ML12080A193

Ltr. 03/19/12 Braidwood Fire Protection Request for Information

ML12080A193
Person / Time
Site:	Braidwood
Issue date:	03/19/2012
From:	Dave Hills NRC/RGN-III/DRS/EB1
To:	Pacilio M Exelon Generation Co, Exelon Nuclear
James Neurauter
References
Download: ML12080A193 (6)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 March 19, 2012 Mr. Michael J. Pacilio Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville IL 60555

SUBJECT:

BRAIDWOOD STATION UNITS 1 AND 2 - NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION

Dear Mr. Pacilio:

On June 25, 2012, the U. S. Nuclear Regulatory Commission (NRC) will begin inspection of refueling and other outage activities (NRC Inspection Procedure 71111.20). This inspection will utilize NRC Operating Experience Smart Sample: (OpESS) FY2007-03, Revision 2, Crane and Heavy Lift Inspection, Supplemental Guidance for IP 71111.20, issued September 12, 2008.

This inspection will focus on the impact of load handling activities on the reactor core and its cooling and plant support systems. Specifically, this inspection will review the upgrade of the containment polar cranes to single-failure-proof equivalency using guidelines developed by the Nuclear Energy Institute (NEI) and contained in NEI 08-05, Industry Initiative on Control of Heavy Loads, Revision 0, and NRC Regulatory Issue Summary 2008-28, Endorsement of Nuclear Energy Institute Guidance for Reactor Vessel Head Heavy Load Lifts, dated December 1, 2008. The on-site inspection is scheduled to take place on June 25-29, 2012, and July 9-13, 2012.

Experience has shown that inspection of these activities is resource intensive both for the NRC inspector and licensee staff. In order to minimize the inspection impact to the site and to ensure a productive inspection for both parties, we have enclosed a request for information needed for the inspection. This information should be available in Region III by June 18, 2012, (preparation week). 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.

The lead inspector for this inspection is Mr. James Neurauter. We understand that our regulatory contact for this inspection is Mr. Murtaza Abbas of your organization. If there are any questions about the inspection or the material requested, please contact the lead inspector at (630) 829-9828 or via e-mail at 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.

M. Pacilio In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77

Enclosure:

REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION DOCUMENT REQUEST cc w/encl: Distribution via ListServ'

REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION DOCUMENT REQUEST Inspection Report: 05000456/2012004; 05000457/2012004 Inspection Dates: June 25-June 29, 2012, and July 9-July 13, 2012 Inspection Procedures: Inspection Procedure (IP) 71111.20, ARefueling and Other Outage Activities@

NRC Operating Experience Smart Sample: (OpESS) FY2007-03, Revision 2, Crane and Heavy Lift Inspection, Supplemental Guidance for IP-71111.20, issued September 12, 2008 (available at NRC Web site at http://www.nrc.gov/reactors/operating/ops-experience/opess/2007/index.html)

Inspector: Jim Neurauter, Senior Reactor Inspector (630) 829-9828 james.neurauter@nrc.gov A. Information Requested for the In-Office Preparation Week The following information (electronic copy CD ROM if possible) is requested to be available at the Region III office on June 18, 2012. If you have any questions regarding this information, please call the inspector as soon as possible.

A copy of the following documents related to heavy load control:

1. For heavy load lifts:

a. Design calculations and site procedures associated with control of heavy loads - safe load paths;

b. Site procedures for removal and installation of the reactor pressure vessel head;

c. Implementation of industry standards related to training and qualification of crane operators;

d. Implementation of industry standards related to use of special lifting devices;

e. Implementation of industry standards related to use of slings;

f. Implementation of industry standards related to the inspection, testing, and maintenance of the polar crane;

g. Implementation of industry standards related to the design of the polar crane; 1 Enclosure

REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION DOCUMENT REQUEST

h. Polar crane vendor recommendations regarding preventative maintenance, and inspections and testing prior to use;

i. Site procedures associated with polar crane preventative maintenance, inspection, and testing prior to lifting the reactor pressure vessel head;

j. Documentation for polar crane preventative maintenance, inspection, and testing performed during last refueling outage prior to lifting the reactor pressure vessel head;

k. Documentation for visual inspections performed prior to use during last refueling outage on lifting device for the reactor pressure vessel head;

l. Site procedures associated with non-destructive examination (NDE) of the load bearing components for the reactor pressure vessel head lifting device; and

m. Documentation for the last NDE performed for all load bearing components of the reactor pressure vessel head lifting device.

2. For reactor vessel head lifts, documentation that establishes use of an equivalent single-failure-proof crane system that bounds the planned lifts with respect to load weight.

a. Completed Engineering Change (EC) for upgrade of polar crane heavy load handling structures, systems, and components to single-failure-proof equivalency;

b. Title 10 CFR 50.59 Evaluation for the upgrade of polar crane heavy load handling structures, systems, and components to single-failure-proof equivalency;

c. Matrix (if performed) that demonstrates the completed EC upgrade to single-failure-proof equivalency is in compliance with Nuclear Energy Institute (NEI) 08-05, Industry Initiative on Control of Heavy Loads,@ Revision 0 (ADAMS Accession No. ML082180666) and the NRC Staff Safety Evaluation addressing NEI 08-05 (ADAMS Accession No. ML082410532);

d. Documents that establish the crane total lifted weight for movement of the reactor pressure vessel head;

e. Design calculations for the reactor pressure vessel head lifting device; and

f. Design calculations for interfacing lift points, i.e., reactor pressure vessel head lifting lugs.

2 Enclosure

REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION DOCUMENT REQUEST

3. Documentation that demonstrates movement of heavy loads is treated as a configuration management activity in administrative controls established to implement Paragraph (a)(4) of 10 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants.

4. UFSAR description of heavy load handling program (or UFSAR Change document).

5. A copy of the Braidwood UFSAR.

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

3 Enclosure

M. Pacilio In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77

Enclosure:

REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION DOCUMENT REQUEST cc w/encl: Distribution via ListServ' DISTRIBUTION:

RidsNrrDorlLpl3-2 Resource Breeda Reilly RidsNrrPMBraidwood Resource RidsNrrDirsIrib Resource Chuck Casto Cynthia Pederson Jennifer Uhle Steven Orth Jared Heck Allan Barker DRPIII DRSIII Carole Ariano Linda Linn Patricia Buckley Tammy Tomczak DOCUMENT NAME: G:\DRSIII\DRS\Work in Progress\Ltr 031912 Braidwood Request for Information jen.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 JNeurauter:ls DHills DATE 03/19/12 03/19/12 OFFICIAL RECORD COPY