ML092790424
| ML092790424 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 10/06/2009 |
| From: | Thomas Farnholtz Region 4 Engineering Branch 1 |
| To: | Bannister D J Omaha Public Power District |
| References | |
| IR-09-005 | |
| Download: ML092790424 (11) | |
See also: IR 05000285/2009005
Text
UNITED STATESNUCLEAR REGULATORY COMMISSIONREGION IV612 EAST LAMAR BLVD, SUITE 400ARLINGTON, TEXAS 76011-4125 October 6, 2009
David J. Bannister, Vice President and Chief Nuclear Officer
Omaha Public Power District Fort Calhoun Station FC-2-4 P. O. Box 550 Fort Calhoun, NE 68023-0550
SUBJECT: FORT CALHOUN STATION - NOTIFICATION OF INSPECTION NRC INSPECTION REPORT (05000285/2009005) AND REQUEST FOR INFORMATION
Dear Mr. Bannister:
On November 9, 2009, reactor inspectors from the Nuclear Regulatory Commission's (NRC) Region IV office will begin baseline inservice inspection activities at Fort Calhoun, using NRC Inspection Procedure 71111.08, "Inservice Inspection Activities," and TI 2515/172, "Reactor Coolant System Dissimilar Metal Butt Welds." Experience has shown that this inspection is a resource intensive inspection both for the NRC inspectors and your staff. In order to minimize
the impact to your onsite resources and to ensure a productive inspection, we have enclosed a request for documents needed for this inspection. These documents have been divided into two groups. The first group (Section A of the enclosure) identified information to be provided prior to the inspection to ensure that the inspectors are adequately prepared. The second group (Section B of the enclosure) identifies the information the inspectors 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 Mr. Erick Matzke of your licensing organization. The tentative inspection schedule is as follows:
Preparation Weeks: November 2 - 9, 2009 Onsite weeks: November 9 - 20, 2009
Our inspection dates are subject to change based on your updated schedule of outage
activities. If there are any questions about this inspection or the material requested, please contact the lead inspector Gerond George at (817) 276-6562 (Gerond.George@nrc.gov) or Isaac Anchondo at (817) 860-8152 (Isaac.Anchondo@nrc.gov).
Omaha Public Power District - 2 -
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 (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/
Thomas R. Farnholtz, Chief Engineering Branch 1 Division of Reactor Safety
Docket: 50-285
License: DPR-40
Enclosure: Inservice Inspection Document Request
cc w/enclosure: Jeffrey A. Reinhart Site Vice President Omaha Public Power District Fort Calhoun Station FC-2-4 Adm
P.O. Box 550 Fort Calhoun, NE 68023-0550
Mr. Thomas C. Matthews Manager - Nuclear Licensing
Omaha Public Power District Fort Calhoun Station FC-2-4 Adm. P.O. Box 550 Fort Calhoun, NE 68023-0550
Winston & Strawn Attn: David A. Repke, Esq. 1700 K Street, NW Washington, DC 20006-3817
Chairman Washington County Board of Supervisors
P.O. Box 466 Blair, NE 68008
Omaha Public Power District - 3 -
Ms. Julia Schmitt, Manager Radiation Control Program Nebraska Health & Human Services R & L Public Health Assurance 301 Centennial Mall, South
P.O. Box 95007 Lincoln, NE 68509-5007
Ms. Melanie Rasmussen Radiation Control Program Officer
Bureau of Radiological Health Iowa Department of Public Health Lucas State Office Building, 5th Floor 321 East 12th Street Des Moines, IA 50319
Chief, Technological Hazards Branch
FEMA, Region VII 9221 Ward Parkway Suite 300 Kansas City, MO 64114-3372
Omaha Public Power District - 4 - Electronic distribution by RIV: Regional Administrator (Elmo.Collins@nrc.gov) Deputy Regional Administrator (Chuck.Casto@nrc.gov) DRP Director (Dwight.Chamberlain@nrc.gov) DRP Deputy Director (Anton.Vegel@nrc.gov) DRS Director (Roy.Caniano@nrc.gov)
DRS Deputy Director (Troy.Pruett@nrc.gov) Senior Resident Inspector (John.Kirkland@nrc.gov) Resident Inspector (Jacob.Wingebach@nrc.gov) Branch Chief, DRP/E (Jeff.Clark@nrc.gov) Senior Project Engineer, DRP/E (Ray.Azua@nrc.gov)
FCS Site Secretary (Berni.Madison@nrc.gov) Public Affairs Officer (Victor.Dricks@nrc.gov) Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov) RITS Coordinator (Marisa.Herrera@nrc.gov) Regional Counsel (Karla.Fuller@nrc.gov) Congressional Affairs Officer (Jenny.Weil@nrc.gov) OEMail Resource
ROPreports DRS STA (Dale.Powers@nrc.gov) OEDO RIV Coordinator (Leigh.Trocine@nrc.gov)
SUNSI Review Completed: ___Y___ ADAMS: Yes No Initials: _GAG
_ Publicly Available Non-Publicly Available Sensitive Non-Sensitive
RI:PSB2 RI:EB1 C:EB1 IAnchondo GAGeorge T. Farnholtz
/RA/ /RA//RA/ 10/6/09 10/6/09 10/6/09 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
- 1 - Enclosure INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Dates: November 9 through November 20, 2009
Inspection Procedures: IP 71111.08 "Inservice Inspection (ISI) Activities" TI 2515/172 "Reactor Coolant System Dissimilar Metal Butt Welds" Inspectors: G. George, Reactor Inspector (Lead Inspector - ISI) I. Anchondo, Reactor Inspector
A. Information Requested for the In-Office Preparation Week
The following information should be sent to the Region IV office in hard copy or electronic format (ims.certrec.com preferred), in care of Gerond George, by November 2, 2009, 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 then request from your staff additional documents needed during the onsite inspection week (Section B of this enclosure). We ask that the specific items selected from the lists be available and ready for review on the first day of inspection. *Please provide requested documentation electronically if possible. If requested documents are large and only hard copy formats are available, please inform the inspector(s), and provide subject documentation during the first day of the onsite inspection. If you have any questions regarding this information request, please call the inspector as soon as possible.
A.1 ISI/Welding Programs and Schedule Information
a) A detailed schedule (including preliminary dates) of:
i) Nondestructive examinations (NDEs) planned for Class 1 & 2 systems and containment, performed as part of your ASME Section XI, Risk
Informed (if applicable), and augmented ISI programs during the upcoming outage.
Provide a status summary of the NDE inspection activities vs. the required inspection period percentages for this Interval by category per
ASME Section XI, IWX-2400 (Do not provide separately if other documentation requested contains this information)
ii) Reactor pressure vessel head (RPVH) examinations planned for the upcoming outage.
iii) Examinations planned for Alloy 82/182/600 components that are not included in the Section XI scope. (If applicable)
iv) Examinations planned as part of your Boric Acid Corrosion Control Program (Mode 3 walkdowns, bolted connection walkdowns, etc.)
- 2 - Enclosure
v) Welding activities that are scheduled to be completed during the upcoming outage (ASME Class 1, 2, or 3 structures, systems, or components (SSCs)).
b) A copy of ASME Section XI Code Relief Requests and associated NRC Safety Evaluations applicable to the examinations identified above.
c) A list of NDE reports (ultrasonic, radiography, magnetic particle, dye penetrate, Visual VT-1, VT-2, and VT-3), which have identified relevant conditions on Code Class 1 & 2 systems since the beginning of the last refueling outage. This should include the previousSection XI pressure test(s) conducted during start up and any evaluations associated with the results of the pressure tests. Also, include in the list the NDE reports with relevant conditions in the RPVH penetration nozzles which have been accepted for continued service. The list of NDE reports should include a brief description of the SSC where the relevant condition was identified.
d) A list with a brief description (e.g., system, material, pipe size, weld number, and NDE performed) of the welds in Code Class 1 and 2 systems which have been fabricated due to component repair/replacement activities since the beginning of the last refueling outage, or are planned to be fabricated this refueling outage.
e) If reactor vessel weld examinations required by the ASME Code are scheduled to occur during the upcoming outage, provide a detailed description of the welds to be examined and the extent of the planned examination. Please also provide reference numbers for applicable procedures that will be used to conduct these examinations.
f) Copy of any 10 CFR Part 21 reports applicable to your SSCs within the scope of Section XI of the ASME Code that have been identified since the beginning of the last refueling outage.
g) A list of any temporary non-code repairs inservice (e.g., pinhole leaks).
h) Please provide copies of the most recent self assessments for the ISI, Welding, and Alloy 600 Programs.
A.2 Reactor Pressure Vessel Head (RPVH)
a) Provide the detailed scope of the planned NDE of the reactor vessel head which identifies the types of NDE methods to be used on each specific part of the vessel head to fulfill commitments made in response to NRC Bulletin 2002-02 and NRC Order EA-03-009. Also, include examination scope expansion criteria and planned expansion sample sizes if relevant conditions are identified. (If
applicable)
b) A list of the standards and/or requirements that will be used to evaluate indications identified during NDE of the reactor vessel head (e.g., the specific
- 3 - Enclosure industry or procedural standards which will be used to evaluate potential leakage and/or flaw indications).
A.3 Boric Acid Corrosion Control Program (BACCP)
a) Copy of the procedures that govern the scope, equipment and implementation of the inspections required to identify boric acid leakage and the procedures for boric acid leakage/corrosion evaluation.
b) Please provide a list of leaks (including Code class of the components) that have been identified since the last refueling outage and associated corrective action documentation. If during the last cycle, the Unit was shutdown, please provide documentation of containment walkdown inspections performed as part of the BACCP. c) Please provide a copy of the most recent self-assessment performed for the BACCP. A.4 Steam Generator Tube (SGT) Inspections
a) Please provide a copy of your SG ISI Inspection Program and Plan. Please include a copy of the Operational Assessment from last outage and a copy of the
following documents as they become available:
i) Degradation Assessment ii) Condition Monitoring Assessment
b) Provide, if available, past history of the condition and issues pertaining to the secondary side of the steam generators (including items such as loose parts, fouling, top of tube sheet condition, crud removal amounts, etc.)
c) Please provide copies of your most recent self assessments of the SG monitoring, loose parts monitoring, and secondary side water chemistry control programs.
A.5 Materials Reliability (MRP-139) Program Activities
a) A list of, with verification, that the baseline inspections of all applicable Dissimilar Metal Butt Welds (DMBWs) have been completed by December 31
st, 2009. b) Verification that baseline inspection of hot leg and cold leg temperature DMBWs have been included in the inspection program and that the schedules for the baseline inspections are consistent with the baseline schedules in MRP-139.
c) A list and schedule (examination dates) of all DMBW examinations planned for the upcoming refueling outage. If none are scheduled, then data from previous examinations should be available for review.
- 4 - Enclosure d) A list and schedule for any welding to be performed on DMBWs in the upcoming outage. If no welding will be performed, then records of previous welding on DMBWs and postweld NDE documentation.
e) A list and schedule of any stress improvement (SI) activities planned for the upcoming refueling outage. If none are scheduled then have qualification reports for any SIs previously performed.
f) Documentation and description of how the baseline and inservice inspection specifications in MRP-139 are satisfied at your facility.
g) A list of weld locations controlled by MRP-139 which includes the MRP-139 weld category, pre-mitigation volumetric examination date, type of mitigation or stress improvement, post mitigation volumetric examination date, and plans for future MRP-139 required examinations.
A.6 Additional information related to all ISI activities
a) A list with a brief description of ISI, BACCP, and SGT inspection related issues (e.g., condition reports) entered into your corrective action program since the beginning of the last refueling outage. For example, a list based upon data base searches using key words related to piping or SG tube degradation such as: ISI,
ASME Code,Section XI, NDE, cracks, wear, thinning, leakage, rust, corrosion, boric acid, or errors in piping/SGT examinations.
b) Please provide names and phone numbers for the following program leads:
ISI contacts (Examination, planning) Containment Exams RPVH Exams Snubbers and Supports Repair and Replacement Program Manager
Licensing Contact Site Welding Engineer Boric Acid Corrosion Control Program SG Inspection Activities (site lead and vendor contact)
B. Information to be provided onsite to the inspector(s) at the entrance meeting (November 9, 2009):
B.1 ISI / Welding Programs and Schedule Information
a) Updated schedules for ISI/NDE activities, planned welding activities, and schedule showing contingency repair plans, if available.
b) For ASME Code Class 1 and 2 welds selected by the inspector from the lists provided from section A of this enclosure, please provide copies of the following documentation for each subject weld:
- 5 - Enclosure
i) Weld data sheet (traveler) ii) Weld configuration and system location iii) Applicable Code Edition and Addenda for weldment iv) Applicable Code Edition and Addenda for welding procedures
v) Applicable weld procedures (WPS) used to fabricate the welds vi) Copies of procedure qualification records (PQRs) supporting the WPS from B.1.b.v vii) Copies of mechanical test reports identified in the PQRs above viii) Copies of the nonconformance reports for the selected welds (If applicable) ix) Radiographs of the selected welds and access to equipment to allow viewing radiographs (If RT was performed) x) Copies of the preservice examination records for the selected welds. xi) Copies of welder performance qualifications records applicable to the selected welds, including documentation that welder maintained proficiency in the applicable welding processes specified in the WPS (at
least six months prior to the date of subject work) xii) Copies of NDE personnel qualifications (VT, PT, UT, RT), as applicable
c) For the ISI related corrective action issues selected by the inspector(s) from section A of this enclosure, provide a copy of the corrective actions and
supporting documentation.
d) For the NDE reports with relevant conditions on Code Class 1 & 2 systems selected by the inspector from section A above, provide a copy of the examination records, examiner qualification records, and associated corrective action documents.
e) A copy of (or ready access to) most current revision of the ISI Program Manual and Plan for the current Interval.
f) For the NDEs selected by the inspector from section A of this enclosure, provide copy of the NDE procedures used to perform the examinations (including calibration and flaw characterization/sizing procedures). For ultrasonic examination procedures qualified in accordance with ASME Code,Section XI, Appendix VIII, provide documentation supporting the procedure qualification (e.g., the EPRI performance demonstration qualification summary sheets). Also, include qualification documentation of the specific equipment to be used (e.g., ultrasonic unit, cables, and transducers including serial numbers) and NDE personnel qualification records.
B.2 Reactor Pressure Vessel Head (RPVH)
a) Provide the NDE personnel qualification records for the examiners who will perform examinations of the RPVH.
- 6 - Enclosure b) Provide drawings showing the following: (If a visual examination is planned for the upcoming refueling outage)
i) RPVH and CRDM nozzle configurations ii) RPVH insulation configuration
The drawings listed above should include fabrication drawings for the nozzle attachment welds as applicable.
c) Copy of NDE reports from the last RPVH examination.
d) Copy of evaluation or calculation demonstrating that the scope of the visual examination of the upper head will meet the 95 percent minimum coverage required by NRC Order EA-03-009 (If a visual examination is planned for the upcoming refueling outage).
e) Provide a copy of the procedures that will be used to identify the source of any boric acid deposits identified on the RPVH. If no explicit procedures exist which govern this activity, provide a description of the process to be followed including personnel responsibilities and expectations.
f) Provide a copy of the updated calculation of effective degradation years (EDY) for the RPVH susceptibility ranking.
g) Provide copy of the vendor qualification report(s) that demonstrates the detection capability of the NDE equipment used for the RPVH examinations. Also, identify any changes in equipment configurations used for the RPVH examinations which
differ from that used in the vendor qualification report(s).
B.3 Boric Acid Corrosion Control Program (BACCP)
a) Please provide boric acid walkdown inspection results, an updated list of boric acid leaks identified so far this outage, associated corrective action documentation, and overall status of planned boric acid inspections.
b) Please provide any engineering evaluations completed for boric acid leaks identified since the end of the last refueling outage. Please include a status of
corrective actions to repair and/or clean these boric acid leaks. Please identify specifically which known leaks, if any, have remained inservice or will remain inservice as active leaks.
B.4 Codes and Standards
a) Ready access to (i.e., copies provided to the inspector(s) for use during the inspection at the onsite inspection location, or room number and location where available):
- 7 - Enclosure i) Applicable Editions of the ASME Code (Sections V, IX and XI) for the in-service inspection program and the repair/replacement program.
ii) EPRI and industry standards referenced in the procedures used to perform the SGT eddy current examination.
Inspector Contact Information:
Reactor Inspector Reactor Inspector 817-276-6562 817-860-8152 Gerond.George@nrc.gov
Isaac.Anchondo@nrc.gov Mailing Address: US NRC Region IV Attn: Gerond George
612 E. Lamar Blvd, Suite 400 Arlington, TX 76011