ML20042B301

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IE Insp Rept 70-1151/82-03 on 820208-12.No Noncompliance Noted.Major Areas Inspected:Operations,Facility Changes & Mods,Safety Committees & 10CFR21 Implementation
ML20042B301
Person / Time
Site: Westinghouse
Issue date: 02/25/1982
From: Mcalpine E, Troup G
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20042B297 List:
References
70-1151-82-03, 70-1151-82-3, NUDOCS 8203250198
Download: ML20042B301 (4)


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UNITED STATES 8

NUCLEAR REGULATORY COMMISSION o

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REGION 11 101 MARIETTA ST., N.W., SUITE 3100 o,

ATLANTA, GEORGIA 30303 s

MAR 011982 Report No. 70-1151/82-03 Licensee: Westinghouse Electric Corporation Nuclear Fuel Division Columbia, SC 29205 Facility Name:

Columbia Plant Docket No. 70 1151 License No. SNM-1107 Inspection at Columbia Plant Nuclear Fuel Division site near Columbia, SC Inspector:

d!a t G. L. Troup~

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Date Signed Approved by: / 2 L//-

at R/Jr/T L

/ge E(/J. McAlpine, Section Chief Ofte Signed Technical Inspection Branch Engineering and Technical Inspection Division

SUMMARY

Inspection on February 8-12, 1982 Areas Inspected This routine, unannounced inspection involved 34 inspector-hours on site in the areas of operations, facility changes and modifications, safety committees, organization and 10 CFR 21 implementation.

Results Of the, areas inspected, no violations or deviations were identified.

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4 2.

REPORT DETAILS 1.

Persons Contacted Licensee Employees

  • M. D' Amore, Manager, Columbia plant.
  • E.-F. Buonanno, Manager, Chemica' Operations
  • W. L. Goodwin, Manager, Regulatory Compliance
  • C. F. Sanders, Manager, Radiological.and Environmental Services
  • E. K. Reitler, Jr., Fellow Engineer H. T. King, Nuclear Criticality Engineer J. L. Weatherford, Jr., Manager, Health Physics Operation G. T. Lowder, General Supervisor, Conversion and Scrap Reprocessing M. R..Spinnato, Supervisor, Waste Recovery and Disposal F. Shaffer, Manager, Mechanical Manufacturing R. E. Fischer, R&E Engineer H. T. Shannon, R&E Engineer B. G. Ratcliff, Purchaser

.0ther licensee employees contacted included two technicians and two opera -

tors.

- Attended exit interview 2.

Exit Interview The inspecticn scope and findings were summarized on February 12, 1982, with those persce, indicated in paragraph 1 above.

3.

Licensee Action on Previous Inspection Findings t

l (Closed) Violation (81-14-01) Improper-Sealing of Fuel Assemblies. 'The inspector reviewed the corrective actions stated in the licensee's letter of December 8,1981, and verified that the corrective actions had been com-l-

pleted (paragraph 7.b.).

4.

Unresolved Items e

Unresolved items were not identified during this inspection.

5.

10 CFR 21 Implementation a.

The inspector verified that the licensee has approved policies and procedures for the evaluation of material deviations or safety concerns and for informing a responsible officer, procedures establishing reporting criteria, and procedures to-include 10 CFR 21 requirements on procurement documents for designated components. The following proce-dures were examined:

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(1) OPR-WRD-600-1, Rev. 2, " Identification and ' Reporting of Substan-tial Safety Hazards, Significant Deficiencies and Unreviewed Safety Questions (Policy)".

(2) Nuclear Fuel Division procedure P-710, ' Rev. 6, dated 8/11/80,

" Identification' and : Reporting of Substantial Safety Hazards, Significant Deficienicies and Unresolved Safety Questions".

(3) Columbia. Plant Procedure P-710-1, Rev.1, dated 6/2/78, "Identi-fication and Reporting of Substantial Safety Hazards (10 CFR 21)

Relative to NFD Licensed Facilities".

(4) " Basic Components List". Revision 3,- dated 8/28/81.

(5) Plant Procedure MA-318, Revision 2, dated 8/17/81, "Ide tifica-tion, Evaluation and Reporting of Defects and Noncomplian ".

(6) Purchasing Form 102, Revision 2, dated 1/6/78, " Quality Assurance-and Administrative Requirements".

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b.

The inspector verified that an approved -list of basic components exists for the Columbia Plant and that the Regulatory Compliance Committee evaluates any reported deficiencies or concerns. No evaluations have been required in the last twelve months. The committee reviewed and approved the changes of the Basic Components List prior to its revisions in the June 1981 meeting.

c.

The inspector verified that Section 206 of the Energy Reorganization Act of 1974 and 10 CFR 21 are posted on the facility bulletin board, as required by 10 CFR 21.6.

6.

Safety Committees a.

The inspector reviewed the meeting minutes for the Regulatory Com--

pliance Committee (RCC) meetings for the period September 1981 -

January 1982.

Participants and meeting frequency were as required by License Condition No.19.

b.

The agenda items discussed during these RCC meetings included internal and external inspections and audits, license and permit amendments, safeguards, nuclear criticality safety, environmental control and training.

c.

The inspector also discussed the actions for the Airborne Radiation Task Force with licensee representatives. A licensee representative statea that the ALARA report for the second half of 1981 was in pre-paration and would be submitted to the RCC when completed.

The inspector had no further questions.

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--Operations a.

The inspector examined operating procedures during tours of the

-facility and found that current approved procedures were available and included radiation protection and criticality safety requirements.

b.

The inspector -reviewed the licensee's corrective actions regarding a previously identified violation (70-1151/81-14-01), regarding providing free drainage of fuel assemblies. Operating Procedure OP 73701, " Wrap Fuel Assembly for Temporary Storage", Rev. 3, dated 10/27/81 provided for the slitting of.the plastic cover to provide drainage as a f.inal step. The inspector also verified -that stored assemblies were provided with drainage slits. The inspector had no further. questions;. this item is closed.

c.

The inspector observed several containers (patis'and bird cages)' stored outside of marked " crit safe" zones near. the waste incinerator.

The containers met the license spacing requirement for criticality spacing.

'The licensee took immediate action to relocate the containers or post these areas.

d.

Criticality limit signs were posted for work areas, storage arrays and transfer carts.

General housekeeping conditions were good and no industrial safety. items were identified.

e.

The inspector verified that vaporizer detectors were operable, that remote closin a devices were inplace for closing UF6 cylinder valves in the vaporizer chests and that valve covers were in place on UF6 cylinders.

8.

Facility Changes and Modifications

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a.

The inspector reviewed eight facility changes in progress or completed since October 1981. Records were reviewed for conformance with safety review, evaluation and approved requirements stated in Section 2.3.2.3 of the license application. Except for o'ne change still in prooress, all changes had been inspected and released prior to startup as required by License Condition No. 44.

o b.

One change-involved a major relocation of a piece of equipment. _The inspector verified that the criticality calculations had been performed and reviewed. The layout drawirg of the area was being revised at the time of the inspection.

The inspector ' observed that the criticality spacing requirements for the equipment in the new location had been met.

9.

Organization The inspector discussed the plant organization and key personnel with licensee representatives. No changes have occurred in the organization or personnel for positions related to safety.

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