practices." 198182 Annual Report Revision to the Original Ramards Summary Report, pages 101 - ' 10-2, Section 10.1, paragraph 1: Dalata: "The facilities provided at the Research Reactor Facility for performing maintenance ; task's include: i (1) One 15 ton overhead crane in the reactor containment vessel. .i [] rev.1982 - (5) A mechanical maintenance shop on grade level of the laboratory. (6) An electrical and instrument maintenance shop on grade level of the laboratory. , The two shops (items 5 and 6 above) are equipped with the machine tools, small tools, electrical and instrument equipment necessary to perform the normal maintenance : tasks required by the laboratory and the reactor." t
- Renlam with: "The facilities provided at the Research Reactor Facility for performing I
! maintenance tasks include: -l i (1) One 15 ton overhead rectilinear crane and one 500 lb. jib crane in the i reactor containment building. _ j (2) A mechanical maintenance shop within the site boundary. (3) An electrical and instrument shop within the site boundary. The two shops (items 2 and 3 above) are equipped with the machine tools, small ! I tools, electrical and instrument equipment necessary to perform the normal , j maintenance tasks required by the Research Reactor Facility." f III-2 1 i
a y .x ; Original Hasards Summary Report, page 10 2, Section 103, paragraph 1: ' ; Dalata: " Subsequent to reactor operation and prior to entry into contaminable areas a complete radiation survey will be made to establish does rates. Also, following any _~ change of conditions in which the dose rates may be effected, such as a change in pool
~ water level, a survey will be made to ensure acceptable exposure rates." ,
y . : Related with.: " Subsequent to reactor operation and prior to entry into potentially , contaminated areas, a complete radiation survey will be made to establish dose rates. Also, following any change of conditions in which the dose rates may be i effected, such as a change in pool water level, a survey will be conducted to ensure dose rates are within acceptable limits." . Original Hazards Summary Report, pages 10 3 and 10 4, Section 10.2, paragraphs 5 & 8: , Delsta: *To prevent endangering personnel during maintenance activities on electrical i equipment a tag out procedure will be utilized on the electrical control to the associated equipment and, where possible, electrical breakers will be de-energized and i tagged. (Refer to Section 10.7 for tag procedure). Maintenance tasks other than routine (i.e., removal of graphite reflector, etc.) will be , performed in accordance with special written procedures establishing condition of reactor, special tools required, monitoring requirements, personnel protection, and a detailed procedure. These special procedures will be reviewed and approved by the reactor supervisor." Ranlace with: "To prevent endangering personnel during maintenance cetivities, a tag out
. system will be utilized. (Refer to Section 10.7 for tag procedure). ,
Non-routine maintenance tasks (i.e., removal of graphite reflector, etc.) will be , pedormed in accordence with special written procedures. These special procedures will establish the condition of the reactor, include special tools ;~ required, describe the monitoring and personnel protection requirements, and include a step by step guide for completion of the maintenance activity. These special procedures will be reviewed and approved by the Reactor Manager." i Original Hazards Summary Report, page 10 4, Section 10.3, paragraph 2, sentence 5: - Deleta " Point of control will be at the entries as shown on Figure 3.2." l Renlace with: " Point of control will be at the entries designated by Health Physics." I 5 Original Hazards Summary Report, page 10-5, Section 10.3, paragraph 3, sentence 2: Delein: "In the event that the maintenance activity may create air-borne activity continuous l sir samples will be taken and, if necessary or as a precautionary measure, proper l respiratory protection will be provided." Replace with: "In the event that the maintenance operation may create air-borne activity, continuous air monitoring capability, as necessary, will be prescribed by Health ! Physics." i III-3 ' i 1 y e , , , y-..
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T 198183 Annual Repod Revision to Ori H====11s S=====y Report, page 10 5, maah= 10J, paragraph 8, sentence 2 end of paragmph:; , Deleta: " Regeneration of the domineralizers is accomplished as described in Sectiu 7.1.9 in ' areas shielded from the domineralizers. At intervals of approximately 18 to 24 months the resins will require changing. They will be discharged mmotely into . shielded containers and discarded as radioactive waste. [ ](rev 1982). Constant health physics monitoring will be provided to personnel during the resin transfer procedure. Personnel will be provided proper protective clothing when necessary." . Ranlace with: " Regeneration or replacement of the domineraliser resin is accomplished as described in Section 7.1.9 in areas shielded from the denuneralizers. At intervals of approximately two to four months the resins will require changing. They will be discharged into containers and discarded as radioactive waste. Monitoring, as prescribed by Health Physics, will be provided to personnel during ' the resin transfer procedure. Personnel will be provided proper protective
- clothing as necessary."
Original Hm=ards Summary Report, page 10 6, Section 10A, paragraph 1, sentence 3 & 4: i Dalata: " Protective clothing and respiratory protection will be provided when handling the . ! contaminated filters. Immediately following removal of the filter from the system it i will be placed in a plastic bag or other suitable air tight container and sealed." Renlmee with: " Protect.ive clothing will be prescribed by Health Physics when handling - + contaminated filters. Immediately following removal of a filter from the system it will be placed in a plastic bag or other suitable air tight container and sealed." ; Original Hazards Summary Report, page 10 6, Section 10.5, paragraph 1, sentence 1: ' { Delsia: "A periodic maintenance system will be in efect on all reactor, process and laboratory equipment." ; Raniace with: "A periodic maintenance system will be in effect on all reactor and process . ; equipment." .j i Original Hazards Summary Report, page 104, Section 10.5, paragraph 1, sentence 3: - i Dalata: "A card file will be maintained providing the date and nature of maintenance activities . on all equipment." Replace with: "A record will be maintained providing the date and nature of maintenance activities on all equipment." .! P Oris;8.aal Hammeds Summary Report, page 10-7, Section 10.5, paragraph 3: , Delata " Acid resistant protective clothing and face shield will be worn by personnel performing -t work on the acid and caustic system, and an eye wash and shower is provided in the cooling tower building for use in the event of an emergency." i Raplace with: " Acid resistant protective clothing and face shield will be worn by personnel L performing work on the acid system. An eye wash and shower are provided in t the cooling tower building for use in the event of an emergency." Original Banards Summary Report, page 10 7, Section 10.6, paragraph 3: Dalsla: "A source check of the radiation monitoring system will be performed once every week - to ensure proper operation. The calibration ofinstrumentation will be included in the maintenance program." ~ : f III-4 .
l Ren1mee with: "A source check of the radiation monitoring modules which are connected to the Safety System will be performed at least once per week to ensure proper operation. A source check of all the radiation monitoring modules will be performed quarterly to ensure proper operation. The calibration ofinstruments will be included in the maintenance program." Original Hazards Summary Report, page 10-8, Section 10.7, number (1), sentence 2: Delete: ". . . contain information as to the time it was initiated . . . ." Ran1mee with ". . . contain information as to the date it was initiated . . . ." Original Harneds Summary Report, page 10-8, Section 10.7, number (2), sentence 2: Delete ". . . contain information as to the time it was initiated . . . ." l Reninee with ". . . contain information as to the date it was initiated . . . ." Original Hazards Summary Report, page 10-8, Section 10.7, number (3): Delete: "A log book will be maintained containing the tag number, the time initiated, the equipment involved, the time of tag removal, and operator initials." Rennlee with: "A log book will be maintained containing the tag number, the date initiated, the equipment involved, the date of the tag removal, and the initials of the person responsible for tag placement and removal." Original Hazards Summary Report, page 10-9, Figure 10.1: Delete Figure 10.1; renlace with updated Figure 10.1, Main Reactor Equipment Room. l III-5
s ADDENDUM 3 - HAZARDS
SUMMARY
REPORT (AUGUST 1972) Hm==wds Su==mey Report, Addendum 3, page 8, Section 2.1.2.12, sentence 1 and 2: Dalcia:
" . . . of the lock shield type with key. The locked shield is a cap which fits over the operator to prevent inadvertent operation of the valve."
Hamants Summary Report, Addendum 3, pages 910, Section 2.1.3.1: Delegg the phrase " pressure differential switch (es)"; replace with the phrase " differential pressure sensor (s)" throughout the section. Baumeds Summmey Report, Addendum 3, page 10, Section 2.1.3.1, paragraph 2: j Dalata *DPS 949"; ren1=ea with "DPS 929" f Hamards Summary Report, Addendum 3, page 18, Section 2.3.2.2, sentence 1: Dalata: " Cooling tower cell is a double flow . . . ." l 1 Renlace with: " Cooling tower cell #3 is a double flow . . . ." j Hazards Summary Report, Addendum 3, page 20, Figure 2.2: Dalcia Figure 2.2; renlace with updated Figure 2.2 HSR, Addendum 3, page 195, Section 5.4.2: Add: "(October 1966 in July 1971)" after the section title. HSR, Addendum 3, page 195, Section 5.4.2., paragraph 2: Dalcia: "The reactor has operated at 5 MW from June 30,1967, to the present. This power level was maintained for approximately 40 hours per week during the period of time from July 30,1967, to September 29,1969, and approximately 100 hours per week for the period from September 29,1969, to the present." Ranlace with: "The reactor was operated at 5 MW from June 1967 to May 1974. This power level was maintained for approximately 40 hours per week during the period of time from July 1967 to September 1969, and approximately 100 hours per week for the period from September 1969 to May 1974." III-6
t ADDENDUM 4 - HAZARDS
SUMMARY
REPORT (OCTOBER 1973) Hazards Summary Report, Addendum 4, page B 11, Section B.3, paragraph 2,line 5: Delete: "The vent line from the existing vent tank will be extended and discharge into the gas retention tank." Renlace with "The vent line from the existing vent tank will be extended and discharge through filters to the containment exhaust system." Hazards Summary Report, Addendum 4, page D-3, Appendix D, Figure D.1: Add the word " SIMPLIFIED" to beginning of title to read, " SIMPLIFIED SCHEMATIC DIAGRAM OF THE MURR PRIMARY COOLAh"r SYSTEM" Add the following note under title: "(NOTE: This schematie does not include system changes made since 1974.)" l I III-7
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- FIGURE D.1 e SIMPLIFIED SCHEMATIC DIAGRAM OF THE MURR PRIMARY COOLANT SYSTEM (NOTE: This schematic does not include system changes made since 1974.) (rev 1994)
SECTION IV PLANT AND SYSTEM MODIFICATIONS 1 January 1994 through 31 December 1994 The safety evaluation for each modification described below is on file at MURR and documents that it does not present an unreviewed safety question as per 10 CFR l 50.59. I Modification 93-2: Pneumatic tube airintake moved to air sunniv duct This modification changed the location of the air supply for the pneumatic tube system from the basement to the ventilation system supply air mixing box for the basement. This modification also changed the supply HEPA filter from a 6 inch to a 12 x 12 x 12 inch HEPA. The exhaust filter housing was moved from the discharge side to the suction side of the blowers. Modification 94-1: The elimination of ernerimental can in beamnort exneriments This modification eliminated the experimental can from beamports "A", "B" and "C." This results in higher beam intensity for research. The beam tube can be flooded, drained, evacuated, or back filled with helium, the same as the previous mode with an experimental can. Modification 94-2: Renlacine cranhite reflector elements 2 and 3. and renlacing wedce "I" and "J" (silicon wedge) This modification package documents the change of original graphite wedge 2 with 2A, and original graphite wedge 3 with 3B. Wedge 2A is virtually the same as wedge 2. Wedge 3B has two irradiation positions designed for pneumatic tube terminals. Both new wedges are made of the same material as the original wedges. Wedge "I" and "J" are aluminum wedges containing a void and self powered rhodium detectors. The new replacement wedge is the same as the one removed except for the addition of a small amount of graphite. The reactivity change was measured to be +0.0001 Ak/k. IV-1 L______________________________________ _ _ _ _ _ _ _ _ _ _ _ _ ___ _ _
Modification 94 3: Snmnline and recording of mactor operating narameters for research into develoning an "Ernert System" This modification package documented the connection ofvarious reactor process variables to a computer based sampling and recording program to obtain data for an " Expert System." The necessary isolation devices were installed to ensure the data collection did notinterfere with the process system or any safety related functions. Modincation 94 6: Costar tower constructed inside of the containment building This modification package documented the addition of a five level steel storage structure on the west side of the containment building. 1 I IV-2 t - - - _ _ _ _ _ _ - _ _ _
SECTION V r-NEW TESTS AND EXPERIMENTS 1 January 1994 through 31 December 1994 New experimental programs during this period are as follows: RUR 291, Zinc metal and zinc oxide; enriched Zn 64 or Zn-67: Experimenter: S. Gunn
Description:
This RUR authonzed irradiation of zine metal and oxide in a boron nitride shielded can for production of Cu-64 or ~l l Cu-67. RUR-303, Zinc metal, natural abundance: Experimenter: S.Gunn L
Description:
This RUR authorized irradiation of zine metal for the l- production of Zn-65. 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.
i i V-1
w SECTION VI l SPECIAL NUCLEAR MATERIAL ACTIVITIES 1 January 1994 through 31 December 1994
- 1. SNM Receipts: A total of 24 new fuel elements were received from Babcock and Wilcox (B & W), Lynchburg, Virginia.
Grams Grams Shipper Elements _ U U 235 B&W MO-401, MO-402, MO-403, MO-404, MO-405, MO-406, 19,934 18,562 MO-407, MO-408, MO-409, MO-410, MO-411, MO-412, MO-413, MO-414, MO-415, MO-416, MO-417, MO-418, MO-419, MO-420, MO-421, MO-422, MO-423, MO-424
- 2. SNM Shipments: A total of 8 spent fuel elements were shipped to DOE -
facilities at Savannah River Plant, Aiken, South Carolina. Grams Grams Shipper Elements U U-235 MURR MO-343, MO-344, MO-345, MO-346, MO-348, MO-350, 5,397 4,709 MO-351, MO-353
- 3. Inspections: None.
- 4. SNM Inventory: As of 31 December 1994, MURR was financially responsible for the following DOE-owned amounts:
Total U = 55,411 grams Total U-235 = 49,484 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
- M
, ; m A
a The fuel elements on hand have accumulated the following burn-ups as of 1 31 December 1994. Burned-up Element.s (32) Element No. MWD Element No. MWD Element No. MWD MO-321 126.10 MO-360 135.08: MO-371 118.50 MO-322 126.10 . MO-361 131.22 MO-372 134.27 M O.347 137.81 MO-362 131.58 MO-373 129.35. MO-349 137.81 MO-363 131.22 MO-374 - 132.31 M O-352 136.11 MO-364 131.58 MO-375 129.35 MO-354 136.11 MO-365 126.99 MO-376 - 132.31 MO-355 130.10 MO-366 129.14 MO-378 127.98 MO-356 130.10 MO-367 126.99 MO-380 127.98 MO-357 134.86 MO-368 129.14 MO-381 114.55 MO-358 134.86 MO-369 - 113.50 MO-383 114.55 MO-359 135.08 MO-370 134.27 Elements in Service (44) MO 377 98.59 MO-396 99.78 MO-411 77.75 MO-379 - 98.59 MO-397 90.36 MO-412 69.22 MO-382 -99.44 MO-398 86.89 MO-413 69.16 MO-384 99.44 MO 399 90.36 MO-414 59.47 MO-385 99.46 MO-400 86.89 MO-415 69.16 MO-386 95.93 MO-401 85.00 MO-416 42.79 MO 387 99.46 MO-402 88.36 MO-417 59.47 MO-388 95.93 MO-403 85.00 MO-418 42.79 MO-389 99.31 MO-404 88.36 MO-419 28.60 MO-390 94.03 MO-405 86.41 MO-420 - 28.60 MO-391 99.31 MO-406 92.27 MO-421 10.32 MO-392 94.03 MO-407 86.41 - MO-422 0.00 MO-393 94.97 MO-408 92.27 MO-423 10.32
' MO-394 99.78 MO-409 77.75 MO-424 - 0.00 MO-395 94.97 MO-410 69.22 Average Burn-up (all elements): 98.40 MWD l
)
VI-2
o SECTION VII REACTOR PHYSICS ACTIVITIES 1 January 1994 through 31 December 1994
- 1. Fuel Utilization: During the period 1 January 1994 through 31 December 1994, the following elements reached licensed or feasible burn-up and were retired:
Serini Number Finni Core Date Tmt Used MWD MO-355 94-09 03 07-94 130.10 MO 356 94-09 03 07-94 130.10 MO 357 94-35 08 08-94 134.86 MO-358 94-35 08-08-94 134.86 MO-361 94-12 03-21-94 131.22 MO 362 94-22 05-23-94 131.58 MO-363 94-12 03-21-94 131.22 MO-364 94-22 05 23 94 131.58 MO-365 94-17 04-18-94 126.99 MO-366 94-03 01 24-94 129.14 MO 367 94-17 04-18-94 126.99 MO-368 94-03 01-24 94 129.14 MO-369 94-54 12-08-94 113.50 MO-370 94 23 05-31-94 134.27 MO-371 94-54 12-08-94 113.50 MO-372 94-23 05-31-94 134.27 MO-373 94 45 10 10-94 129.35 MO-374 94-26 06-20-94 132.31 MO-375 94-45 10-10-94 129.35 MO-376 94-26 06-20-94 132.31 MO-378 94-5'2 11-28-94 127.98 MO-380 94-52 11 28-94 127.98 MO-381 94-56 12-19-94 114.55 MO-383 94-56 12-19-94 114.55 I i 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 com 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 1994. To increase operating efficiency, fuel elements are used in mixed core loadings. Therefore, a fuel element fabrication core number is i different fromits coreload number. VII-1
& l s 4 Y
l
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4
- Fabrication - InitialCore : Initial Serial Number Com Number Imad Number Operating Data , :
1 MO-394 65 94 01-18-94: .j MO-396 65 94 01-18-94 l MO-397 65 94-5 01-31 94 l MO-398 65 94 01-31 94 M O-399 66 94-5 01-31-94 j MO-400 66 94-5 01-31-94. 'l MO-401 66 94-12 03-14 94 1 MO-402 66 94-16 04-04-94 j MO-403 66 94-12 03-14-94 l MO-404 66 94 16 04-04 94' ] MO-405 66 94-20 05-02-94 MO-406 66 94 20 05-02-94 l MO-407 67 94-20 05-02-94 1 MO-408 67- 94-20 05-02-94 , MO-409 67 94-30 07-05-94 , MO-410 67 94-35 08-01 94- ! MO-411 67 94-30 07-05-94 [ MO-412 67 94 35 08-01 94 ; MO-413 67 94-38 08-22-94 [ MO-414 67 94-45 10-03 94 ' jl MO-415 68 94-38 08 22-94 : MO-416 68 94-48 10-24-94' ! MO-417 68 94-45. 10-03-94 ! MO-418
- 68 94-48 10-24-94 f MC-419 68 94-52 11 21-94 l MO-420 68 94-52 11-21-94 j MO-421 68 94-57 12-20-94 l MO-423 69 94-57 12 20 94 l 1
l
- 2. Fuel Shipments: Eight spent fuel elements were shipped from MURR to !
Savannah River Plant, Aiken, South Carolina. The identification numbers of -. j these elements are: t MO 343 MO-345 MO-348 MO-351 M O-344 MO-346 MO-350 MO-353 , Fuel Procurement: Babcock and Wilcox, Lynchburg, Virginia, is MURR's fuel f 3. 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 [i December 1994,225 fuel assemblies fabricated by B & W had been received and j f' 223 used in cores at 10 MW. [ I i VII-2 , i l l
fL Licensing Activities: On August 5,1994, the Nuclear Regulatory Commission ; approved Amandment No. 26 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. l This amendment requires that this annual report include the status of these .j ahipments. Eight spent fuel elements wem shipped in the period of this mport. l Three shipments are scheduled in 1995, but late enough in the year that the l 60 kg limit will be e=adad in June 1995. Early in February 1995, MURR will '! submit a request for a temporary increase of the possession limit to 75 kg until l May 31,1997. This will ensure that MURR can continue normal operation into j early 1997 even though we may not be allowed to ship spent fuel in 1996. If i spent fuel shipments are not made in 1996, the 75 kg temporary possession limit } will be reachedin February 1997. ! t i MURR staff have continued their efforts to achieve more regular acceptance of ; spent fuel at Savannah River Plant with limited success. The Department of : Energy has had to juggle the spent fuel needs of university research reactors and . DOE reactors, with the receipt and storage of foreign fust This has lead to j uncertainty and numerous changes to our spent fuel shipping opportunities. l l A request for a unique purpose exemption as defined in 10 CFR 50.2 'was submitted September 26,1986, and is pending.
)
i
- 5. Reactor Characteristic Measurements: Fifty-nine refueling evolutions were i completed. An excess reactivity verification was performed for each refueling and the average excess reactivity was 1.86%. The largest excess reactivity was I
2.79%. MURR Technical Speci6 cation 3.1(0 requires that the excess reactivity be less than 9.8%. ! i Reactivity measurements were performed for ten evolutions to verify reactivity l parameters for the flux trap. Four differential worth measurements were made [ on shim blades. Two measumments were made when graphite reflector wedges I were changed. One measurement of a temperature coefficient was made. l I VII-3 ! i
i j p. SECTION VIII. l
SUMMARY
OF RADIOACTIVE EFFLUENT RELEASED ; TO THE ENVIRONMENT Sanitary Sewer Effluent i 1 January 1994 through 31 December 1994 . Descen' ding Order of Activity Released for Isotope Totals > 1.00E-5 Ci: l Nuclide Amount (Ci) H3 1.089E-01 , t S-35 1.117E-02 l i Ca-45 3.794E-03 j Co-60 1.496E-03 As-77 1.411E-03 f Re-186 3.193E-04 Zn-65 1.118E-04 1 Se-75 6.626E-05 j Cr-51 4.781E-05 Eu-152 2.533E-05 Gd-159 1.686E-05 . i Sb-124 1.632E-05 ! Ta-183 1.555E-05 I Total H-3 1.089E-01 Ci I
)
Total Other 1.849E-02 Ci 1 VIII-1 1
c f l Stack Effluent , 1 January 1994 through 31 December 1994 ; Ordered by % Technical Specification (TS) Limit , Average. TotalRelease Concentration 1/94 - 12/94 TS Limit Isotope (pCi/ml) (Ci) Multiolier % T8* Ar-41 7.44E-07 3.7E+02 350 21.2578 Cd 109 2.14E-13 1.1E-04 1 0.3062 1-131 6.09E-13 3.0E-04 1 0.3045 ; H-3 3.10E-08 1.5E+01 350 0.0886 i Pd-103 2.59E 12 1.3E-03 1 0.0519 Je 40 1.73E 14 8.6E-06 1' O.0346 S+76 1.35E-13 6.7E-05 1 0.0169 Ce-34 2.33E-15 1.2E-06 l' O.0116 7o12.$M 8.31E-14 4.1E-05 1 0.0083 i 14 -4 0 4.46E-14 2.2E-05 1 0.0074 , i W 188' 1.30E 13 6.4E-05 1 0.0065 Hg-203 2.90E-14 1.4E-05 1 0.0029 Cs-137 5.32E-15 2.6E-06 1 0.0027 Eu 155 5.24E-15 2.6E-06 1 0.0026 Zn-65 6.23E-15 3.1E-06 1 0.0016 I133 5.18E 12 2.6E-03 350 0.0015 , Rb-86 1.27E 14 6.3E-06 1 0.0013 > Tm-170 3.35E-15 1.7E-06 1 0.0011 Sn 113 7.01E-15 3.5E-06 1 0.0009 [ Pa-233 5.52E-15 2.7E-06 1 0.0007 . Ce-139 5.32E-15 2.6E-06 1~ 0.0006 t I 135 1.18E-11 5.8E-03 350 0.0006 Sc-46 1.30E-15 6.4E-07 1 0.0004 ; As 77 9.51E-12 4.7E-03 350 0.0004 Os 191 7.62E-15 3.8E-06 1 0.0004 Ir-192 1.14E-15 5.7E-07 1 0.0004 [ I 134 4.05E-11 2.0E-02 350 0.0002 Co-57 1.52E-15 7.5E-07 1 0.0002 t 1-132 1.10E-11 5.5E-03 350 0.0002 Re-188 1.63E-12 8.1E-04 350' O.0001 f 1 0.0001 ! Ce-141 7.74E-16 3.8E-07 Xe-135M 1.19E-11 5.9E-03 350 0.0001 Pd 109 1.63E-12 8.1E-04 350 0.0001 , Cd-115 L35E-15 6.7E-07 1 0.0001 { Ba 140 1.21E-15 6.0E-07 1 0.0001 Mn-54 5.60E-16 2.8E-07 1 0.0001 Total 22.1134' , l
- Isotopes observed at <0.0001% TS limit are not listed.
l Stack flow rate 33,500 cfm. VIII-2
SECTION IX
SUMMARY
OF ENVIRONMENTAL SURVEYS 1 January 1994 through 31 December 1994 4 Environmental samples are collected two times per year at eight locations (HP-11: " Environmental Sampling") and analyzed for radioactivity. These locations l are shown in Figum 1. Soil and vegetation samples are taken at each location. i Water samples are taken at three of the eight locations. Results of the samples are 5 shownin the following tables.
- 1. Sampled April 1994.
1 Detection Timits* Matrix Alpha Beta Gamma Tritium l Water 0.8 pCi/l 2.7 pCi/l 245.8 pCi/l 22.8 pCi/ml ofsample Soil 0.8 pCi/g 2.7 pCi/g 0.3 pCi/g N/A Vegetation 1.6 pCi/g 5.4 pCi/g 1.0 pCi/g 22.8 pCi/mi ofdistillate
- Gamma and tritium analyses are based on wet weights while alpha and beta are bated on dry weights.
Determined Radioactivity Levels -- Vegetation Samnles Sample - Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) H-3 (pCi/ml) ___ IV45 < 1.6 27.9 < 1.0 < 22.8 3 2V45 < 1.6 22.2 < 1.0 < 22.8 3V45 < 1.6 21.8 < 1.0 < 22.8 4V45 < 1.6 23.7 1.0 < 22.8 5V45 < 1.6 19.2 1.4 < 22.8 6V45 < 1.6 26.7 1.5 < 22.8 ! 7V45 < 1.6 19.4 < 1.0 < 22.8 10V45 < 1.6 16.8 < 1.0 < 22.8 IX-1
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s Figure 1. MURR Environmental Program Sample Stations il0TE : September 1983 City sewerage plants at stations 8 and 9 closed. All waste .
.water now processed at City Waste Treatment Facility at station 10.
. ~ , .- .. . . - .-- . .l:
Determined Radioactivity Levels - Soil Samples , 1 Sample ' Alpha (pCi/g) - Beta (pCi/g) - Gamma (pCi/g)'- 1845 1.0 - 16.3 4.5 y "2845 < 0.8 12.4 6.1
'3S45 0.8 10.9 '6.8 ~ j , 4S45 0.8 9.6 4.8 )
5845- 0.8 14.3 6.6 l 6S45 < 0.8 7.8 6.2 ' j 7845 1.2 13.9 7.0 l 10S45 0.8 15.2 5.8 i 1 Determined Radioactivity Levels - Water Ramnles Sample Alpha (pCi/l) Beta (pCi/1) Gamma (pCi/1) H-3 (pCi/ml) - ; 4W45 < 0.8 10.9 < 245.8 < 22.8 6W45 1.7 10.7 < 245.8 < 22.8 _ l 10W45 < 0.8 4.7 < 245.8 < 22.8
.i
- 2. Sampled October 1994.
Detection Limits * 'i Matrix Alpha Beta Gamma Tritium Water 0.64 pCi/l 2.19 pCi/l 214.99 pCi/l 12.26 pCi/ml l ofsample : Soil 0.63 pCi/g 2.17 pCi/g 0.33 pCi/g N/A. !
' Vegetation 1.23 pCi/g 4.22 pCi/g 0.79 pCi/g 12.26 pCi/ml a ofdistillate '
' ' Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights. E i
i IX-3 t
p ; F' I Determined Radioactivity Levels -- y;- A l Sample Alpha (pCUg) Beta (pCi/g) Gamma (pCi/g) H 3 (pCi/ml) IV46 < 1.23 15.01 < 0.79 < 12.26 2V46 < 1.23 18.95 < 0.79 < 12.26 3V46 < 1.23 8.95 1.04 < 12.26 4V46 < 1.23 20.75 0.97 < 12.26 . 5V46 < 1.23 15.57 < 0.79 < 12.26 , 6V46 < 1.23 36.07 < 0.79 < 12.26 , 7V46 < 1.23 18.41 1.23 < 12.26 10V46 < 1.23 17.97 < 0.79 < 12.26 i Determined Radioactivity Levels - Soil Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) IS46 < 0.63 12.25 6.63 2S46 0.99 16.65 7.56 3S46 0.83 11.64 6.77 4S46 < 0.63 7.43 3.80 5S46 1.31 14.11 7.36 6S46 < 0.63 10.04 6.76 - 7S46 0.82 12.33 6.73 10S46 0.66 11.55 8.24 - Determined Radioactivity Levels -- Water Sample Alpha (pCi/l) Beta (pCi/1) Gamma (pCi/1) H-3 (pCi/ml) _ l 4W46 2.05 19.01 < 214.99 < 12.26 6W46 < 0.64 12.86 < 214.99 < 12.26 10W46 < 0.64 16.29 < 214.99 < 12.26 IX-4
I p-'&
. lc' ENVIRONMENTAL TLDs The table on the following page lists the external radiation doses acorded by I monitors deployed around MURR in 1994. All doses are about 50 mrem / year orless, l
' except monitor number 9. This monitor is located above the loading dock whom . j packages containing radioactive material are loaded on transport vehicles and the monitor location is shielded from activities in MURR by two feet of concrete. The dose recorded by this monitor is considered to be the result of exposum to packages in transit. To help validate this conclusion, the thini and fourth quarter of 1994 monitors numbered 1, 2, and 3 wem located in the loading dock area. The monitors wem positioned so that they were shielded from packages in transit, but not shielded j from activities in the building. The results of these measurements support the {
~ previous evaluation. Doses recorded by monitors located on the brick exterior of the l building have been corrected to account for the natural radiation emitted from the bricks. Tests indicate that contact with the type of brick used in this facility will add l 15 to 20 mrem / quarter to the dose results. !
l i t i l 1 I IX-5 l l
4: ! s , 4 Environmental TLD Summary January through December 1994 1 f Map Distance fkess' plotQtr.:;: fpSad % sJrdQtr4 $4thQtr %Tletal;, ! fhp#f23j i M231:ssotiW WsitURE8 tack # $1994# $n1994% $1994%@ dBQ994$g g$is g@Npg h$19948 l nue Ryrosn MURR "; Winetiers)WM #NetinRi 1NatimR2 ENuisRs ?NitinR2 t INetinRs i t 1 S 27- 0.6 0.9 2.5 4.3 8.3 - ! 2 S 27 0.6 0.3 7.5 9.5 17.9
- 3 S 27 -0.3 0.0 0.0 9.8 9.5 {
4 S 70 0.9 2.3 0.0 13.1' 16J ; 5 Control N/A -0.7 2.6 1.7 1.4 : 5.0
- 6. NNE 34 9.1 10.4 14.7 15.5 49.7 ;
7 ESE 57 9.7 13.2 13.2 14.5 50.6 j 8 WSW 27 11.5 10.8 - 13.8 13.3 49.4 j 9 SSE 27 46.0 65.4 59.4 65.8 236.6 ' 6.1 0.4 2.5 2.0 11.0 ; 10 NE 149 11 N 149 1.5 5.3 6.4 6.0 19.2 12 ENE 301 5.1 9.2 7.9 8.1 30.3- ; 13 NNE 316 6.6 6.3 6.2 6.0 25.1 i 14 S 156 5.2 9.1 8.6 lost 22.9 ! 15 8 65 2.4 4.1 5.7 12.3 ' 24.5 ! 16 SE 107 3.4 6.1 5.4 5.5 - 20.4 ! 17 E 293 2.8 4.0 lost 6.8 13.6 - 18 NE 476 3.8 5.6 -19.9 7.2 -3.3 ; 19 NNE 606 2.8 5.0 5.9 9.4 23.1 [ 20 NE 907 2.5 5.4 4.9 5.2 18.0 21 SE 236 1.8 4.9 6.1 S.2 19.0-22 ESE 168 -0.8 4.3 ' 1.0 1.6 4.1 23 NW . 110 1.5 7.7 4.0 4.4 17.6 24 SSW 328 2.3 1.5 4.4 4.1 12.3 I 25 SSW 480 3.3 6.0 5.4 8.5 23.2 ! 26 SW 301 3.6 5.8 6.9 7.4 23.7 i 27 WSW 141 -1.4 -0.8 0.7 1.5 0.0 l 28 WNW 210 4.0 6.9 5.5 7.3 - 23.7 29 NW 255 4.4 2.2 6.8 5.6 19.0 ; 30 NNW 328 2.3 5.4 4.4 5.1 17.2 .! 31 NNE 671 5.8 4.4 4.7 6.0 20.9 ! 32 NNW 724 4.9 6.4 6.1 7.5 24.9 33 E 671 -0.4 3.1 1.5 2.6 6.8 ! 34 ENE 587 1.6 2.7 2.9 -0.9 6.3 7 TC SSE 499 4.4 E.7 6.3 7.1 24.5- 'l 36 SE 419 5.0 5.5 5.5 4.7 20.7 37 NE 690 0.7 -0.3 -0.6 1.6 1.4 3 38 NW 556 4.7 7.1 - 7.3 5.3 24.4 i 39 W 491 3.9 5.5 7.2 8.5 25.1 ; 40 N 514 3.5 5.5 6.8 5.9 21.7 ! 41 ENE 137 5.3 6.8 8.9 5.6 26.6 l 42 In Building N/A 8.4 11.4 11.4 12.7 43.9 ; 43 In Building N/A 8.2 11.3 7.3 7.2 34.0 0 . 8 27.7 i
g
- , - j 1
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NUMBER OF FACILITY RADIATION AND CONTAMINATION SURVEYS 1
. . . 1
- Surface - ' Air i 1991 Radiation Contamination * - Samples EET j
_ January. .26 -16 11
~
16 , February- 52 50 15 10 l March 63- 57. 15' 6 1 April 48 38 18 May - ~ 55-62 48 56-13 15 9 8 l June :a i July 41 41 15 5 ; August 54 42 ' 16 13 - September 57 52 19 '7 -l October 94 83 19 5 .i
' November 41 39 16' 5 December 2fi aQ 12 fi ;
y TOTALS 608 562 196 95 l cHeia: In addition, general building contamination surveys are conducted each normal work day. I 4 i Miscellaneous Items In March 1994 Dr. Susan M. Langhorst, Manager, Reactor Health Physics, l returned to the University from sabbaticalin Washington, DC. Upon her return she ' immediately accepted an interim assignment as the Radiation Safety Officer responsible for the Columbia Campus, Broad Scope Materials License. Mr. John l Ernst continues to serve as Acting Health Physics Manager in her absence. August 1,1994, Ray W. Stevens resigned from his position as Senior Health Physics Technician. Ray had been a member of the Health Physics Group for over_ eleven j years. In December 1994, James R. Schuh, Health Physicist and Rex G. Ayers, l Senior Health Physics Technician each received a Masters Degree in Nuclear .!
- Engineering / Health Physics. The current Health Physics staffis as follows: Acting ['
Health Physics Manager, one Health Physicist, one Senior Health Physics Technician, three Health Physics Technicians, one Senior Secretary and two half ; time student assistants. : 1 MURR shipped 660 cubic feet of LSA radioactive waste in the first half of1994. On July 1;1icenrees in Missouri wem denied access to the currently operating waste , i disposal sites. Radioactive waste produced at MURR will be stored for the foreseeable future. ] i IX-7 ;
n 3 The ALARA program was expanded to include the review of releases of ,
. radioactive material to the environment as well as occupational exposure. Releases - !
to the sanitary sewer and from the facility ventilation system are reviewed monthly to ensure that they are not only within the regulations, but are also reasonable for ; the work performed. The average monthly whole body deep dose to individuals in each i ALARA review group are shown in the following table: - Group Name Averare Monthly Dome l Actinide Chemistry - minimal i Computer Development minimal Electronic and Mechanical Properties minimal i Director's Office minimal l Facilities Operations 10 mrem ; l Gamma Ray Scattering 10 mrem 1 Health Physics 50 mrem , Instrument Development minimal
- Magnetic and Crystal Structure 10 mrem ,
i Nanostructures and Excitations 10 mrem ; Neutron Optics 20 mrem ! Analytical Group minimal Nuclear Archaeology and Geochemistry minimal i l Nuclear Engineering minimal Operations 85 mrem Radiopharmaceutical minimal ! Services Applications 25 mrem ! l f i l f i e l DG8 ; r I l l !
k . w p ,h SECTION X-SUlOIARY OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS AhT VISITORS
.1 January 1994 through 31 December 1994 E 1. Largest single exposure and average exposure are expressed in millirem. ]
e i 2. Mini ==1 exposure is defined to be gamma <10 mrem; beta < 40 mrem; neutron < 20 mrem. -
. 3.4 ME = Number of monthly units reported with minimal exposure. j
- 4. AME = Number of monthly units reported with exposure above minimal. 1
- 5. - AE = Average mrem reported for all units above mini ==1 j
- 61 HE = Highest mrem reported for a single unit for the month. :
--7f Dosimetry services except for "Self Reading Dosimeters" am provided by l R. S. Landauer, Jr. & Co., Dosimeter Types: "C" - X, Gamma, Beta, Fast Neutron i
. (Neutrak 144), Thermal Neutron; "G" ; X, Gamma, Beta; "U" - TLD (1 Chip Ring). j
. PERMANENTISSUEBADGES I C"Whole Body Badges (Deep Dose):
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC l M E- 137 150 154 137 160 -147 163 134 159 154 166 160 59 49 46 j! AME 70 64 - 59 75 59 67 54 75 51 58 64 65 63 i AE 63 78 82 G1 83 68 57 54 HE 210 200 700 310 330 210 280 190 170 230 180 160 ?, i
."G"Whole Body Badges (Deep Dose): ,
JAN FEB MAR APR MAY JUN JUL AUG SEP GCT NOV DEC ME 54 63 68 65 64 67 68 58 67 64 67 59 l AME 7 7 2 2 5 2 1 4 1 5 3 5 AE 30 27 30 35 16 30 60 30 30 16 27 18 l HE 70 50 40 50 40 50 60 80 30 30 40 30 ! 1 "U"TLD Finger Rings: i JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC .j 174 129 152 145 '141 138 .I ME 162 140 157 149 163 154 AME 83 104 88 90 78 77 67 91 79 68 76 70 l AE 133 140 216 162 231 159 186 173 145 177 152 125 l 690 1910 1040 3200 970 1430 1070 1020 820 710 690 HE- 500 f SelfReadingDosimeters: JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC .; 12 5 22 19 4 'l ME -18 22 16 22 7 13 8 99 121 97 103 96 104 88 74 91 ] AME 103 107 104 42 46 44 37 36 40 45 43 .I AE 44 48 34 52 318 342 230 224 215 202 177 154 186 HE 183 180 190 , X-1 1 l i
e ; i SECTION X
SUMMARY
OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS AND VISITORS 1 Janu.try 1994 through 31 December 1994 SPAREISSUEBADGES "C"Whole Body Badges (Deep Dose): JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 63 42 47 42 38 47 43 39 34 32 ME 36 59 4 3 6 8 5 6 3 2 1 AME 8 4 3 10 18 30 23 90 33 29 28 30 23 30 _ AE 24 30 40 160 50 60 70 60 50 50 10 HE 50 60 "G"Whole Body Badges (Deep Dose): JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 60 57 53 51 54 48 40 33 34 40 ME 32 43 0 0 2 2 0 0 0 0 0 AME O O 1 0 0 100 0 15 10 0 0 0 0 AE O O 0 100 0 20 10 0 0 0 0 0 HE O O "U"TLD Finger Rings: JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 26 31 31 28 37 30 35 35 34 35 ME 35 32 7 7 9 1 7 3 3 4 3 AME 3 6 9 79 146 77 310 283 47 60 60 53 AE 73 57 87 140 350 200 310 1030 70 110 80 100 HE 100 80 160 X-2 l i}}