ML20135G340

Univ of Missouri Research Reactor Annual Rept,Jul 1984 - June 1985

ML20135G340
Person / Time
Site:	University of Missouri-Rolla
Issue date:	06/30/1985
From:	Brugger R, Meyer W MISSOURI, UNIV. OF, COLUMBIA, MO
To:
References
NUDOCS 8509180437
Download: ML20135G340 (49)

Text

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UNIVERSITY OF MISSOURI L i i UNIVERSITY OF MISSOURI i RESEARCH REACTOR j i

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REVISION Ntf1BER 18 TO ,

OCTOBER 1981 MANUAL f I  :

Page Number Date Revised 50P/VIII-11a 3/12/85 SOP /VIII-11b 3/12/85 SOP /VIII-51 3/12/85 SOP /VI!!-52 3/12/85 SOP /A-8a 3/4/85

,I 3/4/85 50P/A-8b 50P/A-16a 3/4/85 I

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'I F. 1. Natural uranium;

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

3. Pure elements: Li, Na, K. Rb, Cs, Ca, Sr. Ba, Hg, Os, H, 0, F Ne, Ar, Kr Xe, and P;

4. Compounds: NH4 NO 3 , CaC 2 , Ca0, perchlorates, perman-ganates. Na20 , and Na2023

5. Materials which chemically react with water to produce undesirable quantities of heat and pressure; I 6. Any explosive, flamable, combustible, or toxic materials.

E. Capsules may be run shielded with cadmium or boron (as ]

boron, BC, or BN) but weight and time are restricted due to the heat generated and their reactivity effect on the reactor. The experimenter shall take measures to insure the heat generated can be dissipated without causing damage to the rabbit or sample. The following limitations apply to shielded capsules in addition to the activity limits of Section VIII.3.2.A:

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

2. Cadmium shielded capsules: 3

a. 5 or less grams of cadmium may be run for up to ]

30 minutes.

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

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3. Boron shielded capsules:

I NOTE: The weight limit is only on the boron, i.e.,

the carbon weight in BC does count towards the weight limit.

Rev. 3/12/85 App'd A SOP /V!!!-11a

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a. 10 or less grams of baron may be run for up to 10 seconds in row 1 or 20 seconds in row 2.

b. Between 10 to 15 grams of boron may be run up to 10 seconds in row 1 or 20 seconds in row 2, but must be approved by Director of NAP and Reactor Manager prior to running.

F. Except for the baron or cadmium shielded samples, the con- ]

trolling factor for determining the weight and time limits of a sample to be irradiated in the p-tube is the activity E

limitation of Section A. If the activity limits do not 5 further restrict a sample's size, the following weight limits shall apply:

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

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

b. Only 1 mg of chemical compounds in solution.

2. For irradiation times of 30 minutas to I hour, the maximum weight of irradiated materials in one rabbit will be 1 gram with two exceptions:

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

b. Only 500 99 of chemical compounds in solution.

The weight limits above do not include the weight of the rabbit, polyethylene vial, or packing, or the cadmium (or other metal) shields.

I Rev. 3/12/85 App'd 50P/VIII-11b I

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,_ m__ y O. Turn on drive motor.

l NOTE: Ensure take-up reel is turning. If not, imediately stop machine.

E. Run film approximately five (5) meters at four (4) to five (5) meters per minute.

I F. Turn off drive motor. Leave speed set at running speed.

G. Turn of lamp.

H. Log entry.

VIII.7 Thermal Column Door Operations VIII.7.1 Cpening The Thermal Column Door l NOTE: Do not open thermal column door with the reactor critical.

1. Clear all obstructions from behind thermal column door.

2. Verify air off to Radiograph with Control Room.

3. Disconnect air supply line on thermal column door at the I 4.

snap fitting.

Verify Neutron Radiograph rotating aperture drive shaf t ]

pulled back and disconnected. ]

5. Preparation of Nuclepore Case:

A. Decouple Nuclepore take-up shaf t.

B. Remove alignment pins from shield box door.

C. Roll shield box cover,as far back along track as ,

possible. (NOTE: If thermal column door must be backed out further than this, attach shield box door I lif ting rig and move to south side of the platform using the building crane.)

D. Decouple Nuclepore drive shaft.

E. Decouple Nuclepore rabbit drive. (NOTE: Remove rubber grammet and store.)

F. Secure air to the Nuclepore equipment.

I G. Disconnect PVC air lines to the drive roll.

6. Unstack shielding as necessary to allow free movement of the door.

I 7. Plug in thermal column door drive motors (2).

Rev. 2/12/85 App'd k b 50p/VI!!-51 r -

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8. Back out thermal column door approximately six (6) inches. l

9. Disconnect four (4) PVC lines connected to the top of the Nuclepore Irradiator Case.

10. With Health Physics coverage, open the thermal column door to the desired position.

VIII.7.2 Shutting The Thermal Column Door

1. Shut the thermal column door far enough to allow the four (4) PVC lines to be reconnected to the Nuclepore Irradiator Case.

2. Reconnect the four (4) PVC lines.

3. Completely shut the thermal column door while monitoring to insure that the four (4) PVC lines do not become pinched off.

4 Verify the thermal column door open limit switch has g

cleared in the Control Room. m

5. Verify Neutron Radiograph rotating aperture drive shaft 3 will mate properly. 3 NOTE: 00 NOT rotate aperture. 3

6. Unplug the thermal column door drive motors.

7. Restack shielding on the top of the thermal column.

8. Connect the Radiograph air supply line to the regulator assembly.

9. Install the platform deck plates.

10. Nuclepore Experiment:-

A. Recouple and lock Nuclepore drive roll.

B. Attach PVC air lines to the drive roll.

C. Install rubber gromet and attach rabbit drive mechanism.

D. Place shield box door back on rails and shut it.

Pin door fully shut.

E. Recouple take-up spline coupling.

F. Open Nuclepore air supply valve and reset all tension controls.

G. Test run film.

H. Place the experiment in its desired operational mode l in accordance with approved procedures.

11. Inform operators of the system status.

Rev. 3/12/85 App'd1f40 50P/VIII-52

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REACTOR ROUTINE PATROL ,

Date:

1. Time of start of patrol.

2. Time and date all charts.

3. Check ARMS trip settings.

I 4 Visual check of entire pool. L _

5. Anti-siphon tank pressure. 36 psig 2 3 psi

6. North iso door seal press. 18-28 psig

7. South iso door seal press. 18-28 psig -

8. 5th level backup doors. Open

9. 5th level detector reading. 0-3.5 mr/hr ,

10. 5th level trip point set. 3.5 mr/hr

11. 16" iso viv A air pressure. 45-55 psig

12. Emerg compress on standby. ,ch$20 kg *

13. Containment hot sump pumps. . Operable

14. Door 101 seal pressure. 18-28 psig

'15. BP Floor Conditions normal.

I 16. Fuel Vault Locked l l

17. Inner airlock door seal press. 18-28 psig

,18. Outer airlock door seal press. 18-28 psig

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19. T-300 level. > 2000 gal.

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20. T-301 level. < 6000 gal.

21. Labyrinth Sump , Level < Alarm Pt.

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22. RO Unit Operate / Standby !3 power ON

23. RO Unit Temp 24-28'C/ standby

24. RO Unit Pressure 190-200 psig/ standby

25. EG Rm. (Batt. check Sun. mids.; Thermostat > 50'F (EG OP switch to Auto ? Temp > 40*F i (Gas l sight glass ) I

26. T-300, 301 Room Thermostat > 55'F Thermostat > 40 F On the first routine patrol of the day or the first patrol af ter a startup, drain all water l from the anti-siphon system. If draining causes the pressure to drop significantly, return I to the middle of the band (36 psig) and record the pressure here. If a condition or reading ]

is normal, enter a "/" (for conditions) or the reading in the applicable box. If the con- ]

dition is abnormal, enter the condition or reading and circle it. Explain all abnormal con- ]

ditions or readings in the remarks.

REMARKS:

I Rev. 3/4/85 App'd Jr /A _ 50P/A-8a

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27. Rm.114 Particulate filter AP < 2.5" H 2O

28. External D: ors (henI on $ t,N "

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29. CT basin water level. 5-10"

30. Acid day tank level. Visible l

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31. CT sump pumps. Operable

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32. P-pump (s) running.

33.

34 Pump strainer AP.

Discharge pressure.

0-7.0 psi

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35. Pump strainer AP. 0-7.0 psi .

36. Discharge pressure.

37. Tunnel sump pumps. Operable  !

33. WT booster fan. Running

39. Acid control and pH. F)oy00gogcc/ min

40. Blowdown control /cond.

CoId.2bh2.k

41. Fission Product Monitor Flow 95-105 cc/ min '

42. Viv control header pressure.90-120 psig 43 Pressurizer N2supply press.- 90-100 psig 44 Check Rm. 114 from door.

45. Deltecn oil filter " red level" < 757. dark red and blowdown.

46. Seal trench. 6 yn pump on days.

l 47. Full N bottles.

2 Total > 3 '

48. Bank A bottle press. > 250 psig

49. Bank B bottle press. > 250 psig

50. Bank on service. A or B l

51. N header pressure.

2 135-145 psi

52. Waste tank #3 level.

53. Waste tank #2 level.

54. Waste tank #1 level.

55. Doors to ct, WT 's, Demin. Locked W Rm. 114 and CT Tunnel.

l 56. Time of Completion of Patrol.

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57. Operator initials.

REMARK 5: ,

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g R2v. 3/4/85 App'd /k< SOP /A-8p

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Montn Year D. I. WATER MAKEUP LOG (Fill in only if sending D.I. water.)

I Day Time Start i Stoo R0 Conductivity T-300 Water Meter 5 tart l Stop l Net Pre-Filter REMARKS

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3 i' AP ]

I Unit S tart i S top 6

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i Rev. 3/4/85 App'd k SOP /A-16a p,

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NOTE: THIS PAGE INTENTIONALLY LEFT BLANK I

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E' REVISION NUMBER 1 TO I MURR REQUALIFICATION PROGRAM l

SUBMITTED January 31, 1978

.I Page Number Date Revised 5 3/20/85 APPENDIX A:

Performance Evaluation Form 3/20/85 l

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Revised: ,3/2f/85 Approved: ,4#f%

l 2.2 On-The-Job Training V

This section of the program provides assurance that all operators will maintain competence in those major evolutions which can be performed by licensed operators only. The on-the-job requirements are outlined in the checklist in Appendix A.

2.3 Periodic Observation and Evaluation

, Reactor Management will, on a continuing basis, observe and evaluate the performance of all operators to maintain familiarity with the operator's competence in handling routine and emergency evolutions. This program implements the means of documenting the evaluations made by management.

The Training Coordinator, Reactor Manager, Reactor Operations Engineer, or Shift Supervisor will annually conduct a performance evaluation of all operators during one of their reactivity manipulations. The supervisor conducting the evaluation will complete an Operator Performance Evaluation Sheet (Appendix A). The evaluator will also discuss or simulate abnormal ]

or emergency conditions and grade the operator on his response to these conditions. Each operator's present supervisor fills out the final section 3 of the evaluation sheet as an. overall appraisal of .the operator's perfor- -]

mance during the time on the supervisor's shif t. If the present supervisor ]

feels there has been insufficient time-on his shift to make such-an evalua- ]

tion, the previous super ~ visor.will fill =out the -final-section of the evalua- 3 j tion sheet based on per'ormance-on the. previous shift. - -

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Revised: 3/20/85 Approved: ,,dcf>fVo, ,

I MURR OPERATOR REQUALIFICATION PROGRAM PERFORMANCE EVALUATION FORM gperator'sName: Date:

Evolution Performed:

Excel- Good Aver- Poor Un sa ti s-lent age factory PERFORMANCE DURING REACTIVITY FMNIPULKTION: ]

mal. Procedures - knowledge and understanding of

.ll2. Console Log Entries - adequacy, completeness and legibility of entries.

j 3. Checksheets and Data Sheets - thoroughness in j

completing checklist, accuracy of and interpre-tation of data on data sheets.

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4. Manipulation of Controls proficiency in handling ll controls and positive approach to handling the pla_nt.

15 5 . Use of Instrumentation - used all available instrumentation and properly inter)reted same.

Awareness of Reactor Conditions - cnowledge of plant Ib. conditions, understanding trends or abnormal indi-cations, t esponse to changing conditions.

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ED U PEiRFORMANCE:

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llRFORMANCE UNDER ABNORMAL OR EMERLENCY CONDITIONS: ]

E l. Immediate actions - recognizea condition and took immediate steps to put plant in safe condition.

Communications - communicated problem, took charge,

12. initiated or directed corrective acticn.

3. Follow-up Actions - ability to recover plant, h6VEnL PIR[DRilAPt.E: _

"" Abnormal or Emergency CondFtlons Imposed or otrerved:

Comments and Recommendations:

Evaluator:

, OPERATOR ON SHITT PERTQWMA} ICE APPRXISAL: . _

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Appraisal Period: From To IE 0VERALL PCRFORMANCE: l l l l l IEbmmants:

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Supervisor's Signature:

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SECTION III 1985 REVISIONS TO THE HAZARDS

SUMMARY

1 July 1984 through 30 June 1985 _

I There were no revisions to the Hazards Summary between July 1,1984 and June 30, 1985.

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III-1

SECTION IV PLANT AND SYSTEM MODIFICATIONS 1 July 1984 through 30 June 1985 SEPTEMER 1984 _

Modi fication 84-7: This modification adds a manual blowdown valve to the nitrogen bank system which allows the nitrogen bank to be bled down, creating a demand on the system and allowing the banks to switch from bank "A" to bank "B" manually.

This does not downgrade the system, but provides a simple way to switch from one bank to the other and test the switch-over pressure point for pre-ventive maintenance.

OCTOBER 1984 Modi fication 84-4: This modification changes the technique used to secure the offset mechanisms to the reflector tank pedestal. An aluminum insert is bolted into the reflector pedestal and then the offset holddown bolt is screwed into the insert to secure the offset mechanism.

This eliminates stainless-on-stainless threads which gall and cause op-erational maintenance problems. It does not change the final positioning and alignment of the offset. The strength of the aluminum insert is many times

. greater than the maximum stress that could be exerted during operation.

Modi fication 84. 3: This modification changes the control room indica-tion for charging pump P533 and the conditions for the indication. The "0N" indication was changed to "AUT0" and will enable only if the foi sowing condi-tions are met:

1) Main power breaker at MCCS is closed.

2) Room 114 lockout switch is unlocked.

3) Control power switch on MCC5 is in 'AUT0", and

4) Control room switch is in 'AUT0".

IV-1 I

This prevents a green light from being indicated for P533 when either the control room switch or control power switch on MCC5 is out of ' AUT0".

During charging, both the red "RUN" light and the green "AUT0" light will be on. When any of the four switches are out of position, both lights will be -

off.

This change enables the operator to more quickly determine that the charging pump control system is lined up for proper operation. It does not affect the operation of the primary water makeup system.

DECEtBER 1984 Modi fication 84-14: This modification replaced the 10 ohm RTD's in Pool Tc and Pool Th with 100 ohm RTD's. The 100 ohm RTD's provide a .227 ohm /*F change over the temperature range of 0*F to 200*F, where the 10 ohm RTD's provided a .0218 ohm /*F change over this range. The increased ohm /*F obtained by using the 100 ohm RTD's makes the temperature indications less susceptible to variations due to small resistance changes, i.e. terminal board connections, wire connectors, etc. in the temperature indicating current loop.

This modification in no way affects the operation of the safety system.

The change is designed to enhance the accuracy of the temperature signal and its transmission to temperature indicating circuitry.

APRIL 1985 i4odi fication 85-1: This modification to the exhaust fan system ensures that the exhaust fan running prior to a loss of site power is the fan that re-start:s when the emergency generator picks up the emergency load. This takes advantage of the fan coast down and reduces the starting current on the emergency generator.

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H je Modification 85-2: This modification, installed first on the Rod "D" il housing, replaced both the " blade full in" and rod drop reed switch with photo-electric activated switches and circuitry.

The " blade full in" indication had been actuated by a spring arm style -

microswitch being moved by the offset pull rod anvil. This was suspected to have created an alignment problem between the anvil and magnet which resulted in unscheduled reactor shutdowns when the anvil would contact the upper guide tube.

Each control blade travel drop time is measured from full out to 80%

full in. A magnetic reed switch had been used as the disconnect to stop the timers. Alignment of the magnet located in the pull rod and the reed switch located on the outside of the upper guide tube was critical and any misalign-ment greater than 1/4" would require a realignment before the drop time could be obtained.

The reliability of this modification has been proven by prior testing.

Rod "A" will have this modification installed in May 1985. Rods "B" and "C" will have this modification installed when their offset mechanisms are changed out on their regular schedule.

MAY 1985 Modi fication 85-4: This modification changes the offset "A" blade arm design, giving a 3/4" step in the arm. The change to the blade arm will allow for clearance of the relocated pneumatic tues. This was dcne in ar, affort t.o maximize and crer e reflector sample irradia.n oa 'acilities. Te do thi s, the pneumatic tube ends will be relocated from the G-1 and G-2 positions (north side of pool) to a special graphite element adjacent to Beamport "A" (south side of pool).

IV-3 I

Two new blade arms were constructed and will be cycled in service for offset "A" at the biennial preventive maintenance. Since the load created by the control blade is vertical, the side load created by the stepped arm will have negligible effect on rod drop times. Operation of the offset and control blade remain as existing.

I Modification 85-5: This modification installed a 1/8" aluminum shim l plate between the reflector tank pedestal and offset "A" base. This was neces-sary due to one of the offset "A" locating pins being galled. Tha offset lacked approximately 1/8" from setting full down on the pedestal.

The shim plate was drilled with 2-1/8" holes to permit adequate pin clearance. The shim plate gives a flat surface on which the offset is mounted so that the blade will not tilt in its groove or come in contact with the pressure vessel.

Operation of the offset assembly does not change and this change does not effect the drop times or compliance requirements.

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SECTION V NEW TESTS AND EXPERIMENTS I 1 July 1984 through 30 June 1985 I New experimental programs during this period are as follows:

RUR-243 Experimenter: J. Steven Morris / Jim Carni Description : An addenum was added to the RUR to include neutron activation analysis of small arms propellant samples.

RUR-247 Experimenter: W. Yelon/H. Kai ser

Description:

An addendum was added to the RUR to include the use of U-235 and Pu-239 samples as phase shifters on Beamport B.

I RUR-264 Experimenter: Don Alger

Description:

The RUR was revised to broaden the scope of the applications of neutron radiographic techniques in research, education and service.

I RUR-265 Experimenter: Mark Prelas

Description:

An addendum was added to the RUR to include the measurement of ultravicle t;arescence production efficiencies of Xenon gas at low power levels.

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SECTION VI I SPECIAL NUCLEAR MATERIAL ACTIVITIES 1 July 1984 through 30 June 1985

1. SNM Receipts: A total of 16 new fuel elements were received from Babcock _

and Wilcox (B & W), Lynchburg, Virginia. These had been fabricated by Atomics International, Canoga Park, California, and shipped to B & W after December, 1982. B & W is holding 5 elements, serial numbers M0145 through M0149. Shipment of these to MURR will be completed in 1985.

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Grams Grams Shipper Elements U U-235 B&W M0132, M0133, M0134, M0135, M0136, M0137, 13,272 12,363 M0138, M0140, M0141, M0142, M0143, M0144, M0200, M0201, M0202, M0203 I

2. SNM Shipments: A total of 24 spent fuel elements were shipped to I Westinghouse Idaho Nuclear Company, Inc., Idaho Falls, Idaho for reprocess-I ing.

Shipper Elements Grams U

Grams U-235 MURR M073, M075, M076, M079, M082, M090, M091, 16,221 14,162 M092, M093, M094, M095, M096, M097, M098, M099, M0101, M0118 M0119, M0120, M0121, M0151, M0153, M0158, M0159

3. Inspections : A routine safeguards inspection was conducted by the Nuclear Regulatory Commission (NRC), Region III office, on 4-7 cnd 11 March 1985.

MURR Special Nuclear Material Control Procedures were reviewed and found ade-equate to enable MURR to comply with 10CFR70.51(c) requirements (accounting procedures for SNM M cossession). Uranium burnup calculations were found in agreement with NRC 742 Material Balance Reports. Shipping and receiving procedures and records were found adequate and NRC 741 Nuclear Material I

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I Transaction Reports were found adequately documented and properly filed with NRC. Internal fuel transfers and storage records were reviewed. Inventory of fuel and non-fuel material was physically identified and no discrepancies in inventory records were noted. By letters from NRC, Region III, dated -

26 March 1985, no items of noncompliance with NRC requirements were identi-fled during the course of these inspections.

4. SNM Inventory: As of 30 June 1985, MURR was financially responsible for the following DOE owned amounts:

Total U = 40,647 grams Total U-235 = 36,147 grams I Included in these totals are 36 grams of U and 34 grams of U-235 non-fuel, 00E owned. In addition to these totals, MURR owns 162 grams of U and 79 grams of U-235. All of this mate 'al is physically located at the MURR.

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I Fuel elements on hand have accumulated the following burnup as of 30 June 1985:

i I Fuel Element Accumulated Number Megawatt Days Fuel Element Accumulated Number Megawatt Days Fuel Element Accumulated Number Megawatt Days

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l 98.27 M0141 0 I M058 122.78 M0117 149.03 M0122 133.10 M0142 40.41 M070 M0123 147.64 M0143 0 M077 147.86 146.99 M0124 144.84 M0144 40.41 M088 145.96 M0125 135.90 M0150 147.82 M0100 145.82 M0126 148.53 M0152 147.82 M0102 122.78 M0127 148.55 M0154 149.01 M0103 145.82 M0128 145.17 M0155 148.59 M0104 138.04 M0129 149.28 M0156 146.76 M0105 129.27 M0130 145.17 M0157 148.59 I M0106 M0107 138.04 M0131 149.28 107.73 M0160 M0161 147.64 148.36 M0108 129.27 M0132 ,

M0109 107.90 M0133 59.50 M0162 147.64 M0111 107.90 M0134 107.73 M0164 148.36 M0112 99.38 M0135 59.50 M0165 146.99 M0113 95.82 M0136 87.35 M0200 9.61 M0114 99.38 M0137 57.84 M0201 6.56 M0115 95.82 M0138 87.35 M0202 9.61 M0116 98.27 M0140 57.84 M0203 6.56 I .

Average Burnup = 110.13 MWD I

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, SECTION VII REACTOR PHYSICS ACTIVITIES 1 July 1984 through 30 June 1985

1. Fuel Utilization: During this period, the following elements reached their licensed burnup and were retired.

Serial Number Core Designation Date Last Used MWDs M070 A-51 10-22-84 149.03 M077 A-52 10-25-84 147.86 M088 A-63 12-31-84 146.99 I M0102 M0104 M0123 85-20 85-20 85-15 4-25-85 4-25-85 4-07-85 145.82 145.82 147.64 I M0124 PO126 M0127 85-15 85-1 85-1 4-07-85 1-17-85 1-17-85 144.84 148.53 148.53 l

l 85-20 4-25-85 145.17 I M0128 M0129 M0130 85-6 85-20 2-14-85 4-25-85 149.28 145.17 M0131 85-6 . 2-14-85 149.28 M0150 A-61 12-13-84 147.82 I M0152 A-61 12-13-84 147.82 M0154 A-51 10-22-84 149.01 I M0155 M0156 M0157 A-37 A-52 A-37 7-26-84 10-25-84 7-26-84 148.59 146.76 148.59 A-59 11-29-84 147.64 I M0160 M0161 M0162 A-60 A-59 12-06-84 11-29-84 148.36 147.64 M0164 A-60 12-06-84 148.36 M0165 A-63 12-31-84 146.99 Due to the requirement of having l'ess than 5 kg of unirradiated fuel in possession, initial criticalities are obtained with four new elements or l fewer as conditions dietate. A core designatton consists of elght fuel elements of which only the initial critical fuel element serial numbers are

! listed in the following table. To increase operating efficiency, fuel ele-ments are used in mixed core loadings. Therefore, a fuel element fabrication core number is different from its core load number.

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I Fabrication Serial Core Load Ini tial Core No. No. Desi gnation Operating Date, I

34 M0112 A-37 7-19-84 34 M0114 A-37 7-19-84 I 34 M0113 A-42 8-23-84 34 M0115 A-42 8-23-84 I 34 34 36 M0116 M0117 M0132 A-54 A-54 A-55 10-29-84 10-29-84 10-31-84 36 M0134 A-55 10-31-84 36 M0133 A-63 12-20-84 37 M0135 A-63 12-20-84 37 M0136 85-1 1-10-85 I 37 37 37 M0138 M0137 M0140 85-1 85-11 85-11 1-10-85 3-14-85 3-14-85 4-23-85 I 37 38 41 M0142 M0144 M0200 85-20 85-20 85-30 4-23-85 6-13-85 41 M0202 85-30 6-13-85 I 41 41 M0201 M0203 85-32 85-32 6-20-85 6-20-85

2. Fuel Shipping: Twenty-four spent fuel elements were shipped from MURR to Westinghouse Idaho Nuclear Company, Inc., Idaho Falls, Idaho. The identi-fication numbers of these elements are:

M073 M091 M097 M0120 M075 M092 M098 M0121 I M076 M079 M082 M093 M094 M095 M099 M0101 M0118 M0151 M0153 M0158 M090 M096 M0119 M0159

3. Fuel Procurement: Babcock and Wilcox, Lynchburg, Virginia is MURR's current fuel assembly fabricator. This work is contracted with the U. S. Department of Energy and administered by E G & G Idaho, Idaho Falls, Idaho. As of 30 June 1985, four fuel assemblies fabricated by B & W had been received j and used in cores at 10 MW.

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4. Licensing Activities: Changes to the MURR Physical Security Plan were submitted 30 May 1985; reviewed and found acceptable 17 June 1985. A re-quest for an increase in Special Nuclear Material Inventory under our Facility License submitted in December,1982 is pending. A revision to I

l Technical Specifications 4.4.d requiring two operating parallel pool pumps submitted in February,1982 is pending.

5. Reactor Characteristic Measurements: Sixty-six refueling evolutions were completed. An excess reactivity verification was performed for each refuel-ing and the average excess reactivity was 2.7%. MURR Technical Specifica-ation 3.1(f) requires that the excess reactivity be less than 9.8%.

Reactivity measurements were performed for 19 evolutions to verify reactivity parameters for the flux trap. Shim blade calibrations were per-formed at selected rod heights in support of reactivity measurements.

A physical inspection of the following fuel elements was performed to verify the operational parameters.

M0156 from Core A-39 during August 1984 M0150 from Core A-38 during October 1984 M0165 from Core A-40 during December 1984 All measurements were within operational requirements.

I I

I VII-3 I

I SECTION VIII

SUMMARY

OF RADI0 ACTIVE EFFLUENTS RELEASED TO THE ENVIRONMENT Sanitary Sewer Effluent 1 July 1984 through 30 June 1985 -

Descending Order of Activity Released Nuclide Anount(Ci[ Nuclide Amount (Ci) Nuclide Amount (Ci)

S35 1.33E-1 Sm153 1.51E-4 Re188 2.16E-5 H3 1.21E-1 Fe59 1.23E-4 Re186 1.91E-5 Co60 3.87E-2 Ag110M 1.91E-4 Au196 1.83E-5 Zn65 2.95E-2 Rb86 8.64E-5 Nb95 1.76E-5 Cs137 7.44E-3 CoS7 7.80E-5 Zr95 1.14E-5 Na24 3.70E-3 Sb122 7.26E-5 Au198 1.09E-5 l

Cr51 2.49E-3 Mn56 6.96E-5 1131 1.03E-5 Mn54 1.54E-3 Ba139 6.63E-5 Na22 1.01E-5 Sc46 1.10E-3 W187 6.45E-5 Se75 7.93E-6 Sb124 5.90E-4 Ni65 6.16E-5 Sn113 7.35E-6 I Sb125 5.89E-4 Zn69M 5.02E-5 Hg203 5.79E-6 As77 4.49E-4 Ba140 4.67E-5 Cs134 3.74E-6 1134 3.52E-4 Ce144 4.66E-5 La140 3.34E-6 Cd109 2.41E-4 Pa233 4.42E-5 Re188 3.12E-6 Ta182 2.36E-4 Ir192 4.39E-5 Hf181 2.88E-6 CoS8 2.05E-4 Ba133 3.21E-5 Tc99M - 1.64E-6 I

I I

I VIII-1

l E Stack Effluent 1 July 1984 through 30 June 1985 Descending Order of Activity Released Nuclide Amount (Ci)

Ar41 1.39E+3 H3 1.01E+1 1133 2.48E-3 1135 1.91E-3 1131 1.51E-3 1134 1.13E-3 As77 5.20E-4 K40 4.91E-4 1132 4.64E-4 Xe135M 3.53E-4 C138 1.66E-4 Ta182 1.21E-4 I

I I .

I I

I I VIII-2 I

l I

SECTION IX

SUMMARY

OF ENVIRONMENTAL SURVEYS I 1 July 1984 through 30 June 1985 I Environmental samples are collected two times per year at eight locations and analyzed for radioactivity. These locations are shown in Figure 1. Soi1 and vegetation samples are taken at each location. Water samples are taken at three I of the eight locations. Results of the samples are shown in the following tables.

Detection Limits Matri x Alpha Beta Gamma Tri tium Water 0.2 pCi/1 2.5 pCi/1 0.04 pCi/1 9.1 pCi/mi I Soil and vegetation 0.2 pCi/g 2.5 pCi/g 0.04 pCi/g 9.1 pCi/g

1. Sampled during October 1984.

Determined Radioactivity Levels Vegetation Samples Sample Alpha pCi/g Beta pCi/g Gamma pCi/g Tri ti um pCi /g 1-V-26 <0.2 13.7 < 0.04 < 9.1 2-V-26 <0.2 18.0 < 0.04 < 9.1 3-V-26 <0.2 26.7 < 0.04 < 9.1 4-V-26 0.3 13.0 < 0.04 < 9.1 5-V-26 <0.2 13.5 < 0.04 < 9.1 6-V-26 <0.2 9.9 < 0.04 < 9.1 7-V-26 <0.2 17.8 < 0.04 < 9.1 10-V-26 <0.2 24.2 < 0.04 < 9.1 IX-1 I 1

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l Figure 1. MURR Environmental Program Sample Stations NOTE: September 1983 City sewerage plants at stations 8 and 9 closed. All waste water now processed at City Waste Treatment Facility at station 10. .

. _ _ _ _ _ _ . _ - - - - n.

I Determined Radioactivity Levels i Soi1 Samples l 1

Sample Alpha (pCi/g) Beta (pCi/g) Gama (pCi/g) 1-S-26 0.3 3.0 < 0.04 2-S-26 0.2 13.7 < 0.04 3-S-26 0.3 5.7 < 0.04 4-S-26 0.4 8.0 < 0.04 5-S-26 0.5 10.6 < 0.04 6-S-26 0.6 8.1 < 0.04 7-S-26 1.3 18.9 < 0.04 10-S-26 0.6 9.9 < 0.04 I Determined Radioactivity Levels Water Samples Sample Alpha (pCi/g) Beta (pCi/g) Gama (pCi/g) 3 H (pCi /ml )

4-W-26 < 0.2 3.7 < 0.04 < 9.1 6-W-26 < 0.2 3.8 < 0.04 < 9.1 10-W-26 < 0.2 9.3 < 0.04 < 9.1 I 2. Samples during April 1985.

Detection Limits -

Matri x Alpha Beta Gama Tri ti um Water 0.5 pCi/1 1.6 pCi/1 150 pCi/1 11 pCi/ml Soil + 0.3 pCi/g 0.9 pCi/g 3.2 pC1/g ----

Vegetatton* 1.5 pCi/g 4.3 pCi/g 8.4 pCi/g 11 pCi/g

• Gama and tritium analyses are based on wet weight; I a and 8 analyses are based on dried weight.

IX-3 I

Determined Radicactivity levels Vegetation Samples Sample Alpha (pCi/g) Beta (pCi/g) Gama (pCi/g) Tritium (pCi/g) 1-V-27 < 1.5 20.4 < 8.4 < 11 2-V-27 < 1.5 25.3 9.6 < 11 3-V-27 < 1.5 22.9 < 8.4 < 11 4-V-27 < 1.5 19.3 < 8.4 < 11 5-V-27 < 1.5 14.0 < 8.4 < 11 1 I

6-V-27 < 1.5 29.7 < 8.4 < 11 7-V-27 < 1.5 21.8 < 8.4 < 11 10-V-27 < 1.5 19.9 < 8.4 < 11 Determined Radicactivity Levels i Soil Samples  !

Sample Alpha (oCi/g) Beta (pci/g) Gama (pCi/g) i 1-S-27 0.3 9.4 8.4 2-S-27 0.8 11.7 10.8 3-S-27 0.6 10.2 8.4 4-S-27 < 0.5 6.6 7.8 5-S-27 < 0.5 10.4 5.8 6-S-27 0.4 6.6 6.6 7-S-27 0.7 8.3 6.2 10-3-27 0.4 9.5 11.8 Determined Radioactivity Levels Water Samples Sample Alpha (pCi/g) Beta (pCi/g) Gama (pCi/g) 3H (pCi/ml) 4-W-27 < 0.5 3.9 < 150 < 11 6-W-27 < 0.5 3.8 < 150 < 11 10-W-27 < 0.5 7.2 < 150 < 11 No gama peaks above background were observed in any of the gama analyses.

I IX-4 I

Radiation and Contamination Surveys iIl The following table gives the number of surveys performed during FY 84-85.

Radi ation Surface Contamination Air Sampies 366 277 253 Forty-four (44) Radiation Work Permits were issued during the year.

Miscellaneous Items I Eight revisions were made to Health Physics standard operating procedures.

A new procedure was added to provide for formal review of unusual unplanned radiation exposure. A second new Health Physics procedure was written to improve use of Radiation Work Permits for better exposure control. l Several actions were taken which contributed to the ALARA effort.

I a. A radwaste shipment in May reduced exposure to personnel who work in the basement an estimated 5 manrem per year,

b. A plexiglass beta shield was put in service to reduce exposure in a laboratory when handling low energy gamma emitters which decay by beta decay. An estimated manrem per year to upper body is I saved by this unit.

c. A lead shield was installed on a glove box to reduce exposure to females processing low energy gamma emitters used for medical studi es. A quantitative value for exposure reduction is not available.

d. Smaller waste containers have been put in use in radiochemistry laboratories to reduce background both for personnel exposure reduction and a more accurate record of isotopes collected for di sposal .

I IX-5 I -

l I

e. The radiation exposure rate in the reactor pool was reduced by several hundred mrem /hr (dependent on location) when a used beryllium reflector and much activated metal, which had been i stored in the pool, were shipped to a radwaste disposal site.

This reduces the potential exposure level should it be necessary to perform repair operations in the reactor pool.

I Gross gamma analysis of environmental samples was improved by Reactor Chemistry to the extent that gamma analyses can be calculated for samples that do not exhibit distinct gamma peaks.

Environmental samples were collected around the University radwaste incinerator and analyzed to establish background data for the area.

I I

I I

~

I

.I  ;

iI IX-6

SECTION X

SUMMARY

OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS AND VISITORS 1 July 1984 through 30 June 1985

1. Largest single exp0ture and average exposure are expressed in millirem.

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

3. M. E. = Nunber of ncnthly units reported with minimal exposure.

4. A. M. E. = Number of monthly units reported with exposure above minimal.

5. A. E. = Average arem reported for all units above minimal.

6. H. E. = Highest nrem reported for a single unit for the month.

PERMANENT ISSUE FILM-BADGES Beta, Carma, Feutron Whalebody Badges: (Six badges are area monitors.)

JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ME 63 66 70 51 60 81 73 80 64 74 67 69 AME 58 S F. 52 68 67 45 57 52 65 59 69 69 AE 108 91 103 423 101 117 125 139 116 130 123 106 HE 210 240 320 680 320 190 260 260 330 350 410 360 Beta and Camma Wholebody Badges: (Six badges are area monitors.)

JULY AUGUST SEPTEMCEK OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ME 47 48 48 51 56 57 59 52 52 53 54 55 AME 4 5 2 5 9 6 7 7 8 5 8 6 AE 50 34 85 66 101 52 34 46 30 60 618 183 HE F0 90 150 140 450 90 60 110 70 - 200 4470 740 TLD Finger Rincs:

JULY AUGUST, SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ME 38 42 38 40 48 47 52 45 48 52 48 51 AME 35 32 35 44 44 38 40 42 37 34 38 37 AE 313 213 233 457 325 486 308 301 253 226 215 269 HE 1640 1250 1310 3160 4010 8170 2830 2390 1720 1670 1740 3470 X-1 s

SPARE ISSUE FILM-BA0GES Beta, Gamme, Weut ron Wholebody Badges:

JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ME 39 31 25 36 37 38 44 40 36 33 39 38 AME 5 17 In 13 9 6 3 6 10 12 7 10 AE 76 46 56 158 73 70 147 75 90 60 41 47 HE 200 140 280 560 160 120 380 140 300 130 150 140

~

Beta and Gamma Wholebody Badges:

JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ME 3a 30 29 30 33 32 32 30 30 29 29 32 AME 3 3 1 0 0 0 4 1 3 3 1 AE 35 47 27 10 0 0 0 68 420 213 53 30 HE 40 80 40 10 0 0 0 120 420 510 130 30 TLD Finger Rings:

JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ME 16 11 20 12 18 17 19 14 11 13 18 19 AME 6 9 12 9 2 4 1 6 7 7 2 7 AE 195 210 167 338 170 88 30 198 229 217 785 263 HE 570 1030 610 1020 210 130 30 510 560 620 1490 540 DOSIMETERS JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE ME O 3 2 6 2 2 8 6 5 6 4 4 AME 47 42 44 49 52 52 53 55 57 49 58 55 AE 77 57 64 114 87 87 72 80 79 79 79 62 HE 260 265 270 620 295 295 295 275 325 335 320 380 X-2 i

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