ML20094P456

Startup Rept on Fuel Follower Control Rod Installation at Afrri

ML20094P456
Person / Time
Site:	Armed Forces Radiobiology Research Institute
Issue date:	03/31/1992
From:	Bumgarner R, Manderfield N, Maria Moore ARMED FORCES RADIOBIOLOGICAL RESEARCH INSTITUTE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9204080155
Download: ML20094P456 (27)

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DEFENSE NUCLE /,R AGENCY

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RSDR 2 April 1992 SUlHECI': Cubmission of Stntup Report on Fuel Follower Control Rod installation Document Control Desk 50 ~ n U.S. Nec! car Regulatory Comtaiwiot Washington, D.C. 20555 _

Oc tiemen:

The AFRR1 TRIGA staff have prepared a startup report as required by Technical Specification 6.6.La. Enclosed are copies of "Stanup Report on Fuel Follower Cordrol Rod Installation at AFRRl" If you have uiy questiom or conunents, please contact myself or the Reactor Operations Supavimr, Capt Matt Forsbacka, at (301; >>5-1290.

Sincerely,

'b] d L[ % s

Enclosure:

MARK L MOORii as stated Reactor Facility Director Counesy Copies to- .

USNRC - Region 1 - Project Engineer Division of Reactor Projects Mr. T. Dragoun ,

USNRC- Healquarters - Project Manager Nuclear Reactor Regulation ,

Mr. M. Mendonca 920[000155 920331 )

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. e aueme Startup Report on l'uct I ollower Control Itod Ins'.allation at AFRRI Docket 50-170 1.icense 11-84 March 1992 Matt l'orsbacka Mark Moore Chris Owens Mike 1.uughery llatry Spence John Nguyen Rob George 1

l DEFENSE NUCLEAR AGENCY

! 1 ARMED FORCES RAD 10810 LOGY RESEARCH INSTITUTE BETHESDA,M ARYLAND 20814 5145 l

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-. . _ . . _ _-_---_ _ ..__ _. . _. m. . ._ ._ . _ -_ . _ _._ ._.- _ _ _-. --. _ _

I Points of contact for further information irguding dils chicument:

Mr. Mark L. Moore Reactor Facility Director Armed Forces Radkhiology Research Institute

. (301)-295-1290 p

Capt Matt ForAcka, USAF Reactor Operations Supervisor Armed Forces Radiobiology Research Institute (301) 295-1290 Submitted by:

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MARK L MOORil'~ #

Reactor Facility Director  ;

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l have deteimined that the nulifications to the Scactor Facility, as desesibed in this 'lechmcal Report (Stattup iteport as per Technical Specification 6.6.1.a), involve no unreviewed salety issues and were conducted in accordance with the 10 Cl:R 50.59 :equest approved by the NHC on 8 OCT 91. I submit this Technical Regmrt to the Reactor and Hadiation l'acility Salety Committee (RRl;SC ' '~. t review and concunence. -

bSi? EC M ARK MOORl! U Reactor Facility Dicector The Riti;SC has reviewed this Technical Reimrt and concurs with the determination that the nuidifications to the Reactor 1:acility, as described in thi. 'lechnical Report, involve no unteviewed safety issues.

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N.W. Manderfield Colonel, 8) sal 8, MSC Chairman, RRI:SC s

APPROVi!D 1 OR Rlil.liASli '

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ROllliRT L. IlUMGAR IR Captain, MC, USN V Director

Introduction [

This report is prepared in accordimee with AFRR1 Technical Specification 6.6. l.a. It addresses i the license change of maximum steady state power ir. crease to 1.1 MW muimum steady state power level and the installation of fuel follower control rmis (FFCRs). The installation of fuel follower control rals (FFCRs) is described in chronohtgical sequence and analysis of the results is provided. For a detailed description of FFCRs and their safety analysis with regard to installation at AFRRI, see AFRRI TR91-1,

• Maximum Temperature Calculation and Operational  ;

Characteristics of Fuel Follower Control Rods for the AFRR1 TRIGA Reactor Facility". FFCRs were installed to offset the long-term effects of fuel-burnup and increase the core excess reactivity, AFRRI first applied to the USNRC for a technical specification amendment to allow for the installation of FFCRs on 30 Apr 90. The FFCRs arrived at AFRRI from General Atomic on 8 Aug 91, and the NRC approved installation of the FFCRs on 8 Oct 91. The FFCR installation project at AFRRI began on 8 Nov 91 and concluded on 12 FEB 92.

Receiving and Storage of FFCRs Prior to Installation Prior to receiving the FFCRs, the llot Cell was prepared for fuel storage. The room was made free of dust and debris, a gamma detector (criticality monitor) was in place, a high security k>ck was installed, and cradles for holding the fuel were built.

The FFCRs entered AFRR1 through the shipping and neceiving department (1 OGS). LOGS

. personnel were instructed to not open the containers holding the FFCRs. LOGS personnel called .

RSDR and SHD immediately upon receipt of the FFCRs. SHD performed a radiological survey in accordance with HPP-0-3 of external radiation and external contamination of the packaging in the huding dock arer prior to moving the FFCR containers to the Hot Cell. No measurable contamination was foun<l. ,

Once the FFCRs were cleared by SHD to be moved to the Hot Cell, RSDR staff conducted a ,

series of tests within the Hot Cell to determine if any uranium was on the outer surface of the ,

FFCR cladding. The testing methodology was similar to the series of measurements outlined in 10 CFR 70.39 which deals with the certification of calibration or refeience radiation sources.

The following tests were conducted:

1. Dry wipe test. The entire surfaces of the FFCRs were wiped with filter paper using malerate finger pressure. No radioactivity was found on the filter paper.

2. Wet wipe test. The entire surfaces of the FFCRs were wiped with filter paper, moistened with water, using moderate finger pressure. No radioactivity was found on the filter paper.

3. Water Bail Test. The FFCRs were completely immerwd in boiling water for one hour. The residue obtained by evaporating the water showed no presence of uranium using the SHD counting lab.

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4 Appendix 1 contains radioanalysis reputs of the t.bove tests.

Core Preparation Prior to shutdown and FFCR installstion, neutron activation foils / wires were used in liR1 with the bare core configuration at a fixed gisition near the center of the nom. .An approximate neutron enenty spectrum was doermined and the data was saved for later comparison with FFCR loaded core.

Fuel unkiading commencet 8 Nov 91 and was completed on 12 Nov 91 (see AFRRI TRIGA Refueling Plan, Appendix 2). Following the removal of fuel, the standard control nxis and transient control nxi were ternoved. The nxi drive support stmeture was then umdified to allow for the case of tnmsient nxl drive maintenance. A platform was built approximately 40 inches above the axl drive mounting plate to accommmiate the transient rod drive mechanism. Work to nuxlify the transient nxi drive platform was completed on 18 NOV 91.

! While thu tunsient nxi drive platform was being fabricated, RSDR staff set up two liF, chambers in the core to be used for suberitical multiplication measurements during fuel reloading. The counting systems consisted of ANPDR 70 neutron detectors which wac modified to use a Harshaw Type S212414AB BF, chamber. The output from the ANPDR 70 was sent to a scaler. The BF, chambers were h>cated in core grid positions F-18 and F-7. A fission chamber was set tap over core grid location F-11 as an additional neutron monitor during fuel reloading.

The signal from the fission chamber was sent through a PA l$ amp'.ifier and scaler.

The FFCR and transient nxi connecting nxis were assembled on 1819 Nov 91. The method for i

determining the correct length of the connecting nxi was as follows

l 1 -

Using blueprints, the center of the poison section was hicated on each control nxi.

The center of the poison was marked on each nxl using a magic marker. i The old control nx! was attached to the barrel ussembly and was extended to its full length. The center points of the old nxi and the FFCR were then matched and the new connecting nxi length was measmrd from the top of the FFCR to the connection point on the barrel assembly. ,

Installation of FFCRs into AFRR1 TRIGA Reactor Core With the core free of fuel, FFCRs were inserted without danger of activation. The FFCRs were <

centered in their grid locations using the set screws for the barrel assemblics. The goal was to r

, minimize any rubbing of the FFCR as it travels up and down. Once the FFCRs were center:d, drop t ime tests were performed to insure compliance with the technical specifications.

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Refueling AFRR1 TRIGA Reactor Core Refuelling of the AFRR1 TRIGA reactor core comm:need on 20 NOV 91.1/M ph>ts wea made to insure that a conservative appmach to refueling the reactor core was taken. The actuni tuel Imding steps w _te recorded in the reactor operations logtook; shown below are the 1/M pkns during the approach to a critical configuration:

1/H vs Number of Fuel Elements 26 November 1991

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A critical configuration was achieved on 29 Nov 91 with 69 elements in a close packed array, Fuel was then addal to get enough excess reactivity to allow for the calibration of control nuls.  ;

A thermal power calibration was performed to insere that the placement of the fission chamber was conect (data is recorded in the core physics logiwk). For an operatiomd fuel loading of 84 standard fuel t!ements and diree FFCRs. control nxi calibraions yielded the following results:

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Transient $4,14 Reg $2.63 i Safe $2.06 Shim $2.41 With the excess reactivity of $4.40 measured on 6 Dec 91, this insured a shutdown reactivity of

$6.71. With the most reactive nxi removed (the transient rod), the shutdown reactivity is $2,57 which is well in excess of the tecimical specification limit of $0.50. The predicted value of the shutdown reactivity with the transient nxi removed (see AFRRI TR91-1) was $2.80, with the [

measured value reasonably close to the predicted value. A mechanical stop was placed on the transient nxi by an udministrative directive to limit its travel and prevent an inadvertent reactivity insertion of greater than $4,00.

Operational Testing Program Power operations greater than cold critical commenced on 2 DEC 91 with a 100 kW steady state l power run to perform a thermal power calibration. 1.0 MW was attained on 4 DEC 91 to calibrate the high. flux safety channels. During the period of 5 Dec 91 to 25 J AN 92 the reactor operated exclusively in the steady state male to continue checkout and system calibrations, Pulsing operations commenced on 25 JAN 92. The sequence of pulse opcations listed in the refueling plan was followed. The purpose of the pulsing program was to gradually stre.tch the fuel cladding in a controlled manner. Following the Nising program, the reactor was operated at full power for two hours to ensure that the cladding had not failed during the course of testing.

No increase in radiation levels in the CAMS or water monitor box were observed. Routine tests l of the water performed by SHD have shown no presence of thsion pnxlucts in the reactor pool j wate; .

l The operational testing program was completed on 12 Fell 92 with the final full power test to the license power limit of 1,1 MW, This test was conducted in accontance with the refueling plan. The following table shows rmi positions, fuel temperatures, and radiation levels during the appnuch to the license limit of 1.1 MW.

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(cpm) (mRihr) g 100 602 582 585 599 128C 111;C 3 30 5 500 670 731 669 669 322C 295C 7* 40* 20 3 7* I 1000 751 818 799 799 431C 430C 40* 50 1050 750 828 817 808 440C 441C 8* 45* 70 1070 750 850 817 808 44'ct' 443C 8' y15* 70 1090 Serum -- -- --- -- - --- --- - -- - - - - - - ---

_ __ n Table 1. Key scactor parameters recorded during approach to full power limit.

• Increase in level is due to shine from the high energy N gamma ray.

Note that the scram set point is set at 1.09 MW to insure that the 1.1 MW power limit is not exceeded. The maximum temperaturr attained was 443C: this is 557C less G au the technical specifications safety limit and 157C less than the limiting safety system setting for fuel temperature.

f Conclusion FFCR installation at the AFRRI reactor was completed in a safe and timely manner. All radiological surveys and measurements indicated that there was no release of fission products during any phase of testieg or operations. The installation of FFCRs resulted in the reduction -

of the core fuel inventt.c by three standard fuel (lement.s. The increase in excess reactivity is exrected to etter.d the current core operational capabilities for five to ten years.

5

o-Appendix 1 Radioanalysis Reports of FFCR Surveys I

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,w DISPOSITION FORM m.m. e. mm, ,, ..,u, SUI Analyses of fuel elemnts w rum ws om L ISt2 Castle 5 lby 91

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1. Analyses were performed 30 Oct 91 - 1 Nov 91 for the fuel elanents recently l received by IED. Piasse note the enclosed AFRRI Form 144 sheeto. Each is described briefly below.

2. Enclosure -(1) contains resulta fran smear surveys of the cap encasing the elements, the plastic wraa surruunding each elanent, a wet smear of the first element, a dry smear os the first elanent, and a dry smear of the first rod after boiling. All activity was less than 10 pCi/ smear.

j 3. Wet arri dry smears were also performed cn the seemd, third and fourth rods.

Results of these smears are ccntained in enclosures (2) and (3). Activity was less than 10 ;Ci/ smear.

4. Water samples were taken after each rod was boiled. 100 4 of each sample -

were boiled down and analyzed for alpha ard beta activity. All were less tJan 1000 ml canples were analyzed for ganna activity. No peaks were l 10 pCi/ smear found in any p a le.

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Appendix 2

!_ AFRR1 TRIGA Refueling Plan and Associated Documents

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AFRRl/RSDR 25 NOV 91 MEMORANDUM FOR REACTOR STAFF P**

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. .ana SUlijECT: Core Reloading and FFCR installation We will commence core reloading tomorrow. For the duratica of this core reloading project, we will use the AFRRI TRIGA Refueling Plan which is more specific than Operational Procedure 7. Record all refueling related data in the refueling laboratory notebook which will be maintained on the teactor control console. f

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Reactor Facility DirectoI

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AFRRI TRIGA Refueling Pisa Receiving and Storagt. of FFCRs Priot w Installation Prior to receiving the FFCRs, the Hot Cell wili be prepared for fuel storage. The room will be reasonably free of dust end debris, a gamma detector (criticality monitor) willis in place, a high

/ sceurity lock will be installed, and cradles for holding the fuel will be available.

The FFCRs will enter AFRRI through the shipping :md receiving department (LCN A memorandum will be preparcd (See attachment 1) to instruct LOGS personnel to not open the containers holding the FFCRs. LOGS personnel will be instructed to call RSDR and SHD immediately upon receipt of the FFCRs. THD will perform a radiological survey in accordance

') with HPF-0-3 of external radiation and external cornamination of the packaging in the loading b dock area prior to moving the FFCR containers to the Hot Cell.

Once the FFCRs have been cleared by SHD to be moved to the Hot Cell, RSDR staff will conduct a series of tests within the Hot Cell to determine if tmj uranium is on the outer surface of the FFCR cladding. The testir.g methodology is sunilar to senes of measurements outlined in 10 CFR 70.39 which deals with the cesification of calibration or reference radiation sources. '

The following tests will be conducted:

l. Dry wipe test. The entire surface of the FFCRs will be wiped with filter paper using moderate finger pressure. Any radioactivity on the tilter paper will be determined by measuring the radiation levels using SHD's counting lab.

(

2. Wet wipe test. The entirc surface of the FFCRs will be wiped with filter paper, moistened with wa'er, using moderate finger pressure. Any radica':dvity on the filter paper will be determined by measuring the nadiation levels using SHD's counting lab. _

3. Water Beil Test. The FFCRs will be completely immersed in haihug water for one hour. The residue obtained by evaporating the water will then be monitored for tbc presence of uranium using the SHD counting lab.

If measurable quantities of radioactivity se preserd following any of the above tests, the FFCRs will be thoroughly cleaned and the tests will be repeated in the event that radioactivity is founu after repeated tests and cleanings, the shipment will be rejected and returned to tlw manufacturer.

Following the cumulation of successful tests showing no contamination of the FFCR exterior cladding with uranium or other radioactive contaminants, the FFCRs may be moved to storage in the Reactor Room.

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Core Preparation P

Prior to shutdown and FFCR installation, neutron activation foils / wires in will be used in ERI

_ with the bare core configuration at a ftxed position

me maer from the core. Determine neutron j energy spectrum, save data for later comparisor *h FFCR loaded core. Next, completely l unload all fuel from the reactor core. Following the removai of fuel, the standard control rods ,

and transient control rod w0 he removed. The rod drive support stmeture will then be modified as required to allow for the .1,e of tnmsient rod drive maintenance. Next, the new transient rod will be installed.

The FFCR connecting rods will be set up to allow for the removal of FFCRs without bringing them out of the reactor pool. Once the FFCRs have been irradiated, they will become highly radioactive due to their fission product inventories, so it will be important to keep them under .

water for shielding purposes.

Installation of FFCRs into AFRR1 TRIGA Reactor Core '

Measurements of the required connecting rod lengths will be made by measuring the entire length of the standard rods connected to the barrel. Correcting for differences between the FFCRs and -

the standard rods, the connecting rod lengths for the FiCRs will be determined. The connecting -

rods will then be attached to the FFCR and the entire unit will be installed into the reactor core.

The connecting rods will then be attached to the barrel assembly to complete the installation of the FFCRs.

Following installation, the FFCRs will centered in their grid locations using the set screws for the barrel assemblies. The goal is to minimize any rubbing of the FFCR as it travels up and ,

down. Oace the FFCRs have been centered, drop time tests will be performed to insure compliance the technical specifications.

Refueling AFRR.I TRIGA Reactor Core A conservative approach to refueling the reactor core will be taken. These instructions will supplement Reactor Operational Procedure Vll. Once the critical loading has been achieved, excess reactivity will be estimated using the transient rod until there is enough excess reactivity to perform rod worth curves. Excess reactivity will be determined after each fuel loading step until the operational configuration is achieved. Care will be taken to ensure that the $5,00 maximum allowed excess reactivity _is not exceeded.

Following Reactor Operational Procedure VII, install the thermocoupled fuel elements and load the B ring. Place neutron source in source holder and 11F neutron detectors in F 7 and F-18.

3 Then load elemems for grid locations C-1, C-5, C-6, C-9, C-10, C-l1, D-14, D-15, E-18. E-19,F-22, and F-23. Loading these elements will allow for the neutronic coupling of the FFCRs l and the neutron source. At this point the rods will be withdrawn as described in step 2.a. of the

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l procedure, and the first suberitical multiplication measurements will be taken. 1 Complete lo ding the C-Ring, load D-ring elements 2, 6, 8,12, and 18, and repeat the suberitical multiplicat i,m measurements. Complete loading the D-ring, and load E-ring elements 5, 6,14, 15; perfor n suberitical multiplication measurements, lead E-ring elements 1,2,8,9,10,16, 17, and 24; perform suberitical multiplication measurements. Load E-ring elements 2, 23, 7, i1,13, and 20; perform suberitical multiplication measurements, lead the following sets of elements and perform suberitical multiplication measurements after each step (note: this load pattern may be modified to accommodate instrumentation or other items that may obstruct fuel loading): E-4 and E-12; E-21 and E-22; F-1 and F-2; F-3 and F-30; F-4 and F-29; F-5 and F-28; F-6 and F-27; F-26 and F-16; F-15 and F-17; F-14 and F-18; F-13 and F-19; F-12 and F-20; F-Il and F-21; F-10; F-9; and F-8. This loading pattern allows for the FFCRs to exercise a high influence over the neutron population while the core is still very soberitical.

Core Calibration Once the core has been loaded to the operational excess reactivity, core calibraticas will proceed in the same manner as following an annual shutdown. Differential and integral reactivity worth curves will be generatul for each rod in core positions 250,500, and 750. U1, to this point all testing has been done at very low powers, so the fission product inventory in the FFCRs will be low. Since the probability that the FFCR cladding may fail is highest shortly after installation, a series of pulses will be performed to stmss the FFCRs before the fission product inventory has much of a chance of building up. During this pulsing operation the water will be closely monitored for any fission fragments. In the event that fission fragments are found in the pool water, all activities will stop, the NRC and GA will be notified, and the leaking element (s) will be found and isolated.

A thermal power calibration will be performed in the usual manner. Next the power coefficient of reactivity curve will be generated followed by the reflection coefficient measurements in p%itions 250,500, and 750. The neutron energy spectrum experiment in ERI and ER2 will be repeated to ensure that the character of the radiation field has not been modified.

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Refueling Checklist Pre-shipment

1. Clean Hot Cell.

2. Inspect Hot Cell, ensure area is reasonably dust free.

3. Install high security lock on Hot Cell.

4. Fnsure radiation monitor in hot cell is functional.

5. Prepare fuel cradles, install in Hot Cr?l.

6. Send memoranda to SHD and LOG on receipt of FFCR shipment.

Receipt of shipment

7. SHD performs radiological suneys of exterior of package in accordance with their procedures.

8. FFCR packages are transferred to Hot Cell.

9. Open FFCR shipping packages in Hot Cell.

10. Place FFCRs in prepared cradles.

Hot cell testing

11. Perform dry wipe test.

12. Perform wet wipe test.

13. Perform water boil test.

14. Repeat wet wipe test.

15. If all tests are successful FFCIb may be moved to the Reactor Room for storage.

Core preparation

16. Use neutron activation wire set from Reactor Experiments to establish base line neutron energy spectrum using Ledney's set up.

17. Unioad all fuel from the core in accordance with Procedure Vil,

18. Modify the rod drive support structure.

FFCR installation

19. Install new transient rod.

'20. Fabricate connecting rods for FFCRs.

22. Install FFCRs, insure that they are not ' bottomed out" with they are fully down.

23. Measure FFCRs against FFCR standard, record results.

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24. Reinstall FFCRs, install rod drive motors, and center FFCRs in their core grid locations.

25. Perform drop time tests to insure compliance with Technical Specifications.

Core refueling

26. Place neutron source in its holder, and place BF, or fission detectors in core grid locations F-7 and F-18.

27. Load the thermoccupied elements into core grid krations B-5 and C-6.

28. Complete loading the B-ring and load C-1, C-5, C-6. C-9, C-10, C-11, D '4, D-15, E-18, E-19, F-22, and F-23. Perform subcritical mukiplication measurements.

29. Complete kuding trTe C-ring. Load D-ring h> cations 2, 4, 6, 8,10,12,14,16, and 18.

Perform suberitical multiplication measurements.

30. Complete loading of D-ring, and %d E-ring elements 5,6,14, and 15. Perform sul. critical multiplication measurements.

31. . Load E-ring elements I, 2, 8, 9,10,16,17, and 24. Perform suberitical multiplication measurements.

32. l. cad E-ring elements 15,19, F-22, and F-23, place neutron source into its holder, and perform subcritical multiplication measurements.

33. Load E-ring elements 2, 23, 7, II,13, and 20. Perform subcritical multiplication measurements.

- 34. Load E-ring elements 4 and 12, and perform suberitical multiplication measurements.

35. Lead E-ring elements 21 and 22, and perforn' suberitical multiplication measurements.

.... NOTE "* *

• When critical configurr.tien is achieved, estimate excess reactivitf usag the transient rod. Continue loading until the is enough excess reactivity to perform a control rod worth measurement

-36. LM F-ring elements I and 2, perform subcritical multiplication / excess reactivity

measurements.

37. Load F-rkg elements 3 and 30, perform subcritical multiplication / excess reactivity meazirements.

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. 38.' Load Fyring elements 4 and 29.- perform suberitical multiplication / excess reactivity measurements.

39. _ Load F-ring elements 5 and 28, perform excess reactivity measurements.

40. lead F-ring elements 6 and 27, perform excess reactivity measurements.

41. Load F-ring elements 16 and 26, perform excess reactivity measurements.

42.1. mad F-ring elements 15 and 17, perform excess reactivity measurements.

43. Load F-ring elements 14 and 18, perform excess reactivity measurements.

• * *

• NOTE * "

• Do not exceed $5.00 excess reactivity!

. . . . . . Perform thermal power calibration'at 500 to insure preper placement of operational channel. Perform rod worth curves for all rods in position 300 when operational loading is achieved  ;

. 44. Load F-ring elements 13 and 19, perform excess reactivity measurements.

45. Load F-ring elements 12 and 20, perform excess reactivity measurements.

46. Load F-ring elemeatx 11 and 21, perform excess reactivity measurements.

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47. Load F-ring elements 10, perform excess reactivity measur ments, t-L - 48. Load F-ring elements 9, perform excess reactivity measurements.

49. Load F-ring elements 8, perform excess reactivity measurements.-

' Core calibration

50. Install all core instrumentation into their permenent positions.

51. Perform tod worth curves for all rods in care positions 250,500, and 750.

52. ! Perform thermal power calihretion and set safety chambers.

- 53. Repeat neutron energy spectra measurement in ERl.

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4 Amendment to AFRRI TRIGA Refueling Plan introduction

.The RFD has postponed the pulse testing of the FFCRs to allow for pulse testing during non-duty hours for the Institute. This is being done to prevent the interruption the work being perfonned in the Institute in case one of the new elements fail during the testing process. Pulse testing will commence during the last week of January. Full power testing to 1.1 MW will be conducted when it will not interfere with low dose studies being conducted in mid-January to early Febntary.

Pulse Testing The parpose of this pulse testing program is to gradually stretch the fuel cladding and test the integrity of the welds in the FFCRs. If the core is cold, it will be preheated at 50 kW steady state power for ten minutes. Allow the core to cool for 20 minutes before commencing pulse operations. Pulse operations will be performed in the following sequence:

At position 500 with balanced control rod configuration (monitor CAM levels and water monitor box radiation levels)

1. Pulse 1.05$

2. Pulse 1.10$

3. Pulse 1.15$

4. Pulse 1.155

5. Pulse 1.20$

t 6. Pulse 1.255 i 7. Pulse 1.25$

S. Pulse 1.25$

9. Pulse 1.25$

10. Pulse 1.25$

, 11. Pulse 1.30$

12. Pulse 1.35$

13. Pulse 1.40$

14. Pulse 1.45$

l: -15. Pulse 1.50$

16. Pulse 1.50$

l

17. Pulse 1.50$

18. Pulse 1.50$

19. Pulse 1.50$

l

20. Pulse 1.55$

21. Pulse 1.60$

22. Pulse 1.655

23. Pulse 1.655

24. Pulse 1.65$

25. Pulse 1.655 l

26. Pulse 1.65$

27. Pulse 1.70$

28. Pulse 1.75$

29. Pulse 1,80$

30. Pulse 1.80$

31, Pulse 1.80$

32. Pulse 1.80$

33. Pulse 1.80$

34. Pulse 1.85$

35. Pulse 1.90$

36 Pulse 1.95$

37. Pulse 2,00$

38. Pulse 2.00$

39. Pulse 2.00$

40. Pulse 2.00$

41. Pulse 2.00$ '

42. Pulse 2.05$

43. Pulse 2.10$

44. Pulse 2.15$

35. Pulse 2.15$

46. Pulse 2.15$

- 47. Pulse 2.15$

- 48. Pulse 2.15$

49. Pulse 2.20$

50. INise 2.20$

51. Pulse 2.205

52. Pulse 2.255

- 53. Pulse 2.30$

54. Pulse 2.35$

55. Pulse 2.35$

56. Pulse 2.35$

57. Pulse 2.35$

58. Pulse 2.40$

59. Pulse 2.45$

60. Pulse 2.50$

Move core to position 250

61. Pulse 2.005

62. Pulse 2.00$

Move core to position 750

63. Pulse 2.00$

64.- Pulse 2.00$

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i t-i Move core to position 500-

65. Pulse 2.50$

66. Pulse 2.50$

67. Pulse 2.50$  !

68. INise 2.50$

69. Puhe 2.50$ ,

4- 70. Pulse 2.50$

71. Pulse 2.50$

72. IN!se 2.50$

73. Pulse 2.50$

74. Stop operations for at least one hour

75. Run reactor at 900 kW for two hours, closely monitor CAM and water monitor box for any -

unexpected increase in readings.

Steady State Full Power Testing Steadily increase state power level to t.09 MW (SCR.AM post). Record control rod positions,

, fuel temperatures, CAM and SGM readings, and R1 readings at 100 kW, 500 kW,1.0 MW, 1.05 MW, and 1.07 MW.

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