ML12348A621

Ltr. 12/13/12 Prairie Island CDBI Request for Information

ML12348A621
Person / Time
Site:	Prairie Island
Issue date:	12/13/2012
From:	Ann Marie Stone NRC/RGN-III/DRS/EB2
To:	Jeffery Lynch Northern States Power Co
Benny Jose
References
IR-13-007
Download: ML12348A621 (8)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 December 13, 2012 Mr. Jim Lynch Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company, Minnesota 1717 Wakonade Drive East Welch, MN 55089

SUBJECT:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2; REQUEST FOR INFORMATION FOR AN NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION (CDBI) INSPECTION REPORT 05000282/2013007; 05000306/2013007(DRS)

Dear Mr. Lynch:

On March 18, 2013, the U.S. Nuclear Regulatory Commission (NRC) will begin a triennial baseline Component Design Bases Inspection (CDBI) at Prairie Island Nuclear Generating Plant. A team of six inspectors will perform this 3-week inspection. This inspection will be performed in accordance with NRC Baseline Inspection Procedure (IP) 71111.21. In addition, as previously discussed, the inspectors will also conduct a portion of Inspection Procedure 71111.07T, Heat Sink Performance.

The CDBI focuses on the design, maintenance, and operation of risk significant components associated with one or more accident scenario. The components to be reviewed during this baseline inspection will be identified during the in office preparation week that occurs prior to the first on-site inspection week. In addition, operating experience issues, associated with the component samples, will also be selected for review. The inspection team may request scenarios to be performed on the simulator. This request would require support from your simulator staff to validate scenarios, simulator time, and a crew to perform the actions, which would most likely occur during the second on-site week. The team will work closely with your staff early on during the inspection process to ensure this activity can be accomplished with minimal impact.

The inspection will include three weeks on-site. The inspection team will consist of six NRC inspectors, of which five will focus on engineering/maintenance and one on operations. The current inspection schedule is as follows:

• On-site weeks: March 18 - 22, 2013; April 1 - 5, 2013; and April 15 - 19, 2013.

The team will be preparing for the inspection, mainly during the week of March 11, 2013, as discussed in the attached enclosure.

Experience with previous baseline design inspections of similar depth and length has shown that this type of inspection is 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 for both parties, we have enclosed a request for information needed for the inspection.

J. Lynch 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 on-site portions of the inspection. Insofar as possible, this information should be provided electronically to the lead inspector. The information request has been divided into three groups:

• The first group lists information necessary for our initial inspection scoping activities.

This information should be provided to the lead inspector no later than February 11, 2013. By February 24, 2013, the lead inspector will communicate the initial selected set of approximately 20 components.

• The second group of documents requested is those items needed to support our in-office preparation activities. This set of documents, including the calculations associated with the initial selected components, should be provided to the lead inspector at the Regional Office no later than March 4, 2013. During the in-office preparation activities, the team may identify additional information needed to support the inspection.

• The last group includes the additional information above, as well as plant specific reference material. This information should be available to the team onsite on March 18, 2013. It is also requested that corrective action documents and/or questions developed during the inspection be provided to the lead inspector as the documents are generated.

The lead inspector for this inspection is Benny Jose. We understand that our licensing contact for this inspection is Mr. Frank Sienczak of your organization. If there are any questions about the inspection or the materials requested in the enclosure, please contact the lead inspector at (630) 829-9756 or via e-mail at benny.jose@nrc.gov.

This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, control number 3150-0011.

The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number.

J. Lynch 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 Publicly Available Records (PARS) component of NRCs document system (ADAMS),

accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Ann Marie Stone, Chief Engineering Branch 2 Division of Reactor Safety Docket No. 50-282; 50-306 License No. DPR-42; DPR-60

Enclosure:

Information Request for Component Design Bases Inspection cc w/encl: Distribution via ListServ'

INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION Inspection Report: 05000282/2013007; 05000306/2013007(DRS)

Inspection Dates: March 18 - 22, 2013; April 1 - 5, 2013; and April 15 - 19, 2013 Inspection Procedures: Inspection Procedure 71111.21 Component Design Bases Inspection Inspection Procedure 71111.07T Heat Sink Performance (limited portion)

Lead Inspector: Benny Jose (630) 829-9756 benny.jose@nrc.gov I. Information Requested Prior to the On-site Information Gathering/Inspection Week The following information is requested by February 11, 2013, or sooner, to facilitate inspection preparation. If you have any questions regarding this information, please call the team leader as soon as possible. (Please provide the information electronically in pdf files, Excel, or other searchable formats, preferably on some portable electronic media (e.g., CDROM, DVD, flash drive, etc.). The portable electronic media 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 light water reactor technology).

1. Risk-ranking of top 250 components from your site specific probabilistic safety analysis (PSA) sorted by Risk-Achievement Worth (RAW). Include values for Birnbaum Importance, Risk-Reduction Worth (RRW), and Fussell-Veseley (FV) (as applicable).

2. Risk-ranking of top 100 containment-related components from your site specific PSA sorted by Large Early Release Frequency (LERF).

3. Provide a list of the top 200 cut-sets from your PSA.

4. Provide a list of the top 100 cut-sets for each initiator modeled in the PSA that contributes more than 5 percent to the baseline plant core damage frequency (CDF).

5. Copies of PSA system notebooks and latest PSA summary document.

6. List of time critical operator actions. Identify those actions that do not have job performance measures (JPMs).

7. Provide copies of the emergency operating procedures (EOPs).

1 Enclosure

INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION

8. If you have an External Events or Fire PSA Model, provide the information requested in Items 1 and 2 for external events and fire. Provide narrative description of each coded event (including fire, flood zone description). Electronic copy of the site IPEEE, if available.

9. 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.).

10. List of available design (setup) margins in both the open and closed direction (identify safety-related direction) for valves in the motor-operated valve (MOV) and air-operated valve (AOV) programs. Identify the basis for how the margin was determined.

11. List of high risk Maintenance Rule systems/components based on engineering or expert panel judgment (i.e., those systems/components not identified in the PRA).

12. Structures, systems, and components (SSCs) in the Maintenance Rule (a)(1) category for the last 3 years.

13. Site top ten issues list (if applicable).

14. A list of operating experience evaluations for the last three years.

15. Information of any common cause failure of components experienced in the last 5 years at your facility.

16. List of Root Cause Evaluations associated with component failures or design issues initiated/completed in the last 5 years.

17. List of open operability evaluations.

18. List of components/systems considered operable but degraded/nonconforming.

19. Current management and engineering organizational chart.

20. Electronic copies of Updated Final Safety Analysis Report, Technical Specifications, Technical Specifications Bases, and Technical Requirements Manual.

21. Major one line electrical drawings (ac and dc) and key diagrams (paper copies).

22. Electronic copy of P&IDs (if available)

23. CDBR project status (brief summary of issues identified, which systems are complete and which systems are currently being looked into).

2 Enclosure

INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION II. Information Requested (For The Approx. 20 Selected Components) to be Available By March 4, 2013, (Will Be Reviewed by the Team in the Regional Office During the Week of March 11, 2013)

This information should be separated for each selected component, especially if provided electronically (e.g., folder with component name that includes calculations, condition reports, maintenance history, etc.).

1. List of condition reports (corrective action documents) associated with each of the selected components/systems for the last 4 years.

2. The maintenance history (corrective, preventive, and elective) associated with each of the selected components for the last 10 years. Identify frequency of preventive maintenance activities.

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 important referenced material (such as drawings, engineering requests, and vendor letters).

4. System Health Reports, System Descriptions, Design Basis Documents, and/or Training Lesson Plans that are associated with each of the selected components.

5. A list of modifications, including equivalency evaluations and setpoint changes, associated with each of the selected components. This list should include a descriptive paragraph on the purpose of the modification. Please ensure this list only includes design completed (not canceled) modifications.

6. Copies of operability evaluations (open/closed for last three years) associated with each of the selected components and plans for restoring operability, if applicable.

7. Copies of selected operator work-around evaluations associated with each of the selected components and plans for resolution, if applicable.

8. Copies of any open temporary modifications associated with each of the selected components, if applicable.

9. Trend data on the selected electrical/mechanical components performance for last three years, (For example, pumps performance including in-service testing, other vibration monitoring, oil sample results, etc., for valves: stroke time and leak rate results, etc.).

10. Copy of latest completed surveillance tests for each component, (for example, for pumps this would include: comprehensive test, quarterly test, flow balance, etc., for valves: stroke time testing, diagnostic testing, leak testing, etc.). Acceptance criteria basis calculations should also be included.

11. Provide copies of the normal and abnormal operating procedures associated with the selected components and selected scenarios.

3 Enclosure

INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION

12. A copy of any internal/external self-assessments and associated corrective action documents generated in preparation for the inspection.

13. A copy of engineering/operations related audits completed in the last 2 years.

III. Additional Information to be Provided on March 18, 2013, On-Site (for final selected Components)

During the in-office preparation activities, the team will be making final selections and may identify additional information needed to support the inspection. The lead inspector will provide a list of the additional information needed during the week of March 11, 2013.

IV. Information Requested to be Provided throughout the Inspection

1. Copies of any corrective action documents generated as a result of the teams 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. One complete set of P&IDs (paper copies).

4. Reference materials. (make available if needed during all on-site weeks):

• IPE/PRA report;

• Procurement documents for components selected (verify retrievable);

• Plant procedures (normal, abnormal, emergency, surveillance, etc.); and

• Vendor manuals.

If you have questions regarding the information requested, please contact the lead inspector 4 Enclosure

J. Lynch 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 Publicly Available Records (PARS) component of NRCs document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Ann Marie Stone, Chief Engineering Branch 2 Division of Reactor Safety Docket No. 50-282; 50-306 License No. DPR-42; DPR-60

Enclosure:

Information Request for Component Design Bases Inspection cc w/encl: Distribution via ListServ' DISTRIBUTION:

Cayetano Santos RidsNrrPMPrairieIsland Resource RidsNrrDorlLpl3-1 Resource RidsNrrDirsIrib Resource Chuck Casto Cynthia Pederson Steven Orth Jared Heck Allan Barker Christine Lipa Carole Ariano Linda Linn DRPIII DRSIII Tammy Tomczak DOCUMENT NAME: G:\DRSIII\DRS\Work in Progress\Ltr 121312 PRA 2013007 CDBI RFI BXJ.docx Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII RIII NAME BJose:ls AMStone DATE 12/13/12 12/13/12 OFFICIAL RECORD COPY