ML071700620: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
(2 intermediate revisions by the same user not shown) | |||
Line 2: | Line 2: | ||
| number = ML071700620 | | number = ML071700620 | ||
| issue date = 06/18/2007 | | issue date = 06/18/2007 | ||
| title = | | title = Notification of NRC Inspection and Request for Information | ||
| author name = Hills D | | author name = Hills D | ||
| author affiliation = NRC/RGN-III/DRS/EB1 | | author affiliation = NRC/RGN-III/DRS/EB1 | ||
| addressee name = Bezilla M | | addressee name = Bezilla M | ||
| addressee affiliation = FirstEnergy Nuclear Operating Co | | addressee affiliation = FirstEnergy Nuclear Operating Co | ||
| docket = 05000346 | | docket = 05000346 | ||
Line 15: | Line 15: | ||
=Text= | =Text= | ||
{{#Wiki_filter:June 18, | {{#Wiki_filter:June 18, 2007 Mr. Mark B. Bezilla Site Vice President FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449-9760 | ||
==SUBJECT:== | ==SUBJECT:== | ||
DAVIS-BESSE NUCLEAR POWER | DAVIS-BESSE NUCLEAR POWER STATION NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION | ||
==Dear Mr. Bezilla:== | ==Dear Mr. Bezilla:== | ||
On July 9, 2007, the NRC will begin inspection of refueling and other outage activities(NRC Inspection Procedure 71111.20) prior to the 2007 refueling outage scheduled for the Davis-Besse Nuclear Power Station. Specifically, this inspection will review applicable | On July 9, 2007, the NRC will begin inspection of refueling and other outage activities (NRC Inspection Procedure 71111.20) prior to the 2007 refueling outage scheduled for the Davis-Besse Nuclear Power Station. 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) polar 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. | ||
This inspection will focus on the impact of load handling activities on the reactor core, and its cooling and plant support systems. This inspection will also utilize NRC Inspection Procedure (IP) 71007. The on-site inspection is scheduled to take place on July 9 through 13, 2007, and July 23 through 27, 2007.Experience has shown that inspection of these activities is resource intensive both for the | This inspection will focus on the impact of load handling activities on the reactor core, and its cooling and plant support systems. This inspection will also utilize NRC Inspection Procedure (IP) 71007. The on-site inspection is scheduled to take place on July 9 through 13, 2007, and July 23 through 27, 2007. | ||
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 on-site by July 9, 2007, (on-site 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. G. Wolfe, of your organization. If there are any questions about this inspection or the material requested, please contact the inspector, Mr. J. Neurauter, at (630) 829-9828. | |||
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 | |||
M. Bezilla (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 No. 50-346 License No. NPF-3 | |||
==Enclosure:== | ==Enclosure:== | ||
REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION | REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION DOCUMENT REQUEST cc w/encl: The Honorable Dennis Kucinich J. Hagan, President and Chief Nuclear Officer - FENOC J. Lash, Senior Vice President of Operations and Chief Operating Officer Richard Anderson, Vice President, Nuclear Support Manager - Site Regulatory Compliance D. Pace, Senior Vice President of of Fleet Engineering J. Rinckel, Vice President, Fleet Oversight D. Jenkins, Attorney, FirstEnergy Director, Fleet Regulatory Affairs Manager - Fleet Licensing Ohio State Liaison Officer R. Owen, Administrator, Ohio Department of Health Public Utilities Commission of Ohio President, Lucas County Board of Commissioners President, Ottawa County Board of Commissioners | ||
M. Bezilla (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 No. 50-346 License No. NPF-3 | |||
==Enclosure:== | ==Enclosure:== | ||
REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION | REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION DOCUMENT REQUEST cc w/encl: The Honorable Dennis Kucinich J. Hagan, President and Chief Nuclear Officer - FENOC J. Lash, Senior Vice President of Operations and Chief Operating Officer Richard Anderson, Vice President, Nuclear Support Manager - Site Regulatory Compliance D. Pace, Senior Vice President of of Fleet Engineering J. Rinckel, Vice President, Fleet Oversight D. Jenkins, Attorney, FirstEnergy Director, Fleet Regulatory Affairs Manager - Fleet Licensing Ohio State Liaison Officer R. Owen, Administrator, Ohio Department of Health Public Utilities Commission of Ohio President, Lucas County Board of Commissioners President, Ottawa County Board of Commissioners DOCUMENT NAME: | ||
To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE RIII C RIII N RIII N NAME JNeurauter BBurgess DHills 06/18/07 06/18/07 06/18/07 OFFICIAL RECORD COPY | |||
M. Bezilla Letter to Mr. Mark Bezilla from Mr. David Hills June 18, 2007. | |||
==SUBJECT:== | ==SUBJECT:== | ||
DAVIS-BESSE NUCLEAR POWER | DAVIS-BESSE NUCLEAR POWER STATION NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION DISTRIBUTION: | ||
RAG1 TEB SPS1 TJW2 RidsNrrDirsIrib GEG KGO JER7 CAA1 DRPIII DRSIII PLB1 TXN | |||
REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION DOCUMENT REQUEST Inspection Dates: July 9 through 13 and July 23 through 27, 2007 Inspection Procedures: IP 71007, Reactor Vessel Head Replacement Inspection IP 71111.20, Refueling and Other Outage Activities Inspector: Jim Neurauter (630) 829-9828 A. Information Requested for the In-Office Preparation Week The following information (paper copy if practicable, unless otherwise indicated) is requested to be available at the Davis-Besse Nuclear Power Station on July 9, 2007. If you have any questions regarding this information, please call the inspector as soon as possible. | |||
1 A copy of the following documents related to heavy load control during removal or installation of the reactor vessel head: | |||
: a. Davis-Besse 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. Davis-Besse corrective action report that evaluated NRC Regulatory Issue Summary 2005-25, Clarification of NRC Guidelines for Control of Heavy Loads. | |||
: d. Current reactor head drop analysis, if different from Phase II submittals. | |||
: 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 | |||
REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION 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. | |||
REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION DOCUMENT | : i. Polar crane vendor recommendations regarding preventative maintenance, and inspections and testing prior to use. | ||
: j. Site procedures associated with polar crane preventative maintenance, inspection, and testing prior to lifting the reactor vessel head. | |||
: k. Documentation for polar crane preventative maintenance, inspection, and testing performed during last refueling outage prior to lifting the reactor vessel head. | |||
: 2. An electronic copy of the Davis-Besse UFSAR. | |||
2 Enclosure}} |
Latest revision as of 06:15, 23 November 2019
ML071700620 | |
Person / Time | |
---|---|
Site: | Davis Besse ![]() |
Issue date: | 06/18/2007 |
From: | Dave Hills NRC/RGN-III/DRS/EB1 |
To: | Bezilla M FirstEnergy Nuclear Operating Co |
References | |
Download: ML071700620 (6) | |
Text
June 18, 2007 Mr. Mark B. Bezilla Site Vice President FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449-9760
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Bezilla:
On July 9, 2007, the NRC will begin inspection of refueling and other outage activities (NRC Inspection Procedure 71111.20) prior to the 2007 refueling outage scheduled for the Davis-Besse Nuclear Power Station. 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) polar 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.
This inspection will focus on the impact of load handling activities on the reactor core, and its cooling and plant support systems. This inspection will also utilize NRC Inspection Procedure (IP) 71007. The on-site inspection is scheduled to take place on July 9 through 13, 2007, and July 23 through 27, 2007.
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 on-site by July 9, 2007, (on-site 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. G. Wolfe, of your organization. If there are any questions about this inspection or the material requested, please contact the inspector, Mr. J. Neurauter, at (630) 829-9828.
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
M. Bezilla (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 No. 50-346 License No. NPF-3
Enclosure:
REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION DOCUMENT REQUEST cc w/encl: The Honorable Dennis Kucinich J. Hagan, President and Chief Nuclear Officer - FENOC J. Lash, Senior Vice President of Operations and Chief Operating Officer Richard Anderson, Vice President, Nuclear Support Manager - Site Regulatory Compliance D. Pace, Senior Vice President of of Fleet Engineering J. Rinckel, Vice President, Fleet Oversight D. Jenkins, Attorney, FirstEnergy Director, Fleet Regulatory Affairs Manager - Fleet Licensing Ohio State Liaison Officer R. Owen, Administrator, Ohio Department of Health Public Utilities Commission of Ohio President, Lucas County Board of Commissioners President, Ottawa County Board of Commissioners
M. Bezilla (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 No. 50-346 License No. NPF-3
Enclosure:
REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION DOCUMENT REQUEST cc w/encl: The Honorable Dennis Kucinich J. Hagan, President and Chief Nuclear Officer - FENOC J. Lash, Senior Vice President of Operations and Chief Operating Officer Richard Anderson, Vice President, Nuclear Support Manager - Site Regulatory Compliance D. Pace, Senior Vice President of of Fleet Engineering J. Rinckel, Vice President, Fleet Oversight D. Jenkins, Attorney, FirstEnergy Director, Fleet Regulatory Affairs Manager - Fleet Licensing Ohio State Liaison Officer R. Owen, Administrator, Ohio Department of Health Public Utilities Commission of Ohio President, Lucas County Board of Commissioners President, Ottawa County Board of Commissioners DOCUMENT NAME:
To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE RIII C RIII N RIII N NAME JNeurauter BBurgess DHills 06/18/07 06/18/07 06/18/07 OFFICIAL RECORD COPY
M. Bezilla Letter to Mr. Mark Bezilla from Mr. David Hills June 18, 2007.
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION DISTRIBUTION:
RAG1 TEB SPS1 TJW2 RidsNrrDirsIrib GEG KGO JER7 CAA1 DRPIII DRSIII PLB1 TXN
REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION DOCUMENT REQUEST Inspection Dates: July 9 through 13 and July 23 through 27, 2007 Inspection Procedures: IP 71007, Reactor Vessel Head Replacement Inspection IP 71111.20, Refueling and Other Outage Activities Inspector: Jim Neurauter (630) 829-9828 A. Information Requested for the In-Office Preparation Week The following information (paper copy if practicable, unless otherwise indicated) is requested to be available at the Davis-Besse Nuclear Power Station on July 9, 2007. If you have any questions regarding this information, please call the inspector as soon as possible.
1 A copy of the following documents related to heavy load control during removal or installation of the reactor vessel head:
- a. Davis-Besse 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. Davis-Besse corrective action report that evaluated NRC Regulatory Issue Summary 2005-25, Clarification of NRC Guidelines for Control of Heavy Loads.
- d. Current reactor head drop analysis, if different from Phase II submittals.
- 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
REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION 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. Polar crane vendor recommendations regarding preventative maintenance, and inspections and testing prior to use.
- j. Site procedures associated with polar crane preventative maintenance, inspection, and testing prior to lifting the reactor vessel head.
- k. Documentation for polar crane preventative maintenance, inspection, and testing performed during last refueling outage prior to lifting the reactor vessel head.
- 2. An electronic copy of the Davis-Besse UFSAR.
2 Enclosure