IR 05000070/1999201
| ML20196K408 | |
| Person / Time | |
|---|---|
| Site: | Vallecitos Nuclear Center, Vallecitos File:GEH Hitachi icon.png |
| Issue date: | 07/01/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20196K397 | List: |
| References | |
| 50-070-99-201, 50-073-99-201, 50-183-99-201, 50-70-99-201, 50-73-99-201, NUDOCS 9907080321 | |
| Download: ML20196K408 (16) | |
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U. S. NUCLEAR REGULATORY COMMISSION Docket Nos: 50-73, 50-70, and 50-183 License Nos: R-33, TR-1, and DR-10 Report No: 50-73/99-201; 50-70/99-201: 50-183/99-201 Licensee: General Electric Company Facility: Nuclear Test Reactor (NTR)
Location: Pleasanton/Vallecitos, CA Dates: June 7-10,1999 Inspector: C. Bassett
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' Approved by: Ledyard 8. Marsh, Director Events Assessment, Generic Communications and Non-Power Reactors Branch Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation
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9907000321 990701 PDR ADOCK 05000070 PDR 0-
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EXECUTIVE SUMMARY
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- This routine, announced inspection included onsite review of selected aspects of the following: operations program, organizational structure and functions program, design j control program, review and audit program, operator requalification program, maintenance l program, surveillance program, fuel handling program, experimental program, procedural l control program, and emergency. preparedness program since the last NRC inspection in
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l- The licensee's programs were acceptably directed toward the protection of public health j and safety, and in compliance with NRC requirement ORGANIZATIONAL' STRUCTURE AND FUNCTIONji l
The' organizational structure and functions were consistent with Technical Specification requirements.-
OPERATIONS !
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The operations program satisfied Technical Specificatio'n requirement DESIGN CONTRQL l_
The design change program satisfied NRC requirement BEVIEW'AND AUDIT-
i f The review and audit program was in comphance with Technical Specification requirement OPERATOR REQUALIFICATION L Operator requalification was conducted as required by the Requalification Program.
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MAINTENANCE t
l The maintenance program satisfied NRC requirements, f
SURVEILLANCE The surveillance program was in compliance with Technical Specification requirement FUEL HANDLING
.The fuel handling program satisfied Technical Specification requirements, a '
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The program for experiments satisfied Technical Specification and procedural requirement ' PROCEDURES The procedural control and implementation' program satisfied Technical Specification
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YEAR 2000 CONCERNJ No ' problems had been identified concerning reactor operations with respect to Year 2000 concerns.-
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The emergency preparedness program was conducted in accordance with the Emergency Pla t
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Report Details Summary of Plant Status During the inspection the reactor was operated daily to support training, surveillance, and contract service work.'
- ORGANIZATIONAL STRUCTURE AND FUNCTIONS (69001)
. ~SSgp3 The inspector reviewed selected aspects of:
e organization and staffing e qualifications e management responsibilities e administrative controls Observations and Findinas The organizational structure and staffing had not changed since the last inspectio However, it was noted that the current NTR Facility Manager is planning to retire in August 1999. A person had been selected to fill the position and that person was on site for training and turn over activities during the period of this inspectio The organizational structure and staffing at the facility and as reported in the Annual Report was as required by the Technical Specifications (TS). Qualifications of the current staff and the incumbent NTR manager met TS requirements. Review of records verified that management responsibilities were administered as required by TS and applicable procedure Conclusions The organizational structure and functions were consistent with Technical Specification requirement . OPERATIONS (69001) Scope The inspector reviewed selected aspects of:
e operational logs and records e staffing for operations e selected operational, staitup, or shutdown activities
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-2- Observations and Findinas -
The operating logs and records were clear and provided an acceptable indication of operational activities. This included documentation of any events that occurred, and resolution or tracking of the events. Logs and records also showed that operational conditions and parameters were consistent with license and TS -
requirements. Observation of actual operational activities further confirmed that these conditions and requirements were satisfie Conclusions The operations program satisfied Technical Specification requirement . DESIGN CONTROL (69001) - Scope The inspector reviewed selected aspects of:
e facility design changes and records e facility configuration and control- ,
i Observations and Findinas Records ano observations showed that changes at the facility were acceptably reviewed in accordance with 10 CFR 50.59 and applicable administrative procedures and controls. All of the reccat changes were minor in nature and none
' of the changes constituted an unreviewed safety question or required a change to the TS.
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I Conclusions
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The design change program satisfied NRC requirements.
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' REVIEW AND AUDIT (69001) Scope The inspector reviewed selected aspects of:
e ' meeting minutes of the Vallevitos Technological Safety Council e safety review and audit records j e responses to safety re/iews and audits {
e. review and audit personnel qualifications
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-3- Observations and Findinos Records showed that the safety reviews were conducted at the TS required frequency. Topics of these reviews were also consistent with TS requirements to provide guidance, direction, and oversight, and to ensure acceptable use of the reactor. This function was performed by the Vallecitos Technological Safety Council (VTSC).
The audit records showed that audits had been completed in those areas outlined in the TS and at the required frequency. Audits were typically completed by members of the Regulatory Compliance group. The inspector noted that the safety reviews and audits and the associated findings were acceptably detailed and that the licensee responded and took corrective actions as neede The safety review and audit personnel qualifications satisfied TS requirements and licensee administrative controls. Further, the number of personnel involved in the safety reviews and audits also satisfied licensee procedural requirements.
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The review and audit program satisfied Technical Specification requirement . OPERATOR REQUALIFICATION (69001)
a. Scope The inspector reviewed selected aspects of:
j e the Requalification Program e operator licenses e operator training and examination records j- e operator physical examination records
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e operator active duty status b. Observations and Findinos The Requalification Program was being maintained up to date. Operator licenses were also current. Records showed that operator training was consistent with the Requalification Program requirements. Physical examinations of the operators were conducted as required. Records showed that written and operating examinations of the operators were acceptably completed. Logs showed that operators maintained active duty status as require There are currently three Senior Reactor Operators (SROs) employed at the facilit l
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' Conclusions Operator requalification was conducted as required by the Requalification Progra . h1AINTENANCE (69001) ; Scope The inspector reviewed selected aspects of:
o maintenance procedures e equipment manuals e equipment maintenance records l b. Observations and Findinas Logs indicated that corrective maintenance activities and problems were addressed and preventive maintenance operations completed as required by procedur Records showed that routine maintenance activities were conducted at the required frequency and in accordance with the TS and/or the applicable procedure or i equipment manual. Maintenance activities ensured that equipment remained !
consistent with the Safety Analysis Report and TS requirements. Further, maintenance activities were consistent with the requirements of 10 CFR 50.5 '
c. Conclusions The maintenance program satisfied NRC requirement . SURVEILLANCE (69001)
a. Scoce The inspector reviewed selected aspects of:
e surveillance and calibration procedures, e surveillance, calibration, and test data sheets e operationallogs and records
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-5- Observations and Findings Surveillance, test, and Limiting Conditions for Operation (LCO) verifications and '
calibrations were completed on schedule and in accordance with licensee procedures. All the recorded results were within the TS and procedurally prescribed parameters or adjustments were made to the equipment as needed. The i records and logs reviewed were complete and were being maintained as require Checks, tests, and calibrations were completed as required by TS.
c Conclusions The surveillance program satisfied Technical Specification requirement . FUEL HANDLING (69001)
a. Scope The inspector reviewed selected aspects of:
e previously approved fuel handling procedure e fuel handling equipment and instrumentation b. Observations and Findinas l l
The fuel handling procedure provided a prescribed method to move and handle fuel consistent with the provisions of the TS and the licensee safety analyses. The procedure was not currently approved for use but the licensee emphasized that it would be reviewed and approved before it was implemented. Because the fuel handling procedure was not used very frequently, the licensee stated that personnel would be trained so that they were knowledgeable of the procedural and equipment requirements for criticality control and assurance of fuel integrity. The licensee did not anticipate any need to move fuel or refuel the reactor for possibly up to ten years, c. Conclusions The fuel handling program satisfied licensee Technical Specification requirement .
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-6- EXPERIMENTS (69001) - Scope The inspector reviewed selected aspects of:
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experimental program requirements e procedures e logs and records e experimental administrative controls and precautions Observations and Findinos The experiments at the facility were routine procedures that had been in place for several years. No new or unknown-type experiments had been initiated, reviewed, -
or approved since the last inspection. if any experiments were to be initiated, they would be completed with the cognizance of the Reactor Supervisor and a Senior Reactor Operator and in accordance with TS requirements (e.g., reactivity limitations). The results of the experiments were documented in appropriate logs or records. Engineering and radiation protection controls were implemented as required to limit exposure to radiatio Conclusions The program for experiments satisfied Technical Specification and procedural requirement . PROCEDURES (69001) Scoce The inspector reviewed selected aspects of:
e administrative controls e records of changes and temporary changes e procedural implementation e logs and records I
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-7- ' Observations and Findinas Administrative controls of changes and temporary changes to procedures, and
. associated review and approval processes were as required. Training of personnel on procedures and changes thereto was acceptable. Personnel conducted activities-in accordance with applicable procedures. Records showed that procedures for-
. potential malfunctions (e.g., radioactive releases and contaminations, and reactor equipment problems) were implemented as require c .- Conclusions
- The procedural control and implementation program satisfied Technical Specification requirement . YEAR 2000 CONCERNS REVIEW Inspection Scoo The inspector reviewed the status of the licensee's preparations to deal with the potential computer problems caused by the upcoming Year 2000 (Y2K) through reviewing selected aspects of:
e " operating system o . security system o General Electric Company approach to the problem Observations and Findinas The licensee had completed an extensive review / analysis of the various types of equipment and computer based applications supporting activities at the site and the TS requirements at the NTR facility. They had concluded that the only problem
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concerning Y2K might exist with some of the radiation monitoring at the site, in order to correct the situation, the licensee.was buying new software that would alleviate the problem. In their review of the current status of the NTR facility, the licensee had not identified anything that would pose a problem to the reactor operations and no instances were identified that could pose a threat to public health and safet The licensee determined that the security system was Y2K compliant. The
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-8- 1 1 Conclusions No problems had been identified concerning reactor operations with respect to Y2K I concern . EMERGENCY PREPAREDNESS (69001) i l Scooe The inspector reviewed selected aspects of:
e the Emergency Plan l e implementing procedures e emergency response facilities, supplies, equipment and instrumentation e training records e offsite support e emergency drills and exercises Observations and Findinas The Emergency Plan (E-Plan) in use at the NTR and associated emergency facilities I was the same as the version most recently approved by the NRC. The E-Plan was audited and reviewed as required. Implementing procedures were revie'.ved and revised as needed to employ the E-Plan effectively. Facilities, supplies, instrumentation, and equipment were being maintained, controlled, and inventoried as required in the E-Pla Through records review and through interviews with licensee personnel, emergency responders were determined to be knowledgeable of the proper actions to take in case of an emergency. Agreements with outside response organizations had been updated and maintained as necessary. Communications capabilities were acceptable with these support groups and had been tested as stipulated in the E-Plan. Off-site support organization participation was verified to be in accordance with the E-Pla Emergency drills had been conducted as required by the E-Plan. Critiques were held following the drills to discuss the strengths and weaknesses identified during the exercise and to develop possible solutions to any problems identified. The results of these critiques were documented and filed. Emergency preparedness and response training was being completed as required. Training for reactor staff personnel was conducted and documented as stipulated by the E-Plan.
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. During the inspection, it was noted that there was a separate set of procedures
- that was being maintained with the E-Plan implementing procedures. This other set of procedures was entitled, " Building 105 Emergency Procedures." The procedures had been written in 1984 and had been approved by the NTR Facility Manager in December 1984. Licensee representatives indicated that these were not " official" procedures but were supplementary to the existing implementing procedures, it was not clear whether or not these supplementary procedures should be reviewed and incorporated into the facility Standard Operating Procedures (SOPS) or the E-Plan, or whether they should be eliminated. The supplementary procedures appeared to be a duplication of some of the regular implementing procedures. The licensee was informed that an inspector Follow-up Item (IFI) would be established to track what was decided concerning the supplemeatary procedures and whether or not they should be revised and included in the E-Plan or SOPS or perhaps eliminated (IFl 50-73/99-201-01).
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The emergency preparedness program was conducted in accordance with the Emergency Pla . FOLLOW-UP ON PREVIOUS OPEN ITEMS (69001) Inspection Scoce The inspector reviewed the actions taken by the licensee following identification of I violations (VIOs) during previous inspection l Observations and Findinas (1) VIO - 50-73/98-201-01 - Failure to perform whole body counts four times per year as required by procedure
i NRC Inspection Report No. 50-73/98-201 and Notice of Violation, dated March 18,1990, outlined this problem. During this inspection, the inspector reviewed the actions taken by the licensee to correct the problem concerning missed whole body counts. These corrective actions had been documented in i the licensee's response to the NOV dated April 17,1998. The corrective actions were determined to be acceptable. This item is considered close i
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(2) VIO - 50-73/98-201-02 - Failure to post a radiation area NRC Inspection Report No. 50-73/98-201 and Notice of Violation, dated March 18,1998, outlined the failure to post a radiation area. The inspector reviewed the actions taken by the licensee to correct the identified proble These corrective actions had been documented in the licensee's response to
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the NOV dated April 17,1998. The corrective actions were determined to be acceptable. This item is considered closed, i
(3) VIO - 50-73/98-201-03 - Failure to comply with certain requirements of the l Physical Security Plan (PSP) l NRC Inspection Report No. 50-73/98-201 and Notice of Violation, dated March 18,.1998, outlined the problems noted with the PSP. During this inspection, the inspector reviewed the actions taken by the licensee to correct the problems and properly implement the provisions of the PSP. These corrective actions had been documented in the licensee's response to the NOV dated April 17,1998. The corrective actions were determined to be acceptable. -This item is considered closed, Conclusions Acceptable actions were taken by the licensee regarding three previously identified problems and these issues are considered close . REVIEW OF THE STATUS OF OTHER REACTORS AT VNC (40755) Insoection Scope The inspector reviewed the following to ensure that the requirements of the applicable TS were being met for the General Electric Test Reactor (GETR) and the Empire State Atomic Development Associates (ESADA) Vallecitos Experimental Superheat Reactor (EVESR) facilities:
e annual reports e Regulatory Compliance Reviews of the facilities e Annual Inspection Checklists for each facility
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I Observations and Findinos The inspector verified that the GETR and EVESR were being maintained in a j deactivated status in accordance with the appropriate licenses. - No major i preventive or corrective maintenance activities having safety significance were l performed. Annual entries have been made into the buildings to perform routine l radiation surveys and to check the areas to ensure that the conditions remain I unchanged in the facilities. All reactor fuel had been removed from the reactors and shipped off site. The GETR and EVESR facilities were being maintained in a safe shutdown conditio Conclusions The GETR and EVESR facilities were being maintained in accordance with the applicable TS requirements and in a safe shutdown conditio . EXIT INTERVIEW
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The inspection scope and results were summarized on June 10,1999, with members of licensee management. The inspector described the areas inspected and discussed in detail the inspection finding No dissenting comments were received from the licensee. The licensee did not identify as proprietary any of the material provided to or reviewed by the inspector.
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! PARTIAL LIST OF PERSONS CONTACTED Licenses C. Bassett, Manager, Regulatory Compliance W. Kreutel, Senior Reactor Operator B. Murray, Senior Licensing Engineer M. Rogers, Specialist, Radiation Monitoring D. Smith, Manager, NTR R. Snyder, Senior Reactor Operator G. Stimmell, Manager, Vallecitos, Morris, & San Jose Operations H. Stuart, Specialist, Radiological Engineering l
l l lNSPECTION PROCEDURES USED L IP 69001 Class ll Non-Power Reactors l IP 40755 Class lll Non-Power Reactors l
ITEMS OPENED, CLOSED, AND DISCUSSED Opened 50-73/99-201-01 IFl Follow-up on the licensee's decision regarding supplementary " emergency" procedures entitled " Building 105 Emergency Procedures," as to whether they should be reviewed and incorporated into the facility (SOPS), the E-Plan, or whether they should be eliminate I Closed 50-73/98-201-01 VIO Failure to perform a whole body count four times per year as required by procedure for individuals who are regularly i assigned to work in radioactive material areas around the
! NTR on a daily baris.
l 50-73/98 201-02 VIO Failure to post an area outside the South Cell of the NTR in which radiation levels could result in an individual receiving 5 millirem in o'ne hour with a " Caution, Radiation Area" sig /98-201-03 VIO Failure to comply with requirements o'. ihe PSP for:
1) conducting semi-annual operability tests of the emergency generator prior to 1998, 2) conducting calls from the Off-Site Emergency Agencies Call List on the first l
! Thursday of the month of March, June, September, and December of 1997, and 3) conducting a test of the High- j Level Conference Circuit on the first Wednesday of the !
month in 199 I
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LIST OF ACRONYMS USED CFR Code of Federal Regulations E-Plan Emergency Plan ESADA Empire State Atomic Development Associates EVESR . ESADA Vallecitos Experimental Superheat Reactor .
GETR General Electric Test Reactor IFI' inspector Follow-up item l
'IP inspection Procedure LCO Limiting Conditions for Operation NOV 3 Notice of Violation NRC Nuclear Regulatory Commission NTR Nuclear Test Reactor PSP Physical Security Plan SNM Special Nuclear' Material SOP Standard Operating Procedure SRO Senior Reactor Operator TS Technical Specifications VIO Violation VNC Vallecitos Nuclear Center VTSC ~ Vallecitos Technological Safety Council I