IR 05000269/1990007
| ML15224A653 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/22/1990 |
| From: | Earnestine Clay, Mcguire D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML15224A652 | List: |
| References | |
| 50-269-90-07, 50-269-90-7, 50-270-90-07, 50-270-90-7, 50-287-90-07, 50-287-90-7, NUDOCS 9004030021 | |
| Download: ML15224A653 (11) | |
Text
C, REG(
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, &
ATLANTA, GEORGIA 30323 Report Nos.:
50-269/90-07, 50-270/90-07, and 50-287/90-07 Licensee:
Duke Power Company 422 South Church Street Charlotte, NC 2824 Docket Nos.: 50-269, 50-270, License Nos.: DPR-38, DPR-47, and and 50-287 DPR-55 Facility Name:
Oconee 1, 2, and 3 Inspection Conducted: February 26 - March 3,1990 Inspector:
&
1/
Ce E. L. C1 Saf uards Eng e
Date Signed Approved By:
D. uire, Chief Da e S gned Safeguards Section Nuclear Materials Safety and Safeguards Branch Division of Radiation Safety and Safeguards SUMMARY Scope:
This routine, unannounced inspection entailed a review of procedures, records, operations, and physical inventory for use, control and accountability of special nuclear materia Results:
No violations or deviations were identifie The licensee was noted to be handling MC&A documentation in an informal manner and had no formalized training program for MC&A personne These items are being corrected by the license C0403C)02 1 900322 PDRIJ ADCK 0500Q 69
REPORT DETAILS 1. Key Persons Contacted
- B. Barron, Oconee Nuclear Station, Station Manager
- P. Gillespie, Associate Reactor Engineer
- M. Hone, Reactor Engineer
- D. Hubbard, Performance Section Manager
- G. Lareau, Reactor Engineering Unit Supervisor
- E. La Gett, Shift Supervisor
- E. Price, Jr., Associate Reactor Engineer The inspector also interviewed several other licensee employee NRC Resident Inspectors
- P. Skinner, Senior Resident Inspector L. Wert, Resident Inspector D. Benoit, Resident Inspector
- Denotes those persons present at the exit intervie. Preface - Oconee Nuclear Station The Oconee Nuclear Station (ONS)
is owned and operated by Duke Power Company, Charlotte, North Carolin The facility is licensed to operate as a pressurized water reactor (PWR)
facility containing three separate power generating unit Each operating unit contains 177 fuel assemblies (F/A),
with each F/A comprised of 208 encapsulated zircalloy clad fuel rods containing sintered U02 fuel pellet Each unit core is zoned with fuel rods containing three enrichments of 2.1% U-235, 2.25% U-235, and 2.65% U-23 Some statistical data for ONS is exhibited in Table ONS is licensed according to 10 CFR 50 (Licensing of Production and Utilization Facilities) requirements to posses, use, and operate the ONS in accordance with procedures and limitations specified in the licens In accordance with 10 CFR 70 (Domestic Licensing of Special Nuclear Material), the licensee is authorized to receive, possess, and use special nuclear material (SNM)
as reactor fuel in accordance with the limitations specified for storage and the amounts required for reactor operations as describe in the facility FSAR documen In accordance with 10-CFR 30, 40, and 70, the licensee is authorized to receive, posses and use byproduct, source and special nuclear material as sealed neutron sources for reactor startup, reactor instrumentation and radiation monitoring equipment calibration, and as fission chambers in the amounts required. The license is authorized to posses, but not separate, such byproduct and SNM as may be produced by operation of the facilit. Material Control and Accounting - Reactors (85102)
This inspection was conducted to determine the adequacy and effectiveness of the Duke Power Company's program to account for and control the SNM in its possession and that the use of SNM was being restricted to those locations and purposes authorized by license at the Oconee Nuclear Station (ONS).
At the time of this inspection, the licensee's SNM holdings were in the form of cold and irradiated F/As, fission chambers in the forms of Source Range Detectors (SRD),
Intermediate Range Detectors (IRD),
Power Range Detectors (PRD), and PuBe calibration source The licensee's SNM use, control and accountability functions were examined by a review of facility procedures, review of organizational structure and functions, audit of records, review of the facility internal audit program, interviews with appropriate license personnel, and reviews observations and verifications of the license's conduct of a physical inventor Facility Organization The facility Station Manager bears the overall responsibility for the physical control and surveillance of SNM at the Oconee nuclear facilit The Station Manager has delegated, in writing, those responsibilities for daily operational activities associated with receipts, shipments, inspections, handling, storage, reporting and inventorying of SNM to the Superintendent of Operation The Superintendent of Operations has redelegated the above functions to members of his staf The Performance Section of the Superintendent of Operations staff has delegated to the Reactor Engineering Unit the responsibilities for maintaining control of activities associated with receipt of new fuel, offsite shipments of SNM, onsite shipments between spent fuel pools, onsite shipments within ICA's, activities for fuel movements during refueling operations, conducting physical inventories (PI),
generating data and reviewing of reports data transmitted to DOE/NRC, and to provide and correlate data to maintain the inhouse Special Nuclear Material Control Accounting (SNMCA) computerized database for use and control of SNM at the sit The inspector determined that written statements of responsibility and authority have been established for those positions having responsibility for SNM receiving, shipping, inventory, storage.,
internal control, and records and reports as required by regulatory requirement document minimum qualifications for positions associated with MC&A activities at the sit The license accepted the inspector's suggestion and made plans for its implementatio Although the licensee was practicing informal training, the inspector determined from discussions, observations and interviews of MC&A personnel who were performing material control and accountability functions, that MC&A personnel appeared acceptably qualified and were cognizant of programmatic requirements of MC&A activitie d. Management Reviews and Internal Audits As required by regulatory requirements and internal procedures, management reviews and audits of the facility SNM use and control program were being performed annuall The current review was performed by the facility Quality Assurance (QA)
Section who is organizationally independent of the SNM use, control and accounting operations at the sit The inspector examined the current audit report, NP-89-03 (ON)
(See TABLE II), dated March 13, 1989 and followup activities on the one finding associated with the facility SNM control progra For this audit, the license used an audit team comprised of three onsite QA personnel, one onsite engineer, and one member from the McGuire nuclear facility. Each team member was considered to be well qualified to perform technical evaluations of the SNM control progra The audit team used the facility Administrative Policy Manual, Oconee Station Directives, Oconee Technical Specifications, Oconee FSAR, station procedures and instructions to provide guidance for the audi The audit was conducted January 16, 1989 through February 22, 1989 and addressed facility procedures and instructions, technical specifications surveillance, qualifications and training, measuring and test equipment, document control, special nuclear material, records management, computer software control, housekeeping, special processes, testing and test records and refueling technical specifications and activitie The audit was performed under the cognizance of the facility Nuclear Safety Review Board (NSRB)
in accordance with Technical Specifications 6.1.3.4(A),
(B),
and (D)
requirements and contained thirteen findings and seven recommendation One finding was noted to be in the area of SNM controls and was examined by the inspector during this inspectio Finding NP-89-03 (ON)
02 indicated that the licensee had "failed to provide-effective control for protection of station records".
Specifically, the licensee had misplaced SNM Inventory Record PT/0A/0750/03 for the September 1988 physical inventory and had incomplete station records for some DOE/NRC Form 741 (DOE/NRC Form 741 - Nuclear Material Transaction Report) document transaction The inspector's examination of this audit finding indicated that the licensee was able to locate all documents identified in the audit report. The inspector noted that these documents were scattered in various offices of the Performance Section and had not been transmitted to the facility Master File (vault) as required by internal procedure As a result of this audit findings, the license made changes in their document control techniques to provide the Performance Section management with timely notifications of the use and control of active document It was noted that various other licensee groups maintain copies of some SNM activity records as working copies of these records and that all official copies of documents associated with the use and control of SNM are maintained in the Charlotte, North Carolina corporate offices. The inspector's examination of the records in question, determined that they had now been transmitted to the facility Master File and had.been distributed in accordance with NUREG/BR-0006 (Instructions for Completing Nuclear Material Transaction Reports)
and NUREG/BR-0007 (Instructions for
.Completing Material Balance Report and Physical Inventory Listing)
requirement The inspector determined that the findings of this audit was not a violation of regulatory requirements since the records in question were "unofficial copies" and the "official copies" were being maintained as described by approved procedure The inspector determined that:
(1) the audit findings involving the use and control of SNN were satisfactorily resolved; (2) that the audit was thorough and covered material receipts, transfers, material control, and records and reports; and (3) that the licensee had performed annual audits as require Records and Reports (1) Nuclear Material Transaction Reports The inspector examined many Nuclear Material Transaction Reports (DOE/NRC Form 741) used during facility operations from 1984 to dat Receipt documents for SNM received from Babcock and Wilcox Company (B&W), Lynchburg, Virginia into each of the three unit licenses at the site, receipt and shipments documentation from in-house movements of F/As between spent fuel pools for Units 1 and 2 and Units 2 and 3, shipments documentation for returning fuel rods and F/As to B&W and shipments documentation of 300 spent fuel F/As transferred to the Duke Power Company's McGuire nuclear station for storage were examined during this inspectio A random selection of documents from the above transaction reports were retrieved from the corporate Charolette, North Carolina office and selected F/As from these records were traced through facility internal records to the facility's computerized inventory dat The transactions reviewed indicated that the licensee had followed approved procedures for SNM fuel transactions and that the transactions were properly acknowledged by the licensee within the time
constraints specified by NUREG/BR-0006 and as referenced in 10 CFR 74.15(a).
The inspector concluded that the licensee's DOE/NRC Form 741 transaction reports were properly executed and reflected acceptable fuel receipts and shipments dat (2) Nuclear Material Balance Reports (MSR) and Isotopic Inventories The inspector examined the licensee's MSRs (DOE/NRC Form 742)
issued under licenses DPR-38, DPR-47 and DPR-55 for the accountability periods of October 1, 1988 through March 31, 1898 and April 1, 1989 through September 30, 1989. This examination was used to determine whether the report accurately reflected quantities of fuel received and shipped and whether uranium depletion and plutonium (Pu) production had been calculated and properly recorde The inspector determined that the MSRs were completed and distributed in accordance with the printed instructions in NUREG/BR-0007 as referenced in 10 CRF 74.13(a)(1) and that the recorded data for SNM shipments and receipts were found to be in agreement with accountability record The inspector noted that the Oconee nuclear facility MSRs data were calculated and formulated into a reporting format by the corporate office in Charlotte, North Carolin The corporate office uses copies of receipts and shipments transaction data and transmitted site exposure data to calculate isotopic inventories for inclusion into these reports. The exposure data is transmitted directly, via modems, from on-line computer systems from each operating unit. The inspector determined that the facility MSRs included all the necessary material balance data, including Inventory Differences (ID),
uranium depletion and Pu production data for isotopic inventories and were submitted semiannually in accordance with the instructions in NUREG/BR-0007, as referenced in 10 CFR 74.13(a)(1).
The inspector rioted that MSRs are distributed directly by the corporate office, after review and signature by appropriate station management, to the Martin Marietta Energy Systems, Oak Ridge, Tennessee as require This reporting technique is considered acceptabl The inspector concluded that the licensee had determined and reported accurate MSRs and that the MSRs contained calculated isotopic i-nventories as require Internal Control Areas (ICA)
The licensee was determined to have established internal ICAs for which physical and administrative controls of SNM were being administere The inspection of ICA records determined them to appropriately reflect information sufficient to enable the licensee to maintain current knowledge of the identity, quantity and location of all SNM bearing items or sit At the time of this inspection,
4III7 the following ICAs had been established and were being used at the Oconee Nuclear Statio (1) Unit 1 ORX1 Reactor Vessel (2) Unit 2 ORX2 Reactor Vessel (3) Unit 3 ORX3 Reactor Vessel (4) Units 1 & 2 OSF1 & OSF2 Spent Fuel Pool Storage (5) Unit 3 OSF3 Spent Fuel Pool Storage Physical Inventory (PI)
At the time of this inspection, all units were operating at 100% peak power and the licensee's activities associated with the actual conductance of a PI could not be observe A formalized PI is conducted for each core at the end of each operating cycl (approximately 410 peak power operating days) and piece count PIs of the spent fuel pools are conducted on a semiannual basi The licensee maintained documentation of the quantity, identification, and location of each fuel bearing and nonfuel bearing item by using an in-house computer system called Special Nuclear Material Control and Accountability (SNMCA).
This computer database contains all historical and current data for each fuel bearing and nonfuel bearing iterr onsit The SNMCA database controls and accounts for all SNM bearing items (F/As, calibration sources and fission chambers) within the three nuclear facilities (Oconee, Catawba, and McGuire) of the Duke Power Compan SNMCA database contains data for current locations and descriptions of each F/A and records of previous locations and movements of individual F/A The SNMCA database program is used by the licensee to generate schedules for SNM movements, provide SNM inventory reports, and produce maps of each site fuel storage area and reactor cor The SNMCA database is the official record of SNM on inventory at the site and is maintained by the corporate General Office Nuclear Engineering Group (GO).
This database data is updated by site personnel and furnished to the GO for insertion into the database program. A schematic diagram of each unit core and spent fuel pool is used as support and backup data to substantiate the PI data of the SNMCA databas During this inspection, the inspector examined the inventory data, taken by video camera of Units 1 and 2 and piece count data verification of Unit 3, for the inventories conducted during the periods of March 22, 1989 through April 18, 1989 and November 18, 1989 through December 6, 198 The inspector also examined the data of the PI taken at the time of an operating outage for Unit 3. For this outage PI, the licensee performed a piece count inventory of Units 1 and 2, camera visual verification of Unit 3, and physically identified and verified the existence of nonfuel bearing item The inventory reports for these PIs were thorough and detailed each individual SNM fuel bearing and nonfuel bearing item on sit All minor discrepancies noted during the listing of these PIs were corrected at the time of the listin During this inspection, the inspector independently verified the identification and location of 25 F/As in each of the spent fuel pools, 15 F/As in each of the three operating reactor cores and the physical existence of all nonfuel bearing items on sit No discrepancies in the licensee's data were noted during these verification activitie At the time of this inspection, the licensee's SNM inventory consisted of 2,170 F/As and eight nonfuel bearing items. A recap of these items is shown in Table II The inspector concluded that the licensee had conducted physical inventories of SNM at the required frequencies in accordance with approved procedures and that the procedures employed would probably detect losses, thefts and diversions of SNM from authorized use Summary The inspector determined that the licensee had established and was maintaining program for controlling and accounting for SNM in his possession, and had limited the use of SNM to those locations and purposes authorized by licens No violations or deviation from NRC requirements were detected during this inspectio.
Licensee Actions on Previous Enforcement Matters (92702)
No previous enforcement matters were pending in the areas inspected during this inspectio. Exit Interview The inspection scope and findings were summarized on March 2, 1990, with those persons indicated in paragraph 1 abov The licensee acknowledged the inspection findings and took no exception TABLE I OCONEE NUCLEAR STATION STATISTICS (50-269, 270, AND 287/90-07)
UNIT I UNIT 2 UNIT 3 Docket Number 50-269 50-270 50-287 Operating License N DPR-38 DPR-47 DPR-55 Operating License Date 2/6/73 10/6/73 10/6/73 Commercial Operation Date 7/15/73 9/9/74 12/16/74 Power Rating (MWt)
2568 2568 2568 Core Fuel Assemblies 1.77 177 177 Reporting ID Symbol YNR XEK XFV
TABLE II TYPICAL OPERATING PROCEDURES (50-269, 270, AND 287/90-07)
1. Duke Power Company Administrative Procedures Manual, Section 3.9, Revision 28, Special Nuclear Materials Safeguards and Accountabilit.
Oconee Nuclear Station Directive 2.1.8, Special Nuclear Materials Control and Accountability, dated April 29, 198. Oconee Nuclear Station Performance Manual, Section 4.6, Special Nuclear Material Accountability Program, dated April 28, 198.
Procedure Process Record, Core Inspections Procedure, dated September 26, 198.
Procedure Process Record, Spent Fuel Pool Inspections Procedure, dated September 26, 198.
Procedure Process Record, Physical Inventory of Reportable Special Nuclear Materials, dated September 26, 198. Quality Assurance Departmental Audit (NP-89-03 (ON))
-Refueling, Inservice Inspection, Computer Services, and Performance Group Activities, Oconee Nuclear Station, dated March 13, 198 LII
(III TABLE III PHYSICAL INVENTORY DATA RECAP (50-269, 270, AND 287/90-07)
Location F/As Nonfuel Unit 1 177 Unit 2 177 Unit 3 177 Unit 1 & 2 SFP 1039 Unit 3 SFP 600 Warehouse # 5
Storage Areas
Incore
Totals 2,170 8