ML20031F725
| ML20031F725 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 09/29/1981 |
| From: | Coryell G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20031F716 | List: |
| References | |
| 70-1201-81-10, NUDOCS 8110200370 | |
| Download: ML20031F725 (5) | |
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4 UNITED STATES
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8 NUCLEAR REGULATORY COMMISSION n
E REGION 11 e
101 MARIETTA ST., N.W.,f *llTE 3100 k...,.. o ATLANTA, GEORL 30303 Report No. 70-1201/81-10 Licensee: Babcock & Wilcox Company Nuclear flaterials and flanufacturing Division Lynchburg, VA 24505 Facility Name: Comraercial Nuclear Fuel Plant baket No. 70-1201 License No. SN!1-1168 Mc-[
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Inspector:
G. P. Coryell
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Date Signed Accompanying Personnel: N. Ketzlack, Uranium Fuel Licensing Branch, FCUF Approved by:
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G. P. Corygll, Actipg Chief, Fuel Facilities Date Signed Project Section,'RRPI SUltriARY Inspection on August 31 to September 4,1981 Areas Inspected This routine unannounced inspection invcived 30 inspector-hours on site in the areas of facility changes and modifications, safety committees, training, procedures, nuclur criticality safety, operations, and internal review and audit.
Resul ts No items of noncompliance or deviations were identified in the seven areas inspected.
A PDR ADOCKB110200370 810930 07001201 C
4 DETAILS 1.
Persens Contacted Ltcensee Bnployees 4
- R. A. Alto, Manager, Virginia Operations
- J. Ficor, Manager, quality Assurance
- D. W. Zeff, Manager, Licensing and Safety 4
- J. T. Ford, Licensing Engin sr W. T. Engelke, Manager, Manufacturing Engineering C. W. Speight, Manager, Facility Engineering L. T. Lee, Manager, Manufacturing Operations K. E. Shy, Foreman, Health Safety W. E. Cyrus, Supervisor, Pellet Fabrication P. A. Cure, Associate Health Physicist Other licensee employees contacted included three technicians and four opera tors.
Other Organizations N. Katzlach, Project Manager, FCUF NRC Resident Inspector
- Attended exit interview i
2.
Exit Interview The inspection scope and finalngs were summarized on September 4,1981 with those persons indicated in paragraph 1 above.
Additional discussions related to the Commercial Nuclear Fuel Plant License renewal application.
3.
Licensee Action an Previous Inspection Findings Not inspected.
4.
Unresolved Items i
Unresolved items were not identified during this inspection.
5.
Facility Change and Modifications a.
Facility change request records were audited for compliance with license application Section V, Subsection 7.1.4 and the licensee's procedure AS-1120, Rev. 3, dated 7/7/80.
Records for additional fuel assembly storage racks, modification of a powder moisture sampling hood and one storage array were examined.and no deviation from crocedural requirements were identified.
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b.
Verification was made that proposed changes were reviewed by the Licensing and Safety tbnager for determination of the need for a nuclear safety evaluation and Safety Review Board review. A preoperational inspection was performed and work station posting and procedures are in place for the facility changes examined.
6.
Safety Commit # ae a.
The inspector examined Safety Review Board meeting minutes for the June 3 and August 11, 1981 meetings. Confirmation was made that all board members were in attendance.
b.
Meeting topics included the ALARA program, internal and external audit / inspection findings licensing activities, review of proposed j
modifications and fire safety training. The topics conform with the committee's charter and no violations of requirements were identified.
7.
Internal Review and Audit An examination of the audit files show 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 perfonned in accordance with the requirements of the license and the licensee's procedures. Also, the records reflected that all the health and safety procedures has been reviewed and revised, as scheduled, on an annual basis.
8.
Procedures a.
Each functional component of the licensee's organization has the responsibility for preparing, obtaining approvals, issuing, distribution control and revision of procedures. All components must comply with requirements of procedure PC-1300, Rev. 4, "CNFP Procedure Numbering System" and PC-1330, Rev.1, " Preparation and' Appro.al of CNFP Administrative and Operative Procedures."
b.
The procedure system is divided into Administrative Precedures that define systems for control of manufacturing service functions, and Operative Procedures that direct manufacturing operations.
c.
Selected procedures were reviewed for conformance.with the basic procedures noted in "a" above and with the appropriate component procedures as follows:
(1) QC-1421 - Review and approval of Drawings, Specifications and procedures..
(2) ItA-1200 - Manufacturing Document Control
3 (3) f1A-1206 - Rev. 2, - Preparation and Approval of Manufacturing Procedures.
(4) MA-1210, Rev. 2, - Preparation and Approval of Manufacturing process procedures temporary revisions.
(5) AS-1124, Rev. 4, - Preparation, Distribution and Control of Health, Safety and Licensing Procedures d.
Verification was made that the correct revision of proceoures were in use and that distribution is by Document Control Voucher per procedure.
No violations of requirements were identified.
9.
Training a.
Training records were reviewed for conformance with conditions specified in Section V, subsection 6.3 of the license application and with the licensee's procedure AS-1101, Rev. 5 - Employee Safety Training.
Personnel records verify performance of initial radiation, nuclear and industrial safety training and annual retraining of radiation workers.
Training coverage includes requirements of 10 CFR 19 and 21.
b.
The health and safety staff provided special training sessions in CPR, respiratory protection, OSHA training films, plant emergency procedures and fire brigade training in the last twelve month period.
No training deficiencies were identified.
- 10. Nuclear Criticality Safety a.
The inspector verified that special nuclear material is controlled in safe slab geometries and masses.
Scrap accumulations are in approved storage arrays.
Only approved carts and containers were used to transfer special nuclear material.
b.
Service water pipes in the moderation controlled areas were enclosed.
Vessels containing liquids were limited to 3.5 gallons.
Correct nuclear criticality controls were posted in the work area.
c.
The inspector verified that the criticality alann system is functionally tested each month, and all units were calibrated in the snop on May 14, 1981.
Calibrations are perfonned annually.
- 11. Opera tions a.
The inspector verified during plant tours, that operating procedures were available in the work areas and that current revisions were in use. Criticality safety limits were posted for work stations and
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i arrays. General safety requirements were posted in various areas of i
the plant.
b.
Discussions with operators and technicians indicated a good working knowledge of industrial and nuclear safety criteria and confirmed performance of safety retraining in 1981.
i-c.
No apparent.. fire or industrial safety hazards wert. observed and general housekeeping conditions were satisfactory.
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