ML21189A069

NRC-2021-000173 - Resp 1 - Final. Agency Records Subject to the Request Are Enclosed

ML21189A069
Person / Time
Issue date:	07/07/2021
From:	NRC/OCIO
To:
References
FOIA, NRC-2021-000173
Download: ML21189A069 (28)

Text

6/9/2021 NMED.: Report Single Event Report NMED Item Number: 9.41072 NarraUve: Last Updated: 02/21/1996 A FIRE DUE TOA HYDROCARBON LEAK WHICH IGNITED WAS IN THE PROXIMITY OFA 10 mCi CS-137 SE.ALEO SOURCE. A CONSULTANT RADIATION SPECIALIST WAS SUMMONED TO ASCERTAIN IF THE SOURCE WAS DAMAGE.D. THE LICENSEE. DETERMINE.D THAT THE CS-137 SOURCE. WAS NOT DAMAGED DURING THE FIRE.

AND THAT NO PERSONNEL EXPOSURES OCCURRED . RADIATION SURVEYS HAVE DETERMINED THAT NO RELEASES OCCURRED .. UPDATE: AT 1140 EST, A SECOND FIRE OCCURRED ON A RUPTURED LINE AT THE BOTTOM OF THE "12" PIPESTILL TOWER NEAR A 5 Ci CS-137 SOURCE. THE SOURCE IS LOCATED ON THE SECOND FLOOR OF THE AFFECTED TOWER. THE FIRE WAS EXTINGUISHED DURING THE NOTIFICATION, NO DAMAGE TO THE SOURCE OCCURRED. INITIAL RADIATION SURVEYS IN DI.CATE THAT NO RADI.ATION RELEASE OR PERSONNEL EXPOSURES OCCURRED . THE CAUSE OF THE RUPTURE IS BELIEVED TO BE THERMAL CYCLING OF THE. LINE.S ..

Event Date: 01/23/1994 Date Reported to Agreement State:

Di.scovery Da.te: 01/23/.199.4 Da.te Reported. to NRC: 01/23/1994 Licensee/Reporting Party Information:

Regulated By: NRC Reciprncity: NONE.

License Number: 1.3-25952-01 Name: AMOCO CHEMICAL CO .

NRC Docket Number; 03030725 City: WHITING NRC Program Code: 03120 State: INDIANA NRC Region: 3 Site of Event:

Site Name.: WHITING State: INDIANA Additional Involved Party:

License Number; NA Name: NA NRC Do.cket Number:. NA City: NA NRC Program Code: NA State : NA NRC Region: NA Other Information:

NRC Reportable Event: Y Abnormal Occ.u.rrenc.e.: N Agreement State Reportable Event: N Investigation:

Atomic Energy Act Material: Y Record Complete: Field not used Consu.ltant. Hired : Y Event Closed by Region/State: Y Event Type:

OTH-OTHER Event Cause:

0TH Cause: EXTERNAL/ EXTERNAL FIRE OR EXPLOSION Event IAEA Aggregate Category:.

0TH IAEA Aggregate Category: 3 INon Responsive Record 1/2

6/9/202 1 NMED: Report Corrective Actions Information :

Event Type: Number: Action :

0TH 1 NOT REPORTED.

Source/Radioactive Material Information:

0TH Source Number: 1 Source./Material : SEALED SOURCE GAUGE Radionuclide : CS-137 Manufacturer: NR Activity (Ci): 0.01 Model Number; NR IAEA Category: 5 Seri.a.I Number: NR 0TH Source Number: 2 Source/Material : S.EALED S.OURC.E GAUGE Radionuclide : C.S-.137 Manufacturer: NR Activity (Ci): 5 Model Number; NR IAEA Category: 3 Serial Number: NR Leak Test Results (uCi):

Device/Associated Equipment Information:

0TH De.vice. Number; 1 Device/Equipmemt: GAUGE F.IXED Model Number: NR Manufacturer: NR Serial Number: NR 0TH Device Number: 2 Device/Equipmemt: GAUGE FIXED Model Number:. NR Manufacturer: NR SeriaJ Number: NR Reporting Requirement Information:

~:;;~ Requirement:

30.S0(a) - Event that pre.vents immedi.ate protective actions necessary to avoi.d exposures to radi.ation or.

0TH radioactive materials that could exceed regulatory limits or releases o(material that could exceed regulatory limits.

• Reference Documents:

Reference Document Number:. Entry Date: Retraction D.ate:. Type of Report:

EN26667 05/02/1994 EVENT NOTIFICATION INon Responsive Record 2/2

• • • Net I-er Publie Dietributier1 ***

Event Notification Report U.S. Nuclear Regulatory Commission - Operation Center Event Reports For Last Updated Date (6/24/1985 - 6/24/2021)

Total EN's Returned: 1 EN's Returned:

26667 General Information or Other Event Number: 26667 Facility:AMOCO OIL REFINERY Notifcation Date: 01 /23/1994 Region : 3 State: IN Notification Time: 07:15:00 ET Unit : Event Date: 01/23/1994 RX Type : Event Time : 04 :47:00 EST NRC Notified By: GROVES Last Updated Date : 01 /23/1994 HQ OPS Officer: TIM McGINTY Emergency Class : NON EMERGENCY Person (Organization) :

10 CFR Section ROBERT DEFAYETTE(RDO)

INFORMATION ONLY Event Text 6/24/2021 2:22:23 PM Page 1 of 2

• • • Net I-er PYblie QietribYtieA ***

Event Notification Report U.S. Nuclear Regulatory Commission - Operation Center Event Reports For Last Updated Date (6/24/1985 - 6/24/2021)

HYDROCARBON FIRE IN PROXIMITY TO A 10 mCi CS-137 SEALED SOURCE .

A FIRE DUE TO A HYDROCARBON LEAK WHICH IGNITED IS IN THE PROXIMITY OF A 10 MILLICURIE CS-137 SEALED SOURCE. THE FIRE PRECLUDES BEING ABLE TO TELL WHETHER THE SOURCE IS ACTUALLY INVOLVED OR DAMAGED. FIREFIGHTERS AT THE SCENE ARE BEING MAINTAINED AT A REASONABLE DISTANCE, AND A CONSULTANT RADIATION SPECIALIST HAS BEEN SUMMONED TO ASCERTAIN IF THE SOURCE WAS DAMAGED, WHEN IT WILL BE POSSIBLE TO DO SO.

THE FIRE IS AT THE AMOCO OIL REFINERY, LOCATED AT 2815 INDIANA BLVD, WHITING , INDIANA, 46394. THE FIRE IS "JUST ABOUT UNDER CONTROL", AND AMOCO WILL BE PROVIDING FURTHER INFORMATION ABOUT THE STATUS OF THE SOURCE ONCE IT IS DETERMINED .

• • UPDATE DATE/TIM E: 1/23/94@ 0910 EST ***FROM LICENSEE:GROVES BY :McGINTY **

THE FIRE HAS BEEN EXTINGUISH ED. PRELIMINARY SURVEYS (FROM ABOUT 6 FEET OF THE SOURCE) SHOW THAT THE SOURCE HAS NOT BEEN DAMAGED. THE CONSULTANT WILL BE PERFORMING A LEAK AND WIPE TEST SHORTLY. HOO NOTIFIED R3DO (DEFAYETTE).

• • • UPDATE 01 /23/93 1145EST FROM :GROVES BY:SCARFO * *

• THE LICENSEE DETERMINED THAT THE CS-137 SOURCE WAS NOT DAMAGED DURING THE FIRE AND THAT NO PERSONNEL EXPOSURES OCCURRED. RADIATION SURVEYS HAVE DETERMINED THAT NO RELEASES OCCURRED .

R3DO(DEFAYETTE) NOTIFIED.

• • • UPDATE 01 /23/93 1412EST FROM :MANSUETO BY:SCARFO * **

AT 1140EST, A SECOND FIRE OCCURRED ON A RUPTURED LINE AT THE BOTTOM OF THE "12" PIPESTILL TOWER NEAR A 5-CURIE CS-137 SOURCE. THE SOURCE IS LOCATED ON THE SECOND FLOOR OF THE AFFECTED TOWER.

THE FIRE WAS EXTINGUISHED DURING THE NOTIFICATION. NO DAMAGE TO THE SOURCE OCCURRED. INITIAL RADIATIOI\J SURVEYS INDICATE THAT NO RADIATION RELEASE OR PERSONNEL EXPOSURES OCCURRED. THE CAUSE OF THE RUPTURE IS BELIEVED TO BE THERMAL CYCLING OF THE LINES . R3DO(DEFAYETTE) NOTIFIED.

6/24/2021 2:22:23 PM Page2of2

Consultants to Nuclear Medicine

• Radiology

• Nuclear Industry STAN A. HUBER CONSULTANTS, INC. 0 200 NORTH CEDAR ROAD O NEW LENOX. IL 60451 0 (815) 485-6161 0 FAX (815) 485-4433 January 24, 1994 Don Groves safety Specialist Amoco Oil Company Whiting Refinery 2815 Indianapolis Blvd.

Post Office Box 710 Whiting, Indiana 46394-0710

Dear Don:

This is a summary of our emergency response visits on Sunday, January 23, 1994 following two separate fires at the Whiting Refinery, in which the integrity of seven (7) nuclear gauges needed to be checked. There was an earlier third fire in which nuclear gauges were not included.

We responded to the first fire at 6:00 A.M. (arriving at Amoco about 1 1/2 hours later) and surveyed and wipe tested four (4) nuclear gauges. We had just returned to our facility around Noon and unloaded supplies and performed the leak tests on the four (4) gauges when Dan Mansueto called us to respond to a second fire. When we arrived, we gave Dan the leak test reports on the first four (4) gauges. (You and Dan had called NRC-Washington to alert that agency to the incident as the local NRC was not reachable. )

In the afternoon response, we surveyed and wipe tested three (3) additional nuclear gauges and performed the analyses upon return to our lab and faxed the results to you as soon as we completed those analyses. Hard copy originals of the final three (3) leak test reports are enclosed, so you can discard the certificate copies of the second batch of three (3) leak tests that we faxed to you.

Also enclosed with this report are the radiation survey results that we took upon surveying the nuclear gauges that we wipe tested. The shutters on all seven (7) gauges were also checked as operating properly.

During our afternoon visit, we also checked out a small concrete building next to a relatively new construction, in which it was thought that an instrument (analyzer) was present which may contain a nuclear source. That building was close to the first fire. However, upon checking that device, we found that it was an x-ray analyzer and was in good shape. Although this unit

Page 2 required no wipe testing, you asked that we plan to check that x-ray unit in the same manner that we check other x-ray units at Amoco, during our next regular visits. I made a note to add this new unit to our schedules.

On the day following this visit, I called for you to suggest that local NRC be called about the incident, even though NRC Washington, o.c. had been notified, since the local NRC issues Amoco's nuclear licenses. Shirley said she had the local NRC phone numbers and would relay my suggestion to you. Shirley also told me to use our existing contract Purchase Order number for the emergency response visits we had made.

During our visits, you indicated there were 12 nuclear gauges in storage and I suggested that you ask Kay Ray about gauge return instructions when they visit your facility this week . Nuclear disposal options are becoming less available and prices are almost certain to escalate in 1994, if disposals (returns) can even be made at all due to site closings. If we 'can assist with transfer of the gauges or related matters, please call us.

Thank you again for the opportunity to be of service. Please call if there are any questions or nuclear concerns in the follow-up to these fire incidents.

Sincerely,

~A~

Stan A. Huber President SAH: ac enclosures

STAN A. HUBER CONSULTANTS, INC.

200 NORTH CEDAR ROAD- NEW LENOX IL 60451-1751-PHONE 815-485-6161 REPORT DATE: 01-24-94 FACILITY: AMOCO OIL COMPANY WHITING IN NRC LICENSE NUMBER: 13-00155-12 RADIATION SURVEY READINGS TAKEN FOLLOWING FIRE INCIDENTS ON 1-23-94 SURVEY METER READINGS MAXIMUM INVENTORY EXPOSURE EXPOSURE WIPE TEST NUMBER ACTIVITY MODEL# SERIAL# SURFACE 1 FOOT RESULTS W-309 100 mCi NIA 9381 1.3 mR/hr 0.3 mR/hr < 0.000001 UCi W-313 3Ci 7064 9376 2.0 mR/hr 0.8 mR/hr 0.000002 uCi W-370 10 mCI 7064 9379 0.2 mR/hr .07 mR/hr < 0.000001 uCi W-371 10 mCi 7062P 10444 0.2 mR/hr .07 mR/hr 0.000018 uCi W-384 5Ci 7064 13089 5.2 mR/hr 1.5 mR/hr 0.000042 uCi W-386 5Ci 7064 13089 3.5 mR/hr 1.6 mR/hr 0.000044 uCi W-387 3Ci 7064 13091 1.5 mR/hr 0.9 mR/hr 0.000048 uCi N,O fES: Afl Of The Above Gauges Are Manufactured By Kay Ray And Contain Cs-137 Sources SURVEY INSTRUMENT USED: LUDLUM MODEL 14 C SERIAL# 95056 calibrated on 10-13-93 CONCLUSIONS: 1.) THE RADIATION SURVEY READINGS LISTED ABOVE ARE SIMILAR TO ROUTINE SEMI-ANNUAL RADIATION SURVEY RESULTS AND SHOW NO BREACH OF INTEGR:I TY OF THE LEAD SHIELDS IN THE NUCLEAR GAUGES.

2.) THE WIPE TEST RESULTS LISTED ABOVE CONFIRM THAT THE NUCLEAR GAUGES WHICH MAY HAVE SEEN EXPOSED TO THE FIRE ARE NO,T LEAKING. REMOVABLE CONTAMINATION IS LESS THAN (0.005 uCi ) *

( SEE SEPARATE LEAK TEST CERTIFICATES FOR EACH GAUGE, FOR MORE INFORMATION)

Submitted by: ~~ ,44c_

S. A. HUBER NUCLEAR CONSUL TANT

STAN A. HUBER CONSULTANTS, INC.

200 NORTH CEDAR ROAD - NEW LENOX IL 60451-1761 - PHONE 815-485~161 SEALED GAMMA/BETA SOURCES - LEAK TEST CERTIFICATE REPORT DATE: 01 ~23-94 FACILITY: AMOCO OIL COMPANY WHITING IN NRC LICENSE NUMBER: 13--00155-12 STATE LICENSE NUMBER:

SOURCE IDENTIFICATION:

RADIONUCLIDE Cs-137 ACTIVITY: 5 Ci CALIBR. DATE:

MANUFACTURER: KAY RAY MODEL NUMBER: 7064 SERIAL NUMBER: 13089 OTHER DESCRIPTION: W-384 ASSAY RESULTS:

COUNTING EFFICIENCY: 0.244 BACKGROUND AT TIME OF ASSAY: 46 MAX CPM NETCPM DPM ACTIVITY uCi WET WIPE 69 23 94 0.000042 DRY WIPE 50 4 16 0.000007 ANALYSIS OF RESULTS:

Sources are not leaking at this time Removable contamination Is less than 5E-3 uCI. (.005)

NEXT LEAK TEST DUE: 06-94 LEAK TEST PERFORMED BY: J M AHRWEILER DATE: 01-23-94 ANALYSIS PERFORMED BY: SA HUBER~ DATE: 01-23-94 RADIATION SAFETY OFFICER SIGNATURE:

STAN A. HUBER CONSULTANTS, INC.

200 NORTH CEDAR ROAD - NEW LENOX IL 60451-1751 - PHONE 815-485-6161 SEALED .G AMMA/BETA SOURCES - LEAK TEST CERTIFICATE REPORT DATE: 01-23-94 FACILITY: AMOCO OIL COMPANY WHITING IN NRC LICENSE NUMBER: 13-00155-12 STATE LICENSE NUMBER:

SOURCE IDENTIFICATION:

RADIONUCLIDE Cs-137 ACTIVITY: 5 Ci CALIBR. DATE:

MANUFACTURER: KAY RAY MODEL NUMBER: 7064 SERIAL NUMBER: 13089 OTHER DESCRIPTION: W-386 ASSAY RESULTS:

COUNTING EFFICIENCY: 0.244 BACKGROUND AT TIME OF ASSAY: 46 MAX CPM NETCPM DF>M ACTIVITY uCI WET WIPE 64 18 74 0.000033 DRY WIPE 70 24 98 0.000044 ANALYSIS OF RESULTS:

Sources are not leaking at this time Removable contamination is less than SE-3 uCi. (.005)

NEXT LEAK TEST DUE: 06-94 LEAK TEST PERFORMED BY: J M AHRWEILER DATE: 01 94 ANALYSIS PERFORMED BY: SA HUBER -5,f ff DATE: 01-2J.94 RADIATION SAFETY OFFICER SIGNATURE:

STAN A. HUBER CONSULTANTS, INC.

200 NORTH CEDAR ROAD - NEW LENOX IL 60451-1751 - PHONE 816-485-e161 SEALED GAMMA/BETA SOURCES - LEAK TEST CERTIFICATE REPORT DATE: 01-23-94 FACILITY: AMOCO OIL COMPANY WHITING IN NRC LICENSE NUMBER: 13-00155-12 STATE LICENSE NUMBER:

SOURCE IDENTIFICATION:

RADIONUCLIDE Cs-137 ACTIVITY: 3 Ci CALIBR. DATE:

MANUFACTURER: KAY RAY MODEL NUMBER: 7064 SERIAL NUMBER: 13091 OTHER DESCRIPTION: W-387 ASSAY RESULTS:

COUNTING EFFICIENCY: 0.244 BACKGROUND AT TIME OF ASSAY: 46 MAX CPM NETCPM DPM ACTIVITY uCi WET WIPE 72 26 107 0.000048 DRY WIPE 58 12 49 0.000022 ANALYSIS OF RESULTS:

Sources ere not leaking et this time Removable contamination is less than 5E-3 uCi. (.005)

NEXT LEAK TEST DUE: 06-94 LEAK TEST PERFORMED BY: J M AHRWEILER DATE: 01 94 ANALYSIS PERFORMED BY: SA HUBER .fA-1.1. DATE: 01-23-94 RADIATION SAFETY OFFICER SIGNATURE:

DEC 151994 Amoco Oil Company Whjting Refinery ATTN: Julie G. Murphy Environmental Health and Safety Manager 2815 Indianapolis Blvd.

Whiting, IN 46394

Dear Ms. Murphy:

This refers to the routine safety inspection conducted by Robert Gattone of this office on October 28, 1994, of activities authorized by NRC Byproduct Material License No. 13-00155-12, and to the discussion of our findings with you at the conclusion of the inspection.

The inspection was an examination of activities conducted under your license as they relate to radiation safety and to compliance with the Commission's rules and regulations and with the conditions of your license. The inspection consisted of a selective examination of p.rocedures and representative records, observations, independent measurements, and interviews with personnel.

No violations of NRC re-quirements were identified during the course of this inspection.

Two areas of concern were identified during the inspection. The first concern is that some of your gauges {e.g., W-413 and W-431) are mounted on an angle resulting in a gap of about 8 inches between the gauges and the vessels. This gap is large enough for an individual to place his/her extremity directly into the beam and possibly receive a radiation exposure in excess of regulatory limits. We are also concerned that, at the time of the inspection; you had not evaluated the potential change in the gauges' operating environment as a result of installation of fireboxes. Some gauges are mounted on vessels that contain materials heated to high temperatures. It is conceivable that heat from these vessels may be concentrated in the firebox and damage the gauge's source housing. Please address these concerns by responding to the following:

(1) describe the actions you have taken or will take to ensure individuals cannot access radiation beams; and {2) submit verification that gauges enclosed in fireboxes are operated in environments which satisfy manufacturer reconvnendations. Your response is requested within 30 days of the date of this letter.

In accordance with 10 CFR 2.790 of the Comm*i ssion's regulations, a copy of this letter and your response to this letter will be placed in the NRC Public Document Room.

9412270043 941215 PDR ADOCK 03004326 C PDR

DEC 5 1994 Amoco Oil Company The response requested by this letter is not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, Pl 96-511.

We will gladly discuss any questions you have concerning this inspection.

Sincerely, Oritinal Sit.ned by 8. J. Holt B. J. Holt, Chief Nuclear Materials Inspection Section 1 License No.: 13-00155-12 Docket No.: 030-04326 bee: PUBLIC DOCUMENT NAME: G:\INSPRPTS\MTLS\030\03004326.941 To ,ecalve

• oopy of tin doou-nt. lncloat* In th* boa.: *c*

• Copy without attechment/encio.ure "E"

• Copy with attachment/enclo1ure "N"

• No copy OFFICE DRSS/RIII DRSS/R DATE 12/

APPENDIX E NOTE: All areas indicated in field notes are not required to be addressed during each inspection INDUSTRIAL/ACADEMIC/RESEARCH INSPECTION FIELD NOTES Region III Inspection Report No.94-001 License No. 13-00155-12 Licensee (Name & Address): Docket No. 030-04326 Amoco Oil Company Whiting Refinery 2815 Indianapolis Blvd.

Whiting, IN 46394 Licensee Contact Donald Groves, RSO Telephone No. 219-473-3039 Last Amendment No. 44 Date of Amendment 11-3-93 Priority: 5 Program Code 03120 Date of Last Inspection 4-8-76 Date of This Inspection 10-28-94 Type of Inspection: ( ) Announced (x) Unannounced (x) Routine ( ) Special

( ) Initial (x) Reinspection Next Inspection Date 10-99 (x) Normal ( ) Reduced ( ) Extended Summary of Findings and Action:

( ) No violations cited, Clear 591 issued

( ) Violation(s), 591 issued (x) Areas of Concern, Regional letter issued

( ) Followup on Previous Violations Were non-cited violations identified during this inspection? ( ) Y (x) N was proprietary information reviewed by or received by the inspector? ( ) Y (x) N Inspector:

Issue Date: 03/07/94 E-1 87100, Appendix E

Approved, /

l

-,;:,;_~£ ~

~ ~ ( .,.__..

gn~

- a~ure--)

t - -

Date NOTE& "HR" MEANS "NOT REVIEWED"

1. INSPECTION HISTORY ( ) N/A - Initial inspection A. Viol ations were identif ied during any of the last two inspections or two years , whichever is l onger ( ) Y (x) N B. Res ponse letter(s) or 59l(s) dated

c. Open violations from previous inspections: (x) N/A Status Requirement Violation Corrective Action Taken IY/Nl Open/Closed D. Explain any previous violation(s) not corrected or repeated (x) N/A

2. ORGANIZATION AND SCOPE OF PROGRAM A. Organizational Structure

+*Julie G. Murphy, Environmental Health and Safety Manager

+*Donald R. Groves, Environaental, Health, and Safety Coordinator, RSO

+*Dan Mansueto, Safety Specialist, Assistant RSO

+Eileen Smith, Shipping and Receiving

+Larry Hinson, Electrical Repairman

+Mark Yarichak, Metallurgic Inspector

+Dan Stolarz, Metallurgic Inspector

+ Individuals contacted during inspection

• Individuals present at exit meeting

1. Meets license requirements (L/C] (x) Y ( ) N

2. Multiple authorized locations of use and/or laboratories ( ) Y (x) N If yes, may use ATTACHMENT A as a guide for location(s) or lab(s) inspected and note lab numbers where violations are found. (x) N/A

3. Briefly describe scope of activities, including types and quantities of use involving byproduct material, frequency of use, staff size, etc.

The licensee is the fifth largest oil refinery in the world . It proce:sses over 450,000 barrels of oil per day, and! possesses over 100 devices containing byproduct material, Approximately 20 di£ferent models of devices are possessed. The vast majority of devices are fixed level gauges, Some devices are metallurgic analyzers and gas chroaatographa. The RSO and bis assistant supervise relocations a .a authorized.

B. Radiation Safety Committee required (L/C] ( ) Y (x) N 87100, Appendix E E-2 Issue Date: 03/07/94

1. RSC fulfills license requirements [L/C] y N

2. Records maintained [L/C) y N

c. Radiation Safety Officer

1. Authorized on license [L/C] (x) y N

2. Fulfills duties as RSO (x) y N D. Use by authorized individuals [L/C ] (x) y N Remarks:

3. TRAINING , RETRAINING, AND INSTRUCTIONS TO WORKERS A. Instructions to workers/students per [10 CFR 19 . 12) (x) Y ( N B. Training program required [L/CJ (x) y ( N

1. If so, briefly describe training program:

Individuals assisting with device relocations must be trained by an authorized user regarding radiation safety, biological effects of radiation and types o f radiation, Based on inspector interview of an individual who had assisted with a device relocation, i t appeared that the individual had recei.ved appropriate trainin,g from the authorized user.

2. Training program implemented (X) Y ( ) N

3. Periodic training program required ( ) Y (x) N

4. Periodic training program implemented (x) Y ( ) N

s. Records maintained (x) Y ( ) N

c. Individuals understanding of procedures and Regulations is adequate (x) Y N

1. current operating procedures (x) Y N

2. Emergency procedures (x) Y N

3. Use of survey instrumentation (x) y N D. Revised Part 20 Workers cognizant of requirements for:

1. Radiation Safety Program [20 .1101] NR y ( ) N

2. Annual dose limits [20. 1301, 1302] Y (X) N

3. New forms 4 and 5 NR ( ) y N ( ) N/A

4. 10% monitoring threshold [20.1502] NR y ( ) N Based on the inspection, the likelihood of an individual exceeding 10 % of the dose limits was remote, ~herefore, this area was not reviewed.

5. Dose limits to embryo/fetus and declared pregnant worker [20.1208) Y (x) N

6. Grave Danger Posting [20.1902) ( ) Y N (x) N/A Issue Date: 03/07/94 E-3 87100, Appendix E

7. Procedures for opening packages (20.1906] y N (x) N/A

8. Sewer disposal limits [20.2003] y N (X) N/A Deficiencies in this area, while not always a violation, should be brought to the attention of licensee management at the exit meeting and in the cover letter transmitting the inspection report or NOV.

Remarks:

The inspector diacuaaed applicable portion* of Part 20 with the licensee as they applied to its program.

4. INTERNAL AUDITS, REVIEWS OR INSPECTIONS A. Audits are required [L/C) y (x) N B. Audits or inspections are conducted y (x) N

( 1) Audits conducted by (2) Frequency

c. content and implementation of the radiation protection program reviewed annually by the licensee [20.llOl(c)) ( y N NR D. Records maintained [20.2102] NR ( ) y N

s. FACILITIES A. Facilities as described in license application [L/CJ (x) Y ( ) N B. Describe any Self-contained dry-source-storage irradiators [Part 36] and/or survey instrument calibrators (model, radionuclide, activity, use, etc.)(x) N/A

1. Maintenance of safety-related components performed by authorized persons (L/C] y N

2. Access to keys and/or material controlled

[20.1801, 1802, L/C] y N

3. Access to high/very high radiation areas controlled (20.1601, 1602, L/C] y N

4. Adequate protection of shield integrity, fire protection (L/C] y N Remarks:

6. MATERIALS A. Isotope, chemical form, quantity and use as authorized (L/C] (x) Y N

8. Licensed materials secured to prevent unauthorized removal or access (20.1801, 1802] (X) y N The inspector toured the gauge storage facility and determined that the gauges were 87100, Appendix E E-4 Issue Date: 03/07/94

properly secured by padlock within a fenced-in area. The only key was issued to an authorized user.

The inspector surveyed the storage area and measured a maximum of 0.4 mR/hr 30 centimeters from the fence (bkg was< 0.05 mR/hr),

C. Leak tests and Inventories [L/C)

1. Performed as required (x) Y ( ) N ( ) N/A The licensee contracts Stan Buber consultants to perform 6 month leak tests, shutter checks and physical inventory of all licensed material. Based on inspector review of a random sample of records and interview with licensee personnel, the licensee appeared to be in compliance with the required tests/checks.

The licensee assigns numbers to each gauge to quickly reference it on leak test/inventory records. The inspector randomly verified the accuracy of the licensee's inventory control system.

2. Adequate analysis methodology and sensitivity (x) Y ( ) N N/A

3. Records maintained [L/C) (X) y N Remarks:

7. RADIATION SURVEYS A, Instruments and equipment:

1. Appropriate operable survey instrumentation possessed and readily accessible [L/C) (x) y ) N

2. Calibrated as required [20.1501, L/C] (x) Y ) N

3. Calibration records maintained (20.2103(a)) (x) Y ) N The licensee possesses the following survey instruments:

o Eberline MN 130-A, SH 8316, Calibrated on 1-15-94, Range: 1-1000 mR/hr o Eberline MN 130-A., SN 8317, Calibrated on 1-15-94, Range: 1-1000 mR/br o Eberline MN ESP, SN 1902, Calibrated on 1-15-94 Based on the inspector's random record review and staff interviews, the licensee possessed appropriate instrumentation and demonstrated proper use of it.

Calibrations are performed annually by Stan Buber Consultants.

B. Briefl y describe area survey requirements [20 .lSOl(a), L/C)i The licensee is required to perform surveys to ensure proper installation of gauges. Based on inspector interviews of personnel, t~e licensee performs appropriate surveys of each device immediately after completion of device installation to ensure radiation levels are as expected. If radiation levels exceed what is expected , the area would be re,s tricted and the RSO would be contacted.

Issue Date: 03/07/94 E- 5 87100, Appendix E

c. Performed as required (20.lSOl(a), L/C] (X) y N

1. Contamination found (x) Y ( ) N

2. Corrective action taken and docUI11ented (x) N/A( ) Y ( ) N The last leak test wa performed on 6-22-94, and all results were below 0.005 microcuries.

D. Records maintained (20.2103, L/C] (x) Y ( ) N E. Protection of members of the public

1. Licensee made adequate surveys to demonstrate either (l) that the TEDE to the individual likely to receive the highest dose does not exceed 100 mrem in a year, or (2) that if an individual were continuously present in an unrestricted area, the external dose would not exceed 2 mrem in any hour and 50 mrem in a year (20.130l(a)(l), 1302(b)) ( ) Y ( ) N NR

2. Unrestricted area radiation levels do not exceed 2 mrem in any one hour (20.130l(a)(2)) (x) Y N

3. Records maintained (20.2103, 2107) NR ( ) Y N Remarks:

8. RADIOACTIVE WASTE ( ) N/A All radioactive waste ii transferred to an authorized recipient (e.g.,

manufacturer).

A. Disposal ( ) N/A

1. Decay-in-storage (x) N/A

a. Procedures approved [20.200l(a)(2), L/C] ) y ( N

b. In accordance with (L/C) ) y ( N

c. Labels removed or defaced [20.1904(b)) ) y ( N

2. Special procedures performed as required (L/C) ( ) y ( N (x) N/A

3. Liquid scintillation (LS) media and animal carcasses per [20.2005) ) y ( ) N (x) N/A

4. Improper/unauthorized disposals [ 20 :2001) ( ) y (x) N

5. Records maintained [20.2103(a), 2108, L/C) (x) y ( ) N B. Effluents (x) N/A

1. Release into sanitary sewer (20.2003) ( ) y ( ) N ( ) N/A

a. Material is readily soluble or readily dispersible [20.2003(a)(l)] y N

b. Monthly average release concentrations do not exceed Appendix B values [20.2003) y N

c. No more than 5 Ci of H-3, 1 Ci of C-14 87100, Appendix E E-6 Issue Date: 03/07/94

and 1 Ci of all other radionuclides combined released in a year [20.2003] ) y ( ) N

d. Procedures to ensure representative sampling and analysis properly implemented

[20,150l(a)(2), L/C] ( y N

2. Release to septic tanks [20.2003] ( ) y N N/A

a. Within unrestricted limits [App B,Table 2]( y N

3. Waste incinerated ( ) y N N/A

a. License authorizes [20.2004(a)(3)] y { N

b. Licensee directly monitors exhaust y ( N

c. Airborne releases evaluated and controlled

[20.1501, 1701] y N

4. Control of effluents and ashes [20.1201, 1301, 1501, 2001, L/C] {See also IP 87102, RG 8.37} y ( ) N

c. Waste Management N/A

1. Waste compacted [L/CJ y (x) N

2. Storage area(s) N/A

a. Protection from elements and fire [L/C) (x) y ( ) N

b. Control of waste maintained (20.1801] (x) y ( ) N

c. containers properly labeled and area properly posted [20.1902, 1904] (x) y N d, Package integrity maintained [L/C) (x) y N

3. Packaging, Control and Tracking (App. F.III]

(20.2006(d)):

Note: The licensee's waste is likely to be Class A.

a. Not packaged for disposal in cardboard or fiberboard boxes (61.56(a)J (x) Y ( ) N b, Liquid wastes solidified, i . e., less than 1% freestanding liquid, and void spaces minimized [61.56(a), (b)] (x) N/A( ) Y ( ) N

c. Does not generate harmful vapors [61.56] (x) Y ( ) N

d. Structurally stable (will maintain its physical dimensions and form under expected disposal conditions) (61.56(b)J (x) Y N

e. Packages properly labeled (App. F.III,A,2](x) Y N f, Licensee conducts a QC program to ensure compliance with [ 61. 55, 56) and includes management evaluation of audits

[App. F.III.A.3] NR ( ) Y ( ) N

g. Shipments not acknowledged within 20 days after transfer are investigated and reported [App. F,III.A.8) NR ( ) Y ( ) N ( ) N/A

4. Transfers to land disposal facilities (x) N/A Issue Date: 03/07/94 E-7 87100, Appendix E

a. Transferred to person specifically licensed to receive waste (30.41, 20.200l{b)] { ) y { ) N

b. Each shipment accompanied by a manifest prepared as specified in Section I of Appendix F [20.2006(b), App. F.III.A.4] y N

c. Manifests certified as specified in Section II of Appendix F [20.2006{c)} y N

o. Records of surveys and material accountability are maintained (20.2103, 2108} NR ()Y{)N Remarks:

9. RECEIPT AND TRANSFER OF RADIOACTIVE MATERIAL A. Describe how packages are received and by whom: { ) N/A Based on i.nspector interviews of licensee personnel, the licensee receives all packages in a central location, Receiving staff receive training to recognize hazardous material shipments via paperwork review. Upon receipt of a package containing radioactive material, the staff are instructed to call the safety office (RSO).

B. Written package opening procedures established and followed [20.1906(e)) NR y N

c. All incoming packages with DOT l a b e l s ~ . unless exempted (gases and special form) [20.1906(b)(l)]NR y N

o. Incoming packages surveyed per [20.1906(b){2)] NR y N E. Monitoring in {c) and (d) performed within time specified [20.l906{c)) NR y N F. Transfer(s) between licensees performed per [30.4l]NR y N G. All sources surveyed before shipment and transfer

[20.lSOl(a), 49 CFR l73.47S(i), L/C) NR y N H. Records of surveys and receipt/transfer maintained

[20.2103(a), 30,51] NR y N I. Transfers within licensee's authorized users or locations performed as required [L/C) NR { ) Y N N/A J. Arrangements made for Type A packages [20.1906{a)J y N K. Package receipt/distribution activities evaluated for compliance with 20.1301 (20.1302] NR { ) Y N N/A Remarks:

10. TRANSPORTATION (10 CFR 71.S(a) and 49 CFR 170-189) (x) N/A A. Licensee shipments are:

delivered to common carriers transported in licensee's own private vehicle both no shipments since last inspection 87100, Appendix E E-8 Issue Date1 03/07/94

B. HAZMAT training (172.700-704] y ( ) N

c. Packages N/A

1. Authorized packages used [173.415, 416(b)J y ( ) N

2. Performance Test records on file N/A

a. Special Form Sources [173.476(a)] y ( ) N

b. DOT-7A packages (173.41S(a)J y ( ) N

3. coca on file with NRC for Type B [71.12(c)(l)] y N

4. Two labels (White-I, Yellow-II, Yellow-III) with TI, Nuclide, Activity, and Hazard Class

[172.403, 173.441] y ( ) N

s. Properly marked (Shipping Name, UN Number, Package Type, RQ, "This End Up" (liquids), Name and Address of consignee) [172.301,306,310,312,324] y N

6. Closed and sealed during transport (173.475(f)J y N D. Shipping Papers N/A

1. Prepared and used [172.200(a)J Y ( ) N

2. Proper {Shipping name , Hazard Class, UN Number, Quantity, Package Type, Nuclide, RQ, Radioactive Material, Physical and chemical form, Activity, Category of label, TI, Shipper's Name, certification and Signature, Emergency Response Phone Number, "Limited Quantity" ( if applicable), "Cargo Aircraft Only" (if applicable)} (172.200-204] ( Y N

3. Readily accessible during transport [177.718(e)]( Y N E. Vehicles N/A

l. Placarded [172.504] y N

2. Cargo blocked and braced [l77.842(d)J y N

3. Proper overpacks (shipping name, UN Number, labeled, statement indicating that inner package complies with specification packaging)

[173 . 25] y N F. Any incidents reported to DOT (171.15, 16) y N Remarks:

11. PERSONNEL RADIATION PROTECTION A. Licensee pe*rformed exposure evaluation [ 20. 1501] (X) y N B. Licensee in.c orporated ALARA considerations in the Radiation Protection Program (20.llOl(b)J (x) Y ( N

c. External Dosimetry ( ) N/A

l. Licensee monitors workers [20.1502(a), L/C] (x) Y ( ) N Based on inspector staff interviews and random record reviews, the licensee assigns film badges to individuals involved with device relocations, Issue Date: 03/07/94 E-9 87100, Appendix E

2, External exposures account for contributions from airborne activity (20.1203] ( ) y ( ) N (x) N/A

3. Supplier Landauer Frequency Monthly

4. Supplier is NVLAP-approved (20,lSOl(c)J (X) y N

5. Dosimeters exchanged at required frequency (L/C] (x) y N D. Internal Dosimetry (x) N/A

l. Licensee monitors workers [20.1502(b), L/C) ()Y()N

2. Briefly describe licensee's program for monitoring and controlling internal exposures (20.1701, 1702, L/C]:

3. Air sampling performed y N

4. Monitoring/controlling program implemented y N

5. Respiratory protection equipment [20.1703, L/C] y N E. Reports N/A l, Reviewed by Dan Mansueto Frequency Upon receipt

2. Inspector reviewed personnel monitoring records for period (to 9-94).llli 12..ll WB max (mrem) M 10

3. Prior dose determined for individuals likely to receive doses [20.2104] NR ()Y()N

4. Maximum exposures TEDE Othe.r

s. Maximum CDEs Organs

6. Maximum CEDE

7. Licensee ,sums internal and external (20.1202) ( ) y ( N (x) N/A

8. TEDEs and TODEs within limits (20 . 1201] (x) y ( ) N

9. NRC Forms or equivalent (20 .2104( d), 2106(c)JNR

a. NRC-4 y N Complete: y N

b. NRC-5 y N Complete: y N

10. Worker declared her pregnancy in writing during inspection period (review records) NR ( ) Y N N/A If yes, licensee in compliance with (20 . 1208] y N and records maintained (20.2106(e)J y N F. Who performed PSEs at this facility (number of people involved and doses received) [20.1206, 2104, 2105, 2204] (x) N/A G. Records of exposures, surveys, monitoring, and e~aluations maintained (20.2102, 2103, 2106, L/CJ (x) Y ( ) N Remarks:

87100, Appendix E E-10 Issue Date: 03/07/94

12. NRC INDEPENDENT MEASUREMENTS A. Survey instrument Serial No . Last calibration Ludlum Model 3 109308 1-21-94

a. Inspector's measurements were compared to licensee's (x) Y ( ) N

c. Describe the type, location, and results of measurements:

The inspector performed surveys of all the devices that were inspected and accessible. Devices that were inspected are highlighted in yellow in the attached leak teat record dated 6-22-94. Except for one device (reference Item 18), all devices bad radiation dose rates that were less than 2 mR./hr at 30 centimeters from the device.

13. NOTIFICATION AND REPORTS ( ) N/A A, Licensee in compliance with (19 . 13, 30.50) (reports to individuals,public and occupational, monitored to show compliance with Part 20) NR ( y N ( ) N/A B. Licensee in compliance with (20.2201, 30.50)

(theft or loss) y N (X) None

c. Licensee in compliance with [20.2202, 30.50)

(incidents) (x) y N ( ) None The licensee had a fire on 1-23-94, and it reported the incident to NRC Headquarters on the same day. The licensee opted to be conservative regarding NRC notification since the fire was lim.ited to the vicinity of several gauges. The gauges involved were inventory numbers W-384, W-385, W-386, W-387, W-309, W-313, W-370 and W-371 (these devices are highlighted with a pink mark on the attached leak test record dated 6-22-94). The gaug*e s were located downwind of the fire, and W-309 was the closest to the fire. At the time of the inspection, gauges W-384, W-385, W-386 and W-387 were in the storage room. Gauges W-309, W-313, W-370 and W-371 were in use at the time of the inspection.

The fire was extinguished quickly, and the licensee hired Stan Buber Consultants to evaluate the status of the aforementioned gauges on 1-23-94, The consultant performed ambient dose rate surveys and leak tests on the gauges, and provided a report dated 1-24-94 (attached) indicati.ng no evidence of gauge damage. The licensee called NRC Headquarters to report no damage was done to the gauges, and NRC said no additional information is required, The inspector measured less than 2 mR/hr at 30 centimeters from gauges W-309, W-370 and W-371 , Gauge W-313 was not surveyed due to relative inaccessibility. The inspector reviewed leak test records for the aforementioned gauges to verify the results were negative, Based on the inspector's review of the licensee's response, no violations were identified.

o. Licensee in compliance with [20 . 2203, 30 . 50)

(overexposures and high radiation levels) ( ) Y ( ) N ( x) None E. Licensee aware of NRC Ops Center phone number (X) Y ( ) N

14. POSTING AND LABELING Issue Date: 03/07/94 E-11 87100, Appendix E

A. NRC-3 "Notice to Workers" is posted (19.11] (x) Y ( ) N B. Parts 19, 20, 21, Section 206 of Energy Reorganization Act, procedures adopted pursuant to Part 21, and license documents are posted or a notice indicating where documents can be examined is posted [19.11, 2l.6JNR ( ) Y N

c. Other posting and labeling per [20.1902, 1904]

and the licensee is not exempted by [20.1903, 1905) (x) Y N of the many gauges inspected, all had legible labels/postings.

Remarks:

15 . RECORDKEEPING FOR DECOMMISSIONING NR ( ) N/A A. Records of information importa.n t to the safe and effective decommissioning of the facility maintained i n an independent and identifiable location until license termination [30,JS(g)J ( y ( N B. Records include all information outlined in [30.JS(g)J( y ( N Remarks:

1 6. BULLETINS AND INFORMATION NOTICES A. Bulletins, Information Notices, NMSS Newsletters, etc., received by the Licensee (x) Y N B. Licensee took appropriate action in response to Bulletins, Generic Letters, etc. (x) Y N Remarks:

17. SPECIAL LICENSE CONDITIONS OR ISSUES (x) N/A A, Special license conditions or issues to be reviewed :

B. Evaluation:

18. CONTINUATION OF REPORT ITEMS ( ) N/A 1, Gauges W-413 and W-431 are mounted on an angle. A gap of about 8 inches exists between the gauges and the vessels. This gap is large enough for an individual to place his/her extremity directly into the beam. The inspector measured 2 mR/hr at 30 centimeters from the surface of W-413 (Note: W-431 was relatively inaccessible) and greater than 200 mR/hr in the beam.

Inspector calculations determined that the dose rate to an extremity placed 87100, Appendix E E-12 Issue Date: 03/07/94

in the beam close to the source would be approximately 21 R/hr. Based on the inapector' s observation a, peraoDDel interviews, and calcul.a tions, the likelihood of an individual placing his extremity in the beam and receiving a dose in excess of Part 20 liaits is remote. The gauges are located in relatively remote, inaccessible locations and there is no reason why anybody would place his extremity in the beam.

The inspector discussed the aforementioned concern with the licensee, and it agreed to examine ways to prevent individuals from placing their extreaitie"*.~>..~'

in the beam. / 1'.o ~~

2. The gauges are covered with aluminum fireboxes to prevent f.lre damage. ~ '

However, based on personnel interviews, it appeared the licensee had not - ~

evaluated the potential of gauge damage due to the firebox concentrating heat around the gauge in the event of vessel failure, and subsequent release of heat into the firebox. Al.though most of the gauges inspected did not appear to be adjacent to vessels containing hot contents, some were (e.g.,

W-318).

3. On the diy of the inspection, the licensee was responding to an event that occurred on 10-27-94, involving a spil1 of 23 barrels of oil into Lake Michigan. The incident did not involve radioactive material. The licensee informed the inspector that the NRC inspection did not interfere with its response to the event.

4. All gauge lock outs are performed by Dan Mansueto. Mr. Mansueto demonstrated appropriate lockout of randomly selected gauges.

5, In September 1994 authorized licensee personnel removed and reinstalled 8 gauges for servicing by Kay Ray. !the inspector surveyed one of these gauges (i.e., W-397) and measured 1,2 mR/hr at 30 c from the gauge. An authorized user demonstrated appropriate survey and lock out of the device.

19. VIOLATIONS, NCVs, AND OTHER ISSUES ( ) N/A Note: Briefly state (1) the requirement and (2) how and when the licensee violated the requirement. Fo,r non-cited violations, indicate why the violation was not cited.

1, AOC/Potential of an individual receiving an overexposure to an extremity due to direct beam access 2, AOC/Potential of gauge damage due to heat concentration by firebox 20 . PERFORMANCE EVALUATION FACTORS Licensee (name & location) Inspector Robert Gattone Amoco Oii Company Whiting Refinery 2815 Indianapolis Blvd.

Whiting, IN 46394 Inspection Date 10-28-94 A. Lack of senior management involvement with the radiation safety program and/or Radiation Safety Officer (RSO)

Issue Date: 03/07/94 E-13 87100, Appendix E

oversight y (x) N B. RSO too busy with other assignments y (x) N

c. Insufficient staffing y (x) N

o. Radiation Safety Committee fails to meet or functions inadequately y N (x) N/A E. Inadequate consulting services or inadequate audits y N (x) N/A Remarks (consider above assessment and/or other pertinent PEFs):

The licensee has a good radiation safety program. The RSO and RSO assistant appear to have good oversight of licensed material. Both individuals were familiar with the location of all gauges inspected. Licensee aanagement appeared concerned regarding compliance with NRC requirements and radiation safety.

Regional follow-up on above PEFe citations:

87100, Appendix E E-14 Issue Date: 03/07/94

6/9/2021 NMED: Report Single Event. Report NMED Item Number: 941072 Narrative: Last Updated: 02/21/1996.

A FIRE DUE TO A HYDROCARBON LEAK WHICH IGNITED WAS IN THE PROXIMITY OF A 10 mCi CS-137 SEALED SOURCE, A CONSULTANT RADIATION SPECIALIST WAS SUMMONED TO ASCERTAIN IF THE SOURCE WAS DAMAGED. THE LICENSEE DETERMINED THAT THE CS-137. SOURCE WAS NOT DAMAGED DURING THE FIRE AND THAT NO PERSONNEL EXPOSURES OCCURRED. RADIATION SURVEYS HAVE DETERMINED THAT NO RELEASES OCCURRED. UPDATE: AT 1140 EST, A SECOND FIRE OCCURRED ON A RUPTURED LINE AT THE BOTTOM OF THE "1.2"* PIPESTILL TOWER NEAR A 5 Ci CS-137 SOURCE. THE SOURCE IS LOCATED ON THE SECOND FLOOR OF THE AFFECTED TOWER. THE FIRE WAS EXTINGUISHED DURING THE NOTIFICATION. NO DAMAGE TO THE SOURCE OCCURRED. INITIAL RADIATION SURVEYS INDICATE THAT NO RADIATION RELEASE OR PERSONNEL EXPOSURES OCCURRED, THE CAUSE OF THE RUPTURE IS BELIEVED TO BE THERMAL CYCLING OF THE LINES .

Event Date: 01/23/1994 Date Reported to Agreement State:

Discovery Da.te: 01/23/1994 Da.te Reported to NRC: 01/23/1994 Licensee/Reporting Party Information :

Regu,la.ted By: NRC Reciprocity: NONE License Number: 1.3-25952-01 Name: AMOCO CHEMICAL CO.

NRC Docket Number: 03030725 City: WHITING NRC Program Code: 0.3120 State: INDIANA NRC Region: 3 Site of !Event:

Site Name: WHITING State:. INDIANA Additional Involved Party:

License Number: NA Name: NA NRC Docket Number: NA. City: NA NRC Program Code: NA Sta.l e: NA NRC Region: NA.

Other Information:

NRC Reportable Event Y Abnormal Occurrence: N Agreement State Reportabl.e Event N Investigation:

Atomic Energy Act Material: Y Record Complete: Field not used Consultant Hired: Y Event Closed by Region/State: Y Event.Type:

0TH -OTHER Even.t Cause:

0TH Cause.:. EXTERNAL/ EXTERNAL FIRE OR EXPLOSION Eve.n.t IAEA Aggregate Category; 0TH IAEA Aggregate Category: 3 https://nme.dJnl..gov/Auth Users/Ev.entReportFulJ?ReportType.=Single.&lternNumber=941072 1/2

6/9/2021 NMED: Report Corrective Actions Information:

Event Type; Number: Action:

0TH 1 NO.T REPORTl:D Source/Radioactive Material Information:

0TH Source Number; 1 Source/Material: SEALED SOURCE GAUGE. R;:idionuclide: CS-137 Manufacturer: NR Activity (Ci): 0.01 Model Number: NR IAEA Category: 5 Serial Numb.er: NR 0TH Source Number; 2 Source/Material; SEALED. SOURCE GAUGE Radionuclide.: CS-137 Manufacturer: NR Activity (Ci): 5 Model Number: NR IAEA Category: 3 Serial Numb.er: NR Leak Test Results (uCi);

D.e vice/Associated Equipment Information:

0TH Device Number: 1 Device/Equipmemt GAUGE. FIXED Model Numb.e r; NR Manufacturer: NR Serial Number: NR 0TH Device Number: 2.

Device/Equipmemt: GAUGE FIXED Model Numb.er: NR Manufacturer: NR Serial Number: NR Reporting Requirement Information:

~;;;~ Requirement 30.S0(a) - Event that prevents immediate prote.ctive. actions necessary to avoid exposures to radiation or 0TH radi.oactive material.s that could exceed regulatory limits or rel.eases of material. that could exceed regulatory limits,

• Reference Documents:

Reference Doc.ument Number: Entry Date: Retraction Date: Type of Report:

EN26667 05/0.2/1.994 EVENT NOTIFICATION https://nmed.inl.gov/Auth U.sers/EventReportFull?.Repo.rtType=Single&l.temNumber=9.41072 2/2