IR 05000498/2002008
| ML022840476 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 10/11/2002 |
| From: | Johnson W Division of Nuclear Materials Safety IV |
| To: | Cottle W South Texas |
| References | |
| IR-02-008 | |
| Download: ML022840476 (12) | |
Text
ber 11, 2002
SUBJECT:
SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION - NRC INSPECTION REPORT 50-498/02-08; 50-499/02-08
Dear Mr. Cottle:
On September 21, 2002, the NRC completed an inspection at your South Texas Project Electric Generating Station, Units 1 and 2, facility. The enclosed report documents the inspection findings which were discussed on September 26, 2002, with Mr. J. Sheppard and other members of your staff.
This inspection examined activities conducted under your licenses as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your licenses. Within these areas, the inspection consisted of selected examination of procedures and representative records, observations of activities, and interviews with personnel. This inspection was the second in a series of three inspections to cover steam generator replacement activities at the South Texas Project, Unit 2. This inspection covered design and planning activities in support of steam generator replacement.
Based on the results of this inspection no finding of significance was identified.
In accordance with 10 CFR 2.790 of the NRCs "Rules of Practice," a copy of this letter, its enclosure, and your response will be made 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/
William D. Johnson, Chief Project Branch A Division of Reactor Projects
STP Nuclear Operating Company -2-Dockets: 50-498 50-499 Licenses: NPF-76 NPF-80
Enclosure:
NRC Inspection Report 50-498/02-08; 50-499/02-08
REGION IV==
Dockets: 50-498 50-499 Licenses: NPF-76 NPF-80 Report No: 50-498/02-08; 50-499/02-08 Licensee: STP Nuclear Operating Company Facility: South Texas Project Electric Generating Station, Units 1 and 2 Location: FM 521 - 8 miles west of Wadsworth Wadsworth, Texas 77483 Dates: June 16 - September 21, 2002 Inspectors: N. F. OKeefe, Senior Resident Inspector G. L. Guerra, Resident Inspector R. P. Mullikin, Senior Reactor Inspector, Engineering and Maintenance Branch, Division of Reactor Safety J. L. Taylor, Reactor Inspector, Engineering and Maintenance Branch J. B. Nicholas, Ph.D., Senior Health Physicist, Plant Support Branch Division of Reactor Safety Approved By: W. D. Johnson, Chief, Project Branch A, Division of Reactor Projects Attachment: Supplemental Information
SUMMARY OF FINDINGS South Texas Project Electric Generating Station NRC Inspection Report 50-498/02-08; 50-499/02-08 IR 05000498-02-08; IR 05000499-02-08; on 06/16-09/21/2002; South Texas Project Nuclear Operating Company; South Texas Project Electric Generating Station, Unit 2. Integrated Resident & Regional Report of Steam Generator Replacement Activities.
This inspection was conducted by resident, regional health physics, and regional engineering inspectors. This inspection was the second in a series of three inspections to cover steam generator replacement activities at the South Texas Project in accordance with the approved inspection plan. This inspection covered design and planning activities by the licensee. No findings of significance were identified. Unit 1 was included in this inspection to the extent of inspecting representative examples of licensee activities common to both units.
Report Details Plant Status Unit 1 operated at full power throughout the inspection period.
Unit 2 began the inspection period at approximately 7 percent power restarting from a manual plant trip on June 14, 2002. Full power was achieved on June 20. On July 7, the unit automatically tripped on high steam generator level. The unit was restarted on July 9, and achieved full power the next day. The unit operated at full power for the remainder of the inspection period.
1. REACTOR SAFETY Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity 1R17 Evaluation of Permanent Plant Modifications for Steam Generator Replacement a. Inspection Scope (71111.17, 50001)
The inspectors reviewed five permanent plant modification packages and associated documentation, such as safety evaluations associated with the replacement of the Units 1 and 2 steam generators, to verify that they were performed in accordance with regulatory requirements and plant procedures. The inspectors also reviewed procedures governing plant modifications to evaluate the effectiveness of the programs for implementing modifications to risk-significant systems, structures, and components, such that these changes did not adversely affect the design and licensing basis of the facility. Permanent plant modifications and procedures reviewed are listed in the attachment to this report.
The inspectors interviewed the cognizant engineers for selected modifications as to their understanding of the modification packages.
b. Findings No findings of significance were identified.
2. RADIATION SAFETY Cornerstone: Occupational Radiation Safety 2OS2 ALARA Planning and Controls a. Inspection Scope (71121.02, 50001)
The inspector interviewed radiation workers and radiation protection personnel throughout the radiologically controlled area to determine their knowledge of as low as is reasonably achievable (ALARA) practices and conducted independent radiation surveys of selected work areas. The following radiation protection program controls, planning, and preparation items were reviewed to determine whether the licensee had an adequate program to maintain occupational exposure as low as is reasonably achievable during the upcoming Unit 2 Steam Generator Replacement Outage, 2RE09:
-2-
- ALARA program procedures
- Radiation protection department self-assessments (external exposure control, performed October 3 through November 8, 2001, and ALARA planning/radiation protection/generation support, performed May 20-23, 2002)
- Radiation Protection Quality Monitoring Reports (MN-02-0-0451 and MN-02-0-0477)
- Health Physics Observation Reports (HP-02-2-0086, HP-02-0-0188, HP-02-1-0218, HP-02-2-0235, HP-02-2-0228, HP-02-2-0309, HP-02-1-0322, HP-02-2-0400, HP-02-0-0407, HP-02-2-0453, HP-02-2-0455, and HP-02-2-0481)
- ALARA and radiological work planning for three activity packages that may result in some of the highest personnel collective exposures during the 2RE09 Steam Generator Replacement Outage (steam generator replacement - feedwater baseplate modification, steam generator replacement - sever/modify/reinstall secondary piping systems, and steam generator replacement -
remove/reinstall/modify upper and lower lateral restraints)
- Processes used to estimate and track personnel exposures
- Plant collective exposure history for the past 3 years, current exposure trends, and 3-year rolling average dose information
- Use of engineering controls to achieve dose reductions, including six temporary shielding request packages planned for installation during 2RE09
- Contamination control processes proposed for 2RE09
- Emergency contingency planning proposed for radiological work activity packages to be conducted during 2RE09
- Staffing and training plans for radiation protection coverage during 2RE09
- Prejob briefings, job site inspection, and ALARA controls involved with the preparation and transfer of a high integrity container from the Unit 1 truck bay to the radwaste storage yard prior to shipment offsite for disposal
- A summary of ALARA related condition reports written between February 1 and July 12, 2002, with eighteen reviewed in detail (02-1550, 02-2647, 02-2659, 02-2715, 02-2763, 02-3753, 02-4190, 02-4191, 02-4729, 02-5392, 02-5394, 02-5706, 02-7036, 02-7923, 02-8370, 02-8507, 02-9206, and 02-9582).
b. Findings No findings of significance were identified.
-3-4. OTHER ACTIVITIES (OA)
4OA5 Steam Generator Replacement Activities
.1 Outage Planning and Controls a. Inspection Scope (50001)
The inspectors inspected the licensees activities associated with planning for the steam generator replacement in Unit 2 using the guidance provided in NRC Inspection Procedure 50001, Steam Generator Replacement. The inspectors observed the licensee and its contractors increase staffing levels to the planned staffing requirements that had been outlined for the outage. The inspectors evaluated project planning and status with regard to the observed activities of replacement steam generator preparation for installation and the construction of the containment outside lift system. The inspectors reviewed the licensees readiness review package and attended portions of the readiness review meetings. The inspectors discussed actions to avoid adverse impacts on the operating unit during steam generator replacement activities and special processes for problem identification and resolution progress with licensee personnel.
b. Findings No findings of significance were identified.
.2 Security Considerations a. Inspection Scope (50001)
The inspectors reviewed and discussed with plant protection personnel the licensees plan for access/authorization and badging to accommodate the large numbers of temporary outage workers needed for the outage. This plan was assessed using the guidance provided in NRC Inspection Procedure 50001, Steam Generator Replacement.
b. Findings No findings of significance were identified.
4OA6 Meetings, including Exit On July 18, 2002, the inspectors presented the results of the ALARA planning and controls inspection to Mr. J. Sheppard, Vice President and Assistant to President/CEO, and other members of licensee management.
On August 15, 2002, the inspectors presented the results of the permanent plant modifications inspection to Mr. J. Sheppard and other members of licensee management.
-4-On September 26, 2002, the inspectors presented the results of the resident inspection to Mr. J. Sheppard and other members of licensee management.
The inspectors asked the licensee representatives whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified.
ATTACHMENT Supplemental Information PARTIAL LIST OF PERSONS CONTACTED Licensee R. Aguilera, Supervisor, Radiation Protection S. Blossom, Assistant Installation Manager T. Bowman, Manager, Unit 1, Operations B. Bullard, Supervisor, Radiation Protection R. Gangluff, Manager, Chemistry E. Halpin, Plant Manager S. Head, Manager, Licensing C. Johnson, Director, Oversight T. Jordan, Vice President, Engineering and Technical Services M. Kanavos, Manager, Plant Modifications R. Kerr, Staff Engineer, Quality Assurance J. LeValley, Area Project Manager R. Lovell, Manager, Training M. Ludwig, Quality Auditor M. McBurnette, Director, Quality and Licensee F. Mangan, Vice President, Business Services M. Meier, Manager, Human Resources/Information Technology A. Moldenhauer, Engineer, Probabilistic Risk Analysis J. Meyers, Senior Health Physics Specialist W. Mookhoek, Senior Licensing Specialist M. Oswald, Supervising Engineer, Design Engineering G. Parkey, Vice President, Generation R. Piggott, Senior Licensing Specialist J. Price, Supervisor, Design Engineering K. Richards, Installation/Return to Service Manager J. Sheppard, Vice President & Assistant to the President/CEO J. Simmons, Health Physics Steam Generator Replacement Project Manager C. Stone, Supervisor, Radiation Protection D. Towler, Manager, Generation Quality Licensee Contractor J. Atwell - Project Manager - Bechtel S. Pearson - Site Manager - Bechtel
-2-DOCUMENTS REVIEWED The following documents were selected and reviewed by the inspectors to accomplish the objectives and scope of the inspection and to support any findings:
DESIGN CHANGE PACKAGES NUMBER DESCRIPTION DCP 98-00243-15 Change Tave (Unit 1)
DCP 98-19443-7 Reactor upper Head T-Cold Conversion (Unit 2)
DCP 98-19447-1 Steam Generator Replacement - SG Level Trip Setpoint Changes (Unit 2)
DCP 98-19447-8 SGRP EOP Setpoint Changes (Unit 2)
DCP 99-15476-3 Isolate Steam Generator Blowdown on a Reactor Trip (Unit 2)
PROCEDURES 0PGP04-ZE-0309 Design Change Package, Revision 10 0PGP03-ZR-0050 Radiation Protection Program, Revision 5 0PGP03-ZR-0052 ALARA Program, Revision 4 0PRP07-ZR-0001 ALARA Engineering and Procedure Review, Revision 3 0PRP07-ZR-0004 Temporary Shielding, Revision 6 0PRP07-ZR-0009 Performance of High Exposure Work, Revision 18 0PRP07-ZR-0010 Radiation Work Permits, Revision 8 0PRP07-ZR-0011 Radiological Work ALARA Reviews, Revision 4