IR 05000261/1985034
| ML14175B346 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 12/18/1985 |
| From: | Fredrickson P, Krug H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14175B345 | List: |
| References | |
| 50-261-85-34, NUDOCS 8512300146 | |
| Download: ML14175B346 (10) | |
Text
- pt REG&o UNITED STATES o
NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30323 Report No.:
50-261/85-34 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 Condu vember
-
December 10, 1985 Inspector: ug, Seni ident Inspector Approved by:
P. E. Fredrickson, Section Chief Dat Signed Division of Reactor Projects SUMMARY Scope: This routine, announced inspection involved 118 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, Systematic Assessment of Licensee Performance (SALP) and enforcement action followu Results: No violations or deviations were identified in the areas inspecte PDR ADOCK 05000261 PDR
REPORT DETAILS Licensee Employees Contacted R. Barnett, Maintenance Supervisor, Electrical G. Beatty, Manager, Robinson Nuclear Project Department J. Benjamin, Principal Engineer, Operations R. Chambers, Engineering Supervisor, Performance C. Crawford, Manager, Maintenance D. Crocker, Principal Health Physics Specialist J. Curley, Director, Regulatory Compliance R. Denney, Radiation Control Supervisor J. Eaddy, E&C Supervisor W. Flanagan, Manager, Design Engineering W. Gainey, Maintenance Supervisor, Mechanical G. Honma, Senior Specialist, Regulatory Compliance F. Lowery, Manager, Operations A. McCauley, Director (Acting), Onsite Nuclear Safety W. MacCready, Project Specialist, Radiation Control R. Morgan, Plant General Manager D. Nelson, Operating Supervisor M. Page, Engineering Supervisor, Plant Systems R. Powell, Principal Specialist, Maintenance B. Rieck, Manager, Control and Administration R. Smith, Manager, Environmental and Radiation Control J. Sturdavant, Technician, Regulatory Compliance R. Wallace, Manager, Technical Support C. Wright, Senior Specialist, Regulatory Compliance H. Young, Director, QA/QC Other NRC contributors:
D.P. Loveless 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 December 10, 1985, with the Plant General Manager. The licensee acknowledged the findings without exceptio No written material was provided to the licensee by the inspectors during this report perio The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspectio.
Licensee Action on Previous Enforcement Matters (92702) (Closed)
Violation 50-261/84-43-04:
Licensee craftsmen installed a base plate using incorrect and unauthorized method As corrective action, the licensee installed a required washer and re-torqued the rod head anchor wedge per manufacturers instruction Also, the licensee upgraded Construction Procedure WP-2 "Concrete Expansion Anchor Bolt Installation," thereby promulgating the proper installation method for base plates. This item is close (Closed) Violation 50-261/85-05-01:
The licensee's violation resulted from dye penetrant being left on stainless steel service water system piping contrary to ASME Boiler and Pressure Vessel Code Section V paragraph 6.9 and therefore, 10 CFR 50, Appendix B, Criteria The licensee's immediate action was to remove the penetrant from the piping. Subsequent action included counseling personnel performing dye penetrant inspections and those responsible for supervising the lagging of safety-related stainless steel pipin Also, the licensee determined that the penetrant used contains less than 1 percent chloride by weight per ASME Section 5, Article 6. This item is close c. (Closed)
Violation 50-261/85-05-02:
Certain licensed personnel had been exempted from taking the annual requalification examination contrary to the requirements of 10 CFR 55 Section 55.33 and Appendix A for the purpose of writing the examination. In response, the licensee stated that three of the four individuals have taken or will take the 1985 requalification examinatio (The fourth individual subsequently gave up his licensee.)
Additional action involved upgrading plant procedure TI-200 "Robinson Operator Requalification Program" to address the exemptions of licensed personnel from the exa This item is close.
Licensee Action on Previously Identified Inspection Items (92701) (Closed)
IFI 50-261/83-28-02:
Plant procedure TI-200 contained erroneous reference to the FSA This reference was updated in Revision 1 of TI-200, "Robinson Operator Requalification Program" to reflect the current FSAR rewrit Furthermore, the licensee moved all references to the front of the procedure in a separate section making it less likely that such an oversight be made in the futur This item is close (Closed)
IFI 50-261/84-43-02:
The concern was that several valves in containment appeared to be in need of maintenanc The inspector observed that not all safety-related and important to safety valves were incorporated into the licensee's preventative maintenance (PM)
program. The licensee review of this observation was documented in an internal licensee memo dated April 26, 198 The review stated that all valves were already covered by Auxiliary Operator shift tours of the plant and weekly area maintenance inspection This item is close (Closed)
IFI 50-261/84-43-03:
The inspector requested licensee documentation of design installation, and pipe hangers associated with a "field run" nitrogen line on top of the "C" Cold Leg Accumulato The documentation included a February 6, 1985 response from Ebasco including their stress calculations for each of the lines involved, licensee questions involving the review dated May 30, 1985 and the A.E.'s response to those question This documentation acceptably described the installatio This item is close (Closed) IFI 50-261/84-52-01: The inspectors previously noted that out of a relatively few valves inspected, three (SI-886E, AFW-43 and SW-562) had no identification tags. Recent inspections proved that all three currently had been fixed with identification tags. The licensee stated that missing or damaged tags are noted and replaced during system walkdowns by operations. The inspectors examined more than 100 valves and noted two (SI-864 A & B "RWST Discharge Valves') that had missing tags and one (PW-15 "Primary Water Pump "B" Isolation Valve")
that had its tag removed and lying below the valv It appears that these are isolated cases which would have been picked up by normal licensee practices. This item is therefore close (Closed)
IFI 50-261/84-52-03:
The inspector was concerned that the shift foreman was declaring portions of an Operations Surveillance Test (OST)
to be "Not Applicable" without appropriate authorizatio The licensee confirmed that the OST's were written with this kind of flexibility in mind and that administrative procedures govern this activit The inspector reviewed Operations Management Manual Procedure OMM-001 "Operations -
Conduct of Operations," and found the changes to be appropriate. Additionally, the inspector reviewed several completed OST's to insure proper procedure implementation. No problems were identified. This item is close f. (Closed) IFI 50-261/84-52-04: Non-Conformance Reports (NCRs) submitted by an individual could be cancelled by the individual's supervisor without appropriate reviews or documentatio The licensee now requires all NCRs to receive a number before being reviewe Additionally, all cancellations of an NCR must have a written justification for the cancellation signed by the Director of Quality Assurance. Cancelled NCRs are then logged and retained as if they had been issued. The inspectors reviewed several cancelled NCRs to insure implementation of this new procedure. This item is close (Closed)
IFI 50-261/85-05-03:
No written criteria were available to identify the selection process and the required training for the nuclear safety reviewer The licensee has since developed plant procedure PLP-032 "Nuclear Safety Reviewer Qualification Program" which addresses this are The inspectors also reviewed the licensee's Nuclear Safety Reviewer Training Course and course attendance sheets and found them to be acceptable. This item is close.
Plant Tour (71707, 62703, 71710)
The inspector 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 inspector 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 date Areas emphasized included the Control Building, Turbine Building, Auxiliary Building and the Spent Fuel Pi Some tours were conducted on backshift Plant housekeeping and contamination control was observed to be outstandin The inspector performed valve lineup verifications and system status checks on the following systems:
a. Station Vital Batteries b. Electrical Switchgear Emergency Diesel Generators The inspector observed three valves that were missing identification tag After identifying this to the operations staff, the missing tags were replaced withir 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The inspector observed that one valve (CVC-295)
had wet Boric Acid deposits on the stem. This valve was immediately placed on a Work Request when the licensee was notifie Within the areas inspected, no violations or deviations were identifie.
Plant Operations Review (71707, 62703, 61726, 61707, 61711)
Periodically during the inspection interval, the inspector 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 inspector routinely observed operator alertness and demeanor during plant tours. The inspector conducted random off-hours inspections during the reporting interval to assure that operations and security remained at an acceptable leve During this reporting interval, the inspector 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 The licensee informed the inspectors that a shipment of radioactive waste (concrete) from the plant had arrived at Barnwell on November 14, 1985 where a state inspector found a 1/8" hole in the bottom of the containe The licensee, who faced a potential state violation, claim the hole was not there when it left the site. The licensee inspected the shipment and found no contamination on the outside of the container or on the truck. The State is evaluating the need for enforcemen A Region II health physics inspector will followup on this matte The inspector periodically verified the reactor shutdown margi The inspector also periodically observed the reactor axial flux difference and compared the observed valves with those required by the T Within the areas inspected, no violations or deviations were identifie.
Physical Protection (71707)
The inspector verified by observation, perimeter walkdowns and interviews that measures taken to assure the physical protection of the facility met current requirement Areas inspected included the organization of the security force, the establishment and maintenance of gates, doors and isolation zones in the proper condition, that access control and badging were proper, that search practices were appropriate, and that escorting and communications procedLres were followed. The inspector continued to monitor tne progress and activities of the Security Task Force with respect to the HBR Security System Upgrade Projec Within the areas inspected, no violations or deviations were identifie. Monthly Surveillance Observation (61726)
The inspector observed portions of surveillance activities on the safety injection system and components to ascertain that these activities were conducted in accordance with license requirements. The inspector determined that the surveillance test procedure conformed to Technical Specifications (TS) requirements, that Limiting Conditions for Operations (LCO's) were met and that the surveillance test was completed at the required frequency. The inspector also verified that the required administrative approvals and tagouts were obtained prior to initiating the test, that the testing was accomplished by qualified personnel in accordance with an approved test procedure and that the required test instrumentation was properly calibrated. Upon completion of the testing, the inspector observed that the-recorded test data was accurate, complete and met TS requirements; verified that test discrepancies were properly rectifie Within the areas inspected, no violations or deviations were identifie. Monthly Maintenance Observation (62703)
The inspector observed portions of maintenance 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 inspector determined that these activities were not violating LCO's and that redundant components were operable. The inspector 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 administrative 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 certifie The inspector verified that these activities were accomplished by qualified personnel using approved procedures. Additionally, the inspector reviewed several outstanding job orders to determine that the licensee was giving priority to safety-related maintenance and a backlog, which might affect its performance, was not developing on a given syste Specifically, the inspector observed preventative maintenance in progress on the "A" Emergency Diesel Generator Starting Air Compressor. The compressor was properly taken out of service, and tagged out with its breaker open by operations personnel before work commenced. All activities observed were either done by procedure or were within the "skill of the trade".
The inspector reviewed the procedure for checking and replacing the compressor belt drives and found it to be adequate to control the activit Upon completion of the maintenance, the compressor was properly tested and turned over to operation The inspector observed portions of the conduct of MST-015 "Turbine First Stage Pressure Protection Channel Testing". The inspector observed that the technicians were following the pro'cedure which included verifying that redundant components were operable and that administrative approvals were obtained before initiating the wor Further observation showed that the equipment was properly returned to service and independent verification was obtaine The inspector noted that when the technicians received a signal they had not anticipated, they properly ceased work and pulled out the design drawings to insure the proper function of the instrument The inspector reviewed the documentation involving the above maintenance activities and found that all individuals were properly trained, that parts and materials were properly certified and that radiological procedures were being appropriately implemented. The inspector also noted that throughout all maintenance activities cleanliness was maintaine Within the areas inspected, no violations or deviations were identifie.
ESF System Walkdown and Monthly Surveillance Observation (71710, 61726, 56700)
The inspector verified the operability of an engineered safety features system by performing a walkdown of the accessible portions of the "A" diesel generator starting air syste The inspector confirmed that the licensee's system lineup procedures matched plant drawings and the as-built configuration. The inspector looked for equipment conditions and items that might degrade performance (hangers and supports were operable, housekeeping, etc.). The inspector verified that valves were in proper position, power was available, and valves were locked as appropriat Within the areas inspected, no violations or deviations were identifie.
Organization and Administration (36700)
The inspector reviewed portions of the on-site licensee organization to ascertain whether changes made to the licensee's onsite organization are in conformance with the requirements of the TS by verifying that (1) the established organization is functioning as described in the TS, (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 inspector also ascertained 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 procedures. Licensee procedures now require all items to be closed out by the plant in writing. This is a significant improvement over the previous syste 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; ongoing construction activities; and communications interfaces. Topics emphasized included the security system upgrade, health physics, and reactor trip reduction progra Within the areas inspected, no violations or deviations were identifie.
Onsite Review Committee (40700)
The inspector 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 inspector followed up on previously identified PNSC activities to independently confirm that corrective actions were progressing satisfac torily. The inspection emphasized dosimetry and the reactor trip reduction progra Within.the areas inspected, no violations or deviations were identifie.
Plant Procedures (42700)
The inspector reviewed portions of the established procedure program to ascertain whether overall plant procedures were in accordance with regulatory requirements, temporary procedures and procedure changes were made in accordance with TS requirements, and the technical adequacy of the reviewed procedures was consistent with desired actions and modes of operation. Procedures examined included general plant operating procedures, startup, operation and shutdown of safety-related system procedures, maintenance procedures and administrative procedure Within the areas inspected, no violations or deviations were identifie.
Surveillance Procedures and Records (61700)
The inspector reviewed sections of the established licensee surveillance progra Inspection criteria included whether the surveillance of safety-related systems and components is being conducted in accordance with approved procedures as required by the TS, inservice inspection (ISI)
and inservice testing programs for pumps and valves, and NRR-approved fire protection/prevention progra The inspector also examined the technical content of procedures associated with the cold leg accumulators to verify that testing of related systems or components ensures compliance with the requirements specified in the TS or ISI program, and is consistent with the appropriate sections of the Updated Final Safety Analysis Repor Within the areas inspected, no violations or deviations were identifie.
Maintenance Procedures (62700)
The inspector reviewed portions of the established program controlling maintenance procedures on the "A" Emergency Diesel Generator Starting Air Compressor to ascertain whether maintenance activities on safety-related systems -and components were conducted in accordance with approved procedures, regulatory guides, and industry codes or standards and in conformance with TS requirements. The inspector examined both corrective and preventive maintenance procedures to verify that the content was technically adequat Within the areas inspected, no violations or deviations were identifie.
Preparation for Refueling (60705)
A refueling outage is scheduled to commence on February 1, 198 The inspector continued to review licensee preparations for refueling including the adequacy of procedures and administrative controls for the upcoming refueling activities/outag As part of this activity, the inspector verified that technically adequate, approved procedures were available covering (1) the inspection and storage of new fuel, (2) fuel handling,
9 transfers and core verification, (3) the inspection of fuel to be reused, and (4) the handling and inspection of any other core internal Within the areas inspected, no violations or deviations were identified.