ML20054E008
| ML20054E008 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 03/26/1982 |
| From: | Mcalpine E, Troup G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20054E005 | List: |
| References | |
| 70-1201-82-04, 70-1201-82-4, NUDOCS 8204230593 | |
| Download: ML20054E008 (5) | |
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tg UNITED STATES d
i, NUCLEAR REGULATORY COMMISSION E
REGION 11 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 MAR 291982 Report No. 70-1201/82-04 Licensee: Babcock and Wilcox Company Nuclear Materials and Manufacturing Division Lynchburg, VA 24505 Docket No. 70-1201 Facility Name: Commercial Nuclear Fuel Plant License No. SNM-1168 3/Cf[g t Inspector:
Date Signed G. L. Troup Approved by:
ESrYYF C%h 3h6 /81-E. J. McAlpine, Chief, Viaterial Control and Date Signed Accountability Section Technical Inspection Branch Division of Engineering and Technical Programs
SUMMARY
Dates of Inspection: March 8-12, 1982 Areas Inspected:
This routine, unannounced inspection involved 29 inspector-hours onsite in the areas of organization, safety committees, internal review and audit,10 CFR 21 implementation, criticality safety and plant operations.
Results: Of the areas inspected, no violations or deviations were identified.
A204230 % %
RFPORT DETAILS 1.
Key Persons Contacted
- R. A. Alto Manager, Virginia Operations
- J. Ficor, Manager,- Quality Assurance
- L. T. Lee, Manager, Manufacturing Operations
- D. W. Zeff, Manager, Safety and Licensing
- W. Power, Manager, Safeguards and Security
- J. T. Ford, License Administrator K. E. Shy, Manager, Health and Safety N. K. Canody, Measurement Control Coordinator R. L. Vinton, Health Physicist P. A. Cure, Associate Health Physicist Other licensee employees contacted included one QC inspector and tvo oper-ators.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on March 12, 1982, with those persons indicated in paragraph 1 above. Regarding the need to desig-nate a new " responsible officer" for the implementation of 10 CFR 21 based on the corporate reorganization, the plant manager stated that the admin-istrative prouedures would be updated to reflect the new organization lines of authority.
Regarding the mass limits for the inspection hoods, the Manager, Safety and Licensing stated that the controls and limits would be reviewed.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Organization a.
A major organizational change in the corporate structure was made effective March 1, 1982.
Effective that date, the Nuclear Materials and Manufacturing Division was disestablished. The Commercial Nuclear Fuel Plant is now organizationally part of the Nuclear Power Generation Division (NPGD) and the Manager, Virginia Operations, reports to Dr. C. Pryor, Manager, Fuel Department, NPGD.
2 b.
No changes in the plant organization relating to safety or operations have been made.
6.
Safety Committee Section V, Subsection 6.1 of the license application requires that the Safety Review Board shall meet at least quarterly. The inspector reviewed the board meeting minutes for the December 21, 1981 meeting. Attendance at the meeting and the topics reviewed were in accordance with procedure AS-1170.
The inspector verified, based on these meeting minutes and the review conducted in Report 70-1201/81-12, that the required meetings had been held in calendar year 1981.
7.
Internal Review and Audit a.
Section V, Subsection 6.7 of the licensee's application requires that independent auditors shall conduct inspections of nuclear safety quarterly. The inspector reviewed the auditor's reports for the fourth quarter of 1981 and first quarter 1982. The fourth quarter report was reviewed by the Safety Review Board during its December meeting; a licensee representative informed the inspector that the first quarter 1982 audit report would be reviewed during the next meeting.
b.
Section V, Subsection 6.7 of the license application requires that Health-Safety supervision shall conduct, at least weekly, a formal audit of the plant status relative to nuclear and radiological safety.
The inspector reviewed the audit reports for the period November 24, 1981 - February 25, 1982. Documentation of the audits was in accord-ance with procedural requirements.
The inspector noted that no in-spection was scheduled or documented for the week of December 28 -
January 1.
A licensee representative informed the inspector that the plant was shutdown for the Christmas holidays during this period and no work, including maintenance, was performed during this period. The licensee representative stated that the administrative procedures would be clarified to reflect that inspections would not be required during periods that the plant is shutdown and no work is scheduled.
The inspector had no further questions.
c.
Section V, Subsection 7.4.3.1 of the license application requires that monthly inspections be conducted of the integrity of baffles, seals, shields or other protective devices used for moderation control. The inspector determined that these inspections are conducted in conjunc-tion with the weekly safety inspections of Area 1 and occur every third week. The inspector had no further questions.
3 8.
10 CFR 21 Implementation The licensee has approved policies and procedures for implementing the a.
requirements of 10 CFR 21, " Reporting of Defects and Noncompliance" The procedures assign responsibility, establish reporting and review requirements, and establish 10 CFR 21 provisions on procurement docu-ments for safety-related components.
The following corporate and Division policies and procedures were reviewed:
(1) B&W Policy 1208-A5, dated March 28, 1978, " Government Aspects of Procurement" (2) B&W Policy 1716-A1, dated December 6, 1977, " Reporting of Defects and Noncompliance Concerning Safety" (10 CFR 21)
(3) Procedure AS-1128, rev. 2, dated June 10, 1980, " Reporting of Defects and Noncompliance (Nuclear Materials and Manufacturing Division)
(4) Drocedure QC-1433, rev. 2, " Reporting of Defects and Nonconform-ance" (5) CNFP memo dated February 24, 1982, "10 CFR 21 Applicability" (basic components list) b.
The inspector noted that procedure AS-1128 designates the Manager of the Nuclear Materials and Manufacturing Division as the " responsible officer" as specified in 10 CFR 21.21. However, a corporate organiza-tion change (paragraph 5) has abolished this position.
A licensee management representative stated that the several administrative procedures would be revised based on the reorganization and that a new " responsible officer" would be designated (82-04-01).
c.
The inspector reviewed the 10 CFR 21 files for identified defects. One equipment aetect had been identified, evaluated as not reportable, and approved in accordance with the licensee's procedures. There were no reportable items.
d.
The inspector observed that Section 206 of the Energy Reorganization Act of 1974 and notices required by 10 CFR 21.6 were posted on various bulletin boards around the facility.
9.
Criticality Safety a.
The inspector observed the storage of SNM, transport, and proce: sing operations. Materials were in approved arrays and storage locations.
SNM scrap was handled in approved containers.
Safety criteria were posted at work stations.
No deviations from posted or procedural requirements were observed.
c?
4 b.
The inspector verified by observation and review of material accounta-bility records that the following criticality limits were met:
(1) Liquid containers in the pelletizing area are limited to 3.5 gallons. Flammable solvents are limited to 2 gallons.
(2) Unsafe geometry containers are marked and covered.
(3) Service water lines in the moderation control area are shielded and baffled to preclude spraying in the event of a ruptured line.
(4) The total SNM inventory is less than the license limit of 20,000 kgs. of U-235.
c.
The inspector reviewed the test records and verified that the criti-cality and fire alarms had been functionally tested monthly during the period January-March 1982.
The inspector also reviewed the test results for the annual test of the interlocks for the sintering furnace performed in January 1982 to satisfy the requirement of Section V, Subsection 6.1 of the license application.
d.
The posted criteria for the QC inspect -
hoods specify a limit of 25 kgs. per unit (2 hoods).
The inspe t.or reviewed the material control log for the area and noted that the log had several entries showing a total mass greater than 25 kgs.
Discussions with licensee representatives indicated that the log recorded the mass in both units.
Observation of the material in the units indicated that the unit mass limit (525 kg.) was met. A licensee representative acknowledged-that the material log was confusing and stated that the log procedure and the mass limit would be reviewed (82-04-02).
1 10.
Operations a.
The inspector verified during plant tours that operating procedures and health and safety procedures were available in the work areas and that current revisions were in use. General safety requirements were posted in various areas of the plant.
b.
No apparent fire or industrial safety hazards were observed. General housekeeping conditions were satisfactory.
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