ML082530206
| ML082530206 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/08/2008 |
| From: | Bywater R L Region 4 Engineering Branch 1 |
| To: | Edington R K Arizona Public Service Co |
| References | |
| IR-08-005 | |
| Download: ML082530206 (12) | |
See also: IR 05000528/2008005
Text
September 8, 2008
Randall K. Edington, Executive Vice President, Nuclear/CNO Mail Station 7602 Arizona Public Service Company P.O. Box 52034
Phoenix, AZ 85072-2034
SUBJECT: PALO VERDE NUCLEAR GENERATING STATION, UNIT 1- NOTIFICATION OF INSPECTION (NRC INSPECTION REPORT 05000528/2008005) AND REQUEST FOR INFORMATION
Dear Mr. Edington:
From October 8 to 22, 2008, reactor inspectors from the U. S. Nuclear Regulatory Commission's (NRC) Region IV office will perform the baseline inservice inspection at Palo Verde Nuclear Generating Station, Unit 1, using NRC Inspection Procedure 71111.08
and Temporary Instruction 2515/172, "Reactor Coolant System Dissimilar Metal Butt Welds." Experience has shown that this inspection is resource intensive 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) identifies 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. Dan Hautala of your licensing organization. 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 W. Sifre at (817) 860-8193 (Wayne.Sifre@nrc.gov
). UNITED STATESNUCLEAR REGULATORY COMMISSIONREGION IV612 EAST LAMAR BLVD, SUITE 400ARLINGTON, TEXAS 76011-4125
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/
Russell L. Bywater, Chief Engineering Branch 1 Division of Reactor Safety
Dockets: 50-528 Licenses: NPF-41
Enclosure: Inservice Inspection Document Request
cc w/enclosure:
Mr. Steve Olea Arizona Corporation Commission 1200 W. Washington Street Phoenix, AZ 85007
Mr. Douglas Kent Porter Senior Counsel Southern California Edison Company Law Department, Generation Resources P.O. Box 800
Rosemead, CA 91770
Chairman Maricopa County Board of Supervisors 301 W. Jefferson, 10th Floor
Phoenix, AZ 85003
Mr. Aubrey V. Godwin, Director Arizona Radiation Regulatory Agency 4814 South 40 Street Phoenix, AZ 85040
Mr. Scott Bauer, Director Regulatory Affairs Palo Verde Nuclear Generating Station Mail Station 7636 P.O. Box 52034
Phoenix, AZ 85072-2034
Mr. Dwight C. Mims Vice President Regulatory Affairs and Plant Improvement Palo Verde Nuclear Generating Station Mail Station 7605
P.O. Box 52034 Phoenix, AZ 85072-2034
Mr. Jeffrey T. Weikert Assistant General Counsel
El Paso Electric Company Mail Location 167 123 W. Mills El Paso, TX 79901
Mr. Eric Tharp Los Angeles Department of Water & Power
Southern California Public Power Authority P.O. Box 51111, Room 1255-C Los Angeles, CA 90051-0100
Mr. James Ray
Public Service Company of New Mexico 2401 Aztec NE, MS Z110 Albuquerque, NM 87107-4224 Mr. Geoffrey M. Cook Southern California Edison Company
5000 Pacific Coast Hwy. Bldg. D21 San Clemente, CA 92672
Mr. Robert Henry Salt River Project
6504 East Thomas Road Scottsdale, AZ 85251
Mr. Brian Almon Public Utility Commission
William B. Travis Building P.O. Box 13326 1701 North Congress Avenue Austin, TX 78701-3326
Ms. Karen O' Regan Environmental Program Manager
City of Phoenix Office of Environmental Programs 200 West Washington Street Phoenix, AZ 85003
Mr. John C. Taylor Director, Nuclear Generation El Paso Electric Company 340 East Palm Lane, Suite 310 Phoenix, AZ 85004
Chief, Radiological Emergency Preparedness Section National Preparedness Directorate Technological Hazards Division Department of Homeland Security 1111 Broadway, Suite 1200
Oakland, CA 94607-4052
Electronic distribution by RIV: Regional Administrator (Elmo.Collins@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 (Ryan.Treadway@nrc.gov ) Resident Inspector (Michelle.Catts@nrc.gov ) Branch Chief, DRP/D (Michael.Hay@nrc.gov) Senior Project Engineer, DRP/D (Don Allen@nrc.gov ) Public Affairs Officer (Victor.Dricks@nrc.gov ) Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov ) RITS Coordinator (Marisa.Herrera@nrc.gov ) DRS STA (Dale.Powers@nrc.gov) Mark Cox, OEDO RIV Coordinator (Mark.Cox@nrc.gov ) ROPreports PV Site Secretary (Patricia.Coleman@nrc.gov )
SUNSI Review Completed: _
RLB__ ADAMS: Yes Initials:
_RLB__ Publicly Available Non-Sensitive
S:DRS/REPORTS/PV ISI ltr-WCS. ML082530206
EB 1 EB 1 C: EB 1 WCSifre MRYoung RLBywater /RA/ /RA/ /RA/ 9/5 /08 9/5 /08 9/ 8/08 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Dates: October 8 - 22, 2008
Inspection Procedures: IP 71111.08 "Inservice Inspection (ISI) Activities"
TI 2515/172 "Reactor Coolant System Dissimilar Metal Butt Welds"
Inspectors: W. Sifre, Senior Reactor Inspector (Lead Inspector - ISI) M. Young, Reactor Inspector
A. Information Requested for the In-Office Preparation Week
The following information (Section A of this enclosure) should be sent to the Region IV office in hard copy or electronic format (ims.certrec.com preferred), in care of W. Sifre, by September 24, 2008, 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 refueling 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.).
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 penetrant, 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 in 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 in service (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 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) A detailed schedule of:
i) SGT inspection, data analyses, and repair activities for the upcoming outage (if occurring).
ii) SG secondary side inspection activities for the upcoming outage (if occurring).
b) 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
c) If you are planning on modifying your Technical Specifications such that they are consistent with TSTF-449, please provide copies of your correspondence with the NRC regarding deviations from the STS.
d) Copy of SG history documentation given to vendors performing eddy current (ET) testing of the SGs during the upcoming outage.
e) Copy of SG Eddy Current Data Analyst Guidelines and Site Validated Eddy Current Technique Specification Sheets (ETSS). Additionally, please provide a copy of EPRI Appendix H ETSS Qualification Records.
f) Identify and quantify any SGT leakage experienced during the previous operating cycle. Also provide documentation identifying which SG was leaking and corrective actions completed or planned for this condition (If applicable).
g) Provide 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.).
h) Please provide copies of your most recent self assessments of the SG monitoring, loose parts monitoring, and secondary side water chemistry control programs.
i) Please also indicate where the primary, secondary, and resolution analyses are scheduled to take place.
j) Please provide a summary of the scope of the SGT examinations, including examination methods such as Bobbin, Rotating Pancake, or Plus Point, and the percentage of tubes to be examined. *Do not provide these documents separately if already included in other information requested. A.5 Metals 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, 2007.
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.
d) A list and schedule for any welding to be performed on DMBWs in the upcoming outage. If no welding will be performed then provide 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.
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 Unit 1). 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 (October 8, 2008):
B.1 ISI / Welding Programs and Schedule Information
a) Updated schedules for ISI/NDE activities, including SGT inspections, 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:
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.
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% 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 in service or will remain in service as active leaks.
B.4 Steam Generator Tube (SGT) Inspections
a) Copies of the Examination Technique Specification Sheets (ETSS) and associated justification for any revisions.
b) Copy of the guidance to be followed if a loose part or foreign material is identified in the SGs.
c) Please provide a copy of the ET procedures used to perform the SGT inspections (specifically calibration and flaw characterization/sizing procedures, etc.). Also include documentation for the specific equipment to be used.
d) Please provide copies of your responses to NRC and industry operating experience communications such as Generic Letters, Information Notices, etc. (as applicable to SGT inspections) *Do not provide these documents separately if already included in other information requested such as the degradation assessment.
e) List of corrective action documents generated by the vendor and/or site with respect to SG inspection activities.
B.5 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):
i) Applicable Editions of the ASME Code (Sections V, IX and XI) for the inservice 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:
Wayne C. Sifre Matthew R.Young Senior Reactor Inspector Reactor Inspector 817-860-8193 817-276-6545 wayne.sifre@nrc.gov
matthew.young@nrc.gov
Mailing Address: US NRC Region IV Attn: W. Sifre 612 East Lamar Blvd, Suite 400
Arlington, TX 76011