ML20247E931: Difference between revisions

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Violations or deviations were not identified.
Violations or deviations were not identified.
: 8. Review of Operational Safety Assessment Findings (92701)
: 8. Review of Operational Safety Assessment Findings (92701)
: a.          An Operational Safety Assessment was conducted by the NRC at the licensee's facility in February 1987.            Findings of the assessment were reported in Inspection Report 70-1201/87-02. By letter dated June 1,1987, the licensee responded to the assessment findings and d' scribed the corrective actions being taken on the identified weaknesses and the improvement items.
: a.          An Operational Safety Assessment was conducted by the NRC at the licensee's facility in February 1987.            Findings of the assessment were reported in Inspection Report 70-1201/87-02. By {{letter dated|date=June 1, 1987|text=letter dated June 1,1987}}, the licensee responded to the assessment findings and d' scribed the corrective actions being taken on the identified weaknesses and the improvement items.
: b.          The following IFI identified in the Operational Safety Assessment was reviewed during the inspection.
: b.          The following IFI identified in the Operational Safety Assessment was reviewed during the inspection.
(0 pen) 87-02-22, Dike and drainage control for hazardous chemicals.
(0 pen) 87-02-22, Dike and drainage control for hazardous chemicals.

Latest revision as of 19:33, 8 March 2021

Insp Rept 70-1201/89-01 on 890306-10.No Violations or Deviations Noted.Major Areas Inspected:Mgt Controls, Training,Nuclear Criticality Safety,Plant Operations,Maint & Followup on Previously Identified Items
ML20247E931
Person / Time
Site: 07001201
Issue date: 03/23/1989
From: Horn M, Macalpine E, Troup G
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20247E920 List:
References
70-1201-89-01, 70-1201-89-1, NUDOCS 8904030272
Download: ML20247E931 (6)


Text

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. . MQto UNITED STATES -

_g ug'o NUCLEAR REGULATORY COMMISSION

.[' o REGION ll

<g' y '101 MARIETTA STREET, N.W.

  • 'c. ATLANTA, GEORGI A 30323 9...

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1 Report No.: 70-1201/89-01 Licensee: B&W Fuel Company Commercial Nuclear Fuel Plant Lynchburg, VA . 24505 Docket No.: 70-1201 (CNFP) License No.: SNM-1168 Facility Name: ' Commercial Nuclear Fuel Plant Inspection Conducted: arch'6, 7, 9, and 10, 1989 Inspector: .7 2M87 G. L. Troup, 'FuelfFacility Project Inspector

~

Date Signed Accompanying Personnel: (March 6 and.7, 1989)

Fuel Cycle . Safety Branch, Division of Industrial and Medical Nuclear Safety, Office of Nuclear Materials Safety and Safeguards:

M. L. Horn, E ironmental Engineer

.D A. ugh ,. Nuclear Process Engineer.

Approved by:

E. J.

I74 3NN icAlpine, Chief j0 ate /Slped Material Control and Accountability Section Nuclear Materials Safety and Safeguards Branch Division of Radiation Safety and Safeguards

SUMMARY

' Scope: This routine, unannounced inspection was conducted in the areas of management controls, training, nuclear criticality safety, plant operations, maintenance, and follow-up on previously identified items. In addition, discussions were held on the NRC comments and questions on the initial submittal of the license renewal application.

Results: Within the scope of the inspection, no violations or deviations were identified. The licensee's implementation of the programs inspected and the controls to assure compliance with specific license requirements were acceptable.

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REPORT DETAILS

1. Persons Contacted Licensee Employees R. A. Alto, Plant Manager
  • W. T. Engelke, Manager, Quality and Safety J. T. Ford, Manager, Fuel Manufacturing
  • R. W. Penoza, Manager, Field Operations
  • B. W. Pugh, Manager, Production and Materials Control
  • K. E. Shy, Health Physicist C. W. Speight, Manager, Facilities and Services The inspector also interviewed several other licensee employees.
  • Denotes those present at the exit interview.
2. Management Organization and Controls (88005)
a. Organizational Structure The in;pector reviewed the facility organization structure and assignment of responsibilities for safety programs and compared them with Section V.5 of the license application. No changes in the safety management organization or in the assignments of individuals in these positions had been made.

The Licensee and Control Administrator position, which is not a direct management position responsible for safety, is currently vacant. The Health Physicist is performing the functions of the position while recruitment of a replacement is in progress.

Violations or deviations were not identified.

b. Safety Committees The membership of the Safety Review Board and the responsibilities of the Board are specified in Procedure AS-1120, "CNFP Safety Review Board." The inspector reviewed the minutes of the Board meetings since September 1988, and determined that the meetings had been held at the required frequency with the required membership present. The inspector also determined that the agenda for items reviewed were in accordance with the charter.

Violations or deviations were not identified.

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3. Training (88010)

The inspector determined that procedural controis were in place for employee safety training. Radiation safety refresher training is currently being conducted for radiation workers as they return from shutdown layoffs and/or assignments with Field Services at power reactors.

Additionally, chemical safety / hazardous material training for plant workers was conducted by a contractor in September.

Violations or deviations were not identified.

4. Audits (88005, 88015, 88020)
a. The inspector reviewed the weekly nuclear safety audits conducted by Health Safety personnel for the period January - March 1989, and the quarterly independent nuclear safety and health physics audits for the 4th quarter 1988. No nuclear safety items were identified. On March 10, 1989, the quarterly independent health poysics audit was conducted,
b. The inspector verified that written guidance was provided for the weekly audits of nuclear safety and for checks of the fire protection system. The inspector also verified that the individuals conducting the audits were qualified to perform such audits and the independent auditors had been designated in writing by the Plant Manager.

Violations or deviations were not identified.

5. Procedures (88005, 88015, 88025)
a. The inspector verified that procedural controls are in place establishing the review and approval of safety procedures, training of plant personnel, calibration of the criticality monitoring system, and performance of audits. The inspector reviewed selected procedures and verified that they had been reviewed and approved as required by internal procedures and the license.

Violations or deviations were not identified,

b. The inspector reviewed revisions to six procedures. All of the procedures had been reviewed and approved in accordance with the internal procedures and the license. The scope of changes were consistent with the regulations and the license.

Violations or deviations were not identified.

c. The inspector determined during tours of facility areas that procedures were available at various work stations which include the nuclear criticality safety limits applicable to that station. Also,

local safety rules were posted in various areas which contained both industrial safety and nuclear criticality safety limits.

Violations or deviations were not identified.

d.Section V.6.5 of the application requires that Health-Safety procedures be reviewed at least annually for technical correctiveness and applicability. In reviewing the index of procedures and the effective' dates, the inspector noted that the effective date was 1987 for procedure AS-1106, Emergency Procedure. The cognizant supervisor explained that the procedure had been reviewed and changes identified but the revisions was being delayed pending approval of a license amendment. The inspector had no further questions.

Violations or deviations were not identified.

.6. Nuclear Criticality Safety (88015, 88025)

a. Facility Changes and Modifications The inspector reviewed two facility modification change requests made since the last inspection. The inspector verified that the changes had been initiated and reviewed in accordance with license and procedural requirements, and had been inspected and released for service. The inspector also reviewed the nuclear safety analysis associated with the change, and verified that it was in accordance with the license requirements.

Violations or deviations were not identified.

b. Criticality Monitoring Systems The inspector reviewed the functional test records for the criticality monitoring system for the period January - February 1989 and determined that the tests had been performed in accordance with the license conditions.  ;

During tours of the plant areas the inspector observed that individual monitors were operable, and that the control panel indicated no monitors in a failed condition.

Violations or deviations were not identified. l

c. SNM Containers Through di ;ussions with the cognizant licensee individuals and j observations during tours of plant areas, the inspector determined I that no new design containers for the handling, storage or shipping j of SNM were in use. Because of the types of operations performed and  !

materials handled, no unfavorable geometry containers which require  !

l l

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r s

poisons (e.g., borated Raschig rings) for secondary control are in use in the facility.

Violations or deviations were not identified.

7. Fuel Handling and Storage (88020)

During tours of the production areas, the inspector observed the handling of pellets, fuel rods and fuel assemblies. All observed activities were in accordance with posted safety limits and storage requirements.

Completed assemblies were stored in permanent fixtures. Storage and transport of fuel pellets were in accordance with the license requirements for slab thickness, unit separations, and enrichment segregation.

Violations or deviations were not identified.

8. Review of Operational Safety Assessment Findings (92701)
a. An Operational Safety Assessment was conducted by the NRC at the licensee's facility in February 1987. Findings of the assessment were reported in Inspection Report 70-1201/87-02. By letter dated June 1,1987, the licensee responded to the assessment findings and d' scribed the corrective actions being taken on the identified weaknesses and the improvement items.
b. The following IFI identified in the Operational Safety Assessment was reviewed during the inspection.

(0 pen) 87-02-22, Dike and drainage control for hazardous chemicals.

The design of the new storage building with dikes and drainage control is being reviewed for conformance with the applicable regulations before final release. The present schedule is for construction during July - September 1989 (B&W Fuel Co. 2nd qtr.

FY 90).

9. Periodic Testing (88025)
a. Section V.7.1.1 of the license applicat40n requires that HEPA filters be tested for efficiency following major maintenance. The inspector reviewed the test results for the controlled area exhaust filters after the filters were replaced in February 1989. The test was in accordance with the license requirements and the results were greater than the minimum acceptable system efficiency.

Violations or deviations were not identified. i

b. Section V.8.2.2 of the license application requires that the minimum face velocity for hoods and similar enclosures shall be at least 100 linear feet per minute and shall be determined weekly except during shutdown. In addition to the hoods, procedure AS-1103 requires that other air control systems, such as exhaust scoops on pellet tables, j 1

I j

~

g.

l be tested weekly as well. The inspector reviewed the air flow test records for the period' January - March 1989 and determined that the tests had been performed at the required interval with satisfactory results. Those systems which were out-of-service were clearly identified.

Violations or deviations were not identified.

10. License Renewal Review (94702)

On April 11, 1988, B&W Fuel Co. submitted the renewal application for Licensee SNM-1168. The application was reviewed by various sections in Region II and the Fuel Cycle Safety Branch. Comments and/or questions were consolidated by the Licensing Project Manager. On March 6-7, these were discussed with licensee representatives. Revised pages and/or sections will be prepared by the licensee and submitted to the NRC so that the renewal review can be completed. By separate correspondence, the licensee was also requested to provide additional information for the preparation of the Environmental Assessment Report.

11. Exit Interview The inspection scope and findings and the inspector's observations were summarized on March 10, 1989, with those persons indicated in paragraph 1.

The inspector also discussed upcoming changes in plant operations, and proposed activities. While some proprietary information was reviewed during the inspection, it is not discussed the report.

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