IR 05000286/2006004
| ML063110369 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 11/07/2006 |
| From: | Cobey E Reactor Projects Branch 2 |
| To: | Dacimo F Entergy Nuclear Operations |
| References | |
| FOIA/PA-2007-0080 IR-06-004 | |
| Download: ML063110369 (29) | |
Text
ber 7, 2006
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT 3 - NRC INTEGRATED INSPECTION REPORT 05000286/2006004
Dear Mr. Dacimo:
On September 30, 2006, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Indian Point Nuclear Generating Unit 3. The enclosed integrated inspection report documents the inspection results, which were discussed on October 4, 2006, with Mr. Paul Rubin and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions 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, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs 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/
Eugene W. Cobey, Chief Reactor Projects Branch 2 Division of Reactor Projects Docket No. 50-286 License No. DPR-64 Enclosure: Inspection Report No. 05000286/2006004 w/Attachment: Supplemental Information
SUMMARY OF FINDINGS
IR 05000286/2006-004; 07/01/2006 - 09/30/2006, Indian Point Nuclear Generating Unit 3;
Routine Integrated Inspection report.
The report covered a 3-month period of inspection by resident inspectors, and region based specialist inspectors. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 3, dated July 2000.
NRC Identified and Self-Revealing Findings
No Findings of Significance Were Identified
Licensee-Identified Violations
None.
ii
REPORT DETAILS
Summary of Plant Status
Indian Point Nuclear Generating Unit 3 began the inspection period at full power. On July 6, 2006, an automatic reactor trip occurred due to a turbine trip for a generator protection relay fault. On July 7, 2006, Unit 3 returned to operation. On July 21, 2006, Unit 3 was manually tripped as a precaution when arcing was observed near the main generator. On July 22, Unit 3 returned to operation and remained at or near full power for the duration of the inspection period.
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R01 Adverse Weather Protection
a. Inspection Scope
For the onset of extreme hot weather, the inspectors reviewed the readiness for extreme weather conditions of risk significant systems. The inspectors reviewed Entergys adverse weather procedures, operating experience, corrective action program, Updated Final Safety Analysis Report (UFSAR), Technical Specifications (TS), operating procedures, staffing, and applicable plant documents to determine the types of adverse weather challenges to which the site is susceptible.
Additionally, the inspectors evaluated implementation of the adverse weather preparation procedures and compensatory measures for the affected conditions before the onset of and during adverse weather conditions. The inspectors performed plant walkdowns and reviews to verify that plant features and procedures for operation and continued availability of the ultimate heat sink during adverse weather were appropriate including equipment availability for performance of the reactor shutdown function under the weather conditions assumed prior to the shutdown. The documents reviewed are listed in the Attachment. The following three risk-significant systems that were required to be protected from adverse weather conditions were selected and collectively they represent one inspection sample of risk significant systems:
- 480V switchgear room;
- safety injection and residual heat removal pumps.
b. Findings
No findings of significance were identified.
1R04 Equipment Alignment
.1 Partial Walkdown
a. Inspection Scope
The inspectors performed four partial system walkdowns to verify the operability of redundant or diverse trains and components during periods of system train unavailability or following periods of maintenance. The inspectors referenced the system procedures, the UFSAR and system drawings in order to verify that the alignment of the available train was proper to support its required safety functions. The inspectors also reviewed applicable condition reports and work orders to ensure that Entergy had identified and properly addressed equipment discrepancies that could potentially impair the capability of the available train. The documents reviewed are listed in the Attachment. The inspectors performed a partial walkdown of the following systems which represents four samples:
- 31 emergency diesel generator (EDG) system following maintenance activities;
- charging, seal water and letdown control following maintenance activities;
- 480V electrical distribution alignment following reactor startup; and
- fire water pumps and storage tank alignment following maintenance activities.
b. Findings
No findings of significance were identified.
.2 Complete Walkdown
a. Inspection Scope
The inspectors performed a complete walkdown of the safety injection system to identify any discrepancies between the existing equipment lineup and the required lineup. The inspectors reviewed operating procedures, surveillance test results, piping and instrumentation drawings, equipment lineup check-off lists, and the UFSAR to determine if the system was aligned to perform its safety functions. The inspectors reviewed a sample of condition reports and work orders written for deficiencies associated with the safety injection system to ensure that they had been evaluated and resolved. The documents reviewed are listed in the Attachment. The walkdown of the safety injection system represents one sample.
b. Findings
No findings of significance were identified.
1R05 Fire Protection
.1 Fire Protection - Tours
a. Inspection Scope
The inspectors conducted tours of the ten areas listed below to assess the material condition and operational status of fire protection features. The inspectors verified that combustibles and ignition sources were controlled in accordance with the Entergys administrative procedures; fire detection and suppression equipment was available for use; that passive fire barriers were maintained; and that compensatory measures for out-of-service, degraded, or inoperable fire protection equipment were implemented in accordance with Entergys fire plan. The inspectors used procedure ENN-DC-161, Transient Combustible Program, in performing the inspection. The inspectors evaluated the fire protection program against the requirements of license condition 2.H.
The documents reviewed are listed in the attachment. This inspection satisfied ten inspection samples for fire protection tours.
The areas inspected included:
- Fire Zones 10, 36A, 101A, and 102A;
- Fire Zones 9, 4A, and 6A;
- Fire Zones 5A, 61A, 62A, and 68A;
- Fire Zone 23;
- Fire Zone 14;
- Fire Zone 3 and 4;
- Fire Zone 52A and 57A;
- Fire Zone 90A and 91A;
- Fire Zone 22; and
- Fire Zone 70A and 71A.
b. Findings
No findings of significance were identified.
1R06 Flood Protection Measures
a. Inspection Scope
The inspectors reviewed Indian Points Individual Plant Examination of External Events and the UFSAR concerning external flooding events. The inspection included a walkdown of accessible areas of the plant to look for potential susceptibilities to external flooding and to verify the assumptions included in the sites external flooding analysis.
The inspectors also reviewed relevant abnormal operating and emergency plan procedures. The documents reviewed are listed in the Attachment. This inspection represented one sample.
b. Findings
No findings of significance were identified.
1R11 Licensed Operator Requalification Inspection
a. Inspection Scope
On September 5, and September 20, 2006, the inspectors observed licensed operator simulator and table top training to assess operator performance during several scenarios to verify that operator performance was adequate and evaluators were identifying and documenting crew performance problems. The inspectors evaluated the performance of risk significant operator actions, including the use of emergency operating procedures. The inspectors assessed the clarity and effectiveness of communications, the implementation of appropriate actions in response to alarms, the performance of timely control board operation and manipulation, and the oversight and direction provided by the shift manager. The inspector also reviewed simulator fidelity to evaluate the degree of similarity to the actual control room. Licensed operator training was evaluated against the requirements of 10 CFR 55, Operators Licenses. The documents reviewed are listed in the Attachment. This observation of operator simulator training and table top exercises constituted one inspection program sample.
b. Findings
No findings of significance were identified.
1R12 Maintenance Effectiveness
a. Inspection Scope
The inspectors reviewed performance-based problems involving selected in-scope structures, systems, or components (SSCs) to assess the effectiveness of the maintenance program. Reviews focused on:
- Proper maintenance rule scoping in accordance with 10 CFR 50.65;
- Characterization of reliability issues;
- Changing system and component unavailability;
- 10 CFR 50.65 (a)(1) and (a)(2) classifications;
- Identifying and addressing common cause failures;
- Trending of system flow and temperature values;
- Appropriateness of performance criteria for SSCs classified (a)(2); and
- Adequacy of goals and corrective actions for SSCs classified (a)(1).
The inspectors reviewed system health reports, maintenance backlogs, and Maintenance Rule basis documents. The inspectors evaluated the maintenance program against the requirements of 10 CFR 50.65. The documents reviewed are listed in the Attachment.
The following three maintenance rule samples were reviewed:
- Primary auxiliary building ventilation;
- Power range nuclear instrumentation; and
- Safety injection system.
b. Findings
No findings of significance were identified.
1R13 Maintenance Risk Assessment and Emergent Work Control
a. Inspection Scope
The inspectors reviewed the following six activities to verify that the appropriate risk assessments were performed prior to removing equipment from service for planned work. The inspectors verified that risk assessments were performed as required by 10 CFR 50.65(a)(4), and were accurate and complete. When emergent work was performed, the inspectors verified that the plant risk was promptly reassessed and managed. The documents reviewed are listed in the Attachment. The following three emergent activities and three planned activities were observed and treated as six inspection samples:
- Work Order (WO) IP3-06-00769, exciter breaker trip circuit;
- WO IP3-06-00281, replacement of Appendix R battery cells;
- WO IP3-06-18483, 32 auxiliary boiler feed pump 3PT-Q120B surveillance testing during severe thunderstorms;
- WO IP3-05-23556, 33 EDG air compressor maintenance with the Appendix R diesel generator out-of-service and steam flow/feedwater flow mismatch testing in progress;
- WO IP3-06-19282, 31 EDG jacket water heater ground troubleshooting; and
- WO IP3-0617646, remove scaffold to remover/reinstall the main generator links to support hi-pot of main generator phases.
b. Findings
No findings of significance were identified.
1R15 Operability Evaluations
a. Inspection Scope
The inspectors reviewed operability determinations to assess the acceptability of the evaluations; when needed, the use and control of compensatory measures; and the compliance with Technical Specifications. The inspectors review included a verification that the operability determinations were made as specified by ENN-OP-104, "Operability Determinations." The technical adequacy of the determinations was reviewed and compared to the Technical Specifications, UFSAR, and associated design basis documents. The documents reviewed are listed in the Attachment. The following five evaluations were reviewed and each constituted inspection program samples:
- Condition Report (CR) IP3-2006-02581, blown fuses for 33 EDG auxiliaries;
- CR IP3-2006-02071, turbine trip due to generator protection differential relay;
- CR IP3-2006-02255, 31 reactor coolant pump trip during reactor trip;
- CR IP3-2006-02080, 33/34 steam generator auxiliary feed flow differences; and
- CR IP3-2006-02078, reactor trip breaker time response.
b. Findings
No findings of significance were identified.
1R17 Permanent Plant Modifications
a. Inspection Scope
The inspectors reviewed modification documents and monitored the installation and testing of modifications to the Indian Point 3 emergency diesel generator air start and ventilation systems in accordance with modification ER-04-3-003. The modifications changed piping material to stainless steel to eliminate the potential for corrosion and reconfigured the location of the strainer upstream of valves and indicators to improve effectiveness. Additionally, the reconfiguring of drain lines for the EDG ventilation system air receiver tanks improves operator access and safety. The modification was completed under work order IP3-02-19116. The post-modification testing included satisfactory completion of 3-PT-M79, EDG Functional Test, as well as functional and leakage tests on affected components.
b. Findings
No findings of significance were identified.
1R19 Post-Maintenance Testing
a. Inspection Scope
The inspectors reviewed post maintenance test procedures and associated testing activities for selected risk significant mitigating systems to assess whether the effect of maintenance on plant systems was adequately addressed by control room and engineering personnel. The inspectors verified that test acceptance criteria were clear, demonstrated operational readiness and were consistent with design basis documentation; that test instrumentation had current calibrations and the range and accuracy for the application; and that tests were performed, as written, with applicable prerequisites satisfied. Upon completion, the inspectors verified that equipment was returned to the proper alignment necessary to perform its safety function. Post maintenance testing was evaluated against the requirements of 10 CFR 50, Appendix B Criterion XI, Test Control. The documents reviewed are listed in the Attachment. The following post-maintenance test activities were reviewed and represent seven inspection program samples:
- WO IP3-05-19466, post work test (PWT) for a preventative maintenance inspection and a rotating element change-out of 32 Boric Acid Transfer Pump;
- WO IP3-06-15384, PWT for Appendix R battery replacement;
- WO IP3-05-01275, PWT for TM-441D rod limit switch;
- WO IP3-06-20108, PWT for 33 safety injection pump inboard seal leak repair;
- WO IP3-05-21105, PWT for 33 EDG inspection;
- WO IP3-05-22199, PWT for 33 charging pump breaker replacement; and
- WO IP3-06-19282, PWT for 31 EDG following jacket water heater and lube oil heater maintenance.
b. Findings
No findings of significance were identified.
1R22 Surveillance Testing
a. Inspection Scope
The inspectors witnessed performance of surveillance tests and/or reviewed test data of selected risk-significant SSCs to assess whether the SSCs satisfied Technical Specifications, UFSAR, Technical Requirements Manual, and Entergy procedure requirements. The inspectors verified that test acceptance criteria were clear, demonstrated operational readiness and were consistent with design basis documentation; that test instrumentation had current calibrations and the range and accuracy for the application; and that tests were performed, as written, with applicable prerequisites satisfied. Upon surveillance test completion, the inspectors verified that equipment was returned to the status specified to perform its safety function. The inspectors evaluated the surveillance tests against the requirements in Technical Specifications. The following surveillance tests were reviewed and represented six inspection program samples (one RCS leak detection sample, one in-service test (IST)samples and four surveillance test samples):
- 3-PT-Q117A, Revision 3, 31 Containment Spray Pump Functional Test;
- 3-PT-M042B, Revision 3, Diesel Fire Pump Test;
- 3-PT-M13B1, Revision 12, Reactor Protection Logic Functional Test;
- 3-PT-M62A, Revision 35, 480V Degraded Grid/UV Test;
- 3-PC-OL39B, Revision 1, Recirculation Sump Level Channel Calibration; and
- 3-PT-M79C, Revision 35, 33 Emergency Diesel Functional Test.
b. Findings
No findings of significance were identified.
Cornerstone: Emergency Preparedness
1EP5 Correction of Emergency Preparedness Weaknesses and Deficiencies
a. Inspection Scope
A region-based specialist inspector conducted an inspection of Entergys corrective actions related to the current Indian Point alert and notification system, and also of the progress made in the design and installation of the new siren system. The inspection was conducted onsite September 13 and 14, 2006, and in the Region I office the week of September 25, 2006, per the baseline inspection program deviation authorized by the NRC Executive Director of Operations in a memorandum approved on October 31, 2005.
The inspector discussed and reviewed two events during the quarter that involved the loss of the ability to actuate the sirens: one occurred on August 2, 2006, as the result of a system computer hard drive failure; and one occurred on September 7, 2006, as the result of a human performance issue which occurred during work to prepare for the installation of the new siren system. The inspector reviewed the condition reports and the corrective actions, for these two events. To assess the effectiveness of the corrective actions and the performance of Entergys siren system, the inspector observed the performance of the quarterly full siren test conducted on September 13, 2006. The inspector monitored the test from the Indian Point Energy Center Emergency Operations Facility (EOF) and observed the licensees communication with the four local counties, the initiation of the siren system actuation, and the reception and logging of siren feedback information to determine the performance of the sirens.
Subsequent to the onsite portion of the inspection, the inspector learned of an additional failure of the siren system on September 19, 2006, as the result of the computer software database failing to reconnect following a preventive maintenance reboot of the siren system computer. The inspector conducted an initial in-office review of the event, but the licensees corrective actions were not finalized prior to the end of the inspection period.
The inspector interviewed the project manager for the new siren system to understand Entergys progress towards meeting the milestone dates required by the NRCs Confirmatory Order dated January 31, 2006. While on site, the inspector observed the progress of Entergys installation of the new siren control system in the EOF. The inspector also reviewed the proposed final Indian Point Energy Center Prompt Alert and Notification System Design Report which Entergy had submitted to the New York State Emergency Management Office on September 28, 2006, for Department of Homeland Security review and approval.
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES
4OA1 Performance Indicator Verification
a. Inspection Scope
The inspectors reviewed the licensees data submitted to the NRC for the performance indicators (PIs) listed below, and performed an independent verification that the source data was consistent with plant records. The inspectors reviewed the licensees collecting and reporting process for PI data as described in procedure SAO-114, Preparation of NRC and World Association of Nuclear Operators (WANO) Performance Indicators. The purpose of these reviews was to determine whether the methods for reporting PI data were consistent with the guidance contained in Nuclear Energy Institute (NEI) 99-02, Regulatory Assessment Performance Indicator Guidelines, Revision 2. The inspection included a review of the indicator definitions, data reporting elements, calculating methods, definition of terms, and clarifying notes for the performance indicators. Plant records and data, including operator log entries, daily morning reports (including daily CR descriptions), monthly operating reports and PI data sheets were sampled and compared to the reported data. This inspection activity represents the completion of two samples.
Reactor Safety Cornerstone
- Reactor Coolant System Leakage (April 2004 - June 2006)
- Reactor Coolant System Activity (January 2004 - June 2006)
b. Findings
No findings of significance were identified.
4OA2 Identification and Resolution of Problems
Review of items Entered into the Corrective Action Program:
a. Inspection Scope
As required by Inspection Procedure 71152, Identification and Resolution of Problems, and in order to help identify repetitive failures or specific human performance issues for follow-up, the inspectors screened all items entered into Entergys corrective action program. This review was accomplished by reviewing hard copies or computer records of each condition report.
b. Assessment and Observations No findings or observations of significance were identified.
4OA3 Event Followup
.1 Unit 3 Automatic Trip - July 6, 2006
a. Inspection Scope
The inspectors responded to an automatic reactor trip that occurred on July 6, 2006, while operating at 100 percent steady state power. The automatic reactor trip occurred due to a main turbine generator trip as a result of a main generator protection circuit trip caused by a short in the insulation of wiring in the junction box of the main generator output phase 'B' differential protection current transformer. The inspectors discussed the reactor trip with Entergy management, as well as operations, maintenance, and engineering 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 discussed the reactor trip with Entergys root cause analysis team and assessed the teams actions to gather, review, and assess information leading up to and following the reactor trip. The inspectors also reviewed the initial investigation report and root cause determination to assess the detail of the review and the adequacy of the root cause analysis and proposed corrective actions prior to unit restart. The inspectors also reviewed the initial licensee notification to verify that it met the requirements specified in NUREG-1022, Event Reporting Guidelines. Inspector observations were compared to the requirements specified in the procedure listed in the Attachment.
b. Findings
No findings of significance were identified.
.2 Unit 3 Manual Trip - July 21, 2006
a. Inspection Scope
The inspectors responded to an manual reactor trip that occurred on July 21, 2006, while operating at 100 percent steady state power. Control room operators initiated a manual reactor trip in accordance with directions provided by the operations shift manager as a result of observing arcing under the main turbine generator between metal scaffolding contacting two phases of the main turbine generator iso-phase bus housing. The inspectors discussed the reactor trip with Entergy management as well as operations, maintenance, and engineering 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 discussed the reactor trip with Entergys root cause analysis team and assessed the teams actions to gather, review, and assess information leading up to and following the reactor trip. The inspectors also reviewed the initial investigation report and root cause determination to assess the detail of the review and the adequacy of the root cause analysis and proposed corrective actions prior to unit restart. The inspectors also reviewed the initial licensee notification to verify that it met the requirements specified in NUREG-1022, Event Reporting Guidelines. Inspector observations were compared to the requirements specified in the procedure listed in the Attachment.
b. Findings
No findings of significance were identified.
.3 (Closed) LER 06000286/2006-001-00 Reactor Trip as a Result of a Main Generator
Trip Due to Short in the Generator Differential Protection Circuit An automatic reactor trip that occurred on July 6, 2006, while the unit was operating at 100 percent steady state power. The automatic reactor trip occurred due to a main turbine generator trip as a result of a main generator protection circuit trip caused by a short in the insulation of wiring in the junction box of the main generator output phase 'B' differential protection current transformer. Entergy maintenance personnel repaired the insulation on the wiring, and the unit was returned to full power operation. The LER was reviewed by the inspectors and no findings of significance were identified and no violation of NRC requirements occurred. The licensee documented the failed equipment in CR-IP3-2006-02071. This LER is closed.
4OA5 Other Activity
Groundwater Contamination Investigation
a. Inspection Scope
Inspection of the groundwater contamination investigation at Indian Point Energy Center was authorized by the NRC Executive Director of Operations in a Reactor Oversight Process (ROP) deviation memorandum approved on October 31, 2005 (ADAMS Accession number ML053010404). Accordingly, oversight of licensee progress has been conducted throughout this inspection period consisting of weekly discussions with the licensee on groundwater investigation status and bi-weekly communications with Federal, State, and local government stakeholders. In addition, NRC continued to split samples of offsite, site boundary and other selected monitoring wells with the licensee in order to verify the licensees sample results.
b. Results The NRCs assessment of the licensees sample data indicated that the licensee continued to report sample results that were consistent with NRC results. The Oak Ridge Institute for Science and Education, Environmental Site Survey and Assessment Program (ORISE/ESSAP) sample results are available in ADAMS under Accession Number ML062720227. To date, sample results from site boundary wells and off-site environmental groundwater sampling locations have not indicated any detectable plant-related activity.
4OA6 Meetings, including Exit
Exit Meeting Summary
On October 4, 2006, the inspectors presented the inspection results to Mr. Paul Rubin and other Entergy staff members, who acknowledged the inspection results presented.
Entergy did not identify any material as proprietary.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- F. Dacimo, Site Vice President
- P. Rubin, General Manager, Plant Operations
- J. Ventosa, Director, Engineering
- J. Comiotes, Director, Nuclear Safety Assurance
- A. Williams, IP3 Operations Manager
- A. Vitale, Site Operations Manager
- T. Barry, Security Manager
- J. Donnelly, Manager, Maintenance
- P. Conroy, Manager, Licensing
- B. Sullivan, Emergency Planning Manager
- T. Jones, Licensing Supervisor
- L. Lee, Systems Engineering Supervisor
- T. Orlando, Manager, Design Engineering
- C. Smyers, Shift Manager, Operations
- P. Parker, Superintendent, Maintenance
- D. Shah, Systems Engineer
- S. Wilkie, Fire Protection Engineer
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened and Closed
06000286/2006-001-00 LER Reactor Trip as a Result of a Main Generator Trip Due to Short in the Generator Differential Protection Circuit (Section 4OA3.3)