ML20210R907

Insp Rept 70-1257/99-02 on 990712-16.No Violations Noted. Major Areas Inspected:Selected Aspects of Licensee Programs for Operational Safety,Radioactive Effluents,Environ Protection,Waste Mgt Programs & Followup of Open Items

ML20210R907
Person / Time
Site:	Framatome ANP Richland
Issue date:	08/12/1999
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20210R902	List: ML20210R896 ML20210R907
References
70-1257-99-02, NUDOCS 9908170253
Download: ML20210R907 (9)

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l ENCLOSURE 1 U.S. NUCLEAR REGULATORY COMMISSION REGION IV Docket Nos.: 70-1257  ;

License No.: SNM-1227 Report No.: 70-1257/99-02 Licensee: Siemens Power Corporation (SPC)

Facility: Siemens Power Corporation Location: Richland, Washington Dates: July 12-16,1999 Inspector: Wayne L Britz, Fuel Facility inspector Fuel Cycle Decommissioning Branch Division of Nuclear Materials Safety (DNMS)

Approved By: D. Blair Spitzberg, Ph.D., Chief Fuel Cycle / Decommissioning Branch, DNMS ATTACHMENT: Supplemental Inspection Information A

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1 9908170253 990012 PDR ADOCK 07001257 C PDR  ;

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1 2-EXECUTIVE

SUMMARY

Siemens Power Corporation NRC Inspection Report 70-1257/99-02 This routine, announced inspection included a review of selected aspects of the licensee's programs for operational safety, radioactive effluents, environmental protection, waste management programs and followup of open items from previous inspections.

Operational Safety

. Operations involving the processing of special nuclear material were in accordance with established safety requirements (Section 1.1).

Radioactive Waste Manaaement

. The licensee was adequately monitoring and controlling radioactive gaseous and liquid effluent releases. Effluents for the period reviewed were well below the limits specified in 10 CFR Part 20 indicating appropriato efforts by the licensee to maintain releases ALARA (Section 2.1).

Environmental Protection

. The licensee's environmental monitoring and audit program were conducted in accordance with commitments specified in the license application, the Safety Manual, and the licensee's implementing procedures (Section 3.1).

Waste Geneotor Reauirements and Low-Level Waste Storace

. The licensee's waste generation and low-level waste storage program were conducted in accordance with the license, the licensee's Safety Manual, and the implementing procedures (Section 4.1).

. The licensee was installing additional systems to improve the processing and control of radioactive waste (Section 4.1).

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Report Details Summary of Plant Status The plant was operating Lines 1,2 and 3 of the dry cc,nversion facility (DCF) intermittently as operations required. Uranium recovery activities were also in operation. Fuel pellet production, fuel rod loading, fuel bundle assembly operations, Solids Processing Facility (SPF) and the Lagoon Uranium Recovery (LUR) facility were also in progress. Fuel rod downloading, Modular Extraction / Recovery Facility (MERF), and the Solid Waste Uranium Recovery (SWUR) systems were not in operation.

1 Operational Safety (88020; T12600/003) 1.1 Insoection Scope General facility operations were reviewed to verify adherence to safety requirements documented in license conditions, criticality safety specifications, operating procedures, and area postings.

1.2. Observations and Findinas The inspector reviewed operations from the Dry Conversion Facility (DCF) control room observing the operators actions, observing systems operations and control of operating parameters. The inspector toured the operations in the UO, Building and attended the morning operations status meeting. The operators were observed to be conducting operations in accordance with current, approved operating procedures. The operators appeared to be well trained and knowledgeable of their duties.

The inspector reviewed the draft Criticality Safety Specification (CSS) and Criticality Safety Analysis for Waste Handling. The specification provided greater control for the collection, sorting and storage of waste items contaminated with relatively low amounts

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of uranium.

The inspector reviewed CSS postings in the UO, Building. The postings reviewed were acceptable, however, room for improvements were noted with the clarity of the CSS and i I

the array markings in the waste handling and assay area in the line 3 area, and in lowering the CSS at the entrance to the powder storage area to eyesight level. l 1.3. Conclusion I

Operations involving the processing of special nuclear material were in accordance with procedures and established safety requirements. ,

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2 Radioactive Waste Management (88035) 2.1 Inspection Scooe The inspector reviewed the licensee's program for ensuring that release of liquid, airbome, and solid wastes met the requirements of the license and regulations. The review included facility tours and review of licensee procedures and selected records.

2.2. Observations and Findinas

~ Responsibilities and controls required by Section 2.7.5, " Environmental Wotection

~ Inspechons," ar,d Section 5.1, " Effluent Controls," of Part I, of the licenu , and Section 13.2, " Gaseous Effluents," and Section 13.3, " Liquid Effluents," of Part II, of the license, and as further desenbed in the licensee's Safety Manual, EMF-30, Chapter 4.0,

" Environmental Standards," were reviewed. The procedures developed to implement this document were also reviewed. The monitoring, sampling, and analysis programs were being conducted as required. The instrumentation, calibrations, and procedures were adequate.

The effluent release records reviewed included radioactive gaseous effluent sampling and liquid releases to the sewer. EMF-94-100, Addendum 6," Environmental Monitoring Report Addendum - 1998," issued May,1999, and the required reporting of effluents per

'10 CFR 70.59 were reviewed. The 1998 gaseous effluent release's calculated dose to a person in the environment was 0.028 mrem / year. The liquid releases to the sewer (Richland Wastewater Treatment Facility) were <0.019 Curie. .The releases were well below the limits specified in 10 CFR Part 20 indicating appropriate efforts by the licensee to maintain releases As Low As Reasonably Achievable (ALARA).

2.3. Conclusions The licensee was adequately monitoring and controlling radioactive gaseous and liquid effluent releases. Effluents for the period reviewed were well below the limits specified )

i in 10 CFR Part 20 indicating appropriate efforts by;the licensee to maintain releases ALARA.

3 Environmental Protection (88045) 3.1 Inspection Scope s 9

The inspector reviewed the licensee's implementation of the environmental control program which included facility tours and review of licensee procedures, selected records of environmental sampling and internal auditing results for the past year to determine compliance with the license.

3.2. Observations and Findinas Responsibilities, controls, and the environmental surveillance program required by

. Section 2.7.5, " Environmental Protection inspections," and Section 5.2, " Environmental y

Monitoring," of Part I, of the license, and as further described in the licensee's Safety Manual, EMF-30, Chapter 4.0, " Environmental Standards," were reviewed. The procedures developed to implement this document were also reviewed.

The environmental records reviewed included. waste effluent monitoring and sampling for the wastes to the Richland Wastewater Treatment Facility; sludge and effluent sampling at the Richland Wastewater Treatment Facility; soil and forage samples; ambient air sampling on the surface in the environment; Lagoon liner sampling; ground water sampling; and fence line radiation level surveys (TLDs). The inspector reviewed the type equipment used, type of samples taken, and the results.

There were no significant changes in the measurements in the soil, forage, ambient air, wastes to or at the Richland Wastewater Treatment Facility and the fence line. There l was no leakage detected from the lagoon leak detection system.

l The present trend for gross alpha and gross beta in the ground water is level to slightly decreasing. There was an increase in two of the wells, GM-8 and GM-16, during 1998 which decreased later in the year. The levels correspond to prior years measurements 4

in these and/or other wells which were the result of lagoon leakage several years ago before the present double liner and liner leakage measurement system was installed.

The licensee's environmental audit program was consistent with Section 2.7.5,

" Environmental Protection inspections," Part I, of the license. These audits were effective in finding deficiencies, cuch as missed samples, that were tracked to resolution. Corrective actions were adequate.

3.3 Conclusions The licensee's environmental monitoring and audit program had been conducted in accordance with the license application, the Safety Manual, and the licensee's implementing procedures.

4 Waste Generator Requirements (84850) and LEiw-Level Waste Storage (84900) 4.1 !nspection Scope The inspector reviewed the licensee's implementation of the waste generator requirements and low-level waste storage program to determine compliance with the license. The review included facility tours and review of licensee procedures and*

selected records from the past year.

4.2. Observations and Findinas l Responsibilities and controls required by Section 6.4.2," Solid Radioactive Wasto," of Part I, of the license, and Section 10.4, " Radioactive Waste Handling," of Part 11, of the license, and as further described in the licensee's Safety Manual, EMF-30, Chapter 5.0,

" Radioactive Material Shipping Standard," were reviewed. The procedures developed to implement this document were also reviewed.

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. l 6-The inspector reviewed and toured the waste areas in the UO, Building, the assay and waste inspection area at Line 3, the waste storage pad, and the updated waste records and manifests data base program. The storage pad area appeared in good order with a good system for identification and retrieval of stored packages. The inspector observed the quality control personnel operate the new data base for container, container manifest, and waste package tracking and control. The inspector reviewed the documentation flow process through the various departments that interact with the waste handling program. The new program appeared adequate to document waste location and release status.

The inspector reviewed the status of waste processing through the Modular Extraction /

) Recovery Facility (MERF), Solids Processing Facility (SPF) and the Lagoon Uranium Recovery (LUR) facility. The SPF and LUR were in operation processing the lagoon wastes. MERF system modifications were in progress to improve portions of the processes. The FY99 Radioactive Solid Waste inventory graph of the waste volumes for disposition to the various process and storage locations was reviewed. When the licensee is able to operate the MERF to process the hazardous wastes in storage, the long range waste inventory reduction goals may be achievable.

The inspector toured and reviewed the new decontamination and volume reduction facility in construction. An area of the powder storage area in the UO, Building is being converted for the decontamination and volume reduction facility. A new air lock was installed for entry and exit of the wastes and to isolate the area from the building.

Process machinery was in place.

The inspector reviewed the new program to be instituted to provide greater control of any shipments of radioactive waste offsite. The program included demarcation of the facility into areas such that all wastes from potentially contaminated areas are packaged as radioactive waste in yellow bags, and waste from clean areas are packaged as clean waste in clear bags.

4.3 Conclusions The licensee's waste generation and low-level waste storage program were conducted in accordance with the license, the licensee's Safety Manual, and the implementing procedures.

The licensee was installing additional systems to improve the processing and control of radioactive waste.

5 Followup (92702) 5.1 (Closed) Violation 71-9248/9901-01. Example 2: Failure to crmoly with 10 CFR 71.12 Recuirements for the terms and conditions of the transport packaae certificate of compliance (Example 1 was previousiv closed),

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(Closed) Violation 71-9248/9901-03 Example 2: Failure to comniv with 10 CFR 71.133 reauirements to assure nonconformances are oromotiv identified and corrected (Example 1 was previousiv closed).

The inspector reviewed the licensee's response to the Notice of Violation dated June 15, 1999 which referenced the licensee's letter " Supplemental Information to Siemens Power Corporation (SPC) 10 CFR 71.95 Notification Reports Filed April 16,1999 and April 30,1999," dated May 21,1999. The inspector reviewed the licensee's corrective actions to comply with the violations which were the result of SPC's inspections of the Model M51032-1 shipping containers to assure compliance with the regulations.

The licensee's corrective actions were to perform a one-to-one correspondence -

between the features specified on the drawings. The dimensional measurements will either be recorded on the inspection plan or confirmed using certified templates. The inspechons will be performed by personnel using qualified inspection techniques specified in the inspection plan. Prior inspechons permitted a visual inspection to determine if the dimensions of the weld were acceptable. Current practice is a dimensional measurement or a template certification. Training will be provided to the inspectors and documented.

The inspector found that the licensee had implemented corrective actions identified as a result of the Quality self-assessment performed as a result of these violations as documented in the licensee's letter to NRC dated May 21,1999. Specifically, the licensee's revised inspection plans, re-inspections, improved inspection documentation, and enhanced training of the assigned inspectors were reviewed and found to be adequate. The corrective actions should assure both 1) compliance with the terms and conditions of the transport package certificate of compliance, and 2) prompt identification and correction of nonconformances, by improved inspection techniques to identify non compliance.

All of the M51032-1 containers had been inspected, removed from service, or placed on hold for other work. A record was generated of the inspection details for each container, These violations are closed.

6 Exit Meeting Summary The inspector presented the inspection results to members of licensee managerpent at the conclusion of the inspection on July 16,1999. The licensee did not identify any of the information discussed at the meeting as proprietary.

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ATTACHMENT SUPPLEMENTAL INSPECTION INFORMATION PARTIAL LIST OF PERSONS CONTACTED

- Licensee .

, B. F. Bentley, Manager, Plant Operations J. B. Edgar, Regulatory Compliance B. N. Femreite,- Vice President, Manufacturing K. L Ford, Manager, inspection Services E. . L Foster, Supervisor, Radiological Safety L E. Hansen, Manager, Manufacturing Engineering W. A. Koglin, Waste Management Engineering B. E. Lewis, Project Engineer, Plant Engineering L J. Maas, Manager, Regulatory Compliance C. D. Manning, Criticality Safety G. A. McGehee, Criticality Safety J. B. Perryman, Environmental group, Regulatory Compliance C. M. Powers, Vice President, Quality and Regulatory Affairs T. C. Probasco, Manager, Safety K. H. Tanaka, Environtnental group, Regulatory Compliance R. E. Vaughan, Manager, Safety, Security & Licensing INSPECTION PROCEDURES USED 88020; T12600/003 Operational Safety 88035 - Radioactive Waste Management 84850 Waste Generator Requirements 84900 Low-Level Waste Storage .

. 88045 Environmental Protection 92702 Followup Violations ITEMS OPENED, CLOSED, AND DISCUSSED Closed k, 71-9248/9901-01 VIO Failure to comply with 10 CFR 71.12 requirements for the terms and conditions of the certificate of compliance (Example 2 is closed; Example 1 was previously closed) 71-9248/9901-03 VIO Failure to comply with 10 CFR 71.133 requirement?to assure nonconformances are promptly identified and corrected (Example 2 is closed; Example 1 was previously closed) l - - _ - _ . _ _ . _ _

"~ 1 LIST OF ACRONYMS USED .

ADU ammonium diuranate-ALARA as low as reasonably achievable CAL confirmatory action letter CSS criticality safety specification DCF dry conversion facility DCS distributed control system GET general employee training IT information technology i I

LUR lagoon uranium recovery MERF modular extraction / recovery facility NRC Nuclear Regulatory Commission 1

PDR public document room QA quality assurance RWT radiological worker training SPC Siemens Power Corpnration SPF solid processing facility 1' SWUR solid waste uranium recovery TLD thermoluminescent dosimeter  ;

UO, uranium dioxide i URI unresolved item f VIO violation Y2K year 2000

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