IR 05000280/2004003
| ML042030379 | |
| Person / Time | |
|---|---|
| Site: | Surry, 07200002  |
| Issue date: | 07/20/2004 |
| From: | Landis K NRC/RGN-II/DRP/RPB5 |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| References | |
| -RFPFR IR-04-001, IR-04-003 | |
| Download: ML042030379 (23) | |
Text
July 20, 2004
SUBJECT:
SURRY POWER STATION - NRC INTEGRATED INSPECTION REPORT 05000280/2004003, 05000281/2004003, AND 07200002/2004001
Dear Mr. Christian:
On June 26, 2004, the United States Nuclear Regulatory Commission (NRC) completed an inspection at your Surry Power Station, Units 1 and 2, and the Surry Independent Spent Fuel Storage Installation. The enclosed integrated inspection report documents the inspection findings which were discussed on July 12, 2004, with Mr. Blount 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. No findings of significance were identified by the NRC.
Based on the results of this inspection, no findings of significance were identified. However one licensee-identified violation which was determined to be of very low safety significance is listed in Section 4OA7 of this report. If you contest this non-cited violation, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the United States Nuclear Regulatory Commission, ATTN.: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Surry Power Station.
In accordance with 10 CFR 2.390 of the NRCs 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
VEPCO 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/
Kerry D. Landis, Chief Reactor Projects Branch 5 Division of Reactor Projects Docket Nos.: 50-280, 50-281,72-002 License Nos.: DPR-32, DPR-37, SNM-2501
Enclosure:
Integrated Inspection Report 05000280, 281/2004003 and 07200002/2004001 w/Attachment: Supplemental Information
REGION II==
Docket Nos.: 50-280, 50-281,72-002 License Nos.: DPR-32, DPR-37, SNM-2501 Report Nos.:
05000280/2004003, 05000281/2004003, 07200002/2004001 Licensee:
Virginia Electric and Power Company (VEPCO)
Facility:
Surry Power Station, Units 1 & 2 Surry Independent Spent Fuel Storage Installation Location:
5850 Hog Island Road Surry, VA 23883 Dates:
March 28 - June 26, 2004 Inspectors:
G. McCoy, Senior Resident Inspector N. Garrett, Senior Resident Inspector D. Arnett, Resident Inspector L. Miller, Sr. Operations Engineer (Section 1R11.1)
M. Scott, Senior Reactor Inspector (Section 1R12.2 )
K. Van Doorn, Senior Reactor Inspector (Section 1R07)
Approved by: K. Landis, Chief, Reactor Projects Branch 5 Division of Reactor Projects
SUMMARY OF FINDINGS
IR 05000280/2004-003, IR 05000281/2004-003, IR 07200002/2004-001, 3/28/2004 -
6/26/2004, Virginia Electric and Power Co.; Surry Power Station Units 1 & 2 and Independent Spent Fuel Storage Installation, Routine Integrated Report.
The report covered a three month period of inspection by resident inspectors and announced inspections by an operations engineer, and two senior reactor inspectors. No findings of significance were identified. The significance of most findings is indicated by their color (Green,
White, Yellow, Red) using IMC 0609, Significance Determination Process, (SDP). Findings for which the SDP does not apply may be Green or be assigned a severity level after NRC management review. 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
One violation of very low safety significance that was identified by the licensee has been reviewed by the inspectors. Corrective actions taken or planned by the licensee have been entered into the licensees corrective action program. This violation is listed in Section 4OA7 of this report.
REPORT DETAILS
Summary of Plant Status
Unit 1 started the report period at full power. On May 13, 2004, Unit 1 power was reduced in order to address temperature problems on the Unit 1 A main transformer high side bushing. On May 15 the unit was taken offline for repairs. The unit was returned online and reached full power on May 16. The unit operated at full power for the remainder of the inspection period.
Unit 2 started the report period at full power. On May 21, Unit 2 tripped because of a generator trip due to a failure of a coupling capacitor potential device in the switchyard. After repairs were completed, the unit was returned to full power on May 31. The unit operated at full power for the remainder of the inspection period.
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity
==1R04 Equipment Alignment
==
.1 Partial System Walkdowns
a. Inspection Scope
The inspectors performed partial walkdowns of the following systems to verify correct system alignment. The inspectors checked for correct valve and electrical power alignments by comparing positions of valves, switches, and breakers to the procedures and drawings listed in the attachment. Additionally, the inspectors reviewed the corrective action system to verify that equipment alignment problems were being identified and properly resolved.
- Unit 1 outside recirculation spray system, while 1-RS-P-2A was out of service,
- Number 1 and number 2 emergency diesel generators while the number 3 emergency diesel generator was out of service, and
- Unit 2 auxiliary feedwater system after the completion of maintenance.
b. Findings
No findings of significance were identified.
.2 Complete System Walkdown
a. Inspection Scope
The inspectors performed a detailed walkdown on the accessible portions of the Unit 2 safety injection system to review the system alignment and condition. The inspectors reviewed applicable documents to determine the correct system alignment, reviewed outstanding maintenance work orders, plant issues associated with system deficiencies, verified valve and breaker position, and component labeling. In addition, the inspectors verified material condition of valves, pumps, hangers, brackets, and other system supports. The inspectors reviewed the corrective action database to identify that equipment alignment issues are being identified and resolved. The documents reviewed are listed in the attachment.
b. Findings
No findings of significance were identified.
==1R05 Fire Protection
==
.1 Fire Area Walkdowns
a. Inspection Scope
The inspectors conducted tours of the following nine areas to assess the adequacy of the fire protection program implementation. The inspectors checked for the control of transient combustibles and the condition of the fire detection and fire suppression systems (using Surry Power Station (SPS) Appendix R Report,) in the following areas:
- Unit 2 emergency switchgear room,
- Battery room 1A,
- Battery room 2A,
- North fuel oil pump house,
- South fuel oil pump house,
- Unit 1 main steam valve house,
- Unit 1 emergency switchgear room,
- Number 2 emergency diesel generator room, and
- Battery room 2B.
b. Findings
No findings of significance were identified.
.2 Annual Fire Brigade Drill
a. Inspection Scope
The inspectors observed a fire brigade drill to evaluate the readiness of the licensees personnel to fight fires. Specific aspects evaluated were: use of protective clothing and self contained breathing apparatus; fire hose deployment and reach; approach into the fire area; effectiveness of communications among the fire brigade members and the control room; sufficiency of fire fighting equipment brought to the fire scene; and the drill objectives and acceptance criteria. The drill was performed in mechanical equipment room number 1 which contains the Unit 1 feedwater regulation valves and the nitrogen-16 monitors.
b. Findings
No findings of significance were identified.
==1R07 Heat Sink Performance
a. Inspection Scope
==
The inspectors reviewed inspection and test procedures and associated records and other documentation to ensure that heat exchanger (HX) deficiencies that could mask or degrade performance were identified. Inspection and monitoring records for risk significant HXs were reviewed which included performance for the charging pump lube oil coolers, control room chiller condensers, and the recirculation spray system. The inspectors also reviewed general health of the service water (SW) system via review of chemistry activities; review of SW corrective maintenance history; review of SW system health reports; and discussions with the system engineer. Selected Plant Issues and a self-assessment were reviewed for potential common cause problems and problems which could affect system performance, to confirm the licensee was entering problems into the corrective action program and initiating appropriate corrective actions. In addition, the inspectors conducted a walk down of most of the SW system and the major components.
b. Findings
No findings of significance were identified.
==1R11 Licensed Operator Requalification
==
.1 Annual Operating Test Results
a. Inspection Scope
The licensee completed the comprehensive requalification written examinations on February 13, and the annual operating tests on April 9, required to be given to all licensed operators by 10 CFR 55.59(a)(2). The inspector reviewed the overall pass/fail results of the written examinations, individual operating tests, and the crew simulator operating tests. These results were compared to the thresholds established in Manual Chapter 609 Appendix I, Operator Requalification Human Performance Significance Determination Process.
b. Findings
No findings of significance were identified.
.2 Operator Requalification Testing
a. Inspection Scope
The inspectors observed licensed operator performance during simulator training session RQ-04.2-SE-1 to determine whether the operators:
- were familiar with and could successfully implement the procedures associated with recognizing and recovering from a loss of condenser vacuum and a major steam line break inside containment;
- recognized the high-risk actions in those procedures; and,
- were familiar with related industry operating experience.
b. Findings
No findings of significance were identified.
==1R12 Maintenance Effectiveness
==
.1 Review of Performance Issues
a. Inspection Scope
For the equipment issues described in the plant issues listed below, the inspectors evaluated the licensees effectiveness of the corresponding preventive and corrective maintenance. For each selected item below, the inspectors performed a detailed review of the problem history and surrounding circumstances, evaluated the extent of condition reviews as required, and reviewed the generic implications of the equipment and/or work practice problem. Inspectors performed walkdown of the accessible portions of the system, performed in-office reviews of procedures and evaluations, and held discussions with system engineers. Inspectors compared the licensees actions with the requirements of the Maintenance Rule (10 CFR 50.65) VPAP 0815, Maintenance Rule Program, and the Surry Maintenance Rule Scoping and Performance Criteria Matrix.
- Emergency service water pump maintenance, and
- Battery maintenance program (black battery, technical support center battery &
security diesel battery).
b. Findings
No findings of significance were identified.
.2 Maintenance Rule Periodic Evaluation (Biennial)
a. Inspection Scope
The inspectors reviewed the licensees maintenance rule (MR) periodic assessment, Self-Assessment SPS-SA-03-27, 2003 Maintenance Rule Periodic Assessment dated 12/18/03, while on-site the week of April 19, 2004. The report was issued to satisfy paragraph (a)(3) of 10 CFR 50.65 and covered the 18 month period ending May 31, 2003. The inspection was to determine the effectiveness of the assessment and that it was issued in accordance with the MR time requirement and included evaluation of:
balancing reliability and unavailability, (a)(1) activities, (a)(2) activities, and use of industry operating experience. To verify compliance with 10 CFR 50.65, the inspectors reviewed selected MR activities covered by the assessment period for the following maintenance rule systems: station blackout generator, emergency diesel generators, 125 Volt DC vital bus, instrument and service air systems, residual heat removal system.
Specific procedures and documents reviewed are listed in the attachment to this report.
During the inspection, the inspectors reviewed selected plant work order (WO) data and the site guidance implementing procedure, discussed and reviewed relevant corrective action issues, reviewed generic operations event data, structural reports, and probabilistic risk data, and discussed issues with system engineers. Operational event information use in MR functions was evaluated by the inspectors. The inspectors selected work orders, a MR assessment, and other corrective action documents of systems recently removed from 10 CFR 50.65 a(1) status and those in a(2) status for some period to assess the justification for their status. The documents were compared to the sites MR program criteria, and the MR a(1) evaluations and MR related databases.
b. Findings
No findings of significance were identified.
==1R13 Maintenance Risk Assessments and Emergent Work Control
a. Inspection Scope
==
The inspectors evaluated the adequacy, accuracy, and completeness of plant risk assessments performed prior to changes in plant configuration for maintenance activities or in response to emergent conditions. When applicable, inspectors assessed if the licensee entered the appropriate risk category in accordance with plant procedures. Specifically, the inspectors reviewed:
- Turbine building sump pumps out of service for sump inspection with the Unit 2 B bearing cooling pump out of service for maintenance and work in the 230KV switchyard,
- Number 3 emergency diesel generator (EDG), the Unit 2 service air compressor and the D component cooling water pump out of service for maintenance,
- Blackout diesel generator out of service for maintenance with the number 2 EDG out of service for a surveillance test,
- Number 3 emergency diesel generator out of service for maintenance and a high temperature on the Unit 1 A main transformer high side bushing,
- Operational test of the Unit 1 B charging pump, number 1 EDG monthly start test and the unit 1 turbine driven auxiliary feed water pump surveillance.
b. Findings
No findings of significance were identified.
==1R14 Operator Performance During Non-Routine Evolutions and Events
a. Inspection Scope
==
For the non-routine events described below, the inspectors reviewed operator logs, plant computer data, and strip charts to determine what occurred and how the operators responded, and to verify if the response was in accordance with plant procedures;
- Unit 1 ramp to repair the A main transformer high side bushing, and
- Unit 2 trip following failure of the A phase coupling capacitor potential device.
b. Findings
No findings of significance were identified.
==1R15 Operability Evaluations
a. Inspection Scope
==
The inspectors evaluated the technical adequacy of the five operability evaluations to ensure that operability was properly justified and the subject component or system remained available such that no unrecognized increase in risk occurred. The operability evaluations were described in the engineering transmittal (ET) and plant issues listed below:
- Plant Issue S-2004-1510, Clogging of the charging pump heat exchanger;
- Plant Issue S-2004-1984, Low residual heat removal differential pressure during surveillance test;
- Justification for Continued Operation (JCO) SC-03-003 revision 3, Control of auxiliary feedwater to the steam generators with one emergency bus de-energized;
- Plant Issue S-2004-1567, Unit 1 Main Steam Pressure transmitter tubing support; and
- Plant Issue S-2004-2112 and WO 513688-01, Oil contamination of the security diesel battery.
b. Findings
No findings of significance were identified.
==1R16 Operator Workarounds
a. Inspection Scope
==
The inspectors reviewed the licensees list of identified operator workarounds as of April 6, 2004, to assess the cumulative effects of operator workarounds on the reliability, availability, and potential for mis-operation of a system to verify that there was no increase in overall plant risk. This assessment included increases of initiating event frequencies, effects on multiple mitigating systems, and the ability of operators to correctly respond to abnormal plant conditions.
b. Findings
No findings of significance were identified.
==1R19 Post Maintenance Testing
a. Inspection Scope
==
The inspectors reviewed the five post maintenance test procedures and activities associated with the repair or replacement of the following components to determine whether the procedures and test activities were adequate to verify operability and functional capability following maintenance of the following equipment:
- WO 512482-01, PS 2 Non-urgent failure of U1 2BD rod control;
- WO 512181-01, Replace relay 3-CLS-IBM-X;
- WO 512673-01, 1-FW-MOV-160A, AFW X-tie; and
- WO 513004-01, AFW recirculation line modification.
b. Findings
No findings of significance were identified.
==1R20 Refueling and Outage Activities (Unit 2)
a. Inspection Scope
==
The inspectors performed the inspection activities described below for the Unit 2 forced outage that began on May 21, 2004, and ended May 27, 2004.
The inspectors reviewed portions of the cooldown process to verify that technical specification cooldown restrictions were followed.
The inspectors confirmed that, when the licensee removed equipment from service, the licensee maintained defense-in-depth commensurate with the outage risk control plan for key safety functions and applicable technical specifications, and that configuration changes due to emergent work and unexpected conditions were evaluated.
During the outage, the inspectors:
- Reviewed reactor coolant system (RCS) pressure, level, and temperature instruments to verify that those instruments were installed and configured to provide accurate indication; and that instrumentation error was accounted for;
- Reviewed the status and configuration of electrical systems to verify that those systems met technical specification requirements and the licensees outage risk control plan;
- Reviewed selected control room operations to verify that the licensee was controlling reactivity in accordance with the technical specifications; The inspectors reviewed the licensees plans for changing plant configurations to verify on a sampling basis that technical specifications, license conditions, and other requirements, commitments, and administrative procedure prerequisites were met prior to changing plant configurations.
The inspectors reviewed various problems that arose during the outage to verify that the licensee was identifying problems related to refueling outage activities at an appropriate threshold and entering them in the corrective action program.
b. Findings
No findings of significance were identified.
==1R22 Surveillance Testing
a. Inspection Scope
==
For the seven surveillance tests listed below, the inspectors examined the test procedure and either witnessed the testing and/or reviewed test records to determine whether the scope of testing adequately demonstrated that the affected equipment was functional and operable:
- 0-OPT-SW-001, Emergency Service Water 1-SW-P-1A performance test;
- 0-NSP-CW-001, High Level Intake Structure Canal Level Probe Inspection;
- 0-OPT-EG-001, Number 3 Emergency Diesel Generator Monthly Start Test;
- 2-PT-1.2, Nuclear Instrumentation System Power Range Trip Channel Test;
- 0-OP-AAC-001, Auxiliary AC Diesel Operation;
- 2-PT-8.1, Reactor Protection System Logic (Normal Operations);
- 0-MOP-EG-001 and 0-OPT-EG-001, Number 3 Emergency Diesel Generator Surveillance Test.
b. Findings
No findings of significance were identified.
Cornerstone: Emergency Preparedness
1EP6 Drill Evaluation
a. Inspection Scope
The inspectors observed an emergency response training drill conducted on April 13, in the simulator and the technical support center to assess the licensees performance in emergency classification, notification, and protective action recommendation development.
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES
4OA1 Performance Indicator Verification
a. Inspection Scope
The inspectors performed a periodic review of the Safety System Unavailability performance indicators for the following two systems:
- Residual heat removal system, and
- Emergency AC power system.
This review included information from both Unit 1 and Unit 2. Specifically, the inspectors reviewed this performance indicator (PI) from the second quarter of 2003 through the first quarter of 2004. Inspectors evaluated whether the performance indicator was calculated in accordance with the guidance contained in NEI 99-02, Regulatory Assessment Performance Indicator Guideline. Documents reviewed included applicable monthly operating reports, licensee event reports, and operator logs.
b. Findings
No findings of significance were identified.
.2 Reactor Coolant System Leakage Performance Indicator
a. Inspection Scope
The inspectors performed a periodic review of the "Reactor Coolant System Leakage" PI for Units 1 and 2. Specifically, the inspectors reviewed this PI for the first quarter through the fourth quarter of 2003. This inspection was to assess the accuracy of the submitted information and if the PI was calculated in accordance with the methodology established in Nuclear Energy Institute (NEI) 99-02, "Regulatory Assessment Performance Indicator Guideline." The inspectors compared the submitted data with that recorded in operator logs for the period January 1, 2003, through December 31, 2003. The inspectors also discussed this PI with the cognizant engineer and licensing staff and reviewed the system engineers data sheets.
b. Findings
No findings of significance were identified.
.3 Reactor Coolant System Specific Activity Performance Indicator
a. Inspection Scope
The inspectors performed a periodic review of the Reactor Coolant System Specific Activity PI for Units 1 and 2. Specifically, the inspectors reviewed this PI from the second quarter of 2003 through the first quarter of 2004. Inspectors evaluated whether the PI was calculated in accordance with the guidance contained in NEI 99-02, Regulatory Assessment Performance Indicator Guideline. Chemistry logs were reviewed to verify the data in the PI.
b. Findings
No findings of significance were identified.
4OA2 Problem Identification and Resolution
.1 Routine Reviews
a. Inspection Scope
As required by Inspection Procedure 71152, Identification and Resolution of Problems, and in order to help identify repetitive equipment failures or specific human performance issues for follow-up, the inspectors performed a daily screening of items entered into the licensees corrective action program. This review was accomplished by reviewing hard copies of each condition report, and attending the daily Plant Issue Review Team meetings.
b. Findings
No findings of significance were identified.
.2 Semi-Annual Review of Plant Issues
a. Inspection Scope
As required by Inspection Procedure 71152, "Identification and Resolution of Problems,"
the inspectors performed a review of the licensees corrective action program (CAP) and associated documents to identify trends that could indicate the existence of a more significant safety issue. The inspectors initially performed a review of the licensees corrective action program to identify trends that might indicate the existence of more significant safety issues as documented in NRC inspection report 05000280/2004002 and 05000281/2004002, dated April 19, 2004. This review was continued during this inspection report. The inspectors review was focused on repetitive equipment issues, but also considered the results of daily inspector CAP item screening discussed in section 4OA2.1 above, licensee trending efforts, and licensee human performance results. The inspectors review nominally considered the six month period of January 2004 through June 2004, although some examples expanded beyond those dates when the scope of the trend warranted. Inspectors also reviewed nine specific CAP items associated with component mis-positioning events that occurred during the period. The review also included issues documented outside the normal CAP in major equipment problem lists, repetitive and/or rework maintenance lists, departmental problem/challenges lists, system health reports, quality assurance audit/surveillance reports, self assessment reports, and maintenance rule assessments. The specific items reviewed are listed in the Documents Reviewed section attached to this report.
The inspectors compared and contrasted their results with the results contained in the licensees latest quarterly trend reports. Corrective actions associated with a sample of the issues identified in the licensees trend report were reviewed for adequacy.
b. Findings
No findings of significance were identified.
4OA5 Other Activities
.1 Review of the Operation of an Independent Spent Fuel Storage Installation
a. Inspection Scope
Inspectors reviewed the normal operations of the Independent Spent Fuel Storage Installation (ISFSI). Inspectors verified through a review of selected records that the licensee has properly identified each fuel assembly placed in the two latest casks which have been placed on the ISFSI pad. Inspectors also verified that the fuel placed in these casks met the requirements of the technical specifications. Inspectors also walked down both ISFSI pads to assess the material condition of the casks, the installation of security equipment, and the performance of the monitoring systems.
Inspectors verified that the required records are being retained for the ISFSI pad and duplicate records are being kept at a separate location.
b. Findings
No findings of significance were identified.
.2 INPO Peer Review
On May 13, 2004, the Senior Resident Inspector reviewed the Institute of Nuclear Power Operations/ World Association of Nuclear Operators (INPO / WANO) Peer Review of Surry Power Station report, dated March, 2003.
.3 (Closed) Temporary Instruction (TI) 2515/154, Spent Fuel Material Control and
Accounting at Nuclear Power Plants Temporary Instruction (TI) 2515/154, Spent Fuel Material and Accounting at Nuclear Power Plants, Phase I and Phase II, were completed during this inspection period.
Appropriate documentation was provided to NRC management as required. This TI is considered closed. Documents reviewed for this TI are listed in the attachment.
.4 (Open) Temporary Instruction (TI) 2515/156, Offsite Power System Operational
Readiness
a. Inspection Scope
The inspectors collected data from licensee maintenance records, event reports, corrective action documents and procedures and through interviews of station engineering, maintenance, and operations staff, as required by TI 2515/156. The data was gathered to assess operational readiness of the offsite power systems in accordance with NRC requirements such as Appendix A to 10 CFR Part 50, General Design Criteria (GDC) 17; Criterion XVI of Appendix B to 10 CFR 50.63; 10 CFR 50.65 (a)(4), and licensee procedures. Documents reviewed for this TI are listed in the attachment.
b. Findings
No findings of significance were identified. Based on the inspection, no immediate operability issues were identified. In accordance with TI 2515/156 reporting requirements, the inspectors provided the required data to the headquarters staff for further analysis. This TI remains open pending completion of that analysis.
4OA6 Meetings, Including Exit
On July 12, 2004, the resident inspectors presented the inspection results to Mr. Blount and other members of his staff who acknowledge the findings.
The inspectors confirmed that proprietary information was not provided or examined during the inspection.
4OA7 Licensee Identified Violations
The following findings of very low significance were identified by the licensee and are violations of NRC requirements which meet the criteria of Section VI of the NRC Enforcement Policy, NUREG-1600, for being dispositioned as Non-Cited Violations (NCV).
- Technical Specification (TS) section 6.4.A.7 requires that the licensee develop procedures for preventive or corrective maintenance operations on equipment which would have an effect on the safety of the reactor and TS section 6.4.D requires that these procedures be followed. On June 14, 2004, the licensee determined that a lug was not properly crimped onto the motor lead on the Unit 1 A high head charging pump and that the pump would not have been able to successfully start from April 12, 2004, until June 13, 2004. The improper installation of the lug on the power cable for this safety related motor is a failure to follow procedure GMP-15. This finding was of very low safety significance because the other two high head safety injection pumps remained operable during this period, and could have fulfilled the required safety functions. This issue is addressed in the licensees corrective action program as Plant Issue S-2004-2242 and S-2004-2279.
If you deny these NCVs, you should provide a response with the basis for your denial, within 30 days of the date of this inspection report, to the United States Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Surry Power Station.
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- R. Allen, Manager, Outage and Planning
- R. Blount, Site Vice President
- M. Gaffney, Director, Nuclear Station Safety and Licensing
- B. Garber, Supervisor, Licensing
- T. Huber, Manager, Engineering
- L. Jones, Manager, Radiation Protection and Chemistry
- D. Llewellyn, Manager, Training
- R. MacManus, Manager, Nuclear Oversight
- K. Sloane, Director, Nuclear Station Operations and Maintenance
- B. Stanley, Manager, Maintenance
- J. Swientoniewski, Manager, Operations
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
None
Closed
2515/154 TI Spent Fuel Material Control and Accounting at Nuclear Power Plants (Section 4OA5.3)
Discussed
2515/156 TI Offsite Power System Operational Readiness (Section 4OA5.4)