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| issue date = 04/29/2015
| issue date = 04/29/2015
| title = Ltr 04/29/15 Prairie Island Nuclear Generating Plant, Units 1 and 2, Request for Information for an NRC Triennial Baseline Component Design Bases Inspection (CDBI) Inspection Report 05000282/2015007; 05000306/2015007 (Jen)
| title = Ltr 04/29/15 Prairie Island Nuclear Generating Plant, Units 1 and 2, Request for Information for an NRC Triennial Baseline Component Design Bases Inspection (CDBI) Inspection Report 05000282/2015007; 05000306/2015007 (Jen)
| author name = Lipa C A
| author name = Lipa C
| author affiliation = NRC/RGN-III/DRS/EB2
| author affiliation = NRC/RGN-III/DRS/EB2
| addressee name = Davison K
| addressee name = Davison K
Line 14: Line 14:
| page count = 8
| page count = 8
}}
}}
See also: [[followed by::IR 05000282/2015007]]
See also: [[see also::IR 05000282/2015007]]


=Text=
=Text=

Revision as of 00:13, 21 June 2019

Ltr 04/29/15 Prairie Island Nuclear Generating Plant, Units 1 and 2, Request for Information for an NRC Triennial Baseline Component Design Bases Inspection (CDBI) Inspection Report 05000282/2015007; 05000306/2015007 (Jen)
ML15121A651
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 04/29/2015
From: Christine Lipa
NRC/RGN-III/DRS/EB2
To: Davison K
Northern States Power Co
References
IR 2015007
Download: ML15121A651 (8)


See also: IR 05000282/2015007

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION III 2443 WARRENVILLE RD. SUIT

E 210 LISLE, IL 60532

-4352 April 29, 2015 Mr. Kevin Davison

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 0500 0 282/20 1 5007; 05000 306/20 1 5007 Dear M r. Davison: On August 3, 2015, the U. S. Nuclear Regulatory Commission (NRC) will begin a

triennial baseline Component Design Bases Inspection (CDBI) at

Prairie Island Nuclear Generating Plant, Units 1 and 2.

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. The CDBI focuses on the design, maintenance, and operation of risk

-significant components

associated with one or more accident scenari o or systems. 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 you

r 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

3 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:

August 3-7, 2015; August 1 7-21, 2015; and August 31-September 4, 2015.

The team will be preparing for the inspection, mainly during the week of

July 27-31, 2015, as discussed in the attached enclosure.

K. Davison

-2- Experience with previous baseline design inspections of similar depth and length has shown that th is 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. 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

June 23, 2015.

By July 10, 2015, the lead inspector will communicate the initial selected set of approximately

15 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

July 22, 2015.

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 August 3, 2015.

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

James Neurauter.

We understand that our licensing contact for this inspection is

Benjamin Hammargren of your organization. If there are any questions about the inspection or the material requested in the enclosure, please contact the lead inspector at (630) 829

-9828 or via e-mail a t James.Neurauter@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.

K. Davison

-3- In accordance with Title 10 of the Code of Federal Regulations

(10 CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding," of the NRC's "Rules of Practice," a copy

of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS)

component of the NRC's Agencywide

Documents Access and Management 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 Andrew Dunlop Acting for/

Christine A. Lipa , Chie f Engineering Branch 2

Division of Reactor Safety

Docket No s. 50-282; 50-306 License No

s. D PR-42; D P R-60 Enclosure:

Information Request for Component Design Bases Inspection (CDBI)

cc w/encl: Distribution via LISTSERV

INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION (CDBI)

Enclosure Inspection Report:

05000 282/20 1 5007; 05000 306/20 1 5007 Inspection Dates:

August 3-7, 2015; August 17-21, 2015; and August 31-September 4, 2015

. Inspection Procedure:

IP 71111.21 "Component Design Bases Inspection"

Lead Inspector:

James Neurauter

, Senior Reactor Engineer, DRS

(630) 829-9828 James.Neurauter@nrc.gov

I. Information Requested Prior to the On

-site Information Gathering/Inspection Week

The following information is requested by June 23, 2015 , 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 t

op 2 50 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 (i.e. Large Early Release Frequency

[LERF]) from your site specific PSA sorted by

RAW. 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 P

S A 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). 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)

.

INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION (CDBI)

2 9. Electronic copy of the site Individual Plant Examination of External Events (IPEEE), if available.

10. 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.). 11. 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.

12. List of high

-risk Maintenance Rule systems/components based on engineering

or expert panel judgment

(i.e., those systems/components not identified in the

P S A). 13. Structures, systems, and components (SSCs) in the Maintenance Rule (a)(1) category for the last

3 years. 14. Site top ten issues list (if applicable)

. 15. A list of operating experience evaluations for the last

3 years. 16. Information of any common cause failure of components experienced in the last 5 years at your facility

. 17. List of Root Cause Evaluations associated with component failures or design

issues initiated/completed in the last

5 years. 18. List of open operability evaluations.

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

20. Current management and engineering organizational chart

. 21. Electronic copies of Updated Final Safety Analysis Report, Technical Specifications, Technical Specifications Bases, and Technical Requirements Manual. 22. Major o ne line electrical drawings (ac and dc) and key diagrams (paper copies).

23. Electronic copy of Piping and Instrumentation Drawing

s (P&IDs) (if available).

II. Information Requested (for the approximate 15 selected components) to be

Available by

July 22, 2015 , (will be reviewed by the team in the Regional office during the week of

July 27-31, 2015). 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

.).

INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION (CDBI)

3 1. List of condition reports (corrective action documents) associated with each of the selected components for the last

6 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). Pipe stress calculations

are excluded from this request

4. System Health Reports, System Descriptions, Design Basis Documents, and/or Training Lesson Plans 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 3 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 3 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. Provide copies of the normal and abnormal operating procedures associated with the selected components

and selected scenarios

. 11. A copy of any internal/external self

-assessments and associated corrective action documents generated in preparation for the inspection

. 12. Copy of latest completed tests and surveillances for each component

, for example: Pumps: comprehensive test, quarterly test, flow balance, etc.

Valves: stroke time testing, diagnostic testing, leak testing, interlocks, etc. Heat Exchangers/room coolers

thermal performance, clean/inspect, fan flows, etc.

Acceptance criteria basis calculations should also be included.

INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION (CDBI)

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

III. Additional Information to be

Provided on August 3, 2015

, On-Site (for final selected components)

1. 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 July 27-31, 2015. 2. Schedule of any testing/maintenance activities to be conducted on the selected components during the three onsite inspection weeks.

IV. 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. One complete set of P&IDs (paper copies)

. 4. Reference materials. (make available if needed during all on

-site weeks):

Individual Plant Examination

/Probabilistic Risk Assessment

(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.

K. Davison

-3- In accordance with Title 10 of the Code of Federal Regulations

(10 CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding," of the NRC's "Rules of Practice," a copy

of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS)

component of the NRC's Agencywide

Documents Access and Management 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 Andrew Dunlop Acting for

/

Christine A. Lipa, Chie f Engineering Branch 2

Division of Reactor Safety

Docket No s. 50-282; 50-306 License No

s. DPR-42; DPR-60 Enclosure:

Information Request for Component Design Bases Inspection (CDBI)

cc w/encl: Distribution via LISTSERV DISTRIBUTION

w/encl: Kimyata MorganButler

RidsNrrPMPrairieIsland Resource

RidsNrrDorlLpl3-1 Resource

RidsNrrDirsIrib Resource

Cynthia Pederson

Darrell Roberts

Richard Skokowski

Allan Barker

Carole Ariano

Linda Linn

DRPIII DRSIII Jim Clay Carmen Olteanu

ADAMS Accession Number ML15121A651

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 RIII RIII NAME JNeurauter:cl

ADunlop for CLipa DATE 04/29/15 04/29/15 OFFICIAL RECORD COP

Y