ML041670477
| ML041670477 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/15/2004 |
| From: | Ogle C NRC/RGN-II/DRS/EB |
| To: | Rosalyn Jones Duke Energy Corp |
| References | |
| IR-04-006 | |
| Download: ML041670477 (7) | |
Text
June 15, 2004 Duke Energy Corporation ATTN: Mr. R. A. Jones Site Vice President Oconee Nuclear Station 7800 Rochester Highway Seneca, SC 29672
SUBJECT:
NOTIFICATION OF OCONEE NUCLEAR STATION - SAFETY SYSTEM DESIGN AND PERFORMANCE CAPABILITY INSPECTION - NRC INSPECTION REPORT 05000269/2004006, 05000270/2004006, AND 05000287/2004006
Dear Mr. Jones:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a safety system design and performance capability inspection at your Oconee Nuclear Station during the weeks of August 16, 2004, and August 30, 2004. A team of five inspectors will perform this inspection. The inspection team will be led by Mr. Jim Moorman, a Senior Reactor Inspector from the NRC Region II Office. This biennial inspection will be conducted in accordance with baseline inspection program Attachment 71111.21, Safety System Design and Performance Capability.
The inspection will evaluate the capability of installed plant equipment to detect and respond to a steam generator tube rupture event. Procedures which direct the mitigating actions for this event will also be evaluated.
During a telephone conversation on June 4, 2004, Mr. Moorman of my staff, and Mr. Larry Nicholson of your staff, confirmed arrangements for an information gathering site visit and the two-week onsite inspection. The schedule is as follows:
Information gathering visit: Week of July 26, 2004 Onsite inspection weeks: August 16, 2004, and August 30, 2004 The purpose of the information gathering visit is to obtain information and documentation outlined in the enclosure needed to support the inspection. Mr. Walter Rogers, a Region II Senior Reactor Analyst, may accompany Mr. Moorman during the information gathering visit to review probabilistic risk assessment data and identify risk significant components which will be examined during the inspection. Please contact Mr. Moorman prior to preparing copies of the materials listed in the Enclosure. The inspectors will try to minimize your administrative burden by specifically identifying only those documents required for inspection preparation.
During the information gathering visit, the team leader will also discuss the following inspection support administrative details: office space; specific documents requested to be made available to the team in their office space; arrangements for site access; and the availability of knowledgeable plant engineering and licensing personnel to serve as points of contact during the inspection.
DEC 2
Thank you for your cooperation in this matter. If you have any questions regarding the information requested or the inspection, please contact Mr. Moorman at (404) 562-4647 or me at (404) 562-4605.
In accordance with 10 CFR 2.390 of the NRCs "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publically 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/
Charles R. Ogle, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 50-269, 50-270, 50-287 License Nos.: DPR-38, DPR-47, DPR-55
Enclosure:
Information Request for the Safety System Design and Performance Capability Inspection cc w/encl:
B. G. Davenport Compliance Manager (ONS)
Duke Energy Corporation Electronic Mail Distribution Lisa Vaughn Legal Department (PB05E)
Duke Energy Corporation 422 South Church Street P. O. Box 1244 Charlotte, NC 28201-1244 Anne Cottingham Winston & Strawn LLP Electronic Mail Distribution (cc w/encl cont'd - See page 3)
DEC 3
(cc w/encl contd)
Beverly Hall, Acting Director Division of Radiation Protection N. C. Department of Environmental Health & Natural Resources Electronic Mail Distribution Henry J. Porter, Assistant Director Div. of Radioactive Waste Mgmt.
S. C. Department of Health and Environmental Control Electronic Mail Distribution R. Mike Gandy Division of Radioactive Waste Mgmt.
S. C. Department of Health and Environmental Control Electronic Mail Distribution County Supervisor of Oconee County 415 S. Pine Street Walhalla, SC 29691-2145 Lyle Graber, LIS NUS Corporation Electronic Mail Distribution R. L. Gill, Jr., Manager Nuclear Regulatory Issues and Industry Affairs Duke Energy Corporation 526 S. Church Street Charlotte, NC 28201-0006 Peggy Force Assistant Attorney General N. C. Department of Justice Electronic Mail Distribution
DEC 4
Distribution w/encl:
L. Olshan, NRR C. Evans (Part 72 Only)
L. Slack, RII EICS RIDSNRRDIPMLIPB PUBLIC OFFICE RII:DRS RII:DRP SIGNATURE RA RA NAME Moorman Haag DATE 6/14/2004 6/14/2004 6/ /2004 6/ /2004 6/ /2004 6/ /2004 6/ /2004 E-MAIL COPY?
YES NO YES NO YES NO YES NO YES NO YES NO YES NO PUBLIC DOCUMENT YES NO OFFICIAL RECORD COPY DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML041670477.wpd
Enclosure INFORMATION REQUEST FOR THE SAFETY SYSTEM DESIGN AND PERFORMANCE CAPABILITY INSPECTION OCONEE STEAM GENERATOR TUBE RUPTURE MITIGATION (Please provide the information electronically in searchable.pdf files on CDROM. The CDROM should be indexed and hyperlinked to facilitate ease of use. Information in lists should contain enough information to be easily understood by someone who has a knowledge of pressurized water reactor technology.)
1.
Piping and instrumentation drawings for the following systems: High Pressure Injection (HPI), Emergency Feedwater (EFW), Main Steam (MS), Main Feedwater (MFW),
Condensate (Cond), Low Pressure Injection (LPI), Reactor Coolant System (RCS),
Borated Water Storage Tank (BWST) Make-up (Paper copies (2) are preferred for these) 2.
The normal operating procedures for the systems listed above. Include the procedures which specify the normal valve alignment for these systems.
3.
Surveillance procedures used to ensure the operability of equipment required by your Technical Specifications that is used during the mitigation of the SGTR event.
4.
Procedures used for the operational testing of check valves in portions of the emergency core cooling systems used during mitigation of the SGTR event.
5.
Procedures used to sample the reactor coolant system and the steam generators during a SGTR event.
6.
Calibration and functional testing procedures for the main steam line, steam generator blowdown, and condenser air ejector radiation monitoring instrumentation.
7.
Calibration and functional test procedures for instruments used to monitor RCS pressure, pressurizer level and pressure, SG level and pressure, RCS hot and cold leg temperature, RCS subcooling, feedwater flow, steam flow, core exit temperature, high pressure injection flow, SI flow, refueling water storage tank level, pressurizer heater status, safety relief valve position indicator, EFW flow, condensate storage tank (CST) level, makeup flow, and letdown flow.
8.
Test procedures for the primary and secondary system safety relief valves and pressurizer power operated relief valves.
9.
Test procedures for the EFW starting logic.
10.
A list of Action Requests and non-routine work requests initiated since 1999 affecting the systems used to detect and mitigate a SGTR event; including their power supplies.
2 Enclosure 11.
Emergency Operating Procedures (EOPs) and supporting procedures, EOP basis documents, step deviation document, writers guide, and users guide. Abnormal Operating Procedures that would be used during a steam generator tube leak/rupture event.
12.
Calculations used to support the setpoints in Emergency Operating Procedures for a SGTR event.
13.
A list of engineering calculations applicable to EFW, HPI, LPI, RCS, and other systems used in the mitigation of the SGTR event.
14.
A list of temporary modifications and operator work-arounds since 2001.
15.
A list of operability determinations performed since 1999.
16.
A list of corrective action program documents and non-routine work requests initiated since 2001 for EFW, HPI, LPI, BWST make-up, Cond., Radiation Monitoring, and MS systems.
17.
System Health Reports and System Performance Trends for all systems going back 2 years.
18.
A copy of the Maintenance Rule program procedure and performance criteria for all plant systems. A list of plant systems currently monitored under 50.65(a)(1) and the performance goals. A list of Maintenance Rule functional failures since 2000.
19.
Quality Assurance audits, self-assessments and third party assessments performed on EFW, HPI, LPI, RCS, systems and other related systems in the last 24 months. Quality Assurance audits, self-assessments, and third party assessments performed on engineering and maintenance department activities performed in the last 24 months..
20.
Operator training lesson plans, system descriptions, and job performance measures for the EOPs, EOP support procedures, abnormal, and normal operating procedures that would be used to mitigate an SGTR event.
21.
Key electrical single line drawings of the intermediate and low voltage alternating current (AC) and DC power systems. (Paper copies (2) are preferred for these) 22.
The electrical system load list(s).
23.
A brief description of the mitigation strategy for the SGTR event. This should include operator actions, equipment and power sources, as well as indications and control circuits.
24.
A list of Operating Experience Program evaluations of industry, vendor, or NRC generic issues for the past 3 years.
3 Enclosure 25.
A list of equipment and operator actions with a Risk Achievement Worth (RAW) greater than 1.02.
26.
Probabilistic Risk Assessment (PRA) Event Tree for SGTR initiating event. A List of PRA system dependencies and success criteria for EFW, HPI, LPI, MS, systems and their support systems.
27.
Design Basis Manual for major plant electrical, mechanical, and control systems.
28.
Plant Technical Specifications, Bases, and Technical Requirements Manual 29.
A current copy of the Updated Final Safety Analysis Report.
30.
All Oconee design basis requirements, commitments, and industry standards related to mitigation of the SGTR event.
31.
A list of all permanent plant changes, design changes, setpoint changes, procedure changes, equivalency evaluations, suitability analyses, calculations, and commercial grade dedications since 2001 32.
Plant procedures that provide the guidelines for the following programs: 1) Corrective Action Program, 2) Program for the evaluation of changes, tests, and experiments
[50.59 Program], 3) Program for the incorporation of local and industry operating experience into Oconee programs and procedures, 4) the design control program
- 33.
A list of operations training packages which were required due to modifications, if any.
- 34.
A list of Action Requests which were initiated in the area of modifications and the 50.59 process.
- 35.
Copies of the most recent self-assessment(s) and audit(s) of the modifications process and the 50.59 process.