ML030350714
| ML030350714 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/31/2003 |
| From: | Dave Hills NRC/RGN-III/DRS/MEB |
| To: | Bakken A American Electric Power Service Corp |
| References | |
| BL-02-002 | |
| Download: ML030350714 (7) | |
Text
January 31, 2003 Mr. A. C. Bakken III Senior Vice President Nuclear Generation Group American Electric Power Company 500 Circle Drive Buchanan MI 49107
SUBJECT:
D. C. COOK NUCLEAR POWER PLANT, UNIT 2 NOTIFICATION OF NRC INSERVICE BASELINE INSPECTION AND REACTOR PRESSURE VESSEL HEAD AND VESSEL HEAD PENETRATION NOZZLES INSPECTION (NRC BULLETIN 2002-02)
Dear Mr. Bakken:
On May 12, 2003, the NRC will begin the Inservice baseline inspection and a Reactor Pressure Vessel Head and Vessel Head Penetration Nozzles inspection at the D. C. Cook Nuclear Power Plant, Unit 2. These on-site inspections will be performed May 12-23, 2003, in accordance with the NRC baseline Inspection Procedures 71111.08 and Temporary Instruction 2515/150.
Experience has shown that the these inspections are resource intensive both for the NRC inspector and your staff. In order to minimize the inspection impact on the site and to ensure a productive inspection for both sides, we have enclosed a request for documents needed for these inspections. 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.
The inspector for this inspection is Melvin Holmberg. We understand that our regulatory contact for this inspection is Richard Meister of your organization. If there are any questions about the inspection or the material requested, please contact the inspector at (630) 829-9748.
A. Bakken In accordance with 10 CFR 2.790 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 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 Mechanical Engineering Branch Division of Reactor Safety Docket No. 50-316; License No. DPR-074
Enclosure:
Inservice Inspection Document Request cc w/encl:
J. Pollock, Site Vice President M. Finissi, Plant Manager R. Whale, Michigan Public Service Commission Michigan Department of Environmental Quality Emergency Management Division MI Department of State Police D. Lochbaum, Union of Concerned Scientists cc w/encl:
A. Bakken In accordance with 10 CFR 2.790 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 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 Mechanical Engineering Branch Division of Reactor Safety Docket No. 50-316; License No. DPR-074
Enclosure:
Inservice Inspection Document Request cc w/encl:
J. Pollock, Site Vice President M. Finissi, Plant Manager R. Whale, Michigan Public Service Commission Michigan Department of Environmental Quality Emergency Management Division MI Department of State Police D. Lochbaum, Union of Concerned Scientists cc w/encl:
DOCUMENT NAME: G:DRS\\ML030350714.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 MHolmberg:sd DHills AVegel DATE 01/31/03 01/31/03 01/31/03 OFFICIAL RECORD COPY
A. Bakken ADAMS Distribution:
WDR DFT JFS2 RidsNrrDipmIipb GEG HBC BJK1 DRPIII DRSIII PLB1 JRK1
INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates:
May 12 - 23, 2003 Inspection Procedures:
IP 7111108, Inservice Inspection TI 2515/150, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzles Lead Inspector:
Inspector: Melvin Holmberg (630 829-9748)
A.
Information Requested for the In-Office Preparation Week The following information is requested by April 25, 2003, 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 submit a list of additional documents needed on-site to your staff by May 8, 2003. We request that the specific items selected from the lists be available and ready for review on the first day of inspection. If you have any questions regarding this information, please call the inspector as soon as possible.
1)
A detailed schedule of nondestructive examinations planned for Class 1 & 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 which fulfill NRC commitments made in response to NRC Bulletin 2002-02. Provide a detailed schedule of steam generator (SG) tube inspection and repair activities for the upcoming outage.
2)
A copy of the 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 nondestructive examination reports (ultrasonic, radiography, magnetic particle, dye penetrant, visual (VT-1, VT-2, VT-3)) which have identified relevant indications on Code Class 1 & 2 systems in the past two refueling outages (both Units).
Also, identify any NDE examinations with recorded indications in the vessel head penetration nozzles which have been accepted for continued service.
5)
List of welds in Code Class 1, and 2 systems which have been completed since the beginning of the last refueling outage (both Units and identify system, weld number and reference applicable documentation).
6)
For reactor vessel weld examinations required by the ASME Code, that are scheduled during the inspection, provide a detailed description of the welds to be examined, and the extent of the planned examination.
7)
Provide a list with description of ISI and steam generator related issues entered into your corrective action system beginning with the date of the last refueling outage (both Units).
8)
Copy of any part 21 reports submitted beginning with the date of the last refueling outage.
9)
Copy of SG history documentation given to vendors performing eddy current (ET) testing of the SGs during the upcoming outage.
10)
Copy of procedure containing screening criteria used for selecting tubes for in-situ pressure testing and the procedure to be used for in-situ pressure testing.
11)
Copy of previous outage SG tube operational assessment completed following ET of the SGs.
12)
Copy of the document defining the planned ET scope for the SGs and the scope expansion criteria which will be used.
13)
Copy of the document describing the ET probe types, and ET acquisition equipment to be used, including which areas of the SG (e.g. top of tube sheet, U-bends) each probe will be used in. Also, provide your response letter(s) to generic letters 95-03, 95-05, 97-05, and 97-06.
14)
Copy of document describing actions to be taken if a new SG tube degradation mechanism is identified.
15)
Identify the types of SG tube repair processes which will be implemented for defective SG tubes. Provide the flaw depth sizing criteria to be applied for ET indications identified in the SG tubes.
16)
If tube leakage was identified during the previous operating cycle, provide documentation identifying which SG was leaking and planned corrective actions.
17)
Provide a copy of the EPRI Technique Specification Sheets which support qualification of the ET probes to be used during the upcoming SG tube inspections.
18)
Provide a copy of the guidance to be followed if a loose part or foreign material is identified in the SGs.
19)
Detailed scope of the planned nondestructive examinations (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 Bulletin 2002-02. Also include examination scope expansion criteria and planned expansion sample sizes if relevant indications are identified.
20)
Copy of NDE procedures to be used for performing vessel head inspections that fulfill NRC commitments in response to NRC Bulletin 2002-02.
21)
Identify what standards or requirements will be used to evaluate indications identified during NDE examinations of the vessel head.
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.
h)
Copies of the nonconformance reports for the selected welds.
i)
Radiographs of the selected welds and access to equipment to allow viewing radiographs.
j)
Copies of the preservice examination records for the selected welds.
2)
For the replacement activities selected by the inspector 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)
Provide a list of NDE personnel performing inspections of the vessel head and the qualification records for these personnel.
4)
Copies of commitments made to the NRC for performing vessel head examinations under bulletin 2002-02.
5)
Copy of the most recent quality assurance department audit, which included the ISI program and activities. Copies of documents resolving findings in this audit.
6)
Updated schedules for item A.1 (including schedule showing contingency repair plans for vessel nozzles if available).
7)
Copy of the vendor qualification report(s) used to demonstrate the detection capability of the NDE equipment used for the vessel head penetration inspections. 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).
8)
Provide the susceptibility ranking calculation for the vessel head operating time and temperature. Also, provide the plant specific records (or vendor information) used to determine the inputs for this calculation.
9)
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.
10)
Provide drawings showing the vessel head and nozzle configuration.
11)
Copy of document describing the flaw evaluation guidelines which will be followed for any cracking identified in the vessel nozzles or J-welds.
12)
Copy of documentation including nondestructive examination reports for the last Unit 2 vessel head examination completed in response to NRC Bulletins 2001-01 or 2002-02.