IR 05000261/1986023
| ML14175B435 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 10/10/1986 |
| From: | Fredrickson P, Krug H, Latta R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14175B434 | List: |
| References | |
| 50-261-86-23, NUDOCS 8610210366 | |
| Download: ML14175B435 (8) | |
Text
REG UNITED STATES NUCLEAR REGULATORY COMMISSION REGION il 101 MARIETTA STREET, ATLANTA, GEORGIA 30323 Report No.:
50-261/86-23 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: August 11 -
September 10, 1986 Inspectors:
2FOJLkb (0,/6 /
HI E. P Krug, Senio-Resident Inspector Date Signed R..
tta, esident Inspector Date Signed Approved by:
//0d 6 P.. Fredrickson, Section Chief Vate !igned 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, Plant Status Report, Systematic Assessment of Licensee Performance (SALP)
and enforcement action followu Results:
No violations or deviations were identified within the areas inspecte *
8610210366 861010 PDR ADOCK 05000261 G
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 0. 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 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. 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 0. Sayre, Senior Specialist, Regulatory Compliance 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 H. Young, Director, Quality Assurance/Quality Control Other licensee employees contacted included technicians, operators, mechanics, construction personnel, security force members, and office personne. 2. Exit Interview (30702, 30703)
The inspection scope and findings were summarized on September 11, 1986, with the Plant General Manager, Acting Director of Quality Assurance, and the Director of Onsite Nuclear Safety Group. 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 inspectio No written material was given to the licensee by the Resident Inspectors during this report perio.
Licensee Action on Previous Enforcement Matters (92702)
(Closed) Violation 50-261/84-19-04: The inspectors, using plant procedure OST-624 (Revision 6) "Fire Damper Inspection" as guidance, performed a walk down of selected fire dampers and determined that the licensee had taken corrective measures to properly identify them. This item is close (Closed)
Violation 50-261/82-33-03:
The inspectors reviewed Corporate Quality Assurance audits for the preceding 18 months and determined that the subject audits, with one exception, had been issued within the required time frame. The exception occurred when audit report 85-08 was issued 3 days late. This example appears to be an isolated case and does not represent a programmatic breakdown. This item is close.
Licensee Action on Previously Identified Inspection Items (92701)
(Closed) Inspector Followup Item 50-261/83-02-10: The licensee modified E &
ORC Surveillance Test Procedure RST-020 titled "Verification of Electronic Calibration of Radiation Monitoring System Monitors R-32 A & B" to record the post-calibration check source valve on the test data sheets for RMS monitors R-32 A & B. Additionally, Technical Support Management Manual TMM-003 titled "Q-List Control Procedure" was modified to include RMS monitors R-32 A & B on the Q-List. This item is close (Closed)
Inspector Followup Item 50-261/83-05-02:
The licensee revised the appropriate refueling surveillance procedures to include the functional testing of Reactor and Turbine Gaugeboard (RTGB)
pushbuttons for reactor trip, safety injection, containment phase A isolation, and main steam isolation. This item is close.
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 backshifts. Plant housekeeping was observed to be outstandin 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. Electrical Switchgear f. Chemical and Volume Control System g. Containment Spray System h. Dedicated Shutdown Diesel 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. 7. 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 malfunction 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 tour 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 requirements. The inspectors routinely observed the alertness and 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, 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 September 3, 1986 meeting of the Security Project Implementation Task Force and determined that the licensee was pursuing corrective measures to previously identified 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 observed all aspects of operations surveillance test OST-202 (Revision 5) "Steam Driven Auxiliary Feedwater System Component Test". The purpose of this test is to verify the mechanical performance and assess the operational readiness of components in the Auxiliary Feedwater System (AFW).
Successful completion of this monthly surveillance test satisfies the requirements set forth in TS 4.8.2, 4.8.3, 4.8.4 and Table 4.2-2, Item 3 TS 4.8.2 states:
The steam turbine driven auxiliary feedwater pump by using motor operated steam admission valves will be started at intervals not to exceed one month, run for 15 minutes, and determined that it is operable when the reactor coolant system is above the cold shutdown condition. When periods of reactor cold shutdown extend this interval beyond one month, the test shall be performed immediately following reactor heatu Whereas TS 4.8.3 states:
The auxiliary feedwater pumps discharge valves will be tested by operator action at intervals not greater than one mont Whereas TS 4.8.4 states:
These tests shall be considered satisfactory if control board indication and subsequent visual observation of the equipment demonstrate that all components have operated properl The inspectors determined that the surveillance test procedure conformed to TS requirements, that all precautions and Limiting Conditions for Operations (LCO's)
were met and that the surveillance test was completed at the required frequenc 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 calibrate Upon completion of the testing, the inspectors observed that the recorded test data was accurate, complete and met TS requirements; and, independently verified that the systems were properly returned to servic In particular, the inspection emphasized the following pump and valve test activities:
inlet (suction)
pressure, pump differential pressure, pump vibration amplitude, lubricating oil pressure and temperature, turbine pump speed, valve stem travel and position indication, valve cycle times, and verification of pump discharge flow control valve operatio No violations or deviations were identified within the areas inspecte. Monthly Maintenance Observation (62703)
The inspectors observed the performance of maintenance surveillance test MST-801 (Revision 1),
"DSD and UPS Batteries" to ascertain that these activities were conducted in accordance with approved procedures, and appropriate industry codes and standard The inspectors determined that these activities were not violating LCO' 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 certifie The inspectors verified that these activities were accomplished by qualified personnel using approved procedure The inspectors independently verified that equipment was properly tested before being returned to servic The inspectors observed that all test precautions and limitations were observed, that the multimeter used was properly calibrated, and that required protective clothing was worn by the maintenance technicia The inspectors verified that battery bank voltages and electrolyte levels in each cell were properly measured and recorded in accordance with the parameters and acceptance criteria stated in MST-80 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)
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 At 0530 on September 3, 1986, the inspectors observed plant conditions and reviewed the records and charts in the control room associated with the plant primary system hydrostatic test (to a test pressure of 2335 psig) and the achievement of hot shutdown with the shutdown bank fully remove The source reciprocal multiplication plot was examined as were the time-temperature graphs associated with plant heatup. No abnormalities were observe No violations or deviations were identified within the areas inspecte.
ESF System Walkdown (71710, 61726, 56700)
The inspectors verified the operability of the engineered safety features system by performing a walkdown of 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 confirmed that the licensee's system lineup procedures 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.).
The inspectors verified that valves were in proper position, power was available, and valves were locked as appropriat The inspectors compared both local and remote position indication 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 certain LERs to establish the status of ongoing licensee activities associated with them; however, no LER's were closed during this inspection interva 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
7 established organization, as described in the TS, 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, 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, especially concerning the dry spent fuel storage facility; 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 August 20, 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 satisfactoril No violations or deviations were identified within the areas inspecte.
Followup on Headquarters Requests (92704, TI 0110/3, TI 0110/4)
The licensee received Material License No. SNM-2502 issued pursuant to 10CFR Part 72 on August 13, 198 Issuance of this license constitutes authorization for a twenty-year term to receive, possess, store, and transfer spent fuel from H. B. Robinson Unit 2 to an independent spent fuel storage installation located on sit In conjunction with this activity, the resident inspectors have become familiar with the licensee's project schedule and will coordinate the timing of in-process inspections with the regional staf No violations or deviations were identified within the areas inspected.