ML20063F888

Reactor Operations Annual Rept,Jul 1981-June 1982

ML20063F888
Person / Time
Site:	University of Missouri-Columbia
Issue date:	08/31/1982
From:	Alger D, Mckibben J MISSOURI, UNIV. OF, COLUMBIA, MO
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ML20063F875	List: ML20063F871 ML20063F888 ML20063F919
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e l UNIVERSITY OF MISSOURI I

l Annual

! Report l

I 1981-82 I

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I UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY I

REACTOR OPERATIONS ANNUAL REPORT August 1982 I

I Compiled by the Reactor Staff Submi ted by 0 <

A I J. C. McKibben Reactor Manager Reviewed and Approved I . .

D. M. Alger Associate Director

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TABLE OF CONTENTS Section Page I. RtACTOR OPERATIONS

SUMMARY

...................... 1 II. OPERATING PROCEDURE CHANGES ..................... 10 III. REVISIONS TO THE HAZARDS

SUMMARY

REPORT .. . . ... . . 19 IV. PLANT AND SYSTEM MODIFICATIONS .................. 32 V. NEW TESTS AND EXPERIMENTS ....................... 36 VI. SPECI AL NUCLEAR MATERI AL ACTIVITIES . . . . . . . . . . . . . 37 VII. REACTOR PHYSICS ACTIVITIES ...................... 40 VIII

SUMMARY

OF RADI0 ACTIVE EFFLUENTS RELEASED TO THE ENVIRONMENT ................... 44 IX.

SUMMARY

OF ENVIRONMENTAL SURVEYS ................ 46 X.

SUMMARY

OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS, AND VISITORS .................................. 49 I

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I SECTION I REACTOR OPER 7 IONS

SUMMARY

I The following table and discussion summarize reactor operations in the period July 1,1981 to June 30, 1982.

I Date Full Power Hours Megawatt Days Full Power Percent

• of Total Time of Schedule July 81 692.7 291.73 93.10 104.26 Aug. 81 670.7 279.59 90.15 100.95 Sep. 81 674.6 281.26 93.69 104.92 Oct. 81 522.8# 221.05# 70.27# 78.69#

Nov. 81 627.1 262.01 87.10 97.54 Dec. 81 693.1 285.78 93.16 I Jan. 82 661.1 276.31 88.86 104.32 99.51 Feb. 82 606.2 252.75 90.21 101.02 Mar. 82 696.8 290.50 93.66 104.88 Apr. 82 663.1 276.54 92.10 103.14 May 82 673.0 281.14 90.46 101.30 June 82 629.1 262.40 87.38 97.85 I Total for Year 7,810.3 3,261.06 89.16% of time for yr.

99.865% of sched. time at 10MW for yr. at 10MW

• MURR is scheduled to average at least 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> per week at 10MW.

Total time is the number of hours in a month or year.

1. The reactor shutdown at 2000, October 15, to perform major maintenance, I replacement of the beryllium reflector, the reactor returned to normal operation at 0800 on October 24.

JULY 1981 The reactor operated continuously during July with the follewing exceptions: two maintenance shutdowns on July 13 and 27; nine scheduled shutdowns for flux trap sample changes; and four unscheduled shutdowns.

On July 14 and 27, the reactor was shutdown by a rod-run-in when blade "C" disengaged from its magnet. The blade "C" mechanism was pulled to investigate the problem, the upper housing was realigned and the reactor returned to operation.

The reactor was shutdown by loss of site electrical power on July 19 and 20. Both power outages were verified with the University Power Plant and the reactor returned to operation.

Major maintenance items in July included installation of new Nuclear Instrumentation detectors in channels 3 and 6, the installation of a new drain collection tank (DCT), and the visual inspection of seven fuel elements.

Nuclear Regulatory Commission Region III inspector, A. Finley, conducted a Special Nuclear Material Accountability inspection from July 29 through July 31.

AUGUST 1981 The reactor operated continuously during August with the following exceptions:

nine scheduled shutdowns for flux trap sample changes; three maintenance shutdowns on August 10, 24, and 31; and one unscheduled shutdown, August 6.

The unscheduled shutdown (manual scram) occurred when the pool loop "B" flow transmitter (912F) developed a leak on the high pressure sensing lne. The reactor was subcritical at the time of the manual scram. (A startup was in progress following a flux trap sample changeout when the leak was discovered.) The leak was repaired and the compliance check (CP-7B) for pool flow loop "B" was completed and the reactor returned to normal operation.

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Major maintenance items for August consisted of regenerations of two D1-200 beds, work on realigning the regulating rod, and the installation of a new secondary flow transmitter (Rosemount).

l SEPTEMBER 1981 The reactor operated continuously in September, with the following exceptions:

eight scheduled shutdowns for flux trap sample changes; two maintenance shutdowns on September 14 and 28. There were no unscheduled shutdowns in September.

Major maintenance items for September included preparation of the National Lead cask for fuel storage, completion of the National Lead cask loading sequence, the repair of the emergency generator electric fuel pump switch, and the completion of a physics startup on test core BNB. The emergency generator failed to start on September 28, when the starting sequence was initiated by the automatic weekly exerciser; but started up when tested in manual. This was reported to the Nuclear Regulatory Commission in a letter to the Director of Licensing dated October 27, 1981.

OCTOBER 1981 The reactor operated continuously in October with the following exceptions: four scheduled shutdowns for flux trap sample changes; one maintenance shutdown from October 15 to October 24 to replace the beryllium reflector; and three unscheduled shutdowns.

On October 6, the reactor was shutdown, by a rod-run-in, when blade "D" was bumped by an operator retrieving a sample spacer on the reflector.

A Power Level Interlock Scram shutdown the reactor on October 24. Air trapped in DPS-929 caused erratic indication in control. The detector was vented and the reactor returned to normal operation.

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I A loss of site power caused a reactor shutdown on October 28. The power outage was verified with the University Power Plant and the reactor returned to normal operation.

l Major maintenance items for October consisted of replacement of the drive motor for coolin3 tower fan #2 and the replacement of the beryllium reflector (SMP-ll).

The old beryllium reflector had been installed in original construction, and had been used for approximately 26,000 MWD of operation.

Mr. K. R. Ridgway, NRC Region III inspector, conducted a routine safety inspection on October 26-30, 1981. No items of noncompliance with NRC requirements were identified during the course of this inspection.

NOVEMBER 1981 The reactor operated continuously in November with the following exceptions:

ten scheduled shutdowns for flux trap changes; three maintenance shutdowns on November 2,16, and 30; and six unscheduled shutdowns.

On November 9, following maintenance day, there was a rod not in contact with magnet rod-run-in as blade "A" fell off during the normal startup. The anvil was cleaned and the upper housing realigned. The second unscheduled shutdown occurred during the subsequent startup, when blade "A" fell off again. The pocl was pumped down and the housing was realigned from the refuel bridge to minimize drag of the anvil on the housing tube. A rod drop was performed on blade "A" and the reactor returned to normal operation.

The unscheduled shutdown on November 19 was caused by the pool reflector differential pressure transmitter PT-917. The shift supervisor checked all indications and found no anomalies, the reactor was returned to normal operation.

The unscheduled shutdown on November 27 was caused by an electrical glitch in the I 4 I

I PT-917 circuit. The shift supervisor inspected and vented the transmitter and verified all systems normal and returned the reactor to normal operation.

An unscheduled shutdown occurred on November 27 and again on November 28, when the reactor scrammed while acknowledging a high level annunciator alarm while filling the demineralized water tank. No cause for the scram was indicated on the annunciator board and all indications were normal. The reactor was returned to normal operation.

The annunciator circuits were inspected by the Electronics Shop during maintenance day on Novernber 30. The source of the electrical problem could not be determined. The

" white rat" system was installed in the jumper board panel for the safety system to detect what contacts in the safety system were causing the scrams. This monitor detects momentary opening of a safety system relay contact.

Major maintenance items for November were: replacement of reflector graphite element number 6; replacement of the cooling tower exhaust fan; replacement of the emergency generator electric fuel pump breaker; and replacement of the drain valve on the pool strainer with a ball type valve.

I DECEMBER 1981 The reactor operated continuously in December with the following exceptions: nine scheduled shutdowns for flux trap sample changes; two maintenance shutdowns on December 14 and 28; one shutdown for operator training; and three unscheduled shutdowns.

The unscheduled shutdown on December 2 was a scram caused by an electrical glitch.

After the shift supervisor investigated and found no anomolies, the reactor was returned to normal operation. On the next sample shutdown on December 3, the yellow leg trip actuator amplifier was replaced. The unscheduled shutdown on December 13 was a manual scram to replace the inner airlock door motor. The second unscheduled shutdown on December 13 was a manual rod-run-in to replace the breaker for the inner airlock door drive motor.

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I Major maintenance items for December were the replacement of the inner airlock door drive motor and its breaker, and the replacement of the drive motor for cooling tower fan number 2.

JANUARY 1982 I The reactor operated continuously in January with the following exceptions:

thirteen scheduled shutdowns for flux trap changes; four maintenance shutdowns on January 7,11,18, and 25; one shutdown for operator license examinations on January 11; and two unscheduled shutdowns.

On January 8, blade "D" fell of f during a shimming evolution. The housing on blade "D" was adjusted and the reactor was returned to normal operation.

The unscheduled shutdown on January 14 was a high power scram thought to be caused by a sample off-gassing in the flux trap. The sample was replaced with a spacer and the reactor was returned to normal operation.

Major maintenance items for January were: repair of pump 508A pump bearings and mechanical seal; three spent fuel shipments; and replacement of the source range detector.

FEBRUARY 1982 The reactor operated continuously in February with the following exceptions: nine scheduled shutdowns for flux trap changes; two shutdowns for flux trap reactivity measurements; three maintenance shutdowns on February 1, 8, and 22; and one unscheduled shutdown.

On February 18, there was a reactor scram and isolation caused by a short circuit in the ARMS Recorder. This short circuit was inadvertently caused by the electronics technician trouble shooting a drive malfunction in the ARMS Recorder. The containment building was evacuated as per emergency procedure for reactor isolation. After surveys I 6

taken by Health Physics' personnel showed all radiation levels were normal, the reactor was returned to normal operation.

I MARCH 1982 The reactor operated continuously in March with the following exceptions: eight scheduled shutdowns for flux trap sample changes and two maintenance shutdowns on March 8 and 22. There were no unscheduled shutdowns in March.

Major maintenance in March included Machine Shop repair and balancing of primary pump P501A and operations regeneration of DI-201 bed "Q".

APRIL 1982 The reactor operated continuously in April with the following exceptions: ten scheduled shutdowns for flux trap changes; two maintenance shutdowns on April 5 and 19; and one unscheduled shutdown.

On April 1, there was a reactor scram caused by a loss of site electrical power.

All systems were checked by the shift supervisor. Electrical power was restored by the Power Plant and the reactor was returned to normal operation.

On April 5, the new 3" irradiation hole was installed in the H position of the graphite reflector. This new H-3 element replaced the existing 2" element and the solid element of the H position. The S-Basket, Reuter-Stokes Air Force and Bulk Pool Lead Shield Irradiation Facilities were removed from the reflector at this time, in preparation for installation of the new Bulk Pool Lead Shield Irradiation Facility under offset "D".

On April 19, a new offset, Assembly number 7, was installed in position A. The new Bulk Pool Lead Shield Irradiation Facility was installed under offset "D" at this time.

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MAY 1982 The reactor operated continuously in May with the following exceptions: twelve shutdowns for flux trap sample changes; three shutdowns for maintenance; five shutdowns for RTP-5, Reactivity Measurement; and four unscheduled shutdowns.

On May 11 and 14, the reactor was scrammed due to loss of site electrical power.

The power loss was verified with the University Power Plant by the shift supervisor.

The unscheduled shutdown on May 24 was caused by a static charge build-up on the l

WRM switch. The reactor scrammed while performing RTP-11, Reactivity Measurement. The WRM switch was wiped and reactor power was restored for RTP-11.

The unscheduled shutdown on Fby 25 was a manual scram to repair the gasket on the inner airlock door. The gasket was repaired and the reactor was returned to power of 10MW.

Major maintenance activities were: Containment Building Leak Test, RTP-13, performed on May 13; the replacement of primary pump P-501A on May 20; the replacement of reflector graphite element number 5 on May 20; and the inspection and gapping of fuel elements M0-53, MO-67, and M0-69 and the inspection of M0-80 on May 27. The containment leak rate was 12.1 scfm, which is less than the Technical Specification limit of 16.3 l

l scfm.

JUNE 1982 1

The reactor operated continuously in June with the following exceptions: nine shutdowns for flux trap sample changes; four shutdowns for maintenance; and five unscheduled shutdowns.

On June 1 and 7, the reactor was shutdown to repair the airlock door. The timing sequence was adjusted and the door gasket was reinstalled and tested before the reactor

, was returned to power.

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l Two unscheduled shutdowns on June 8 were caused by a loss of site electrical power.

The power losses were verified with the University Power Plant and the reactor was returned to power.

The unscheduled shutdown on June 24 was due to an electrical glitch on the annunciator caused by acknowledging and clearing an alarm. The annunciator was tested for normal operation and the reactor was returned to power of 10MW.

Major maintenance activities were: replacement of control tower fan number 3 motor on June 2; the disassembly and disposal of offset number 4 on June 7; replacing the mechanical seal on P513-A on June 14; replacement of channel number 4 Nuclear Instrument detector on June 14; replacement of the cylinder heads on the emergency generator on June 21; the replacement of P513A motor bearings on June 28; and the installation of the emergency generator fuel day tank and vacuum break system, Modification Package Number 82-3, on June 28.

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SECTION 11 OPERATING PROCEDURE CHANGES As required by the MURR Technical Specifications, the Reactor Manager reviewed and

approved the Standard Operating and Emergency Procedures (SOP). Two additional revisions (#11 and #12) have been made during the past year to the 50P manual which was issued June 1980. The revisions are contained in this section with the part of each page that was revised marked on the right side of the page by a vertical black line.

Also, a new S0P manual was issued October 1981 which revised the June 1980 manual.

There have been six revisions made to the October 1981 manual during the past year. The revisions are contained in this section with the part of each page that was revised marked on the right side of the page by a bracket (]). The October 1981 revision is enclosed with the Nuclear Regulatory Commission copy of the Annual Report. Additional copies may be obtained upon request.

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REVISION NUMBER 11 TO JUNE 1980 MANUAL I S0P/VII-53 Revised 9/81 SOP /VII-54 Revised 9/81 SOP /A-7a Revised 9/81 I

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2. Start the waste pump (WP1) and verify flow through the buliseye.

3. Recirculate for 10 minutes prior to sampling.

4. Draw off sample through W22 and discard to liquid waste drain.

5. Draw off a sample through W22 for analysis.

6. Close W22 and secure the waste pump.

7. Close W6a, 6b, 10, 16, 17, 18, 19, 27.

8. Deliver the sample and completed form to the Nuclear Science Group for analysis.

9. Record taking of sample in Reactor Log.

VII.8.7 Pumping to Sanitary Sewer Note: Can be done only with Shift Supervisor's Authorization.

Check the following valves closed: W1, 7 , 3, 15, 22, 23, 24, 25, 26, 27. If pumping with WP2, open W7 and 8 instead of W9 and l'0.

A. Pumping WT2 to Sewer (check closed 6a, 6b)

1. Open W5a, 5b, 9,10,16,17,18,19, 28 and 30.

2. Commence a virgorous air sparge through W41. ,

3. Start the waste pump (WP1) and verify flow through the bullseye.

4. Check the WT level frequently until the tank is empty.

5. When it is empty, shut W41 and secure the waste pump.

6. Close W5a, b, 10, 16, 17, 18, 19, 28 and 30.

7. Record the volume remaining on the Waste Tank Sample Form and return it to the Health Physics Office.

8. Record pumping evolution completion in the Reactor Log.

B. Pumping WT3 to Sewer

1. Check valves W5a, b closed.

2. Open W6a, 6b, 9,10,16,17,18,19, 28 and 30.

3. Start the waste pump (WP1) and verify flow through the bullseye.

4. Check the WT level frequently until the tank is empty.

5. When it is empty, secure the waste tank pump.

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Rev. 9/ 81 App'f 8<.- 50P/VII-53

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Pf;EUMATIC TUEE IP.RADIAT10f;5

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Room Irrac1ation Ruri Clock Tire file !!O-In '

Out fiame Proj.i;o.l{o_ f'i n __Iltc 1

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Rev. 9/2/81 App'd ' /* SOP /A-7 a

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I REVISION NUMBER 12 TO JUNE 1980 MANUAL I SOP /A-la Revised 10/81 S0P/A-lb Revised 10/81 I

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E RE. ACTOR STARTUP CHECKSHEET DATE:

E FULL POSER OPERAT10tl Time (Started)

(or Low Pomer Forced Circulation)

BUILDING AND MECHANICAL EQUIPMENT CHECKLIST

1. Run emergency generator for 30 minutes and check the governor oil level.

(Required if shutdown for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or af ter each maintenance day.)

2. a. Check operation of fan failure buzzer and warning light. Shift fans.

(Required if shutdown longer than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.)

b. Test stack' monitor per 50P while in west tower.

c. Test the stack monitor low flow alann.

3. Visual check of room 114 equipment completed.

a. P501 A and P501B coolant water valves open.

b. Si and 52 hydraulic pumps on (oil level normal).

c. Pump controllers unlocked to start (as required).

d. Insure N backup system on per SOP.

Open air2 valve for valve operating header (V0P 31).

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N9 backup valve open, Check valves 599A and 599B open.

h. Pipe trench free of water (on Monday startups, check the four-pipe I 4.

annulus drain valves for water leak. age).

Visual check of CT equipment completed.

a. Oil level in CT fans normal (Monday startups).

I 5. Beamport Floor

a. Beamport radiation shielding (as required).

b. Unused beamports checked flooded (Monday).

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c. Seal trench low level alann tested (Monday).

Emergency air compressor (load test for 30 minutes on Monday),

p 7. Reactor Pool

a. Reflector experimental loadings verified and secured for start-up.

Flux trap experimental loading verified and secured for start-up, or

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strainer in place.

REACTOR CONTROL SYSTEM CHECKLIST

1. All chart drives on; charts timed and dated. IRM recorder to slow.

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4.

Fan failure warning system cleared.

Annunciator board energized; born off.

Television receiver on.

Primary / pool drain collection system in service per 50P.

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Secondary system on line per 50P (as needed).

Primary system on .line per S0P.

a. Primary cleanup system on line.

I 8. Pool system on line per 50P.

a. Pool clear.up system on line.

b. Pool skimmer system vented.

Pool reflector Ap trips set per S0P.

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c. .

Valves S1 and S2 cycled in manual mode and positioned as required.

Nuclear instrumentation check completed per 50P.

a. The following trip values were obtained during the check.

I IRM-2, run-in IRM-3, run-in WRM-4, run-in seconds seconds Scram Scram _

Scram seconds seconds I 11.

PRM-5, run-in PRM-6, run-in Scram Scram Channel 4, 5, and 6 pots returned to last heat balance position.

12. SRM-1 detector response checked and set to indicate >l cps.

Rev. 10/81 App'd A SOP /A-la

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13. Check of process radiation monitors (front panel checks).

a. Fission product monitor,

b. Secondary coolant monitor.

Note: Items 14 through 35 are to be completed in sequence ie.ediately prior to pulling rods for a reactor startup.

14. Annunciator tested.

15. Annunciator alam cleared or noted.

16. Power selector switch IS8 in position required.

17. a. Bypass switches 2540 and 2S41 in position required,

b. All keys removed from bypass switches.

18. Master switch IS1 in "on" position.

19. Magnet current switch on, check " Reactor On" lights.

20. Reactor isolation, facility evacuation and ARMS checks. (Monday start-up)

These itemr, are to be checked with scrams and rod run-ins reset, and when appropriate items are actuated, verify that the TAA's do trip.

a. Reactor isolation switch (leave valves and doors closed) . ("onday start-up)

b. Facility evacuation switch (check outer containment horns).(Monday start-up)

c. ARMS trip setpoints checked and tripped, check buzzer operational locally for all channels and remotely for' channels 1 through 4 and 9. E Channel 1 - Beam Room South Wall 5 Channel 2 - Beam Room West Wall Channel 3 - Beam Room North Wall Channel 4 - Fuel Storage Vault Channel 6 - Cooling Equipment Room 114 Channel 7 - Building Exhaust Air Plenum (Monday start-up)

Channel 8 - Reactor Bridge (Switch in " Normal") (Monday start-up)

Channel 9 - Reactor Bridge backup (switch in " upscale") (Monday start-up) -

d. Check hV readings: volts.

e. Check 150V reading: volts,

f. Selector switch on ARMS in position 5.

g. Trip backup monitor with attached source.

h. Reactor isolation horns switch in " Isolation Horns On" position.

Valves and doors open.

i. All ARMS trips set per SOP.

j. Check ventilation fans, containment and backup doors.

21. Operate reg blade front full-out to full-in and set at 10"+.05". E

a. Check rod n2n-in function at 10% withdrawn and annuncTator at rod bottomed. 5

22. Raise blade A to 2" and manually scram.

23. Raise blade B to 2" and trip manual rod run-in. E

24. Raise blade C to 2" and scram by hP3f trip. g

25. Raise blade D to 2" and scram by IRM trip.

26. Annunciator board energized; horn on.

27. Jumper and tag log cleared or updated.

28. IRM recorder in fast speed.

29. Check magnet current for 90 ma on each magnet. g

30. Cycle hPS1 range switch. 3

31. Predicted critical blade position ( inches).

32. Pre-startup process data taken.

l 33. Visually check room 114 after all systems are in operation.

l a. Check oil reservoir for pump P501A, 501B, and P533 for adequate supply.

Add if necessary. E

34. Routine patrol completed. E

35. Reactor ready for startup. Time (Completed)

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Senior Reactor Operator l Rev. 10/81 App'd M A SOP /A-lb

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REVISION NUMBER 1

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TO OCTOBER 1981 MANUAL i

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50P/A-8a Revised 3/82 iI l 50P/A-8b Revised 3/82 II

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Reactor Routine Patrol Date E2 Time of start of patrol I Time and date all charts I. 3. Check ARMS trip settings

4. Visual check of entire pool

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

6. North iso door seal press 18-28 psig 7 South iso door seal press 18-28 psig I. 8. 5th level backup doors Open

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g9. 5th level detector reading 0-3.5 mr/hr "10, 5th level trip point set 3.5 mr/hr 16" iso viv A air pressure hl. 45-55 psig B open,

,12. Emerg compress on standby g e g E13. Coretainment hot sump pumps Operable

. Door 101 seal pressure 18-28 psig

15. BP floor Conditions normal

16. Fuel vault Locked

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

El8. Outer airlock door seal press 18-28 psig gl9. T-300 level > 2000 gal

'20. T-301 level < 6000 gal Labyrinth sump Level < Alarm Pt.

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22* RO UNIT lRun daily: 1 ON/Runon0700 routine]

- POWER ON \to T-300 or drain./ (for #- 4 hrs. /

h3. R0 Unit Temp 24-28*C / standby g 24. R0 Unit Pressure 190-200 psig / standby 5 25 EG rm.IlsMp'%fictl"to Auf3l- Thennostat > 50 F (Gas > sight glass.) Temo > 40*F l26.

T-300, 301 room oyat g at > ' F Rm 114 particulate filter t.P < 2.5" H20 l0n the first routine patrol of the day or the first patrol after a startup, drain all water from the anti-siphon system. If draining causes the pressure to drop significantly, return to the middle of the band (36 3sig) and record the pressure here.

Rev. 3/82 App' (fh SOP /A-8a

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All locked except east '

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28. External Doors when sec on duty l E

29. CT basin water level 5-10"

30. Acid Day Tank Level Visible

31. CT sump pumps Operable H

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32. P-pump (s) running

33. Pump strainer iP 0-7.0 psi

34. Discharge Pressure

35. Pump Strainer AP 0-7.0 psi

36. Discharge Pressure

37. Tunnel sump pumps Operable

38. WT Booster Fan Running l g

Acid Control and pH * "

39. g 7.5-8 5 Flow 500-800 cc/ min

40. Blowdown Control /Cond. Cond . 2.0 K-2. 9 K u

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

42. Vlv control header pressure 90-120 psig

43. Pressurizer f:2 supply press90-100 psig i.

44 Check Pm 114 from door ,

Deltech oil filter " red a 45' < 75% dark red level" and blowdown g

-6. Seal trench p, n mp on days l

47. Full N2 bottles total > 3

48. Bank A bottle press > 250 psig

49. Bank B bottle press > 250 psig

50. Bank on service A or B 51 . N2 header pressure 135-145 psi

52. Waste Tank # 3 level

53. Waste Tank e 2 level

54. Waste Tank # 1 level

35. Doors to CT, WT's, Demin Locked Rm 114 and CT Tunnel

35. Time of Completion of Patrol ,

57. Operator initials If a condition is normal, enter an "N" or a check "p? in the applicable box. If the condition 5-reading is abnormal, enter "AN" for the condition and circle it. Circle the reading if it is abnormal. Explain all abnonnal readings or conditions in the remarks. E REMARKS:

g Rev. 3/82 App'd /c'/ h SOP /A-8b

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TO OCTOBER 1981 MANUAL

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'3 50P/A-lb Revised 3/82

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RE ACTOR STARTUP CHECKSHEET DATE:

FULL POWER OPERATION I. (or Low Power Forced Circulation) Time (Started)

BUILDING AND MECHANICAL EQUIPMENT CHECKLIST

1. Run emergency generator for 30 minutet and check the governor oil level.

(Required if shutdown for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or after each maintenance day.)

2. a. Check operation of fan failure buzzer and warning light. Shift fans.

(Required if shutdown longer than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.)

b. Test stack' monitor per 50P while in west tower.

c. Test the stack monitor low flow alarm.

3. Visual check of room 114 equipment completed,

a. P501A and P501B coolant water valves open.

b. 51 and 52 hydraulic pumps on (oil level normal).

I c. Pump controllers unlocked to start (as required).

d. Insure N backup system on per 50P.

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e. Open air valve for valve operating header (V0P 31).

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N7 backup valve open.

Check valves 599A and 5998 open.

Pipe trench free of water (on Monday startups, check the four-pipe annulus drain valves for water leakage).

4. Visual check of CT equipment completed.

a. Oil level in CT fans normal (Monday startups).

5. Beamport Floor

a. Beamport radiation shielding (as required).

b. Unused beamports checked flooded (Monday).

c. Seal trench low level alann tested (Monday).

6. Emergency air compressor (load test for 30 minutes on Monday).

7. Reactor Pool

a. Reflector experimental loadings verified and secured for start-up,

b. Flux trap experimental loading verified and secured for start-up, or strainer in place.

REACTOR CONTROL SYSTEM CHECKLIST

1. All chart drives on; charts timed and dated. IRM recorder to slow.

I 2.

3.

4.

Fan failure warning system cleared.

Annunciator board energized; horn off.

Television receiver on.

5. Primary / pool drain collection system in service per SOP.

I 6.

7.

Secondary system on line per SOP (as needed).

Primary system on line per 50P.

a. Primary cleanup system on line.

I 8. Pool system on line per SOP.

a. Pool cleanup system on line.

b. Pool skimmer system vented.

I 9.

10.

c. Pool reflector op trips set per 50P.

Valves S1 and 52 cycled in manual mode and positioned as required.

Nuclear instrumentation check completed per 50P.

a. The following trip values were obtained during the check.

I IRM-2, run-in IRM-3, run-in seconds seconds Scram Scram seconds seconds WRM-4, run-in  % Scram  %

PRM-5, run-in  % Scram  %

PRM-6, run-in  % Scram  %

[l 11. Channel 4, 5, and 6 pots returned to last heat balance position.

12. SRM-1 detector response checked and set to indica'.e > l cps.

Rev. 10/81 Ann'd [ h, Rnp/A la

13. Check of process radiation monitors (front pane] checks).

a. Fission product ronitor.

b. Secondary coolant monitor.

Note: Items 14 through 35 are to be completed in sequence immediately prior to pulling rods for a reactor startup.

14. Annunciator tested.

15. Annunciator alarm cleared or noted.

16. Power selector switch 158 in position required.

17. a. Bypass switches 2S40 and 2S41 in posit' ion required.

b. All keys removed from bypass switches.

18. Master switch ISI in "on" position.

19. Magnet current switch on, check " Reactor On" lights.

20. Reactor isolation, facility evacuation and ARMS checks. (Monday start-up) I E

These items are to be checked with scrams and rod run-ins reset, and when appropriate items are actuated, verify that the TAA's do trip.

a. g

b. Reactor isolation switch (leave valves and doors closed). (Monday start-up) 5

c. Facility evacuation switch (check outer containment horns).(Monday start-up)

ARMS trip setpoints checked and trimped, check buzzer operational locally for all channels and remotely for' channels 1 through 4 and 9.

Channel 1 - Beam Room South Wall Channel 2 - Beam Room West Wall Channel 3 - Beam Room North Wall Channel 4 - Fuel Storage Vault Channel 6 - Cooling Equipnent Room 114 Channel 7 - Building Exhaust Air Plenum (Monday start-up)

Channel 8 - Reactor Bridge E Channel 9 - Reactor Bridge (Switch in " Normal") (Monday start-up) backup (switch in " upscale") (Monday start-up) 5

d. Check IN readings: volts.

c. Check 150V reading: volts,

f. Selector switch on ARMS in position 5.

g. Trip backup monitor with attached source.

h. Reactor isolation horns switch in " Isolation Horns On" position.

Valves and doors open.

i. All ARMS trips set per SOP.

j.

Check ventilation fans, containment and backup doors.

21. Operate' reg blade from full-out to full-in and set at 10"+ 05". E

a. 3; Check rod run-in function at 101, withdrawn and annuncTator at rod bottomed. -

22. Raise blade A to :"' and manually scram.

23. Raise blade B to 2" and trip manual rod run-in. E

24. Raise blade C to 2" and scram by hWi trip. g

25. Raise blade D to 2" and scram by IRM trip.

26. Annunciator board energized; horn on.

27. Jumper and tag log cleared or.'ipdated.

28. IRM recorder in fast speed.

29. Check magnet current for 90 ma on each magnet. E

30. Cycle hM1 range switch. 5

31. Predicted critical blade position ( inches).

32. Pre-startup process data taken.

33. Visually check room 114 and D.I. area after all systems are in operation. l a.

Check oil reservoir for pump P501A, 501B, and P533 for adequate supply.

Add if necessary. Vent the 6000 gallon pool hold up tank. .

34. Routine patrol completed.

35. Reactor ready for startup.

Time (Completed)

Senior Reactor Operator Rev. 3/82 App'd 50P/A-l b I

II i

iI l

l

I 1

i l REVISION NUMBER 3 I

TO OCTOBER 1981 MANUAL i

i 1

SOP /Vil-16 Revised 4/82

} i J SOP /VII-23 Revised 4/82 ]

l j S0P/Vil-37 Revised 4/82 ll SOP /A-la Revised 4/82 il lI l

I I

I I

I I

I is

I

1. Connect the quick-disconnect hose to the master DI ]

supply. ]

I 2. Verify adequate level in T300 ~ 5000 gallons. ]

3. Open DI valve. ]

F. Open air valve RE25, bleed any oil or water from the air line via valve RE52. Adjust air regulator to 50 psig.

Nofity the reactor control room of intentions to begin the transferring of water to the drain collection tank.

G. Check valve DI13 closed.

H. Open valve DI9.

I. Open valve DIl0 (01200) or Dill (D1201) or DI12 (D202) de-pending on column to be transferred, to pressurize the DI col umn.

J. Slowly open DI14 to commence the transfer; monitor the transfer at the bullseye.

K. When transfer is complete, close DI14, close DIl0, Dill, or D112 respectively.

L. Open DI8 and vent all pressure from the column. The column will now be refilled and flushed two times by the following procedure.

1. Open the DI supply, valves RE18 and 013. Insure DI8 I 2.

open.

Open R2 and fill the respective DI column with DI water until it starts to exit via DI8.

3. Close R2, DI8, 013. This flush water will now be transferred to the primary / pool collection tank.

4. Check DI13 closed and DI9 open.

5. Open valve DIl0 (01200) or Dill (DI201) or DI12 (DI202) to pressurize the 01 column.

6. Slowly open DI14 and monitor the transfer until all water has been transferred. Repeat the process for the second flush.

7. Close DI14, DI9, DIl0, Dill or D112.

8. Open DI8 and vent all the pressure from the column.

Caution: It is extremely important that valve D114 be closed after the transfer of DI water to the drain Rev. 10/ 81 App ' d, h- SOP /VII-15 e

collection syste.. Failure to close this valve before proceeding further could result in the addition of raw water to the drain collection system.

The unit now needs to be refilled; NEVER LEAVE IT DRY.

M. Open DI3. I N. Open R2 and refill the column until water starts to exit via DI8.

O. Close R2, D13, and DIB.

P. Close all other valves opened (DI supply, RE18).

Q. Log in the resin log the exact status of the DI column.

The DI column is now ready for transfer.

VII.4.4 Preparation of Regenerate Solutions Required by Regeneration VII.4.4.1 Acid Regenerate Selections for Regeneration I

A. Determine the required draws.

B. Fill mixing tank to proper water level for the required draws.

C. Add acid via the measuring tank for the required draws.

VII.4.4.2 Acid Solution Strength A. Specific gravity should be 1.172 0 66*F.

VII.4.4.3 Caustic Regenerate Solutions for Generation 3 I

A. Determine the required draws. ]

B. Fill mixing tank to proper water level for the required draws. ]

C. Commence air sparge of water. ]

D. Add the necessary bags of caustic soda for the required draws. ]

VII.4.4.4 Caustic Solution Strength ]

A. Specific gravity should be 1.275. ]

Rev. 4/82 App'd, s (y 50P/Vil-l

s C. Throttle to 30-35 gpm.

D. Check closed RE2 and RE17.

E. Monitor the rinse by performing an alkalinity test as per "F" listed below.

F. Alkalinity Test: Obtain a 58.3 mi sample from RE23 of rinse water, add 2-3 drops of methyl orange indicator.

While stirring, add 0.4N sulfuric acid, one drop at a I time, until color changes from yellow to permanent faint pink or red. Each drop of acid solution equals 1 grain per gallon (17.1 parts per million, ppm) of alkalinity.

At a resistance of 25K ohms, the alkalinity will be one grain or less.

Note: If the solubridge is used to check the conductivity of the rinse water, it must be turned off before the acid draw to prevent damage to the cell.

G. Close valves RE3, RE7 and RE18.

H. Close the DI supply valve and RE16.

VII.4.5.5 Intermediate Backwash I Inspect the resin through the sight glasses for proper separa-tion. If the resin has not been properly separated, proceed with a DI water backwash for 10 minutes as per VII.4.5.2.

When the separation is adequate, proceed with step VII.4.5.6.

lg Sulfuric Acid Treatment t

5 VII.4.5.6 A. Switch disconnect to DI water.

B. Open DI supply valve.

C. Adjust RE19 for 3 gpm downflow. ]

D. Secure solubridge. ] _

E. Open RE3, RE7 and RE16. ]

F. Open RE1 and RE14.

G. Adjust RE17 for 4-5 gpm and vent the acid vent tank until l

full of water.

J

'l Rev. 4/82 App'd f vw-SOP /VII-23

H. Check shut RE56, RE59, RE60 and RE62. ] g I. Open acid pump isolation valves and close its breaker on ] 5 MCC2. ]

J. Open RES and RE58. ]

K. Start acid pump and timer at ontrol panel. ]

L. Throttle RE57 for 1.5 gpm for 30 minutes. ]

M. Monitor the vent tank while the acid treatment is in prog- ]

ress to insure air does not pass through to the regener- ]

ator. It may be necessary to vent excess air from the ]

vent tank during the treatment. ] E N. When the acid injection is completed, close valve RES and ] 5 RE58 immediately. ]

0. After each draw, rinse for 10 minutes. ]

P. Open RES and RE58 for next draw. ]

Caution: Do not allow air to be injected into the re- ]

generator during the acid treatment. Air bubbles will ]

carry acid up into the anion resin and reduce its capa- ]

city. ]

Q. Continue rinsing without changing the valve lineup for 30 ]

minutes. ]

R. Close the acid pump suction and discharge valves, secure ]

the pump's electrical power at MCC2 and thoroughly rinse ]

the acid pump with DCW inside and out. ]

5. Close RE57. ]

VII.4.5.7 Acid Fast Rinse A. Open DI supply valve. ]

B. Open RE18 for maximum flow. ]

C. Start T300 pump. ]

D. Throttle RE18 flow to 30-35 gpm. ]

E. Close RE1 and RE14. Then drain the acid vent tank and re- ]

fill through RE1. ]

F. Close RE17 and RE19.

]g I

Rev.10/81 App'd +_ SOP /VII-24 V __

VII.4.8.13b Providing DI Water to T300 Without Reverse Osmosis Unit Makeup A. Check valve 3 closed.

B. Open valve 1, open the T300 supply valve RE31.

C. Check valve 7 closed and place the low conductivity cutout circuit into operation using the procedure posted at the DI300 station.

D. Record the resistivity and water meter readings on the log.

I E. Insure that the resistivity reading does not drop below 500 K ohms while making water for T300.

F. Upon completion of making DI water, log the resistivity and water meter readings on the log. Close master T300 l valve, close valves 1 and 17. If the low conductivity cutout circuit was used, secure it.

G. If the resistivity drops to 500 K ohms, the life of the bed can sometimes be extended by following steps VII.4.8.10 through VII.4.8.12.

W H. When the resistivity reading cannot be brought above 500 K ohms, it is necessary to regenerate the unit.

I VII.4.8.13c Providing DI Water to 01200 Units ]

A. Check valve 3 closed and close the T300 supply valve. ]

B. Open valves 1, 7 and 13. ]

C. Open R200 supply valve. ]

D. Record the resistance and water meter readings on the log. ]

E. Should the resistance drop below 500 K, resparge the unit. ]

If a higher resistance cannot be achieved, and the regen- ]

eration of a 200 series bed is required, continue to use ]

I the DI water, for it is still better than DCW. Proceed to ]

regenerate as soon as possible. ]

F. When DI water is no longer necessary for the 200 series, ]

close valves 1 and 7. Close the R200 supply valve. ]

3 G. Record the resistance and meter readings on the log.

o v

I Rev. 4/82 d O SOP /VII-37 E App'g

Vll.5 Skimer System VII.S.1 Nonnal Startup of the Skimmer Systen The skimer system is operated to remove floating debris from the pool at the normal operating level. If necessary, it is also possible to operate this system with the pool at refuel level by securing the skimer box with valve 548A and recirculating the water with suction taken through valve 548B g

from approximately 1 foot below the refuel level. 5 The skimer system is put into routine operation according to the following procedure:

A. Verify that no maintenance has been performed on the skimer system since the last shutdown of the system. If maintenance has been perfonned on the system, verify that a system valve lineup checklist has been performed; if not, do so before proceeding.

B. Energize pump P532 by turning off-on switch located on the instrumentation panel in the control room to the on position. Vent the pump until it shows a steady discharge pressure.

VII.5.2 Pool Pump Down with the Skimmer System A. Prior to pumping the pool down, insure that there is sufficient reserve volume in tank T301 to receive the water.

B. If the pool level is to be lowered below the skimmer suction box, change the suction lineup to the lower suction by closing valve 548A and opening V5480.

C. The skimer pump discharge normally returns to the pool via valve 515H. Pumping the pool down is accomplished by closing valve 515H and opening valve 524 to redirect the discharge to T301. A single control switch on the drain collection system control board operates valve 515H and valve 524. This switch is normally left in the open Rev. 10/81 App'd *m. SOP /VII 38

/

v

sann FULL POWEF OPEully. (Startd,3 (or Low Power iorcc o Circulation)

BUILDING AND MECHMilCAL E0'JIPMENT CHECKLIST I 1. Run emergency generator for 30 minutes and check the governor oil level.

(Required if shutdown for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or af ter each maintenance day.)

2. a. Check operation of f an f ailure buzzer and warning light. Shift fans.

(Required if shutdown longer than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.)

b. Test stack monitor per 50P while in west tower.

c. Test the stack monitor low flow alarm.

3. Visual check of room 114 equipment completed.

e. P501A and P501B coolant water valves open.

b. 51 and 52 hydraulic pumps on (oil level normal).

I c.

d.

e.

Pump controllers unlocked to start (as required).

Insure Ngbackup system on per 50P.

Open air valve for valve operating header (V0P 31).

N backup valve open.

I f.

g.

h.

Cbeck valves 599A and 599B open.

Pipe trench free of water (on Monday startups, check the four.-pipe annulus drain valves for water leakage).

I 4. Visual check of CT equipment completed,

a. Oil level in CT fans normal (Monday startups).

5. Beamport Floor

a. Beamport radiation shielding (as required).

b. Unused beamports checked flooded (Monday).

c. Seal trench low level alann tested (Monday).

I 6. Emergency air compressor (load test for 30 minutes on Monday).

7. Reactor Pool I a. Reflector experimental loadings verified and secured for start-up.

b. Flux trap experimental loading verified and secured for start-up, or strainer in place.

c. Check and reset, as necessary, silicon integrator and totalizer setting. l REACTOR CONTROL SYSTEM CHECKLIST

1. All chart drives on; charts timed and dated. IRM recorder to slow.

2. Fan failure warning system cleared.

3. Annunciator board energized; horn off.

I 4.

5.

6.

Television receiver on.

Primary / pool drain collection system in service per 50P.

Secondary system on line per 50P (as needed).

7. Primary system on line per 50P.

I a. Primary cleanup system on line.

8. Pool system on line per 50P.

a. Pool cleanup system on line.

b. Pool skimmer system vented.

c. Pool reflector Lp trips set per 50P.

9. Valves 51 and 52 cycled in manual mode and positioned as required.

g 10. Nuclear instrumentation check completed per SOP.

E a. The following trip values were obtained during the check.

IRM-2, run-in seconds Scram seconds 1RM-3, run-in seconds Scram seconds I WRM-4, run-in PRM-5, run-in Scram Scram L

PRM-6, run-in t; Scram  %

Channel 4, 5, and 6 pots returned to last heat balance position.

11.

'?. EOM ' detector resconse cnecked and set to indicate >l cps.

Rev. 2/S2 App': . ._ ., 50P/ A-l a

11. O.ed. of re ce." ralir ticr. r.cr.itc t s (frent pau 3 checks).

r. . Tissic: trcitt r. iter.

b. Secenda:,e ceclar.t r.onitor. ~ g

c te: Ite::e 14 thrcugh 35 are to be ccmpleted in sequence i- .ediatcly prior to W pulling Tcds for a reactor startup. ,

14. Armunciator tes ted.

15. Annunciater alarn cleared or noted.

16. Power selectcr switch ISS in position required.

17. a. Bypass switches 2S40 and 2541 in position required.

b. All keys removed from bypass switches.

18. Master switch 151 in "on" position.

10 Magnet current switch on, check " Reactor On" lights. g

20. Reactor isolation, facility evacuation and AP3E checks. (Monday start-up) E These itens are to be checked with scrans and rod run-ins reset, and when appropriate items are actuated, verify that the TAA's do trip.

a. Reacter isolation switch (leave valves and' doors closed). (t'.onday start-up)

b. Facility evacuation switch (check outer containment homs).(nonday start-up)

c. AP35 trip setpoints checked and' tripped, . check buzzer cperational locally for all channels and remotely for channels 1 through 4 and 9.

Channel 1 - Ecam Room South Fall Channel 2 - Beam RoomVest 1:all Channel 3 - Beam Room North h'all g Channel 4 - Fuel Stor' age Vault .,'..

• 3 Channel 6 - Cooling Equipnent Room 114 _. a._. .

Channel 7 - Building Exhaust Air Plenum . (Monday start .bp). . . .

Channel 8 - Reactor Bridge (Switch in " Normals) (Monday" start-up)

Channel 9 - Reactor Bridge backup (switch inL? upscale *.) 1 Monday start-up)

d. Check IW readings: volts. .. '.~. - <

e. Check 150V reading: volts. . ,

_.~  :'.

~

Selector switch on AME in position 5.

f. m

,g. Trip backup nonitor with attached source.

....z.

h. Reactor isolation horns switch in " Isolation Borns On"fyosition.

~ ~

Valves and doors open. >

i. All ARMS trips set per SOP. . . . .

j. Check ventilation fans, containment and backup: doors. ?- ' b

21. . Operate reg blade from full-out to full-in knd set at 10"-CD5". .

a. Check rod run-in function at 301 withdrawn'and annuncTator at rod bottomed. '-

22. - Raise blade A to 2" and manually scram. -

.e i  :'

23. Raise blade E to 2" and trip manual rod run-in J: r.r.-

24. Raise blade C to ~2" and scram bf.i.hW1 trip. -c2 . M.

25. Raise blade-D to 2" and scram by IRM trip. ' . ./. ,

26. . Annunciator ' board energized; horn on. ,- .' [. E

27. Jumper and tag log cleared or.hpdated. "- - r.

3

28. IRM recorder in fast speed. F '

~

29. Check magnet current for 90 ma 'on each magnet. . t;

30. Cycle hM! range switch. .- -

.4 A N

31. Predicted critical blade positioni(f ~

inches). "

32. Pre-startup process data taken. #.

33. Visually check room 114 and D.I. area efter all _. systems lafu in operation; j

a. Check' oil reseIvoir for pu:np P501A,- 501B, and P533 for adequate supply.

Add if necessary. lent the 6000 gallon pc.ol;-hold.up. tank. -

34. Rcutine patrol.ca::plete$. , . g: .p ? :: . ,. d -

35. Reactor, ready for staitup T.ine JCo[n;ileted)

B E

Senior Reacter Operator SC P/." -l o Rev. 3/82 App'd_ 4 h

NS a-_-m_ - ._-. - s _ - . _ ma a a__ m.______a . . ~_ __ _m. 4 - m - . s.m-. _A -- _ .e-ms. _ .a._

_.mam.__

- . -s__- _ .

h l

REVISION NUMBER 4 TO OCTOBER 1981 MANUAL I  :

SOP /A-la Revised 5/82 I

l I

I I 1e I

l REACTOR STARTUP CHECKSHEET DATE:

FULt. POWER OPERATION Time (Started)

(or Low Power Forced Circulation)

BUILDING AND MECHANICAL EQUIPMENT CHECKLIST

1. Run emergency generator for 30 minutes and check the governor oil level.

(Required if shutdown for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or af ter each maintenance day.)

I 2. a. Check operation of fan failure buzzer and warning light. Shift fans.

(Required if shutdown longer than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.)

b. Test stack' monitor per 50P while in west tower.

I 3.

c. Test the stack monitor low flow alunn.

Visual check of room 114 equipment completed,

a. P501A and P501B coolant water valves open.

b. 51 and S2 hydraulic pumps on (oil' level normal).

c. Pump controllers unlocked to start ('as required).

d. Insure N backup system on per SOP.

e. Open air2 valve for valve operating header (V0P 31).

f. N9 backup valve open. ,

g. Check valves 599A and 599B open.

h. Pipe trench free of water (on Monday startups, check the four-pipe annulus drain valves for water leakage).

i. Add DI water to beamport and pool overflow loop-seals.

4. Visual check of CT equipment completed.

a. Oil level in CT fans normal (Monday start-ups).

5. Beamport Floor I a.

b.

c.

Beamport radiation shielding (as required).

Unused beamports checked flooded (Monday).

Seal trench low level alarm tested (Monday).

6. Emergency air compressor (load test for 30 minutes on Monday).

7. Reactor Pool

a. Reflector experimental loadings verified and secured for start-up.

I b.

c.

Flux trap experimental loading verified and secured for start-up, or strainer in place.

Check and reset, as necessary, silicon integrator and totalizer setting.

REACTOR CONTROL SYSTEM CHECKLIST

1. All chart drives on; charts timed and dated. IRM recorder to slow.

2. Fan failure warning system cleared.

I, 3. Annunciator board energized; horn off.

4. Television receiver on.

5. Primary / pool drain collection system in service per SOP.

6. Secondary system on line per S0P (as needed).

7. Primary system on line per SOP.

a. Primary cleanup system on line.

8. Pool system on line per SOP.

a. Pool cleanup system on line.

b. Pool skimer systen vented.

c. Pool reflector op trips set per SOP.

I 9. Valves Si and S2 cycled in manual mode and positioned as required.

10. Nuclear Instrumentation check completed per S0P.

a. The following trip values were obtained during the check.

IRM-2, run-in seconds Scram seconds IRM-3, run-in seconds Scram seconds WRM-4, run-in  % Scram  %

PRM-5, run-in  % Scram  %

PRM-6, run-in  % Scram  %

11. Channel 4, 5, and 6 pots returned to last heat balance position.

12. SRM-1 detector response checked and set to indicate > 1 cps.

Rev. 5/82 App'd h e . SOP /A-la 9 --

1

13. Check of process radiation monitors (front panel checks).

a. Fission product monitor.

b. Secondary coolant monitor.

Note: Items 14 through 35 are to be completed in sequence innediately prior to pulling rods for a reactor startup.

14. Annunciator tested.

15. Annunciator alarm cleared or noted.

16. Power selector switch 1S8 in position required. g

17. a. Bvpass switches 2S40 and 2S41 in position required. g

b. All keys removed from bypass switches.

18. Master switch 1S1 in "on" position.

19. Magnet current switch on, check " Reactor On" lights.

20. Reactor isolation, facility evacuation and ARMS checks. (Monday start-up)

These items are to be checked with scrams and rod run-ins reset, and when appropriate items are actuated, verify that the TAA's do trip. E

a. Reactor isolation switch (leave valves and doors closed). (Monday start-up) 5

b. Facility evacuation switch (check outer containment horns).(Monday start-up)

c. ARMS trip setpoints checked and tripped, check N z:er operational locally for all channels ani remotely for~ channels 1 through 4 and 9.

Channel 1 - Beam Roim South Wall Channel 2 - Beam Room West Wall Channel 3 - Beam Room North Wall Channel 4 - Fuel Storage Vault Channel 6 - Cooling Equipnent Room 114 Channel 7 - Building Exhaust Air Plenum (Monday start-up) '

Channel 8 - Reactor Bridge (Switch in " Normal") (Monday start-up)

Channel 9 - Reactor Bridge backup (switch in "tpscale") (Monday start-up)

d. Check HV readings: volts.

e. Check 150V reading: volts.

f. Selector switch on ARMS in position 5.

g. Trip backup monitor with attached source.

h. Reactor isolation horns switch in " Isolation Horns On" position. E Valves and doors open. 3

i. All ARMS trips set per SOP.

j. Check ventilation fans, containment and backup doors.

21. Operate reg blade from full-out to full-in and set at 10"+.05".

a. Check rod run-in function at 10% withdrawn and annuncTator at rod bottomed.

22. Raise blade A to 2" and manually scram.

23. Raise blade B to 2" and trip manual rod nzn-in. E

24. Raise blade C to 2" and scram by hM1 trip. E

25. Raise blade D to 2" and scram by IRM trip.

26. Annunciator board energized; horn on.

27. Jumper and tag log cleared or updated.

28. IRM recorder in fast speed.

29. Check magnet current for 90 ma on each magnet.

30. Cycle hEt range switch.

N

31. Predicted critical blade position ( inches). E

32. Pre-startup pIncess data taken.

33. Visually check room 114 and D.I. area after all systems are in operation.

a. Check oil resencir for pump P501A, 501B, and P533 for adequate supply.

lE Add if necessary. Vent the 6000 gallon pcol hold up tank. i

34. Routine patrol conpleted. I

35. Reactor ready for startup. Time (Completed)

Senior Reactor Operator Re v. 3/82 App'd <_

I I

i 4

4 I

I I

I l

1l REVISION NUMBER 5 TO OCTOBER 1981 MANUAL  ;

i i

l SOP /VII-16 Revised 6/82 l

l SOP /VII-22 Revised 6/82 l

l S0P/VII-24 Revised 6/82 l,

I l

i I

,1 i

I l

i I

1 I

i 1 i l 17

1. Connect the quick-disconnect hose to the master DI ]

supply. ]

2. Verify adequate level in T300 ~ 5000 gallons. ]

3. ]

Open DI valve.

F. Open air valve RE25, bleed any oil or water from the air l line via valve RE52. Adjust air regulator to 50 psig.

Nofity the reactor control room of intentions to begin the

. transferring of water to the drain collection tank.

G. Check valve DI13 closed.

l H.

I.

Open valve DI9.

Open valve DIl0 (DI200) or Dill (DI201) or D112 (D202) de -

l pending on column to be transferred, to pressurize the DI column.

l J. Slowly open DI14 to commence the transfer; monitor the transfer at the bullseye.

K. When transfer is complete, close DI14, close DIl0, Dill, or DI12 respectively.

L. Open DI8 and vent all pressure from the column. The column will now be refilled and flushed two times by the following procedure. ,

1. Open the DI supply, valves RE18 and DI3. Insure DI8 open.

I 2. Open R2 and fill the respective DI column with DI water until it starts to exit via 018.

3. Close R2, DIB, DI3. This flush water will now be transferred to the primary / pool collection tank.

4. Check DI13 closed and DI9 open.

5. Open valve DIl0 (D1200) or Dill (DI201) or DI12 (DI202) to pressurize the DI column.

6. Slowly open DI14 and monitor the transfer until all water has been transferred. Repeatt'he process for the second flush.

7. Close DI14, DI9, DIl0, Dill or DI12.

8. Open DI8 and vent all the pressure from the column.

Caution: It is extremely important that valve DI14 be closed after the transfer of DI water to the drain l Rev. 10/81 App'd, ~

SOP /VII-15 f/

collection system. Failure to close this valve before proceeding further could result in the addition of raw water to the drain collection system.

The unit now needs to be refilled; NEVER LEAVE IT DRY.

M. Open D13.

11 . Open R2 and refill the column until water starts to exit via DI8.

O. Close R2, DI3, and DI8.

P. Close all other valves opened (DI supply, RE18).

Q. Log in the resin log the exact status of the DI column.

The DI column is now ready for transfer. ,

VII.4.4 Preparation of Regenerate Solutions Required by Regeneration VII.4.4.1 Acid Regenerate Selections for Regeneration A. Detennine the required draws.

B. Fill mixing tank to proper water level for the required draws.

C. Add acid via the measuring tank for the required draws.

VII.4.4.2 Acid Solution Strength A. Specific gravity should be 1.172 0 66 F.

VII.4.4.3 Caustic Regenerate Solutions for Regeneration ]

A. Determine the required draws.

B. Fill mixing tank to proper water level for the required draws.

C. Commence air sparge of water.

D. Add the necessary bags of caustic soda for the required draws.

VII.4.4.4 Caustic Solution Strength A. Specific gravity should be 1.275.

R. . e . App.d x . ,,II ,

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1 M. After draining for 4 minutes, close RE15 and RE9, open RE16 and RE17 and re-establish a flow rate of 5-6 gpm at 100-110'F.

Note: Excessive gas volume may build up, and may be l N.

vented by opening RE9.

Open and throttle valve RE55 to educt Nacl to the resin at a rate of 3/4-7/8 inch per minute (1.2-1.4 gpm) for 40 minutes. Continually observe the resin column for indica-tion of offgasing; observe the draw down rate, the eductor flow and maintain proper temperatures. The temperature, flow rates, and peracentage of Nacl must remain within '.

their limits to obtain the desired results.

O. After the total volume of 20% Nacl solution has been educted, close valve RE55 and allow the bed to rinse for a minimum of 40 minutes. If, however, at the end of the treatment excessive offgasing is still being observed, re-peat the procedure after the 40 minute rinse with another 50 lbs. of Nacl by repeating steps J through 0. If off-gasing is not observed, proceed with step P.

! P. Close DHW valve RE28, RE17 and RE2. Open RE18 and open RE3 for a 25-30 gpm flow. Allow the bed to rise an addi-tional 30 minutes.

Q. Close valves RE27, RE18, RE3, RE7, RE16 to complete the Nacl treatment.

R. Log in the resin-filter log the exact status aad location of all resin beds.

VII.4.5.2 Backwash A. Connect the quick-disconnect hose to the DCW supply and open the master DCW supply valve (RE27).

B. Open valve RE18.

C. Open valve RE8 and RE16; close RE15.

D. Open valve RE4 gradually to give a flow rate of 15 gpm.

Rev. 10/81 Ap I; -- SOP /VII-21

E. During the backwash, frequently inspect through the sight glass to insure that proper separation is being achieved.

It may be necessary to vary the flow rate to obtain a good separation.

F. Backwash for 30 minutes minimum.

G. Close valves RE8, RE4, RE18, RE27, and RE16.

Note: Periodic hot water regenerations may be necessary to remove silicates which are not removed during cold water regenerations.

VII.4.5.3 Caustic Soda Treatment I A. Open the master DCW supply valve RE27 ]

B.

C.

Secure the solubridge.

Open RE2, RE7 and RE16. Close RE15.

l D. Open RE17 and adjust flow rate to 7 gpm.

E. Close breaker on MCC2 for caustic pump.

F. Open caustic pump suction and discharge valve.

G. Check closed RE61, RE63 RE66 and RE67.

H. Open RE6 and RE65.

I. Start pump and timer with pushbutton on control panel.

J. Throttle RE64 to maintain caustic flow of 1.25 gpm for 40 minutes.

K. Ten minute rinse between draws.

L. To prevent caustic eduction during rinse, close RE6.

M. Open RE6.

H. When last caustic draw is completed, close RE6, RE64 and RE65 and let unit rinse as is for 30 minutes.

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0. Secure the caustic pump at MCC2 and close its discharge valve.

P. After 30 minutes, close RE17, RE2, RE7. and RE27: secure DCW. 3 VII.4.5.4 Caustic Fast Rinse A. Open RE18, RE3, DI water supply from T300 pump, and RE7.

B. Turn on T300 pump. m Rev. 3L App' SOP /VII-22

1

\

C. Throttle to 30-35 gpm.

D. Check closed RE2 and RE17.

E. Monitor the rinse by performing an alkalinity test as per I "F" listed below.

F. Alkalinity Test: Obtain a 58.3 m1 sample from RE23 of rinse water, add 2-3 drops of methyl orange indicator.

While stirring, add 0.4N sulfuric acid, one drop at a time, until color changes from yellow to permanent faint pink or red. Each drop of acid solution equals 1 grain l per gallon (17.1 parts per million, ppm) of alkalinity.

At a resistance of 25K ohms, the alkalinity will be one ',

l grain or less.

l Note: If the solubridge is used to check the conductivity of the rinse water, it must be turned off before the acid draw to prevent damage to the cell.

G. Close valves RE3, RE7 and RE18.

H. Close the DI supply valve and RE16.

VII.4.5.5 Intermediate Backwash I

Inspect the resin through the sight glasses for proper separa-tion. If the resin has not been properly separated, proceed with a DI water backwash for 10 minutes as per VII.4.5.2.

When the separation is adequate, proceed with step VII.4.5.6.

Sulfuric Acid Treatment VII.4.5.6 h A. Switch disconnect to DI water. ,

B. Open DI supply valve.

l C.

D.

Adjust RE19 for 3 gpm downflow.

Secure solubridge.

]

]

E. Open RE3, RE7 and RE16. ]

F. Open RE1 and RE14 G. Adjust RE17 for 4-5 gpm and vent the acid vent tank until full of water.

I Rev. 4/82 4 p'd,h p h 30P/U R-P23

I H. Check shut RE56 RE59, RE60 and RE62.

I. Open acid pump isolation valves and close its breaker on MCC2.

J. Open RE5 and RE58.

K. Start acid pump and timer at control panel.

L. Throttle RE57 for 1.5 gpm for 30 minutes.

M. Monitor the vent tank while the acid treatment is in prog-ress to insure air does not pass through to the regener-ator. It may be necessary to vent excess air .from the vent tank during the treatment. .

When the acid injection is completed, close valve RE5 and N.

RE58 immediately.

O. After each draw, rinse for 10 minutes.

P. Open RES and RE58 for next draw.

Caution: Do not allow air to be injected into the re-generator during the acid treatment. Air bubbles will carry acid up into the anion resin and reduce its capa-city.

Q. Continue rinsing without changing the valve lineup for 30 R.

minutes.

Close the acid pump suction and discharge valves, secure l

the pump's electrical power at MCC2 and thoroughly rinse the acid pump with DCW inside and out.

S. Close RE57, RE58 and RES. ]

VII.4.5.7 Acid Fast Rinse A. Open DI supply valve.

E B. Open RE18 for maximum flow. E C. Close REl and RE14. Then drain the acid vent tank and ]

refill through REl .

D. Start T300 pump. ]

E. Throttle RE18 flow to 30 - 35 gpm.

]l F. Close RE17 and RE19.

Rev. Z- App' M% SOP /VII-24

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REVISION NUMBER 6 TO OCTOBER 1981 MANUAL SOP /I-17 Revised 6/82 I S0P/I-18 Revised 6/82 g SOP /A-16a New Addition 6/82 (3

SOP /A-16b New Addition 6/82 I

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\. . - - - - _ _ - _ _ _ _ . . _ _

M M , M .

M M Table IV (continued)

Scram Run-in Alarm Units

--- 40K cps

28. Fission Product ---

Monitor ill Activity Ssee below cpm

29. Off-Gas ll1 Act{vity --- ---

10 cps

30. Secondary Coolant --- ---

111 Actlyity

>6 --- inches

31. Anti-Siphon Line Hi ---

Level (abovevivs)

>23' 29'-1" --- inches

32. Pool Level Low

<10% or <20% or >60%  % withdrawn

33. Reg Blade ---

bottomed

--- 9 --- inches

34. Vent Tank Low Level (below{}

<1800 gpm

35. Secondary Coolant --- ---

Low Flow

36. Ch 4, 5 or 6 Downscale --- --- <75  % full-scale ]

--- --- off closed

37. Valve 546 A or 8

38. Valve 509 off open --- ---

--- --- off open

39. Valve 547 off open --- closed with

40. Valves 507 A/B P501 on

--- --- 90% open or ---

41. Valve S-1 90% shut SThis setpoint is determined by the semiannual calibration 50P/1-17 Rev. 6/82 App'd [/Fvv ,

Table IV (continued)

Scram Run-In Alarm Units

42. Nuclear Instrument sinoperative --- anomaly ---

43. Anti-Siphon System --- --- 31 psig Pressure Low Anti-Siphon System --- --- 44 psig Pressure High

--- open ---

44. Thermal Column Door ---

45. Truck Entry --- door seal ---

deflated

46. Evacuation or manual / auto --- manual / auto Isolation

47. Rx Systsm low 316 --- --- psig ]

Pressure (PT-943) 3 Pressurizer Pressure with normal system flow ]

6Any channel will scram on NI Inoperative except SRM App'd 50P/l-18 Rev. 6/82 9 a e,

E /

m Month Year D.1. WATER MAKEUP LOG

. l- Fill in only if sending DI water. +l Time Conductivity '

Water Meter Day Start Stop RO T-300 5 tart Stop Net Remarks Unit Start t Stop i

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5 1 Rev. 6/82 App'd , SOP /A-16a K

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NOTE: THIS PAGE INTENTIONALLY LEFT BLANK I

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p-.g- - - - - - - -

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SECTION 111 REVISIONS TO THE HAZARDS

SUMMARY

REPORT I

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I 1982 REVISIONS TO THE HAZARDS

SUMMARY

1. Page 1-1, section 1.1.2: Delete " animal quarters" in the seventh line.

2. Page 1-1, section 1.1.3: Delete "a laboratory for reactor operations" in the last line.

3. Page 1-2, section 1.1.3: Replace the word "five" with "four" in the third line of the first paragraph.

4. Page 1-2,3, section 1.1.3: Delete "and consists of two regions. The intermost region...the fuel region".

5. Page 1-3, section 1.1.3: Change "4" to read "up to 4" for the number of p-tube irradiation positions.

6. Page 1-3, section 1.1.3: Delete "8" for the number of reflector irradiation positions.

7. Page 1-4, section 1.1.3: Delete the last paragraph of this section.

8. Page 1-8, Table 1.1 EXPERIMENTAL FACILITIES: Delete "1.61 inch" for the flux trap.

Change "4" to read "up to 4" for p-tubes. Delete "8" and change " baskets" to " positions" for reflector irradiation.

9. Page 1-9, Table 1.1 FLUX TRAP: Change "1.61"" to read "3-5/16"".

10. Page 1-9, Table 1.1 WATER ISLAND: Change "1.33" to read "5".

11. Page 3-3, section 3.2.1 LIST OF SERVICES IN THE SEAL TRENCH: Change "4" inch to read "6" inch in item 2.

Add: Item 10. 3/8" copper drain to sewer for Beamport B Item 11. 1-1/4" vacuum line Item 12. 3/4" pvc Film irradiator helium supply Item 13. 3/4" pvc Alternate air supply line to exhaust plenum backup doors from emergency air compressor.

Item 14. 3/4" pvc (blanked)

12. Page 3-5, section 3.2.6: Delete the last part of the first sentence "and one 4" exhaust line from the blower".

13. Page 4-9, Table 4.1: Change " Average Power Density... 303 MJ/ liter at 10 MW".

Change "Maxgeff with One Stuck Rod 6.2 Kg(25) Core... 938".

14. Page 4-10, Table 4.1: Change " Equilibrium Xenon Worth 6.2 Kg(25) Core...

I -0.02730 AK/K". Add: Change Peak to Equil. ratio to 2.22." Change " Equilibrium Samarium Worth...

-0.008275 t>K/K".

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15. Page 4-11, Table 4.2: Add under the heading " Energy Group Structure for Four  !

Groups". Add in the left side of the table:

Fission Spectrum Group 4

3

.25 2

.75 1

16. Page 24 and 25a of Addendum 1: Delete the last three paragraphs and replace with:

"The generator will run for approximately 30 minutes weekly under no load conditions. This is accomplished by a timer in which the generator runs on Monday mornings. The generator is load tested on a semi-annual interval ."

17. Page 7-5: Change " weekly" to " prior" to startup in the third paragraph.

18. Page 7-5: Change "4" to "6" in the first paragraph of section 7.1.7.

19. Page 7-7: Add after the last paragraph: "A longer air operated fuel handling tool is presently bein used. The pool level remains at its normal level when using the longer tool. Fuel can be transferred to the X, Y or Z I baskets using the longer tool."

20. Page 7-16: Change " aluminum storage tanks" to " carbon steel tanks" in the first sentence of section 7.2.2.

21. Page 7-17: Add "This system is presently not being used" at the end of section 7.2.3.

22. Page 7-19: Delete the words " located within the reactor containment building" from the second paragraph of section 7.2.8.

23. Page 7-20: Add after the heading for section 7.2.9: "A computerized telephone system has been installed in this facility. This new system incorporates a paging feature with several different phones being able to originate the page."

24. Page 5 of Addendum 2: Add after the second paragraph (See Section 12.2.2 revision 1977 for current requirements for RAC reviews.)"

25. Page 8-10: Change the words "four" to read "up to 4" and seven" to read "up to 6" in the third sentence of the first paragraph of section 8.5.

, 26. Page 8-11: Change the word "four" to read "up to 4" in the first sentence of the second paragraph of section 8.5.

ll

27. Page 8-11: Change the word "four" to read "up to 4" in the first sentence of the fourth paragraph of section 8.5.

21

l l 28. Page 8-12: Delete " passes through the containment wall...for a long period of time where temperature is of prime concern" and replace it with " exhaust to the facility stack plenum".

29. DELETE: Section 8.4 and replace with:

8.4 Irradiation Baskets Irradiation baskets are housed in the graphite (rev. 1982) reflector region between Beamport A and Beamport D.

There were originally 12 removable graphite elements which could be replaced with irradiation baskets (modified graphite elements to house samples while being irradiated at relatively high thermal neutron fluxes).

This graphite region has been modified.

A large wedge shaped irradiction basket occupies two rows of the original four row design.

This wedge is an aluminum helium filled structure with six irradiation positions. A solid aluminum three-inch irradiation basket occupies two sections of another row. Two pneumatic tubes occupy two sections of the last row.

All s6mples that are irradiated are approved, prepared, and scheduled for irradiation by the Reactor Services group. A record is kept of all i rradi ations. Various forms are now utilized. The type of form is determined by the type of sample and position required for irradiation.

s 22

30. Page 93 of Addendum 1: Delete "into the containment building. From there... evacuation alarm is initiated" and replace with "the facility exhaust stack plenum". Delete "On the fifth level of the containment... volume of 20,411 cfm", in the last paragraph of page 93 of Addendum 1, item 3.19, in section 8.5.

31. Page 8-13: Delete the second and third paragraphs of section 8.6 and replace with:

"The graphite stack incorporates a bismuth filter, neutron radiographic variables aperture, and a slot for the irradiator case for the film irradiator experiment. The original thermal column door has been replaced with a new door that incorporates a film irradiator experiment. Figure 8.3 is a cross seccional view of the thermal column door, and the film irradiator experiment. The thermal column door moves on two floor level tracks and is driven by an electric motor through a gear reducer box. An electrical interlock assures that the control rods cannot be withdrawn unless the door is fully closed."

32. Page 9-3: Change "90%" to "60%" in the first paragraph.

33. Page 9-6, Table 9.1 #57: Change "90%" to "60%". Add "81. . .P-tube blower light... light." Add "85... Digital Readout. . . Digital Readout".

34. Page 9-7: Delete #50. Change #59 to read: " Intrusion Alarm Switch.. 2 Pos.

Switch". Add: "78... Intercom Box". Add: "79...T.C. Door Shutter.. 2 Pos. Switch". Add: "80... Airlock Door Security Switch.. 2 Pos.

I Switch". Add: "82...P-Tube Blower Exhaust.. 2 Pos. Switch". Add:

"83. .. Airlock Door Open Switch. . .P. B. Switch". Add: "S4... Digital Selector Switch.. 25 Pos. Switch".

35. Pages 9-7 through 9-9, Table 9.2: Change complete table to read exactly as the following pages 9-7 through 9-9.

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23

Table 9.2 presents a summary of the devices installed in the instrumen?. (rev. 1982) cubi_le. The " Number" column Table 9.2 refers to the identification on Figure 9.3.

I TABLE 9.2 INSTRUMENT CUBICLE DEVICES Item No. Function 1 Annunciator 2 Source Range (Level) Channel 1 Recorder 3 Intermediate Range (Level) Channel 2 and 3 Recorder 4 Power Range (Level) Recorder 5 Area Radiation and Process Recorder 6 Reactor Water Inlet-Outlet Temperature Recorder, 2 Pen Reactor Water Temperature Control Controller I 7 8 Pool Water Inlet-Outlet Temperature Recorder, 2 Pen 9 Pool Water Temperature Control Controller 10 Reactor Water Flow Recorder, 2 Pen 11 Pool Water Flow Recorder, 2 Pen 12 Demineralizer Flow Recorder, 2 Pen 13 Secondary Flow Inlet-Outlet Temperature Recorder, 3 Pen 14 Reactor Water Inlet-Outlet Differential Temperature 15 Pool Water Inlet-Outlet Differential Temperature 16 In-Pool Heat Exchanger Differential Temperature 17 Primary Pressure 18 Differential Pressure Across Pool Reflector 19 Reactor Water Conductivity 20 Demineralized Reactor Water Conductivity 21 Pool Water Conductivity 22 Demineralized Pool Water Conductivity 23 Clock 24 " Reactor On" Indicating Light 25 Source Range Count Rate Scaler 26 Source Range Monitor 27 Channel 2 Intermediate Range Monitor 28 Channel 3 Intermediate Range Monitor (9-7) 24

i TABLE 9.2 (Cont'd)

INSTRUMENT CUBICLE DEVICES lI I

Item l No. Function 29 Master Power (2CB1A/B) 30 Power Level Channel 4 31 Power Level Channel 5 32 Power Level Channel 6 33 House Relays for Interlock and Annunciator Use (K-1 Relay) 34 Regulating Blade Servo Anplifier 35 Area Radiation Monitoring 36 Area Radiation Monitoring 37 Area Radiation Monitoring 38 Noncoincidence Logic Unit Scram / Yellow 39 Actuator Amplifier Scram Unit / Yellow I 40 Actuator Amplifier Scram Unit / Green 41 Noncoincidence Logic Unit Scram / Green 42 26 VDC Regulated Power and Magnet Current Indication and Adjustment 43 Fuel Rupture Monitoring 44 Safety System Relays (K-2 Relays) 45 Secondary Coolant Monitoring 46 Door 101 Open Lite and Tag 47 TV Monitor 48 South Wall Area Radiation Monitor 49 West Wall Area Radiation Monitor 50 North Wall Area Radiation Monitor I 51 Fuel Storage Area Radiation Monitor 53 Cooling Room Area Radiation Monitor 54 Building Air Plenum Area Radiation Monitor 55 Bridge Area Radiation Monitor (4) 56 Bridge Area Radiation Monitor (2) 58 Noncoincidence Logic Rod Run-In Unit 59 Rod Run-In Actuator Amplifier 61 (Not Used)

Pump and Fan Operation "Off-On" (Note 2) (13)

I 62 63 (Not Used)

(9-8)

I 25

TABLE 9.2 (Cont'd)

IhSTRUMENT CUBICLE DEVICES ITEM NO. FUNCTION 64 Annunciator Alarm Power Switch Of f, Annunciator f5, Horn Off, Both On 65 Valve Control (See Note 1) (8) Switch, 2 Pos " Auto-Man" 66 Valve Control (See Note 3) (12) Switch, 2 Pos "Open-Close" 67 Pump and Fan Control (See Note 2) (13) Fan Switch, 3 Pos "On-Off-On" Pump and Fan Control (See Note 2) (13) Pump Switch, 2 Pos "Off-On" 68 Valve Pos "Open-Closed" (See Note 4) Indicating Lights 69 Vent Duct M0 Door 1 Stop Push Button 70 Vent Duct M0 Door 2 Stop Push Button 71 Vent Duct M0 Door 1 Indicator Light end Switch Push Button 72 Vent Duct M0 Door 1 Indicator Light and Switch Push Button Vent Duct M0 Door 2 Indicator Light and Switch Push Button I 73 74 Vent Duct M0 Door 2 Indicator Light and Switch Push Button 75 Branch Circuit Protection Fuse (7) 131 16A Valve Closed Marker Plate and Light 132 16A Valve Open Marker Plate and Light 133 16B Valve Closed Marker Plate and Light 134 16B Valve Open Marker Plate and Light 135 Fan Failure Alarm Lights 136 Emergency Generator On 137 Secondary H2O Temperature Hi 167 Back-Up Door Alarm 168 3 Off-Gas Recorders 169 Stack Monitor On Light, Hi/Lo Flow Alarm 170 Auxiliary Radiation Monitor and Nuclepore Alarm Panel 171 Radio 172 Power Level Monitor I NOTE 1: Valves AS46A, A546B, A507A/B, A509, A545, A526, A527A, A527B NOTE 2: Pumps P-1, P-2, P-3, Fans CT-1, CT-2, CT-3, Pumps P-501A, P-501B, P508A, P508B, P513A, P513B, P533 NOTE 3: Valves A546, 547, 507A/B, 509, 543A/B, 527E, 527F, 545, 526, 527A, 527B, 527C NOTE 4: Valve Indicator Lights V546A, V5468, V507A/B, V509, V543A/B, V527E, V527F, V545, V526, V527A, V528B, V527C (9-9)

TABLE 9.2 (Cont'd)

INSTRUMENT CUBICLE DEVICES Item No. Function 173 Mode Selector Switch 2S40 174 Mode Selector Switch 2S41 175 Drain Collection Control Panel 176 980/990 RTD Readout 177 Conductivity Amplifiers 193 Valve 552A Open Light 194 Valve 552A Closed Light 195 Valve 552B Open Li9ht 196 Valve 552B Closed Light 197 Valve 552B Open/ Normal Switch 198 Valve 527D Open Light 199 Valve 527D Closed Light 200 Valve 527D Open/ Normal Switch 202 003A/B Reactor Water Inlet Temperature 203 903A/B Reactor Water Outlet Temperature 204 953 Reactor Water Outlet Hi Temperature Scrams 205 954 Reactor Water Differential Summer Temperature 207 In-Pool HX AT 208 903C/D Pool Water Outlet Temperature 209 903C/D Pool Water Inlet Temperature 210 952 Pool Water Differential Summer Temperature 211 911A/B Power Supply GE/MAC 212 919A/B Reactor Water Flow Square Root Converter 912C/D Reactor Water Flow Square Root Converter 213 919A/B Pool Water Flow Square Root Converter 919C/D Pool Water Flow Square Root Converter 214 955 In-Pool HX Temperature Differential 215 911A/B Power Supply GE/MAC 216 919A/B Reactor Water Demin. Square Root Converter I 919C/D Reactor Water Demin. Square Root Converter (9-9a)

I TABLE 9.2 (Cont'd)

INSTRUMENT CUBICLE DEVICES No. Function 71T 920A/B Reactor and Pool Water Low Flow Scram 218 919A/B Pool Water Demin. Square Root Converter 919C/D Pool Water Demin. Square Root Converter 219 920C/D Reactor and Pool Water Low Flow Scram 220 911C Power Supply GE/MAC 221 Blower 222 Room 114 Door Open 223 Cooling Tower Tunnel Door Open 224 DI-200-Di-201 Door Open 225 DI-202-R200 Door Open 226 Cooling Tower Door Open 227 Alarm Cut Out Flasher 228 DCW Low Pressure Alarm 229 Fire Main Low Pressure 230 Channel 5 and 6 Recorder 231 Rod Drop On/0ff Power Switch I 232 Rod Drop Reset Push Button 233 Control Blade Drop Time 234 Rod A Drop Timer 235 Rod B Drop Timer 236 Rod C Drop Timer 237 Rod D Drop Timer 238 Alarm Cutout Switches 239 Mode Annunciation I 240 241 RTD 980A Pkter RTD 980B Meter 242 DPS 928A Meter 243 DPS 928B Meter 244 DPS 929 thter

<g 245 919F Poo's Water Flow Square Root Converter 246 920F Pressurizer Level Alarm Unit (9-9b) 28

I TABLE 9.2 (Cont'd)

INSTRUMENT CUBICLE DEVICES l No. Function I 74 7-248 920G Pressurizer Level Alarm Unit 920H Pressurizer Level Alarm Unit 249 Pressurizer Level Indication 255 PS 944A Peter 256 PS 944B Meter 258 V547 Position Indication 259 919E Reactor Water Flow Square Root Converter 260 Nuclepore Exhaust Valves 261 Hot Cell Isolation Valve (9-9c)

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36. Page 9-16, Table 9.3: Change #8 to read " Water tank T-301 Hi or Low Level". #9 to read: " Water tank T-300 Hi or Low Level", #13 to read:

"20% withdrawn", #15 to read: " Jumper board in use", #16 to read: " Thermal column door open", #17 deleted, #25 to read:

" Fuel vault intrusion".

37. Page 9-18: Change "36" to "40" in the second paragraph of section 9.6.1.

38. Page 9-18: Change "65%" to "60%" in the first paragraph of section 9.6.2.

39. Page 9-19. Change "65%" to "60%" in the sixth paragraph of section 9.6.2.

40. Page 9-22: Delete section 9.7.4 paragraph and replace it with: "A scintillation detector is installed in the return leg of the secondary piping. The output of the scintillation detector is fed into a I l og-count-rate-meter. This instrument provides a signal to the multipoint radiation recorder and a high radiation alarm to the annunciator."

41. Page 9-23: Change "105%" to "120%" and "110%" to "125%" in the third paragraph of section 9.8.1.1.

42. Page 9-24: Delete "and three flow switches" from the first sentence of section 9.8.2.1.

43. Page 9-25: Delete the last paragraph of section 9.8.2.1.

44. Page 10-1: Delete items 2, 3, and 4 under section 10.1.

45. Page 10-5: Delete "The 2 ton monorail crane listed in Section 10.1 will be used to service the area" from the sixth paragraph of section 10.3.

46. Page 11-10: Delete the second paragraph of section 11.7.

47. Page 11-12: Delete the last sentence of section 11.9.

48. Page 11-12, Section 11.10: Delete " Reactor Period (as indicated on channel 2 and 3).

49. Page 11-13: Delete the words "will be recorded as specified in Appendix A" from the first and second sentence on this page.

I 50. Page 13-3, Table 13.1: Change " void coefficignts" to read " Island...x 6.48x10-4 and core... -2.51x10-3".

51. Page 13-9: Change the first sentence to read: "a reduction to less than 23'".

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52. Appendix: The following Appendices are deleted by this 1982 revision.

1 Appendix C Radiation Safety Program 2 Appendix D Internal Staff Resumes 3 Addendum 5 Appendix A, Change 1 to Technical Specifications dated 10-3-73 4 Addendum 2 Appendix II, Reactor Designer Technical Memoranda 5 Addendum 1 Appendix I, Preoperational Checkout Procedure for the Process Instrumentation and Interlock 6 10MW Preoperational Test Procedures

53. Page 12-1, section 12.1: Last sentence of the second paragraph, change "5" to "7" and " Appendix E" to Figure 12.1".

54. Page 12-2, section 12.1: In the last paragraph, change " Dean of Research Administration" to " Associate Vice President Academic Affairs".

section 12.2.1. In the first sentence, change " Dean of Research Administration" to " Associate Vice President Academic Affairs".

55. Page 12 -3, section 2.2.2: Delete the original first paragraph.

56. Page 9-22, section 9.8: Add after the heading "See Sections 9.14 and 9.15 for 10MW upgrade modifications."

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SECTION IV PLANT AND SYSTEM MODIFICATIONS JULY 1981 I Modification 81-15: Replaced the rectangular aluminum drain collection tank with a round dished-end stainless steel tank. This change incorporated oil separators on the inlet drains and a tank drain valve replacing the drain plug.

Safety Analysis Summary: Modification 81-15 presents no unresolved safety question. It changes the tank material and capacity and minimizes the potent tal leakage of radioactive water to the liquid waste collection system.

AUGUST 1981 Modification 81-18: Installed a new secondary flow detector in parallel with the existing Bailey flow sensor. The new flow detector is of the Rosemount design and provides a digital indication on the reactor control panel.

Safety Analysis Summary: Modification 81-18 presents no unresolved safety l question. It provides provides a backup indication of secondary flow.

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OCTOBER 1981 Modification 81-21: Permitted added clearance for the insertion and future removal of the beryllium reflector. This modification was the machining of the reflector support skirt to allow for increased clearance between the skirt and graphite reflector support plate. Aluminum oxides have been measured at 0.004" on materials in the pool for long periods. Burrs or defects that existed on the reflector support tank base

, could easily occupy 0.012". Original design designated a clearance of 0.010" nominal, between the outside of the beryllium support skirt and the graphite reflector support plate. This modification increased the cleararice to 0.030".

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Safety Analysis Summary: Modification 81-21: Modification 81-21 presents no unresolved safety question. This modification does not alter the size, location, position, or any other aspect of the beryllium reflector. This permitted the new reflector to be placed in position with greater ease and will facilitate future I removal.

Modification 81-22: This modification is to facilitate removal of the terminal pins at each end of the pressure vessel tie rods. It will prevent dropping and loss of any component part and minimize the time required for installation and removal of the tie rods, decreasing radiation dose. The pin diameter and shear strength are identical to that specified by original design. Stainless steel bolts, nuts and jam nuts are replaced by stainless steel pins and a spring retainer clip attached to the tie rod end by stainless steel cable. The installation of the attachment nuts, on the tie rod flats, does not affect the function of the tie rods and minimizes radiation dose during work on the rods.

Safety Analysis Summary: Modification 81-22 presents no unresolved safety question. All materials at load bearing points are of equal strength to the original.

NOVEMBER 1981 Modification 81-20: This modification replaced the drain valves on the two primary and one pool strainers. The original valves, designated 518AE, 519AF, and 518AG, were 1/2" aluminum body, natural rubber, diaphragm valves. These valves were replaced with stainless steel ball valves to facilitate flushing the strainers and removal of debris.

Safety Analysis Summary: Modification 81-20 presents no unresolved safety question. The valves removed hat a pressure rating of 200 psig while the new valves have a pressure rating in excess of 1000 psig. The rapid flushing afforded by a ball valve design will minimize radiation dose received by personnel when debris must be flushed from the strainers.

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Modification 81-23: This modification is for use in Compliance Check CP-13, testing the vent tank system. This change incorporates a method of interruptiag power to V552 A/B solenoids which is safer and should prove more reliable than the past method of lif ting electrical leads. The use of insulated, dummy phono jacks provides the interruption of elec rical power to V552 A/B solenoids.

Safety Analysis Summary: Modification 81-23 presents no unresolved safety question. The continuity of the contacts will be checked as part of the compliance procedures when the plugs are removed and before the 552 A/B valves will be considered operable.

JANUARY 1982 Modification 81-7: This modification installed flanged connections on the primary relief valves to minimize chance of damage to the pipe bung in the primary loop.

Because there are three interchangeable relief valves, the valve located in the pool also has flanged fittings installed.

Safety Analysis Summary: Modification 81-7 presents no unresolved safety question.

The flanged connections allow easier removal, installation and testing of the relief valves.

I APRIL 1982 Modification 80-5: This modification was the installation of a new Bulk Pool Lead Shield Irradiation Facility under offset "D". This modification removed the "S" basket, Reuter-Stokes Air Force Irradiation Facility, and the old Bulk Pool Lead Shield Irradiation Facility which were no longer in use.

Safety Analysis Summary: Modification 80-5 presents no unresolved safety question.

The installation of the new Bulk Pool Lead Shield Irradiation Facility under offset "D" will allcw an easier sample operaticn in the graphite reflector.

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APRIL 1982 Modification 82-2: This modification replaced the 2" diameter H-2 irradiation reflector element and H-3 graphite reflector element with a single irradiation element dimensioned to accommodate a 3" diameter sample holder.

Safety Analysis Summary: Modification 82-2 presents no unresolved safety question.

The installation of the r.ew 3" irradiation position will allow the reactor to better serve the needs of its users.

JUNE 1982 Modification 81-16: This modification replaced the installed acid and caustic pumps in the regeneration system. The new pumps are better able to handle the severe environment of strong acid and caustic.

Safety Analysis Summary: Modification 81-16 proposes no unresolved safety question. The installation of these high quality pumps will minimize the hazards of working with strong corrosives.

Modification 82-3: Replaced the existing gasoline day tank with one of a larger capacity and provided a vacuum break system to minimize vapor lock on the emergency generator.

Safety Analysis Summary: Modification 82-3 proposes no unresolved safety question.

The installation of the larger gasoline day tank and vacuum break system will enhance the reliability of the emergency generator.

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SECTION V NEW TESTS AND EXPERIMENTS New experimental programs durin;; 2. period of July 1981 through June 1982 are as follows.

RUR150 Experimenter: David Troutner

Description:

The RUR was amended to include

! irradiation of 10 microcuries of Am-241 for the purpose of determining the fission product yields.

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SECTI0t1 VI l SPECIAL NUCLEAR MATERIAL ACTIVITIES 1 July 1981 through 30 June 1982

1. SNM Receipts: During the year, the MURR received fuel from Rockwell International Energy Systems Group (Atomics International). A total of 18 new fuel elements were received.

I Shipper Elements Grams U

Grams U-235 Atomics Int'l. 70, 73, and 78 through 14,928.91 13,904.3 85, 71, and 87 through 93

2. SNM Shipments: Spent fuel elements were shipped to U.S.D.0.E. Savannah River Plant for reprocessing.

Grams Grams Shipper Elements U U-235 MURR M03, M038, MOS, M039, M034, 16,148.33 14,077.38 M040, M044, M042, M018, M020, M019, M036, M014, M045, M035, M047, M032, M016, M030, M037, M023, M024, M025, M028

3. Inspections: On July 29-31, 1981, Safeguards Inspection was conducted by Mr. A. G.

Finley of Region III, USNRC. One item of noncompliance was identified during the course of his inspection.

4. Stim Inventory: As of 30 June 1982, the IfdRR financially responsible inventory was as follows:

Total U = 37,218 Total U-235 = 33,145 All of this material is physically located at the IfJRR. In addition, ifJRR has three 350 gram elements stored at Atomics International.

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I Fuel elements on hand have accumulated the following burnup as of 30 June 1982: -

Fuel Element Accumulated Fuel Element Accumulated Number Megawatt Days Number Megawatt Days M015 147.16 M067 132.27 I M017 M021 147.68 147.80 M068 M069 95.58 132.27 M022 143.13 M070 91.97 M026 148.61 M071 41.62 M027 148.22 M072 103.84 M029 148.76 M073 91.97 M031 146.65 M074 103.84 M033 146.59 M075 93.05 M041 146.44 M076 95.58 M043 146.44 M077 93.05 M046 146.09 M078 105.44 146.09 I M048 M053 147.53 M079 M080 105.44 89.50 M054 147.53 M081 105.69 M055 149.30 M082 89.50 M056 41.62 M083 105.69 M057 149.30 M084 60.19 M059 115.88 M085 60.19 M060 115.88 M087 51.42 M061 100.61 M088 0.00 M062 100.38 M089 51.42 M063 145.98 M090 40.03 M064 112.98 M091 50.09 M065 145.98 M092 40.03 M066 112.80 M093 50.09 I

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I The three 350 gram fuel elements stored at Atomics International have the following inventory content:

Total U = 1,112.39 grams Total U-235 = 1,036.19 grams Also MURR owns a total of 128 grams U and 49 grams U-235.

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I SECTION VII .

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

Serial Number Core Designation Date Last Used M038 A0-12 08-06-81 M040 A0-12 08-06-81 M020 AP-1 08-10-81 I M016 M037 AP-1 AP-2 08-10-81 08-24-81 M026 AP-6 10-06-81 I M017 M043 M041 AP-6 AP-9 AP-9 10-06-81 11-09-81 11-09-81 M033 AP-10 11-16-81 M021 AP-10 11-16-81 M031 AP-13 12-28-81 M017 AP-15 01-10-82 M026 AP-15 01-10-82 M046 A0-4 02-08-82 M048 A0-4 02-08-82 I M015 M027 M022 A0-7 A0-7 A0-7 03-14-82 03-14-82 03-14-82 l M029 A0-7 03-14-82 M055 A0-14 06-07-82 i M057 A0-14 06-07-82 i M063 A0-17 06-28-82 l M065 A0-17 06-28-82 Normally 24 fuel elements are listed as retired, but due to increased shipping costs i for new and irradiated fuel, fuel elements that cannot be utilized during a normal fuel cycle (previous definition for retirement) are retained in the active fuel cycle structure for possible use in an abbreviated fuel cycle.

lI Due to requirements of having less than 5 kg of unirradiated fuel on hand at one time, initial criticalities are normally conducted with four new elements or fewer I as conditions dictate. A core designation consists of eight fuel elements of which only initial critical fuel element serial numbers are listed in the following table. To increase operating efficiency, fuel elements are used in mixed core 40 I

loading, therefore, a fuel element fabrication core number is different from its "

core load number.

Fabrication Serial Core Load Initial Core flo. No. Designation Operating Date 29 M072 AP-1 08-06-81 29 M074 AP-1 08-06-81 29 M075 AP-2 08-10-81 I 30 29 30 M077 M070 M078 AP-2 AP-5 AP-5 08-10-81 09-14-81 09-14-81 I 29 30 30 M073 M079 M081 AP-5 AP-5 AP-12 09-14-81 09-14-81 11-30-81 30 M083 AP-12 11-30-81 I 30 30 M080 M082 AP-13 AP-13 12-15-81 12-15-81 30 M084 A0-5 02-08-82 31 M085 A0-5 02-08-82 27 M056 A0-7 03-09-82 31 M087 A0-7 03-09-82 29 M071 A0-7 03-09-82 31 M089 A0-7 03-09-82 31 M090 A0-12 04-04-82 31 M091 A0-12 04-04-82 31 M092 A0-12 04-04-82 32 M093 A0-12 04-04-82 31 M088 (initial criticality will be next fiscal year)

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2. Fuel Shipping: Twenty four spent fuel elements were shipped from our facility during the fiscal year. The following list contains the serial numbers of the fuel elements that were shipped.

M03 M024 M037 M05 M025 M038 l

I M014 M016 M018 M028 M030 M032 M039 M040 M042 l3 M019 M020 M034 M035 M044 i 3 M045 M023 M036 M047 I

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3. Fuel Procurement: At the present time, MURR fuel is being fabricated by Rockwell International Energy Systems Group of Canoga Park, California. This work is contracted with U.S.D.0.E. and administered by the Idaho Operations Office.

4. Licensing Activities: A revised physical security plan as per 10CFR70:67 that was l submitted May 16, 1980 is still pending. No changes were made to our Facility License No. R-103 (Docket No. 50-186) during this fiscal year. The latest amendment to our license is Amendment 14 which was issued April 14, 1981.

5. Reactor Characteristic Measurements: In September 1981, an initial criticality startJp Was performed on Test Core BNB (MWD's 750) to benchmark reflector response and general criticality conditions. The reactor's original Be reflector was replaced during a maintenance shutdown scheduled between October 15, and October 23, 1981. The original reflector had a power history of 26,529 MWD which was accumulated between 1966 and 1981. The power level for the Be reflector was SMW until 1975 at which time it was raised to 10MW. After the Be reflector replacement,

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Test Core BNB (MWD's 750) was used to measure the new Be reflector response and general criticality conditions. Test Core ANB (NWD's 92) and Core AP-8 (MWD'S 493) were also used in physics measurements. Shim blade calibrations and reactivity measurements of triple barrel flux trap holder were performed to verify reactivity parameters.

A series of four (4) reactivity measurements for various flux trap sample loadings were performed during May of 1982. A physical inspection of the following fuel elements was performed at approximately 130 MWD's to verify the operational parameters:

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l M053 from Core 27 during May 1982 J M067 from Core 28 during May 1982 M069 from Core 29 during May 1982

. All measurements were within operational requirements.

i Computer analysis of graphite reflector was accomplished using Citation Computer Code. A master's degree was granted to Mark Pohlman for his work in this area.

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I SECTION VIII

SUMMARY

OF RADI0 ACTIVE EFFLUENTS RELEASED TO THE ENVIRONMENT Released to Sanitary Sewer 1-81 to 6-30-82 Nuclide Amount (Ci) Nuclide Am' aunt (Ci)

H-3 via cooling .001 Sb-125 .001 tower drain 1-131 < .001 H-3 .812 1-133 < .001 Na-24 < .001 Cs-134 < .001 K-42 < .001 Cs-137 .001 Sc-46 .006 Ba-140 < .001 Cr-51 .012 Ga-72 < .001 Mn-54 .004 Ta-182 < .001 Co-57 < .001 La-140 < .001 Co-58 .002 Ce-144 < .001 Fe-59 .001 Na-122 < .001 Co-60 .046 Cd-115 < .001 Zn-65 .106 Zn-69m < .001 Ni-65 < .001 Ba-139 < .001 Se-75 < .001 Tc-99m < .001 I As-76 < .001 Mo-99 < .001 As-77 .004 Hf-181m < .001 Ag-110m .002 Au-196 < .001 Sn 113 < .001 Au-198 < .001 Sb-122 < .001 Hg-203 < .001 Sb-124 .006 I

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Stack Ef fluent 1-81 to 6-30-82 Nuclide Amount (Ci) Nuclide Amount (Ci)

H-3 16.265* Pb-212 < .000001 Na-24 .000001 Tc-99m < .000001 C1-38 .000428 Tc-101 .000005 Ar-41 2504.1 In-114m ,

.000006 Sc-46 < .000001 Cd-115 < .000001

< .000001 Sb-122 < .000001 I Mn-54 Co-57 < .000001 1-128 .000011 Co-58 .000001 1-131 .000646 Co-60 .000006 I-132 .000220 Cu-64 .000016 Te-132 .000001 Zn-65 .000001 1-133 .000982 Se-75 < .000001 Xe-133 .000029 As-76 .000002 1-134 .000360 As-77 .000519 I-135 .000706 Br-82 .000073 Xe-135 .000002 Kr-85m .000001 Xe-135m .000276 Kr-87 < .000001 Cs-137 < .000001 I Rb-89 .000004 Cs-138 .000014 Zr-97 < .000001 Ba-139 .000038 Mo-99 .000001 Ce-139 .000002 Sb-124 < .000001 Ba-140 .000002 Sn-113 < .000001 La-140 .000002 Ag-110m < .000001 Ce-144 .000004 Fe-59 < .000001 Hf-181m < .000001 l

l K-40 .000433 Ta-183 .003143 1

Na-22 < .000001 Ir-192 < .000001 W-183m .003143 Au-196 < .000001 Xe-131m .000015 Hg-203 .000097 f

! Cs-138 .000014 Bi-214 .000024 l Au-198 < .000001 Pb-214 .000013 l

• 742 Ci evaporated via cooling tower.

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I SECTION !X

SUMMARY

OF ENVIRONMENTAL SURVEYS Environmental samples are collected two times per year at nine locations and analyzed for radioactivity. These locations are shown in Figure 1. Soil and i vegetation samples are taken at each location. Water samples are taken at four of the nine locations. Results of the samples are shown in the following tables.

Detection Limits Matrix Alpha Beta Gamma Tritium Water 0.2 pCi/1 2.5 pCi/1 0.04 pCi/1 9.1 pCi/ml Soil and 0.2 pCi/g 2.5 pCi/g 0.04 pCi/g 9.1 pCi/g vegetation

1. Sampling Date: 10-29-81 Determined Radioactivity Levels Sample M pha Beta Gamma Tritium 1 v 20 < 0.2 pCi/g 9.1 pCi/g < 0.04 pCi/g < 9.1 pCi/g 2 v 20 < 0.2 pCi/g 15.0 pCi/g < 0.04 pCi/g < 9.1 pCi/g 3 v 20 < 0.2 pCi/g 9.2 pCi/g < 0.04 pCi/g < 9.1 pCi/g 4 v 20 < 0.2 pCi/g 19.1 pCi/g < 0.04 pCi/g < 9.1 pCi/g 5 v 20 < 0.2 pCi/g 13.4 pCi/g < 0.04 pCi/g < 9.1 pCi/g 6 v 20 < 0.2 pCi/g 13.8 pCi/g < 0.04 pCi/g < 9.1 pCi/g 7 v 20 < 0.2 pCi/g 10.1 pCi/g < 0.04 pCi/g < 9.1 pCi/g 8 v 20 < 0.2 pCi/g 17.9 pCi/g < 0.04 pCi/g < 9.1 pCi/g 9 v 20 < 0.2 pCi/g 13.6 pCi/g < 0.04 pCi/g < 9.1 pCi/g 1 S 20 0.3 pCi/g 7.4 pCi/g < 0.04 pCi/g 2 S 20 < 0.2 pCi/g 7.5 pCi/g < 0.04 pCi/g 3 S 20 < 0.2 pCi/g 4.1 pCi/g < 0.04 pCi/g I 4 S 20 0.2 pCi/g 4.6 pCi/g < 0.04 pCi/g

< 0.04 pCi/g 5 S 20 0.4 pCi/g 5.0 pCi/g 6 S 20 < 0.2 pCi/g 4.2 pCi/g < 0.04 pCi/g 7 S 20 < 0.2 pCi/g 8.8 pCi/g < 0.04 pCi/g 8 S 20 < 0.2 pCi/g 6.4 pCi/g < 0.04 pCi/g 9 S 20 < 0.2 pCi/g 4.7 pCi/g < 0.04 pCi/g 46

I 4 W 20 < 0.2 pCi/g 7.7 pCi/1 < 0.04 pCi/1 < 9.1 pCi/g 6 W 20 < 0.2 pCi/g 5.9 pCi/1 < 0.04 pCi/1 < 9.1 pCi/g 8 W 20 < 0.2 pCi/g 7.3 pCi/1 < 0.04 pCi/1 < 9.1 pCi/g 9 W 20 < 0.2 pCi/g 11.1pCifl < 0.04 pCi/1 < 9.1 pCi/g Detection Limits Matrix Al pha Beta Gamma Tritium Water 0.2 pCi/1 2.5 pCi/1 0.04 pCi/1 9.1 pCi/ml Soil and 0.2 pCi/g 2.5 pCi/g 0.04 pCi/g 9.1 pCi/g vegetation

2. Sampling Date: 4-27-82 Determined Radioactivity Levels Sample Al pha Beta Gamma Tritium 1 V 21 < 0.2 pCi/g 25.4 pCi/g < 0.4 pCi/g < 9.1 pCi/g 2 V 21 < 0.2 pCi/g 23.1 pCi/g < 0.4 pCi/g < 9.1 pCi/g 3 V 21 0.2 pCi/g 23.4 pCi/g < 0.4 pCi/g < 9.1 pCi/g 4 V 21 < 0.2 pCi/g 32.2 pCi/g < 0.4 pCi/g < 9.1 pCi/g 5 V 21 < 0.2 pCi/g 34.2 pCi/g < 0.4 pCi/g < 9.1 pCi/g

< 0.2 pCi/g 41.6 pCi/g < 0.4 pCi/g < 9.1 pCi/g 6 V 21 7 V 21 < 0.2 pCi/g 25.8 pCi/g < 0.4 pCi/g < 9.1 pCi/g 8 V 21 < 0.2 pCi/g 24.8 pCi/g < 0.4 pCi/g < 9.1 pCi/g 9 V 21 < 0.2 pCi/g 32.2 pCi/g < 0.4 pCi/g < 9.1 pCi/g 1 S 21 < 0.2 pCi/g 12.8 pCi/g < 0.4 pCi/g 2 S 21 0.5 pCi/g 6.8 pCi/g < 0.4 pCi/g 3 S 21 0.2 pCi/g 8.4 pCi/g < 0.4 pCi/g 4 S 21 0.3 pCi/g 10.1 pCi/g < 0.4 pCi/g 5 S 21 < 0.2 pCi/g 11.7 pCi/g < 0.4 pCi/g 6 S 21 0.3 pCi/g 11.9 pCi/g < 0.4 pCi/g 7 S 21 0.7 pCi/g 12.2 pCi/g < 0.4 pCi/g 8 5 21 < 0.2 pCi/g 9.2 pCi/g < 0.4 pCi/g 9 S 21 1.2 pCi/g 21.5 pCi/g < 0.4 pCi/g I 4 W 21 < 0.2 pCi/1 6.3 pCi/1 < 0.4 pCi/1 15.1 pCi/ml 6 W 21 < 0.2 pCi/1 3.8 pCi/1 < 0.4 pCi/1 15.3 pCi/ml 8 W 21 < 0.2 pCi/1 12.0 pCi/1 < 0.4 pCi/1 < 9.1 pCi/ml 9 W 21 0.4 pCi/1 113.0 pCi/1 < 0.4 pCi/1 12.1 pCi/ml 47

Radiation and Contamination Surveys The following table gives the number of surveys performed during FY 81-82.

Radiation Contamination 321 303 Forty-nine (49) Radiation Work Permits were issued during the year.

Miscellaneous Items Reactor Health Physics developed the ability to analyze neutron spectra l

using a Bonner Spheres type spectrometer.

The Missouri Coanission on Low Level Radioactive Waste met at the Reactor Facility for a discussion on radioactive waste disposal needs. The Manager of Reactor Health Physics gave a talk describing radioactive waste and disposal needs.

Replacement of the reactor beryllium reflector was accomplished using 14 manRem of exposure. The highest exposure for the calendar quarter for any person involved was 880 mrem.

Reactor Health Physics obtained equipment to perform alpha, beta and gamma spectromet ry.

During the year, ALARA efforts used $28,000 on nine equipment items which is expected to result in 9 manRem/ year exposure reduction. In addition, three of the items reduce or eliminate the potential for unplanned exposure to workers.

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SIC 110% i Sweef Dr aclailDA t P050EE510 FCILlif 5f MF, itP[RIN hTERS A43 V15110R5 personnel W itoring (esposu re in weew) 1981 Jaly Asqutt Septe*ber October hnveedee C+tember A B C D t 8 C D t 9 C D I 8 C D E 9 C D t B C D 1 E 67 53 104 343 73 45 ICJ 255 70 49 76 270 63 4D 154 E95 64 55 71 255 63 43 67 235 I r.5 pare

• 53 15 IG3 15 5 192 643 14 19 155 633 IF 5 llE 235 5 3 97 17D IE 4 77 3 5:

6 77 ili 1105 12 33 649 15D95 17 31 413 7670 34 14 351 105; 11 31 Zib 1033 73 3D 155 E50 U{C)

U(C).5 pare

• 2 0 0 0 7 1 3155 3T50 2 6 310 133D 1 7 163 163 1 3 563 1610 3 3 113 233 F. (Il 55 140 22 4 75 1 R, 26 3 73 13) 3 29 93 135 49 0 0 0 29 3 12G 203 G.5 pare' 9 4 17 60 5 1 33 33 5 2 95 165 i 5 95 133 7 1 193 195 4 0 0 0 iK) 12 2 545 610 9 1 725 77S 6 t- 266 510 F 5 233 510 15 1 33 31 7 6 526 3433 U(G).5 pare" 4 13D lb < 0 0 0 1 7 595 7s3 7 1 595 793 0 3 523 2495 0 0 0 0 1

D 0 49 97 3C TO 26 1;z Faa 10 27 121 243 0 36 65 170 0 43 95 250 9 32 94 230 1982 January February N rch April Ny June A B C D E B C D E B C D E B C D E B C D E B C D E E 67 5E 93 350 71 56 56 193 47 74 63 210 70 50 73 333 10 50 73 333 65 52 66 243 E.5 pare

• 9 7 70 310 11 5 14 2 00 6 15 43 120 14 10 33 183 14 3 63 143 27 5 164 150 17 33 165 660 22 36 333 4100 33 21 223 2030 10 7 186 5993 33 50 263 3365 44 43 565 5410 U(C)

U[C)-5 pare

• 0 3 143 4C'I 5 135 263 7 5 124 333 3 7 96 260 0 3 103 160 14 7 543 2170 G 40 4 66 220 42 16 41 393 1 29 30 33 56 25 25 493 26 7 25 160 61 6 21 50 G.5 pare

• 1 1 53; 530 5 0 0 0 1 15 60 60 6 1 20 20 6 0 0 0 6 3 37 70 9 6 473 1850 6 9 268 1193 7 5 121 643 10 6 173 610 5 6 655 3563 + + + +

C{C) h(G).5 pare

• 393 383 0 0 0 4 0 100 183 0 0 0 0 2 0 0 0 = + + +

0 1 1 D 13 26 92 200 11 29 bi 210 15 zi 1G1 270 13 29 96 205 12 29 111 .'2 5 la 29 tl zea hote: C = monthly beta gama. neutron file 4,adge Column headings: A = Type of dostmeter I U(C) = monthly finger ILD E = hamber reported as sinteu'r G

• monthly bete.gawa film badge C = henber eeported with esposures above einimum U(G) = monthly finger ILD D = Average of esposures above sintBJm P= self-reading dosimeter i = Single highest ecstseter reported eCombined accounts with U(C) and U(C).5 pace.

Sund for temporary workers, vies w3rkers peter to issue of permanent, and replatewnt f or lost badges.

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