IR 05000261/1987020
| ML14191A839 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 07/17/1987 |
| From: | Fredrickson P, Krug H, Latta R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14191A838 | List: |
| References | |
| 50-261-87-20, NUDOCS 8707250029 | |
| Download: ML14191A839 (10) | |
Text
0 REZc UNITED STATES
.o NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30323 Report N /87-20 Licensee Carolina Power and Light Company P. 0. Box 1551 Raleigh, NC 27602
.Docket N License N DPR-23 Facility Name H. B. Robinson Inspection Con cted: Ju e 11 -
July 10, 1 87 Inspectors:
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Kru, Senior Reside 11Inspector Oat Signed R. M tta, Resident Inspector Oat Signed Approved by:
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P.E. Fredrickson, Sectibn Chief ate-Signed Division of Reactor Projects SUMMARY Scope:
This routine, announced inspection was conducted in the areas of Technical Specification (TS)
compliance; including observance of any Limiting Conditions for Operation (LCO), plant tour, operations performance, reportable occurrences, housekeeping, site security, surveillance activities, maintenance activities, quanty assurance practices, radiation control activities, outstanding items review, IE Bulletin and IE Notice followup, organization and administration, independent inspection, Plant Status Report, Systematic Assessment of Licensee Performance (SALP)
and enforcement action followu Results:
No violations or deviations were identified within the areas inspecte GPDR ADOC 05000261
REPORT DETAILS 1. Licensee Employees Contacted R. Barnett, Maintenance Supervisor, Electrical G. Beatty,' Vice President, Robinson Nuclear Project Department R. Chambers, Engineering Supervisor, Performance D. Crocker, Supervisor, Radiation Control J. Curley, Director, Regulatory Compliance J. Eaddy, Supervisor, Environmental and Chemistry R. Femal, Shift Foreman, Operations W. Flanagan, Manager, Design Engineering W. Gainey, Supervisor, Operations Support P. Harding, Project Specialist, Radiation Control E. Harris, Director, Onsite Nuclear Safety 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. Miller, Maintenance Supervisor R. Moore, Shift Foreman, Operations 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 D. Sayre, Senior Specialist, Regulatory Compliance LSeagle,.Shift Foreman, Operations R. Smith, Manager, Environmental *and Radiation Control R. Steele, Shift Foreman, Operations R. Wallace, Manager, Technical Support L. Williams, Supervisor, Security D. Winters, Shift Foreman, Operations H. Young, Director, Quality Assurance/Quality Control (QA/QC)
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 July 10, 1987, with
- the Plant General Manager and the Director of Quality Assuranc 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 inspectio No written material was given to the licensee by the Resident Inspectors during this report perio.
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 expeditiously. During tours, the inspectors 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 date Some tours were conducted on backshift Plant housekeeping and contamination control were observed to be outstandin The licensee was informed of a number of minor items observed by the inspectors during numerous plant tours including damaged pipe lagging, missing valve identification tags, inadequate housekeeping in specific areas, and minor equipment oil leaks. These items were responded to by the. licensee in.a timely manner and corrective actions were promp The inspectors performed system status checks on the following systems:
a. Safety Injection (SI).System Component Cooling Water (CCW) System c. Auxiliary Feedwater (AF) System Vital Station Batteries (VSB)
e. Electrical Switchgear f. Chemical and Volume Control System (CVCS) Emergency Diesel Generators (EDG)
h. Dedicated Shutdown (DS) Diesel Generator 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 activities. These verifications were accomplished by direct observation of monitoring instrumentation, valve positions, switch positions, and review of completed logs and record In addition.,
on a daily basis in the control room, the inspectors independently examined Emergency Response Facility Information System (ERFIS)
and Safety Parameter Display Systems (SPDS)
display of safety related parameters, including component status information, for indications related to conformance with the T No violations or deviations were identified within the areas inspecte.
Plant Operations Review (71707, 62703, 61726, 61707)
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 record 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 values 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 inspectors included a review of the licensee's physical security progra 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 inspectors routinely observed the alertness an demeanor of security force personnel during plant tour 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; and patrols and compensatory posts. In addition, the inspectors observed protected area lighting, protected and vital areas barrier integrity and verified an interface between the security organization and operations at the motor driven auxiliary feedwater pump room. The inspectors also toured both the central and secondary alarm.station No violations or deviations were identified within the areas inspecte. Monthly Surveillance Observation (61726, 61700, 71710)
The inspectors observed certain surveillance related activities of safety-related systems and components to ascertain that these activities were conducted in accordance with license requirement The inspectors observed portions of selected surveillance tests including all aspects of one major surveillance test involving safety-related systems. The inspectors determined that the surveillance test procedure conformed to TS requirements, that all precautions and LCO's 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 reauired test instrumentation was properly calibrate Upon completion of the testing, the inspectors observed that the recorded test data was accurate, complete and met TS requirements; verified that test discrepancies were properly rectified, and; independently verified that the systems were properly returned to servic On June 30, 1987, the inspectors witnessed the conduct of OST-910 (Revision 9) titled "Dedicated Shutdown Diesel Generator".
OST-910 is designed to verify the operability of the DS diesel. generator under emergency conditions and to confirm the operational readiness of associated mechanical and electrical component The inspectors determined that the DS diesel generator was aligned for service in accordance with the latest revision of OP-602; that the required administrative approvals were obtained; that precautionary limitations were observed; and that the stated acceptance criteria were achieve Specifically, the inspectors determined that subsequent to the manually initiated start of the DS diesel generator it was properly synchronized with other power sources and that the assumption of load (300 amps) by the DS diesel generator did not exceed either 2400 kw or 300 amp The inspectors also determined that all components associated with the DS diesel generator appeared to function properly and that the recorded readings were within the normal rang No violations or deviations were identified within the areas inspecte. Monthly Maintenance Observation and Maintenance Program Evaluation (62703, 62700, 62704, 62705)
The inspectors observed several maintenance related activities of safety-related systems and components to ascertain that these activities were conducted in accordance with approved procedures, TS and appropriate industry codes and standard The inspectors determined that these activities were not violating LCO's and that redundant components were operable. The inspectors 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, and (3) that proper radiological, and appropriate ignition and fire prevention controls were implemente The inspectors verified that these activities were accomplished by qualified personnel using approved procedures. The inspectors independently verified that equipment was properly tested before being returned to servic In particular, the inspectors witnessed major portions of maintenance surveillance test MST-010 (Revision 14) titled "Reactor Protection Logic Train A and.B at Power and Safeguards Relay Rack Train A. and B'".
This test is performed to insure that the reactor protection logic train A and B and safeguard relay rack train 'A' and 'B' function properly and satisfy TS requirement The inspectors observed the adequacy of communications between the safeguards logic panel and the control room as
well as the conduct of the individuals involved in the surveillance. The inspectors witnessed the safeQuard relay logic testing of train 'A' and
'B' and determined that the safeguards and test lights and annunciator alarms were received on the reactor turbine generator boar During-the conduct of this test, the inspectors noted that all prerequisites and precautions were observed by the personnel involved including the limitation that only one reactor protection logic train bypass breaker was racked out at any given tim The inspectors witnessed the return to service. of both trains of the safeguard relay logic system-without inciden Additionally, the inspectors witnessed the repair activities conducted on the DS Diesel Generator as prescribed in maintenance work request 87-AIXT The inspectors witnessed the adjustment of the DS diesel governor compensating needle valve associated with the speed control sensitivity of the diesel at idle speed This work was conducted using approved and controlled procedures by qualified operations and maintenance personne Additionally, the inspectors reviewed several outstanding job orders to determine 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, 82301)
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 and Monthly Surveillance Observation (71710, 61726, 56700, 617.15)
The inspectors verified the operability of an engineered safety features system by performing a walkdown of the accessible portions of the Motor Driven Auxiliary Feedwater (MDAFW)
syste The inspectors confirmed that the licensee's system lineup procedures matched plant drawings and the as-built configuration. The inspectors looked for equipment conditions and items that might degrade performance (hangers and supports were operable, housekeeping, etc.)
and inspected the interiors of electrical and instrumentation cabinets fordebris, loose material, jumpers, evidence of rodents, etc. The inspectors verified that valves were in proper position,
power was available, and valves were locked as appropriate. The ihspectors compared both local and remote position indication In particular, the inspectors determined that the MDAFW system conformed to the flow diagram description contained in drawing G-190197 (Revision 11) titled "Feedwater, Condensate, and Air Evacuation System" sheet 4 of 4. During the course of the walkdown, the inspectors assessed the overall condition of the MDAFW system to identify any problems which could impact system performanc The. inspectors verified that the associated process instrumentation was properly installed, functioning, and that the calibration dates were curren The inspectors also determined that. the valves in the system flow path were correctly positioned as required by procedure and that they did not exhibit excessive 'packing leakage, bent stems, or missing hand wheel Additionally, the inspectors examined system hangers, snubbers, and supports for proper make up, alignment and configuratio No prohibited ignition sources or flammable materials were identified in the vicinity of the MDAFW pump The inspectors did note several missing valve identification tags during the system walkdown; however, when identified to the licensee, prompt corrective action.was take No violations or deviations were identified within the areas inspecte.
Plant Startup from Refueling (71711)
The inspectors reviewed plant startup activities during the recovery from the recent refueling outage which ended on June 16, 1987. The inspectors ascertained that systems disturbed or tested during the refueling outage were returned to an operable status before plant startup and that plant startup, heatup, approach to criticality, and core physics tests following the outage were conducted in accordance with approved procedures. :Before plant startup, the inspectors performed a walk-through of appropriate portions of Containment Spray and the Safety Injection systems disturbed during the refueling outage and independently ascertained that these systems have been returned to service in accordance with approved procedure The inspectors also observed portions of the control rod drive and control rod position checks including the conduct of EST-048 (Revision. 5) "Control Rod Drop Test, Refueling Outage".
The purpose of this procedure is to meet the requirements of TS Section 3.10.4.1 which states:
"The drop time of each control rod shall be not greater than 1.8 seconds at full flow and operating temperature from the beginning of rod motion to dash pot entry."
The inspectors verified that Revision 5 was the latest revision of EST-048 and that all prerequisites, precautions, and limitations had. been accomplishe The inspectors also determined that the test equipment being utilized was properly calibrated and controlle The inspectors reviewed selected visicorder traces taken during the rod drop test and
reviewed the recorded test data and determined that the rod drop times were within the required 1.8 second interva While witnessing the startup, the inspectors verified that the. control rod withdrawal sequence and rod withdrawal authorization were available and that all surveillance tests required to be performed.before the startup were satisfactorily completed. Additionally, the: inspectors verified that the startup was performed in accordance with technically adequate and approved procedures which had been revised to reflect changes made to the facility and to the startup testing program, and verified that startup activities were conducted in accordance with TS requirement The post-refueling initial criticality and zero power physics tests were conducted by the licensee in accordance with Engineering Surveillance Test Procedure EST-050 (Revision 7) titled "Refueling Startup Procedure".
Revision 7 to EST-050 was inspected and found to be technically adequate, properly approved, and in accordance with TS requirements. The inspectors witnessed the approach to, and the achievement of, reactor criticalit The inspectors noted that the measured boron concentration of 1398 ppm at criticality was approximately 77 ppm less than the expected criticality point (ECP)
of 1475 pp This concentration exceeds the 50 ppm limit specified by EST-050 for unreviewed acceptanc This occurrence was determined to be the result of errors introduced by the core physics modeling of the high enrichment of gadolinia used in the computer calculations for this core. Subsequent to a special plant nuclear safety committee meeting, which determined that the analytical errors in the ECP were within acceptable limits for the existing gadolinia concentrations, unrestricted power operations were resume The inspectors also observed portions of the measurements of the moderator temperature coefficient at two rod positions; and control rod banks "C" and "D" differential and integral reactivity wort In every case, the measured values agreed with those predicted within the prescribed acceptance criteri Licensee personnel were observed to properly follow and annotate the procedur The inspectors observed portions of a number of surveillance activities of safety-related systems and components to ascertain that these activities were conducted in accordance with license requirements. On July 1, 1987, the. inspectors observed all aspects of operations surveillance test OST-010 (Revision 6), "Power Range Calorimetric During Power Operation."
The inspectors determined that the surveillance test procedure OST-010 conformed to TS requirements, that all precautions and LCO's were met and that the surveillance test was completed at the required frequenc The inspectors also verified that the required administrative approvals were obtained prior to initiating the test, that the testing was accomplished by qualified personnel in accordance with the current version of an approved test procedure and that the required test instrumentation was properly calibrate Upon completion of the testing, the inspectors
observed that the recorded test data were accurate, complete and met TS requirement There were no test discrepancie On June 29, 1987, the inspectors witnessed the core flux mapping performed in accordance with performance of EST-054, Revision This engineering surveillance test was conducted to obtain information pertinent to core power distribution and to obtain data necessary for proper calibration of the excore detectors. Duri'ng the conduct of this surveillance, control room personnel were observed aligning the movable detector system and operating the ERFIS computer in order to perform a full core flux ma The licensee personnel involved were qualified and they used Revision 3 which was the latest revision of EST-054. Upon the completion of EST-054, the inspectors witnessed the return of the movable detectors to their respective storage'areas as indicated by the control room instrumentatio No violations or deviations were identified within the areas inspecte Onsite Followup of Events and Subsequent Written Report's of Nonroutine Eve.nts 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 commitments. 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 87-08 Reactor Trip at Cold Shutdown 87-09 Injection/Recirculation Switchover Interruption 87-10 Reactor Trip Due -to Failed SOLA Transformer 87-12 Shutdown Trip on Voltage Drop 87-13 Low Head Safety Injection Isolation 87-14 Leaking Valve RHR-750 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 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 standards. The inspectors also reviewed appropriate licensee records to ascertain whether the licensee's use of overtime is in conformance with regulatory requirements and that any deviations from maximum overtime limits were authorized in accordance with TS and/or plant administrative procedure Comprehensive discussions of current safety-related activities were conducted with plant management and technical personnel during this reporting period including, and in particular, Operations, 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 interfaces. On July 6, 1987, the licensee announced five significant personnel changes intended to strengthen the plant organizatio 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 PNSC meeting held on June 29, 1987, 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 satisfactoril No violations or deviations were identified within the areas inspected.