ML20138Q660

Reactor Operations Annual Rept for 1996

ML20138Q660
Person / Time
Site:	University of Missouri-Columbia
Issue date:	12/31/1996
From:	Mckibben J, Meyer W MISSOURI, UNIV. OF, ROLLA, MO
To:	NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9703070165
Download: ML20138Q660 (60)

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{{#Wiki_filter:__ I S. '8 Research Reactor Center Research Park II Columbia, Missouri 65211 Telephone (573) 882-4211 UNIVERSITY OF MISSOURI-COLUMBIA FAX [573] 882=3443 l 1 February 28,1997 i i l l Director of Nuclear Reactor Regulation ATTN: Document Control Desk Mail Station F1-37

.             U.S. Nuclear Regulatory Conunission Washington, DC 20555

REFERENCE:

Docket 50-186 ) University of Missouri Research Reactor 4 License R-103 Enclosed is one copy of the Reactor Operations Annual Report for the

            . University of Missouri Research Reactor. The reporting period covers 1 January 1996 through 31 December 1996.                                                       !

i Ifyou have any questions, please feel free to call. 1 Sincerely, q - NI Walt A. MeyerJr. I Reactor Manager bjb enclosure h 1

,           xc: Seymour H. Wei 1, USNRC                                                                      l 4

9703070165 961231 PDR ADOCK 05000186 R PDR m. 9 0700r3 9 J

' UNIVERSITY OF MISSOURI UNIVERSITY OF MISSOURI RESEARCH REACTOR REACTOR OPERATIONS A]NNUAL REPORT 1 January 1996 - 31 December 1996
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L RESEARCH REACTOR FACluTY

UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY l l REACTOR OPERATIONS l ANNUAL REPORT 1 January 1996 - 31 December 1996 [ [ Compiled by the Reactor Staff { Submitted February 1997 by M(  % . Walt A. Meyer, Jr. [ Reactor Manager [ Reviewed and Approved lal / J. Charles McKibben [ Associate Director r P

TABLE OF CONTENTS Section Eage I. Reactor Operations Summary 11 through 6 II. MURR Procedures 11-1 through 6 A. Changes to Standard Operating Procedures B. Changes to MURR Site Emergency Procedures l and Facility Emergency Procedures C. Changes to Health Physics Standard Operating Procedures III. Revisions to the Hazards Summary Report III-1 through 26 f IV. Plant and System Modifications IV-1 f V. New Tests and Experiments V-1 f VI. Special Nuclear Material Activities VI-1 through 2 VII. Reactor Physics Activities VII-1 through 3 VIII. Radioactive Efiluent VIII 1 through 2 IX. Environmental Monitoring and Health Physics Surveys IX-1 through 6 f X. Personnel Radiation Exposures X-1 through 3 { ( {- O [ ... g e. 9

1 SECTION I REACTOR OPERATIONS

SUMMARY

1 January 1996 through 31 December 1996 The following table and discussion summarize reactor operations in the period 1 January 1996 through 31 December 1996. Full Power Full Power % of Full Power % of Date Hours . Megawatt Days Total Time Schedule

• f Jan 1996 647.70 270.00 87.06 97.50 Feb 1996 643.33 268.14 92.43 103.52 Mar 1996 667.27 278.23 89.69 100.45 Apr 1996 623.69 260.02 86.62 97.02 May 1996 663.80 276.84 89.22 99.93 Jun 1996 660.25 275.20 91.70 102.70 Jul 1996 638.46 266.22 85.81 96.11 f Aug 1996 689.36 287.33 95.74 103.77 Sep 1996 641.65 267.49 89.12 99.81 Oct 1996 684.13 285.14 91.95 102.99

[ Nov 1996 669.13 278.89 92.93 104.09 Dec 1996 678.35 282.77 91.18 102.12 Total 90.29% of Time 100.8 % of for Year 7,907.12 3,296.27 for Year at Sched. Time for 10 MW Yr. at 10 MW

     *MURR is scheduled to average at least 150 hours per week at 10 MW. Total time is the number of hours in a month or year.

There were nine unscheduled shutdowns recorded during the period 1 January 1996 through 31 December 1996. Of these unscheduled shutdowr.s, seven were scrams and two were rod run ins. { Two of the unscheduled shutdowns were manually initiated scram or rod run in to allow investigation and/or repair of various reactor equipment. Of the remaining seven unscheduled ( shutdowns, six were spurious, and one was due to low fire main pressure. There were two Licensee Event Reports (LERs) submitted to the NRC in 1996. One in February regarding reactor operation with the regulating blade inoperable for lest than 5 minutes in January [ 1996, and one in July regarding a determination that, subsequent to a week's reactor operation, the Emergency Generator would not have been operable. Neither of the events reported in the LERs represented a safety concern to the reactor or the public. f All Technical Specification required surveillance tests were completed within specified intervals. The surveillance test results are documented to allow for inspection. The surveillance indicated compliance with Technical Specification requirements. ( I

i I January 1996 The reactor operated continuously in January with the following exceptions: five shutdowns for scheduled maintenance and refueling; one unscheduled shutdown. On January 23, a manual scram was initiated by the console reactor operator upon discovering that the regulating blade was not operating properly. Electronics technicians discovered, and replaced, a bad bearing in the gearbox input shaft coupling. The regulating blade was tested satisfactorily, and returned to normal operation. A Licensee Event Report was written regarding this failure which involved non-compliance with Technical Specification 3.2.a, which states, "All control blades, including the regulating blade, shall be operable during reactor operation." On January 29, during scheduled maintenance with the reactor shutdown, one of two redundant anti-siphon valves (V543A) was found to be inoperable. Compliance testing of the anti-siphon system was performed to verify the redundant valve (V543B) was operable. This test verified that the siphon break system was operable as required by Technical Specification 3.9.a. Operability of the siphon break system is also verified at each reactor startup as part of the startup procedure for the primary system. Special Maintenance Procedure, SMP-10 was performed to investigate the V543A failure. The cause of failure was a missing pin connecting the valve stem to the actuating linkage. The valve was removed, rebuilt and tested, and returned to the system. A new pin with a keeper assembly was installed to ensure the pin could not work its way out of the adaptor. This pin had previously been staked into place. The adaptor pin for the redundant valve, V543B, was inspected to ensure a similar problem with it was not occurring. Details of the valve failure and corrective actions were reviewed by the Action Subcommittee (a subset of the Safety Subcommittee) on February 12,1996. These details were reviewed by the full Safety Subcommittee at the June 5,1996, meeting. Other major maintenance items for the month included: replacing the bearing in the input shaft g coupling gearbox of the regulating binde; installing a south pneumatic tube terminal in graphite wedge E

#3; installing new 'G' and 'H' graph: wedges for sample calibration.

Esbrunrv 1996 The reactor operated contimiously in February with the following exceptions: four shutdowns for scheduled maintenance and refueling. On February 5,1996, after shutting down the reactor for a regularly scheduled maintenance day, the control room operator found that anti siphon valve V543A failed to open as expected while securing the primary system. The redundant anti-siphon valve V543B opened as expected. The air operator for V543A had not cycled, which indicated a failure ofits three way solenoid valve to operate normally to vent the air operator and allow spring force to open V543A. Compliance testirig of th'e^ anti-siphon system was performed to verify that V543B was operable. This test verified that the siphon break system was operable as required in Technical Specification 3.9.a. I.2

The failure of the three-way solenoid valve for V543A was investigated by the Reactor Manager to determine if the previous week's maintenance on this solenoid had been performed correctly. A new seal kit had been installed and was verified to be installed correctly. Subsequent rebuilding of the solenoid valve on February 5 resulted in the valve failing to vent after several successful cycles of operation. The entire three-way solenoid for V543A was replaced. Valve 543A was cycled successfully over twenty times. Compliance testing was completed to verify that both anti siphon valves were operable prior to resuming reactor operation. Subsequent bench testing of the three-way solenoid valve indicated an O-ring seal problery associated with the operating piston in the valve. This operating piston was removed from service. Details of the failure and corrective actions were reviewed by the Reactor Action Subcommittee on . February 12,1996. The details were reviewed by the full Safety Subcommittee at the June 5,1996, meeting. Major maintenance for the month included: re installing old 'G' and 'H' graphite wedges; replacing l i the leading trolley hanger bolt and tension spring on the inner personnel airlock door. March 1998 ( The reactor operated continuously in March with the following exceptions: four shutdowns for scheduled maintenance and refueling; one unscheduled shutdown. On March 29, a manual scram was initiated by the duty operator after receiving and verifying a alarm indicating that the fire main water pressure had dropped below the pressure sufficient to supply at least 1,000 gallons per minute to the emergency pool fill system as specified by Technical ( Specification 3.1(c). The loss of fire main system pressure was caused by a fire hydrant pipe rupture during excavation remote from the reactor facility. After the broken fire hydrant was repaired, fire main water pressure was returned to normal and the reactor was refueled and returned to operation. [ Major maintenance items for the month included: shipping sixteen spent fuel elements; replacing the cabi to the channel 4 nuclear instrument detector; loading two new deionization beds for use on ( the pool and primary systems. Anril 1996 The reactor operated continuously in April with the following exceptions: five shutdowns for scheduled maintenance and refueling. There were no unscheduled shutdowns this month. Major maintenance items for the month included: completing the biennial change-out of control blade offset mechanism "B"; replacing the voltage regulator on the wide range monitor; removing ( experimental cans from beamports "E" and "F", and installing new collimators with new fill and drain lines. E , 1-3

I May 1996 The reactor operated continuously in May with the following exceptions: four shutdowns for scheduled maintenance and refueling; one shutdown for maintenance. Major maintenance items for the month included: rebuilding 529 series solenoids B-C F-G-H. S-V; rebuilding pool pump 508B with a replacement bearing housing including new bearings and seals; replacing the front panel on the Gamma Metrics neutron flux monitor; installing the vestibule box en beamport 'E'. E 3 June 1996 The reactor operated continuously in June with the following exceptions: four shutdowns for scheduled maintenance and refueling. There were no unscheduled shutdowns this month. Major maintenance items for the month included: rebuilding Q following 529 series solenoid operated valves: D-L-M-N-Q-R-W-U. July 1996 I The reactor operated continuously in July with the following exceptions: four shutdowns for scheduled maintenance and refueling; four unscheduled shutdowns. On July 1, the Emergency Generator tripped on high coolant temperature 25 minutes into its weekly 30-minute unloaded exercise. The cause was failure of the water pump. Details of the failure I

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were reported to the NRC in a Licensee Event Report dated July 30,1996. On July 2, a rod not in contact with magnet rod run-in occurred when control blade 'B' disengaged from its magnet. No activity was occurring with or near the control blade mechanism when the incident occurred. The control bla'de drive mechar. ism amphenol connect ~' was disassembled and the electronics technicians discovered that one of the leads that supplies powe ne magnet had broken at the pin solder cup. The pin was re-soldered and the connection tested st. .Jactorily. The reactor was returned to normal operation. During the maintenance day shutdown July 9, the intermediate range monitor (channel #2) period indication began oscillating erratically. Electronics technicians replaced the detector and the problem remained. They then replaced the detector cables and connections and the erratic indication ceased. Approximately 3 hours later, a spurious intermediate range monitor (channel #2) short period scram g occurred while the reactor was suberitical during a normal startup. All other period and power 3 indications were normal. The IRM channel #2 detector was again replaced and no further problems of this type have occurred. On July 15, a spurious wide range monitor (channel #4) high power scram occurred simultaneously with a reactor operator closing the channel #4 chart recorder door. All other reactor instrumentation indicated ncrmal prior to and subsequent to the scram, The chart recorder and channel #4 drawer wiring and integrity appeared satisfactory and the problem could not be duplicated. Approximptely one minute after a hot startup was completed, another spurious scram occurred when a reactor operator , closed the source range monitor chart recorder door. Electronics technicians subsequently discovered ~ 1-4

loose connector screws on the channel #4 picoammeter module. The picoammeter module was rescated and the connections were tightened. The instrument functions were tested satisfactorily and the reactor l was returned to normal operation. l The channel #4 drawer problems were further investigated during the following maintenance day, f July 22. The electronics technicians repaired a broken solderjoint on the remote gain potentiometer i I connector which may have contributed to the July 15 unscheduled shutdowns.  ; i Major maintenance items for the month included: repairing a faulty connector pin on control blade [

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        'B' amphenol connector; performing an overhaul of the diesel emergency generator cooling system in response to its water pump failure July 1, which included replacing the water pump, belts, thermostat, pre-high temp. sensor, pre low temp. sensor and associated gaskets, cleaning the radiator, and            f replacing the governor controller; replacing NI channel #2 (IRM) detecter and cables; repairing a broken  (

solderjoint on the remote gain potentiometer connector on the wide range monitor (channel #4). August 1996 The reactor operated continuously in August with the following exceptions: four shutdowns for scheduled maintenance and refueling; one unscheduled shutdowns. On August 12, a rod not in contact with magnet rod run-in occurred while the reactor was f suberitical during a normal startup when control blade *B" disengaged from its magnet. The control rod drive mechanism was removed and some misalignment of the magnet seating surface (the anvil) was noted. The alignment was adjusted and the blade and drive mechanism were further examined and tested and no other problems were noted. The reactor was then returned to normal operation. Major maintenance items for the month included: repairing an air leak in the actuator for pool f isolation valve 509; replacing cooling tower fan #3 motor. Sentember 1996 The reactor eperated continuously in September with the following exceptions: five shutdowns for scheduled maintenance and refueling; two unscheduled shutdowns. b On September 9, a wide range monitor (channel #4) nuclear instrument anomaly scram occurred. Electronics technicians traced the problem to the wide range monitor high voltage power supply (HVPS). This HVPS was replaced and channel #4 was tested satisfactorily. The reactor was returned to normal operation. On September 16, a spurious wide range monitor (channel #4) high power scram occurred during a normal reactor startup. No actual high power was indicated on any instrumentation. Electronics technicians traced the problem to the channel #4 detector, which'was replaced. Channel #4 was tested satisfactorily and the reactor returned to normal operation. \ Major maintenance items for the month included: replacing the sealing gasket air regulator for truck entry door 101; replacing the high voltage power supply on the wide range monitor (channel #4); replacing channel #4 detector; replacing the high voltage power supply on the Gamma-Metrics wide [ .. L I-5

I range amplifier due to source range oscillations; replacing the lower gasket on the north back-up I isolation door. October 1996 The reactor operated continuously in October with the following exceptions: four shutdowns for scheduled maintenance and refue!;ng. Major maintenance items for the month included: replacing the lower gasket on the south back-up isolation door; performing the biennial change-out of control blade ofTset "D"; replacing the calibration feedback module for intermediate range monitor (ND channel #3. November 1996 The reactor operated continuously in November with the following exceptions: four shutdowns for scheduled maintenance and refueling. The annual Reactor Operations / Health Physics NRC inspection p was performed this month, hj Major maintenance items for the month included: replacing the log calibration feedback unit L (Z-14) in intermediate range monitor channel #3. December 1996 The reactor operated continuously in December with the following exceptions: five shutdowns for scheduled maintenance and refueling. Major maintenance items for the month included: replacing the primary heat exchanger 503B differential pressure meter (for differential pressure transmitter 928B); dumping depleted deionization bed "G" to waste barrels--loading new deionization bed "B". I 4 e e 1-6

I SECTION II MURR PROCEDURES 1 January 1996 through 31 December 1996 This section includes the summary of procedure changes required by Technical Specification 6.1.h(4) to be part of the annual report. These procedure changes were reviewed and approved by the Reactor Manager or Health Physics Manager to assure the changes were in accordance with 10 CFR 50.59. These procedure changes are also reviewed by the Procedures Review Subcommittee of the Reactor Advisory Committee to meet 10 CFR 50.59 requirements. A. CHANGES TO THE STANDARD OPERATING PROCEDURES,2nd edition, Effective Date: 5/2/89. (Revisions #1 through #24 to the October 1981 printing were incorporated.) 4 As required by the MURR Technical Specifications, the Reactor Manager reviewed and approved the following:

1. Revision Nc.17. dated 1/4/93 Revision No.17 incorporated various minor changes which were consistent with the original purpose of the procedures (e.g., grammatical and typographic corrections, or clarifications to existing procedures).

2. Revision No.18. dated 5/31/96 Revision No.18 incorporated various minor changes which were consir. tent with the original purpose of the procedures (e.g., grammatical corrections, format changes). One significant change was adding to SOP I.4.2 General Ooerntine Policies. :.h requirements imposed by MURR Materials License Condition 28 when the control room is unstaffed.

f

3. Revision No.19. dated 12/4/96 Revision No.19 incorporated various minor changes which were consistent with the f original purpose of the procedures (e.g., grammatical and typographic corrections, additional clarifications, cross-references to reformatted Health Physics SOPS). One significant change was adding to SOP VIII.2.3, Flux Trno Irradiations. the authorization f to run small diameter seal-welded samples in flooded multi-carrier cans. This change is described in Section V, New Tests and Exoeriments.

B. CHANGES TO THE MURR SITE EMERGENCY PROCEDURES AND FACILITY f EMERGENCY PROCEDURES, dated January 1985; revised and reprinted May 13,1988. ( As required by the MURR Technical Specifications, the Reactor Manager reviewed and [ approved the following:

1. Revision No. 22. dated 6/12/96

[ Revision No. 22 incorporated minor changes which were consistent with the original purpose of the procedures (e.g., telephone number changes, update to emergency call list).

2. Revision No. 23. dated 10/8/96 Revision No. 23 incorporated minor changes which were consistent with the original purpose of the procedures (e.g., telephone number changes, additional clarifications, updating the facility drawing, and updating the list of contact persons in SEP-7, Pubhc Information Procedurg),

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1 l l C. CHANGES TO HEALTH PHYSICS STANDARD OPERATING PROCEDURES j Manual issued 10/29/90: HP-42. Rev. O. dated 7/17/96 New procedure which provides r adance in performing sealed source leak tests. HP-43. Rev. O. dated 8/27/96 New procedure which provides instructions for shipping LSA, radioactive waste when a waste broker has been contracted to handle the shipment. The format of the Health Physics Standard Operating Procedures manual was revised and was reissued in its entirety October 18,1996. Health Physics and Reactor Chemistry Procedures were divided into eight sections based on their particular application and are now contained in a single manual. The new format was developed in an effort to improve the ease of using the manual. The Table of Contents of the 2nd Edition of the Health Physics Standard Operating Procedures M provided here followed by a summary of revisions to existing procedures and a listing of new procedures. I' I MURR IIEALTH PHYSICS STANDARD OPERATING PROCEDURES TABLE OF CONTENTS I. ADMINISTRATIVE CONTROL s

 -       HPA-1         Rev.O     Request for Radiation Safety Evaluation                                  i HPS-2         Rev.1     Radiation Work Permits HPd-3         Rev.2     Controlled Special Exposures: ALARA Considerations                      i HPA-4         Rev.4     PersonnelIndoctrination Documentation HPA-5         Rev.O     MURR Indoctrination Train %g Program                                  g IIPA-6        Rev.2     MURR Identification Badge F ogram and Implementation HPS-7         Rev.1     Beamport Area Access                                                  E II. PERSONNEL MONITORING                                                                             i i

IIP /II-1 Rev.3 Issuing Radiation Dosimeters at MURR Reception Desk IIP /II-2 Rev.1 Review of Unplanned Radiation Exposures IIPMI-3 Rev.2 Report of Personnel Contamination l HPMI-4 Rev.4 II-3 Air Samples I IIPMI-5 Rev.3 Tritium Bioassay III. INSTRUMENTATION IIP /III-1 Rev.4 Calibration of Radiation Survey Instruments l IIP /III-2 Rev.1 Self-Reading Dosimeter Calibration IIP /III-3 Rev.2 Calibration of Stack Particulate Channel: NMC Model AM-22IF HPSII-4 Rev.3 Calibration of Stack Iodine Channel: NMC Model AM 221F HPMII-5 Rev.3 Calibration of Stack Gas Channel: NMC Model AM-221F IIP /III-6 Rev.0 Stack Monitor Preventive Maintenance: NMC Model RAK HP/III-7 Rev.O Calibration of Stack Monitor System: NMC Model RAK HPMII-8 Rev.O Calibration of Stack Particulate Channel: NMC Model RAK IIPAII-9 Rev.O Calibration of Stack Iodine Channel: NMC Model RAK i HPSII-10 Rev.O Calibration of Stack Gas Channel: NMC Model RAK IIP /Ill-11 Rev.O Calibration and Operation of Canberra Model 2404 Alpha / Beta / Gamma System HPMII-12 Rev.O Calibration and Operation of Tennelec LB-5100 Alpha / Beta 11-2

[1 )

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HPMII-13 Rev.O Calibre. tion and Operation of Baird Polyspec HPMII-14 Rev.O Calit ation and Operation of Eberline BC-4 Beta Counter HPMII 15 Rev.O Portal Monitor Calibration / Optimization tiPMII 16 Rev.O Portal Monitor Figure of Merit Functional Test HPMII-17 Rev.O HFM 10 Calibration / Optimization HPAII-18 Rev.0 HFM 10 Source Check HPMII-19 Rev.0 Efiiciency Calibration on VAX HPMII 20 Rev.0 Energy Calibration on VAX HPMII 21 Rev.O Reactor Chemistry Trending HPMII-22 Rev 0 Quench Curve on the Searle Liquid Scintillation Counter HPMII 23 Rev.O Preparing Tritium Standard for Searle Liquid Scintillation Counter HPMII-24 Rev.O Preparing Europium Sources f IV. HEALTH PHYSICS APPLICATIONS HPAV-1 Rev.1 Standard Contamination Wipe Procedure { HPSV-2 Rev.3 Receiving and Opening Packages of Radioactive Material l HPSV-3 Rev.1 Transfer of Radioactive Material Within Reactor Building HPSV-4 Rev.1 Murr Hot Cell Operation HPAV-5 Rev.3 Cobalt-60 Facility Safety Checks HPAV-6 Rev.3 Co-60 Facility Pool Water Analysis HPSV-7 Rev.O Sealed Source Leak Test Procedure V. ENVIRONMENTAL MONITORING HPN-1 Rev.2 Environmental Sampling HPN-2 Rev.3 Analysis of Radioactivity in Environmental Samples ( HPN-3 Rev.3 Changing Stack Monitor Filters: NMC Model AM-221 F l HPN-4 Rev.O Changing Stack Monitor Filters: NMC Model RAK HPN 5 Rev.3 Analysis of Particulate and Charcoal Filters HPN-6 Rev.1 Tritium Monitoring of Stack Air Exhaust HPN-7 Rev.4 Waste Tank Analysis HPN-8 Rev.4 Secondary and Sump Water Analysis HPN-9 Rev.O Survey ofItems for Unrestricted Release VI. WASTE MANAGEMENT . HPNI1 Rev.0 Experimenters Waste Disposal Procedure HPNI2 Rev.1 Direct Barrel Compaction Operation HPNI-3 Rev.1 Shipment of Radioactive Material NOS, Waste HPNI-4 Rev.4 Exclusive Use Shipment of Radioactive Material, LSA Waste HPNI-5 Rev.O Non-Exclusive Use Shipment of Radioactive Material, LSA Waste HPNI-6 Rev.1 Shipment of Radioactive Material, LSA Waste or SCO Waste Utilizing [ a Broker VII. REACTOR OPERATIONS SUPPORT [ HPNII1 Rev.2 Room 114 Unscheduled Entry HPNII-2 Rev.2 Handling Radioactive Materialin MURR Pool HPNII-3 Rev.3 Health Physics Monitoring of Beam Ports for Reactor Start-up [- HPNII-4 Rev.6 Pool and Primary Water Analysis HPNII-5 Rev.3 Spent Fuel Shipping Cask Analysis VIII. HEALTH PHYSICS EMERGENCY PROCEDURES IIPNIII-1 Rev.2 Air Sampling During Reactor Emergency HPNIII-2 Rev.0 Evaluation of Exhaust Gas Stack Monitor Filters in an Emergency HPNIII-3 Rev.1 Remote Sampling of Containment Air C m II-3

I l

    'Ihe following existing Health Physics and Reactor Chemistry Standard Operating Procedures were not revised except to change the procedure number to follow the new format:

I HP1 Request for Radiation Safety Evaluation; new # HPS-1. HP-2 Room 114 Unscheduled Entry; new # HPNII 1 HP-9 Standard contamination Wipe Procedure; new # HPdV 1 HP-11 Environmental Sampling; new # HPN-1 HP-12 Transfer of Radioactive Material Within Reactor Building; new # HP/IV-3 HP 13 MURR Hot Cell Operation; new # HPAV-4 l HP-17 H 3 Air Samples;new # HP/II 4 l HP19 Self Reading Dosimeter Calibration; new # HPHII 2 HP-22 Review of Unplanned Radiation Exposures; new # HPMI 2 HP 28 Exclusive Use Shipment of Radioactive Material, LSA Waste; new # HPNI-4 ' HP-29 Health Physics Monitoring of Beam Ports for Reactor Start up; new # HPNII-3 , HP-30 Evaluation of Exhaust Gas Stack Monitor Filters in an Emergency; new # HPNIII-2 HP-34 MURR Identification Badge Program and Implementation; new # HPS-6 HP-35 Beamport Area Access; new # HPA-7 . HP-36 Remote Sampling of Containment Air; new # HPNIII-3 HP-37 Experimenters Waste Disposal Procedure; new # HPNI-1 HP-39 Shipment of Radioactive Material NOS Waste; new # HPNI-3 HP-40 Survey ofItems for Unrestricted Release; new # HPN-9 g' g HP-41 Non-Exclusive Use Shipment of Radioactive Material, IEA Waste; new # HPNI-5 HP-42 Sealed Source Leak Test Procedure; new # HPAV-7 RCAI-1 Analysis of Particulate and Charcoal Stack Filters; new # HPN.5 E' E, RCSI 2 Pool and Primary Water Analysis; new # HPNII-4 RCSII-1 Analysis of Radioactivity in Environmental Samples; new # HPN-2 l RC/III-2 Calibration of Stack Particulate Channel: NMC Model AM 221F; new # HP/III-3 RCSII-3 Calibration of Stack Iodine Channel: NMC Model Am 221F; new # HP/III-4 RCSII-4 Calibration of Stack Gas Channel: NMC Model AM 221F; new # HP/III-5 RCSII-5 Co-60 Facility Pool Water Analysis; new # HPAV-6 The following is a summary of revisions to existing Health Physics and Reactor Chemistry Standard Operating Procedures: HP-3 Receiving and Opening Packages of Radioactive Material; new # HP/IV-2. Revised to include directions to verify Project Authorization and materialinventory. The revision also includes package receipt requirements specified in 10 CFR 20. HP-4 Handling Radioactive Material in MURR Pool; new # HPNII-2. Revised to clarify responsibilities and limitations covered by this procedure. HP6 Air Sampling During Reactor Emergency; new # HPNIII-1. Revised to include steps necessary for relocation of analysis equipment in the event the MURR laboratory building is evacuated. HP-8 Controlled Special Exposures: ALARA Considerations; new # HP/I 3. Revised to limit the number of reactor positions permitted to authorize a controlled special exposure. IIP-10 Radiation Work Permits; new # llP/I-2. Revised to include more detailed ir structions for completing the documentation required for using a Radiation Work Permit. II-4

{ HP 14 Changing Stack Monitor Filters; new # HPN-3. The title was revised to specify which stack monitor is covered by this procedure. { HP 18 Calibration of Radiation Survey Instruments; new # HPAII 1. Revised to include a blank example of the Certificate of Calibration used to document instrument calibration. ( HP-20 Report of Personnel Contamination; new # HP/II-3 Revised to include a blank example of the survey form used to document personnel contamination, f HP-21 Urine Tritium Analysis; new # HP/II-5. Revised in its entirety to provide more detailed instruction for performing tritium analysis and calculation of sample activity. [ HP-24 Issuing Radiation Dosimeters at MURR Reception Desk; new # HP/II-1. Revised to t clarify the definition of visitors and temporary workers and provide instructions for issuing appropriate dosimetry. HP-25 Cobalt-60 Facility Safety Checks; new # HPSV-5. Revised to incorporate updated [ instructions for performing radiation alarm detector source checks. HP-27 Calibration of Sample Counting Systems. Deleted; this procedure was superseded by ( HP/III 11, -12, 13 and -14. HP-31 Personnel Indoctrination at MURR; new # HPS-4. Revised title to distinguish procedure from a newly developed procedure covering other aspects of the indoctrination process. HP-32 Tm 170 Wafer / Pellet Transfer and Packaging. Deleted; this process is no longer performed at MURR. HP-33 Operation of Sample Counting Systems. Deleted; this procedure was superseded by HPMII 11, -12, -13 and 14. HP 38 ( Direct Barrel Compaction Operation;new # HPNI-2. Format was revised to comply with standardized method ofidentifying individual procedural steps. HP-43 Shipment of Radioactive, LSA Waste Utilizing a Broker; new # HPNI 6. Revised to [ include instructions for shipping Radioactive SCO waste. RCS3 Tritium Monitoring of Stack Air Exhaust; new # HP/V-6. Revised to provide directions for using a new sampling station. The revision includes instructions for calculating tritium { stack concentration. RC/II 3 Gamma Analysis of Quality Control Silicon. Deleted; superseded by procedures {' documented in the Service Applications Silicon program. RCSV-2 Waste Tank Analysis; new # HPN 7. Revised to include instructions for using either the Searle LSC or the new Packard instrument to perform sample analysis. [ RCAV-3 Spent Fuel Shipping Cask Analysis; new # HPNII-5. Revised in its entirety to provide step by step instructions for performing the sample analysis. [ RC/IV-4 Preparation of Waste Tank Carrier Solution & Titration for Use. Deleted; carrier solution is no longer used to treat waste tank water. [ RCAV-5 Gamma Analysis of Flux Monitors. Deleted; flux monitors are now analyzed by protocols developed for individual research applications. _ RCSV-6 Secondary and Drain Tile Sump Water Analysis; new # HPN-8. Revised to include [ directions to sample cooling tower and tunnel sump as well as the secondary and drain tile sump. - e 11-5

I l The following are new Health Physics Standard Operating Procedures issued in 1996: 1 \ l HPM5 MURR Indoctrination Training Program l l HPMII-6 Stack Monitor Preventive Maintenance: NMC Model RAK HPMIl-7 Calibration of Stack Monitor System: NMC Model RAK HPMII-8 Calibration of Stack Particulate Channel: NMC Model RAK HPAII-9 Calibration of Stack Iodine Channel: NMC Model RAK HPMII 10 Calibration of Stack Gas Channel: NMC Model RAK HPMII-11 Calibration and Operation of Canberra Model 2404 Alpha / Beta / Gamma System HPMII-12 Calibration and Operation of Tennelec LB-5100 Alpha / Beta HPAII-13 Calibration and Operation of Baird Polyspec HPMII-14 Calibration and Operation of Eberline BC-4 Beta Counter g{ gi HPSII-15 Portal Monitor Calibration / Optimization HPMII-16 Portal Monitor Figure of Merit Functional Test l HPMII-17 HFM-10 Calibration / Optimization g, E HPMil 18 HFM-10 Source Check HP/III-19 Efficiency Calibration on VAX i HPMII 20 Energy Calibration on VAX HPAII-21 Reactor Chemistry Trending HPMII-22 Quench Curve on the Searle Liquid Scintillation Counter HPMII-23 Preparing Tritium Standard for Searle Liquid Scintillation Counter HPMII-24 Preparing Europium Sources  ! HPN-4 Changing Stack Monitor Filters: NMC Model RAK l I l 4 I I~ e~ ee

f SECTION III REVISIONS TO THE HAZARDS

SUMMARY

REPORT 1 January 1996 through 31 December 1996 These changes were reviewed by licensed staff and by members of the Safety Sub-committee and have j been determined not to involve a change in Technical Specifications or an unreviewed safety question as defined in 10CFR50.59. [- HAZARDS

SUMMARY

REPORT (ORIGINAL JULY 1,1965) Original HSR, page 3-3, Section 3.2.3, paragraph 1, sentence 2: f Delete: "Each of the two doors is electrically driven closed and when in the closed position contacts a microswitch which activates an air valve to inflate a gasket which seals against the door." [ Reolace with: "Each of the two doors is electrically driven closed and when in the closed position l contacts in a cam actuated microswitch activate an air valve to inflate a gasket which seals against the door." ( Original HSR, page 3 6, Section 3.2.6, paragraph 2, sentence 1: Delete "In addition to the eight pneumatic tubes running through this steel plate there are a number of pipes welded to the plate to permit compressien of the building . . . ." Reolace with: "In addition to the eight pneumatic tubes running through this steel plate there are a number of pipes welded to the plate to permit pressurization of the building . . . ." 1995 Revision to Original HSR, page 3 7, Section 3.2.8, paragraph 1, sentences 2 and 3: Delete. "This emergency air compressor normally " rides" on the main air supply line until there is a {~ drop of pressure in the main air line t'o less than 85 psi. At that time the small emergency air compressor comes on and a check valve closes off all of the compressed air system external to the containment building." ( Reolace with: "This emergency air compressor normally " rides" on the main air supply line until there is a drop of pressure in the main air line to less than 70 psi. At that time the small emergency air compressor comes on and a check valve closes off all of the compressed air system external to the containment building, except for backup [ door supply." 1995 Revision to Original HSR, pago 3-8, Section 3.2.8, paragraph 3, sentence 1: Delete "This system is equipped with check valves and automatic starters such that if there is a failure or loss of compressed air from the main unit, the emergency air system will come on and carry the inflatable gaskets and any other air controlled devices associated with the ( reactor." Renlace with: "This system is equipped with ched valves and automatic starters such that if there r is a failure or loss of compressed air from the main unit, the emergency air system ( will come on and carry the inflatable gaskets and any other air controlled devices associated with reactor isolation." Original HSR, page S-9, Section 3.3, paragraph 2,last sentence: { Delete: "This heavy equipment door to the outside will only be opened when the reactor is completely shut down." { r ._ 111-1

Reclace with: "This heavy equipment door to the outside will only be opened when the reactor is secured." Original HSR, page 3 9, Section 3.3, paragraph 3, sentence: Delete "Specifically, a high radiation level detected in the off-gas line to the stacks will initiate a signal that will provide building closure." Renlace with: "Specifically, a high radiation level detected in the off gas line to the stacks or high radiation at the reactor bridge willinitiate a signal that will provide building closure." 1995 Revision to Original HSR, Figure 3.1: Reninee with: Updated Figure 3.1- Basement Level (MURR Dwg #2269, Sheet 1 of 5, dated 12/19/95) 1995 Revision to Original HSR, Figure 3.2: Renlace with: Updated Figure 3.2--Grade Level Plan (MURR Dwg #2269, Sheet 2 of 5, dated 12/19/95) 1995 Revision to Original HSR, Figure 3.3: Renlace with: Updated Figure 3.3.a--Third Floor Plan (MURR Dwg #2269, Sheet 3 of 5, dated 12/19/95) Updated Figure 3.3.b--Fourth Floor Plan (MURR Dwg #2269, Sheet 4 of 5, dated 12/19/95) Updated Figure 3.3.c- Fifth Floor Plan (MURR Dwg #2269, Sheet 5 of 5, dated 12/19/95) 1995 Revision to Original liSR, Figure 3.8: Renlace with: Updated Figure 3.8--Cooling Tower Building at Grade Plan (dated 5/20/96) Original HSR, pages 4 5 and 4-6, paragraphs 2 and 3; 1968 Revision to Original HSR: Delete: 'The shim blades are constructed of formed boral plate. The neutron absorbing material is 50% boron carbide and 50% aluminum, by weight. The boron carbide aluminum mixture is clad with .030 inches of aluminum, The nominal blade thickness is 0.200 (rev 1968) inches. The sides and bottom of the blades have a 1.0 inch aluminum frame where the blade thickness is 0.25 inches." Renlace with: "The shim blades are constructed of formed boral plate. The neutron absorbing 3l, material is nominally 50% boron carbide and 50% aluminum, by weight. The boron carbide-aluminum mixture is nominally clad with 0.0375 inches of aluminum. The E nominal blade thickness is 0.175 inches. The sides and bottom of the blades have a 0.25 inch aluminum frame where the , blade thickness is 0.25 inches." l Original HSR, p' : ' 8, Section 5.4.2: Delete "The secondary water flows on the shell side of the reactor primary and pool heat , exchangers. These exchangers are as described in Sections 5.2.3 and 5.3.5." i l Renlace with: "The secondary water flows on the shell side of the reactor primary heat exchanger, and on the opposite plate side of the pool coolant in the pool heat EI exchanger." 3 III-2 l I

1974 and 1971 revisions to Original HSR, page 5 9, Section 5.4.3, paragraph 1: Add the followine sentence to end of naracranh:

               "The fans will be configured to run as necessary to provide sufficient cooling for reactor 10 MW l        operation."

Original HSR, Figure 5.1: f Renlace with: Updated Figure 5.1--Piping & Instrument Diagram (MURR Dwg #156, dated 10/4/95) Original HSR, Section 8.1, page 8-1, first paragraph, first sentence: l Delete 'The prime purpose of a university . ." { Renlace with: 'The primary purpose of a university . ." Original HSR, Section 8.1, page 8-1, first paragraph, last sentence: f Delete "The result may suffer from certain shortcomings which may be overcome in an AEC test reactor, however, it is possible . . . . " Renlace with: 'The research history of MURR shows it is possible . . . . " Original HSR, page 8 2, Section 8.2, paragraph 3, sentence 2: Delete 'This canister consists of a hollow aluminum tube assembly which is inserted in the center test hole previous to startup." Renlace with: "This canister consists of a hollow aluminum tube or a triple tube assembly which is inserted in the flux trap prior to startup." 1968 Revision to Original HSR, page 8-2, Section 8.2, paragraph 3: Delete. "These capsules are originally maintained in their positions by a locking rod latched at the assembly top canister." Rentace with: "These capsules are maintained in their positions by a locking rod or rods latched at {- the assembly top canister." Original'HSR, page 8 2, Section 8.2, paragraph 3,last sentence: Delete "The canister has a closure at the top to preclude . Renlace with: "The canister top is designed to preclude . Original HSR, page 8-2, Section 8.2, paragraph 4, first sentence: Delete "All sample insertions into the flux trap position are subject to review by the reactor { supervisor. Renlace with: "All sample insertions into the flux trap position are subject to review by the Reactor ( Manager." - 1968 Revision to e ginal HSH, Section 8.5, pages 8 2 & 8 3, paragraph 4, sentence 2: [ Delete "The reactor shift supervisor will supervise the installation and removal of the canister during shutdown; he will see that either a canister is in place or that a cover is provided over the test hole previous to startup." r . . 111-3

Reolace with: "A senior reactor operator will supervise the installation and removal of the canister during shutdown and see that either a canister is in place or that a l strainer is provided over the test hole prior to startup." Original HSR, page 8-3, Section 8.2, paragraph 6, sentence 2: Delete "AEC"; Reolace with "NRC" Original HSR, page 8-5, Section 8.3, paragraph 2, sentence 1: Delete "The prime use of the beamports . .." Reolace with: "The primary use of the beamports . . . . " Original HSR, pages 8 5 & 8-6, Section 8.3, paragraphs 4 & 5: Delete:

      "The tangential beamports have been installed to minimize the fast neutron and gamma ray             3 background. The beamport plug assemblies, which provide shielding for the tangential ports, are          g!

identical to those used in the radial ports. In addition to the expected utilization of the beamports for neutron diffraction or neutron chopper work it is contemplated that a port may occasionally be used in a " loop" type experiment. For this E purpose there are available experimental cans mounted as extensions of a modified shield plug. 3 These modiGed shield plugs have helical conduits through them to admit electrical leads and utility lines to the experimental can. A water line is put through all shield plugs whether the plug is designed for experimental use or shielding. Utilizing this water line it is possible to Good the port when it is not in use or to provide cooling water to an experiment if this is required." Original HSR, page 8-6, Section 8.3, paragraph 7, sentences 2 & 3: Delete: "Further, the reactor supervisor will determine if any of the parameters should be used to activate an annunciator and/or the reactor scram system. Spare annunciator positions are available for this purpose." Reolace with: "Further, the Reactor Manager will determine if any of the parameters should be used to activate an annunciator and/or the reactor scram system." Original HSR, page 8-7, Section 8.3, paragraph 11, sentences 3: Delete "All ports are closed with a three inch lead . . " Reolace with: "All ports can be closed with a 3-inch lead . . " Original HSR, page 8-7, Section 8.3, paragraph 11,last sentence: Delete "When the port is not in use it may be filled or drained without opening the door by means of a valving system recessed in the door immediately below each beamport." Reolnce with: "When the port is not in use it may be filled or drained without opening the door by means of an external valving system when the reactor is shutdown." Original HSR, page 8-8 Section 8.3,2nd paragraph on page: Delete "Within the rEMble port liner is located the beamport plug. The plug is also closed with a bolt ring and gasket such that the regica in front of the plug, or between the end of the plug and the end cMne movable port liner, can be Gooded with water and, if necessary at higher power, can be water cooled." Reolace with: "Within the movable port liner is located the collimator liner. The collimator liner is also closed with a bolt ring and gasket such that the region in front of the collimator liner'and the end of the movable port liner can be Gooded with water." 111-4

i 1988 and 1989 Revisions to Original HSR, Section 8.4, page 8 9: Delete section:

          " Irradiation baskets are housed in various elements in the graphite reflector region. There were originally 12 removable graphite elements between Beamports "A" and "F" which could be replaced with irradiation baskets (modified graphite elements to house samples during irradiation at relatively high thermal neutron Hux). (rev 1988)

This graphite region has been modified. A large wedge shaped irradiation basket occupies two rows (30*) of the original four row (60') design. This wedge is an aluminum helium filled structure with six irradiation positions. Two solid aluminum elements, one with a 3 inch O.D. and the other with a 1 inch O.D. irradiation basket, occupy one of the original rows (15'). Two pneumatic tubes terminating in solid aluminum elements and a solid small graphite element occupy the remaining row (15'). (rev 1988) The remainder of the graphite reflector region (300') originally consisted of ten (10) 30' wedges (designated elements 1,2,3,4,5A,5B,6,7,8,9) comprised of graphite canned in aluminum. Four of these 30' graphite wedges have been modified to provide irradiation baskets (positions) between Beamport "C" and Beamport "D". The graphite element at position 4 has been replaced with a graphite wedge accommodating both a 2 inch O.D. and a 3 inch O.D. irradiation basket. The graphite elements at positions 5A and 5B have been replaced with elements that each accommodate a 5-1/2 inch O.D. irradiation basket (rev 1989). The graphite element at position 6 has been replaced with an element containing a solid graphite block which provides one 3 inch O.D. irradiation basket and a 1/4 inch I.D. hole to house self-powered neutron detectors (rev 1989). (rev 1988) All samples that are irradiated are verified to be covered by an approved Reactor Utilization Request (RUR), prepared and scheduled for irradiation by the Reactor Services group. A record is kept of all irradiations. Various forms are utilized based on the type of sample and position required for irradiation. (rev 1988) Renlace section with:

           "The graphite reflector region outside the permanent beryllium reflector is made up of removable reflector elements which can be reconfigured to provide sample irradiation positions. These irradiation positions are used to introduce samples of greater size, and for a longer time, into a relatively high thermal neutron flux than would be normal for the pneumatic tube system.

Each of the removable reflector element locations is capable of supporting several types of irradiation samples. Changes in sample irradiation configurations are analyzed for reactor safety, i approved by the Reactor Manager, and reviewed by the Safety Subcommittee." l 1981-82 Revision to Original HSR. Section 8.5, page 8-10, paragraph 1, sentence 3: Delete. "The system consists of up to four reactor terminals, up to six sending. receiving stations,  ! two deflector switches, orie sole ~rioid cabinet, one turbo-compressor together with the I necessary piping, tubinis, electrical conduit, and mounting hardware." Renlace with: "The system consists of up to four reactor terminals, up to six sending-receiving stations, two deflector switches, one solenoid cabinet, two turbo-compressors I together with the necessary piping, tubing, electrical conduit, and mounting hardware. Currently only two reactor terminals and four sending receiving stations are used." Original HSR, page 811, Section 8.5, paragraph 2,last sentence: Delete " Automatic timing is available for periods varying from two seconds to 20 minutes." Reolace with: " Automatic timing is available for periods varying from 2 seconds to 120 minutes." Original HSR, page 811, Section 8.5, paragraph 3, sentence 2: Delete "First, two of the pneumatic tubes . Renlace with: "First, each of the pneumatic tubes . 111 5

I, Original HSR, page 812, Section 8.5, paragraph 6, sentence 2: Delete "There are four webs each of 0.22 inch thickness with a vertical web cross section, per inch oflength, of 0.875 square inches." Reolace with: "There are four webs each of 0.22 inch thickness with a vertical web cross section of 0.875 square inches per inch of length." Original HSR, Figure 8.1, Beamport Assembly: Reolnee with- Updated Figure 8.1, Beamport Assembly (dated 11/15/96) Original HSR, page 9-12, Section 9.3.3: Delete section:

        "Two identical intermediate range channels are functioning during all phases of reactor operation. The intermediate range neutron detectors are compensated ion chambers mounted in the pool outside the reflector region at approximately core center line elevation in water tight containers.

The intermediate range detection locations are variable both vertically and radially. The compensated ion chambers deliver a d.c. signal proportional to neutron flux to the intermediate range monitor chassis which are mounted on the instrument panel. The intermediate range monitor develops an output which is proportional to the logarithm ofion chamber current. The logarithmic output :s delivered to local and remote levelindicators and to a recorder. The logarithmic output also drives a period amplifier which delivers a period signal to two independently adjustable trip circuits and to a local and remote period indicator. The remote period and level indicators are located on the control console. A single intermediate range power level recorder serves both intermediate range monitors. The channel to be recorded is switch selected by the operator at the control console." Renince with:

        "Two intermediate range channels are required to be operable during all phases of reactor operation. The intermediate range neutron detectors may either be compensated ion chambers (CIC) or fission chambers mounted in the pool outside the reflector region at approximately core centerline      g elevation in water tight drywells. The intermediate range detector locations are designed such that detector locations may be varied both vertically and radially. The compensated ion chamber (CIC) g based intermediate range channel delivers a d.c. signal proportional to neutron flux to an intermediate range monitor chassis which is mounted on the instrument panel. The intermediate range monitor develops an output which is proportional to the logarithm ofion chamber current. The logarithmic output is delivered to local and remote level indicators and to a recorder. The logarithmic output also drives a period amplifier which delivers a period signal to two independently adjustable trip circuits and to a local and remote period indicator. The remote period and level indicators are located on the control console.

The fission chamber based intermediate range channelis part of wide range monitor that operates in both the pulse counting mode and the mean. square-voltage (MSV) mode. g1 The Wide Range signal is a series of randomly spaced pulses superimposed on a d.c. voltage, The pulse signal is processed by one of the log count rate and rate-of-change circuit boards and the g d.c. voltage signal is processed by the log amplifier, rate-of. change, and auctioneer circuit board. The  ! log count rate circuit provides an output that is proportional to the logarithm of the average count rate of pulses of the Wide Range signal over the range of about 10-8% to 3 x 10-2% power. The log amplifier circuit provides an output that is proportional to the logarithm of the mean square variation of the Wide Range signal over the range of about fiva decades, from 10 3% to 200% of i reactor power. i The two signals are combined by the auctioneer circuit to provide one continuous output over the l range of10-8% to 200% of reactor power. Two rate-of-change circuits associated with these log l signals provide outputs that are also combined to provide one continuous rate-of-change signal over l the full reactor flux range. The combined log output and period output are displayed locally on the i plasma displays on the front panel and remotely on the control console. l The two ' intermediate range level indications will be capable of being recorded, although only one  ; IRM level indication is required to be recorded." I I l l Ill-6

Original HSR, Figure 9.6: Renlace with: Updated Figure 9.6--Operating Bridge Plan View (dated 2/7/97) Original HSR, Figure 10.1: Renlace with: Updated Figure 10.1 -Main Reactor Equipment Room (MURR Dwg #2463, Rev. 0) Original HSR, page 11 11, Section 11.8.3: Delete. " Daily routines patrols will be established for the mechanical and electrical technician, a reactor operator and the health physicist." Reolace with: " Daily patrols (Monday Friday) are established for a mechanical technician and a member of the health physics group. Reactor Operations performs routine patrols every day the reactor operates, including weekends and holidays." Original HSR, page 11 12, Section 11.10, list of parameters: Delete: " Linear power (one of three channels to be selected)." Renlace with: " Linear power" Original HSR, Section 12:

    +_

Delete the followinc chrases throuchout section: f Reactor Supervisor; Reactor Health Physicist

         - Renlace with:
         ' Reactor Manager; Reactor Health Physics Manager Original HSR, page 121, Section 12.1; 1982 Annual Report revisions:

f Delete. l "The reactor and laboratory facilities will be available to any faculty member or graduate student interested in pursuing research involving radiation, radioisotopes, or the reactor. The diverse research programs initiated will be coordinated and health and safety supervision provided { by the permanen' staff employed to operate the facilities. The research stafT, composed of faculty members and graduate students, will be semi-transient, since no permanent assignment of space or facilities will be made. Administration of the reactor and laboratory will be divorced from the research programs to eliminate the possibility of a compromise in safety for the sake of experimental f expediency. The research reactor facilities staffis divided into two groups. One group, the reactor-operating group, has responsibility for the routine operation and maintenance of the reactor. The second, the f laboratory-operations group, has responsibility for the supervision and maintenance of the laboratory ( facilities associated with the reactor. Coordination and overall administration of these groups is performed by the director of the project. A current table of organization for the Research Reactor Facility based upon continuous operation 7 days a week is presented in Figure 12.1 of this report [ (rev 1982), It is estimated that the staff requirements for operation of these facilities on an i eight-hour day, five-day week, will be twelve to sixteen people. These people will provide operation and supervision of the facilities for all research personnel, expected to number from thirty to sixty people. The Research Reactor Facility fits within the organizational structure of the University of Missouri as a separate entity. " ~ III-7 e

Renlace section with (chances boldedh

       'The reactor and laboratory facilities are available to faculty members or graduate students interested in pursuing research involving radiation, radioisotopes, or the reactor. The diverse research programs are coordinated and health and safety supervision provided by the permanent staff employed to operate the facilities. Part of the research staff, composed of faculty members and graduate students, will be semi-transient, with no permanent assignment of space or facilities.

Administration of the reactor is separate from the research programs to eliminate the possibility of E a compromise in safety for the sake of experimental expediency. The Research Reactor operations stafris divided into two groups. One group, the reactor E operations group, has responsibility for the routine operation and maintenance of the reactor. The second, the facility operations group, has responsibility for the supervision and maintenance of the laboratory facilities associated with the reactor. Coordination and overall administration of these groups is performed by the Facility Director. A current table of organization for the Research Reactor Facility based upon continuous operation 7 days a week is presented in Figure 6.0, , Technical Specifications. The Reactor Operations stafTrequirements for operation of these facilities is expected to be twelve to sixteen people. These people provide operation and supervision of the facilities for all research personnel. The Research Reactor Facility fits within the organizational structure of the University of Missouri as part of the Columbia campus." Original HSR, page 12-4, Section 12.2.3: Add sentence to end of section:

        "He will be assisted in the performance of these duties by the Operations Engineer and Reactor Shift Supervisors."                                                                                        '

Original HSR, page 12 4, Section 12.2.5, first paragraph: Delete naracraoh 1: I "The Reactor Health Physicist is not part of the Research Reactor Facility Staff. He is l responsible to the Radiological safety oflicer who,in turn, reports to the Dean of Research l Administration. The Reactor Health Physicist is permanently housed at the Research Reactor i Facility." l i Add to becinning of second naracranh:

        'The Reactor Health Physics Manager is part of the Research Reactor Facility stafT."                  l Original HSR, page 12-6, Section 12.2.6, paragraph 1, last sentence:

Add the bolded chrase to the end of the sentence:

        "During work periods when they are not operating the reactor these individuals will continue their training and will assist in routine maintenance, repair operations, and c mole handling."

1968 Revision to Original HSR, page 12 7, Section 12.2.7, sentence 2: Delete "The shops will be under the direct supervision of the Reactor Supervisor." Reolace with: "The shops will be under the direct supervision of the Facilities Operatione Manager." Original HSR, page 12-7, Section 12.3, paragraph 1: Delete first naracranh which reads:

        "The reactor operators will be hired and a teaching and training program completed at the University of Missouri prior to reactor startup. In this manner, these individuals can procure          E valuable experience in the final construction and installation of machinery, as well as with the        E electronics associated with the contrrl of the reactor. The machinist and electronic technician will also be trained in the first group of reactor operators to permit them to procure an operator's license so that they might be better prepared to do maintenance on the reactor."

111-8

l Original HSR, page 12-7, Section 12.3, paragraph 2: ( Delete.

                "The training program for operators will consist of a series oflectures on reactors, reactor safety, general health physics, reactor control systems, and postulated reactor malfunctions. These lectures will be coupled with a series of experiments which will demonstrate the utilization of health-physics

{ equipment, the operation of components of the reactor systems, and the operation of the reactor controls. This program of training will prepare these people for the A.E.C. operator's license examination." Renlace with (chances boldedh "The training program for operators will consist of guided self-study on reactors, reactor safety, general health physics, reactor control systems, and postulated reactor malfunctions and ( emergency response. This study will be coupled with on-the-job training which will demonstrate the utilization of health physics equipment, the operation of components of the reactor systems, and the operation of the reactor controls. This program of training will prepare these people for the NRC operator's license examination." 1974 Revision to Original HSR, page 12-7, Section 12.3, paragraph 3: Delete "Following licensing by the AEC. . . ."; Renlace with: "Following licensing by the NRC. . { Original HSR, page 12 8, Section 12.4, paragraph 2, sentences 1 through 4: ( Delete. "There will be one afternoon of each week open for visitors between the hours of 1 and 5

                                                                                        ~

p.m. Nontechnical visitors will be guided through the facility oy a trained student guide. This guide will be equipped with the normal personnel-monitoring equipment and he will be instructed to stay with the group of12 to 25 people assigned to him. He will take the group ( on a preassigned path through the fecilities." Renlace with: "Nontechmcal visitors will be guided through the facility by trained guides. These guides will be equipped with the normal personnel-monitoring equipment and he [ will be instructed to stay with the group of10 to 15 people assigned to them. They take the group on a preassigned path through the facilities." { Original HSR, page 12 9, Section 12.4,last paragraph,last two sentences: Delete " Technical visitors who have no desire to view the facilities but who wish only to speak to members of the staff or use the library facility, will not be required to have a film badge for ( intermittent visits. Ifit is their intent to work in the library or any of the facilities for an extended period of time, they must comply with the established regulations for use of the facilities." Original HSR, page 12 9, Section 12.5, first paragraph: Delete:

                "The research reactor facilities shall be available for research utilization by any member of the

[ faculties of the University of Missouri and of the universities comprising the Mid. America Association of State Universities. Priorities for the use by the faculty members of any specialized facilities on the reactor shall be established by the simple technique of"who asked first." In the event that questions ( arise as to the advisability of such a priority assignment, these questions will be negotiated with the Reactor Advisory Committee, and their findings will be final." Renlace with: [ "The research reactor facilities shall be available for research utilization by members of the faculty of the University of Missouri and other universities. Priorities for the use of any specialized facilities on the reactor shall be established by the Facility Director. In the event that questions arise as to the advisability of a priority assignment, these questions will be reviewed by the [ Reactor Advisory Committee, and their recommendations made to the Facility Director." Y L 111-9

l 1 Original HSR, page 1210, Section 12.5, paragraph 3, sentence 2 through end of paragraph: Delete " Space and radiation facility assignments will be made by the Reactor Supervisor in consultation with the chairman of the graduate student's research committee (or his advisor). Routine irradiations for graduate students who have demonstrated competency in the handling of radioactive materials may be performed without the approval of his faculty advisor." Renlace with: " Space and radiation facility assignments will be made by the Director in consultation with the graduate student's MURR radiation work supervisor. Routine irradiations for graduate students who have demonstrated competency in the handling of radioactive materials may be performed when authorized by the MURR supervisor." ADDENDUM 1 HAZARDS

SUMMARY

REPORT (FEBRUARY 1966) HSR, Addendum 1 Item 3.1, page 6, paragraph 10, sentence 1: Delete "The control rod drive system will receive a thorough inspection in addition to the rod drop checks following approximately every 4000 hours of operation above 100 KW but not less than once per week." Renlace with: "The control rod drive system will receive a thorough inspection in addition to the rod drop checks." HSR, Addendum 1. Item 3.1, page 6, paragraph 10: Add new sentence to end of naracranh:

       " Currently each b'ade is checked once every two years with one blade done every six months."

HSR, Addendum 1, Item 3.11, page 32, paragraph 8,last sentence: Delete "The automatic valves on the sixteen inch and six inch ventilation pipes are both quick acting and close in less than one second." Renlace with: "The automatic valves on the 16 inch ventilation pipes are quick acting and close in about three seconds." IISR, Addendum 1, Section 3.17, pages 84 and 85 and first paragraph of page 86: Delete neces 84 and 85:

       "As an illustration of the type of experimentation expected for the beamports consider four experiments presently under construction.

One of the port experiments currently under construction on this campus consists of apparatus for slow nautre; scatter studies under the direction of Professor Horace Danner. Considerations which are being made at this time have to do with the shielding of the neutron and gamma radiation penetrating through the collimator. Shielding calculations are being made and collimator design is being dictated partially by these shielding calculations. Calculations were made and design established for the heat flux generated in the collimator assembly. A part of the collimator consists of an annulus oflead located approximately five feet from the reactor core. It is recognized that this gamma shield, which is surrounded by a cadmium neutron absorber, will undergo some gamma heating. Initially it was planned that this shield would be made of a low melting lead-bismuth alloy. However, calculations showed that the temperature rise in such a material would closely approach the melting point of the material. Lead has been , substituted in place of the low melting alloy. The remainder of the materials in this collimator consist of high melting point materials. Another criteria to which this experiment has been subjected has to do with the voiding of the beamport. When this collimator assembly is not in use the assembly will be flooded with water. To E initiate a neutron beam the collimator assembly and beamport will be drained. It will be a part of E the low-level calibration work to evaluate the void coeflicient of this beamport. 111-1 0

l A second beamport experiment consists of a dual beam, triple axis, neutron diffractometer currently on order from Japan. (This unit is identical to that installed at the CP-5 type reactor at f Ames, Iowa.) This research program is under the supervision of Dr. Newell Gingrich of the Physics Departmeo Those criteria having to do with beamport Good and void reactivity measurements and collimator materials and their heat generation are the same in this experiment as in the previous one. This experiment must also be properly shielded. Calculations are being made to determine the f requisite shielding for this experiment. Still a third beamport experiment currently being prepared for insertion in the reactor is one r under the direction of Dr. Robert Hurst. This is research having to do with capture gamma-ray { measurements. This research group is also constructing a collimator, internal to which there 'viil be an irradiation position where various materials may be subjected to thermal neutron bombardment. The emergent beam,in this instance, will be capture gammas of energies to 10 mev. Criteria [ applied have to do with reactivity addition on void or flooding of the beamport, heat generation in the l collimator materials, and shielding external to the biological shield. A fourth study currently in design has to do with the measurement of neutron scattering spectrum and is under the direction of Dr. Ed Dowdy of the Nuclear Engineering staff. Again, criteria for review of this experiment have to do with reactivity addition by flood and void of beamport, heat ( generation in the collimator assembly inserted in the beamport, and shielding external to the biological shield." [ Delete first naracraoh of onge 86:

           "In summary it might be said that the criteria applicable to all"in reactor" experiments have to do with reactivity insertion or removal, heat production in the irradiated material, and shielding requirements external to the confines of the reactor pool or the biological shield."

HSR, Addendum 1, Section 3.17, page 86, second paragraph, second and third sentences: Echte: "Under this general classification one finds the grouping of experimental facilities including ( the flux trap position, the irradiation baskets, the lmeumatic tubes and any in pool samples external to the reflector. All experiments of this type are subject to review by the reactor supervisor and the reactor health physicist." Reolace with: "Under this general classification one finds the grouping of experimental facilities including the flux trap position, the graphite reflector positions, the pneumatic tubes, and any in pool samples external to the reflector. All experiments of this type [ are subject to review by the Reactor Manager and the Reactor Health Physicist." HSR, Addendum 1, Section 3.17, page 86, third paragraph, sentence 1: Delete "The reactor supervisor critically reviews the proposed experiments to ascertain the reactivity affect, the problem of heat generation, the possibility of sample decomposition, and the general precedence for this type ofirradiation." [ Reolace with: "The Reactor Manager critically reviews the proposed experiments to ascertain the reactivity effect, the problem of heat generation, the possibility of sample decomposition, and the general precedence for this type ofirradiation through the [ review of a Reactor Utilization Request (RUR)." HSR, Addendum 1, Section 3.17, page 86,last two sentences of paragraph 3: Delete "It is pertinent to point out that samples positioned in the flux trap or in the irradiation baskets will not be moved during reactor operation. Those samples in the pneumatic tube positions will be moved in and,out while the reactor is operating." [ Reolace with: "It is pertinent to point out that samples positioned in the flux trap will not be moved during reactor operation. Those samples in the graphite reflector and pneumatic tube positions may be moved in and out while the reactor is operating." j t III-11

I HSR, Addendum 1, Section 3.17, page 87, paragraph 1, sentence 1: Delete: "In any instances where the reactor supervisor feels that he is not qualified to make a judgement pertaining to the safety of a proposed experiment he may refer the experiment to the Reactor Advisory Committee." Raolace with: "In any instances where the Reactor Manager feels that he is not qualified to make a judgement pertaining to the safety of a proposed experiment he may refer the experiment to the appropriate subcommittee of the Reactor Advisory Committee." HSR, Addendum 1, Section 3.17, pages 87 and 88: Ilclete:

      "The charge delivered by the President of the University to the Reactor Advisory Committee reads as follows:

Purnose: The purpose of the Reactor Advisory Committee is to provide to the Research Reactor g Facility a body of experts representing a variety of technical disciplines from which advice, counsel and direct assistance relative to matters of safety and experiment design can be drawn. E The Committee shall assist in the determination of priority in the assignment of facility space and time. Tia Committee shall assist in the establishment and assessment of facility-use charges. The Committee shall review procedures pertaining to nuclear and experimental operations. Certain experiments, as defined by the reactor supervisor. shall be presented to the Reactor Advisory Committee for approval. The final design of the experiments must have the written approval of the Committee. 1 Meetines: The Committee shall convene normally once each month or at the request of the a reactor supervisor. An agenda shall be prepared and distributed prior to each meeting." g Renlace with:

  "Resnonsibilities:

The Reactor Advisory Committee is the Committee of the University of Missouri appointed by the  ; University of Missouri-Columbia (UMC) Chancellor to satisfy requirements imposed by the federal government. The University and the Nuclear Regulatory Commission expect this Committee to review and make recommendations concerning experimental and operational activities at the Reactor Facility. Responsibilities of the Committee are partially set forth in the Technical Specifications portion of the reactor operating license as follows:

1. Review and make recommendations concerning proposed changes to reactor equipment or procedures when such changes have a safety significance, involve an amendment to the operating license including a change in the Technical Specifications, or create an unreviewed safety 3 question as defined by 10 CFR 50.59.

2. Review and make recommendations concerning proposed tests or experiments significantly E different from any previously reviewed or which involve an unreviewed safety question as defined by 10 CFR 50.59.

3. Review circumstances of all abnormal occurrences and violations of the Technical Specifications and the remedial measures taken or to be taken to prevent recurrence.

The Committee shall act in an advisory capacity to the Director of the Reactor Facility in matters pertaining to the safe operation of the reactor and with regard to planned research activities and use of the facility building and equipment. It may independently explore policies and procedures as they relate to interaction with other administrative elements of the University and with clients of the su Reactor Facility that are not part of the University. It will respond to matters brought before it by the Director, researchers, or other University administrative ofTicials. g The Committee, through its Chairman, may appoint subcommittees consisting of students, faculty, and staff of the University when it is deemed necessary to delegate a part ofits responsibilities. Membership on subcommittees need not be limited to appointed members of the Committee. Subcommittees may be authorized to act in behalf of the Committee." lil-12

HSR, Addendum 1. Section 3.17, page 88, paragraph 4, sentence 2: Delete "First, it is the jury for ascertaining the safety of any experiments which the reactor supervisor or the reactor health physicist feels are subject to questic n." Reolace with: "First, it is the jury for ascertaini .g the safety of any experiments which the Reactor Manager or the Reactor Health Physicist feel are subject to question." HSR, Addendum 1, Section 3.17, page 89: Delete.

           "As an indication of the " degree ofindependence" possessed by the Reactor Advisory Committee it seems logical to enumerate the makeup of this Committee. The name and rank of each Committee member follows:

Duane Fitzgerald - Reactor Supervisor (Executive Secretary) Clifford Thompson - Anoc. Prof. Physics Don Gibson - Assoc. Prof. Mechanical Engineering John L. Cassidy - Assoc. Prof. Civil Engineering Edward J. Dowdy Asst. Prof. Nuclear Engineering f Robert L. Carter Professor Electrical Engineering Ellis Graham Professor Soils (Chairman) Dave Troutner Assoc. Prof. Chemistry ( Deyle R. Edwards Director, Nuclear Reactor Facility, Rolla, Mo. I Jcb .Yan - Radiation Safety OfIicer Bob Marriott - Asst. Business Manager & Safety Coordinator ( Jim McQuigg - Meteorologist, U.S. Weather Bureau and Research Assoc. in Soils University of ( Missouri

 !    Carl Jansen - Resident in Radiology George Leddicotte - Laboratory Supervisor, Research Reactor Facility Only one member of the reactor operating staffis a member of this Committee. The reactor

{ supervisor is executive secretary of the Committee. It is felt that in this position he can determine the need for assembling the Committee, he can define the reactor operations, and he can point out questionable experiments to the Committee membership." HSR, Addendum 1, pages 94 96: Delete " laboratory supervisor" Reolace withi " principal experimenter" ADDENDUM 2 - HAZARDS

SUMMARY

REPORT (MAY 1966) HSR, Addendum 2, page 5,last paragraph of page, sentence 2: Delete "It will be the function of the reactor staff, the laboratory supervisor, and . . . . " Reolace with: "It will be the function of the reactor staff, the principal experimenter, and . . . ." HSR, Addendum 2, page 6, Reactor Utilization Request form: At the too of once 6 incert the following note: ( "(This is a historical representation of a Reactor Utilization Request (RUR). RURs currently in use include all information asked for in this form, but may include more detailed information and analysis.)" 111-1 3

HSR, Addendum 2, Item 8, page 19, paragraph 3, sentence 1: Delete "The air which drives the pneumatic cylinder is delivered through a normally energized solenoid valve." Reolace with: 'The air which drives the pneumatic cylinder is delivered through two normally energized solenoid valves." HSR, Addendum 2, Item 8, page 19, paragraph 3, sentence 2: Delete 'These " backup" isolation doors operate only in the event of radiation existing in the ' ventilation chambers of the east building tower." l l Reolace with: "These " backup" isolation doors operate in the even', of radiation existing in the ventilation chambers of the east building tower or nigh radiation levels at the reactor bridge." , HSR, Addendum 2, Item 8, page 20, paragraph 6, sentences 5 through 7: Delete "ARer a few seconds wait the normal door circuitry will again send the door closed. If the obstruction has cleared, the door will complete the isolation cycle. If not, it will continue to cycle open and close, but will not damage itself." Reolace with: "The door will only close if the operator pushes the button to close the door." l ADDENDUM 3 - HAZARDS

SUMMARY

REPORT (AUGUST 1972) HSR, Addendum 3, page 35, Item 2.5.4.2, IS8 (SBM) Power Level table: Delete Column I headinc: ".1 MW" Reolace with: "50 kW" 1995 Revision to HSR, Addendum 3, page 14, Section 2.2.2.10: Revision stated: " Changed tense from past to present tense." Should have read: " Changed ten;e from futiire to past tense." 1995 Revision to HSR, Addendum 3, page 15, sections 2.2.3.2, 2.2.3.3, 2.2.3.4: Revision stated: ' Changed tense from past to present tense " Should have read: " Changed tense from future to past tense." I i g{ 111-14 5 l

   )

ADDENDUM 4 HAZARDS

SUMMARY

REPORT (OCTOBER 1973) HSR, Addendum 4, Appendix A, Item A.3.14, page A-22, paragraph 2, sentence 1: Delete: " Bypass switches are utilized to change the protective system to correspond to the three modes of operation (0.1 MW,5 MW, or 10 MW)." f Reolace with: " Bypass switches are utilized to change the protective system to correspond to the three modes of operation (50 kW,5 MW, or 10 MW)." HSR, Addendum 4, Appendix A. Item A.3.3.4, page A 8, paragraph 1, sentence 1: Delete "The period scram channels WI channels 2 and 3) and the power level scram channels (NI channeis 4,5 and 6) have separate detectors and separate electronics chassis (Refer to section 2.5.2 of Addendum 3 to Hazerds Summary Report)." { Reolace with: "The redundant period scram channels (NI Channels 2 and 3) have separate detectors and separate electronics chassis. The redundant power f level scram channels (NI Channels,4,5 and 6) have separate detectors and separate electronics chassis. (Refer to section 2.5.2 of Addendum 3 to Hazards Summary Report)." HSR, Addendum 4, Appendix A, Item A.33.11, page A 13, paragraph 3, sentence 1:

1. Delete "At present, all potentially radioactive gases from the pool, pneumatic tube system, beamports, thermal column . . . ."

Reolace with- "At present, all potentially radioactive gases from the pool, beamports, thermal column . . . ." HSR, Addendum 4, Appendix A, Item A.33.11, page A-14, paragraph 3, sentence 7: Delete " Control and operation are identical to the present valve, except the new valve is air to open, f spring-loaded to close." Reolace with: " Control and operation are identical to the first valve, except the second valve is air. to-open, spring-loaded to close." { HSR, Addendum 4, Appendix A, Item A.33.11, page A-14, paragraph 3, sentence 9: I Delete " Air is supplied from the same source as the present valve." { Reolace with: " Air is supplied to both valves from a common source." (' HSR, Addendum 4. Appendix A, Item A 33.11, page A-14, paragraph 3: i Add a new naracraoh after oaracraoh 3: i

           'The pneumatic tube exhaust is routed through particulate filters directly to the MURR off-gas

[- stack in the west tower The old 4 inch line in the containment building has been sealed." [ . r L 111 15

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SECTION IV PLANT AND SYSTEM MODIFICATIONS 1 January 1996 through 31 December 1996 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 50.59. Modification 95-3: Relocation of oneumeu tube to south side of reflector This modification package documents the relocation of the pneumatic tubes from north side graphite reflector region to south side reflector region, graphite wedge number 3. I Modification 96-1: Removal of Nuclenore cas lines. isolation valves and valve control wiring This modification documents the removal and capping of Nuclepore gas lines and isolation valves. Nuclepore was a fueled experiment which has been removed from service and the reactor. The isolation valves and control wiring were part of the reactor isolation system. I I I I I I I I I _. I IV-1 I

SECTION V i NEW TESTS AND EXPERIMENTS 1 January 1996 through 31 December 1996 Addendum to RUR-219: This addendum authorized small diameter seal welded samples to be run inside standard size

               " flooded" sample cans for flux trap irradiations. These " flooded" cans provide the mechanical support to keep the smaller diameter samples rigidly 6xed within the can, but allows water contact to the surface of the smaller diameter samples.

The use of" flooded" cans is limited to small diameter seal-welded samples that can retain the same number of barriers (e.g., double or single encapsulation) to the release of contents as evaluated in target specific Reactor Utilization Requests (RURs) A number of beamport floor experimental equipment upgrades are nearing completion that are part of a class of experiments previously evaluated and do not involve an unreviewed safety question as per 10 CFR 50.59. l ( l { { { l L V-1 . . . ..i. .

SECTION VI SPECIAL NUCLEAR MATERIAL ACTIVITIES 1 January 1996 through 31 December 1996

1. SNM Receipts: A total of 24 new fuel elements were received from Babcock and Wilcox (B & W), Lynchburg, Virginia.

Grams Grams Shipper Ehments U U-235 B&W MO-453, MO-454, MO-455, MO-456, MO-457, MO-458, 19,944 18,575 MO-459, MO-460, MO-461, MO-462, MO-463, MO-464, MO-465, MO-466, MO-467. MO-468, MO-469, MO-470, MO-471, MO-472, MO-473, MO-474, MO-475, MO-476

2. SNM Shipments: A total of 16 spent fuel elements were shipped to DOE facilities at Savannah River Plant, Aiken, South Carolina.

f Grams Grams Shipper Elements , U U-235 f MURR MO-377, MO-379, MO-382, MO-384, MO-385, MO-386, 11,253 9,948 MO-387, MO-388, MO-389, MO-390, MO-391, MO-392, MO-394, MO-396, MO-402, MO-404

3. Inspections: None.

f 4. SNM Inventory: As of 31 December 1996, MURR was financially responsible for the following DOE-owned amounts: f Total U = 58,240 grams Total U 235 = 51,993 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 171 grams of U and 90 grams of U-235. All of this material is physically located at the MURR. ( ( ( r- yI.1 e r*

l The fuel elements on hand have accumulated the following burn-ups as of 31 December 1996. 1 l l Burned-un Elements (28) l Element No. MWD Element No. MWD Element No. MWD l ) MO-393 123.264 MO407 116.854 MO-417 134.856 l MO 395 123.264 MO-408 138.484 MO-418 133.286 MO-397 122.151 MO-409 133.083 MO-419 132.195 MO-398 118.747 MO410 134.506 MO-420 132.195 MO-399 122.151 MO-411 133.083 MO-421 138.741 MO-400 118.747 MO412 134.506 MO-422 138.384 MO401 139.760 MO-413 134.876 MO-423 138.741 MO-403 139.760 MO-414 134.856 M O-424 138.884 MO-405 116.854 MO-415 134.876 MO-406 138.484 MO-416 133.286 Elements in Service (52) MO-425 134.615 MO-443 93.718 MO-461 87.058 MO-426 118.692 MO 444 MO-427 134.615 96.724 MO-462 75.417 g MO-445 103.949 MO-463 87.058 g MO-428 118.692 MO-446 95.176 MO-464 75.417 MO-429 112.257 MO-447 103.949 MO-465 71.119 MO-430 104.517 MO-448 95.176 MO-466 54.285 MO-431 112.257 MO-449 103.975 MO-467 71.119 MO-432 104.517 MO-450 94.128 MO-468 54.285 MO-433 96.415 MO-451 103.975 MO-469 37.376 MO-434 95.224 MO-452 94.128 MO-470 9.595 MO-435 96.415 MO-453 ' 104.871 MO-471 37.376 MO-436 95.224 MO-454 90.060 MO-472 9.595 MO-437 90.972 MO-455 104.871 MO-473 2.045 i MO-438 89.843 MO-456 90.060 MO-474 0.000 l MO-439 90.972 MO-457 91.114 MO-475 2.045 MO440 89.843 MO-458 84.611 MO-476 0.000 MO-441 93.718 MO-459 91.114 MO-442 96.724 MO-460 84.611  ! Average Burn-up (all elements): 99.44 MWD I Il l VI-2 l l

l SECTION VII REACTOR PHYSICS ACTIVITIES 1 January 1996 through 31 December 1996

1. Fuel Utilization: During the period 1 January 1996 through 31 December 1996, the following elements reached feasible burn-up and were retired:

Serial Number Final Core Date Last Used MWD ( MO-401 96-10 03-04-96 140 MO-403 96-10 03-04-96 140 MO-406 96-13 03-25-96 138 {- MO-408 96-13 03-25-96 138 MO-409 96-28 06-24-96 133 [ MO-410 96-33 07-29-96 134 i MO-411 96-28 06 24-96 133 MO-412 96-33 07-29-96 134 MO-413 96-38 09-03-96 125 l t MO-414 96-19 04-29-96 135 MO-415 96-38 09-03 96 135 MO416 96-18 04-22-96 133

f. MO-417 96-19 04-29-96 135 MO-418 96-18 04-22-96 133 MO-419 96-27 06-17-96 132

[- MO-420 96 27 06-17-96 132 MO-421 96-43 10 07-96 139 MO-422 96-50 11 25-96 139 MO-423 96-43 ( MO-424 96-50 10-07-96 11-25-96 139 139 Due to the requirement of having less than 5 kg of unirradiated fuel in possession, initial [ criticalities are obtained with four new elements or fewer as conditions dictate. A core designation consists of eight fuel elements of which only the initial critical fuel element serial r numbers are listed in the following table of elements in service 31 December 1996. To [ increase operating efficiency, fuel elements are used in mixed core loadings. Therefore, a fuel element fabrication core number is different from its core load number. I VII-1

I Fabrication Initial Core Initial Serial Number Core Number Load Number Oneratine Date MO-449 68 96-1 01-02-96 MO-450 69 96-3 01-16-96 MO-451 69 96-1 01-02-96 MO-452 69 96-3 01-16-96 MO-453 69 96-4 01-22-96 MO-454 69 96-13 03-18-96 MO-455 69 96-4 01-22-96 MO 456 69 96-13 03-18-96 MO-457 70 96-14 03 25-96 MO-458 70 96-21 05-06-96 MO-459 70 96-14 03-25-96 MO-460 70 96-21 05-06-96 MO-461 70 96-24 05-20-96 MO-462 70 96-32 07-15-96 MO-463 70 96-24 05-20-96 MO-464 70 96-32 07-15-96 MO-465 71 96-34 07-29-96 MO-466 71 96-43 09-30-96 MO-467 71 96-34 07-29-96 ' MO-468 71 96-43 09 30-96 g MO-469 71 96-47 10-28-96 E MO-470 71 96-55 12-23-96 MO-471 71 96-47 10-28-96 MO-472 71 96-55 12-23-96  ! MO-473 72 96-56 12-30-96 MO-475 72 96-56 12-30-96

2. Fuel Shipments: Sixteen spent fuel elements were shipped from MURR to Savannah River Site, Aiken, South Carolina. The identification numbers of these elements are:

l MO-377, MO-379, MO-382, MO 384, MO-385, MO-386, MO-387, MO-388, MO-389, MO-390, MO-391, MO-392, MO-394, MO-396, MO-402, MO-404 El lj

3. Fuel Procurement: Babcock and Wilcox, Lynchburg, Virginia,is MURR's fuel assembly fabricator. This work is contracted with the U.S. Department of Energy and administered by EG&O Idaho Inc., Idaho Falls, Idaho. As of 31 December 1996,277 fuel assemblics fabricated by B & W had been received and 275 used in cores at 10 MW.

I I VII-2

4. Licensing Activities: On March 15,1995, the Nuclear Regulatory Commission approved Amendment No. 28 to the facility operating license R-103. This amendment temporarily increased the Special Nuclear Material inventory limit to 75 kg U-235 to May 31,1997, pending the completion of spent fuel shipments. This amendment also authorized possession of up to 60 kg of U-235 without an expiration date.

Amendment 28 requires that this annual report include the status of spent fuel shipments. Two shipments of eight fuel elements each were completed in 1996, and four such shipments are scheduled in 1997. MURR staff continue their efforts to achieve more regular acceptance of spent fuel at Savannah River Plant with limited success. The Department of Energy has to contend with the spent fuel nseds of university research reactors, DOE reactors, and with the receipt and storage of foreigr. fuel. This has lead to uncertainty and continuing changes to our spent fuel shipping opportunities. A request for a unique purpose exemption as defined in 10 CFR 50.2 was submitt-d September 26,1986, and is pending.

5. Reactor Characteristic Measurements: Fifty-six refueling evolutions were completed. An excess reactivity verification was performed for each refueling and the average excess reactivity was 1.90%. The largest excess reactivity was 2.41%. MURR Technical Specification 3.1(f) requires that the excess reactivity be less than 9.8%.

f Reactivity measurements were performed for five evolutions to verify reactivity parameters for the flux trap. Three differential worth measurements were made on shim blades. One differential worth measurement was made on the regulating blade. I ( { f .. 1 [ VII-3

[ SECTION VIII ( RADIOACTIVE EFFLUENT 1 January 1996 through 31 December 1996 ( TABLE 1 SANITARY SEWER EFFLUENT { 1 January 1996 through 31 December 1996 [' Descending Order of Activity Released for Nuclide Totals > 1.00E-05 Ci Nuclide Activity (Ci) H-3 1.487E-01 S-35 3.764E-03 [ Ca-45 1.724E-03 Co-60 9.962E-04 (.- Zn-65 5.608E-04 As-77 3.546E-04 Re 186 3.855E-05 { Cd-109 2.950E-05 { Re-188 Nb-95 2.621E-05 2.358E-05 Cr-51 1.743E-05 { Total H 3 1.487E-01 Total Other 7.534E-03 [ f' VIII-1 r

i i TABLE 2 l STACK EFFLUENT 1 January 1996 through 31 December 1996 Ordered by % Technical Specification (TS) Limit Average Total Release Concentration 1/96- 12/96 TS Limit Isotope Ci/ml (Ci) __ Multiplier % TS* Ar-41 1.62E-06 7.28E+02 350 46.2632  ; Cd 109 1.32E 13 5.94E-05 1 0.1889 Hg-203 1.48E-12 6.67E-04 1 0.1484 1131 2.93E-13 1.32E-04 1 0.1467 H-3 2.50E-08 1.12E+01 350 0.0715 Zn 65 2.69E 14 1.21E-05 1 0.0067 Ce 144 1.29E-15 5.81E-07 1 0.0065 Se-75 4.85E-14 2.18E-05 1 0.0061 S-35 1.60E 13 7.20E-05 1 0.0053 Cs-137 1.01E 14 4.54E-06 1 0.0050 Co-60 1.45E-15 6.50E-07 1 0.0029 Eu 155 4.21E-15 1.89E-06 1 0.0021 Sc-46 4.57E-15 2.05E-06 1 0.0015 Os 191 8.98E-15 4.04E-06 1 0.0004 Cd-115 6.28E-15 2.82E-06 1 0.0003 1133 1.08E-12 4.87E-04 350 0.0003 Cl-38 4.00E-11 1.80E-02 350 0.0002 Ce-141 1.16E 15 5.22E-07 1 0.0001 Ce-139 1.27E-15 5.73E-07 1 0.0001 Br 82 1.99E 12 8.93E-04 350 0.0001 Pa-233 9.04 E-16 4.06E-07 1 0.0001 1-135 2.12E-12 9.54E 04 350 0.0001 Total 46.8568

• Isotopes observed at <0.0001 % TS limit are not listed.

Stack flow rate = 30,198 cfm W i-2

l l SECTION IX f ENVIRONMENTAL MONITORING AND HEALTH PHYSICS SURVEYS 1 January 1996 through 31 December 1996 ( Environmental samples are collected two times per year at eight locations and analyzed for radioactivity. The sempling locations are shown in Figure 1. Soil and vegetation samples are taken at each location. Water samples are taken at three of the eight locations. Analytical results are ( shown in Tables 1 and 2. Table 3 lists the radiation doses recorded by environmental monitors deployed around MURR in 1996. All doses are about 50 mrem / year or less, except monitor numbers 9 and 15. These ( monitors are located near the loading dock where packages containing radioactive material are loaded on transport vehicles. The doses recorded by these monitors are considered to be the result ( of exposure to packages in transit.

• The number of radiation and contamination surveys performed each month are provided in Table 4.

Table 1 Summary of Environmental Set 49 April 1996 ( Detection Limits

• Matrix Alpha Beta Garama Tritium Water 1.83pCi/l 2.86 pCi/l 204.12 pCi/l 9.96 pCi/mi

[. of sample Soil 1.4 pCi/g 2.18 pCi/g 1.27 pCi/g N/A Vegetation 2.8pCi/g 4.36 pCi/g 4.54 pCi/g 7.87 pCi/ml of distillate

• Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry

                                                                                ~

weights. [ Activity Levels -- Vegetation (. Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/g) H-3 (pCi/ml) 10V49 < 2.8 < 4.36 < 4.54 < 7.87 IV49 < 2.8 5.60 < 4.54 < 7.87 [ 2V49 < 2.8 < 4.36 < 4.54 < 7.87 3V49 < 2.8 < 4.36 < 4.54 < 7.87 4V49 < 2.8 < 4.36 < 4.54 < 7.87 5V49 < 2.8 < 4.36 4.92 < 7.87 6V49 < 2.8 < 4.36 5.00 < 7.87 7V49 < 2.8 < 4.36 < 4.54 < 7.87 [ [ IX.1 I L e i . . . - -

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_ M * . . l> j; - l f cw . /  ; Figure 1. MURR Environmental Program Sample Stations j NOTE: September 1983 City sewerage plants at stations 8 and 9 closed. All waste i water now processed at City Waste Treatment Facility at station 10. m m m m m m m____________________ - ______ - m m m m m m m m m m m m

Activity Levsis - Soil .

                      ' Sample         Alpha (pCi/g)           Beta (pCi/g)          Gamma (pCi/g) l10S49              < 1.4-                  < 2.18                 5.16 IS49               ~< 1.4                     2.68                7.14 2S49               < 1.4                      2.19                4.87 3S49               < 1.4 -                ' < 2.18                4.20
                      '4S49               < 1.4                    < 2.18                3.47 5S49               < 1.4                      2.75                5.39
                     -6S49                < 1.4                    < 2.18                4.60
                      .7S49               < 1.4                      2.33                6.19 l.,.

Activity Levels . Water Sample Alpha (pCi/l) . Beta (pCi/l) Gamma (pCi/1) H-3 (pCi/ml) 10W48 < 1.83 3.70 < 204.12 < 9.96 f < 1.83 < 2.86 < 204.12 < 9.96 4W48 6W48 < 1.83 < 2.86 < 204.12 < 9.96 h Table 2 Summary of Environmental Set 50 October 1996 Detection Limits

• Matrix Alpha - Beta Gamma Tritium Water 0.73 pCi/l 2.49 pCi/l ' 210.63 pCi/l 2.62 pCi/ml of sample Soil 0.65pCi/g 2.22 pCi/g 1.55 pCi/g N/A Vegetation 1.3 pCi/g 4.44 pCi/g 3.05 pCi/g 2.62 pCi/ml

{ ofdistillate

• Gamma and tritium analyses are based on wet weights while alpha and beta are based en dry r

L- weights. h { g IX-3 L

Activity Levels -- Vegetation Sample 10V48 Alpha (pCi/g)

                     < 1.30 Beta (pCi/g) 4.70 Gamma (pCi/g)
                                                                          < 3.05 H-3 (pCi/ml)
                                                                                              < 2.62 I'

IV48 < 1.30 9.11 < 3.05 < 2.62 2V48 < 1.30 < 4.44 < 3.05 < 2.62 3V48 < 1.30 < 4.44 < 3.05 < 2.62 4V48 < 1.30 8.23 < 3.05 < 2.62 , SV48 < 1.30 4.55 < 3.05 < 2.62 ' 6V48 < 1.30 < 4.44 < 3.05 < 2.62 7V48 < 1.30 4.85 < 3.05 < 2.62 Activity Levels Soil l Sample Alpha (pCi/g) Beta (pCi/g) Gamma (pCi/p I 10S48 < 0.65 4.64 6.30 l IS48 < 0.65 2.97 6.95 , 2S48 < 0.65 2.95 6.02  ! 3S48 < 0.65 2.64 5.58 4S48 < 0.65 < 2.22 3.74 ' 5S48 < 0.65 3.15 6.92 6S48 < 0.65 2.26 3.98 7S48 < 0.65 2.68 5.28 ' Activity Levels - Water l l Sample Alpha (pCi/l) Beta (pCi/l) Gamma (pCi/l) H-3 (pCi/ml) 10W48 < 0.73 4.70 < 210.63 < 2.62 4W48 < 0.73 4.91 < 210.63 < 2.62 6W48 < 0.73 < 2.4 9 < 210.63 < 2.62 l I I IX-4

Table 3 Environmental TLD Summary

• 1 January 1996 through 31 December 1996 Map Distance from 11st Qtr. [2nd Qtr.1 c.3rd Qtr.) - 4th Qtr.'  ; Total; l Badge? 7 Direction L 'MURR Stackj 1996 t . 1996}

11996'. 1996t 1996i Nu'mber From MURR -(metera) ? . Net mR " Net mR' " Net mR iNet mR  : Net mR-1 Various N/A 3.6 1.3 0.1 -3.1 -5.3 2 Various N/A -4.7 1.8 1.8 0.4 -5.1 3 Various N/A 1.8 6.1 8.6 5.5 22.0 4 Various , N/A -2.9 -0.5 0.5 -0.6 -4.5 5 Various N/A 2.2 0.7 -1.0 -0.3 -2.8 6 N 34 5.5 12.2 7.0 4.5 29.2 7 NE 57 6.9 10.6 9.1 8.3 34.9 l 8 SW 27 8.4 7.4 0.8 5.7 22.3 9 S 27 40.4 63.0 64.1 53.5 221.0 10 NE 149 -1.4 0.3 0.0 0.3 0.8 11 NW 149 -0.2 4.0 2.4 2.6 8.8 12 ENE 301 1.2 6.4 2.3 4.0 13.9

 ;         13      NNE                      316                 0.2           6.3           2.9          2.1           11.5 l          14     S                        156                 1.5           7.4           3.4          4.8           17.1 15      S                          65             15.4           19.7          15.3         18.3            68.7 16     SE                        107                3.6           3.3         -0.2            0.7            7.4 f         17       E                       293                 3.3           2.0           0.3           2.5            1.5 18      NE                      476              12.3             3.7         -0.7          -0.2           15.1 19      NNE                     606                 1.7           5.8            1.1          2.9          11.5 20       NE                      907                 1.9           2.4         -2.9       absent              1.4 f         21       SE'                     236                 3.7           4.0           0.5           2.0          10.2 22       ESE                      168              -4.5           -2.2          -3.2         -0.3           10.2 23       NW                       110              -2.4            0.2            3.5          1.0            6.7

l. 24 SSW 328 0.3 1.2 -4.7 3.3 -7.1 25 SSW 480 -1.3 2.1 2.0 2.6 5.4 l

26 SW 301 3.8 1.4 -1.0 2.7 6.9 1 27 WSW 141 -1.8 2,4 5.4 -2.2 11.8 28 WNW 210 4.9 absent 1.9 3.3 10.1 29 NW 255 -1.1 2.3 1.8 3.8 6.8 f 30 NNW 328 0.5 2.3 4.7 0.1 6.6 31 NNW 671 -0.4 4.6 2.5 2.3 9.0 32 NNW 724 -0.4 2.3 1.9 4.5 8.3 ( 33 34 E ENE 671 3.2 0.1

                                                                             -0.8
                                                                                           -2.0
                                                                                           -3.6 2.1
                                                                                                         -0.6
                                                                                                                        -3.0
                                                                                                                        -8.9 587               -3.9 35      SSE                      499               -0.9            0.8           0.5          1.1             1.5 36      SE                       419                0.7       absent             3.1          1.6             4.0

[ 37 NE 690 -3.2 -2.8 -6.2 -3.3 -15.5 38 NW 556 -0.1 4.4 2.6 0.9 7.8 39 W 491 -1.0 3.1 1.8 1.9 5.8 ( 40 N 514 -0.9 2.5 0.0 6.1 7.7 41 NNE 137 5.2 4.1 1.1 1.4 11.8 [ 42 In Building N/A 10.6 9.6 9.9 7.2 37.3 l 43 In Building N/A 10.4 6.2 2.9 3.0 22.5 , 44 Distant Site N/A -2.4 1.2 -2.4 -1.6 -5.2 45 S N/A 7.7 6.0 5.2 4.2 23.1

       *All measurements have background subtracted. Negative values indicate dose rates not significantly different than background.

IX-5 ( F

I Table 4 Number of Facility Radiation and Contamination Surveys Surface Air 189fi Radiation Contamination

• Samoles RWP January 68 63 25 23 February 70 65 22 14 March 71 68 21 12 April 68 64 12 13 May 85 72 23 8 June 66 77 16 10 July 71 62 18 11 August 45 47 25 7 September 65 60 23 12 October 67 65 20 10 November 51 47 25 7 December 58 51 22 S TOTALS 7S5 747 252 135
• Note: In addition, general building contamination surveys are conducted each normal work day.

Miscellaneous Items 1 In December 1996 Rex G. Ayers resigned from his Health Physicist position. The current l Health Physics staffis as follows: Manager, Reactor Health Physics; Assistant Manager, l Reactor Health Physics; four Health Physics Technicians; one part time Health Physics  ! Technician Trainee; and one Senior Secretary. MURR made two radioactive waste shipments in 1996. The total radioactive LSA waste shipped was 728 cubic feet.

                          ~

,\

e IX-6

i l SECTION X

SUMMARY

OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS AND VISITORS 1 January 1996 through 31 December 1996 I 1. Largest single exposure and average exposure are expressed in millirem.

2. Minimal exposure is defined to be gamma <10 mrem; beta < 40 mrem; neutron < 20 mrem.

3. ME = Number of monthly units reported with minimal exposure.

4. AME = Number of monthly units reported with exposure above minimal.

5. AE = Average mrem reported for all units above minimal.

{ 6. HE = Highest mrem reported for a single unit for the month.

7. Dosimetry services except for "Self Reading Dosimeters" are provided by R. S. Landauer, Jr.

                          & Co., Dosimeter Types: "C" - X, Gamma, Beta, Fast Neutron (Neutrak 144), Thermal l                        Neutron; "G" X, Gamma, Beta; "U" - TLD (1 Chip Ring).

f PERMANENTISSUE BADGES "C" Whole Body Badges (Deep Dose): JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC ME 117 136 116 116 109 102 112 101 121 104 100 110 AME 55 44 52 49 60 60 50 59 50 58 62 42 AE 78 61 63 83 69 69 62 52 61 50 49 59 HE 300 190 220 230 290 240 180 190 270 230 150 200 "G" Whole Body Badges (Deep Dose): JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC ME 57 56 60 63 68 58 58 57 64 68 70 66 AME 3 3 3 3 5 2 3 4 3 5 4 4 AE 10 20 27 67 48 50 23 30 25 53 38 10 HE 10 40 60 170 120 80 30 80 40 150 _ .1_00_ 10 ( 'U' TLD Finger Rings: JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC ME 132 118 114 106 108 112 104 115 132 105 124 130 [ 68 84 71 58 l AME 63 75 77 89 95 72 84 75 AE 200 171 158 190 149 161 167 135 197 144 143 159 HE 1000 1150 900 1610 670 680 870 720 1130 1040 930 820 Self Reading Dosimeters: JAN FEB MAR APR MAY JUN JUL AUG SEP lOCT NOV DEC [ ME 17 21 11 14 4 2 15 5 12 in 5 11 AME 75 73 82 75 86 86 76 84 80 73 83 70 52 54 53 56 57 46 42 38 47 41 44 40 A_E HE 213 179 189 225 300 253 169 179 206 165 186 158 X-1

l Il SPARE ISSUE BADGES l

 "C" Whole Body Badges (Deep Dose):

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC , ME 17 45 37 33 32 37 45 45 35 44 12 26  ! AME 5 1 1 3 1 9 2 2 1 3 3 1 l AE 12 10 10 37 50 24 70 70 20 20 20 10 HE 200 10 10 70 50 80 120 120 20 20 30 10 "G" Whole Body Badges (Deep Dose): JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC ME 48 58 43 35 42 60 73 73 61 63 41 43 i AME 1 0 0 0 0 1 1 1 0 0 2 0 I AE 10 0 0 0 0 50 50 50 0 0 10 0 HE 10 0 0 0 0 50 50 50 0 0 10 0 l

  'U' TLD Finger Rings:

JAN lFEB MAR APR lMAY JUN JUL AUG SEP OCT NOV DEC I ME 11 6 14 31 12 12 18 18 13 9 12 12 AME 8 7 5 4 6 3 4 5 0 5 4 1 AE 260 40 108 215 83 93 40 66 0 46 130 40 HE 580 60 190 390 190 160 50 170 0 60 220 40 l i l l l I' l l X2 l

ALARA Program The ALARA program continues to function as intended. Occupational exposure, releases to the sanitary sewer and releases 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 ALARA review group are shown in the following table: Groun Name Average Monthlv Dose Actinide Chemistry minimal Cnmputer Development minimal Electronic and Mechanical Properties minimal l Director's Oflice minimal Gamma Ray Scattering minimal Instrument Development minimal Magnetic and Crystal Structure minimal Thin Films and Interfaces minimal Analytical Group minimal Nuclear Archaeology and Geochemistry minimal Nuclear Engineering minimal Radiopharmaceutical minimal Facilities Operations 10 mrem Neutron Optics 20 mrem Services Applications 20 mrem Health Physics 50 mrem Reactor Operations <5 mrem ( ( { . ) l de}}