ML19289F399

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IE Insp Rept 70-1201/79-10 on 790320-23.No Noncompliance Noted.Major Areas Inspected:Organization,Facility Changes & Mods,Internal Review & Audits,Safety Committees & Operation Review
ML19289F399
Person / Time
Site: 07001201
Issue date: 04/06/1979
From: Kahle J, Potter J, Woodruff R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML19289F394 List:
References
70-1201-79-10, NUDOCS 7906070323
Download: ML19289F399 (6)


Text

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UNITED STATES n at00g'o NUCLEAR REGULATORY COMMISSION

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101 M ARIETTA STREET, N.W.

ATLANTA, GEORGI A 30303

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Report No. 70-1201/79-10 Licensee:

Babcock and Wilcox Company P. O. Box 1260 Lynchburg, V.irginia 24505 Facility Name:

Commercial Nuclear Fuel Plant Docket No. 70-1201 License No. Sh3-1168 Inspection at Commercial Nuclear Fuel Plant, Lynchburg, VA

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Inspectors:

J. B. Kahle Date Signed A,,

- A.1 nd 6

-)/c /7 c1 R. L.;)'oodruf f Date Signed v

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6/7jf Approved by:

J. JK P6tter, Section Chief, FFMS Branch D6 te' Si gned

SUMMARY

'opection on March 20 - 23, 1979.

Areas Inspected This routine unannounced inspection involved 56 inspector-hours on site in the areas of 10 CFR Part 21, organization, facility changes and modif

ons, internal review and audits, safety committees, operations review, mai ce, nuclear criticality safety and ncaroutine events.

Results Of the nine areas inspected, no apparent items of noncompliance or deviations were identified.

2231 199 7906070 %,7

DETAILS 1.

Persons Contacted Licensee Employees

  • R. A. Alto, Acting Plant Manager
  • D. W. Zef f, Acting Safety, Licensing and Safeguards Manager
  • J. Ficor, Quality Control Manager
  • R. L. Vinton, Health Physicist
  • K. E. Shy, Health Safety Supervisor W. E. Cyrus, Supervisor K. H. Campbell, Maintenance Foreman Other licensee employees contacted included two technicians, six operators, and one office personnel.
  • Attended exit interview 2.

Exit Interview The inspection scope and findings were summarized on March 23, 1979, with those persons indicated in Paragraph I above.

3.

Licensee Acti.on_on Previous Inspection Findings Not inspected.

4.

Urnesolved Items Unresolved items were not identified during this inspection.

5.

10 CFR Part 21 a.

Procedures Procedure AS-AD-1128, " Reporting of Defects and Non-Compliances -

10 CFR 21," describes the implementing procedure and responsi-bilities for evaluating deviations and noncompliance, informing the responsible officer of noncompliance or defects and reporting noncompliance or defects to the Commission. Requirements per-taining to procurement, records and reports are described. No items of noncompliance or deviations were identified.

2231 200

. b.

Postings An examination of several bulletin boards showed that Section 206 of the Energy Reorganization Act of 1974 and notices, which describe the regulations and where copies are maintained, were properly posted. No items of noncompliance or deviations were identified.

c.

Procurement Documents The inspector selected two requisition / purchase order forms and verified that 10 CFR 21 requirments were included on the form.

Criteria for including the 10 CFR 21 requirements on purchase orders were discussed with licensee representatives. No items of nonccmpliance or deviations were identified.

d.

Evaluations An examination of the 10 CFR 21 file showed that several occur-rences or events had been evaluated by the licensee but none were judged to be of significance to be reportable pursuant to 10 CFR 21.

No items of noncompliance or deviations were identified.

6.

Organization Mr. M. A. Glora, Safety, Licensing and Safeguards Manager terminated employment with the licensee eifective November 10, 1978.

Mr. D. W. Zeff has been acting since that time. Discussions with management personnel revealed that the licensee has been very active in interviewing and selecting a candidate for the vacancy. They stated that, because of the importance of the position, it may be a few months before a choice is made. No iters of noncompliance or deviations were identified.

7.

Facility Changes and Modifications A new walking beam furnace has been installed in the pelletizing a.

area replacing the pusher sintering furnace. Licensee representa-tives stated that the brick would be replaced in the new furnace prior to operation and at that time the preoperational audit would be performed.

Installation of the new furnace required movement of a hood and several storage racks for containers of special nuclear material. The inspector verified that the placement of the hood and the racks met the nuclear criticality criteria and requirements.

b.

The decontamination room has been expanded to include the ladies change room to the pelletizing area. A new ladies change room has been established at the old entrance to the rod loading area.

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. Licensee representatives stated that the equipment has been ordered c.

for installation of the ultrafiltration system.

Documentation pertaining to the system showed that appropriate safety reviews hai been accomplished.

d.

No items of noncompliance or deviations were identified.

8.

Internal Review and Audits An examination of the audit files showed that the nuclear criticality safety and health physics audits had been performed on a quarterly basis by independent auditors as required by the conditions of the license.

The results had been reported to the plant manager and the documentation showed that corrective actions had been taken when necessary. Weekly and monthly audits were performed in accordance with the requirements of the license and the licensee's procedures.

Also, the records reflected that all the health and safety procedures had been reviewed and revised, if necessary, during the 1978 calendar year.

No items of noncompliance or deviations were identified.

9.

Safety Committees The inspector examined the Safety Review Board meeting minutes for 1978.

The Board had met at least quarterly with the required members in atten-dance. The minutes reflected that the discussion topics dealt with KRC and internal audit results and corrective actions, proposed license amendments, facilities and equipment changes and changes in regulations.

No items of noncompliance or deviations were identified.

10.

Maintenance The inspector reviewed the licensee's procedure MA-AD-1800, " Safety During Maintenance Activities." The procedure provides general safety guidelines pertaining to ventilation, filters, radiation work permits, cutting and welding, removal of tools from controlled areas, protection clothing and safety glasses. The procedure had been approved by safety and management personnel. Maintenance work involving radioactive materials or radiation is performed in accordance with approved proce-dures or a radiation work permit (RWP). RWP's must be approved by Health and Safety and the operating supervisor of the area.

An exami-nation of several RWP's showed that appropriate safety equipment and precautions were used and the permits were issued in accordance with the RWP procedure.

Discussions with licensee representatives revealed that a work order system is not used but a record is maintained for all maintenance work.

A representative stated that the activity of each maintenance worker could be traced to a specific piece of equipment or operation in the controlled area.

No items of noncompliance or devia-tions were identified.

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. 11.

Operations Review a.

Procedures and Postings During a tour of the plant the inspector verified that operating procedures were available to operators at the various work sta-tions. Discussions with operators revealed that supervision notified them when procedures were revised. Nuclear criticality limits and controls were posted at the work stations and general safety requirements were posted in the areas.

No items of non-compliance or deviations were identified.

b.

Housekeeping Housekeeping conditions were satisfactory.

No apparent fire or industrial safety hazards were observed.

No items of noncompliance or deviations were identified.

12.

Nuclear Criticality Safety a.

Waste and Scrap The inspector verified that accumulations of scrap containing special nuclear material was placed in safe volume containers and the containers were placed in storage arrays approved by the condi-tions of the license. Waste materials contaminated with special nuclear materials were placed in containers in accordance with the requirements of the license and operating procedures.

No items of noncompliance or deviations were identified.

b.

Controls and Arrays The inepector verified that special nuclear material was handled in safe slab geometries and masses. Only approved carts and transfer containers were used to transfer special nuclear materials.

Con-tainers of material were placed in safe arrays or designated work locations.

Special nuclear material was processed, handled and stored in accordance with operating procedures. No items of noncompliance or deviations were identified.

c.

Special Requirements and Controls Water sprinkler systems were prohibited from certain designated areas and fire fighting agents were limited to designated quanti-ties or nonhydrogenous types.

Service water pipes to the furnaces in the pelletizing area were baffled.

Vessels containing liquid moderators were limited to 3.5 gallons.

Solvent containers were limited to 2 gallons. Vacuum cleaners were limited to safe geometry.

2231 203

. Unsafe geometry containers in the pelletizing area were marked and covered. Doors were posted as required by the conditions of the license.

Independent calculations were made of the H/U ratio prior Provisions had to placing special nuclear material in the blender.

been made to prevent accumulation of water in fuel assemblies wrapped with plastic.

No items of noncompliance or deviations were identified.

d.

Criticality Monitoring System The inspector verified f rom the records that preventative main-tenance and calibration of the criticality alarm system had been performed at least annually and that a source functional check was performed conthly.

A licensee representative stated that an indium foil in the dosimetry device would be used to quick-sort individuals in the event of a criticality accident and then a blood sodium evaluation to determine dose.

Procedure AS-AD-1106, " Evaluation of 70-24(b)(1) Requirement," would be used for the dose evaluation.

No items of noncompliance or deviations were identified.

e.

Sludge Buildup An examination of the waste water retention tanks records showed that there has been no sludge buildup in these tanks. A licensee representative stated that these tanks are only tanks on site where there is ny possibility of sludge buildup which would contain special nuclear material.

No items of noncompliance or deviations were identified.

f.

Inventory The inspector verified from the material control and accounting records that the total quantities of source and special nuclear material at the plant did not exceed the license limits. No items of noncompliance or deviations were identified.

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