IR 05000261/1986013
| ML14175B386 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 06/13/1986 |
| From: | Fredrickson P, Fredrickson P, Krug H, Latta R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14175B385 | List: |
| References | |
| 50-261-86-13, IEIN-85-045, IEIN-85-048, IEIN-85-45, IEIN-85-48, NUDOCS 8606300332 | |
| Download: ML14175B386 (10) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30323 Report No.:
50-261/86-13 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: May 11 - June 10, 1986 Inspectors: (2-9
-
/3/
H E Krug, Senior Resident Inspector Da e Signed R. M. Latta, Resident Inspector Date Signed Approved by:
L-
-6---
P. E. Fredrickson, Section Chief Dake Signed Division of Reactor Projects SUMMARY Scope:
This routine, announced inspection was conducted 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, Systematic Assessment of Licensee Performance (SALP) and enforcement action followu Results:
No violations or deviations were identified within the areas inspecte PDR ADOCK 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 D. Crocker, Principal Health Physics Specialist J. Curley, Director, Regulatory Compliance J. Eaddy, Supervisor, Environmental and Radiation Control W. Flanagan, Manager, Design Engineering W. Gainey, Maintenance Supervisor, Mechanical E. Harris, Director, Onsite Nuclear Safety G. Honma, Senior Specialist, Regulatory Compliance D. Knight, Shift Foreman, Operations E. Lee, Shift Foreman, Operations F. Lowery, Manager, Operations D. McCaskill, Shift Foreman, Operations A. McCauley, Principal Specialist, Onsite Nuclear Safety R. Moore, Shift Foreman, Operations
.
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 D. Quick, Manager, Maintenance B. Rieck, Manager, Control and Administration W. Ritchie, Supervisor (Acting), Radiation Control D. Seagle, Shift Foreman, Operations R. Smith, Manager, Environmental and Radiation Control R. Steele, Shift Foreman, Operations 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 June 10, 1986, with the Manager of the Robinson Nuclear Project and the Director of Regulatory Compliance. The licensee acknowledged the findings without exceptio The licensee did not identify as proprietary any of the materials provided to or
reviewed by the inspectors during this inspection. No written material was given to the licensee by the Resident Inspectors during this report perio.
Licensee Action on Previous Inspection Findings (92702)
(Closed) Inspector Followup Item 50-261/83-26-03. The licensee promulgated Plant Program Procedure PLP-30, Revision 0, titled
"Independent Verification" in response to the requirements for independent verification as defined in NUREG-0737, Item 1.c.6.(5).
(Closed) Inspector Followup Item 50-261/83-15-08. The inspectors reviewed Technical Support Management Manual Procedure TMM-005, Revision 0, titled
"10CFR5O, Appendix J Testing Program" Attachment 6.2 and determined that the licensee had developed a program for controlling local leak rate tests in plant procedures for post maintenance testing of valves delineated in 10CFR5O, Appendix.
Plant Tour (71707, 62703, 71710)
The inspectors 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 inspectors determined that appropriate radiation controls were properly established, excess equipment or material was stored properly, and combustible material was disposed of expeditiousl 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 backshift Plant housekeeping and contamination control were generally observed to be generally excellen The inspectors performed system status checks on the following systems:
a. Safety Injection System b. Component Cooling Water System c. Auxiliary Feedwater System d. Vital Station Batteries e. Residual Heat Removal System f. Emergency Diesel Generators g. Containment Spray System h. Electrical Switchgear i. Containment Personnel Airlock No violations or deviations were identified within the areas inspecte. Technical Specification Compliance (71707, 62703, 61726)
During this reporting interval, the inspectors 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 inspectors 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 inspectors routinely observed operator alertness and demeanor during shift changes and plant tours. The inspectors conducted random off-hours inspections during the reporting interval to assure that operations and security were maintained in accordance with plant procedure The inspectors periodically verified the reactor shutdown margi The inspectors also periodically observed the reactor axial flux difference and compared the observed valves with those required by the T No violations or deviations were identified within the areas inspecte. Physical Protection (71707)
In the course of the monthly activities, the Resident Inspectors included a review of the licensee's physical security program. The inspectors verified by general observation, perimeter walkdowns and interviews that measures taken to assure the physical protection of the facility met current requirement The performance of various shifts of the security force was observed in the conduct of daily activities to include; protected and vital areas access controls, searching of personnel, packages and vehicles, badge issuance and retrieval, escorting of visitors, patrols and compensatory post In addition, the Resident Inspectors observed protected area lighting, protected and vital areas barrier integrity and verified an interface between the security organization and operations or maintenanc During the inspection period, the inspectors continued to monitor the progress and activities of the HBR Security System Upgrade Projec The inspectors attended the May 14, 1986 meeting of the Security Project Implementation Task Force and determined that the licensee was actively pursuing corrective measures to previously identified inspector followup items and facility improvements in the area of physical securit No violations or deviations were identified within the areas inspecte.
Monthly Surveillance Observation (61726, 61700, 71710)
The inspectors witnessed major portions of EST-010 (Revision 2) titled
"Containment Personnel Airlock Leakage Test". This engineering surveillance test is conducted semi-annually in order to determine the total leakage through the.containment personnel airlock. Satisfactory completion of this surveillance test is designed to fulfill the requirements of 10CFR50, Appendix J for type "B" tests, and a requirement of paragraph a of TS 4.4.1.2., which states that the personnel airlock shall be tested every six month The inspectors determined that the surveillance test procedure conformed to TS requirements, that all precautions and limitations were met and that the surveillance test was completed at the required frequency. The inspectors also verified that the required administrative approvals and tagouts were obtained prior to initiating the test, that the testing was accomplished by qualified personnel in accordance with an approved test procedure and that the required test instrumentation was properly calibrated. Upon completion of the testing, the inspectors observed that the recorded test data was accurate, complete and met TS requirements; observed that there were no test discrepancies; and independently verified that the system was properly
returned to servic In particular, the inspectors witnessed the following activities:
airlock exterior door closure, airlock pressurization, periodic pressure and temperature readings, airlock depressurization and return to service of the airloc No violations or deviations were identified within the areas inspecte.
Monthly Maintenance Observation (62703)
On May 10 and 16, 1986, the inspectors witnessed major portions of the activities associated with Corrective Maintenance Procedure CM-033 (Revision 0) titled "Charging Pump Maintenance, Power Frame".
The purpose of this corrective maintenance procedure is to provide instructions for disassembly, inspection, repair, and reassembly of the charging pump power fram This maintenance activity was precipitated by the May 7, 1986 shear failure of the crankshaft on the "A" charging pump. The exact cause of the crankshaft shear failure was not identified however; the licensee, in conjunction with the pump manufacturer, was in the process of investigating the inciden The inspectors determined (1) that this maintenance activity was conducted in accordance with approved procedures, (2) that the subject procedures appeared to be technically adequate to control the activity, (3) that the required administrative approvals and tagouts were obtained prior to work initiation, (4) that proper radiological and cleanliness controls were implemented, and (5) that removed, reinstalled, and replaced parts were properly controlled for reassembl Also, the inspectors observed that the licensee personnel involved in this activity were observing the precautions and limitations pertaining to the use of a designated storage area for parts removed while performing maintenance. It was also noted by the inspectors that the external surfaces of the charging pump and the surrounding areas were free of foreign material and loose objects during disassembly and reassembly and that when not required for maintenance, the charging pump was covered to preclude the entry of foreign materia The inspectors also observed major portions of the safety related maintenance associated with the replacement of the hydraulically operated actuator for the "B" Auxiliary Feedwater Pump (AFW) discharge valve AFW-4 It was ascertained that this activity was conducted in accordance with approved procedures, TS, and appropriate industry codes and standards.. The inspectors determined that these activities were not violating Limiting Conditions for Operations (LCO's)
and that redundant components were operabl The inspectors also determined (1) that the procedures used appeared to be adequate to control the activity, (2) that required administrative approvals and tagouts were obtained prior to work initiation, (3) that proper radiological controls were implemented, (4) that replacement parts and materials used were properly certified and (5) that these activities were accomplished by qualified personne The inspectors independently verified that equipment was properly tested before being returned to servic In particular, the inspectors witnessed the mechanical and electrical installation of the actuator on AFW-46 including the attachment of associated seismic restraints and connection of electrical lead The inspectors also visited the onsite level "A" storage area and reviewed the Purchase Order (PO)
file for the subject electro-hydraulic actuator which contained the certification of compliance, receipt inspection documentation, and purchase specificatio The materials contained in this PO file appeared complete, were stored properly, and were easily retrievabl No violations or deviations were.identified within the areas inspecte.
Operational Safety Verification (71707)
The inspectors 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.
ESF System Walkdown (71710, 61726, 56700)
The inspectors verified the operability of certain engineered safety features systems by performing a walkdown of the accessible portions of the safety injection, residual heat removal and containment spray systems as prescribed by Operations Surveillance Test Procedure OST-158 (Revision 3)
titled "Safety Injection and Containment Spray Systems Flowpath Verification Monthly Interval (At Power)".
The inspectors noted that the current revision of the subject procedure was used by qualified operations personnel and that the monthly performance of this surveillance test satisfied the requirements of Section 4.5.2.2 of the TS which states:
At monthly intervals during power operations each valve (manual, power operated, or automatic) in the safety injection (low and high pressure) and containment spray system flow paths that is not locked, sealed or otherwise secured in position shall be verified as correctly positione The inspectors determined that the prerequisites for the performance of this surveillance test were performed and that all specified precautions and limitations were observed. The inspectors looked for equipment conditions, maintenance status and items that might degrade performance (that hangers and supports were operable, acceptable housekeeping, etc.). The inspectors verified that valves were in proper position, power was available, and valves were locked as appropriate. The inspectors compared both local and remote position indication The inspectors notified the licensee that housekeeping in the Residual Heat Removal Pump Pit was well below the conditions maintained throughout the plant and that the motor operated RHR valves located in this area were difficult to identify due to the lack of stencil 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 inspectors determined that the licensee had taken corrective actions 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 inspectors 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 implication When licensee identified violations were noted, they were reviewed in accordance with enforcement policy. The inspectors had no further comment LER EVENT 83-07 Pressurizer PORV Failed to Meet Required Cycle Time 83-16 Steam Binding in Steam Driven Auxiliary Feed Pump 84-03 Steam Generator Snubbers, Failed Load Test 84-06 SI While Shutdown 84-10 SI Resulting from Disconnection of Battery Bus 84-12 Low Temperature Over Pressure Protection Procedural Error 85-01 Missed Weekly Surveillance Test on Diesel Fire Pump Batteries 85-06 Seismic Restraints 85-09 Reactor Trip Generator Lockout/Turbine Trip 86-02 Reactor Trip on High Steam Generator Level 86-03 Reactor Trip on Instrument Bus Spike 86-04 Reactor Trip on Surveillance Error 86-06 SI due to Rapid Cooldown 86-09 Reactor Trip on Steam Generator Level 86-10 Reactor Trip on Generator Motoring Protection No violations or deviations were identified within the areas inspecte.
Organization and Administration (36700)
The inspectors 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 is functioning as described in 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 standard 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; plant modifications, including the security system upgrade; the fire protection system; ongoing construction activities; and communications interface No violations or deviations were identified within the areas inspecte. Onsite Review Committee (40700)
The inspectors reviewed certain activities of the Plant Nuclear Safety Committee (PNSC)
to ascertain whether the onsite review functions were conducted in accordance with TS and other regulatory requirement The inspectors (1) attended the regular monthly PNSC meeting held on May 21, 1986 and observed the conduct of the meeting, (2)
ascertained that provisions of the TS dealing with membership, review process, frequency, qualifications, etc., were satisfied, and (3) reviewed meeting minutes to confirm that decisions and recommendations were accurately reflected in the minutes, and (4) followed up on previously identified PNSC activities to independently confirm that corrective actions were progressing satisfactorily. In particular, the PNSC reviewed a proposed change to the TS involving the limiting small break LOCA analysis as well as a review of the safety implications concerning the onsite Independent Dry Spent Fuel Storage Installatio No violations or deviations were identified within the areas inspecte.
Core Thermal Power Evaluation (61706)
The inspectors verified that the calculation of core thermal power was properly performed in accordance with Revision 5 to Operations Surveillance Procedure OST-010 titled "Power Range Calorimetric During Power Operation Daily;" and that the power level instruments indicated that the reactor power was within prescribed limits. The inspectors also reviewed the current revision of OST-010 for technical adequacy and reviewed the results for a specific evaluation at 98% powe The licensee performed the evaluations every day, which is within the frequency prescribed by the T No violations or deviations were identified within the areas inspecte.
IE Information Notice Followup (92717) IEN 85-45/Temporary Instruction 2500/15 Licensee actions in response to IE Information Notice 85-45 included an analysis, by Westinghouse, of the potential seismic interaction involving the movable in-core flux mapping syste The licensee concluded that the Unit 2 flux mapping system would maintain its
structural integrity during the plant specified seismic event and without jeopardizing the seal table pressure boundary. The inspectors also examined the safety review sheets associated with the licensee's analysis. This IEN is close IEN 85-48 Licensee actions in response to IE Information Notice 85-48, concerning a serious defect in the self-contained breathing apparatus (SCBA)
air cylinders manufactured by Luxfer USA Ltd.,
included immediate removal from service of approximately 25 of the affected cylinders at the Robinson Nuclear Sit The licensee replaced the affected air cylinders with replacements fitted with a steel neck ring to preclude rupture. This IEN is closed.