IR 05000400/2006004
| ML063040003 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 10/30/2006 |
| From: | Binoy Desai NRC/RGN-II/DRP/RPB4 |
| To: | Gannon C Carolina Power & Light Co |
| References | |
| IR-06-004 | |
| Download: ML063040003 (17) | |
Text
October 30, 2006Carolina Power and Light CompanyATTN:Mr. C. J. Gannon, Jr.Vice President - Harris PlantShearon Harris Nuclear Power Plant P. O. Box 165, Mail Code: Zone 1 New Hill, North Carolina 27562-0165SUBJECT:SHEARON HARRIS NUCLEAR POWER PLANT - NRC INTEGRATEDINSPECTION REPORT 05000400/2006004
Dear Mr. Gannon:
On September 30, 2006 the US Nuclear Regulatory Commission (NRC) completed aninspection at your Shearon Harris reactor facility. The enclosed integrated inspection reportdocuments the inspection findings, which were discussed on October 18, 2006 with Mr.
McCartney and other members of your staff.The inspection examined activities conducted under your license as they relate to safety andcompliance with the Commission's rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, no findings of significance were identified.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and itsenclosure will be available electronically for public inspection in the NRC Public DocumentRoom or from the Publicly Available Records (PARS) components of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
\RA\Binoy B. Desai, Acting ChiefReactor Projects Branch 4 Division of Reactor ProjectsDocket No.:50-400License No.:NPF-63
Enclosure:
NRC Inspection Report 05000400/2006004 w/Attachment: Supplemental Information
ML063040003OFFICERII:DRPRII:DRPRII:DRPSIGNATURESONRXM1PBONAMESNinh:rcmRMusserPO'BryanDATE10/24/200610/30/200610/24/200611/ /200611/ /200611/ /200611/ /2006 E-MAIL COPY? YESNO YESNO YESNO YESNO YESNO YESNO YESNO
REGION IIDocket No:50-400License No:NPF-63 Report No:05000400/2006004 Licensee:Carolina Power and Light Company Facility:Shearon Harris Nuclear Power Plant, Unit 1 Location:5413 Shearon Harris RoadNew Hill, NC 27562Dates:July 1, 2006 through September 30, 2006Inspectors:R. Musser, Senior Resident InspectorP. O'Bryan, Resident InspectorApproved by:Binoy B. Desai, Acting ChiefReactor Projects Branch 4 Division of Reactor Projects 2Enclosure
SUMMARY OF FINDINGS
IR 05000400/2006-004, 07/01/2006 - 09/30/2006;
Shearon Harris Nuclear Power Plant, Unit 1;Routine Integrated Report.The report covered a three-month period of inspection by resident inspectors. The NRC'sprogram for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 3, dated July 2000.A. Inspector-Identified and Self-Revealing Findings None.
B. Licensee-Identified Violations
None.
Enclosure
REPORT DETAILS
Summary of Plant Status The unit began the inspection period at full rated thermal power. On September 19, 2006, withthe unit at 100% power, the unit automatically tripped due to a failed relay in the main generator lockout circuitry. The unit was restarted on September 21, 2006 and operated at rated power for the remainder of the inspection period.1.
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity1R01Adverse Weather Protection
a. Inspection Scope
When Tropical Storm Ernesto was approaching the site on August 31, the inspectorsreviewed actions taken by the licensee in accordance with Procedure AP-300, "SevereWeather Response," prior to the onset of that weather
, to ensure that the adverseweather conditions would neither initiate a plant event nor prevent any system, structure, or component from performing its design function.
b. Findings
No findings of significance were identified.
1R04 Equipment Alignment
a. Inspection Scope
Partial System Walkdowns:The inspectors performed the following three partial system walkdowns, while theindicated structures, systems and components (SSCs) were out-of-service (OOS) for maintenance and testing:*B motor driven auxiliary feed water pump and the turbine driven auxiliaryfeedwater pump with the A motor driven feedwater pump out-of-service on July 19, 2006*B emergency diesel generator with the A emergency diesel generator out-of-service on September 13, 2006*The boration flow path from the refueling water storage tank with the borationflow path from the reactor make-up water system out-of-service on September 26, 2006To evaluate the operability of the selected trains or systems under these conditions, theinspectors reviewed valve and power alignments by comparing observed positions of 4Enclosurevalves, switches, and electrical power breakers to the procedures and drawings listed inthe Attachment.Complete System Walkdown:The inspectors conducted a detailed review of the alignment and condition of theemergency diesel generator system. To determine the proper system alignment, the inspectors reviewed the procedures, drawings, and Final Safety Analysis Report (FSAR)sections listed in the Attachment. The inspectors walked down the system to verify that the existing alignment of thesystem was consistent with the correct alignment. Items reviewed during the walkdown included the following:*Valves are correctly positioned and do not exhibit leakage that wouldimpact the function(s) of any given valve*Electrical power is available as required
- Major system components are correctly labeled, lubricated, cooled,ventilated, etc.*Hangers and supports are correctly installed and functional
- Essential support systems are operational
- Ancillary equipment or debris does not interfere with system performance
- Tagging clearances are appropriate
- Valves are locked as required by the licensee's locked valve programThe inspectors reviewed the documents listed in the Attachment to verify that the abilityof the system to perform its function could not be affected by outstanding design issues, temporary modifications, operator workarounds, adverse conditions, and other system-related issues tracked by the Engineering Department.The inspectors reviewed the following ARs associated with this area to verify that thelicensee identified and implemented appropriate corrective actions:*200980, "High Differential Pressure Across A EDG Fuel Oil Filter"*197690, "EDG Unavailability"
b. Findings
No findings of significance were identified.
1R05 Fire Protection
a. Inspection Scope
For the twelve areas identified below , the inspectors reviewed the licensee's control oftransient combustible material and ignition sources, fire detection and suppression capabilities, fire barriers, and any related compensatory measures, to verify that those 5Enclosureitems were consistent with FSAR Section 9.5.1, Fire Protection System, and FSARAppendix 9.5.A, Fire Hazards
Analysis.
The inspectors walked down accessibleportions of each area and reviewed results from related surveillance tests, to verify that conditions in these areas were consistent with descriptions of the applicable FSAR sections. Documents reviewed are listed in the Attachment. *190' level of the reactor auxiliary building including areas 1-A-1-PA and 1-A-1-PB(2 areas) *Process instrument control cabinet room, area 12-A-6-PICR1 (1 area)
- Main control room, area 12-A-CR (1 area)
- 261' level of the reactor auxiliary building including areas 1-A-4-CHFA, 1-A-4-CHFB, 1-A-EPA, and 1-A-EPB (4 areas)*236' level of the reactor auxiliary building including areas 1-A-3-COMC, 1-A-3-COMB, and 1-A-3-COMI (3 areas)*236' level of the reactor auxiliary building including areas 1-A-3-PB (1 area)
b. Findings
No findings of significance were identified.
1R11 Licensed Operator Requalification
a. Inspection Scope
On August 22, the inspectors observed licensed-operator performance duringrequalification simulator training to verify that operator performance was consistent with expected operator performance as described in Exercise Guide DSS-047. This training tested the operators' ability to mitigate a stuck open PORV and a ruptured steam generator. The inspectors focused on clarity and formality of communication, the use of procedures, alarm response, control board manipulations, group dynamics and supervisory oversight. The inspectors reviewed AR 204301204301 "Inconsistent EAL Classification During LOCTExam" to verify that the licensee identified and implemented appropriate corrective actions.
b. Findings
No findings of significance were identified.
1R12 Maintenance Effectiveness
a. Inspection Scope
The inspectors reviewed three degraded SSC/function performance problems orconditions listed below to verify the licensee's handling of these performance problems 6Enclosureor conditions in accordance with 10CFR50, Appendix B, Criterion XVI, Corrective Action,and 10CFR50.65, Maintenance Rule. Documents reviewed are listed in the Attachment.*Unavailability of the emergency diesel generators*High vibrations on the B boric acid transfer pump
- Radiation monitor functional failuresThe inspectors focused on the following attributes:
- Appropriate work practices*Identifying and addressing common cause failures
- Scoping in accordance with 10 CFR 50.65(b)
- Characterizing reliability issues (performance)
- Charging unavailability (performance)
- Trending key parameters (condition monitoring)
- 10 CFR 50.65(a)(1) or (a)(2) classification and reclassification
- Appropriateness of performance criteria for SSCs/functions classified (a)(2)and/or appropriateness and adequacy of goals and corrective actions for SSCs/functions classified (a)(1)The inspectors reviewed the following ARs associated with this area to verify that the licensee identified and implemented appropriate corrective actions:*209980, "EDG Unavailability"*159131, "EDG Relay Failures"
- 174210, "Faulty EDG Shuttle Valve"
- 201947, "B Boric Acid Transfer Pump Vibrations"
- 190624, "Radiation Monitor Maintenance Rule Reclassifications"
- 156321, "System Performance Trending"
- 150443, "Emerging Trend: Radiation Monitor Failures"
- 158622, "Plant Vent Stack Radiation Monitor Inoperable"
b. Findings
No findings of significance were identified.
1R13 Maintenance Risk Assessments and Emergent Work Evaluation
a. Inspection Scope
The inspectors reviewed the licensee's risk assessments and the risk managementactions for the plant configurations associated with the three activities listed below. The inspectors verified that the licensee performed adequate risk assessments, and implemented appropriate risk management actions when requred by 10 CFR 50.65(a)(4). For emergenent work, the inspectors also verified that any increase in risk was promptly assessed, and that the appropriate risk management actions were promptly implemented.
7Enclosure*Planned maintenance on the A auxiliary feedwater pump and the grid in asystem reliability alert on July 19, 2006*Surveillance testing on the B EDG and the grid in a system reliability alert onAugust 2, 2006*Emergent corrective maintenance on the reactor make-up system on September13, 2006
b. Findings
No findings of significance were identified.
1R15 Operability Evaluations
a. Inspection Scope
The inspectors reviewed two operability determinations addressed in the ARs listed below. The inspectors assessed the accuracy of the evaluations, the use and control ofany necessary compensatory measures, and compliance with the TS
. The inspectorsverified that the operability determinations were made as specified by Procedure OPS-NGGC-1305, "Operability Determinations." The inspectors compared the justifications made in the determination to the requirements from the TS, the FSAR, and associated design-basis documents, to verify that operability was properly justified and the subject component or system remained available, such that no unrecognized increase in risk occurred:*193706, TDAFW limit switch does not agree with design*196382, 'A' essential services chiller compressor surging
b. Findings
No findings of significance were identified.
1R19 Post Maintenance Testing
a. Inspection Scope
For the four post-maintenance tests listed below, the inspectors witnessed the testand/or reviewed the test data, to verify that test results adequately demonstratedrestoration of the affected safety function(s) described in the FSAR and TS. The tests included the following:*OST-1211, Auxiliary Feedwater Pump 1A-SA Operability Test Quarterly IntervalModes 1-4, following maintenance on the 1A motor driven auxiliary feedwater pump on July 19, 2006*OP-112, Containment Spray System, following maintenance on the 1Acontainment spray pump on August 21, 2006 8Enclosure*OP-139, Service Water System, following maintenance on the A emergencyservice water booster pump on September 14, 2006*OST-1093, CVCS/SI System Operability Train B Quarterly Interval Modes 1-4after maintenance on the B boric acid transfer pump on September 25, 2006 The inspectors reviewed AR 201947201947 "B Boric Acid Transfer Pump Vibrations", to verifythat the licensee identified and implemented appropriate corrective actions:
b. Findings
No findings of significance were identified.
1R22 Surveillance Testing
a. Inspection Scope
For the two surveillance tests identified below, the inspectors witnessed testing and/orreviewed test data, to verify that the systems, structures, and components involved in these tests satisfied the requirements described in the TS and the FSAR, and that the tests demonstrated that the SSCs were capable of performing their intended safety functions.*OST-1411, Auxiliary Feedwater Pump 1X-SAB Operability Test Quarterly IntervalMode 1, 2, 3**OST-1076, Auxiliary Feedwater Pump 1B-SB Operability Test Quarterly IntervalModes 1-4 *This procedure included inservice testing requirements.
b. Findings
No findings of significance were identified.Cornerstone: Emergency Preparedness1EP6Drill Evaluation
a. Inspection Scope
The inspectors observed an emergency preparedness drill conducted on July 25, 2006,to verify licensee self-assessment of classification, notification, and protective action recommendation development in accordance with 10CFR50, Appendix E.
b. Findings
No findings of significance were identified.
9Enclosure4.OTHER ACTIVITIES4OA2Identification and Resolution of Problems Routine Review of ARs To aid in the identification of repetitive equipment failures or specific humanperfromance issues for followup, the inspectors performed frequent screenings of items entered into the corrective action program. The review was accomplished by reviewing daily AR reports.4OA3Event Follow-upTurbine Trip/Reactor Trip - September 19, 2006
a. Inspection Scope
The inspectors responded to an turbine trip and reactor trip that occurred on September19, 2006. The inspectors discussed the trip with operations, engineering, maintenance, and licensee management personnel to gain an understanding of the event and assess followup actions. The inspectors reviewed operator actions taken in accordance with licensee procedures and reviewed unit and system indications to verify that actions and system responses were as expected. The inspectors assessed the licensee's actions to gather, review, and assess information leading up to and following the trip. The inspectors later reviewed the initial investigation report and cause determination to assess the detail of review and adequacy of the cause determination and proposed corrective actions prior to restart.The licensee's investigation identified the cause of the turbine trip was a main generatorlockout signal that was generated by a failed relay in the generator protective circuitry.
At the end of the inspection period, the licensee was investigating the root cause of the relay failure. The inspectors also reviewed the initial notification to verify that it met the requirements specified in NUREG-1022, Event Reporting Guidelines.
b. Findings
No findings of significance were identified. 40A5OtherWorld Association of Nuclear Operators (WANO) Peer Review Report
a. Inspection Scope
The inspectors and branch chief reviewed the final report for the WANO peer review ofthe Shearon Harris Nuclear Power Plant conducted in January, 2006. The report was reviewed to ensure that issues identified were consistent with the NRC perspectives of 10Enclosurelicensee performance and to determine if any significant safety issues were identifiedthat required further NRC follow-up.4OA6Meetings, Including ExitOn October 18, 2006, the resident inspectors presented the inspection results to Mr. McCartney and other members of his staff. The inspectors confirmed that proprietary information was not provided or examined during the inspection.ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
- D. Alexander, Superintendent, Environmental and Chemistry
- A. Barginere, Superintendent, Security
- D. Corlett, Supervisor - Licensing/Regulatory Programs
- R. Duncan, Director - Site Operations
- P. Fulford, Manger, Nuclear Assessment
- C. Gannon, Vice President Harris Plant
- W. Gurganious, Training Manager
- K. Henderson, Maintenance Manager
- C. Kamiliaris, Manager - Support Services
- E. McCartney, Plant General Manager
- T. Natale, Manager - Outage and Scheduling
- S. O'Connor, Manager - Engineering
- T. Pilo, Supervisor - Emergency Preparedness
- G. Simmons, Superintendent - Radiation Control
- E. Wills, Operations Manager
NRC personnel
Binoy
- B. Desai, Acting Chief, Reactor Projects Branch 4
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened None
Closed
None
Discussed
None
LIST OF DOCUMENTS REVIEWED
Section 1R04: Equipment AlignmentPartial System WalkdownAuxiliary Feedwater System*Procedure
- OP-137, Auxiliary Feedwater System*Drawing 2165-S-0544, "Simplified Flow Diagram Feedwater System Unit 1Emergency Diesel Generator System*Procedure
- OP-155, Diesel Generator Emergency Power System*Drawing 2165-S-0633, sheets 1 through 4, Simplified Flow Diagram EmergencyDiesel Generator SystemsBoration flow path from the refueling water storage tank*Drawing 2165-S-1305, Chemical and Volume Control System