IR 05000261/1986010
| ML14175B375 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 05/15/1986 |
| From: | Fredrickson P, Krug H, Latta R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14175B374 | List: |
| References | |
| 50-261-86-10, NUDOCS 8605200270 | |
| Download: ML14175B375 (12) | |
Text
0 R Gfk UNITED STATES S
tNUCLEAR REGULATORY COMMISSION
REGION II
< o 101 MARIETTA STREET, ATLANTA, GEORGIA 30323 Report N /86-10 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:
April 11 - May 10, 1986 Inspectors:
'5&/__ 8_ E. P Kr Resident Inspector Date Signed M Latta, Resident Inspector Date Signed Approved by:I P. E. Fredrickson, Section Chief Oate igned Division of Reactor Projects SUMMARY Scope: This routine, announced inspection involved 254 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 enforcement action followu Results: No violations or deviations were identified within the areas inspecte PI R ADOCK pPR
REPORT DETAILS 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, E&C Supervisor W. Flanagan, Manager, Design Engineering W. Gainey, Maintenance Supervisor, Mechanical 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, Director (Acting), 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 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 May 8, 1986, with the Manager of the Robinson Nuclear Project Department, the Acting Plant General Manager and the Acting Director of Regulatory Complianc The licensee acknowledged the findings without exception. 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 50-261/83-09-0 The inspectors reviewed table 3.4-1, Amendment 86 of the T The identified discrepancies in the subject table, relative to the auxiliary feed water system, have been correcte (Closed) Inspector Followup Item 50-261/83-15-04. The inspectors examined Amendment 83 to the facility Operating License which consisted of numerous changes to the TS including changes to Table 3.5.2, items 16 and 17 and Table 4.1-1, items 39 and 4 The inspectors determined that the above mentioned, approved changes to the TS adequately described the protective functions provided for steam flow/feed flow mismatch in coincidence with low steam generator level including trip logic, attendant setpoints, channel operability, and channel surveillance requirement (Closed) Inspector Followup Item 50-261/84-02-06. A Loose Parts Monitoring System has been installed to detect loose objects within the primary and secondary system Additionally, the inspectors reviewed various plant procedures concerning the control of material introduced into these systems; in particular, Maintenance Management, Manual Procedure MMM-010, Revision 1, Cleanliness and Flushing Requirements. Based on this review, it was deter mined that adequate procedures exist to detect and prevent the ingress of loose parts into the primary and secondary system. 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 inspectors looked for the existence of unusual fluid leaks, piping vibra tions, 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 observed to be excellen The inspectors performed system status checks on the following systems: Safety Injection System Component Cooling Water System c. Auxiliary Feedwater System Vital Station Batteries e. Turbine Redundant Overspeed Trip System f. Electrical Switchgear g. Chemical and Volume Control System 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 accomp lished 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 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 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 April 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. Determination of Reactor Shutdown Margin (61707)
The inspectors reviewed the following current revisions to the licensee procedures for conformance to the TS, technical accuracy and completeness:
FMP-012 (Revision 3) titled "Manual Determination of Shutdown Margin Boron Concentration" FMP-010 (Revision 1) titled "Manual Determination of Xenon and Samarium Worth" FMP-015 (Revision 0) titled "EXSPACK" The inspectors reviewed the shutdown margin calculation performed by licensee personnel on May 6, 198 The calculation was performed and verified by qualified personnel using the CP&L Nuclear Computer Program titled EXSPACK (Version PNRO2011).
The inspectors questioned licensee personnel concerning the use and meaning of the various printout quantitie The inspectors also verified selected reactivity results printed out against the corresponding information provided by the graphs in the plant curve book. Agreement between the results was acceptable in every cas The inspectors also verified that the frequency of calculations, including all conditions and actions prescribed by TS, were met; and that changes made in boron concentration as a consequence of the shutdown margin calculation results were properly verified by chemical analysi No violations or deviations were identified within the areas inspecte. Target Axial Flux Difference Calculation (61711)
On April 18, 1986, the licensee performed a measurement of the target axial flux difference using Procedure EST-002, Revision 4, titled "Nuclear Instrumentation System Power Range Axial Offset Calibration". The inspectors determined that Revision 4 was the most current version and that the measurement was performed by qualified personne The inspectors verified that the subject procedure was technically adequate and that the target flux difference updating occurred at the frequency prescribed by the T Specifically, the inspectors verified (1) that appropriate prerequisites and initial conditions for the measurements were delineated in the procedure and were met, (2) that appropriate precautions and/or limitations were deline ated in the procedure and were observed for the measurements, (3) the correctness of the calculations for establishing the target axial flux difference for each of the excore detectors, and (4) that the process computer was updated to reflect the current target axial flux difference and that the plant operators were utilizing the current target flux value No violations or deviations were identified within the areas inspecte.
Monthly Surveillance Observation (61726, 61700, 71710)
The inspectors observed portions of the licensee's performance of Revision 3 to Operations Surveillance Test Procedure OST-551 titled "Turbine Valve and Trip Functional Test" on April 19, 198 The current revision of the subject test procedure was used by the operations personnel involved in this activity. The stated purpose of OST-551 is to ensure the proper operation of the Turbine Stop Valves, Control Valves, Reheat and Interceptor Valves, Main Steam Isolation Valves, and Turbine Trip Function The inspectors verified that this test satisfied the requirements of Table 4.1.3 of the TS for the monthly testing required during power operation The inspectors determined that the prerequisites for the performance of this surveillance test were met and that all precautions and limitations were observe The inspectors witnessed the functional testing of the Reheat and Inter ceptor valves and the Main Steam Isolation Valves as well as the Turbine Trip Functions of the following test valves:
Vacuum Trip Bearing Oil Trip Thrust Bearing Trip Overspeed Trip During the conduct of this test, the inspectors noted from reference to control room logs that at approximately 2:00 p.m. on April 19, 1986, the E-H Turbine control transferred from IMP-IN to IMP-OUT and the turbine load dropped approximately 35 MWE. The turbine load was stabilized using the E-H limiter to control the load. The licensee informed the inspectors that the
above condition is currently under investigation. The inspectors determined that OST-551 was successfully completed because all test parameters and acceptance criteria were me The inspectors witnessed portions of the licensee's performance of Revision 6 to Maintenance Surveillance Test Procedure MST-010 titled
"Reactor Protection Logic Train "A" and "B" at Power Safeguard Relay Rack Train "A" and "B" on April 15, 1986. The inspectors noted that the current revision of the subject procedure was used by qualified operations personnel involved in this activit This test was performed to ensure the Reactor Protection Logic Train "A" and
"B" and Safeguards Relay Rack Train "A" and "B" functioned properl The inspectors verified that the monthly performance of this test satisfied the requirements of Section 4.0, Surveillance Requirements, of the T The inspectors also determined that the procedural prerequisites for the performance of this surveillance test were performed and that all precau tions and limitations were observed by the license The inspectors independently determined that the system was properly returned to service, that the test results met TS requirements and that the test was completed at the required frequenc The inspectors also witnessed the surveillance testing of the "Turbine Redundant Overspeed Trip System" as prescribed in MST-552, Revision 3. This test is conducted monthly in accordance with TS requirements, as defined in Table 4.1-1, to determine the operability of the Turbine Redundant Overspeed Trip System. The inspectors determined that the test technicians involved in this activity were qualified and that they were working to the latest revision of MST-552. The inspectors verified that all procedural prerequi sites were satisfied and that the precautions and limitations of this activity were complied with by the license The inspectors observed that the following surveillance test criteria were satisfied:
Voltages were within the specified tolerance Overspeed test potentiometer settings remained within the specified allowable ranges Proper indications were observed on the Test and Failure lamps Required operation of the overspeed trip system logic occurred as verified by the correct operation all test light indications The inspectors also witnessed the performance of Operations Surveillance Test OST-908, Revision 9, titled "Component Cooling System Component Test" on April 16, 198 The purpose of this surveillance test was to verify the mechanical perfor mance and access the operational readiness of specified portions of the Component Cooling Water (CCW)
system to fulfill their required safety function In particular, the inspectors witnessed the following oper ability and performance checks on the CCW pumps:
Inlet (suction) pressure readings Differential pressure readings Vibration amplitude measurement Lubrication oil levels verification The inspectors determined that the licensee performed this surveillance test in accordance with approved procedures and that all prerequisites were accomplished prior to commencing the activit Additionally, it was determined that OST-908 appeared to be adequate,.that radiological controls were maintained throughout the conduct of this test, and that the acceptance criteria for CCW pump operation were me OST-910 is designed to verify the operability of the Dedicated Shutdown (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 properly aligned for service in accordance with the latest revision of OP-602; that the required administrative approvals were obtained; that precautionary limita tions were observed; and that the prescribed acceptance criteria were achieve In particular, the inspectors observed 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 amps. 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 (62703)
The inspectors observed two maintenance activities of safety-related systems and components to ascertain that these activities were conducted in accord ance 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 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 inspectors verified that these activities were accomplished by qualified personnel using approved procedures. The inspectors independently verified that eqtipment was properly tested before being returned to servic The inspectors observed the performance of maintenance activities associated with Corrective Maintenance Procedure CM-035, Revision 0, titled "Charging Pump Maintenance, Valve Disassembly and Reassembly."
The purpose of this corrective maintenance procedure is to provide instruc tions for the disassembly, inspection, and reassembly of the positive displacement charging pump suction and discharge valve The inspectors determined (1) that this maintenance activity was conducted in accordance with approved procedures, (2) that the subject procedures were technically adequate to control the activity, (3) that the required admini strative 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 In particular, 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 witnessed the replacement of the 2" Schedule 80 pipe and flange down stream of the check valve (RFW-17) on the recirculation line of the Steam Driven Auxiliary Feedwater (SDAFW) pump on April 17, 198 The purpose of this safety related maintenance activity was to repair a leak in the subject recirculation line detected during a SDAFW pump surveillance test conducted on April 15, 198 This maintenance was conducted in accordance with approved procedures. The inspectors also determined (1) that this activity did not violate limiting conditions for operation, (2) that redundant components were operable, (3)
that the procedures used were adequate to control the activity, (4) that required administrative approvals and tagouts were obtained prior to work initiation, (5) that proper radiological, and appropriate ignition and fire prevention controls were implemented, and (6) that replacement parts and materials used were properly certifie The inspectors verified that these activities were accomplished by qualified personne I
Additionally, the inspectors determined that the station welding procedures, cleanliness controls, QC hold points, and the design, fabrication, and installation documents and records used during this repair activity were appropriat During this reporting period, the inspectors 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 inspected 1 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. 1 ESF System Walkdown and Monthly Surveillance Observation (71710, 61726, 56700)
The inspectors verified the operability of the engineered safety features system by performing a walkdown of the accessible portions of the Auxiliary Feedwater Syste The inspectors confirmed that the licensee's system lineup matched plant drawings and the as-built configuratio The inspectors looked for equipment conditions, maintenance status and items that might degrade performance (that hangers and supports were operable, acceptable housekeeping, etc.) and inspected the interiors of electrical and instrumentation cabinets for loose material, debris, and jumper The inspectors verified that valves were in proper position, power was avail able, and valves were locked as appropriat 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 83-29 SI Accumulator Level transmitter found out of calibration 84-04 2nd quarter fish samples not taken within allowed interval 84-08 Condensate storage tank level transmitters out of calibration 84-09 Containment pressure channels out of calibration 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 were in conformance with the requirements of the TS by verifying that (1) the established organization as described in the TS was functioning effectively, (2) personnel qualification levels were in conformance with applicable codes and standards, and (3) the lines of authority and responsibility were 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; radiation control 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 regularly scheduled PNSC meeting held on April 16, 1986 and observed the conduct of the meeting, (2) ascertained
that provisions of the TS dealing with membership, review process, qualifi cations, etc., were satisfied, and (3) followed up on previously identified PNSC activities to independently confirm that corrective actions were progressing satisfactoril The inspectors determined, through a review of the meeting minutes, that the following topics of concern were reviewed by the committee:
Procedures, tests, and experiments Proposed procedure changes Plant modifications Reportable events to the NRC Non-conformance reports Reactor trips PNSC subcommittee activities In particular, the events related to the reactor trips which occurred on March 22, 1986 and March 24, 1986 were discussed as were the highlights of the ALARA subcommittee meeting minute 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 performed using approved methods and that the power level instruments indicated that the reactor power was within prescribed limits. Specifically, the inspectors reviewed the current revision of the licensee core thermal power evaluation procedure for technical adequacy and reviewed the results for a specific evaluation at 98% powe The licensee performed the evaluations every day, which was within the frequency prescribed by the T No violations or deviations were identified within the areas inspected.