ML20209F074

Insp Rept 70-7001/99-09 on 990621-25.No Violations Noted. Major Areas Inspected:Insp Noted That Operators Response to Small UF6 Release in Building C-337A Was Effective & Consistent with Guidance Provided in Alarm Response

ML20209F074
Person / Time
Site:	07007001
Issue date:	07/09/1999
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20209F066	List: ML20209F061 ML20209F074
References
70-7001-99-09, 70-7001-99-9, NUDOCS 9907150212
Download: ML20209F074 (10)

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U.S. NUCLEAR REGULATORY COMMISSION l

REGION lli Docket No: 70-7001 Certificate No: GDP-1 Report No: 70-7001/99009(DNMS)

Facility Operator: United States Enrichrnent Corporation Facility Name: Paducah Gaseous Diffusion Plant- 1 l

Location: 5600 Hobbs Road P.O. Box 1410 ,

Paducah,KY 42001 )

1 Dates: June 21 through June 25,1999 Inspector: T. D. Reidinger, Senior Fuel Facilities inspector Approved By: Patrick L. Hiland, Chief, Fuel Cycle Branch Division of Nuclear Materials Safety l

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l 9907150212 990709 PDR ADOCK 07007001 C PDR

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l EXECUTIVE

SUMMARY

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United States Enrichment Corporation Paducah Gaseous Diffusion Plant NRC Inspection Report 70-7001/99009(DNMS)

Plant Sucoort

• The inspector ncted that the operators' response to a small uranium hexafluoride release in Building C-337A was effective and consistent with the guidance provided in the alarm response, off-normal and emergency procedures. (Section E1.1) -

e The inspector noted that routine radiation survey requirements were met, radiological instrumentation was properly maintained, seal source leak test and survey techniques were satisfactorily conducted in accordance with the appropriate procedures. (Section R1.1) e The inspector noted that the intemal dosimetry program was effectively implemented through extensive dose investigations in addition to good employee participation in the routine urinalysis bloassay program. (Section R1.2)

• The inspector concluded that the certificates was effectively implementing its radioactive materials transportation program. Selected records and surveys reviewed for the  !

shipment of radioactive materials were in accordance with both the Department of I Transportation and NRC regulations. Procedures for the performance of transportation t activities were adequate. (Section T1.1)

• The inspector concluded that the waste management staff implemented an effective program for the management of various waste streams generated onsite, as evidenced by overall reductions in waste streams over the past several calender years. (Section W1.1) 2

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Report Detalls IV. Plant Support E1. Conduct of Emeraency Preoaredness Activities E1.1 Buildina X-330 Emeraency Resoonse Observations

a. "Insoection Scooe (88050)

The inspector observed the plant staff's response to an unexpected uranium hexafluoride (UF.) release in Building C-337A.

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b. Observations and Findinas On June 23, the Building C-337A Area Control Room operators and facility manager were conducting valving operations to facilitate the evacuation of various UF, process headers and observed that UF, was leaking from a UF. header isolation valve (SE3E). l The building manager directed that the area be evacuated and notified the Plant Shnt I Superintendent (PSS) of the event. The PSS initiated an emergency squad response to  ;

the scene.

During the emergency squad response, which lasted approximately 2-hours, the PSS, I acting as the Incident Commander, directed several actions, including: l

• The sheltering of all building personnel, as appropriate;

• The monitoring and assessment of airbome UF, hydrolyzation products such as uranyl and hydrogen fluorides;

• The coordinating, with the building manager, of actions required to isolate the leaky valve and to determine that the leak was minor in nature;

• The posting of affected areas as airbome contamination areas based upon sampling results; and,

• The mitigation, cleanup, and subsequent retum of the affected areas to normal operations. I 1

Following the event, the inspector reviewed operations alarm response, off-normal l

-- ' procedures and emergency procedures relative tc the event. The inspector noted that l the operators' actions were consistent with the procedures.

c. Conclusions The inspector noted that the operators' actions were effective and consistent with the guidance provided in the alarm response, off-normal procedures and emergency proceduras for a small UF release.

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i R1. Radiation Protection R1.1 Radiation Protection Routine Ooerations

a. Inspection Scooe (83822)

The inspector interviewed health physics technicians (HPT) and accompanied HPTs on routine radiological surveys. During facility tours, the inspector checked the operability of radiologicalinstrumentation.

b. Observations and Findinas The inspector accompanied HPTs on numerous routine radiological contamination (

surveys in the cascade process buildings and observed radiological surveys of various floors and major pieces of equipment located in contamination control zones. {j Survey techniques were consistent with good health physics practices and plant j Procedure CP44HP-RP2101," Performance of Radiological Surveys." A review of j routine survey frequencies and randomly selected survey records indicated that the

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requirements of Appendix D," Removable Contamination Survey Frequency," were met.  !

During tours, the inspector checked calibration intervals and daily radiological , l Instrumentation source check records. Radiological instrumentation were either in i calibration, with a daily source check performed, or properly tagged out of service, per j the requirements of Procedure UE2-HP-RP1033," Radiological Instrumentation." The  !

Inspector observed that a HPT conducted a sealed source leak test that was consistent i with applicable health physics procedures.

The inspector observed that several electronic calibration staff had calibrated various pieces of radiological instrumentation in accordance with applicable vendor technical manuals. Review of the training records for the electronic calibration staff and manager indicated that the training was consistent and current with applicable training ,

development and administrative guidelines. Interviews with the calibration staff and j manager indicated that staff and manager were knowledgeable regarding industrial practices relating to current calibration techniques for radiological instrumentation.

. During interviews with HPTs, the inspector noted a consistency between plant policies ,

and HPTs issuance of problem reports (assessment and tracking reports). Interviews

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with HPTs highlighted that it was clear to the HPTs when problem reports should be initiated; as a result, problem reports were generated accordingly. The inspector reviewed, Procedure CP2-BM-CI1031," Corrective Action Process," with the HPTs. The HPTs explained to the inspector what types of incidents were required to be reported, and that the procedure included violations of radiation protection requirements as an example. During the inspection, the inspector observed several instances of problem reports being processed for various radiation protection violations identified by the HPTs.

The inspector reviewed the following audits: 1) 1997 Radiation Program;

2) 1998 Radiological Protection Program; and,3) 1998 Radiation Program. The audits were conducted by either the radiation protection manager or the intemal assessment staff. The audits evaluated the adequacy and effectiveness of the radiation protection program to assure compilance with the regulatory requirements. In addition, the audits addressed administration, training, field operations, dosimetry, 4

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i instrumentation, and site characterization using performance-based observations of field l activities, compliance reviews and staff interviews. The inspector noted that the audit I findings were adequately addressed by the staff via the corrective action program. The l

, inspector agreed with the audit conclusions in that increased management attention was j warranted to improve the radiation protection program's general radiation worker {

compliance.  !

c. Conclusions The inspector noted that routine radiation survey requirements were met, radiological I instrumentation was properly maintained, sealed source leak test and survey techniques were satisfactorily conducted with the appropriate procedures. The inspector noted that the HPTs had adequate general knowledge regarding the issuance of problem reports j for radiation protection deviations. Training records for the electronic calibration staff and manager indicated that the training was consistent and current with applicable training development and administrative g'idelines. Calibration staff and managers i were knowledgeable regarding industrial practices relating to current calibration i techniques for radiological instrumentation. Audit findings were adequately addressed )

by the staff via the corrective action program. l t

R1.2 Internal Dosimetry Proaram

a. Inspection Scope (83822)

The inspector reviewed the plant's intemal dosimetry program and current bloassay data for plant personnel. Several intemal dose investigations for bloassay resu'ts, in  !

exceedance of administrative plant limits, were also reviewed.

b. Observations and Findinos The inspector reviewed the intemal dosimetry program procedures and noted that the procedures implemented the intemal dosimetry program as described in Safety Analysis Report Section 5.3.2.3. Routine employee bloassays were conducted monthly, and employee delinquencies for late participation were low. The inspector verified that employees, who did not submit samples within 10 days of the scheduled test date, were placed on radiological work restrictions until the routine bloassay was performed. Placement of employees on work restrictions was required by Procedure CP2-HP-DS1030,"Paducah Gaseous Diffusion Plant Urinalysis Program for the Detection of Intakes of Radionuclides."

Procedure CP4-HP-DS7600," Routine and Special Bioassay," listed scheduling criteria, frequencies and protocols for the bloassay program. The inspector reviewed the current list of plant personnel participating in the intemal dosimetry program and found the practices to be in accordance with the procedural requirements. Intemal dosimetry logs indicated special bloassays were conducted according to the criteria described in Section 6.4.2, of Procedure CP4-HP-DS7600.

Appendix C of Procedure CP2-HP-DS1030 established three administrative action levels for uranium bioassay exposure results. The limits were 5,20 and 40 rr"rograms per liter of uranium (ug/L). A bloassay result of 5 g/L required re-sampling. Bioassay 5

m results in excess of 20 ug/L required an investigation, in addition to periodic re-sampling until bioassay results retumed to levels below 5 g/L. Bioassay results in excess of 40 pg!L required employees to be restricted from radiological areas, in addition to the requirements imposed when bioassay results exceed 20 ug/L. The inspector reviewed corresponding investigation reports of approximately 4 bioassay results that exceeded 40 g/L from Januay 1998 to June 1999. The inspector determined the investigations were thorough and extensive in determining tne root cause of the uptakes. Several other investigations for bioassay results above 20 pg/L, but below 40 g/L were also reviewed and determined to be equally thorough and extensive. All re-samples for bioassays abova administrative limits were conducted until a final result below 5 g/L was observed. The inspector verified that workers whose bloassays were in excess of 40 g/L were placed on a work restriction until bioassay re-samples indicated results below 5 g/L.

A review of 1998 and 1999 (first quarter) dosimetry data for the plant illustrated that the maximum Committed Effective Dose Equivalent respectively was 4 millirem and 3 millirem. The maximum Total Effective Dose Equivalent for 1998 and 1999 (first quarter) respectively was 382 mlIlirem and 110 millirem. These maxima were below 10 percent of the 10 CFR 20 maximum dose for radiation workers.

c. Conclusions The inspector noted that the intemal dosimetry program was effectively implemented through extensive dose investigations in addition to good employee participation in the routine urinalysis bioassay program. The intemal dosimetry program was implemented in accordance with Safety Analysis Report Section 5.3.2.3.

T1 ' Transportation T1.0 Conduct of Transportation Activities T1.1 Observation of Radioactive Material Shloments

a. [rlspection Scooe (86740)

The inspector reviewed selected records for the shipment of radioactive materials, including surveys of packages for radioactive contamination, intemal process documentation, and shipping papers,

b. Observations and Findinos The inspector reviewed the final packaging of randomly selected chipments and shipping papers of various radioactive shipments made to authorized licenses. The inspector's review included the following: 1) Bills of Lading; 2) Shipping records;

3) Procedure Inspection forms; and,4) Exclusive use vehicle instructions to carriers as applicable for approximately 10 shipments made between October 8,1998, to June 25, 1999. The review of documentation regarding the radioactive shipments indicated that the appropriate radiological surveys and inspections of packagings were performed prior

' to shipment, and removable contamination and radiological surveys were below the limits specified in 49 CFR 173.443. A review of shipping papers also verifed that the information required by both 49 CFR 172 and 10 CFR 20 was available in the shipping 6

documentation. In addition, the shipments were appropriately labeled, placarded and marked in accordance with 49 CFR 172.

On June 25, the inspector observed two traliers that had been loaded with metal melt shipping containers in preparation for transport. The loaded containers were appropriately marked and labeled, braced and fastened for shipment as required by 10 CFR 71 and the Department of Transportation (DOT) regulations. Shipping papers prepared for the shipments conta!ned the bill of lading with correct identification of container contents, shipper's certification, exclusive use requirements as applicable, and emergency response information, as required by DOT regulations, in addition, the inspector noted that the trailers ware appropriately placarded for the shipment. The inspector observed and discussed the shipment of radioactive materhl with the transportation manager who was certified as a packaging and transportation specialist.

In addition, the inspector reviewed the training records and the certificatee's procedures

' for the shipments of radioactive matsrial. The inspector noted the transportation staff training was consistent with requirements listed in the training development and administrative guidelines. Interviews with the transportation staff indicated that the staff was knowledgeable of the applicable transportation requirements and that the transportation procedures contained adequate information fcr the preparation and shipment of radioactive materials from the plant site

c. Conclusions The inspector concluded that the certificatee was effer/Jvely implementing its radioactive materials transportation program. Staff performing these activities were adequately trained on the procedures and qualified for the applicable assigned tasks. Selected records and surveys reviewed for the shipinent of radioactive materials were in accordance with both the DOT and NRC regulations. Procedures for the performance of transportation activities were adequate and provided plant staff with the appropriate information to ship materials in accordance with the DOT and NRC regulations.

W1 Radioactive Waste Management W1.0 Conduct of Radioactive Waste Management Activities (88035)

W1.1 Review of Onsite Radioactive Waste Manaaement

a. Jnsoection Scone (88035)

The inspector reviewed the overall implementation of the onsite radioactive waste management program with the waste management staff. The inspector also observed the shipment of low level radioactive waste offsite. j

b. Observations and Findinas

' The inspector reviewed and discussed overall waste management data from calender year 1997 to the present with cognizant waste management staff. Waste management data indicated that for the hazardous and mixed waste streams onsite, an overall average reduction of 40 percent of the waste volume was observed from 1997 to the j present.  !

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I t f The inspector also reviewed data for low level radioactive waste generated onsite. Data for the loiv level radioactive waste streams onsite indicated an overall average reduction of 23 percent of the waste volume from 1997 to the present The inspector also reviewed the methods used to characterize onsite low level radioactive waste, as documented in KY/R-15, " Characterization of Low Level Radioactive Waste." Review of this document and interviews with the waste management staff indicated that the program for the characterization of low level radioactive waste was comprohensive and conservative.

c. Conclusions The inspector concluded that the waste management staff implemented an effective program for the management of various waste streams generated onsite, as evidenced by overall reductions in waste streams over the past several calendar years.

V. Manaaement Meetina X Exit Meeting Summary The inspector presented the 1.ispection results to members of the plant staff and management at the conclusion of the inspection on June 25,1999. The plant s'aff acknowledged the findings presented. The inspector asked the plant staff whether any materials examined during the j inspection should be considered proprietary. No proprietary infonnation was identified.

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PARTIAL LIGT OF PERSONS CONTACTED United States Enrichment Corooration

• L. Albritten, Nuclear Regulatory Affairs Staff

• M. Allen, Health Physics Manager

• L. Beach, Waste Management Manager

• M. A. Buckner, Operations Manager

• R. Cothron, Calibration & Electronics Group Manager

• L. L. Jackson, Nuclear Regulatory Affairs Manager ,

• S. R. Penrod, Enrichment Plant Manager I

• H. Pulley, General Manager

• M. Sampson, Shipping & Transportation Manager "4 Shanks, Production Support Manager "J. Sheppard, Calibration & Eiactronics Group Manager ,

• R. Starkey, Training Manager

• J. Wittman, Work Control Manager

• Denotes those present at the exit meeting June 25,1999.

Other members of the plant staff were also contacted during the inspection period.

IlSPECTION PROCEDURES USED I

IP 83822: Radiation Protection -

IP 88050: Emergency Preparedness ,

IP 80740: Transportation IP 88035: Radioactive Waste Management ITEMS OPENED, CLOSED, AND DISCUSSED Opened None Closed l None Discussed None 9

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l LIST OF ACRONYMS USED l 1

CFR Code of Federal Regulations DOT Department Of Transportation HPT Health Physics Technician l NRC Nuclear Regulatory Commission )

PSS Plant Shift Supervisor UF. Uranium Hexafluoride USEC United States Enrichment Corparation i

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