ML20151U264

Insp Rept of Department of Energy Shipment Conducted on 980721-23.No Violations Noted.Major Areas Inspected: Security,Safeguards & Radiological Controls

ML20151U264
Person / Time
Issue date:	08/21/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20151U229	List: ML20151U225 ML20151U264
References
NUDOCS 9809100339
Download: ML20151U264 (29)

Text

_.

t U. S. NUCLEAR REGULATORY COMMISSION REGION Il i

t Shipper:

U. S. Department of Energy Locations:

Concord. California Idaho Falls. Idaho Date:

July 21-23. 1998 Inspectors:

James Knicely. Security Inspector, Region III Blaine Murray. Branch Chief. Region IV Blair Nicholas. Health Physicist. Region IV William J. Tobin. Senior Safeguards Inspector. Region II Approved:

Edward J. McAlpine. Chief Fuel Facilities Branch Division of Nuclear Materials Safety Region II i

1 i

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+

e Enclosure 9809100339 980821 PDR ADOCK 07200020 PDR

..______m._..

1 EXECUTIVE

SUMMARY

I By correspondence dated April 1.1998, the NRC was informed of the Department of Energy (DOE) proposal to import irradiated research reactor fuel from the Republic of Korea to the Idaho Falls facility. through the Concord Naval Station in California via the. Union Pacific Railroad.

i l

From April 20-27. 1998, two NRC region based security inspectors conducted the required Route Survey which included contacting the four governor's representatives from the states of California. Nevada. Utah and Idaho either i

personally or via telephone. Discussions included:

a) the criteria of 10 CFR Part 73.37 " Requirements for Physical Protection of Irradiated Reactor Fuel in Transit." b) the need to protect Safeguards Information. c) the duties of 4

the NRC security and health physicist inspectors relative to this shipment.

and d) other state specific issues.

The NRC approved the shipment route on June 2, 1998.

)

On July 10. 1998, the DOE notified NRC of the scheduled arrival of the shipment at the Concord Naval Station, primary rail route. description of the i

cargo and mode of transport to Idaho. As required by 10 CFR Part 73.37. the i

DOE further provided such advanced notification to the four governor's j

representatives and the chairmen of the appropriate tribal reservations.

On July 21, 1998. three NRC inspectors met the shipment as it arrived at the Concord Naval Station, a fourth NRC ins]ector was dispatched to the Idaho Falls facility to monitor the shipment )y telephone / radio and tu inspect it l

t ll of the U. S. Coast Guard, conducted radiation measurements inside the cargo upon arrival.

Prior to off loading the shipment, the DOE. with the assistance l

bays of the ship and found no radioactive leakage. As each of the three casks 1

was lifted from the ship, it was inspected for radiation leakage, and no readings of concern were detected. The dose rates measured around the individual freight containers and the loaded rail cars. as well as the levels of removable contamination measured from the freight containers, were well below the regulatory limits.

These radiation surveys were independently i

I conducted by the DOE. the California Department of Health, the Contra Costa County Department of Health, and the NRC.

The train /railcars/ caboose received inspections from Union Pacific personnel as well as, independently from the U. S. Federal Railroad Administration.

The NRC also verified armed police were on the train and that they were equipped with the required security equipment. After receiving approvals from all of the above mentioned organizations. the NRC inspector authorized the departure of the shi] ment at 12:46 a.m. on July 22.

Some 31 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br /> later the shipment was again clecked for radiation by DOE technicians as it entered DOE property at the Idaho facility.

The results of that survey were in harmony with the Concord measurements.

l

.The shipment was conducted in accordance with NRC and the Department of Transportation (DOT) requirements.

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REPORT DETAILS 1.

Security and Safeguards (81310) a.

Inspection Scope

{

10 CFR Part 73 was the security regulation in effect for this shipment of spent fuel.

NRC Inspection Procedure No. 81310

" Physical Protection of Shipments of Irradiated Fuel" contained the applicable criteria to determine compliance with the NRC i

security requirements. The DOE utilized an Operational and Contingency Emergency Plan dated July 15, 1998, to coordinate with all parties having duties and res)onsibilities for the shipment.

An Escort Book was furnished to tie Union Pacific police officers escorting the shipment which detailed their role in the event of a delay or other contingency.

b.

Observations and Findings The Route Survey was performed from April 20-27. 1998. All " crew change" locations were visited as were all " heavily populated areas." The representatives of the four state governors were contacted and other appropriate state officials were also visited.

A complete list of these officials is contained in Attachment 1.

DOE correspondence dated July 10. 1998, informed the NRC of this pending shipment to include a description of the cargo and mode of travel. Additional letters dated July 14. 1998, were sent to the a)proariate state governors and tribal chairmen informing them of tie slipment.

During the evening hours of July 21 this shipment arrived at the Concord Naval Station and commenced offloading.

Security was i

provided by the U. S. Coast Guard and at the pier, by U. S. Navy personnel.

These armed officers were the " escorts" while the unloading process was completed.

The Naval Station had set u) a Situation Center while the unloading process was ongoing so tlat communications and coordination were assured.

A canine from a nearby U.S. Air Force facility was used to search the various cars of the train with negative results.

The search was professionally conducted.

]

Once positive feedback from local. state. 00E Federal Railroad Administration and NRC inspectors, and following a verification of J

communication capabilities. NRC authorized the movement of the shipment.

-]

1 2

During the approximately 31 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br /> of movement, the NRC inspectors visited Command Centers located in e,ncord and Idaho Falls to witness the radio capabilities of the Union Pacific train.

The required two hour checks to these stations were completed without difficulty.

On July 22, 1998, an inspector arrived at the DOE Idaho National Engineering and Environmental Laboratory (INEEL) and visited the Warning Command Center (WCC) which functioned as the communication center for this shipment.

Transportation Tracking and Communication System (TRANSCOM) was utilized to track the shipment. The Concord Situation Center had 3rimary communication oversight-until the shipment crossed the Utal border at which time the primary communication responsibility switched to the WCC.

At the WCC the inspector reviewed the situation reports which documented the status of the shipment every two hours (usually hourly).

The inspector verified through questioning. observation and record review that the WCC eperators and all other persons contacted were knowledgeable of the responsibilities and that Safeguards Information was ap)ropriately protected. The " Primary" rail route was utilized and tie crew change and fuel stops were as planned.

There were no credible event / threats identified.

Interviews with local law enforcement personnel and others revealed-that DOE comaleted training some 3000 "first responders" along the route and t1 roughly inspected the tracks. locomotives, railcars and shipping containers.

On July 23, 1998, at approximately 8:54 a.m. the train arrived in Scoville. Idaho. (00E property) where the Union Pacific Railroad transferred the train to DOE and all personnel accompanying the train departed.

The inspector verified that communication capabilities were serviceable and that the health physicist.

security communication. DOE and Union Pacific personnel performed their duties as required.

Radiation surveys were performed with negative results. At approximately 10:00 a.m. the train crossed Route 20 (last public area) and further entered DOE protected property without incident.

On July 23. 1998. DOE issued a press release that the spent fuel shipment arrived safely in Idaho.

c.

==

Conclusion:==

The NRC insp6ctor verified that the three shipping casks containing spent fuel elements safely arrived at the DOE /INEEL facility.

T1e NRC requirements identified in 10 CFR 73.37

" Requirements for Physical Protection of Irradiated Reactor Fuel in Transit" were adequately implemented.

No violations of NRC requirements were identified.

3 2.

Radiological Controls (86740) a.

Inspection Scope The inspectors reviewed the DOE's program, performance, and procedures for compliance with the NRC requirements in 10 CFR Part

71. Packaging and Transportation of Radioactive Material and Department of Trans)ortation (DOT) requirements in 49 CFR Parts 170 through 189. T1e inspectors performed radiological surveys of the freight containers to determine compliance with dose rate and removable contamination limits.

b.

Observations and Find'ings The DOE shipped three casks from the Republic of Korea containing spent fuel elements with activities ranging from 2.600 to 26.400 curies per cask.

Prior to the shipment from overseas each spent fuel cask was placed in a separate, sealed freight container designed to be easily secured to a flat rail car.

Upon receipt in the United States. the three freight containers were off-loaded from the ship at the Naval Weapons Station. Pier 4. located at Concord. California, and were loaded on two flat rail cars.

Two freight containers were secured to one rail car, and the third freight container was secured to a second rail car. An empty flat rail car was positioned in the train to separate the two locomotives from the first rail car containing two freight containers, the next rail car in the train contained the third freight container, and a second empty flat car separated that loaded flat car from the caboose.

The three spent fuel casks were shipped as an " exclusive use" shipment.

The inspectors examined the shipping pa)ers prepared for each cask.

The inspectors determined that tie shipping papers were properly completed and were in compliance witi 49 CFR 172.200 through 172.205.

The spent fuel casks were transported as an " exclusive use" rail shipment and each spent fuel cask was placed in individual, sealed freight containers that made the conveyance a closed transport vehicle.

Since the spent fuel casks were in sealed freight containers and were in a " transit mode" from the overseas shipment origination point enroute to their final destination the inspectors did not have access to the spent fuel casks.

Therefore, the inspectors did not have direct access to the radioactive material packages and no direct radiation surveys of the radioactive material package surfaces were performed.

Prior to the freight containers being loaded on the flat rail cars, the inspectors performed a contamination and radiation survey of the bottom of each freight container. After the three freight containers were loaded on the flat rail cars, the inspectors conducted additional radiological surveys (dose

=

4 rates and smear surveys for alpha and beta-gamma removable contamination) of each freight container to determine if the shipment complied with the dose rate and contamination limits specified in 49 CFR 173.441 and 173:443 and 10 CFR 71.47.

The radiological survey results are documented in Attachment 2.

Since the inspectors did not have access to the radioactive I

material Jackages, the inspector was unable to determine the level of remova)le radioactive contamination on the external surfac= -f each s)ent fuel cask.

However the inspectors took several smet s from t1e exterior surfaces of each freight container and near any openings into the freight containers.

The 100 cm contamination 2

smears were each counted for one minute with an Eberline Model PS-2 Portable Scaler (NRC: 012773) connected to an Eberline HP-210 shielded " pancake" Geiger-Mueller detector (NRC: 012384) for i

beta-gamma analysis, and each smear was counted for one minute with an Eberline Model SAC-4 Scintillation Alpha Counter (NRC: 012831) for alpha analysis.

The analysis results of the contamination smear counts ranged from less than the instrument background count rate to a maximum of 104 disintegrations per minute (dpm) beta-gamma and to a maximum of 3 dpm alphas.

Initial scan surveys were performed with a Ludlum Model 12 Geiger-Mueller survey meter (NRC: 012753) to identify general elevated radiation levels.

Follow-up radiation surveys were performed using an Eberline R0-20 (NRC: 057124): survey meters to measure the contact dose rate on each side of the freight containers and at the vertical plane and 2 meters from the vertical plane on each edge of the flat rail cars loaded with the freight containers to establish dose equivalent radiation levels.

The background radiation level was less than or equal to 0.15 millirem per hour (mrem /hr).

The measured contact dose rates ranged frcm background to 1.6 mrem /hr.

The measured dose rates at the edge of the flat rail cars ranged from background to 1.4 mrem /hr. The measured dose rates at 2-meters from the vertical plane at the edges of the flat rail cars ranged from background to 0.6 mrem /hr.

The measured dose rates in the caboose and in the area where the locomotives would be attached to the train was <0.1 mrem /hr.

Based on the radiation survey results.

the inspectors determined that the shipment did not exceed the vehicle outer surface radiation level limits of 200 mrem /hr. the 10 mrem /hr limits at 2 meters from the rail car edges, and the 2 mrem /hr limit in the occupied spaces of the train's locomotives and caboose, c.

Conclusions The shipping Japers and shipment documentation were properly completed. T1e dose rates measured around the loaded rail cars and individual freight containers and the levels of removable 1

contamination measured from the freight containers were well below l

5 1

the regulatory limits.

The shipment was conducted in accordance with NRC and the DOT requirements.

3.

Exit Meeting Prior to the departure of this shipment. the inspector met with the two DOE Project Managers identified in Attachment 1 of this Report to discuss the findings of this inspection. There were no regulatory issues to be voiced, the DOE was informed that the shipment was meeting NRC and DOT requirements.

This meeting took place at 12:40 a.m..

July 22. at the Railroad Exit Gate of the Concord Naval Station.

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

ATTACHMENT 1 1.

Persor,s Contacted Route Survey (April 20-27. 1998)

M. Arenaz. DOE.'INEEL M. Cornell. DOE Livermore R. Coombs. DOE. INEEL R. Dahlquist. Lockheed. INEEL A. Dold. State of Idaho D. Finerfrock. State of Utah R. Gerber. California Emergency Services R. Healy. California Highway Patrol S. Jones. Idaho State Police S. Marshall. Nevada Health Services (Governor's Representative)

M. Planka. California Highway Patrol (Governor's Representative)

D. Rich. Idaho State Police (Governor's Representative)

G. Schwartz. Idaho Statt.olice W. Sinclair. State of Utah (Governor's Representative)

J. Strolin. Nevada Office of the Governor

• R. Stump. Project Manager. DOE. INEEL D. Tuohy. Nevada Highway Patrol D. Walker. State of Idaho D. Wells. State of Idaho K. Yocum. Concord Naval Station Shipment Inspection (July 21-23. 1998)

B. Benike. Contra Costa County Health Department G. Carnes. TRANSCOM Inc.

B. Cimino. Contra Costa County Emergency Services P. Dirtmaat. DOE, INEEL L. Glassbrook. DOE. Livermore R. Johnson. Federal Bureau of Investigation (FBI). San Francisco W. Lew, California Department of Health J. Lorraine. Union Pacific Railroad Police

• T. Mustin Project Manager. DOE. Washington D.C.

S. Pay California Department of Health G.- Phillips. Security Services Inc.

j J. Tijan. Federal Railroad Administration J. Turner. D0E Oakland C. Urbanski, Lockheed. INEEL S. Wallack. Schenker International Corporation B. Williams. Nuclear Assurance Corporation

!J. Wolflick. Nevada Public Utilities Commission

/

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2 NRC Personnel J.

Kniceley. Security Ins)ector. Region III B.

Murray. Branch Chief.

Region IV B.

Nicholas. Health Physicist. Region IV

• W.

Tobin. Security Inspector Region II

• Denotes attendance at the Exit Meeting 2.

Inspection Procedures Used~

No. 81310 Physical Protection of Shipments of Irradiated Fuel.

No. 86740 Transportation Activities 3.

Acronyms Used i

CFR Code of Federal Regulations DOE Department of Energy DOT Department of Transportation dpm' disintegrations per minute FBI.

Federal Bureau of Investigation INEEL Idaho National Engineering and Environmental Laboratory mrem /hr millirem per hour

-PS Portable Scaler SAC Scintillation Alpha Counter TRANSCOM.

Transportation Tracking and Communication System WCC Warning Command Center I

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d SPENT FUEL RADIATION SbRVEY RESULTS USNRC REGION IV 7/A / !9ff DATE:

INSPECTOR M b M M 4A 6dt/

INSPECTOR:

l ATTACHMENT 2

Pre-Survey Form 1 Instrument Calibration /Reponse Test Instrument instrument Source Source ID Known Value Actual Efficiency Acceptance Acceptable ID No.

Radionuclide No.

Reading Range y,smn RO20 057122 Cs-137 No.1

-8uCi ef.o N/A 8.0 - 10.0 mr/hr fg5 RO2O 057124 Cs-137 No.1

-8uCi 7, y N/A 8.0 - 10.0 mr/hr YES Model 12 012753 Cs-137 No.1

-8uCi

/0,o EV N/A 9.0E4 - 11.0E4 cpm YES PS-2 Scaler 012773 Cs-137 13154 29,244dpm 6 /So Jt/,o %

18.0 -22.0 %

Yg5 SAC-4 012831 Tb-230 11668 21.300dpm 5 7Pf 27,2 /,

25.0-29.0 %

YE5 i

7[.2/!97

/7md PDr' Inspector 3/d$,

Date/ Time:

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Post-Survey Instrument Calibration /Reponse Test instrument instrument Source Source Known Value Actual Efficiency Acceptance Acceptable ID No.

Radionuclide ID No.

Reading Range yesmn RO20 057122 Cs-137 No.1

-8uCi 77 N/A 8.0 - 10.0 mr/hr 76S RO20 057124 Cs-137 No.1

~8uCi 7.7 N/A 8.0 - 10.0 mr/hr YES Model 12 012753 Cs-137 No.1

-8uCI

/.0Ef N/A 9.0E4 - 11.024 cpm yfs-PS-2 Scaler 012773 Cs-137 13154 29,244dpm 4/20 24,9 "/,

18.0 - 22.0 %

YES SAC-4 012831 Th-230 11668 21,300dpm 5757 p7.o 7o 25.0 -29.0 %

Y65 Nls MA/!97

// M P 'PP7' Inspector

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Date/ Time:

SPENT FUED.. JIATION SURVEY Form 2.,

CASK SHIPPING CONTAINER Container I.D. No.: A[ Ace ( F5do /# /r)

Contents: 96 L,dtJeJ My,/uv K,e/ 6 /e -.c/r TcJ:..eltye hfdert.A, Proper Shipping Name: c:,stle vos, r-o c/.117 U.N.I.D.No.:

29//'

(94 7 Fy) u#T J4odymms Radionuclidc(s):

//. M rP Activity: 26 oo (%v le.s Package Labels: Td,J;oo <J :ve % //.,o 77Z' Package Mark,ings:

2 9 /P' Transport Index: tis o. o y Fissile Class:

6/orr 7 RO.to N Re : 057/.2:{ 6/: Y-Jo.97 Instrument: m..J. t e.t. naeso,2.233 d.l:,.is-vr Date/ Time of Survey:

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Nge:or.2th LIMITS:2200 dpm/100cm (Beta, Gamma) am e p-5 TOP f.o m.'-

R0 W100 cni (alplia) i DATEITIME: 7/a s /9P

/9 2 2o p 07-6 BOTTOM 2Ja ce-ilNSPECTOR: ' bI i

(Readings in mrem /hr gamma unless noted otherwise) p,na

~7 ne t r

p 1

4

-,ab an.

a.

s

-m-

---m-a

,_gw-Ws a

m Am+-

L-,,._aw

-ma,,

D

$a a!

5 5

9 5

9 9

9 3

9 E

9 5

i I

e 3 g; a

(

a o

w o

.t.

R P

E e

z a

.a o

o 4

EI a

?

5 N

A t

A a

x m

a

~

.N D

E O e 5

.O

~<

0 0

0 0

0 D )

D o

3 0

o 0

0 i

f a

m u

m y

9 r

t T

I>

E 1

+-

O E

O n

O 2

zH>

E_z>

k, d

0 0

3 3

3 0

3 f

O O

3 3

0 0

O e

E z

a 8

z>r

~

(n n

rn o k_h Q

. y P

i&

m O

O C

c r

8 d

8 en I"s 3' "

0 0

0 0

o a

o o

0 0

t B~2 n

O N

N 5

m

t REMOVABLE BETAIGAMMA CONTAMINATION ANALYSIS RESULTS Form 2.e Container I.D. No. fS o o /r(3)

Bac k q vo u nd. = So c. p m Sample Instrument Gross CPM BkoCPM Net CPM Detector DPM per Efficiency 100 cm' 1

PS.tlH P-a ro C3 So 3

3 / 0 9a

/4 ts-t k

Oks 4

ay

< a e, i s.2.

4. O K1 13-3 So

<6kg 1

18 4 45

< SKq

< B Kg

' 6-5 47

< Bka

< B Ws iS-C N9

< D rq

4. B kg os.7 7 2.

1.L fohl

/s r 35

< BR$

< 0 kg

/S 9 3I

< 6k,

< DR, IT-so 33

< O K,

< B km

/F //

37

< U K,

< 6 t, tr-/L 32

<. DKg

< 0 kg

/ S -13 37

4. B K, 4 Gkg I

IS sq 23

,s

< D Kg

<Bh v

Date/ Time of Survey-7ItI/or a a */r ? DT Inspector-t 1

Page 9 of /7

e 3

i SPENT FUEL SHIPMENT..aD:ATION SURVEY RESULTS Form 3 i

Container I.D. No.:

F3oo/S(3)

Date/ Time: *//2/[9F l

Instrument:

Ro2a A>ac: o s'? / 2 4. PS 1/H P-Aso. sac.4 lnspeClor" E

Ace sastin{ ant.h une t **192:

I Background Radiation Level:

o. /5 e m /Av O-Y sSteps xs o erw i

1 DOSE RATES (mremlhr)

REMOVABLE CONTAMINATION (dpm/100cm')

7 Location Contact 1-Meter 2-Meters Sample Beta / Gamma Alpha

- i No.

No.

l Rcts g Lo.L

<o.I tr.

14 o

s p'non t

< O. 1-

< o. I t.r-1.

< (Ik, a

L E F 1~

I. S~

6. 5 17-3

< B K, o

R tcar*

I4

c. 4 tv 't

< 0 kg o

l Yo P

l. O IT-f

< 0 kg o

t.T-4

< B k, o

oS-7 10 4

=

o i

{

s:r-F

- Uk, 3

1 of-9

<. Q kg a

s F-so

< 0 kg o

1 es-er 4 0 X, o

ir-n.

< U k, o

s c-o3

4. 0Ks o

or s1

< 0 Ke o

i LIMITS:

200 mrem!hr N/A 10 mrom/hr 2200 dpm/100cm 220 dpm/100cm 2

2 Page of _Zo_.of /7

t-SPENT. FUEL.

.1ATION SURVEY Form 2.u CASK SHIPPING CONTAINER Container I.D. No.: A[Acu Proo/4 (9 )

Contents:

/o 7 Iv'voc/tuled M,./... Gol IIIe mds T.Jt.. 1:ve. m 1sveaf, Proper Shipping Name: r;ni/a //05-e/.,r 7 U.N.I.D.No.:

z9/r Radionuclide(s)

t/. m F P Activity: /& Joo day.ks

/,c.ov Ytk,.)

a #'E 4 9coSm-s Package Labels: Tact;.eJ:n % //,, ~!If Package Markings:

29/P Transport Index:

fr-o.7 Fissile Class:

d less 7 ROAO ^) RC t 05 21k W

$All4'00*SI Instrur 't: m.J. I,.t.

une so,2 7s3 c.b <.es.9r Date/ Time of Survey: 7/,xi/9r ac ao po r 1

Inspector:9I IJ.D

(

i

'B OI C La.t: g 1

/b ax lo s a t kv ace 1 2.,1 m yst s kr.

/-mafev :

o,P mva-/ hv.

1 4

Page

//

of /7

CONTAINER RADIATION ovRVEY MAP AND RECORD F"I gh 0*f faox3r s

b

,g,A

,f g

og CONTAMINATION SURVEY RESULTS (l

NO.

BETA-GAMMA ALPHA e

io /**

yofSW 1

< ok9 o

f*

• p.t' c

y 2

< Bn o

po) 4

,.s.

l 2e !

&l-l

~?'

g,7 61V 5

<. B kg o

1 y

gge

{

k"/

6

<. U kg o

7

<. O R, o

I b

8

4. O r, o.

9

< D r, o

10

< a x, o

HO.

LOCATION CONTACT 1 METER 11 x 3g '

g o

'o ce -

CONTAINER ID. NO.:

ffs aoi4(9 )

1 N

< o. l -,

12

<.o 2,,

go.ao unc s dryiav SURVEY INST. NO.: McAi #2 nac : ois 7s.r 2

/j[,

( o, g s, 13 14 f a go c,,

3 LEFT SIDE o.6 -

o. 2-l Ely COUNTER NO.:

Pr.2 / nr.2so unc g'

i naesoam / nae s o*1sv4 '

s t av e r -.

4 RIGHT SIDE o.r,

o,3 m,-

LIMITS:2200 dpm/100cm*(Beta, Gamma)

! CI COUNTER NO.:

sac-4 N ee o/2,3t l

5 TOP j

220 dpm/100 cm*(alpha)

~

DATE/ TIME:

>di/97 2 o Ed P D*e' 6

BOTTOM isocep, l

INSPECTOR

UN L

(Readings in mrem /hr gamma unless noted otherwise)

Pane It of /7

REMOVABLE ALPHA CONTAMINATION ANALYSIS RESULTS Form 2.d Container I.D. No. Troo 16(9)

'Sck,vouJ *OcP^

Sample lastrument Gross CPM BkoCPM Net CPM Detector DPM per Efliciency 100 cm'

/6 -1 SAC-4 O

O o

2729a o

/ta-A b

6 O

/6-3 o

o n

s6 -4

/

I 3

IL - T o

o n

JC-4 o

O o

/4-7 o

o o

Ib

• Y O

O O

/6 'l o

o o

16 -/C 6

c)

O 14 -Il D

O

\\p o

M Daterrime of Survey-7 4//97 33/d P DT inspector:

t

/

Page /3 ct /7

=

REMOVABLE BETAIGAMMA CONTAMINATION ANALYSIS RESULTS Form 2.e Container I.D. No. 8So o /4 (9)

BackgroumA 1 So c.p m l

Sample Instrument Gross CPM Bkg CPM Net CPM Detector DPM per Efficiency 100 cm' iu-jr., - 1 Ps-2. lH e.)oo 2I 5o

< B kg 2 f. o To

'~ G kg I

/4-z-J7 4 0 x, L

<0k q

l

/ 4 -3 43 4 0 r, 4 GR9

/4-V 47 s7 T'/

/ 4 -s-g4 48k3

< 0 g,

//. -d so

<0K3

< O R.

< Ok IL-7 No

<- O k 4

g

//,-Y N s-40%

< O r,

/4-9 l

43

4. QK, E BK4 14 so 34

4. 0 K,

<. O kg

( O k,

,e

< B R,

/4 -//

v 3 s-Date/ Time of Survey: 7/2./ 97

1. J/oPDT Inspectoc Page /'f of /7

SPENT FUEL SHIPMENT k...>lATION SURVEY RESULTS Form 3 Container I.D. No.:

Froo / 4r (9 )

Date/ Time:

7 di/7//

Instrument: RO2O PS-2./# #.aso SAC-4 lnSpector*

MRes eC1/29 NAc s oIA1S) nac.tc1173I Background Radiation Level:

0.rY mm /A.

p -Y - sb s p w cx s oc_ps DOSE RATES (mremlhr)

REMOVABLE CONTAMINATION (dpm/100cnf)

Location Contact 1-Meter 2-Meters Sample BetalGamma Alpha

~

No.

No.

pgy 40.1.

< o. I 14-1

< B kg o

f cour

4. o. 2-

< o. I 14 L-

4. D K4 o

LliPY

o. 4 0. 2,

/L-3

< D tg a

R I C H 7~

O<?

O.3 16 'M V/

3 7op o.5 16 - f

< B kg o

1

/4 -d.

4 0kg o

k 14 ~ 7

< 0K9

. o 14-7 4 0K, o

4 s4 -9

< B kg o

14 -to

< Bkg a

14 - ll

< 6 kg o

8 2

LIMITS:

200 mrem /hr N/A 10 mremlhr 2200 dpm/100cm 220 dpm/100cm

'l Page of /f of /7

TRAIN CAR NO.

.L RADIATION SURVEY MAP AND RECORD (w A,a A lue-oh) 2 8

Fv d

[

]

[5]

3

[

10

[{j]

3 Rw e 9111 gg

'2 CONTAINER ID. No.: Pfad/V CONTAINER ID. No.: Fro o es' SURVEY INST. NO.: 'Ro ;to NRe t os 7/W DATE/ TIME: 7/.u/9r INSPECTOR:

SMb No.

LOCATION CONTACT LIMIT 2-METER LIMIT Container No. FrooN t

1 Front Vertical Plane 4 o. l=rm/A, 200 mrem /hr 4 o. /==m/k 10 mremrnt l f

2 Top

<o.2.mv=-/A, 200 mrem /hr

4. o,lmvo w /kr N/A 3

Rear Vertical Plane

<o.Imv==/h, 200 mrem /hr 4.o. /my

/ A, 10 mrem /hr 4

Left Side Vertical

<.o.1mram/Le 200 mrem /hr 40.1mye-/A, 10 mrem /hr 5

Right Side Vertical 4.o.2mve=/kv 200 mrem /hr 4 o,l uvah, 10 mrem /hr 6

Bottom

<o,Imva-/kr 200 mrem /hr 4.o.Imvem/ke N/A Container No. froo ts 7

Front Vertical Plane 4o.Amva=/k, 200 mrem /hr

4. 0, /mm /k,.

10 mrem /hr 8

Top

/.o mr - / A,.

200 mrem /hr N/A 9

Rear Vertical Plane

<. o. 2.=vem / kv 200 mrem /hr

< o. i mve=/ Av 10 mrem /hr 10 Left Side Vertical

/.rmya / hr 200 mrem /hr o.5%r.,/kr 10 mrem /hr 11 Right Side Vertical

/. 6 mr.~ / h r 200 mrem /hr o.4 mre /h,.

10 mrem /hr 12 Bottom

/.o u r a /A, 200 mrem /hr N/A 13 Locomotive 4.o,/mv. /Ar 2 mrem /hr N/A 14 Caboose

<o.1 mre /Av 2 mrem /hr N/A Page /4 of /7

TRAIN CAR NO.

3 RADIATION SURVEY MAP AND RECORD (0.h t,,,( u. loem tiv.)

\\

[

,/

8 r"

I

[F1 1

Il

~

Io]

rm..

3] x-y

/

S S Ls gg i2 CONTAINER ID. Nc.: A/o b la/ w CONTAINER ID. No.: 75oo ic SURVEY INST. NO.: RoAo Nite or7W DATE/ TIME:

7/.u/9p INSPECTOR:

(

No.

LOCATION CONTACT LIMIT 2-METER LIMIT Container No. No d s lo,*, a,.

1 Front Vertical Plane 200 mrem /hr 10 mrem /hr 2

Top 200 mrem /hr N/A 3

Rear Vertical Plane 200 mrem /hr 10 mrem /hr 4

Left Side Vertical 200 mrem /hr 10 mrem /hr 5

Right Side Vedical 200 mrem /hr 10 mrem /hr 6

Bottom 200 mrem /hr N/A Container No. troo/t.

7 Front Vertical Plane 4o.2-vem/Av.

200 mrem /hr 4 o. I %v.~/kv 10 mrem /hr 8

Top o.bmm / br 200 mrem /hr N/A 9

Rear Vedical Plane

< o. A mye-/ x<

200 mrem /hr

<o.Isv.*/Ar 10 mrem /hr 10 Left Side Vertical

o. 4. -=-/ A r 200 mrem /hr o.1myu /Lv 10 mrem /hr 11 Right Side Vertical

o. 7 uve / k,.

200 mrem /hr

o. 3 %va-/ Ar 10 mrem /hr 12 Bottom

<c.2xven/kv 200 mrem /hr N/A 13 Locomotive 2 mrem /hr N/A 14 Caboose 2 mrem /hr N/A Page /7 of

/1

I I

U.S. Nucteer Regul; tory Commission INSPECTION FOLLOW-UP SYSTEM (IFS)

Rrgfon 11 l

POWER REACTOR. FUEL FACILITY & VENDOR DATA ENTRY FORM l

OPEN NEW ITEMS ONLY -(r.on escalated) l s

tlTE NAME: AtS Oo2 WEtt.sedrMM r

N SUBMITTED BY:

I k DATE:

/ d i

REPORT NO.:

UNIT DOCKET NO.:

1 Ph(9F 2

3 DATE:

REVIEWED BY:

,diggp/qjf {fg*g;)g(p,p 3 7 jigi Report Transmittel Date:

Lead Responsible inspector Responsible Org. Code: jguv'ufvlirrTfSigf.Q!

Last Name:

RTTS Inittain:

MStop lier

- r

;, NNdh;N hb kN kNb

kk 3,;

08/21/98

$6 [4 l t.d T T c?

Y I

C N!b. INN @$

IEk Item Seq. No.:

l Item Type:

l Severity Level:

l Supplement No.:

lN$1/8fMMI EA NO.

d i

[ Fill in the EA NO. If opening an

• eel

• Item. The EA NO. can.

y%*!T & Q7?*T'iT:f$ i %g'g{[; "f,j,jdMj}@)

ITEM Unit 1:

Unit 2:

Unit 3:

4 f -

gf4 ""4. i bo obtained from EICS)

STATUS:

w,,,.4; ?. Pr..b..n

,7. a.

v> 4.u I

m uu

,a

. a l

Title:

i l

(I10 Characters Maxi

(

inepectlen Procedure Number:

SALP Functional Area: h Cause Code:

Closeout Org. Code:

hh hhN@[ };;h[g~ThdEh'$$$$$:h[jN[:f['q pi ; w

r ;gDi9a.

ww n

wamm sm..

..fh - w.neu.r may _ _ NOV Summary / Comments: { r l

• NOTE: See back for CODES t

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