ML20151Y084

Submits Preliminary Status Rept 1 of Possible Failed Fuel Event at Mcclellan Nuclear Radiation Ctr on 980819

ML20151Y084
Person / Time
Site:	University of California-Davis
Issue date:	08/20/1998
From:	Richards W AIR FORCE, DEPT. OF
To:	NRC
Shared Package
ML20151Y014	List: ML20151Y010 ML20151Y084 ML20151Y093 ML20151Y100
References
NUDOCS 9809180094
Download: ML20151Y084 (11)

Text

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DEPARTMENT OF THE AIR FORCE HEA00UACTEQS SACRACENfQ AlO LOCIS?lC$ CENTEC(AFCC)

McC:.ELLAN AIR FCACE 8ASE. CAUFCANIA 20 Aug 98 MEMORANDUM FOR NRC OPERATIONS CENTER FROM: SM-ALC/Ti-1 5335 Price Ave.

McClellan AFB CA 95652-2504

SUBJECT:

Preliminary Status Report #1 of Possible Failed Fuel Event at the MNRC 1.

Reactor conditions pnor to the anomaly and what occurred during the anomaly:

On 19 Aug 98, during run # 3071, the reactor was operating at 2 Mw. All of the radiation monitoring readings appeared normal. At 1829 hrs a watchdog scram occurred. The reactor was rebooted successfully and all watchdog scram tests were satisfactenly performed prior to the start up of the reactor. ,

Tha duty SRO granted permission to start the reactor, run number 3072. The reacter was l taken critical at 1841 hrs, all radiation monitoring equipment readings were normal. Core excess was $3.93. The r erator continued to raise power and at approximately 1849 hrs, the reactor was at 80% r ;wer. At this time the reactor room CAM Alerted, and Alarmed.

The readings taken at this time were:

At time of incident CAM Set Points Alert Alarm Particulate 2.0E5 cpm Particulate 2.8E3 cpm 5.1E3 cpm Noble Gas 1.0E4 cpm Noble Gas 4.9E4 cpm 9.8E4 cpm lodine 1.5E3 cpm lodine 3.1E3 cpm 6.3E3 cpm l

Health Physics staff was immediately notified and began the investigation. The reactor I room ventilation system went into recirculation mode and the Stack cam readings did not change at the time of the incident. Operations Supervisor, Health Physics supervisor, and The facility director were a!! notified as soon as possible.

2. Actions to correct the anomaly:

The reactor room ventilation went into recirculation mode. The stack cam readings did  :

not change at the time of the incident. The dehumidifier system tumed on and has  !

continued to operate as designed.

Health Physics personnel obtained a reactor room portable air sample (PAS), primary water sample, and pulled the reactor room CAM particulate filter. Gamma spectroscopy analysis revealed the presence of fission product daughters on all three samples. The stack CAM particulate filter was analyzed and no fission product daughters were observed. A PAS in the equipment room outside the reactor room revealed no abnormal radionuclides. Contamination surveys revealed no contamination outside of the reactor room or the recire vent system. Radiation surveys were performed outside the reactor room and on the recire vent system. The dose rate was 0.25 mR/hr on contact with the reactor room door and the highest contact dose rate on the recirc vent system was 0.8 mR/hr. The condensate from the dehumidifier (part of the recirc vent system) was analyzed and fission product daughters were observed.

9809180094 980915 PDR ADOCK 05000607 S PDR

Entry into' the reactor room has been restricted and the reactor room has been posted as L

a high airborne radioactivity area. Periodic reactor room air samples, primary water samples and dehumidifier condensate water samples are being obtained and analyzed.

The stack CAM filters and the reactor room CAM filters are being periodically analyzed.

Contamination and radiation surveys are being performed on the recire vent ducts.

Stack CAM readings and filter analysis indicate that no release of fission products to the environment.

3.

Corrective actions needed to prevent this anomaly from reoccurring in the future:

TBD W

o ,

\

• Fn m.

WADE J. RIC (R S, Ph.D.

Director McClellan Nuclear Radiation Center cc: Dr. Warren Eres:an, NRC NSC Members I

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McCLELLAN NUCLEAR SAFETY COMMITTEE (NSC) As of 20 Aug 98 Name Office

• ColGerald Adair(Chairman) TI l

• Wade J. Richards TI-1 Jeffrey Ching TIMH Charles Heidel TIMR ,

• John O'Brien (Primary)' SEG Gary Percival(Altemate) SEG

• Robert Woodson (Primary) SGPB Patrick Pierce (Altemate) SGPB Warren Eresian NRC Lt Col Catherine Zeringue AFSC/SEWE Capt Edward Jakes )

AFSC/SEWE Kenneth Tallman AFMC/SES Maj James Hicks AFMOA/SGOR Indeoendent Members l

• Donald Feltz

• Lt Col Kenneth Hodgdon

• ArthurJohnson

• Dr. Robert Nelson

• William Stephens ~~

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• Voting Member 1

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' l ATTACHMENT 4 l

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mes -

} 6

APPENDIX A RADIATION WORK PERMIT r

RWP NUMBER N- IO I -

4 PARTI Requested byt 7. LJ i*

Name Crgantzacon

% -107. 3 Phone

_cate- MWMb _

1

Location of work to be periormed

8EAf.fcA W W '

Desenation of work to be performed:

MDICt48dC 6 ME D 'MT PART11 EXPECfED RADIOLOGICAL CONDITIONS:

Highest contact readings , -

H'; nest readirgs in the general area

@b 'Ib D Contarrunacon:

AirWrne concentracon

\

P'**%

• HEALTH PHYSICS REQUIREMENTS Protective Clothing and Joe Cc.ers; Equipment Hartr Intermcent O Rubber gloves G M SGdy.;

Continous Tyvek Shoe Covers O  !

8 1 pair cas Lab Coat O Rubber Boots e Tyvek Sut 9 ACMfWl6 O O O O Ccstmetry; Head; TLD 4 Res werv_* _Mqq; Safety glasses O SCSA Cirect Reading 9 Tyvek Hood O O O Resotrator O O O Faco ShieM Hh O 9h9K e e

SPECIAL REQUIREMENTS

__t. f_edt 4. RW As, cSMA M MED AfWR- *t4 D _ _

.'4LtS h *t ~ 6'IAUlV#tC&W E LM -

s.rds.75h4tm7UI-wrc n.t Awn HT t _'Ti! iL%TT  % 90 ~6E PJL '

I~mi. rwa-wu wo.

' MWWfi41e %fV/U'f':? El ~~

g rf u Dwysw.sh k n.s NnrM m%i uusun N. uTM , ~

cs9 I

RWP APPROVAL: RWP INITIATED:&p_/ # /f/

9 144M (f / MP3ECH 0 ATE d

_ b EXPIRATION DATE: MM HE$TH PHYSICIS DATE ' '

HP

(/

_ [d ,

RWP CLOSE OUT Mk 11 Aud$

~H .e. TEC OATE (RWP. DOC REV. 06) 18 2

..O84dJsd *-+4ehAI4+.+-.J.aa-4aa. hMA4h*4 &+a-brJA.sa- aw,4-mwas AA,f.auAm..,esa aso p a -.m e s am usa s A42u ..-ws,ja,m. ..

J2-Ae-saA.+Aad-.ha. AAA A~e s sa Asi-J.-m=4-wA-JW--ah*+6A at.--4..2 maw-a.4.4- m,.

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ATTACHMENT 5 l

1 b

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l RADIOLOGICAL DATA l

The 98:

following is a summary of the radiologicalinformation at the time.of the problem on 19 Aug Radiation Con *1mination Airbome Radioactivity .

l 0.25 mR/hr None detected outside Reactor Room CAM:

l

' Outside reactor room door reactor room Particulate 5.8E-07 uCi/ml lodine 1.6E 08 uCi/mi j 11 mR/hr on reactor room RAM Noble gas 2.7E-04 uCi/mi 0.85 mR/hr on recire vent =

system Stack CAM: Normal readir.gs I (recirc system operating) '

560 mR/hr on demin system

' Analysis of the reactor room CAM (continuous air monitor) particulate filter revealed the presence l of Rb-88, Rb-89, and Cs-138 which are particulate daughter products of fission gases. A portable grab air sample from the reactor room revealed the presence of Rb-88 and Cs-138. A portable grab air sample taken in the equipment room just outside of the reactor room revealed no fission product daughters. Analysis of the stack CAM particulate filter showed no fission product l daughters l i

Analysis results of primary water samples are shown on Table 1.

i Analysis or'the recirculation ventilation system dehumifier condensate water revealed the  !

presence of fission products.

An entry was made into the reactor room on 20 Aug 98 to perform radiological surveys. The results are as follows:

Radiation Contamination Airbome Radioactivity 0.9 mR/hrinside the None detected inside the Particulate: 1.99E-08 uCi/mi reactor room reactor room (Rb-88) lodine: None detected Noble gas: 2.88E-05 uCi/ml (Xe-133, Xe-133m, and Xe-135)

Based on the derived air concentrations (DACs) for Xe-133, Xe-133m, and Xe-135, the individual making the entry into the reactor room received 1.4 mrem during the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> spent inside the_

reactor room.

On 21 Aug 98, the reactor room was vented out the stack to clear the reactor room of xenon. A total of approximately 153 mci of Xe-133 was released up the stack on 21 Aug 98 and 24-25 Aug 98, Figures 1 and 2 are graphs of the two Xe-133 releases. The highest concentration of Xe-133 in the unrestricted area was estimated to be 8.4E-09 uCi/ml (the 10 CFR 20 effluent limit for Xe-133 is 5E-07 uCi/ml).

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. On 24 Aug 98, the reactor room was released for unrestricted entry after contamination surveys revealed no loose surface contamination.

Tatdo 1 Primary Water on Detector 25 AN watues In uCi/ml Date Sf19f98 ar18t98 SI2W98 St28t98 S/28/98 S/28t90 S/28t90 S/21/98 S/21198 Sf21!90 S/24/98 Sf24/98 St2548 S/2698 S/27/98 St28t98 S/31/98 Time 19:54 23:58 4:08 S:28 9:58 14:08 23:00 5:58 13:25 21:95 S:31 12:12 S:17 9:41 8:45 11:32 4:10 HS-283 6 22E46 528EG 1.11E44 6 53E45 7 91E@

Co-141 4.42E47 Te-12304 1.16E46 3 39Em 1.43r!45 1.72E45 160E45 1.78E45 8 61E46 Se-139 3 96E45 5.25E45 4 56E45 2 83E45 Cs-134 3 83E47 121E&

Cs-138 1.71E47 4 20E47 Cs-137 8.34E48 7 97Em 7.2SE M 613E46 7 57E@ 8 00E46 5 55EM 4 06E@ 3 62E-06 2.78EG 3 80E& 163E46 3 41E46 3 67E@ 3 27E& 9 80EM Cs-138 4.31E45 M35 1.35E45 Xe-13508 515E46 4.81E45 186E45 131E45 117E45 8 65E@

Xe-135 3 73E44 1.16E43 3 87E43 414E43 3 85E43 4.90E43 2 94E43 2 27E43 9 34E44 616E44 2.17E45 91E46 171E46 I-133 4.41E45 4.1dE45 3 59E45 2.77E45 2 98E45 167E45 119E45 6 94E46 4 61F@ 2.67E46

(( 82E46 Xe-13308 2 62E45 149E44 411E44 4 95E44 5 22E44 8 22E44 7.59E44 S.42E44 56E44 4 86E44 3 30E44 2.45E44 168E44 104E44 7 39E45 172E45 1 57E &

Xe-133 8 79E44 6 84E43 189E42 2.29E42 2 56E42 4 22E42 3 94E42 4.87E42 3 21E42 2 86E42 2 69E42 2 30E42 163E42 127E42 108E42 5 61E43 4.36E43 1-132 1.3SE44 5 41E45 316E45 170E45 165E45 1.27E45 9 38E46 8 20E46 632E @ 4 51E46 189E46 1.16E@ 1.15E M 4 92E47 922E47 4 45E47 l-131 5 66E45 S.22E45 568E45 509E45 5 2SE45 4 00E45 3 45E45 2 57E45 217E45 5 94E45 4 90E45 2.1145 2 94E45 2 45E45 124E45 195E45 Xe-13104 181E44 176E44 2.54E44 2 31E44 197E44 158E44 1.34E44 8 2tE45 6 81E45 Kr48 155E44 2.95E44 2 86E44 191E44 9 46E45 6 38E-05 Ab48 2 39E44 6 80E44 1.16E43 8.87E44 4 70E44 148E44 Kr47 7.21E45 3 95E45 169E45 212E@

Kr4504 4.82E-05 2 04E45 Kr45 7 27E45 2.23E44 330E44 2 74E44 180E44 156E44 Se45 3 2EEE 3.57E48 2 06EM 205E46 174Ee 159E46 132E46 9 70E47 9 47E47 6 84E47 4 48E47 Total Act 4 24E43 1.13E42 2 58E42 2 96E42 311E42 4 91E42 4 34E42 5.SSE42 3 38E42 301E42 2.76E42 2.37E42 167E42 130E42 111E42 6 75E43 4 48E43 i

Bold values indicate highest recorded concentration.

. ________.__i_..-._____------------------- - - -

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M NUTES 21 AUG 98

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%- A- %-  % g% g N g Q g% g% g% g g% g% q 3Nq Q o- A k- s  %-  %-  %- A-  %-

HOURS 24-25 AUG 98

~

.. . - - - - - - - - - - , - - . - - --------.--,--.---r-------

ATTACHMENT 6

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I SOP 98-13 -

VENTILATION OF REACTOR ROOM AIR OUT THE STACK l

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. PREPARED BY: 'IY I DATE: l'N' N WalterGuisteiligiss ' ~"

REVIEWED BY: tx ~Y , _ k ~

DATE: %-u-%

OPER OS PE R

> . DATE: E-L \ -'0 $

HEALTH PHtSIC$ SUPER 190R APPROVED BY: k '

DATE 8 ~dI-9 6 FACILITY Dl8ECTOR q_Q p.M$[ E -

I. PURPOSE r

j

The purpose of this document is to provide instruction on changing the Automatic recir to a manually overridden one to complete the ventilation of the Reactor Room.

i.

IL PRECAUTIONS A.

The following precautions shall be observed during all phases of the operation.

1.

All equipment and tools that come in contact with exposed sections of potentially contaminated systems shall be sun / eyed for contamination.

2. All operations conceming the reactor ventilation system shallbe under the direct supervision of a Senior Reactor Operator.

3.

All work shall cease if there is a question about the procedure or operation by any member of the Operation and/or Health Physics staff. Work will only

continue when the question is answered to their satisfaction or management resolves the matter.

Ill. RADIOLOGICAL CONTROLS A. Exposure Control:

1.

A pre-work briefing shall be performed subsequent to commencing this SOP.

l

2. Whole body TLD and pocket dosimeter shall be recuired. i 3.

The Health Physics Supervisor shall specify dosimetry location and any additional dosimetry required.

)

8. Contamination Control:

1. Lab coats, and rubber gloves shall be required for all personnelin the immediate work area.

l IV. CHANGING THE VENTILATION LINE UP

1. } A. Change the Rx Room Cam sample point to the stack.

ty /UI B. Disconnect the Rx Room Ventilation Damper motor linkages from the Rx Room Recirc and Exhaust dampers. Then Manually shift the dampers to exhaust Rx Room Air to the Stack. (See Fig.1 attached).

M C. Ventilate in this configuration for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

b + 5 J asse .. Uu/u w - s S e""o m me*,

D. Perform an air samph +'ie Reactor room. If air samples are within limits, return ventilation to normal. If not normal continue to ventilate the Reactor room until air samples are within the limits.

1600 CFM I I REACTOR ROOM 4 400 CFu _ _

AC-1 5 "" e' CLOSED n

OPEN '

d~ '#

800 CFM '" CLOSED l

PRE-FILTER PRE-FILTER ,

l ABSOLUTE ABSOLUTE FILTER FILTER CHARCOAL FILTER #1 -

,5 CLOSED CHARCOAL FILTER #2 RECIRCULATION DAMPER CLOSED

{ 1[

, OPEN,. -

'0 j gs TO STACK = O' c I EF 1 ,C OPEN

~

. DAMPER TO STACK REACTOR VENTILATION FIGURE 1 l

FIG 1: Xe-133 RELEASE CONC uCi/mi 5.00E_06 m_ .

dx: mag _e-4 .. , .

.."5-+-s

gfi:-

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^^ 4 mci RELEASED di, '

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- @ ag?! "? " H.. (5019 cfm RELEASE RATE) 2Rs 7 '" ac J na:

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ATTACHMENT 7 .

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SOP 98-12 '

INSPECTION OF THE FUEL FOLLOWED CONTROL RODS AND SELECTED FUEL ELEMENTS l

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PREPARED BY: DATE: l'E'~ll Walter uy4thfgass ,

REVIEWED BY: k% ~Y< + b t ~

DATE: S' W%

OPE P" ISDR loge M$h HEALTH OHYSICS SU E VISOR DATE: b ~L\ 'Y i

APPROVED BY: ack [$A DATE E-2l-9 8 FACILITY DIRECTOR mij 'z' f ll 3 L';; ~

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e . I. PURPOSE L

The purpose of this od' cument is to provide instruction on the sequence and method to be initially used to locate a failed fuel followed control rod or fuel eiertent.

ll. PRECAUTIONS '

A.

The following precautions shall be observed during all phases of the operation.

1.

All equipment and tools removed from the reactor tank sha// be surveyed for contamination, i

2. All operations in the reactor tank shall be under the direct supervision of a l Sen,or i Reactor Operator.

3.

All work shall cease if there is a question about the procedure or operation by any member of the Operation and/or Health Physics staff. Work will only continue when the question is answered to their satisfaction or management resolves the matter.

Ill. RADIOLOGICAL CONTROLS A. Exposure Control:

1

1. r l

A pre-work briefing shall be performed subsequent to commencing this SOP.

L 2.

Whole body TLD and pocket dosimeter shall be required.

3. The Health Physics Supervisor shall specify dosimetry location and any e

additional dosimetry required.

L B. Contamination Control:

! 11. Lab coats, and rubber gloves shall be required for all personnel in the immediate l work area.

2. All the parts that are removed from the reactor tank shall be placed in a sleeve or plastic bag unless otherwise specified by a HP.

L IV. ' PROCEDURE FOR CONTROL ROD INSPECTION c, w %

y4 v A. This procedure is based on preventive maintenance items for visually inspecting a j -

control rod and normal fuel inspection.

l

1. Ensure that a Fuel Transfer Form has been completed and signed by the Facility Director.

s 2 Place the reactor room ventilation in the recircula ep g pyn IC@ M ' '

b6 .

. . . m.m.._.-~. m. _ _ ... _ _ _ . _ _ _ . . _ _ _ _ _ _ _ . _ . _ . _ - . . - _ _ _ . . .

3.

Remove the bottom 7/16-in, bolt located on the connecting rod below the dash pot.

4; t.- Separate the lower portion of the connecting rod from the upper portion, 5.

Raise the lower connecting rod upward (approximately 18 inches) until the next bolted connection is reached.

6.

Remove the two bottom 7/16-in. bolts and remove the upper portion of the connecting rod.

7.

Lower the bottom connecting rod through the lower bridge structure until the

] lower connecting rod can be moved to the east side of the bridge structure.

8.

Raise the connecting rod upward until the control rod has cleared the upper grid 7 plate.

9.

With the control rod resting either on the upper grid plate or the reflector, carefully lean the control rod over to allow any air / gas trapped below the bottom end fitting to escape.

10.

Slowly raise the control rod as high as radiation levels will permit to visually inspect the control rod for any sign of gas bubbles escaping from a weld or the cladding.

NOTELANY GAS ESCAPING FROM EELOW THE CONTROL ROD WILL

- INTERFERE WITH STEP 9 ABOVE AND MAY RESULT IN AN INCORREC ANALYS!S OF THE SITUATION.

11.

After determining that the control rod is not venting gas through a cladding

, failure, return the control rod to the grid location noted on the fuel transfer form.

12.

Raise the connecting rod through the corresponding hole in the lower bridge structure for that grid location.

13. Install the upper portion of the connecting rod and install the two bottom.7/16-in. ,

bolts.

14. ~ ~

Lower the connecting rod until it can be connected to the rod drive and install the 7/16-in. bolt.

15. -

Perform steps 2 through 13 for SHIM 1, SHIM 2, SHIM 3, and SHIM 4 necessary to verify that the fuel followed control rods have not failed by visual indication

, only.

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7 3 TESTING TR'OL\ROfrFOgEkLTN f o Qor allhontrofrods.y V m

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18.

If none of the control rods show visual clues of failure, commence fuelinspect of individual fuel elements using the list and Fuel Transfer Form provided by others. (See Attached Sheets).

19. If no con rod sted fu ement givegin i ion of f i e, the STA EEL rol rod shall Was led an * , .alled i - ce of (or et rod as direct F the ap O- -

r ove th G rod, the stall STAINL le ste ove t ain l q.u-%c STEE ontrol r in its place. l 1

20.

The reactor will have to be operated at power as necessary to assist in locating the failure. This procedure will be provided at a later date.

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PICTURE OF ELEMENT 10730 TO BE PROVIDED WHEN AVAILABLE 4

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ORTH REMOVABLE CENTER GRID PLATE INSERT J1 11 0 l J9 O 19 O

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F.8 o H8 e E7 G7 17 6 B5 F7 H7 L5 cs Ee 08 ie xs us

@:B4 F6 He L4 gSOvece F5 o H5 O 3 E2 mn MLL MD CONTROL RODS MCCLELLAN NUCLEAR RADIATION CENTER 1 _. .

's ELEMENT MOYEDATE LOCATION ' REASON NOTE 10730** 10/30/95 TEMP 12 RECEIVED FROM GA 2/6/97 Rack 1-16 Periodic Inspection and move to in tank storage Rack 3/7/97 Core K-1 For Load and Test Procedure 6/16/97 Core E-9 Rearrange core to increase core excess

.10/10/97 Core E-9 PeriodicInspection Core E-9 Elesient** is 20 wt. % Element ElementM are 30% wt. U / 20% wt. U-235

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - " ' ^ ' - - " ' ~ ~ ~ ^ ^ ~

97 core 1 I I i i l ELEMENT POWER (KW) ELEMENT I POWER (KW) ELEMENT POWER (KW) 5263 8.06 10176 9.87 10689 9.81 5265 8.35 10177 8.14 10690 9.02 i

5267 7.59 10178 I 9.9 10691 l 9.53 5268 11.3 10179 l 10.97 10692 10.18

{

5269 7.41 10180 i 10.83 10693 l 10.2 5271 l 8.07 10181 11.76 10729 9.18 5272 l 8.43 10182 8.53 10730 8.87 5273 l 8.75 10183 l 11.28 10731 l 9.19 5274 l 10.03 10184 l 11.21 ~ 10732 I 7.95 5276 I 9.98 10185 8.21 10733 l 7.53 5277 10.09 10186 8.04 10734 8.37 5278 10.15 10187 7.93 10735 8.25 5279 9.82 10188  ! 8.51 10736 8.62 5280 8.2 10279 l 6.95 10737 7.92 5292 10.17 10280 l 7.94 10738 8.47 l 5293 10.18 10281 7.33 10739 8.99 5295 5.2 10282 8.03 10740  ! 8.23 5296 8.57 10653 12.02 10741 8.06 5298 7.19 10664 10.13 10742 9.08 5301 7.25 10665  ! 9.69 10743 8.86 5302 8 10666 l 9.99 10744 8.46 5303  ! 8.4 10667 i 10.11 10745 i 7.73 5304 i 8.2 10668 i 10.62 10746 8.05 l t 5307 l 12.18 10669 i 9.74 10747  ! 8.17

~

5308 l 8.39 10670 l 10.17 1074) 1 8.33 5310 l 5.41 10671 i 10.01 i  !

5311 I 8.54 10672  ! 9.41 CORE  ! 1002.4 i 5312 I 8 10673 l 9.62 j l 5313 5.53 10674 i 10.03 PEAK ELEMENT POWER : 12.49 kW 5314 9.94 10675 9.86 ELEMENT iNUMBER 5319 5315 5.17 10676 10.34 t 1 5316 l 5.24 10677 l 10.63 i i~

5317 l 9.98 10678 l 10.4 l i 5318 5.41 10679 i 10.24 i  !

5319 12.49 10680 l 10.34 l 5320 12.33 10681 1 9.94 l 5321 10.05 10682 l 9.86 l l 5329 11.22 10683 l 10.13 l i

! 5338 12.17 10684 I 9.77 i  !

l 5343 4.92 10685  ! 9.36 l l

~

5344 5.07 10686 j 9.83 j i 9160 8.67 10687 l 9.02 l i 10175 I 8.18 10688 i 10.38 i l l I i  ! i i i I  !

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5263 10.07 I 10176 18.37 10689 20.89 5265  ;

10.9 10177 10.97 10690 20 '

5267 12.48 10178 18.21 10691 18.19 5268 -l 19.71 10179 18.68 10692 t 19.38 5269 10.82 10180 l 11.6 ~ 10693 l 20.49 5271 11.14 10181 l 12.07 10729 i 23.9 5272 10.71 10182 i 18.38 10730 I 24.6 5273 1 10.1 10183 i 23.4 10731 l 23.54 l 5274 11.62 10184 22.85 10732 23.6 i

5276 10.21 10185 15.08 10733 l 22.86 5277 11.51 10166 15.18 10734 1 22.63 l 5278 19.39 10187 l 14.64 10735 22.98 i

5279 10.57 10188 15.72 10736 l 23.09

' l 5280 1 10.32 10279 11.38 10737 l 21.07 l 5292 11.93 10280 1 10.77 10738 l 21.72 5293 11.52 10281  ! 11.56 10739 l 22.77 5295 24.33 10282 } 9.59 10740 l 22.39 5296 l 11.1 10653  ! 24.67 10741 l 22.73 5298  ! 11.43 10664 l 20.37 ~ 10742 j 23.75 5301 12.15 10665 18 10743 I 23.98 5302 10.41 10666 20.02 10744 } 23.85 5303 11.38 10667 l 19.89 10745 l 23.27 5304 11.34 10668 l 19.87 10746 i 25.04 l 5307 .

25.24 10669 l 18.93 10747 l 24.65 l 5308 l 11.68 10670 1 20.16 10748 i 23.71

. 5310 i 25.59 10671 l 18.93 i I 5311 i 11.59 10672 l 19.06 CORE  ! 2003.4 l 5312 i 11.42 10673 i 18.95 i i 5313 1 23.28 10674 j 18.49 PEAK ELEMENT POWER : 26.21 kW 5314 l 18.78 10675 i 19.89 ELEMENT i NUMBER 5316 5315 i 23.82 10673 j 19.27 l l l

5316 l 26.21 10677 l 19.39 1  !

5317 l 11.78 10678 1 18.95 l l 5318 l 23.87 10679  ! 20.28 l l 5319 l 26.03 10680 19.45 i i 5320 25.26 10681 21.19 I l 5321 19.19 10682 l 18.83 l l 5329 18.88 10683 I. 18.91 i i 5338 [ 19.33 10684 l 19.23 I 5343 i 19.62 10685 i 18.18 1 5344  ! 19.35 10686 l 19 34 i i

9160 15.41 10687 l 17.51 1  !

10175 11.12 10688 l 19.51 i l

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! I 5261 23.86 5337 l 23.62 10689 i 20.87 5263 l 9.97 5339  ! 26.08 10690  ! 20.12 5264 l 19.8 5343 l 19.26 10691  ! 18.29 5265 l 10.78 5344  ! 19.52 10692  ! 19.49 5266 l 23.5 9160 l 15.21 10693 1 20.53 5267 l 12.29 10175 l 11.05 10729  ! 23.96 5269 10.74 10177 l 10.89 10730 l 24.48 5271 11.02 10180 l 11.45 10731 l 23.66 5272 10.62 10181 l 11.9 10732 l 23.53 5273 9.98 10185 l 14.79 10733 l 22.92 5274 11.5 10186 i 14.82 10734 i 22.69 5276 10.15 10187 l 14.45 10735 t 23.11 5277 l 11.39 10188 l 15.48 10736  ! 23.26 5279 l 10.44 10279 11.21 10737 i 21.08 5280 j 10.24 10280 10.71 10738  : 21.67 5292 i 11.76 10281 l 11.48 10739 I 22.73 5293 l 11.42 10282 l 9.55 10740 1 22.47 5295 19.38 10653 24.01 10741 l 22.82 5296 11.01 10664 20.32 10742 1 23.85 5298 11.28 10665 18.08 10743 i 23.89 5299 19.43 10666 19.97 10744 i 23.73 5301 l 11.98 10667 19.9 10745 1 23.28 5302 10.3 10668 l 19.83 10746  ; 24.87 5303 11.23 10669 i 18.89 10747 24.57 5304 11.18 10670 -i 20.15 10748 i 23.63 5305 i 19.37 10671 1 19.01  : >

5306 l 25.73 10672 l 19.08 CORE I 2002.7 i 5308 l 11.54 10673 l 19.04  !

5311 l 11.51 10674 l 18.52 PEAK ELEMENT POWER : 26.08 kW 5312 l 11.27 10675 l 19.86 ELEMENT iNUMBER 5339 5313 l 18.79 10676 l 19.25 I  !

5315 l 19.06 10677 1 19.37 I 5316 l 19.52 10678 l 18.92 t 1 5317 l 11.66 10679 l 20.24  !  :

5318 l 18.96 10680 i 19.49 i 5319 j 18.97 10681  ! 21.33 1 5320 18.69 10682 l 18.91 I i 5322 24.07 10683 l 18.96 i  !

5324 l 25 49 10684 19.34 I i 5328 j 25.83 10685 18.14  ! i l 5331 l 25.37 10686 19.35 l l 5333 l 24.07 10687 i 17.59 I i 5335 l 23.52 10688 l 19.57 i ,

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ELEMENT POWER (KW) ELEMENT POWER (KW) ELEMENT I POWER (KW)

I 5261 22.46 10186 14 10736 l 23.09 5263 8.84 10187 13.92 10737 20.4 5264 18.81 10188 14.95 10738 20.4 l 5266 22.11 10279 10.36 10739 21.98 1 l 5267 11.76 10281 l 11.13 10740 l 22.11 5269 10.31 10653 1 22.13 10741 l 22.79 5271 1 10.64 10664 l 19.71 10742 23.76 5272 10.15 10665 1 17.73 10743  ! 22.74 i 5273 9.5 10663 j 18.67 10744  ! 22.94 5279 9.94 10667 l 18.53 10745 l 23.3 1 5292 11.38 10668 l 19.09 10746  ; 23.81 5293 11.11 10669 l 18.11 10747 l 24.38 5295 18.53 10670 l 19.48 10748 l 23.29 l

5298 10.81 10671 l 18.32 10824 i 15.76  ;

5299 18.65 10672 l 18.61 10825 l 15.55  !

5301 11.51 10673 l 18.37 10827 1 17.23 I 5303 10,71 10674 i 16.87 10830 i 16.02 l 5304 10.57 10675- l 19.04 10831  ! 17.36 5305 18.13 10676 l 17.92 10832 l 16.24 l 5306 24.1 10677  ! 18.83 10838 l 18.3 5312 10.73 10678 l 18.14 10839 l 16.94 5313 17.92 10679 l 19.47 10840 l 18.5 5315 18.26 10680 l 19.87 10841 1 19.06 5316 18.26 10681 l 20.37 10842 i 17.95 5317 11.93 10682 i 18.22 10843 i 18.15 5318 l 18.2 10683 l 17.43 i  !

5319 18.19 10684 j 19.66 CORE  ! 2002.2 <

5320 17.73 10685 i 17.39 j i

! 5322 22.2 10686  ! 17.34 PEAK ELEMENT POWER : 24.38 kW

._5324 23.88 10687 I 16.56 ELEMENT iNUMBER :10747 5328 24.08 10688  ! 19.95 l l 5331 23.65 10689 l 19.89 I l 5333 22.41 10690 1 20.4 l j 5335 21.9 10691 j 17.26 1 1 5337 22.29 10692 i 19.03 1 5339 24.04 10693 l 19.29 .

5343 17.91 10729 l 23.84  !  !

5344 l 18.15 10730 l 23.43 l

~

j 9160 I 14.38 10731 i 23.36 j I 10175 l 11.25 10732 i 22.4 I '

10177 l 10.42 10733 i 22.96  ! i l 10180 l 11.06 10734 1 22.67 i 10185 l 13.71 10735 1 22.87  !

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I i l 5261 20.96 10668 1 18.47 10746 23.99 5264 17.94 10669 17.16 10747 23.72 5266 20.86 10670 18.48 10748 22.95 5267 11.05 10671 1 17.47 10822 i 15.01 5271 10.15 10672 l 17.79 10823 i 17.78 l 5272 9.58 10673 i 17.58 10824 i 15.31

! 5279 9.71 10674 16.19 10825 i 15.16 5293 10.55 10675 '

18.34 10826 l 18.38 5295 17.48 10676  ! 18.05 10827 l 16.41 5299 17.57 10677 l 19 10828 l 18.23 5301 11.09 10678 l 17.79 10829 l 17.38 5304 10.1 10679 l 19.26 10830 i 15.34 5305 17.44 10680 l 18.94 10831  ! 16.08 i

! 5306 22.43 10681 1 20.1 10832 15.93 5313 17.11 10682 l 17.41 10833 1 17.92 5315 17.32 10683 17.44 10834 i 15.78 5316 17.69 10684 18.58 10835 1 17.52 5317 11.31 10685 l 17.36 10836 i 18.55 5318 16.98 10686  ! 16.79 10837 i 17.02 5319 16.97 10687 l 16 10638 1 17.15 5320 16.97 10688 l 19.02 10839 l 16.28 5322 21.2 10689 l 20.21 10840 1 17.73 5324 22.37 10690 l 19.5 10841 f 18.69 5328 22.62 10691 i 16.8 10842 1 17.24 5331 22.32 10692  ! 17.83 10843  ! 17.39 5333 21.27 10693 I 19.11  :  ;

5335 20.77 10729  ! 22.63 CORE i 2002.1  !

5337 20.78 10730 l 23.28 i I

5339 22.85 10731 l 22.95 PEAK ELEMENT POWER : 23.99 kW 5343 17.31 10732 l 22.41 ELEMENT ! NUMBER :10746 5344 17.63 10733 l 22.06 I  !

9160 13.77 10734 l 21.51 l l 10175 i 10.02 10735 l 22.42 l t 10180  ! 11.2 10736 1 22.54 i i 10185 13.32 10737 i 19.47 l l 10186 13.47 10738 l 20.53 1 10187 12.97 10739 l 21.7 l 10188 l 13.95 10740 l 21.72 l l 10653 I 20.98 10741 21.61 i i 10664 19.47 10742 23.09 I l l 10665 16.98 10743 j 22.94 i  ;

. 10666 17.57 10744 l 23.04 l l 10667 1 18.15 10745  ! 22.37 i  !

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97 core 1 Configuration .l l l L

i I l FE # . Position FE # j Position i FE# l Position l 5263 J8 10177 C4 l 10691 F2 5265 13 10178 D5 l 10692 E2 5267 G10 10179 G4 10693 D2 5268 17 10180 E5 10729 11 5269 .C7 10181- F5 10730 K1

-5271 H3 10182 C5 l 10731 C9 5272 D8- 10183 G8 1 10732 E1

, 5273 E9 10184 1 E7- l 10733 F1

! 5274 J6 10185 i G9 l 10734 A2 I- 5276 14 l 10186 { J7 i 10735 i A3 -

5277 18 t 10187 l J4 i 10736 C1 5278. H9 10188 i G3 1 10737 L1 5279 F4 10279 G2 l 10738 D1 5280 H10 10280 F3 j 10739 E11 5292 F9 10281 i C3 l 10740 A4

l. -5293 E8 10282 l C6 1 10741 M2 i' 5295 M5 10653 F8 10742 D10 l 5296 19 10664 J9 10743 l K9 5298- K3 10665 L7 l 10744 J10 5301 K7 10666 i K8 1 10745 H12 5302 K4 1  ! 10667 l L4 1 10746 11 1 l 5303 i K5 l l 10668 i E10 1 10747 M3 5304 ,

K6 I I 10669 i H11 I i 10748 M4 5307 H5 j l 10670 L5 I CPLUG G6

.5308 F10 l l 10671 B4 i CRING F6 5310 F12 .I 10672 I K2  !  ! CRING F7 '

5311 E3 1 10673 l B2 l CRING G5 5312 J3 10674 i B6 i CRING G7 5313 B8 10675 L6 , CRING H6 5314 H4 10676 C8 i CRING H7 5315 AS I 10677 i D9 i PTS J1 5316 A1 i 10678 i F11 SOURCE L8 5317 D6 10679 i 11 0 l I TR D4 5318- B1 10680 l J2 i 5319 16 10681 l C2 i 5320 E6 10682 i B3 l 5321 JS. 10683 i B5 i 5329- 15 10684 l B7 l 5338 H8 10G85 i G11 1 5343 M1 10686 i L3 l l 5344 H1 10687 ! L2 i

! 9160 D7 10688 1 12 i

, 10175 D3 10689 ! H2  ! l l 10176 E4 10690 ; G1 i i e i i

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97 core 2 Configuration l l l 1 l l I l l FE # i Position i i FE # l Position i FE # l Position 5263 ; A5 l l 10177 l B1 l 10691 F2 5265 l M2 l l 10178 i D5 1 10692 E2 5267 l J10 l l 10179 1 14 i 10693 C7 5268 18 l l 10180 l C9 l 10729 '

13 5269 A2 l l 10181 i L7  : 10730 E9 5271 L1 l 10182 ; D6 { j 10731 C5 5272 l A1 I 10183 l G8 i i 10732 F10 5273 H12 1 10184 ? E7 6 l 10733 F3 5274 L2 l 10185 I G9 l 10734 H3 5276 H1 I I 10186 ! J7  ;

1 10735 I C4 5277 B7 l 10187 I J4  ! 10736 i D3 5278 H9 i 10188 i G3 I i 10737 i K3 5279 i F12 l i 10279 l L8 l 10738 l K7 5280 i A4  : j 10280 i E1 ,

i 10739 l D8 5292 i K9 l l 10281 ! D1 1 10740 i C6 5293 I li ,

i 10282 F1 '

i 10741 , J3 5295 ! 17 I I 10653 ! F8 i l 10742 ; E3 5296 A3 i i 10664 : J9 i i 10743 i H10 5298 M4 i l 10665 i H2

• i 10744 i J8 5301 D10 I j 10666 l K8  ;

i 10745 ! K4 5302 M1 l l 10667 l L4  ! I 10746 l 19 5303 E11 l j 10668 I E10 l l 10747 I K5 5304 M5 l l 10669 i H11 j 10748 i K6 5307 H5 i  ! 10670 i L5 i CPLUG G6 5308 l M3 i i 10671 i B4 i l CRING F6 5310 i F5 t

! 10672 l K2 I CRING I F7 5311 1 82 I i 10673 , C2 i CRING l G5

~5312 ; 11 1 i j 10674 i 86 '

l CRING l G7 5313 ! E5 i l 10675 l L6 -

1 CRING ! H6 5314 H4 1 10676 i C8  ! CRING l H7 5315 G4  !

10677 '

D9 l PTS I J1 5316 I H8 1 10678 ! F11 l SOURCEj B8 5317 l K1 i 10679 i 11 0  ! TR D4 5318 15 i i 10680 l J2 1 5319 16 '

i 10681 C3  : I i 5320 i ,E6 i i 10682 , B3  !

I i 5321 i JS t l 10683 i B5 l l 5329 I F4  !  ! 10684 i D2  ! j l 5338 l J6 l l 10685 i G11 i l l 5343 l F9 J l 10686 ! L3 l l l 5344 l E8 l 10687 i G1 i I '!

9160 l D7 i 10688 l 12 i I  !

10175 l C1 l 10689 l G10 ! l l

10176 ! E4 1 10690 1 G2 i i i i  ;  !

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- FE # Position FE # l Position I i FE # 1 Position i 5261 5339 i 15 ,

H8 l 10691 i F2 5263 A5 5343 F9 l 10692 1 E2

.5264 J6 5344 -H9 j 10693 i C7 i 5265- M2 9160 1 D7 I i 10729 i 13 5266 E5 10175 C1 l 10730 l E9 5267 J10 10177 81 l 10731 l C5 5269 A2 10180 i C9 I l 10732 i F10 5271 L1 1 10181 i L7 I i 10733 i F3

, 5272 A1 10185 : G9 i

! 10734 l H3 j 5273 : H12 10186 1 J7 j l 10735 i C4 5274 L2 10187 l J4 l l 10736 i D3 5276 H1 l 10188 i G3 i i 10737 i K3 5277 B7  ! 10279 ! L8 i i 10738 i K7 5279 F12 l 10280 i E1 I i 10739 i D8 5280 A4 l 10281 l D1 l 10740 ! C6 5292 K9 i 10282 i F1 l 10741 1 J3 5293 11 l 10653 i F8 I I 10742 ! E3 5295 J5 I I 10664 i J9 l 10743 i H10 5296 A3 -l 10665 i H2 i 10744 I J8 5298 l M4 i 10666 i K8  ! 10745 i K4 5299 i F4 l 10667 I L4  ! 10746 19 5301 l D10 10668 I E10 l l 10747 K5 5302 l M1 10669 i H11 l 10748 K6 5303 l E11 1 10670 t- L5 I cpi.UG G6 5304 l M5 1 10671 i PA I I CRING i F6 5305 E8 I i 10672 i K2 I i CRING l F7 5306 H5 l i 10673 i C2 l  ! CRING i G5 5308 M3 l l 10674 ; B6 i i CRING l G7 I 5311 i 82 } I 10675 ! L6 l l CRING j H6 5312 l 11 1 i i 10676 i C8 I j CRING l H7 5313 I D5 l } 10677 i D9 i i PTS  ! J1 5315 i E4 l 10678 I F11 '

I SOURCE! 08 5316 18 10679 i 11 0  ! t TR I D4 5317 K1 10680 i J2 i j i 5318 H4 10681 C3 i i  :

5319 14 10682 83  ! I j 5320 D6 10683 B5 l i )

5322 G8 10684 D2 j l l 5324 F5 10685 G11 j 5328 16 10686 i L3 i 5331 E6 10687 G1 l l 5333 17 l' 10688 12 I I l- 5335 I E7  ! } 10689 I G10 !  !

5337 l G4 l l 10690 i G2  ! l l l  ! l i 1  ! l

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1 98 core 1 Configuration l l l l l FE # Position FE # i Position i FE # Position 5261 15 10187 l J4 10738 K7 l

5263 -A5 -10188 I G3 l 10739 D8 5264 J6 10279 l L8 l 10740 C6 5266 ES- 10281 1 D1 10741 i J3 5267 J10 10653 i F8 j 10742 I E3 5269 A2 10664 ; J9 t j 10743 H10 5271 L1 10665 i H2 l l 10744 J8 5272 - A1 10666 i K8 l l 10745 K4

-5273- H12 10667 i L4 I l 10746 19 5279 F12 10668 l E10 1 10747 i K5 5292 K9 10669 i H11 10748 i K6 5293 11 10670 i L5 10824 M1 5295 J5' 10671 -

B4 10825 F1 5298 M4 l 10672 ! K2 l 10827 l A3 5299 F4 ( 10673 i C2 10830 l A4 5301 D10 .

-l 10674 ! B6 10831 i E1 5303 i E11 l 10675 L6 l 10832 i M2 5304 l- MS 10676 I C8 l 1 10838 i M3 5305 l E8 10677 i D9 l l 10839 i H1 5306 -) HS 10678 l F11 l t 10840 B2 5312 11 1 10679 i 11 0 l 10841 L7 5313 DS 10680 I J2 l 10842 L2 5315 E4 10681 ! C3 i 10843 87 5316 18 1 10682 ; 83 i l CPLUG G6 5317 K1 l 10683 ! B5 l l CRING l F6 l 5318 H4 i i 10684 I D2 I l CRING i F7 5319 l 14 l 10685 i G11 i i CRING i G5  !

5320 l D6 i 10686 ! L3 l l CRING I G7 5322'l G8 l 10687 i G1 l CRING l H6 5324 I F5 i 10688 l 12 i CRING j H7 5328 16 - 10689 G10 i PTS I J1 5331 E6 10690-I G2  : SOORCEi B8 5333 17 10691 ! F2 TR l D4 5335 ' E7 10692 i E2 1

-5337- G4 10693 ! C7-5339 H8 10729 l 13

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5343 F9 -10730 l E9 l 5344 H9- 10731 i C5 l j 9160 D7 10732 ; F10 l i 10175 C1 10733 i F3 i j 10177 B1 10734 i H3 I l l l: 10180 C9 10735 i C4' l l  !

10185 G9 10736 i D3 i j 10186 J7 , 10737 ; K3 l L. I I I e i o t t

98 core 2 Configuration  ; 6 I i l i l l l  ! I i I FE # I Position i i FE # Position ! I FE # 1 Position 5261 1 15 l l 10669 : H11 i i 10748 l K6 5264 j J6 l l 10670 i L5 i i 10822 i A5 5266 E5 10671 l 84 j i 10823 j 11 1 5267 J10 10672 ; K2  ! l 10824 l M1 5271 L1 l 10673 i C2  !  ! 10825 I F1 5272 A1 l 10674 i 86 l j 10826 E11 5279 F12 l 10675 L6 i i 10827 A3 5293 l 11 i 10676 '

C8 I l 10828 I D1 5295 I J5 i i 10677 l D9 l l 10829 i L8 5299 i F4  ! l 10678 i F11 I  ! 10830 ! A4 5301 l D10  ; i 10679 i 11 0 l  ! 10831 i E1 '

5304 j M5 i i 10680 l J2  ;

i 10832 i M2 5305 I E8 I i 10681 i C3 1 '

10833 M4 5306 H5 l I 10682 ! B3- 1 i 10834 i H12 5313 D5 I I 10683 i B5  ! I 10835 I B1 5315 E4 i i 10684 i D2  ! l 10836 i K9 5316 18 l l 10685 i G11 i i 10837 i A2 5317 l K1 i i 10686 I L3 l l 10838 l M3 5318 I H4 I i 10687 G1 l l 10839 i H1 5319 l 14 i l 10688 ! 12  ;

i 10840 i 82 5320 l D6  ! f 10689 : G10 i j 10841 ! L7 5322 l G8  ! l 10690 i G2 1 10842 i L2 5324 i F5 { l 10691 t F2 ( f 10843 i B7 5328 l 16 1 i 10692 < E2 l lCPLUGi GG 5331 i E6 i i 10693 i C7 i  ! CRING l F6 5333 j 17  ! l 10729 13

CRING l F7 5335 l E7 l  ! 10730 t E9  !  ! CRING i G5 5337 i G4 I I 10731 <

C5 i  : CRING f G7 5339 l H8 l l 10732 F10 I i CRING i H6 5343 i F9 I 10733 F3 .

I CRING I H7 5344 i H9 1 10734 H3 I  ! PTS I J1 9160 l D7 l j 10735 C4 (SOURCE; B8 10175 l C1 i  ! 10736 D3 i I TR  : D4 10180 i C9 l l 10737 ; K3 I  !

10185 i G9 l  ! 10738 i K7 I i 10186 J7 i  ! . 739 l D8 i  !

10187 J4 I i 10740 i C6 l , i 10188 G3 l 10741 i J3 i i l 10653 F8 10742 i E3 i i i 10664 l J9 10743 i H10 i J l l 10665 H2 1 10744 r J8 I l  !

l 10666 K8 l l 10745

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ELEMENT MOVEDATE ' LOCATION REASON NOTE' 5279 "

g 6/20/89 PITC-04 RECEIVED

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l I 1/1030 RACK 2-04 PREPARING FOR !NITIAL MEASUREMENT 4 ,,g Q j f 1/12/90 RACK 2-04 INITIAL FUEL MEASUREMENT ~ '

1/23SO RACK 3-08 . PLACING EXTRA FUEL IN ONE RACK 7/17/90 CORE F-13 ADJUSTMENT OF CORE EXCESS - .

8/l1/92 CORE F-13 ANNUAL INSPECTION I1/2/94 RACK 2-17 CORE UNLOADING 12/1/94 CORE F-13 CORE D 8/15/95 CORE F-13 ANNUAL INSPECTION 8/19/96 RACK 5-06 CORE UNLOADING

, 9/11/96 Rack 1-06 Periodic Inspection 9/30/96 Rack 1-06 Install adapter 10/1/96 Pit A-06 Make room for Pri.Sys. Installation 2/3/97 Rack 2-06 Return fuel to Rx tank . Prep core load -

2/6/97 Rack 2-06 3/6/97 Core F-04 Following, bottom end adapter installation _ Tus kg,y hy(.,g For Load and Test Procedure 6/16/97 Core F-12 Rearrange core to increase core excess L

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Core F-12 Element ** is 20 wt. % Element Element ## are 30% wt. U / 20% wt. U-235

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FUEL MEASUREMENT DATA

. 10-Feb-97 f

Date Measured Dev. Tot. Tot. NOTES:

ELEMENT Meas. l at. 2 nd. 3 rd. Ave. Ien. Chng.

5279 1/12/90 0.050 0.050 0.051 0.050 24.142 0.000 t 8/11/92 0.071 0.069 0.074 0.071 24.163 0.021 8/15/95 0.069 0.071 0.073 0.071 24.163 0.021 9/11/96 0.070 0.073 0.073 0.072 24.164 0.022 2/6/97 0.265 0.265 0.264 0.265 24.357 0.022 First measurement following bottom end adapter installation i

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ATTACHMENT 12 I

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ELEMENT . MOVEDATE LOCATION REASON NOTE 5304 6/20/89 PITC-19 RECEIVED t.3 % %-T 1/10/90 RACK 2-19 PREPARING FOR INITIAL MEASUREMENT cm ( bD 1/1260 RACK 2-19 INITIAL FUEL MEASUREMENT 1/20/90 CORE F-18 CORE LOADING 8/5/91 CORE F-18 ANNUAL INSPECTION 11/2/94 RACK 3-05 ANNUAL INSPECTION - CORE UNLOADING

, 12/2/94 CORE F-18 CORE D 8/19/96 RACK 1-14 CORE UNLOADING 9/11/96 Rack 1-14 Periodic Inspection ,

9/30196 Rack 1-14 Install adapter 10/1/96 Pit A-13 Make room for Pri. Sys. Installation 2/4/97 Rack 2-13 Return fuel to Rx tank . Prep core load *

, 2/6/97 Rack 2-13 Following bottom end adapter installation Tase:ch ois feur-[1, ec,1.

3/6/97 Core K-06 For Load and Test Procedure 6/16S7 Core M-05 Rearrange core to increase core excess i

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i Cor: M-05 Element ** is 20 wt. % Element Element ## are 30% wt. U / 20% wt. U-235 ,

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FUEL MEASUREMENT DATA 10-Feb-97 '

Date Measured Dev. Tot. Tot.

NOTES:

ELEMENT Meas. I st. 2 ad. 3 rd. Ave. Len. Chag.

5304 1/12/90 0.051 0.055 0.052 0.053 24.145 0.000 8/5/91 0.061 0.061 0.064 0.062 24.154 0.009 11/2/94 0.065 0.064 0.063 0.064 24.156 0.011 9/11/96 0.064 0.060 0.062 0.062 24.154 0.009 2/6/97 0.072 0.072 0.071 0.072 24.164 0.009 First measurement following bottom end adapter installation I

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Element ** Is a 20 wt. % Element Page 37

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L ATTACHNENT 13 r

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SOP 98-14 Removing FuelElement 10730 From the Reactor Core l

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PREPARED BY: Charles C. Heide!

DA TE: %'h' %

REVIEWED BY: WNA ~Yt hnw DATE: %'M-%%

OPERA TI SSyPE VI R \

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! / PURPOSE The purpose of this document is to remove and recover fuel element from the reactor core. Fu element 10730 can not be removed from the reactor core area. The element can be raised approximately S.5 inches at which time it will not pass through the upper grid plate.The fuel element will be recovered by removing the central facility and placing a fuel element capture a

! leveling device (figure 2) in it's place. The element will be raised and the bottom wih be positio in the central facility area to be removed from the reactor core area.

Il PRECAUTIONS l

a.

The following precautions shall be observed during all phases of the operation.

1. .

All equipment and tools removed from the reactor tank shall be checked for contamination.

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2. All primary water shall be treated as potentially contaminated.

3.

All operations in the reactor tank shall be under the direct supervision of a Senior Reactor Operator.

4. l When ever any member of the Operation and/or Health Physics staff has a '

question about the procedure or operation all work shall cease until the question is answered to .their satisfaction or management resolves the matter, lll Removable of FuelElement 10730 g a.

Ensure that all fuel elements are removed from the following areas (Figure 11:

c.p 4 1) Fuel elements surrounding fuel element 10730.

2) Fuel elements surrounding fuel element the central facility.

3) Fuel elements between fuel element 10730 and the central facility.  !

b.

-@ Remove the aluminum plug from the central facility using the fuel element handing l

%, tool and store it in a suitable location in the reactor tank.

4 c. Remove the graphite plug from the central facility and place in the #: Liment

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..,_._. g a9%A:b:. s'Ne @ qg, CG d.

g.3 g Locate the aluminum plug in the center of the graphite plug. -

e.

bkg Remove the central facility from the reactor core area and store it in a suitable

,p C 6 location outside the graphite reflector,

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f. h* " J^ "" ,.aeid _, ,iw mcl pale) iss.the fuel element capture and leveling device (Figure 2). Lower it into the reactor tank and into the center of the Tp#ofo reactor core. The fuel element capture and leveling device rest on the bottom of l

the reactor tank with the top portion even with or slightly below the lower grid plate (Figure 3). Remove the %-20 bolt from the fuel element capture and leveling I device.

SOP 9814 1

g.

Place a snare around fuel element 10730. The snare should be located in the detent location ori the upper pole piece.

h.

Place the hook tool in the reactor tank and lower it into the central facility location,

i. Raise fuel element 10730 approximately 1 to 2 inches.

j.

Using the hook tool guide the lower end of the fuel element into the central facility cavity.

k.

V)/ hen the lower end of the fuel element is in the central facility cavity, slowly lower the fuel element until it is inside the fuel element capture and leveling device (Figure 3). The hook tool may be required to help the element sit in a fully vertical attitude.

I.

Remove the snare from the fuel element. Capture the fuel element using the fuel element-handling tool, m.

Remove the fuel element from the fuel element capture tool and place it in the appropriate location in the fuel storage rack.

n.

Remove the hook Wol and the fuel element capture and leveling device from the reactor tank,

p. Relocate the following into their in-core locations:

1) Central f acility 21 Graphite plug 31 Aluminum plug o

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