ML042310137
| ML042310137 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/18/2004 |
| From: | Dave Hills NRC/RGN-III/DRS/MEB |
| To: | Solymossy J Nuclear Management Co |
| References | |
| Download: ML042310137 (7) | |
Text
August 18, 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 PLANT, UNIT 1 NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Solymossy:
On September 13, 2004, the NRC will begin the baseline inservice inspection (NRC Procedure 71111.08) at the Prairie Island Nuclear Plant, Unit 1. This inspection will also include a review of your activities associated with examination of the lower reactor pressure vessel head and penetration nozzles in accordance with NRC Temporary Instruction 2515/152 and a review of activities associated with Steam Generator replacement in accordance with Inspection Procedure 50001. This on-site inspection is scheduled to be performed September 13 through October 22, 2004.
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 second group identifies the information the inspector will need upon arrival at the site. 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 onsite 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 J. Kivi, of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector, Mr. Bob Daley at (630) 829-9749.
In accordance with 10 CFR 2.390 of the NRCs "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 NRCs
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 Hills, Chief Materials Engineering Branch Division of Reactor Safety Docket Nos. 50-282 License Nos. DPR-42
Enclosure:
INSERVICE 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 Hills, Chief Materials Engineering Branch Division of Reactor Safety Docket Nos. 50-282 License Nos. DPR-42
Enclosure:
INSERVICE 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 JTA DRPIII DRSIII PLB1 JRK1 DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML042310137.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 N
NAME RDaley:tr MShuaibi DHills DATE 08/17/04 08/18/04 08/18/04 OFFICIAL RECORD COPY
Enclosure 1
INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates:
September 13 through October 22, 2004.
Inspection Procedures:
IP 50001, Steam Generator Replacement Inspection IP 7111108, Inservice Inspection TI 2515/152, Reactor Pressure Vessel Lower Head Penetration Nozzles (NRC BULLETIN 2003-02)
Inspector:
Bob Daley (630) 829-9749 A.
Information Requested for the In-Office Preparation Week The following information (electronic copy if practicable - RCD@nrc.gov) is requested by September 6, 2004, to facilitate the selection of specific items that will be reviewed during the onsite 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 1 unless otherwise stated. If you have any questions regarding this information, please call the inspector as soon as possible.
1)
A detailed schedule of nondestructive examinations (NDE) planned for Class 1 and 2 systems and containment, performed as part of your ASME Code ISI Program during the scheduled inspection weeks. Provide a detailed schedule of vessel head examinations (upper and lower) which fulfill NRC commitments made in response to NRC Order EA-03-009 and NRC Bulletin 2003-02. Provide a detailed schedule of the steam generator (SG) replacement activities for the upcoming outage.
2)
A copy of the NDE procedures used to perform the examinations identified in A.1 (including calibration and flaw characterization/sizing procedures). For ultrasonic examination procedures qualified in accordance with Appendix VIII, of Section XI of the ASME Code, provide documentation supporting the procedure qualification (e.g., the EPRI performance demonstration qualification summary sheets). Also, include documentation of the specific equipment to be used (e.g., ultrasonic unit, cables, and transducers including serial numbers).
3)
A copy of any ASME Section XI, Code Relief Requests applicable to the examinations identified in A(1).
4)
A list identifying NDE reports (ultrasonic, radiography, magnetic particle, dye penetrant, visual (VT-1, VT-2, VT-3)) which have identified relevant indications on Code Class 1 and 2 systems in the past two refueling outages. Provide records accepting any relevant indications for continued service. Also, identify the NDE examinations with recorded indications in the vessel head penetration nozzles which have been accepted for continued service.
Enclosure 2
5)
List with short description of the welds in Code Class 1 and 2 systems which have been completed since the beginning of the last refueling outage and identify system, weld number and reference applicable documentation.
6)
List with short description of ASME Code repairs or replacements which have been completed since the beginning of the last outage.
7)
If reactor vessel weld examinations required by the ASME Code are scheduled to occur during the inspection period, provide a detailed description of the welds to be examined, and the extent of the planned examination.
8)
List with description of ISI (e.g., piping degradation or damage) entered into your corrective action system beginning with the date of the last refueling outage (both Units).
9)
Copy of any 10 CFR Part 21 reports applicable to your structures systems or components within the scope of Section XI of the ASME Code, that have been identified since the beginning of the last refueling outage.
10)
Provide the detailed scope of the planned NDE of the vessel head which identifies the types of NDE methods to be used on each specific part of the vessel head to fulfill NRC commitments made in response to NRC Order EA-03-009 and NRC Bulletin 2003-02.
Also include examination scope expansion criteria and planned expansion sample sizes if relevant indications are identified.
11)
Identify what standards or requirements will be used to evaluate indications identified during NDE examinations of the vessel head. Provide the specific industry or procedural standards which will be used to evaluate potential leakage indications on the upper head and lower vessel heads.
12)
Copies of correspondence and commitments made to the NRC for performing vessel head examinations under NRC Order EA-03-009 and NRC Bulletin 2003-02.
13)
Copies of procedures for welding and NDE associated with Steam Generator replacement.
B.
Information to be provided on-site to the inspector at the entrance meeting:
1)
For welds selected by the inspector from A.5 above, provide copies of the following documents:
a)
Document of the weld number and location (e.g., system, train, branch);
b)
Document with a detail of the weld construction; c)
Applicable Code Edition and Addenda for weldment; d)
Applicable Code Edition and Addenda for welding procedures; e)
Applicable weld procedures (WPS) used to fabricate the welds; f)
Copies of procedure qualification records (PQRs) supporting the WPS on selected welds; g)
Copies of mechanical test reports identified in the PQRs above;
Enclosure 3
h)
Copies of the nonconformance reports for the selected welds; i)
Radiographs of the selected welds and access to equipment to allow viewing radiographs; and j)
Copies of the preservice examination records for the selected welds.
2)
For the repair/replacement activities selected by the inspector from A.6 above, provide a copy of the records of the repair or replacement required by the ASME Code Section XI Articles IWA -4000 or IWA 7000.
3)
For the ISI related corrective action issues selected by the inspector from A.8 above, provide a copy of the corrective actions and supporting documentation.
4)
For the nondestructive examination reports with relevant indications on Code Class 1 and 2 systems selected by the inspector from A.4 above, provide a copy of the examination records and associated corrective action documents.
5)
Provide a list of NDE personnel performing inspections of the vessel head (upper and lower) and the qualification records for these personnel.
7)
Copy of the most recent quality assurance department audit, which included the ISI program and activities. Copies of documents resolving findings in this audit.
8)
Updated schedules for item A.1 (including schedule showing contingency repair plans for vessel nozzles if available).
9)
Copy of the vendor qualification report(s) used to demonstrate the detection capability of the NDE equipment used for the vessel head penetration inspections (upper and lower head). Also, identify any changes in system configurations and equipment used for head inspection discussed in item A.1 which differ from that used for in the vendor qualification report(s).
10)
Provide a brief overview of planned repair process (including drawings) for use on the vessel head nozzles and identify the repair procedures to be used. Also include any documented NRC reviews/evaluation/approval of this repair process.
11)
Provide drawings showing the vessel head (upper and lower) and nozzle configuration and head insulation configuration.
12)
Copy of document describing the flaw evaluation guidelines which will be followed for any cracking identified in the vessel nozzles or J-welds.
13)
Copy of documentation including nondestructive examination reports for the last upper vessel head examination completed in response to NRC Bulletins 2002-02. These records should include each nozzle weld examination with the signatures of nodestructive examination personnel that performed, reviewed and approved each examination for each nozzle penetration.
14)
Copy of documentation including nondestructive examination reports for the last lower vessel head examination.
Enclosure 4
15)
Copy of the procedures which govern the scope, equipment used and implementation of the inspections required to identify boric acid leakage from systems and components above the vessel head.
16)
Copy of the previous two completed system pressure tests, documenting the results of the VT-2 inspections completed near the upper vessel head and the lower vessel head.
17)
Copy of any documentation of boric acid deposits/corrosion of the upper and lower vessel heads or head insulation. Also provide supporting corrective action documents and evaluations.
18)
Completed copy documenting the results of the last two Mode 3 walkdowns/inspections near the vessel head (if performed).
19)
Copy of the plant procedures used to perform inspections to identify reactor coolant system leaks or boric acid deposits and the procedures for resolution of leaks or boric acid deposits.
20)
Drawings/procedures or records that identify the systems and components which could be sources of boric acid leakage onto the upper vessel head.
21)
Copy of procedure governing the performance of a leakage assessment into the interference zone of vessel head nozzles and acceptance criteria (reference NRC Order EA-03-009).
22)
If NDE of reactor vessel welds and/or nozzle J-welds is scheduled to occur during this inspection period, provide a copy of the applicable weld fabrication drawings.
23)
Ready access to the Editions of the ASME Code (Sections V, IX and XI) applicable to the inservice inspection program and the repair/replacement program.
24)
Training and qualification records for personnel performing welding and NDE.