IR 05000261/1986005
| ML14175B369 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 03/24/1986 |
| From: | Fredrickson P, Krug H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14175B368 | List: |
| References | |
| 50-261-86-05, 50-261-86-5, NUDOCS 8604020350 | |
| Download: ML14175B369 (7) | |
Text
REG~
UNITED STATES 0,
NUCLEAR REGULATORY COMMISSION REGION 11 101 MARIETTA STREET, N ATLANTA, GEORGIA 30323 Report No.:
50-261/86-05 Licensee: Carolina Power and Light Company P. 0. Box 1551 Raleigh, NC 27602 Docket No.:
50-261 License No.: DPR-23 Facility Name: H. B. Robinson Inspection Conducted: February 11 - March 10, 1986 Inspector:
. E..
Kru, Senior Resident Inspector Date Signed Approved by:
i /
P. E. Fredrickson, Section Chief Date /Signed Division of Reactor Projects SUMMARY Scope:
This routine, announced inspection involved 126 resident inspector-hours on site in the areas of Technical Specification (TS)
compliance, plant tour, operations performance, reportable occurrences, housekeeping, site security, surveillance activities, maintenance activities, quality assurance practices, radiation control activities, outstanding items review, IE Bulletin and IE Notice followup, organization and administration, independent inspection and Systematic Assessment of Licensee Performance (SALP).
Results:
No violations or deviations were identified within the areas inspecte PDR ADOCK 05000261 PDR
REPORT DETAILS 1. Licensee Employees Contacted R. Barnett, Maintenance Supervisor, Electrical G. Beatty, Manager, Robinson Nuclear Project Department A. Beckman, Principal Specialist, Planning and Scheduling J. Benjamin, Supervisor, Operations R. Chambers, Engineering Supervisor, Performance C. Crawford, Manager, Maintenance D. Crocker, Principal Health Physics Specialist J. Curley, Director, Regulatory Compliance W. Ritchie, Supervisor (Acting), Radiation Control J. Eaddy, E&C Supervisor W. Flanagan, Manager, Design Engineering W. Gainey, Maintenance Supervisor, Mechanical G. Honma, Senior Specialist, Regulatory Compliance F. Lowery, Manager, Operations A. McCauley, Director (Acting), Onsite Nuclear Safety P. Harding, Project Specialist (Acting), Radiation Control M. Marquick, Senior Specialist, Planning and Scheduling R. Morgan, Plant General Manager M. Morrow, Specialist, Emergency Preparedness D. Nelson, Operating Supervisor B. Murphy, Senior Instrumentation and Control Engineer M. Page, Engineering Supervisor, Plant Systems R. Powell, Principal Specialist, Maintenance B. Rieck, Manager, Control and Administration R. Smith, Manager, Environmental and Radiation Control J. Sturdavant, Technician, Regulatory Compliance R. Wallace, Manager, Technical Support L. Williams, Supervisor, Security C. Wright, Senior Specialist, Quality Assurance/Quality Control H. Young, Director, Quality Assurance/Quality Control Other licensee employees contacted included technicians, operators, mechanics, security force members, and office personne.
Exit Interview (30702,30703)
The inspection scope and findings were summarized on March 10, 1986, with the Plant General Manager. The licensee acknowledged the findings without exceptio The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspectio.
3. Plant Tour (71707, 62703, 71710)
The inspector conducted plant tours periodically during the inspection interval to verify that monitoring equipment was recording as required, equipment was properly tagged, operations personnel were aware of plant
conditions and maintenance activities, and plant housekeeping efforts were adequate. The inspector determined that appropriate radiation controls were properly established, excess equipment or material was stored properly, and combustible material was disposed of expeditiously. During tours the inspector looked for the existence of unusual fluid leaks, piping vibrations, pipe hanger and seismic restraint abnormal settings, various valve and breaker positions, equipment clearance tags and component status, adequacy of fire fighting equipment, and instrument calibration dates. Some tours were conducted on backshifts. Plant housekeeping and contamination control were observed to be excellen The inspector performed system status checks on the following systems: Emergency diesel generators Safety Injection System Vital Station Batteries Emergency Electrical Switchgear No violations or deviations were identified within the areas inspecte. Technical Specification Compliance (71707, 62703, 61726)
During this reporting interval, the inspector verified compliance with selected limiting conditions for operation and reviewed results of certain surveillance and maintenance activitie These verifications were accomplished by direct observation of monitoring instrumentation, valve positions, switch positions, and review of completed logs and record No violations or deviations were identified within the areas inspecte. Plant Operations Review (71707, 62703, 61726, 61707, 61711)
Periodically during the inspection interval, the inspector reviewed shift logs and operations records, including data sheets, instrument traces, and records of equipment malfunctions. This review included control room logs, maintenance work requests, auxiliary logs, operating orders, standing orders, jumper logs, and equipment tagout records. The inspector routinely observed operator alertness and demeanor during plant tour The inspector conducted random off-hours inspections during the reporting interval to assure that operations and security mained inaccordance with plant procedure No violations or deviations were identified within the areas inspecte.
Physical Protection (71707)
The inspector verified by observation, perimeter walkdowns and interviews that measures taken to assure the physical protection of the facility met current requirement Areas inspected included the organization of the security force; the physical condition of gates, doors and isolation zones;
the performance of access controls and searches; communications procedures; and the enforcement of escorting rule No violations or deviations were identified within the areas inspecte. Monthly Surveillance Observation (61726, 61700, 71710, 71711)
The inspector observed portiohs of the licensee's performance of Revision 3 to Operations Surveillance Test Procedure OST-154 titled "Safety Injection System High Head Check Valve Test (Refueling)". The current version of the procedure was used by the technicians. The purpose of OST-154 is to assess the operational readiness of the Safety Injection System High Head Check Valves as required by Section XI of the ASME Boiler and Pressure Vessel Cod OST-154 requires that the reactor be in a refueling configuration with the reactor pressure vessel head removed and the refueling cavity capable of receiving water from the reactor vessel; and that the primary system temperature is being maintained by the residual heat removal system. These prerequisites were met during the performance by the licensee of OST-15 The Shift Foreman formally authorized the execution of OST-154 which was performed by two qualified technician The inspector also witnessed the execution of the weekly operability test of the emergency diesel, as it was performed on the B emergency diesel generator. This test was conducted using Operations Surveillance Test Procedure OST-401 (Revision 6) titled "Emergency Diesels -
Weekly."
The test technician used the correct and current procedure and was qualified to perform the tes OST-401 is designed to verify the mechanical performance and operational readiness of the emergency diesels; and that the requirements of TS 4.6. and 4.6.1.4 are satisfie With respect to tests and surveillances which are to be performed as stated, TS 4.6.1.1 requires a
"Manually-initiated start of the diesel generator, followed by manual synchronization with other power sources and assumption of load by the diesel generator up to the nameplate ratin Normal plant operation will not be affected."
whereas TS 4.6.1.4 states:
"Diesel generator electric loads shall not be increased beyond the long term rating of 2500 kw."
The inspector observed that the proper administrative approvals were obtained and that the required precautions were observe The inspector noted that although the TS require that this test be performed on a monthly basis, the licensee performs the test weekly in accordance with vendor
recommendations. As part of the test, the operator verified the operation of the redundant solenoid valves on the air start system by isolating one of the solenoid valves on the B diesel prior to the engine start. The B diesel generator successfully completed the test requirement No violations or deviations were identified within the areas inspecte. Monthly Maintenance Observation (62703, 71711)
The inspector observed maintenance activities associated with performance by the licensee of Preventative Maintenance Procedure PM-008 (Revision 3)
titled "Emergency Diesel Generator Inspection Number 2 (Refueling)."
PM-008 provides the approved instructions for performance of preventativ2 maintenance upon the engine fuel injection nozzles and timing components, intake and exhaust porting, cylinders and pistons, engine bearings, camshafts, blower, vertical drive unit, heat exchangers, alternator, engine coupling and holddown bolts, crankshaft strain, lead and float inspections, crankcase vacuum ejector inspection and governor oil change ou This procedure satisfies Section 4.6.1.3 of the TS which states that "Each diesel generator shall be inspected at each refueling."
This maintenance was conducted in accordance with approved procedure The inspector also determined (1) that the procedures used were adequate to control the activity, (2) that required administrative approvals and tagouts were obtained prior to work initiation, (3) that proper radiological, and appropriate ignition and fire prevention controls were implemented, and (4)
that replacement parts and materials used were properly certified. The inspector verified that these activities were accomplished by qualified personne Additionally, the inspector determined that the licensee was giving priority to safety-related maintenance, and that a backlog which might affect its performance was not developing on a given syste No violations or deviations were identified within the areas inspecte. Operational Safety Verification (71707)
The inspector observed licensee activities to ascertain that the facility was being operated safely and in conformance with regulatory requirements, and that the licensee management control system was effectively discharging its responsibilities for continued safe operation by direct observation of activities, tours of the facility, interviews and discussions with licensee management and personnel, independent verification of safety system status and limiting conditions for operation, and reviewing facility record No violations or deviations were identified within the areas inspecte.
Onsite Followup of Events and Subsequent Written Reports of Nonroutine Events at Power Reactor Facilities (92700, 90714, 93702)
For onsite followup of nonroutine events, the inspector determined that the licensee had taken corrective action(s) as stated in written reports of the events and that these responses to the events were appropriate and met regulatory requirements, license conditions, and commitment During this reporting period, the inspector reviewed the following LERs to verify that the report details met license requirements, identified the cause of the event, described appropriate corrective actions, adequately assessed the event, and addressed any generic implications. The inspector had no further comment LER EVENT 86-04 Reactor Trip
-
Nuclear Instrumentation System High Neutron Flux 86-06 Engineered Safety Feature Actuation During Plant Cooldown 86-07 Steam Generator Snubbers No violations or deviations were identified as a result of the LER revie.
Organization and Administration (36700)
The inspector reviewed the on-site licensee organization to ascertain whether changes made to the licensee's onsite organization are in conformance with the requirements of the TS by verifying that (1) the established organization conforms to the TS and is functioning effectively, (2) personnel qualification levels are in conformance with applicable codes and standards, and (3) the lines of authority and responsibility are in conformance with TS and applicable codes and standards. At a special Plant Nuclear Safety Committee (PNSC)
meeting held on March 6, 1986, attended by the inspector, the PNSC discussed recent licensee organizational change The position of Vice President of Corporate Nuclear Safety and Research was eliminate The licensee's Nuclear Safety Organization now reports to the Manager of Nuclear Safety and Environmental Services (a new position),
as do the Managers of the Environmental Services Section, the Corporate Health Physics Section and the Radiological and Chemical Support Sectio The Manager of Nuclear Safety and Environmental Services is a highly competent individual who, for a number of years, was Plant General Manager at H.B. Robinso Comprehensive discussions of current safety-related activities were conducted with plant management and technical personnel during this reporting period including, and in particular, Environmental and Radiation
Controls, Quality Assurance, Regulatory Compliance and Onsite Nuclear Safety organizations. Topics discussed included licensee activities associated with plant operations activities, especially recent reactor trips; plant modifications, including outage activities; ongoing construction activities; and communications interface No violations or deviations were identified within the areas inspecte.
Plant Nuclear Safety Committee (PNSC) (40700)
The inspector reviewed certain activities of the PNSC to ascertain whether the onsite review functions were conducted in accordance with TS and other regulatory requirement The inspector (1)
attended the special PNSC meeting held on March 6, 1986 and observed the conduct of the meeting (2)
ascertained that provisions of the TS dealing with membership, review process, qualifications, etc.,
were satisfied, and (3)
followed up on previously identified PNSC activities to independently confirm that corrective actions were progressing satisfactoril The inspection emphasized current modifications to the Offsite Dose Calculation Manual (00CM), modification M-888 to the boron injection system to eliminate the high concentration injection function, and preliminary findings being evaluated in the area of reactor trip reductio No violations or deviations were identified within the areas inspecte.
Plant Procedures (42700)
The inspector reviewed portions of the established procedure program to ascertain whether overall plant procedures were in accordance with regulatory requirements, temporary procedures and procedure changes were made in accordance with TS requirements, and the technical adequacy of the reviewed procedures was consistent with desired actions and modes of operation. Procedures examined included general plant operating procedures, fuel loading and fuel cavity draining procedures, maintenance procedures and administrative procedure No violations or deviations were identified within the areas inspecte I0