ML082880346

Notification of NRC Inspection and Request for Information

ML082880346
Person / Time
Site:	Perry
Issue date:	10/14/2008
From:	Dave Hills NRC/RGN-III/DRS/EB1
To:	Bezilla M FirstEnergy Nuclear Operating Co
References
Download: ML082880346 (4)

Text

October 14, 2008 Mr. Mark Bezilla Site Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant P. O. Box 97, 10 Center Road, A-PY-290 Perry, OH 44081-0097

SUBJECT:

PERRY NUCLEAR POWER PLANT - NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION

Dear Mr. Bezilla:

On December 1, 2008, the NRC will begin inspection of refueling and other outage activities (NRC Inspection Procedure 71111.20) prior to the 2009 refueling outage scheduled for the Perry Nuclear Power Plant. This inspection will utilize NRC Operating Experience Smart Sample: (OpESS) FY 2007-03, 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 applicable design and licensing bases, engineering design and analysis, procedures, and surveillances associated with the reactor vessel head removal and installation during refueling outages including: (1) Containment building crane preventative maintenance, inspections and testing; (2) reactor vessel head rigging equipment; (3) reactor vessel head drop analysis; and (4) reactor vessel head safe load paths. The on-site inspection is scheduled to take place on December 1, 2008 through December 5, 2008, and December 15 through December 19, 2008.

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 November 24, 2008, (preparatory 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.

We have discussed the schedule for these inspection activities with your staff and understand that our regulatory contact for this inspection will be Mr. K. Russell, of your organization. If there are any questions about this inspection or the material requested, please contact the inspector, Mr. J. Bozga, at (630) 829-9613.

M. Bezilla In accordance with 10 CFR 2.390 of the NRC's 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 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/

David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-440 License No. NPF-58

Enclosure:

Refueling and Other Outage Activities Inspection Document Request cc w/encl: J. Hagan, President and Chief Nuclear Officer - FENOC J. Lash, Senior Vice President of Operations and Chief Operating Officer - FENOC D. Pace, Senior Vice President, Fleet Engineering - FENOC J. Rinckel, Vice President, Fleet Oversight - FENOC P. Harden, Vice President, Nuclear Support Director, Fleet Regulatory Affairs - FENOC Manager, Fleet Licensing - FENOC Manager, Site Regulatory Compliance - FENOC D. Jenkins, Attorney, FirstEnergy Corp.

Public Utilities Commission of Ohio C. OClaire, State Liaison Officer, Ohio Emergency Management Agency R. Owen, Ohio Department of Health

M. Bezilla In accordance with 10 CFR 2.390 of the NRC's 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 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/

David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-440 License No. NPF-58

Enclosure:

Refueling And Other Outage Activities Inspection Document Request cc w/encl: J. Hagan, President and Chief Nuclear Officer - FENOC J. Lash, Senior Vice President of Operations and Chief Operating Officer - FENOC D. Pace, Senior Vice President, Fleet Engineering - FENOC J. Rinckel, Vice President, Fleet Oversight - FENOC P. Harden, Vice President, Nuclear Support Director, Fleet Regulatory Affairs - FENOC Manager, Fleet Licensing - FENOC Manager, Site Regulatory Compliance - FENOC D. Jenkins, Attorney, FirstEnergy Corp.

Public Utilities Commission of Ohio C. OClaire, State Liaison Officer, Ohio Emergency Management Agency R. Owen, Ohio Department of Health DOCUMENT NAME: G:\DRS\Work in Progress\Ltr 10___08 Perry Request for Information JVB.doc 9 Publicly Available 9 Non-Publicly Available 9 Sensitive 9 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 NAME JBozga:ls KRiemer for JCameron DHills DATE 10/14/08 10/14/08 10/14/08 OFFICIAL RECORD COPY

Letter to Mr. Mark Bezilla from Mr. David E. Hills dated October 14, 2008.

SUBJECT:

PERRY NUCLEAR POWER PLANT - NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION DISTRIBUTION:

Russell Gibbs; Tamara Bloomer Cameron Goodwin RidsNrrDirsIrib Resource Mark Satorius Kenneth Obrien Jared Heck Carole Ariano Linda Linn DRPIII DRSIII Patricia Buckley Tammy Tomczak ROPreports@nrc.gov

INITIAL DOCUMENT REQUEST Inspection Dates: December 1 through December 5, and December 15 through December 19, 2008 Inspection Procedures: IP 71007, Reactor Vessel Head Replacement Inspection IP 71111.20, Refueling and Other Outage Activities Inspector: John V. Bozga (630) 829-9613 A. Information Requested for the In-Office Preparation Week The following information (paper copy if practicable, unless otherwise indicated) is requested to be available in Region III on November 24, 2008. If you have any questions regarding this information, please call the inspector as soon as possible.

1. A copy of the following documents related heavy load control during removal or installation of the reactor vessel head:

a. Perry submittals as a result of NRC December 22, 1980, unnumbered Generic Letter (GL) (now NRC numbered as GL 80-113) and GL 81-07, Control of Heavy Loads regarding NUREG-0612, Control of Heavy Loads at Nuclear Power Plants, six month response (Phase I) and nine month response (Phase II).

b. Reactor head drop analysis associated with above Phase II submittals, if applicable.

c. Perry corrective action program reports related to NRC Regulatory Issue Summary 2005-25, Clarification of NRC Guidelines for Control of Heavy Loads, NRC Regulatory Issue Summary 2005-25, Supplement I Clarification of NRC Guidelines for Control of Heavy Loads, Enforcement Guidance Memorandum 2007-006, Enforcement Discretion for Heavy Load Handling Activities, and Nuclear Energy Institute 08-05, Industry Initiative on Control of Heavy Loads.

d. Current reactor head drop analysis (if different from Phase II submittals) or single failure proof crane/equivalency evaluation.

e. Other supporting documents that demonstrate equipment to maintain safe shutdown will be unaffected (i.e., calculations associated with the reactor head drop analysis) and that potential offsite releases at the exclusion boundary will be within 10 CFR Part 100 limits after a postulated reactor vessel head drop.

f. Calculations for rigging and special lifting devices associated with lifting the reactor vessel head.

1 Enclosure

INITIAL DOCUMENT REQUEST

g. Documents that establish the total lift weight for the existing reactor vessel head.

h. Site procedures associated with Control of Heavy Loads, removal of the reactor vessel head during refueling operations, installation of the reactor vessel head during refueling operations, and any contingency actions taken to mitigate the consequences of a postulated reactor vessel head drop.

i. Containment building crane vendor recommendations regarding preventative maintenance, and inspection, and testing prior to use.

j. Site procedures associated with Containment building crane preventative maintenance, inspection, and testing prior to lifting the reactor vessel head.

k. Documentation for Containment building crane preventative maintenance, inspection, and testing performed during last refueling outage prior to lifting the reactor vessel head.

2. An electronic copy of the Perry UFSAR.

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

2 Enclosure