ML083570174
| ML083570174 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 12/16/2008 |
| From: | Thomas Farnholtz Region 4 Engineering Branch 1 |
| To: | Douet J Entergy Operations |
| References | |
| IR-09-006 | |
| Download: ML083570174 (8) | |
See also: IR 05000416/2009006
Text
December 16, 2008
James R. Douet, Vice President of Operations
Grand Gulf Nuclear Station Entergy Operations, Inc. P.O. Box 756 Port Gibson, MS 39150
SUBJECT: GRAND GULF NUCLEAR STATION
- INFORMATION REQUEST FOR NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION NRC INSPECTION REPORT 05000416/2009006
Dear Mr. Douet:
On February 2, 2009, the NRC will begin a triennial baseline Component Design Bases
Inspection at the Grand Gulf Nuclear Station. A seven-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
seven NRC inspectors, of which six will focus on engineering and one on operations. The current inspection schedule is as follows:
Onsite information gathering visit: Week of January 19, 2009 Onsite weeks: February 2, February 16, and February 23, 2009
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. Additional information and documentation needed to support the inspection will be identified, including interviews with engineering managers, engineers, and probabilistic safety assessment staff.
Our experience with these inspections has shown 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 UNITED STATESNUCLEAR REGULATORY COMMISSIONREGION IV612 E. LAMAR BLVD., SUITE 400ARLINGTON, TEXAS 76011-4125
Entergy Operations, Inc. - 2 -
information should be available to the regional office no later than January 27, 2009. 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 are those items that the team will need access to when onsite and after the inspection samples are selected. 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. It is important that all of these documents are up to date and completed 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 Mr. Ronald A. Kopriva. We understand that our licensing engineer contact for this inspection is Mr. Dennis Coulter. If there are any questions about the inspection or the requested materials, please contact the lead inspector at (817) 860-8104 or via e-mail at ron.kopriva@nrc.gov. In accordance with 10 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 http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely, /RA/
Thomas Farnholtz, Chief Engineering Branch 1 Division of Reactor Safety
Docket: 50-416 License: NPF-29
Enclosure: Information Request For Grand Gulf Plant Component Design Bases Inspection.
cc w/enclosure Senior Vice President Entergy Nuclear Operations
P.O. Box 31995 Jackson, MS 39286-1995
Entergy Operations, Inc. - 3 -
Senior Vice President and COO Entergy Operations, Inc. P.O. Box 31995
Jackson, MS 39286-1995
Vice President, Oversight Entergy Services, Inc. P.O. Box 31995
Jackson, MS 39286-1995
Chief, Energy and Transportation Branch Environmental Compliance and Enforcement Division Mississippi Department of Environmental Quality
P.O. Box 10385 Jackson, MS 39289-0385
President Claiborne County
Board of Supervisors P.O. Box 339 Port Gibson, MS 39150
Senior Manager
Nuclear Safety & Licensing Entergy Nuclear Operations P.O. Box 31995 Jackson, MS 39286-1995
Manager, Licensing Entergy Operations, Inc. Grand Gulf Nuclear Station P.O. Box 756 Port Gibson, MS 39150
Attorney General Department of Justice
State of Louisiana P.O. Box 94005 Baton Rouge, LA 70804-9005
Office of the Governor
State of Mississippi Jackson, MS 39201
Attorney General Asst. Attorney General State of Mississippi P.O. Box 22947
Jackson, MS 39225-2947
State Health Officer State Health Board P.O. Box 1700
Jackson, MS 39215
Associate General Counsel Entergy Nuclear Operations P.O. Box 31995
Jackson, MS 39286-1995
Richard Penrod, Senior Environmental Scientist/State Liaison Officer Office of Environmental Services
Northwestern State University Russell Hall, Room 201 Natchitoches, LA 71497
Entergy Operations, Inc. - 4 -
Electronic distribution by RIV: Regional Administrator (Elmo.Collins@nrc.gov ) DRP Director (Dwight.Chamberlain@nrc.gov ) DRP Deputy Director (Anton.Vegel@nrc.gov ) DRS Director (Roy.Caniano@nrc.gov ) DRS Deputy Director (Troy.Pruett@nrc.gov ) Senior Resident Inspector (Rich.Smith@nrc.gov ) Resident Inspector (Andy.Barrett@nrc.gov ) Branch Chief, DRP/C (Geoffrey.Miller@nrc.gov ) Senior Project Engineer, DRP/C (Wayne.Walker@nrc.gov
GG Site Secretary (Nancy.Spivey@nrc.gov ) Public Affairs Officer (Victor.Dricks@nrc.gov ) Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov ) RITS Coordinator (Marisa.Herrera@nrc.gov) RC/ACES (Karla.Fuller@nrc.gov ) C. A. Carpenter, OE Cynthia.Carpenter@nrc.gov
OEMAIL.Resource@nrc.gov
Senior Enforcement Specialist (Mark.Haire@nrc.gov) Only inspection reports to the following:
DRS STA (Dale.Powers@nrc.gov ) Mark Cox, OEDO RIV Coordinator (Mark.Cox@nrc.gov )
SUNSI Review Completed: _ __ ADAMS: Yes No Initials: _RAK
_ Publicly Available Non-Publicly Available Sensitive Non-Sensitive R:\_REACTORS\GG\2009\GG2009-006RFI-RAK.doc ML SRI:DRS/EB1 C:DRS/EB1
RAKopriva TFarnholtz
/RA/ /RA/ 12/16/08 12/16/08 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
- 1 - Enclosure INFORMATION REQUEST FOR GRAND GULF NUCLEAR STATION COMPONENT DESIGN BASES INSPECTION (CDBI)
Inspection Report: 05000416/2009006
Information Gathering Dates: January 21-23, 2009
On-site Inspection Dates: February 2-6, 2009 and February 16-27, 2009
Inspection Procedure: IP 71111.21, "Component Design Bases Inspection"
Lead Inspector/Team Leader: Ronald A. Kopriva 817-860-8104
Ron.Kopriva@nrc.gov
I. Information Requested Prior to the information Gathering Visit
The following information is requested by January 27, 2009, or sooner, to facilitate inspection preparation. If you have any questions regarding this
information, pleased call the lead inspector as soon as possible. (Please provide the information electronically in "pdf" files, Excel, or other searchable formats. 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 boiling
water reactor technology).
1. An excel spreadsheet of equipment basic events (with definitions) including importance measures sorted by risk achievement worth (RAW)
and Fussell-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.
3. Copies of PRA "system notebooks," and the latest PRA summary document.
4. An excel spreadsheet of PRA human action basic events or risk ranking of operator actions from your site specific PSA sorted by RAW and FV. 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.
- 2 - Enclosure 6. Any pre-existing evaluation or list of components and associated calculations with low design margins, (i.e., pumps closest 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 calculations, 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. Grand Gulf Nuclear Station Plant 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
Emergency ac/dc power systems including 120Vac power, and 125Vdc/24Vdc safety class systems
18. List of any common-cause failures of components in the last 3 years.
19. An electronic copy of the Design Bases Documents.
20. An electronic copy of the System Health notebooks.
- 3 - Enclosure
II. Information Requested to be Available on First Day of Inspection (February 2, 2009) 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 calculations 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 air operated valves (AOVs) in the valve program, design and risk ranking. 12. Structure, system and components in the Maintenance Rule (a)(1) category.
13. Site top 10 issues list.
14. 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.
- 4 - Enclosure 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 IPE/PRA report Procurement documents for components selected Plant procedures (normal, abnormal, emergency, surveillance, etc.) Technical Specifications Updated Final Safety Analysis Report
Vendor manuals
Inspector Contact Information
Ronald A. Kopriva Senior Reactor Inspector (817) 860-8104 Ron.Kopriva@nrc.gov
Mailing Address
- US NRC, Region IV Attn: Ronald A. Kopriva 612 East Lamar Blvd., Ste 400 Arlington, TX 76011