IR 05000261/1987001
| ML20211M875 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 02/19/1987 |
| From: | Fredrickson P, Krug H, Latta R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20211M750 | List: |
| References | |
| 50-261-87-01, 50-261-87-1, NUDOCS 8702270383 | |
| Download: ML20211M875 (10) | |
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UNITED STATES
'o NUCLEAR REGULATORY COMMISSION '
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REGION li g-j 101 MARIETTA STREET, N.W.
ATLANTA. GEORGI A 30323
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-Report No.: 50-261/87-01
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Licensee: Carolina Power and Light' Company
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P. O. Box 1551 Raleigh, NC 27602
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Docket No.: 50-261
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ILicenseNo.i.DPR-23
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Facility Name: H. B. Robinson
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Inspection Can, ducted: Jan ary 11 - February 10, 1987'.
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NRfC Inspectors:
u Date Signed fs m}
g, Senior Resident Inspector?-
2h9/87 g.,s.h E. P.
MR\\.
Lat,ta, Resident Ins,ector Date Signed
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Approved by :
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~J P. E. Fredrickson, Section Chief
' Date' 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 Operations (LCO), 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 foi,lowup.
Results: No violations or deviations were identified within the areas inspected.
070227o3e3 B70219 PDR ADOCK 0500
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I REPORT DETAILS
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Licensee Employees Contacted R. Barnett, Maintenance Supervisor, Electrical G. Beatty, Manager, Robinson Nuclear Project Department 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 Chemistry W. Flanagan, Manager, Design Engineering W. Gainey, Maintenance Supervisor, Mechanical P. Harding, Project Specialist (Acting), 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. 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 i
M. Page, Engineering Supervisor, Plant Systems i
R. Powell, Principal Specialist, Maintenance
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D. Quick, Manager, Maintenance B. Rieck, Manager, Control and Administration W. Ritchie, Supervisor (Acting), Radiation Control D. Sayre, Senior Specialist, Regulatory Compliance D. Seagle, Shift Foreman, Operations l
R. Smith, Manager, Environmental and Radiation Control
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R. Steele, Shift Foreman, Operations R. Wallace, Manager, Technical Support L. Williams, Supervisor, Security H. Young, Director, Quality Assurance / Quality Control (QA/QC)
Other licensee employees contacted included technicians, operators, mechanics, construction personnel, security force members, and office personnel.
2.
Exit Interview (30702, 30703)
The inspection scope and findings were summarized on February 10, 1987, with the Plant General Manager and the Director of Regulatory Compliance. 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 itcensee by the Resident Inspectors during this report period.
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Licensee Action on Previous Enforcement Matters (92702)
(Closed) Violation 50-261/86-28-05:
This violation involved two examples of failure to follow procedures which resulted in reactor trips.
The inspectors reviewed the corrective actions taken by the licensee as documented in CP&L's letter, serial: RNPD/87-8, and determined that the changes to the training program and the procedural changes which have been issued appeared adequate.
This item is closed.
4.
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 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 backshifts.
Plant housekeeping and contamination control were observed to be outstanding.
The inspectors performed system status checks on the following systems:
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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.
Diesel Generators h.
Instrument Air System No violations or deviations were identified within the areas inspected, 5.
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 accom-plished by direct observation of monitoring instrumentation, valve positions, switch positions, and review of completed logs and records.
No violations or deviations were iden+1fied within the areas inspected.
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l Plant Operations Review (71707, 62703, 61726, 61707)
6.
Periodically during the inspection interval, the inspectors reviewed shift logs and operations records, including data sheets, instrument traces, and l
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 procedures.
The inspectors periodically verified the reactor shutdown margin.
The inspectors also periodically observed the reactor axial flux difference and compared the observed values with those required by the TS.
No violations or deviations were identified within the areas inspected.
7.
Physical Protection (71707)
In the course of the monthly activities, the 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 tours.
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 or maintenance.
No violations or deviations were identified within the areas inspected.
8.
Monthly Surveillance Observation (61726, 61700, 71710)
The inspectors observed all aspects of operations surveillance test OST-202 (Revision 6) " 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 33.
TS 4.8.2 states:
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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 heatup.
Whereas TS 4.8.3 states:
The auxiliary feedwater pumps discharge valves will be tested by operator action at intervals not greater than one month.
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 properly.
The inspectors determined that the surveillance test procedure conformed to TS requirenents, that all precautions and LC0'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 required test instrumentation was properly calibrated.
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 operation.
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 system was properly returned to service.
The inspectors also witnessed the performance of OST-204 (Revision 2) " Steam Driven Auxiliary Feedwater Pump Emergency Cooling System Chrck Valve Test".
The quarterly performance of this test is designed to verify the operability of check valves SW-261 and SW-272.
These valves are located in the emergency cooling system piping to the steam driven auxiliary feedwater pump (SDAFW).
The inspectors noted that the current revision of the subject procedure was used by the qualified operations personnel involved in this activity and that all prerequisi;es and precautions were accomplished prior to commencing the test.
The insrectors observed that the 50AFW system was properly aligned for the te!.t, that communications had been established between the control room operations personnel and the operator staticned at the SDAFW pump, that the subject check valves appeared to operate as required, and that the prescribed acceptance criteria were achieved.
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No violations or deviations were identified within the areas inspected.
9.
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 standards.
The inspectors witnessed the replacement of the "Y" strainer down stream of isolation valve MS-161 on the Steam Driven Auxiliary Feedwater pump on January 14, 1987.
This safety related maintenance was necessitated by a steam leak in the strainer plug.
Specifically, the inspectors reviewed the controlling Work Request and Authorization Form, with its attached welding instructions and weld sketch, Engineering Evaluation, Weld Data Report and Welding and Brazing Material Control Record. The inspectors examined the Q-Listed material records and reviewed the system tag-out forms.
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 safety-related repair activity appeared adequate.
Additionally, the inspectors witnessed repair activities associated with the
"B" Instrument Air Compressor. The subject repairs were executed in order to eliminate air leaks on the upper cover plate of the compressor.
The inspectors determined that adequate work controls existed in that component isolation both electrical and pneumatic were accomplished and appropriate tags were hung prior to starting work, cleanliness and replacement material were controlled and tools and repair materials were prestaged.
On January 16, 1987, the inspectors witnessed selected portions of MST-016 (Revision 3) " Containment Pressure Protection Channel (Set I, II and III)
Testing". This maintenance surveillance test was conducted to satisfy TS Section 4.1, Table 4.1-1, Item 18 and to determine operability of the Containment Pressure Protection Channels.
The inspectors witnessed the conduct of the individuals involved in this surveillance and determined that the latest revision of the procedure was being utilized, that the shif t foreman had been notified prior to starting the test as required by procedure, and that all prerequisites and precautions were observed including the limitation that only one door in the relay racks be open at any given time.
The inspectors witnessed the return to service of the Containment Pressure Protection Channels, Set I and III and checked the status of the corresponding display light windows on the reactor turbine generator boar.
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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 QC hold points were established where required, (3) that required adminis-trative approvals and tagouts were obtained prior to work initiation, (4) that proper radiological, and appropriate ignition and fire prevention controls were implemented, and (5) 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 equipment was properly tested before being returned to service.
The inspectors also 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 system.
No violations or deviations were identified within the areas inspected.
10. 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 records.
As identified by the licensee, certain inadequacies were detected in a number of electrical and mechanical fire barrier penetrations in the reactor auxiliary building.
During routine surveillance inspection, in accordance with OST-623 titled " Fire Barrier Penetration Seal Inspection", a sample of 350 penetrations were examined of which apt roximately 25 penetrations were found to have less than the required amount of fire retardant material installed.
The inspectors examined the degraded fire barrier penetrations as well as selected normal penetrations.
Additionally, the inspectors examined the physical alarm system, the applicable local detectors, and the auxiliary building deluge control system.
The inspectors also reviewed the following licensee documents to determine post surveillance history.
OST-611, Low Voltage Fire Detection and Actuation System, Zones 1, 2, 3, 4, 5, 6, and 7. (Semi-Annual) Revision 5, Completed January 1,198 __ ______
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OST-613, Low Voltage Fire Detection and Actuation System, Zones 13, 14, and 15 (Semi-Annual) Revision 5, Completed December 3, 1986.
i OST-615, Low Voltage Fire Detection and Actuation System, Zones 20, 21,
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and 22 (Semi-Annual Internal) Revision 5, Completed October 29, 1986.
OST-616, Low Voltage Fire Detection and Actuation System, Zones 23, 27,
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and 28 (Semi-Annual Internal) Revision 3, Completed December 5, 1986.
OST-627, Actuation and Flow Test for Emergency Diesel Generators CO2
"Cardox" Suppression System (18 Month) Revision 5, Completed August 21, 1986.
OST-629, Pre-Action Sprinkler System and Dry Standpipe System Functional Test (18 Month) Revision 4, Completed December 3, 1986.
OMM-007, Equipment Inoperable Record, Attachment 6.4, Fire Protection Gaseous Suppression and Fire Barriers, Revision 10 (For period from January 9, 1987 to January 28,1987).
OMM-008, Minimum Equipment List, Attachment 6.5, Fire Zone Detection and Attachment 6.6, Fire Protection Systems, Revision 27 (For period from January 9,1987 to January 27,1987).
Based upon the results found, the licensee is expanding the scope of the inspections to include 1007 of the penetrations. Concurrently, the licensee will be providing a detailed report of their findings in a Information Only report to the NRC. This is identified as Inspector Followup Item 50-261/
87-01-01.
Inspector Followup Item 50-261/87-01-01; " Fire Barrier Penetrations."
No violations or deviations were identified within the areas inspected.
11.
ESF Systen Walkdown and Monthly Surveillance Observation (71710, 61726, 56700)
The inspectors verified the operability of an engineered safety features system by performing a walkd:wn of the accessible portions of the steam driven auxiliary feedwater system. 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 for debris, loose material, jumpers, 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 indications and determined that the auxiliary feed water flow comparitor and analog displays were operabl i.
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The inspectors also verified that the instrumentation associated with the SDAFW system was - properly calibrated, that pump turbine oil levels were within the prescribed tolerance, and that the SDAFW pump steam trap was functioning properly.
No violations or deviations were identified within the areas inspected.
12.
Cold Weather Preparations (71714)
The inspectors conducted a review of licensee cold weather preparations to ascertain that the licensee maintained effective implementation of the program of protective measures for extreme cold weather. During the inspec-tion, the inspectors verified that the licensee had inspected systems susceptible to freezing to verify the presence of heat tracing, strip heaters and insulation; the proper setting of thermostats; and that the heat tracing and strip heating circuits were energized.
On January 22, 1987, the inspectors witnessed the operability verification, performed by instrumentation 'and control technicians, of various freeze protection panels throughout the plant.
The inspectors observed channel current testing in the subject panels and, for those freeze protection channels which indicated a faulted condition, the inspectors determined that corrective maintenance work requests were initiated.
Subsequent to the completion of the cold weather preventative maintenance testing, the inspectors independently witnessed the return to service of the affected equipment.
No violations or deviations were identified within the areas inspected.
13. 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 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 implications. When licensee identified violations were noted, they were reviewed in accordance with enforcement policy. The inspectors had no further comments.
LER EVENT 86-012 (Rev. 1)
Reactor Trip on August 25, 1986 86-014 Reactor Trip on December 22, 1986 No violations or deviations were identified within the areas inspected.
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14. 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.
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 construc-tion activities; and communications interfaces.
On January 21, 1987, the inspectors attended the regularly scheduled refueling pre-outage meeting.
The inspectors ascertained that the licensee's outage management organization was aggressively pursuing pre-outage planning efforts including expediting required outage materials, manpower forecasts, radwaste and exposure reduction programs and identifica-tion of critical action items.
No violations or deviations were identified within the areas inspected.
15. 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 requirements. The inspectors (1) attended selected portions of the regular monthly PNSC meeting held on January 21, 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 l
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.
The inspection emphasized the review of the Emergency Plan, the Security Plan, outstanding action items, and review of specific design modifications scheduled for the upcoming refueling outage.
No violations or deviations were identified within the areas inspected.
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