ML20195H246

Insp Rept 70-1151/88-07 on 880516-20.No Violations & Deviations Noted.Major Areas Inspected:Mgt Controls,Nuclear Criticality Safety,Operations Review,Maint & Previously Identified Followup Items

ML20195H246
Person / Time
Site:	Westinghouse
Issue date:	06/16/1988
From:	Mcalpine E, Troup G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20195H232	List: ML20195H228 ML20195H246
References
70-1151-88-07, 70-1151-88-7, NUDOCS 8806280250
Download: ML20195H246 (6)

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JUN 161988 Report No.: 70-1151/88-07 Licensee: Westinghouse Electric Corporation Commercial Nuclear Fuel Division Columbia, SC 29250 j Docket No.: 70-1151 License No.: SNM-1107 Facility Name: Commercial Nuclear Fuel Plant i Inspection Conducted: Ma 16 ' , 1988 1 .

l Inspector: h G.LETroup,*ruelFa/ilityProjectInspector I4/W D' ate' Signed Approved by: _ b# h, N 6dVk d l E . J . McAl pi ne , C h'Ttif Date Signed l Material Control and Accountability Section Nuclear Materials Safety and Safeguards Branch

, Division of Radiation Safety and Safeguards l

SUMMARY

Scope: This routine, unannounced inspection involved management controls, nuclear criticality safety, operations review, maintenance and previously identified followup items.

Results: With the scope of the inspection, no violations or deviations were identified.

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8806280250 080616 I PDR ADOCK 07001151 j C DCD l

JUN 161988 REPORT DETAILS

1. Persons Contacted Licensee Employees

• J. S. Baker, Senior Regulatory Engineer-W. L. Goodwin, Manager, Regulatory Affairs J. B. Hooper, Safety Engineer

• J. Hubich, Manager, Chemical Manufacturing

• G. D. LaBruyere, Manager, MAP Operations

• E. P. Loch, Plant Manager

• R. O. Montgomery, Regulatory Engineer

• L. K. Reitler, Manager, Regulatory Engineering J. B. Spangler, Manager, Maintenance Engineering & Technical Support

• G. D. Workman, Manager, Analytical Services 1

Other licensee employees contacted included engineers, technicians, ,

foremen, operators and mechanics.

• Atterded exit interview .

2. Nuclear Criticality Safety Analyses (88015) i

a. The licensee has issued Procedure RA-305, Nuclear Criticality Safety Evaluations Using the NITAWL-XSDRN-KENO Code System, for performing l nuclear criticality safety evaluations. The inspector reviewed the

! procedure and verified that it had been reviewed and approved in i 2

accordance with the license requirements. l l

b. As the use of the KENO code provides a new computational method for l the licensee, the inspector reviewed the validation packages referenced l in the procedure, the benchmark calculations and the verification review. The inspector determined that the validation package was consistent with Section 4.3, Validation of a Calculational Method, of ANSI /ANS-8.1-1983, Nuclear Criticality Safety in Operations with

Fissionable Materials Outside Reactors. The inspector had no further questions.

No violations or deviations were identified.

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3. Review of the Operational Safety Assessment Findings (88025, 92701)  !

a. An Operational Safety Assessment was conducted by the NRC at the licensee's facility in January 1987, Findings of the assessment were

, reported in Inspection Report 70-1151/87-01. By letter dated May 21, 1

1987, the licensee responded to the assessment findings and described i

the corrective actions being taken on the identified weaknesses and improvement items.

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b. The inspector reviewed the status of the corrective actions with licensee representatives. The licensee has placed these items into the computerized Commitment Tracking System, ' and has identified responsible individuals and target completion dates for each time. '

For those items which have been completed, the tracking system identifies the action and completion date. The status of open items

is periodically updated,

c. The following IFIs identified in the Operational Safety Assessment i i were reviewed during the inspection.

(1) (0 pen) 87-01-03. Issue Procedure RA-303 for control of moderat-ing materials. The procedure for controlling moderating materials is in review / concurrence after changes / clarifications were made.

The cognizant supervisor. projected an issue date of-the first week in June 1988.

(2) (0 pen) 87-01-08. Establish a comprehensive fire prevention / fire ,

protection program. A contractor performed a Fire Hazard Analysis in 1987 which produced sixteen general recommendations as well as specific recommendations for individual fire zones or areas. The risk management committee is overseeing the implemen- ,

tation of the recommendetions. Physical changes (protective .

barriers, ventilation modifications, heat detectors) are in progress. ,

Fire hazards analyses for individual areas are being prepared, 1 which will be factored into the final program. The completion I date for the final program is currently December 1988.

(3) (Closed) 87-01-11. Emergency / Fire Brigade Training. The licensee is conducting training using the Fire. Ground Commander training program published by the NFPA. Additionally, scenarios identified in the Fire Hazards Analysis have been provided to the South Carolina Fire Academy for inclusion in the annual }

brigade training. '

The remaining item in training of the brigade is the use of

. specific fire plans for the areas. The IFI is closed for record purposes as the training on the specific fire plans is also being tracked under the IFI 87-01-14. It will be reviewed as part of that IFI.

(4) (0 pen) 87-01-14. Develop Specific Fire Plans. The specific l j plans for areas of the plant are b31ng developed from the i contractor's analysis and other inputs. Brigade training is being conducted for the different areas as plans are completed.

The completion date for the development of the plans and training

of the brigade members is December 1988.

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(5) (Closed) 87-01-17. Adequacy of Fire Hydrants and Hose House.

The evaluation of the fire hydrants and hose houses conducted by a contractor concluded that the existing fire hydrant system was adequate, and the system was acceptable. No further action is required.

(6) (0 pen) 87-01-23. Color Coding and/or Labeling of Chemical Service Piping. Facilities Procedure FP-107-A, Equipment General Specifications, specifies the color coding of piping and machinery. Regulatory Engineering personnel are including this in the safety portion of the Review Request for facility changes 4 or modifications.

During tours of plant areas, the inspector observed the coding and labeling of piping for the vaporization and conversion areas had been renewed and was very clear. However, in the MAP areas, the false ceiling had been removed and the areas painted a flat ,

black. This painting had included all of the piping, conduit and structural supports. Hazardous chemical lines or compressed -

gas lines could not be distinguished from structural supports.

Licensee management acknowledged that this is an unsatisfactory I condition and stated that the piping in MAP would be reviewed and banded or labeled to identify the various lines. ,

(7) (Closed) 87-01-24. Include Safety Precautions in itandard Operating Procedures. The incorporation of safety precautions into the procedures is an on going program, but the five ,

principal Chemical Operating Procedures-(COP-810XXX series) have '

been revised to incorporate special precautions, regulatory requirements, interlock descriptions and operating parameters.

(8) (Closed) 87-01-28, Reliability of Hydrofluoric Acid Monitors.

The licensee conducted a review of availability of hydrofluoric l acid (HF) monitors and determined that other available monitors ,

were no more reliable than the existing monitors. The HF monitors are out of service and will not be replaced.

The HF monitors were intended as a secondary monitoring system. l Piping modifications and maintenance have reduced the leakage I problem and the conductivity monitoring system (primary monitors) '

has been operating reliably. The discontinued use of the HF i monitors appears to be an acceptable step. l 4

l i (9) (Closed) 87-01-29. Testing of Pressure Relief Valves on Vaporizers. New relief valves have been installed on all of the j staam vaporizers. The valves have been entered into calibration i i program for annual tests and five year replacement.  !

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(10)(Closed) 87-01-30. Checking Specific Gravity 'in Battery Pilot Cells. The licensee had -instituted a weekly check of the specific gravity (SG) of battery cells- for the four emergercy diesel generators and the' diesel-driven fire pump. Readings e were recorded on the diesel ' test record - However, such checks had not been incorporated into procedures, nor had limits for the SG reading?' baan specified. After discussions with the cognizant supervisor, he acknowledged that..the tests should be  :

formalized and limits specified. During the inspection, revisions to the five procedures were made to specify the SG checks and limits.

(11) (Closed) 87-01-31. Provide Maintenance ^ History for Diesels.

The maintenance schedules for the diesels are in the computer-

. controlled master schedule. This system tracks the scheduled activities and prints the work tickets when. required. Schedule completion and man-hours required are fed back to the. computer base.

Individual material historys for the diesels are maintained by the maintenance group in computer files. These historys are updated after each maintenance activity and include notes, observations, comments and - other pertinent information. This system provides access to data by unit or by problem.

(12) (0 pen) 87-10-34. Complete Modification Identified by the Risk Assessment Committee. The equipment has been installed for-the two remaining major modifications and some calibration work has a been performed. However, component repairs are necessary for  :

the UNH tank monitoring system, which require replacement of j some components.

The inspector noted that the addition of monitors and the associated alarms have not been addressed in procedures or work area postings. This wcs acknowledged by cognizant supervisors.

Responses to alarms will be incorporated into procedures. )

j 4. Operations Review (88020)

a. Tours During the inspection, tours were made of the various work areas to observe operations. Items reviewed or verified included:

(1) Special nuc' lear material was stored in arrays on carts and in ,

designated storagr. locations in accordance with posted instruc-i tions.

I (2) Scales used for control of special nuclear material had been I i

calibrated and had stickers affixed indicating the next calibra-tion due date.

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S-(3) Housekeeping in all areas was acceptable.

(4). Differential pressure readings in filters and. enclosures were

within the authorized limits.

(5) Positive pressure readings on the IFBA glove boxes were within the license limits.

No violations or deviations were identified.

b. Fuel Handling and Storage 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 completed rods were in accordance with the

. license requirements for slab thickness and unit separations.

No violations or deviations were identified.

5. Exit Interview The inspection scope and. findings were summarized on May 20, 1988, with the persons indicated in paragraph 1. No dissenting comments were received from the licensee. Proprietary materials were reviewed during the inspec-tion but no proprietary material is discussed in~this report.

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