ML20148G288: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 2: Line 2:
| number = ML20148G288
| number = ML20148G288
| issue date = 09/19/1978
| issue date = 09/19/1978
| title = IE Inspec Rept#70-1201/78-12 on 780814-17 During Which 1 Item of Noncompliance Was Noted:Failure to Follow Posted Nuc Criticality Safety Instru
| title = IE Inspec Rept 70-1201/78-12 on 780814-17 During Which 1 Item of Noncompliance Was Noted:Failure to Follow Posted Nuc Criticality Safety Instru
| author name = Kahle J, Potter J
| author name = Kahle J, Potter J
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)

Latest revision as of 22:47, 7 August 2022

IE Inspec Rept 70-1201/78-12 on 780814-17 During Which 1 Item of Noncompliance Was Noted:Failure to Follow Posted Nuc Criticality Safety Instru
ML20148G288
Person / Time
Site: 07001201
Issue date: 09/19/1978
From: Kahle J, Potter J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20148G244 List:
References
70-1201-78-12, NUDOCS 7811130028
Download: ML20148G288 (5)


Text

.

. Of "IGu q UNITEo sT ATEs NUCLE AR REGULATORY COMMISSION y, o, y y ,. cf ,g AEGION H 101 M ARIETT A sT R E E T , N.W.

C/

g(6 o, , f t

ATL ANT A, GE ORGI A 30303

. f

% .x...+

Report No.: 70-1201/78-12 Docket No.: 70-1201 License No.: Sh3-1168 ,

I Licensee: Babcock and Wilcox Company I Coccercial Nuclear Fuel Plant P. O. Box 1260 Lynchburg, Virginia 24505 i

Facility Name: Coccercial Nuclear Fuel Plant (ChTP)  !

inspection at: Lynchburg, Virginia Inspection conducted: August 14-17, 19 8 Inspector: J. B. Kahle Reviewed by: f If N at l

J. P -Potter, J Fuel Facilitie and Materials Safety Section 1 Fuel Facility and Materials Safety Branch l Inspection Su. mary Inspection on August 14-17, 1978 (Report No. 70-1201/78-12)

Areas Inspected: Routine, unannounced inspection of facility changes and modifications, safety coc=ittees, nuclear criticality safety and nonroutine events. The inspection involved 22 inspector-hours on site ,

i by one NP,C inspector.

Results: No items of noncompliance or deviations were identified in three l areas. One item of noncompliance was identified in one area. Deficiency -

Failure te follow posted nuclear criticality safety instructions para-graph 4.b 12-01.

?81113oo.tg c

l

(

i

. k RII Report No. 70-1201/76-12 DETAILS Prepared by: j , A . b f/7((

J.}(. ,able, Fuel F 1 ities Inspector at-FueG Facilities a aterials safety Section Fuel Facility and Materials safety l

Branch

/

Dates of Inspect.i ,: t 4-17, 1978 Reviewed by: i ,

J. P Fuel

' otter, Cnief acilities and Materials Safety Iatf['

Section Fuel Facility and Materials Safety Branch

1. Persons Contacted
  • E. J. Silk, Plant Manager H. Z. Dokuzoguz, Facilities Engineering Manager '

D. W. Zeff, Nuclear Material Control Manager

  • R. L. Vinton, Health Physicist K. E. Sby, Health Safety Supervisor
  • G. Johnson, Supervisor W. E. Cyrus , Supervisor R. T. Shutt, Nuclear Materials Operations Supervisor P. A. Cure, Associate Health Physicist J. P. Watters, Licensing Engineer D. C. Van Metre, Engineer
  • L. T. Lee, Manufacturing General Foreman The inspector also interviewed nine licensee operators and technicians.

1

  • Denotes those attending t.be exit interview.
2. Licensee Action on Previous Inspection Findings Not inspected during this inspection.
3. Unresolved items No unresolved items were disclosed during this inspection.
4. Nuclear Criticality Safety
a. During a tour of the plant the inspector observed that scrap special nuclear material was accumulated in safe volume containers and stored in approved storage arrays in accordance vit.h require-f

9 RI] Report No. 70-1201/78-12 ments of the license. Vaste materials contaminated with uranium were placed in designated containers in accordance with requirements of the license and operating procedures.

b. The inspector observed that special nuclear material from the oxidation furnace was temporarily stored in the pusher sintering furnace hood in a manner which did not conform to the posted instructions. A safe geometry (volume) container of U 208 was stored on the lef t side of the hood while the right side of the '

bood contained plastic bags of filter media containing U 20g from  ;

the oxidation furnace exhaust system. The posted nucleaf critica-lity safety instructions on the hood required that the UO, mass was limited to 1 geometrically safe container to be store 8 on the left side of the hood or a maximum of a 4 inch safe slab. The area supervisor acknowledged that the filter media containing U0 2 g sbould not have been placed in the hood when a safe geometry c6ntainer of special nuclear material was placed on the left side. He further stated that the material from the oxidation furnace was normally placed in the scrap hood, but the special nuclear material mass limits would have been exceeded if the u.aterial had been placed in the scrap hood as required by the procedures. Licensee representatives were informed that storage ,

of special nuclear material in a manner which did not meet the i requirements of the posted procedures was in noncompliance with the requirements of the license. (78-12-01). The inspector verified that other special nuclear material in the plant was processed, handled, transferred and stored in safe geometries and masses and on approved carts. Containers of material were placed in safe storage arrays in accordance with requirements of the license and operating procedures. Isolation distances were maintained as required,

c. The inspector verified that the following special nuclear critica-lity safety criteria and controls were maintained or performed, o

(1) Vessels of liquid moderators in the pelletizing area were l limited to 3.5 gallons.

(2) Flammable solvent containers in the pelletizing area vere limited to 2 gallons.

(3) Service water lines to the sintering furnaces were baffled to preclude spraying in the event of a ruptured line.

(4) Water sprinkler systems were prohibited in designated areas.

RII Report No. 70-1201/78-12 (5) Fire fighting atents were licited to conhydrogenous caterials.

(6) Doors were posted as required by the conditions of the license.

(7) Independent calculations were made of the E/U ratio prior to placing special nuclear material in the blender.

(8) Unsafe geometry containers in the pelletizing area were marked and covered.

(9) There was no accumulation of sludge in the liquid waste retention tanks.

d. The inspector verified that written instructions and acceptance criteria had been completed for calibrating and source checking the criticality alare detectors.
e. The inspector verified from the material control and accounting records that the total quantity of special nuclear material at the plant did not exceed the license limit. A check of the Met Lab Log showed that the quantity of special nuclear material in the Met Lab had not exceeded the licensee's control limit.
5. Safety Committees The Safety Review Board met on March 28 and May 23, 1978, with the required members in attendance. The minutes showed that topics of discussion dealt with the review of h'RC and Cocpany audits, the status of license amendments, f acility changes and modifications, proposed new and changed processes, and industrial and nuclear safety considera-tions of existing programs. Activities of the Safety Review Board met the requirements of the license and the licensee's procedures, AS-AD-1120, ChTP Sa f ety Review Board.
6. Facility Changes and Madifications l a. There have been no new facility changes and modifications, since l

the inspection on March 15-16, 1978, by the Safety Review Board or the Nuclear Criticality Safety Group. The records included evaluations of several minor changes to equipment and processes i

with justifications to show that reviews by the Safety Review Board or the Nuclear Criticality Safety Group were not required.

b. Documentation was available which showed that pre-operational audits were coerleted in accordance with the requirements of the l

license for the powder unloading room, the slug conveyor cleanout trap, and the pellet dryer assembly.

l l

~ ,

s RII Report No. 70-1201/78-12 l

c. The inspector discussed the conceptional design of the ultra filtration system for the liquid waste with licensee represen-tatives. They stated that the detail design has not begun and a target date for completion has not been established. l l
7. Nonroutine Events i
a. On June 9, 1978, there was an acid fire in a cardboard trash container located at the base of the stairway leading to the cafeteria. The container wes removed from the building where the contents continued to burn until immersed into a pail of water. ,

The resulting solution was neutralized with soda ash. One indivi- l I

dual became nauseated and vomited froc inhalation of the fumes.

He was taken to the Lynchburg General Hospital for medical attention.

b. An investigation revealed that earlier in the day a nitric acid spill in the cleaning area had been wiped up with cheesecloth and paper towels which were discarded in the cardboard trasb container.

To prevent reoccurrence the acid containers were modified by providing drains to prevent spills and personnel were instructed to neutralize acid spills with caustic material prior to cleaning.

The above corrective actions were verified by the inspector.

8. Organization The nuclear Material Control Componert of the Safety, Licensing and Safeguards Section has been established as a separate section reporting to the Plant Manag:r. Mr. David Zef f, formerly the Licensing and  ;

Control Administrator, has been appointed as Manager, j l

9. Housekeeping and Industrial Safety l General housekeeping conditions were excellent. Areas were clean and l equipment and materials were placed in an orderly fashion. No indus- l trial safety bazards were apparent. The inspector noted that numerous flammable control component assecbly shipping containers were being stored 2n the final fuel assembly storage area. Licensee management stated that the situation is currently under review to eliminate this heavy combustible burden condition.
10. Exit Interview Tbc inspector met with licensee representatives (denoted in paragraph 1) on August 17, 1978, at the conclusion of the inspection. The inspection findings, particularly the apparent item of noncompliance, were discussed in detail. ,

l l