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| issue date = 07/31/2006 | | issue date = 07/31/2006 | ||
| title = Ltr. 07/31/06 D.C. Cook Nuclear Power Plant Unit 1, Request for Information | | title = Ltr. 07/31/06 D.C. Cook Nuclear Power Plant Unit 1, 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 = Nazar M | | addressee name = Nazar M | ||
| addressee affiliation = Indiana Michigan Power Co, Nuclear Generation Group | | addressee affiliation = Indiana Michigan Power Co, Nuclear Generation Group | ||
| docket = 05000315 | | docket = 05000315 | ||
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=Text= | =Text= | ||
{{#Wiki_filter:July 31, | {{#Wiki_filter:July 31, 2006 Mr. M. Nazar Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 | ||
==SUBJECT:== | ==SUBJECT:== | ||
D.C. COOK NUCLEAR POWER PLANT UNIT 1 INFORMATION | D.C. COOK NUCLEAR POWER PLANT UNIT 1 INFORMATION REQUEST FOR NRC REACTOR VESSEL HEAD REPLACEMENT INSPECTION | ||
==Dear Mr. Nazar:== | ==Dear Mr. Nazar:== | ||
On September 5, 2006, the NRC will begin the modification portion of the reactor vessel | On September 5, 2006, the NRC will begin the modification portion of the reactor vessel head replacement inspection (NRC Inspection Procedure 71007) for the D. C. Cook Nuclear Power Plant, Unit 1 at the Buchanan, Michigan office. This inspection will also utilize NRC Inspection Procedures IP 7111.02, IP 71111.17, and IP 71111.23. The on-site inspection is scheduled to take place on September 5 through September 8, 2006, September 25 through September 29, 2006, and October 10 through October 13, 2006. | ||
/RA/David E. Hills, | Experience has shown that this inspection is resource intensive, both for the NRC inspector and your staff. In order to minimize the impact to your on-site resources and to ensure a productive inspection for both sides, we have enclosed a request for documents needed for this inspection. These documents have been divided into two groups. The first group identifies information necessary to ensure that the inspector is adequately prepared. The lead inspector has scheduled a trip to the Buchanan, Michigan office on August 14 through August 17, 2006, to review the first group of information, request documents for review in the Regional Office prior to the on-site inspection, and to request documents to be available at the Buchanan, Michigan office on September 5, 2006, the first day of the on-site inspection. The second group identifies additional information the inspector will need upon arrival at the Buchanan, Michigan offices on September 5, 2006. 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. R. Meister, of your organization. If there are any questions about this inspection or the material requested, please contact the lead 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 | |||
M. Nazar Room, or from the Publicly Available Records (PARS) component of NRC's 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/ | |||
David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-315 License No. DPR-58 | |||
==Enclosure:== | ==Enclosure:== | ||
REACTOR VESSEL HEAD REPLACEMENT INSPECTION | REACTOR VESSEL HEAD REPLACEMENT INSPECTION DOCUMENT REQUEST cc w/encl: J. Jensen, Site Vice President L. Weber, Plant Manager G. White, Michigan Public Service Commission L. Brandon, Michigan Department of Environmental Quality - | ||
Waste and Hazardous Materials Division Emergency Management Division MI Department of State Police State Liaison Officer, State of Michigan D. Lochbaum, Union of Concerned Scientists M. Nazar | Waste and Hazardous Materials Division Emergency Management Division MI Department of State Police State Liaison Officer, State of Michigan D. Lochbaum, Union of Concerned Scientists | ||
M. Nazar Room, or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). | |||
Sincerely, David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-315 License No. DPR-58 | |||
==Enclosure:== | ==Enclosure:== | ||
REACTOR VESSEL HEAD REPLACEMENT INSPECTION | REACTOR VESSEL HEAD REPLACEMENT INSPECTION DOCUMENT REQUEST cc w/encl: J. Jensen, Site Vice President L. Weber, Plant Manager G. White, Michigan Public Service Commission L. Brandon, Michigan Department of Environmental Quality - | ||
Waste and Hazardous Materials Division Emergency Management Division MI Department of State Police State Liaison Officer, State of Michigan D. Lochbaum, Union of Concerned | Waste and Hazardous Materials Division Emergency Management Division MI Department of State Police State Liaison Officer, State of Michigan D. Lochbaum, Union of Concerned Scientists ADAMS Distribution: | ||
JLD PST RidsNrrDirsIrib GEG KGO BJK1 CAA1 DRPIII DRSIII PLB1 TXN ROPreports@nrc.gov DOCUMENT NAME:E:\Filenet\ML062140128.wpd G Publicly Available G Non-Publicly Available G Sensitive G 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: ls CLipa DHills DATE 07/27/06 07/27/06 07/31/06 OFFICIAL RECORD COPY | |||
REACTOR VESSEL HEAD REPLACEMENT INSPECTION DOCUMENT REQUEST Inspection Dates: September 5 - October 13, 2006 Inspection Procedures: IP 71002, Reactor Vessel Head Replacement inspection IP 71111.02, Evaluation of Changes, Tests, or Experiments IP 71111.17, Permanent Plant Modifications IP 71111.23, Temporary Plant Modifications Inspector: Jim Neurauter Reactor Inspector (630) 829-9828 jen@nrc.gov 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 Buchanan, Michigan office on August 14, 2006, to facilitate the selection of specific items that will be reviewed during the on-site inspection week. The inspector will select specific items from the information requested below and request a list of additional documents needed for the on-site inspection weeks to your staff. We request that the specific items selected from the lists be available and ready for review on September 5, 2006, the first day of inspection. If you have any questions regarding this information, please call the inspector as soon as possible. | |||
: 1) A detailed description of permanent plant modifications and temporary plant modifications associated with the Unit 1 reactor vessel head replacement. | |||
: 2) A list of D. C. Cook generated corrective action reports, design change requests, field change requests, and non-conformance reports associated with the Unit 1 reactor vessel head replacement project. | |||
: 3) A list of Design Specifications and Design Reports associated with the Unit 1 reactor vessel head replacement. | |||
: 4) A list of supporting documents (i.e., design and fabrication drawings, calculations, ASME Code reconciliations, non-conformance, and deviation reports) for Design Reports associated with the Unit 1 reactor vessel head replacement. | |||
: 5) A list of design calculations for permanent and temporary modifications that facilitate the Unit 1 reactor vessel head replacement. | |||
: 6) A copy of the following documents related heavy load control during removal of the old reactor vessel head and installation of the replacement reactor vessel head: | |||
a) D. C. Cook submittals as a result of NRC December 22, 1980, generic letter (GL) (unnumbered) 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); | |||
1 Enclosure | |||
b) D. C. Cook corrective action report that evaluated NRC Regulatory Issue Summary 2005-25, Clarification of NRC Guidelines for Control of Heavy Loads; c) Current reactor head drop analysis (WCAPs). Where applicable, other supporting documentation that demonstrates equipment to maintain safe shutdown will be unaffected and potential offsite releases at the exclusion boundary will be within 10 CFR part 100 limits; d) Calculations for rigging and special lifting devices associated with the replacement reactor vessel head; e) Documents that establish the lift weight for the existing reactor vessel head and the replacement reactor vessel head; f) 10 CFR 50.59 screening and/or evaluation associated with a postulated reactor head drop for the replacement reactor vessel head; and g) Procedure ES-MECH-0908-QCN, Control of Heavy Loads. | |||
8)Copy of procedures related to 10 CFR 50.59 evaluations and screenings.B.Information to be provided on-site to the inspector following the entrance meeting (September 5, 2006):1)Copy of all 10 CFR 50.59 evaluations and screenings associated with the Unit | : 7) An electronic copy of the D. C. Cook UFSAR. | ||
8)Current management and engineering organizational chart.9)Schedule when inspector can verify replacement reactor vessel head has ASME | : 8) Copy of procedures related to 10 CFR 50.59 evaluations and screenings. | ||
B. Information to be provided on-site to the inspector following the entrance meeting (September 5, 2006): | |||
: 1) Copy of all 10 CFR 50.59 evaluations and screenings associated with the Unit 1 reactor vessel head replacement. | |||
: 2) Copy of Design Specifications and Design Reports associated with the Unit 1 reactor vessel head replacement. | |||
: 3) Copy of ASME Section III certifications for registered professional engineers that certified Design Specifications and Design Reports were in accordance with ASME Section III requirements. | |||
: 4) Copy of fracture toughness test reports for the replacement reactor vessel head material that demonstrate compliance with ASME Code and Design Specification requirements. | |||
: 5) Copy of documents selected from Section A during lead inspector August 14 - | |||
August 17, 2006 bag trip. | |||
: 6) ASME Code used for replacement reactor vessel head design, fabrication and testing, 1995 Edition with 1996 Addenda. | |||
2 Enclosure | |||
: 7) Name(s) and phone numbers for the regulatory and technical contacts. | |||
: 8) Current management and engineering organizational chart. | |||
: 9) Schedule when inspector can verify replacement reactor vessel head has ASME NPT stamp. | |||
3 Enclosure}} |
Latest revision as of 16:40, 23 November 2019
ML062140128 | |
Person / Time | |
---|---|
Site: | Cook ![]() |
Issue date: | 07/31/2006 |
From: | Dave Hills NRC/RGN-III/DRS/EB1 |
To: | Nazar M Indiana Michigan Power Co, Nuclear Generation Group |
References | |
Download: ML062140128 (6) | |
Text
July 31, 2006 Mr. M. Nazar Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106
SUBJECT:
D.C. COOK NUCLEAR POWER PLANT UNIT 1 INFORMATION REQUEST FOR NRC REACTOR VESSEL HEAD REPLACEMENT INSPECTION
Dear Mr. Nazar:
On September 5, 2006, the NRC will begin the modification portion of the reactor vessel head replacement inspection (NRC Inspection Procedure 71007) for the D. C. Cook Nuclear Power Plant, Unit 1 at the Buchanan, Michigan office. This inspection will also utilize NRC Inspection Procedures IP 7111.02, IP 71111.17, and IP 71111.23. The on-site inspection is scheduled to take place on September 5 through September 8, 2006, September 25 through September 29, 2006, and October 10 through October 13, 2006.
Experience has shown that this inspection is resource intensive, both for the NRC inspector and your staff. In order to minimize the impact to your on-site resources and to ensure a productive inspection for both sides, we have enclosed a request for documents needed for this inspection. These documents have been divided into two groups. The first group identifies information necessary to ensure that the inspector is adequately prepared. The lead inspector has scheduled a trip to the Buchanan, Michigan office on August 14 through August 17, 2006, to review the first group of information, request documents for review in the Regional Office prior to the on-site inspection, and to request documents to be available at the Buchanan, Michigan office on September 5, 2006, the first day of the on-site inspection. The second group identifies additional information the inspector will need upon arrival at the Buchanan, Michigan offices on September 5, 2006. 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. R. Meister, of your organization. If there are any questions about this inspection or the material requested, please contact the lead 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
M. Nazar Room, or from the Publicly Available Records (PARS) component of NRC's 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/
David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-315 License No. DPR-58
Enclosure:
REACTOR VESSEL HEAD REPLACEMENT INSPECTION DOCUMENT REQUEST cc w/encl: J. Jensen, Site Vice President L. Weber, Plant Manager G. White, Michigan Public Service Commission L. Brandon, Michigan Department of Environmental Quality -
Waste and Hazardous Materials Division Emergency Management Division MI Department of State Police State Liaison Officer, State of Michigan D. Lochbaum, Union of Concerned Scientists
M. Nazar Room, or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely, David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-315 License No. DPR-58
Enclosure:
REACTOR VESSEL HEAD REPLACEMENT INSPECTION DOCUMENT REQUEST cc w/encl: J. Jensen, Site Vice President L. Weber, Plant Manager G. White, Michigan Public Service Commission L. Brandon, Michigan Department of Environmental Quality -
Waste and Hazardous Materials Division Emergency Management Division MI Department of State Police State Liaison Officer, State of Michigan D. Lochbaum, Union of Concerned Scientists ADAMS Distribution:
JLD PST RidsNrrDirsIrib GEG KGO BJK1 CAA1 DRPIII DRSIII PLB1 TXN ROPreports@nrc.gov DOCUMENT NAME:E:\Filenet\ML062140128.wpd G Publicly Available G Non-Publicly Available G Sensitive G 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: ls CLipa DHills DATE 07/27/06 07/27/06 07/31/06 OFFICIAL RECORD COPY
REACTOR VESSEL HEAD REPLACEMENT INSPECTION DOCUMENT REQUEST Inspection Dates: September 5 - October 13, 2006 Inspection Procedures: IP 71002, Reactor Vessel Head Replacement inspection IP 71111.02, Evaluation of Changes, Tests, or Experiments IP 71111.17, Permanent Plant Modifications IP 71111.23, Temporary Plant Modifications Inspector: Jim Neurauter Reactor Inspector (630) 829-9828 jen@nrc.gov 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 Buchanan, Michigan office on August 14, 2006, to facilitate the selection of specific items that will be reviewed during the on-site inspection week. The inspector will select specific items from the information requested below and request a list of additional documents needed for the on-site inspection weeks to your staff. We request that the specific items selected from the lists be available and ready for review on September 5, 2006, the first day of inspection. If you have any questions regarding this information, please call the inspector as soon as possible.
- 1) A detailed description of permanent plant modifications and temporary plant modifications associated with the Unit 1 reactor vessel head replacement.
- 2) A list of D. C. Cook generated corrective action reports, design change requests, field change requests, and non-conformance reports associated with the Unit 1 reactor vessel head replacement project.
- 3) A list of Design Specifications and Design Reports associated with the Unit 1 reactor vessel head replacement.
- 4) A list of supporting documents (i.e., design and fabrication drawings, calculations, ASME Code reconciliations, non-conformance, and deviation reports) for Design Reports associated with the Unit 1 reactor vessel head replacement.
- 5) A list of design calculations for permanent and temporary modifications that facilitate the Unit 1 reactor vessel head replacement.
- 6) A copy of the following documents related heavy load control during removal of the old reactor vessel head and installation of the replacement reactor vessel head:
a) D. C. Cook submittals as a result of NRC December 22, 1980, generic letter (GL) (unnumbered) 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);
1 Enclosure
b) D. C. Cook corrective action report that evaluated NRC Regulatory Issue Summary 2005-25, Clarification of NRC Guidelines for Control of Heavy Loads; c) Current reactor head drop analysis (WCAPs). Where applicable, other supporting documentation that demonstrates equipment to maintain safe shutdown will be unaffected and potential offsite releases at the exclusion boundary will be within 10 CFR part 100 limits; d) Calculations for rigging and special lifting devices associated with the replacement reactor vessel head; e) Documents that establish the lift weight for the existing reactor vessel head and the replacement reactor vessel head; f) 10 CFR 50.59 screening and/or evaluation associated with a postulated reactor head drop for the replacement reactor vessel head; and g) Procedure ES-MECH-0908-QCN, Control of Heavy Loads.
- 7) An electronic copy of the D. C. Cook UFSAR.
- 8) Copy of procedures related to 10 CFR 50.59 evaluations and screenings.
B. Information to be provided on-site to the inspector following the entrance meeting (September 5, 2006):
- 1) Copy of all 10 CFR 50.59 evaluations and screenings associated with the Unit 1 reactor vessel head replacement.
- 2) Copy of Design Specifications and Design Reports associated with the Unit 1 reactor vessel head replacement.
- 3) Copy of ASME Section III certifications for registered professional engineers that certified Design Specifications and Design Reports were in accordance with ASME Section III requirements.
- 4) Copy of fracture toughness test reports for the replacement reactor vessel head material that demonstrate compliance with ASME Code and Design Specification requirements.
- 5) Copy of documents selected from Section A during lead inspector August 14 -
August 17, 2006 bag trip.
- 6) ASME Code used for replacement reactor vessel head design, fabrication and testing, 1995 Edition with 1996 Addenda.
2 Enclosure
- 7) Name(s) and phone numbers for the regulatory and technical contacts.
- 8) Current management and engineering organizational chart.
- 9) Schedule when inspector can verify replacement reactor vessel head has ASME NPT stamp.
3 Enclosure