ML072540813
| ML072540813 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/11/2007 |
| From: | William Jones Division of Reactor Safety IV |
| To: | Edington R Arizona Public Service Co |
| References | |
| Download: ML072540813 (10) | |
Text
September 11, 2007 Randall K. Edington, Senior Vice President, Nuclear Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION, UNIT 3 - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Edington:
During the period from October 9 to December 7, 2007, the NRC will perform the baseline inservice inspection (ISI) at the Palo Verde Nuclear Generating Station, Unit 3 (NRC Inspection Procedure 71111.08, Temporary Instruction 2515/150, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzles, and Temporary Instruction 2515/166, Pressurized Water Reactor Containment Sump Blockage (NRC Generic Letter 2004-02.)
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 on-site 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 Delbert Elkington of your 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 Breck Henderson, (817) 276-6569, bwh@nrc.gov.
Arizona Public Service Company 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 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/
William B. Jones, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 530 License No. NPF-74
Enclosure:
Inservice Inspection Document Request Steve Olea Jeffrey T. Weikert Arizona Corporation Commission Assistant General Counsel 1200 W. Washington Street El Paso Electric Company Phoenix, AZ 85007 Mail Location 167 123 W. Mills Douglas K. Porter, Senior Counsel El Paso, TX 79901 Southern California Edison Company Law Department, Generation Resources John W. Schumann P.O. Box 800 Los Angeles Department of Water & Power Rosemead, CA 91770 Southern California Public Power Authority P.O. Box 51111, Room 1255-C Chairman Los Angeles, CA 90051-0100 Maricopa County Board of Supervisors 301 W. Jefferson, 10th Floor John Taylor Phoenix, AZ 85003 Public Service Company of New Mexico 2401 Aztec NE, MS Z110 Aubrey V. Godwin, Director Albuquerque, NM 87107-4224 Arizona Radiation Regulatory Agency 4814 South 40 Street Geoffrey M. Cook Phoenix, AZ 85040 Southern California Edison Company 5000 Pacific Coast Hwy, Bldg. D21 Scott Bauer, Acting Director San Clemente, CA 92672 Regulatory Affairs Palo Verde Nuclear Generating Station Mail Station 7636 P.O. Box 52034 Phoenix, AZ 85072-2034
Arizona Public Service Company Robert Henry Salt River Project 6504 East Thomas Road Scottsdale, AZ 85251 Brian Almon Public Utility Commission William B. Travis Building P.O. Box 13326 1701 North Congress Avenue Austin, TX 78701-3326 Karen O'Regan Environmental Program Manager City of Phoenix Office of Environmental Programs 200 West Washington Street Phoenix, AZ 85003 Matthew Benac Assistant Vice President Nuclear & Generation Services 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
Arizona Public Service Company Electronic distribution by RIV:
Regional Administrator (EEC)
DRP Director (ATH)
DRS Director (DDC)
DRS Deputy Director (RJC1)
Senior Resident Inspector (GXW2)
Branch Chief, DRP/D (TWP)
Senior Project Engineer, DRP/D (RLN1)
Senior Project Engineer, DRP/D (GEW)
Team Leader, DRP/TSS (CJP)
RITS Coordinator (MSH3)
V. Dricks, PAO (VLD)
D. Pelton, OEDO RIV Coordinator (DLP)
ROPreports PV Site Secretary (PRC)
SUNSI Review Completed: __/ADAMS: / Yes G No Initials: WBJ___
/ Publicly Available G Non-Publicly Available G Sensitive / Non-Sensitive S:\DRS\REPORTS\PV request for info-BWH.wpd ML DRS\EB1 C:EB1 BWHenderson:tek WBJones
/RA/ /RA/
9/11/07 9/11/07 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
ENCLOSURE INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates: October 9 to November 20, 2007 Inspection Procedures: IP 71111.08 Inservice Inspection (ISI) Activities TI 2515/150 Reactor Pressure Vessel Head and Vessel Head Penetration Nozzles TI 2515/166 Pressurized Water Reactor Containment Sump Blockage (NRC Generic Letter 2004-02)
Inspectors: Breck Henderson, Reactor Inspector (Lead Inspector - ISI)
Gerond George Reactor Inspector (Lead Inspector - TI 2515/166)
Shiattin Makor, Reactor Inspector A. Information Requested for the In-Office Preparation Week The following information should be sent to the Region II office in hard copy or electronic format (CD preferred), in care of Breck Henderson by September 21, 2007, 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 inspectors, 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.
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.
Enclosure
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 recordable indications (geometric or flaw) on Code Class 1 & 2 systems since the beginning of the last refueling outage. Also, include in the list the NDE reports with recorded indications 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 recordable indication 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 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 NRC commitments made in response to NRC Bulletin 2002-02 and NRC Order EA-03-009. Also, include examination scope Enclosure
expansion criteria and planned expansion sample sizes if relevant indications 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 walk-down inspections performed as part of the BACCP.
c) Please provide a copy of the most recent self-assessment performed for the BACCP.
A.4 Additional information related to all ISI activities a) A list with a brief description of ISI, BACCP, and SG ISI related issues (e.g., condition reports) entered into your corrective action program since the beginning of the last refueling outage for Unit 3. 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/SG tube 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 Enclosure
B. Information to be provided on-site to the inspector at the entrance meeting October 9, 2007:
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 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 WPS, including documentation that welder maintained proficiency in the applicable welding processes specified in the WPS (At least six months prior to date 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 from section A of this enclosure, provide a copy of the corrective actions and supporting documentation.
d) For the NDE reports with recordable indications 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 Enclosure
(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) and NDE personnel qualification records.
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 walk down 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 Enclosure
specifically which known leaks, if any, have remained in service or will remain in service as active leaks.
B.4 Codes and Standards a) Ready access, upon request, to:
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 SG tube eddy current examination.
Inspector Contact Information:
Breck Henderson Gerond George Shiattin Makor Reactor Inspector Reactor Inspector Reactor Inspector 817-276-6569 817-2766562 817-276-6507 bwh@nrc.gov gag@nrc.gov stm@nrc.gov Mailing Address:
US NRC Region IV Attn: Breck Henderson 611 Ryan Plaza Dr., Ste. 400 Arlington, TX 76011 Enclosure