ML20217B480

Insp Rept 70-1201/99-03 on 990823-27.No Violations Noted. Major Areas Inspected:Plant Operations,Mgt Organization & Controls,Maint/Surveillance & Training

ML20217B480
Person / Time
Site:	07001201
Issue date:	09/21/1999
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20217B467	List: ML20217B461 ML20217B480
References
70-1201-99-03, NUDOCS 9910120269
Download: ML20217B480 (10)

Text

.~ -

U. S. NUCLEAR REGULATORY COMMISSION REGION 11 Docket No.: 70-1201 License No.: SNM-1168 Report No.: 70-1201/99-03 Licensee: Framatorne Cogema Fuels Facility: Lynchburg Manufacturing Facility Location: Lynchburg,VA 24506 Dates: August 23 through 27,1999 Inspector: D. Ayres, Sr. Fuel Facility inspector Approved By: E. McAlpine, Chief Fuel Facilities Branch Division of Nuclear Materials Safety 9910120269 990921 PDR ADOCK 07001201 C PDR Enclos Jre

1, .- -- ,

1 EXECUTIVE

SUMMARY

.The primary focus of this routine unannounced inspection was the evaluation of the licensee's - t

. conduct of plant operations, management controls, training, and maintenance. The report  !

covered a one-week period and included the results of the inspection efforts of one regional fuel I

facility inspector. '

I i

Plant Operations  !

l

- *- . The processing of pellets, rods, and assemblies was performed in accordance with l

" posted safety requirements. Housekeeping was adequate to Avent spread of l contamination outside controlled areas and to ensure proper emergency routes. -!

(Section 2.a) i i

• - Safety controls for handling and movement of completed fuel assemblies were ,

adequately implemented. (Section 2.b) l l

Manaaement Oraanization & Controls I

~

Proposed changes to the facility potentially affecting nuclear criticality or radiological safety were adequately reviewed for safety issues. Any safety issues identified were adequately addressed prior to implementing the changes. (Section 4.a) l Maintenance / Surveillance )

• , Calibrations for criticality detection systems and portable radiation detectors were- l' adequately performed. The repair history of criticality detectors needed monitoring such that detectors with lower reliability could be identified and replaced. Certain safety technicians lacked specific knowledge in basic health physics. (Section 5.a)

Trainina e '. ~ General employee training and controlled area access training adequately covered l the required topics. Training was enhanced by using a computerized presentation. '

(Section 6.a) i l

j l

l

)

REPORT DETAILS

1. Summary of Plant Status This report covered the efforts of one regional inspector during a one week period.

Routine operations were ongoing at Framatome during the week. A new rod washing system was being installed and tested. There were no unusual plant operational occurrences during the onsite inspection.

2. Plant Operations (03)(IP 88020)

a. Conduct of Ooerations (O3.01) and Housekeepina (O3.06)

(1) Insoection Scope Operations were observed in pellet handling, rod filling, and Service Equipment Refurbishment Facility (SERF) areas for verification of adherence to safety requirements.

(2) Observations and Findinas The inspector toured the process areas and observed routine rod loading, bdle assembly, and material handling operations. The inspector examined the pellet receiving bay, the pellet transport corridor, the fuel assembly storage area, and the fuel assembly shipping area and found that safety postings were obeyed. The inspector also l

observed that there were no signs of material spillage in pellet handling areas. The inspector observed in these and other areas that routes of egress were adequately clear of debris.

Conclusions l (3) j The processing of pellets, rods, and assemblies was performed in accordance with posted safety requirements. Housekeeping was adequate to prevent spread of contamination to the non controlled areas and to ensure proper emergency routes.

b. Implementation of Safety Controls for Material Handlina and Movement (03.05)

(1) [nfoection n Scope l

Safety controls for handling of completed assemblies were reviewed to verify that they were in place (engineered controls) or documented in procedures or postings (administrative controls) and were properly implemented.

(2) Observations and Findinas l The inspector reviewed the licensee's various procedures for packaging, shipping, l unloading, and storing fuel assemblies. The inspector noted that the procedures contained adequate instructions for the safe handling of fuel assemblies being  !

transported between the storage, inspection, and shipping / receiving areas. The l

p

)," .

f'

/ ,

2 inspector observed the handling of completed assemblies and found that pertinent safety controls were properly used.

(3): Conclusions -

Safety controls for handling and movement of completed fuel assemblies were

l. adequately implemented.

c. Follow up on Previousiv identified issues (O3.08)

(1) Insoection Scoce .

The licensee's preparations for handling potential difficulties associated with the effect of the year 2000 on computerized systems was evaluated for completeness.

(2) Observations and Findinos The inspector reviewed the licensee's plan for testing on site computer systems and interfacing with off-site utility providers. The inspector found that the licensee's plan was methodical and appeared to cover all pertinent operational and safety systems. The licensee had completed its test plan and corrected any potential deficiencies of on site systems. The inspector was notified that local utility providers (power, water, gas) were confident in providing services through the change to the year 2000, but were unable to provide guarantees of uninterrupted service. The inspector found that the licensee's plan to shut down the facility at the end of the year would provide adequately cafety in case of temporary utility disruption.

l (3) Conclusions The licensee's preparations for potential computer problems due to the year 2000 date were adequate to prevent safety implications.

3. Fire Safety (04)(IP 88055)

a. Follow up on Previous!v Identified issues (O4.11)

(1) Inspection Scoue -

The adequacy of the licensee's corrections to drawings enclosed with the pre-fire plan as identified in Inspector Follow-up ltem (IFI) 98-04-01 was evaluated.

(2) Observations and Findinas Inspector Follow-Up Item 98-04-01 involved incorrect drawings associated with the licensee's pre fire plan. When IFl 98-04-01 was identified, post valve No.17 was not

. correctly shown on the drawings at its present location, hydrant No.18 was not accurately numbered in the drawings, and there was no hydrant No.19 contrary to the l

L l

a :- .

3 drawings. The inspector reviewed the revised Pre-Fire Plan and the accompanying plant fire water loop drawings. The inspector field-verified that the revised drawings correctly depicted the location and numbering of the fire water loop valves and hydrants.

(3) Conclusions The fire water loop drawings were adequately corrected and IFl 98-04-01 was closed.

)

i

4. Management Organization & Controls (05) (IP 88005)

a. Internal Reviews and Audits (O5.03)

(1) Insoection Scooe Pre-operational evaluations were reviewed for each new operation and facility established in fiscal year 1999 to verify that adequate safety reviews were conducted per section 2.3.1 of the License Application.

(2) Observations and Findinas The inspector reviewed the records of facility changes proposed and/or performed during the past twelve months. The inspector identified four such changes as relevant to nuclear criticality or radiological safety; the decontamination of the wet weather stream, the installation of a portable laboratory for SERF-3, the replacement and relocation of the fuel rod washer equipment, and the relocation of a Low Level Waste evaporator in SFRF-4. The inspector reviewed the project file for each of these four projects and found that three of them were adequately reviewed for addressing potential nuclear criticality or radiological safety concems. The inspector found that safety concerns identified during these reviews were appropriately addressed prior to implementation of l the facility change. The fourth project (relocation of the SERF-4 evaporator) was not yet I approved and was still under review. The inspector also found no significant process i changes that were not placed in the licensee's pre operational review system.

(3) Conclusions  !

Proposed changes to the facility potentially affecting nuclear criticality or radiological safety were adequately reviewed for safety issues. Any safety issues identified were adequately addressed prior to implementing the changes.

5. Maintenance / Surveillance (F1) (IP 88025) l

a. Calibrations of Eauioment (F1.07) j (1) Inspection Scope )

Calibrations for the criticality monitoring system and instrumentation used for l

- documented survey results were reviewed to verify they were performed per sections 3.2.4.3 and 3.2.4.4 of the License Application.

I A.

~ .

4

'(2)- Observations and Findinos The inspector reviewed the calibration records for the licensee's criticality detection and l alarm system. The inspector found that these calibrations were performed at the proper l annual frequency. The inspector also found that detection equipment found to be i outside tolerance ranges for sensitivity was promptly removed from service and repaired. ]

The inspector also observed that certain detectors were required to undergo repairs for the last in or three consecutive years, while others did not require any repairs in the last several years. The inspector discussed, with the licensee, the importance of reviewing tha repair history of criticality detectors such that detectors with lower reliability can be identified and replaced. The licensee indicated that detectors requiring frequent (annual) repairs would be considered for replacement.

The inspector reviewed the calibration records for the licensee's Model E-120 portable radiation detectors. The inspector found that these calibrations were performed at the proper semiannual frequency. The inspector also found that proper adjustments were made to the equipment to maintain the instrument's calibration. However, the inspector noticed that the calibration records showed the activity level of the cesium source used to calibrate these instrumerits varied sporadically over the past several years. Upon further investigation, it was found that, at times, the technicians performing the calibrations had recorded the dose rate from the calibration source at a distance of 18 inches, as the activity of the source. Other times, the actual activity was recorded in millicuries; or the millicurie value was recorded, but given units of millirem per hour. The inspector found that this confusion did not affect the calibration of the instruments because the calculated dose rate based on the calibration source's activity was properly used in the calibration. However, the inspector found that this did indicate a lack of technical knowledge and attention to detail by some of the safety staff. The inspector discussed this apparent confusion with licensee management who indicated that although the technicians were trained and qualified in performing equipment calibrations, some of them lacked specific knowledge in basic health physics, leading to the erroneous values entered on the calibration records. The licensee indicated that they were pursuing additional training for safety technicians to improve the overall knowledge base of the staff.

(3) Conclusions Calibrations for criticality detection systems and portable radiation detectors were adequately performed. The repair history of criticality detectors needed monitoring such that detectors with lower reliability couid be identified and replaced. Certain safety technicians lacked specific knowledge in basic health physics.

.~ .

5

6. Training (F2) (IP 88010)

a. 10 CFR 19.12 Trainina (F2.01). General Nuclear Criticality Safety Trainina (F2.02).

General Radioloaical Safety Trainino (F2.03). and General Emeroency Trainina (F2.04)

(1) Insoection Scoce General safety training was reviewed to verify that required topics were adequately covered.

(2) Obsen/ations and Findinas The inspector attended sessions for general employee training and controlled area access training, The inspector observed that all pertinent topics involving nuclear criticality safety, radiological safety, general emergency response, and 10 CFR 19.12 were adequately covered. The inspector also noted that the new computerized presentation format kept trainees rnore focused, and enhanced the quality of the trainir..

(3) Conclusions i

General employee training and controlled area access training adequately covered the required topics. Training was enhanced by using a computerized presentation.

7. Emergency Preparedness (F3) (IP 88050)

c. Follow uo on Previously identified issues (F3.07)

(1) Inspection Scooe The licensee's actions on a) IFl 98-01-01 concerning resolving a procedure inconsistency on when to notify offsite authorities following an emergency classification, and b) IFl 98-01-03 concerning improvements in tracking and correcting deficiencies identified during drills and exercises, were reviewed to determine adequacy for closure.

(2) Observations and Findinas The inspector reviewed the licensee's Emergency Procedure SL-1308 that was rewritten and renumbered to replace procedure AS-1106. The revised procedure included notification requirements for each type of emergency situation, organized i7 a set of Required Action Matrices. These matrices referenced another procedure (SL-1010) when emergency situations required notification of the NRC. This placed all NRC notification instructions in a specific procedure and eliminated the confusion of having conflicting notification instructions in multiple areas of the emergency procedure. Thus, IFl 98-01-01 was closed.

The inspector also reviewed procedure SL-1308 to determine the licensee's revised method for tracking and correcting deficiencies identified during drills and exercises. The inspector observed that specific instructions were included in the procedure to ensure

6 that problems identified during emergency drills and exercises would be documented, tracked, and resolved utilizing the licensee's " Corrective Action Request" (CAR) system.

This CAR system was already used for identifying and tracking quality and safety issues identified through various means throughout the facility. The inspector reviewed the CAR system and found it to be an adequate vehicle for tracking problems identified during emergency drills. Thus, IFl 98-01-03 was closed.

(3) Conclusions The licensee's actions were adequate for eliminating conflicting notification instructions and for improving the tracking of problems identified during emergency drills and ,

exercises. Inspector Follow-up Items 98-01-01 and 98-01-03 werc closed. '

8. Exit Meetings On August 27,1999, the inspection scope and results were summarized with licensee representatives. The inspectors discussed, in detail, the routine program areas inspected, and the findings. No dissenting comments were expressed by the licensee.

The licensee supplied proprietary materials during the inspection, although proprietary information is not contained in this report.

eD

g.

y~ .

[ ATTACHMENT l

PARTIAL LIST OF PERSONS CONTACTED Licensee Personnel

• T. Allsep, Manager, Radiation Protection

!- ,

• C. Armontrout, Manager, Licensing and Quality Systems t' p M. Cox, Project Manager, Y2K Readiness

• A. Jenkins, Manager, Service Equipment Refurbishment Facilities l '

• G.' Lindsey, Health Physicist L

S. Wilkerson, Manager, Quality, Health & Safety, and Licensing Other licensee empivyees contacted included engineers, technicians, production staff, security, and office personnel.

• Attended Exit Meeting on August 27,1999 ;

INSPECTION PROCEDURES USED IP 88005 - . Management Organization and Controls IP 86010 Operator Training / Retraining l- IP 88020 Regional Nuclear Criticality Safety inspection Program

~ IP 88025 Maintenance and Surveillance.

IP 92701 Followup .

[ Tl 2600/003 Plant Operations -

' LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED Opened I- None I Closed I

(70-1201/98-01-01 IFl Resolve Emergency Procedure AS-1106 inconsistency regarding

! when to notify offsite authorities following an emergency 1 I

classification (Section 7.a).

70-1201/98-01-03 IFl Review the adequacy of the licensee's management control

system for tracking and correcting deficiencies identified during tills / exercises (Section 7.a).

70-1201/98-04 IFl Pre-Fire Plan drawings were inaccurate. Procedure No. SL 1316 needed text to explain the conduct of some tests (Section 3.a).

l L.

E I

3 ,

ACRONYMS i CAR Corrective Action Request CFR . Code of Federal Regulations IFl Inspector Follow-up item IP inspection procedure i SERF Service Equipment Refurbishment Facility i i

r l

l l

l l

l i

i I

J j

i e

er