IR 05000382/2011007
| ML111740690 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 06/23/2011 |
| From: | Thomas Farnholtz Region 4 Engineering Branch 1 |
| To: | Kowalewski J A Entergy Operations |
| References | |
| IR-11-007 | |
| Download: ML111740690 (7) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION IV 612 E. LAMAR SUITE 400 ARLINGTON, 76011*4005 June 23, 2011 Joseph A. Kowalewski, Vice President, Operations Entergy Operations, inc. Waterford Steam E!ectric Station, Unit 3 17265 River Road Killona, LA 70057-0751
SUBJECT: WATERFORD STEAM ELECTRIC STATION, UNIT 3-INITIAL INFORMATION REQUEST FOR NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION NRC INSPECTION REPORT 05000382/2011007
Dear Mr. Kowalewski:
On August 22, 2011, the NRC will begin a triennial baseline Component Design Bases Inspection at the Waterford Steam Electric Station, Unit 3. A six-person team will perform this inspection using NRC Inspection Procedure 71111.21, "Component Design Bases Inspection." The inspection focuses on components and operator actions that have high risk and low design margins. The samples reviewed during this inspection will be identified during an information gathering visit and during the subsequent in-office preparation week. In addition, a number of operating experience issues will also be selected for review. The inspection will include an information gathering site visit by the team leader and a senior reactor analyst, and 3-weeks of onsite inspection by the team. The inspection will consist of four NRC inspectors, one inspector in training, and two contractors, of which four will focus on engineering and one on operations.
The current inspection schedule is as follows: Onsite information gathering visit: Week of August 22, 2011 Preparation Week: August 29, 2011 Onsite weeks: September, 52011; September 19, 2011; October 3,2011 The purpose of the information gathering visit is to meet with members of your staff to identify potential risk-significant components and operator actions. The lead inspector will also request a tour of the plant with members of your operations staff and probabilistic safety assessment staff. During the onsite weeks, several days of time will be needed on the plant-referenced simulator in order to facilitate the development of operator action-based scenarios.
Additional information and documentation needed to support the inspection will be identified during the inspection, including interviews with engineering managers, engineers, and probabilistic safety assessment staff.
J. Kowaleski -2 -experience with these inspections has shown that they are extremely resource intensive, both for the NRC inspectors and the licensee staff. In order to minimize the inspection impact on the site and to ensure a productive inspection, we have enclosed a request for information needed for the inspection.
The request has been divided into three groups. The first group lists information necessary for the information gathering visit and for general preparation.
This information should be available to the regional office no later than August 15, 2011. Insofar as possible, this information should be provided electronically to the lead inspector.
Since the inspection will be concentrated on high risk/low margin components, calculations associated with your list of high risk components should be available to review during the information gathering visit to assist in our selection of components based on available design margin. The second group of documents requested is those items that the team will need access to during the preparation week in order to finalize the samples to be inspected.
The third group lists information necessary to aid the inspection team in tracking issues identified as a result of the inspection.
It is requested that this information be provided to the lead inspector as the information is generated during the inspection.
Additional requests by inspectors wiii be made throughout aii three onsite weeks for specific documents needed to complete the review of that component/selection.
It is important that all of these documents are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection.
In order to facilitate the inspection, we request that a contact individual be assigned to each inspector to ensure information requests, questions, and concerns are addressed in a timely manner. The lead inspector for this inspection is Wayne C. Sifre. We understand that our licensing engineer contact for this inspection is Billy Steelman.
If there are any questions about the inspection or the requested materials, please contact the lead inspector at (817) 860-8193 or via e-mail at In accordance with 1 0 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at
.. (the Public Electronic Reading Room). Docket: 50-382 License: NPF-38 -r.?t{Z Thomas Farnholtz, Chief Engineering Branch 1 Division of Reactor Safety J. Kowaleski Component Design Basis Inspection Document Request -3 -cc: Distribution via ListServ for Waterford Steam Electric Station, Unit 3 INFORMATION REQUEST FOR WATERFORD ELECTRIC COMPONENT DESIGN BASES (CDBI) INSPECTION Inspection Report: Information Gathering Dates: On-site Inspection Dates: Inspection Procedure:
Lead InspectorlTeam Leader: 05000382/2011007 August 22 -26, 2011 September 6 -9, 2011 September 19 -23, 2011 October 3 -7,2011 IP 71111.21, "Component Design Bases Inspection" Wayne C. Sifre 817-860-8193 VVayne.Sifre@nrc.gov 3 I. Information Requested Prior to the information Gathering Visit (August 22, 2011) The following information (Section I of this enclosure)
should be sent to the Region IV office in hard copy or electronic format (ims.certrec.com or compact disc, preferred), in care of Wayne C. Sifre, by August 15, 2011 to facilitate the reduction in the items to be selected for a final list during the preparation week of August 22. 2011. The inspection team will finalize the selected list during the prep week using the additional documents requested in Section II of this enclosure.
The specific items selected from the lists shall be available and ready for review on the day indicated in this request. *Please provide requested documentation electronically in "pdf" files, Excel, or other searchable formats, if possible.
The information should contain descriptive names, and be indexed and hyperlinked to facilitate ease of use. Information in "lists" should contain enough information to be easily understood by someone who has knowledge of pressurized water reactor technology.
If requested documents are large and only hard copy formats are available, please inform the inspector(s), and provide subject documentation during the first day of the onsite inspection.
1. An excel spreadsheet of equipment basic events (with definitions)
including importance measures sorted by risk achievement worth (RAW) and Vesely (FV) from your internal events probabilistic risk assessment (PRA). Include basic events with RAW value of 1.3 or greater. 2. Provide a list of the top 500 cut-sets from your PRA. ') 1"' __ ;_ ..... _,c no A
_____ "'_1.-__ 1,_ If __ -.I :.1.-_ 1_", __ .1. nn h -. .. __ ,...._. v. vvt-J,t:;;:, v, ;:'Y;:'lt:;111 IIUlt:;UUUI\;:', dilU LIlt:; IdlC;:,t r rv-\ ;:'UI! II Iidl Y document. -1 -Enclosure 4. An spreadsheet PRA or operator actions from your site specific PSA sorted by RAW and Provide copies of your human reliability worksheets for these items. 5. If you have an external events or fire PSA model, provide the information requested in items 1-4 for external events and fire. 6. Any pre-existing evaluation or list of components and associated calculations with low design margins, (i.e., pumps ciosest to the design limit for flow or pressure, diesel generator close to design required output, heat exchangers close to rated design heat removal, etc.). 7. List of high risk maintenance rule systems/components and functions; based on engineering or expert panel judgment.
8. A list of operating experience evaluations for the last 2 years. 9. A list of all time-critical operator actions in procedures.
10. A list of permanent and temporary modifications sorted by component identified in Item 1. 11. List of current "operator work arounds/burdens." 12. A list of the design ca!culations, which provide the design margin information for components included in Item 1. (Calculations should be available during the information gathering visit). 13. List of root cause evaluations associated with component failures or design issues initiated/completed in the last 5 years. 14. Current management and engineering organizational charts. 15. Waterford Steam Electric Station, Unit 3 IPEEE, if available electronically.
16. Mechanical piping drawings for: Engineered safety features Emergency core cooling systems Emergency diesel generators 17. Electrical one-line drawings for: Offsite power/switchyard supplies Normal AC power systems r _______ .. I\. ,",/f""\,", __ *** ___ ** _J. ____
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!::JCII .... Y rlvl LJv fJUWCI :::'Y:::'LCI I I:::' II II,;IUUII l!::l 120VAC power, and 125VDC/24VDC safety class systems 18. List of any common-cause failures of components in the last 3 years. 2 Enclosure 19. An electronic copy of the Design Bases Documents.
20. An electronic copy of the System Health notebooks.
21. System Description Manuals with simplified drawings of plant systems. 22. List of system acronyms.
II. Information Requested to be Available on First Day of Preparation Week (August 29) 1. List of condition reports (corrective action documents)
associated with each of the selected components for the last 5 years. 2. The corrective maintenance history associated with each of the selected components for the last 2 years. 3. Copies of calcuiations associated with each of the selected components (if not previously provided), excluding data files. Please review the calculations and also provide copies of reference material (such as drawings, engineering requests, and vendor letters).
4. Copies of operability evaluations associated with each of the selected components and plans for restoring operability, if applicable.
5. Copies of selected operator work-around evaluations associated with each of the selected components and plans for resolution, if applicable.
6. Copies of any open temporary modifications associated with each of the selected components, if applicable.
7. Trend data on the selected electrical/mechanical components'
performance for last 3 years (for example, pumps' performance including in-service testing, other vibration monitoring, oil sample results, etc., as applicable).
8. A copy of any internal/external self-assessments and associated corrective action documents generated in preparation for the inspection.
9. A copy of engineering/operations related audits completed in the last 2 years. 10. List of motor operated valves (MOVs) in the program, design margin and risk ranking. 11. List of ali oPerated valves (AOVs) in the valve program, design and risk ranking. 12. Structure, system and components in the Maintenance Rule (a)(1) category. -3 -Enclosure 13. Site top 10 issues list. 1 Procedures used to accomplish operator actions associated with the basic events in your PRA. 15. List of licensee contacts for the inspection team with pager or phone numbers. III. Information Requested to be provided throughout the inspection.
1. Copies of any corrective action documents generated as a result of the team's questions or queries during this inspection.
2. Copies of the list of questions submitted by the team members and the status/resolution of the information requested (provide daily during the inspection to each team member). 3. Reference materials (available electronically and as needed during all onsite weeks): General set of plant drawings I PE/PRA report Procurement documents for components selected Plant procedures (normal, abnormal, emergency, surJeiliance, etc.) Technical Specifications Updated Final Safety Analysis Report Vendor manuals Inspector Contact Information:
Wayne C. Sifre Senior Reactor Inspector (817) 817-8193 Wayne.Sifre@nrc.gov Mailing Address: US NRC, Region IV Attn: Wayne C. Sifre 612 East Lamar Blvd, Ste 400 Arlington, TX 76011 -4-Enclosure