ML043650263
| ML043650263 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/30/2004 |
| From: | Dave Hills NRC/RGN-III/DRS/MEB |
| To: | Solymossy J Nuclear Management Co |
| References | |
| Download: ML043650263 (6) | |
Text
December 30, 2004 Mr. Joseph Solymossy Site Vice-President Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East Welch, MN 55089
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 - NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Solymossy:
On April 18, 2005, the NRC will begin an inspection of the replacement reactor vessel head preservice and design related records (NRC Procedure 71007, Reactor Vessel Head Replacement Inspection) at the Prairie Island Nuclear Generating Plant, Unit 2. This on-site inspection is scheduled to be performed beginning the week of April 18, 2005, and is scheduled to conclude on May 20, 2005.
It is expected that this inspection will be 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. 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 inspection. These documents are needed by the inspector upon arrival at the site on April 18, 2005.
We have discussed the detailed schedule for these inspection activities with Mr. G. Salamon of your staff and understand that our regulatory contact for this inspection will be Mr. J. Kivi of your organization. If there are any questions about this inspection or the material requested, please contact the inspector, Mr. Mel Holmberg, at (630) 829-9748.
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
J. Solymossy 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 Materials Engineering Branch Division of Reactor Safety Docket Nos. 50-306 License Nos. DPR-60
Enclosure:
HEAD REPLACEMENT DESIGN AND PRESERVICE INSPECTION DOCUMENT REQUEST cc w/encl:
C. Anderson, Senior Vice President, Group Operations J. Cowan, Executive Vice President and Chief Nuclear Officer Regulatory Affairs Manager J. Rogoff, Vice President, Counsel & Secretary Nuclear Asset Manager Tribal Council, Prairie Island Indian Community Administrator, Goodhue County Courthouse Commissioner, Minnesota Department of Commerce Manager, Environmental Protection Division Office of the Attorney General of Minnesota
J. Solymossy 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 Materials Engineering Branch Division of Reactor Safety Docket Nos. 50-306 License Nos. DPR-60
Enclosure:
HEAD REPLACEMENT DESIGN AND PRESERVICE INSPECTION DOCUMENT REQUEST cc w/encl:
C. Anderson, Senior Vice President, Group Operations J. Cowan, Executive Vice President and Chief Nuclear Officer Regulatory Affairs Manager J. Rogoff, Vice President, Counsel & Secretary Nuclear Asset Manager Tribal Council, Prairie Island Indian Community Administrator, Goodhue County Courthouse Commissioner, Minnesota Department of Commerce Manager, Environmental Protection Division Office of the Attorney General of Minnesota ADAMS Distribution:
DFT MLC RidsNrrDipmIipb GEG HBC KGO JTA DRPIII DRSIII PLB1 JRK1 DOCUMENT NAME: E:\\Filenet\\ML043650263.wpd 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 NAME MHolmberg:tr DPassehl DHills DATE 12/28/04 12/28/04 12/30/04 OFFICIAL RECORD COPY
Enclosure 1
VESSEL HEAD INSPECTION DOCUMENT REQUEST Inspection Dates:
April 18, 2005, through May 20, 2005 Inspection Procedures:
IP 71007, Reactor Vessel Head Replacement Inspection Inspector:
Mel Holmberg (630) 829-9748 A.
Information Requested for the In-Office Preparation Week The following information (electronic copy if practicable - msh@nrc.gov) is requested by April 4, 2005, 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 on-site to your staff.
We request that the specific items selected from the lists be available and ready for review on the first day of inspection. All information requests relate to Unit 2 unless otherwise stated. If you have any questions regarding this information, please call the inspector as soon as possible.
(1)
List of plant modifications which have/will be implemented to support replacement of the reactor vessel head, control rod drive housings or head upgrade package and issue date for each document. In addition to the list, please provide a brief (one paragraph) description of each modification and a list of associated calculations and affected procedures.
(2)
List (with short description) of corrective action documents (CAPs, vendor or quality assurance condition reports, nonconformance reports, deviation notices, or findings) associated with the design of the replacement reactor vessel head, control rod drive housings, or head upgrade package.
(3)
List of all 10 CFR 50.59 completed evaluations involving: (a) changes to the facility (modifications) to support head replacement; (b) procedure revisions to support reactor head replacement; (c) tests or non-routine operating configurations as a result of head replacement; or (d) changes to the USFAR or technical specification bases due to vessel head replacement.
The list should contain the number and title of each document, issue date (or scheduled issue date), and the corresponding number and type of the affected document (i.e., the modification or procedure to which the evaluation applies).
The list should NOT include any evaluations in which prior NRC approval was sought and obtained.
(4)
List of all 10 CFR 50.59 changes that have been screened out as not requiring a full evaluation involving the same information discussed in request 2.
The list should contain the number and title of each document, issue date (or scheduled issue date), and the corresponding number and type of the affected document (i.e., the modification or procedure to which the evaluation applies).
Enclosure 2
(5)
List (with short description) of any modifications, procedure revisions, or UFSAR changes associated with vessel head replacement where it was determined that 10 CFR 50.59 did not apply.
(6)
List (with short description) of corrective action documents (open and closed) related to 10 CFR 50.59 issues, concerns, or processes for the replacement reactor vessel head (including head upgrade package).
(7)
List (with short description) of the ASME Code,Section XI required pre-service examinations associated with the replacement reactor vessel closure head or control rod drive mechanism housings and head upgrade package. Also, identify each preservice examination record in which a Code relevant condition was detected and identify the document which resolved this condition.
(8)
List (with short description) of corrective action documents (CAPs, vendor or quality assurance condition reports, nonconformance reports, deviation notices or findings) associated with the preservice examinations of the replacement reactor vessel head, control rod drive housings or head upgrade package.
(9)
List (with short description) of the vessel head J-groove weld volumetric and surface examinations which may be used to as pre-service records (e.g., to compare with inservice examinations) for future head examinations as required by NRC Order EA 03-009. Also, identify each J-groove weld examination record in which a Code relevant condition was detected and identify the document which resolved this condition.
(10)
List (with short description) of the design specification(s) and design report(s) for the modifications supporting the reactor vessel head replacement.
(11)
List of the professional engineers who certified each design specification and design report supporting the reactor vessel head replacement. Also, provide the documentation required by the ASME Code to support qualification of these engineers.
(12)
List of ASME Code,Section XI reconciliation report(s) (with short description) associated with the reactor vessel head replacement.
(13)
Name(s) and phone numbers for the regulatory and technical contacts supporting this inspection.
B.
Information To be Provided at the Entrance Meeting The following information is requested to be provided to the inspector at the entrance meeting on April 18, 2005. If some of the requested information is not available by this date, please identify the dates when this information will be provided to the inspector. If you have any questions regarding this information, please call the inspector as soon as possible.
Enclosure 3
(1)
Copies of items selected from the lists of documents in Section I as identified by the inspectors. As a minimum this will include copies of the head replacement and head upgrade package modifications and associated safety evaluations or safety evaluation screenings.
(2)
Copy of the ASME Code,Section XI reconciliation report(s) associated with the reactor vessel head replacement or head upgrade packages.
(3)
Copy of the as-built fabrication drawing(s) for the replacement head and head upgrade package.
(4)
Copy of the Code Data Report(s) for the replacement head and head upgrade package(s) which confirms that the head meets applicable design requirements and was certified by a professional engineer. This documentation should include confirmation that the original vessel N-stamp remains valid and may include rubbings taken of the NPT stamp on the replacement head. Additionally, a copy of the hydrostatic test records for the replacement vessel head.
(5)
Copy of the Design Specifications for the original and replacement head and head upgrade package certified by a professional engineer. Copy of the Certified Design Report(s) reconciling the design changes and changes in Code requirements for the replacement head (e.g., Code Reconciliation reports).
(6)
Copies of Section XI replacement head pre-service examination records including pre-service volumetric examination records for the penetration nozzle-to-head welds which may be used as baseline inspections for subsequent examinations required by NRC Order EA-03-009.
(7)
Copies of completed fabrication process sheets or other records which specified the required pre-service examination records performed on-site or at the vendors fabrication facility.
(8)
Copy available (in resident inspector office) of the applicable Edition/Addenda for the ASME Code, Sections II, III, V, IX, XI and Code Cases used in design and fabrication of the replacement head.
(9)
Copy available (in resident inspector office) of the ASTM Standards for material specifications used in the replacement head.