ML100140898
| ML100140898 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 02/12/2010 |
| From: | Lisa Regner License Renewal Projects Branch 2 |
| To: | Arizona Public Service Co |
| Regner L M, NRR/DLR, 415-1906 | |
| References | |
| Download: ML100140898 (8) | |
Text
February 12, 2010 LICENSEE: Arizona Public Service Company FACILITY: Palo Verde Nuclear Generating Station, Units 1, 2, and 3
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON JANUARY 13, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ARIZONA PUBLIC SERVICE COMPANY, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (the staff) and representatives of Arizona Public Service Company (the applicant) held a telephone conference call on January 13, 2010, to discuss and clarify the staffs draft request for additional information (RAI) concerning the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, license renewal application. The telephone conference call was useful in clarifying the intent of the staffs draft RAI. provides a listing of the participants and Enclosure 2 contains a listing of the draft questions discussed with the applicant, including a brief description on the status of the items.
The applicant had an opportunity to comment on this summary.
/RA/
Lisa M. Regner, Sr. Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-528, 50-529, and 50-530
Enclosures:
As stated cc w/encls: See next page
ML100140898 OFFICE LA:RPOB:DLR PM:RPB2:DLR BC:RPB2:DLR PM:RPB2:DLR NAME SFigueroa LRegner DWrona LRegner (Signature)
DATE 1/15/10 1/22/10 2/5/10 2/12/10 Memorandum to Arizona Public Service Company from L. Regner dated February 12, 2010
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON JANUARY 13, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ARIZONA PUBLIC SERVICE COMPANY, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3, LICENSE RENEWAL APPLICATION DISTRIBUTION:
HARD COPY:
DLR RF E-MAIL:
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TELEPHONE CONFERENCE CALL PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS JANUARY 13, 2010 PARTICIPANTS AFFILIATIONS Lisa Regner U.S. Nuclear Regulatory Commission (NRC)
Simon Sheng NRC Angela Krainik Arizona Public Service Company (APS)
Glenn Michael APS Edison Fernandez APS Chalmer Myer Strategic Teaming and Resource Sharing (STARS) Alliance Neal Schneider STARS Donald Stevens STARS ENCLOSURE 1
DRAFT REQUESTS FOR ADDITIONAL INFORMATION PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION JANUARY 13, 2010 The U.S. Nuclear Regulatory Commission (the staff) and representatives of Arizona Public Service Company (the applicant) held a telephone conference call on January 13, 2010, to discuss and clarify the following draft request for additional information (RAI) concerning the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (PVNGS), license renewal application (LRA).
DRAFT RAI 3.1.2.2.6-1 License renewal application (LRA) Table 3.1.2-1 lists the affected reactor pressure vessel (RPV) internals with the aging effect of loss of fracture toughness due to neutron irradiation embrittlement and void swelling (an aging effect discussed in LRA Section 3.1.2.2.6). These RPV internals are presented in the following with their corresponding Generic Aging Lessons Learned (GALL) Report Table IV.B3 line items: Reactor Vessel and Internals Core Support Structure (RVI CSS) Core Shroud Assembly (item IV.B3-12); RVI CSS Core Support Barrel Assembly (item IV.B3-16); and Core Support Barrel Snubber Assembly (nickel and stainless steel), RVI CSS Lower Support Structure Assembly, and RVI In-Core Instrumentation (ICI)
Support Structure (item IV.B3-20). However, the LRA table did not specifically list core shroud assembly bolts (item IV.B3-10) and tie rods (item IV.B3-12) under this aging effect. Confirm that the unit core shroud assemblies are welded structures that do not have bolts and tie rods.
Further, clarify why the LRA table did not specifically list the core support plate, fuel alignment pins, and core support column bolts as part of the GALL Report Table Item IV.B3-20 under this aging effect.
Discussion: The applicant indicated that the question is clear. This draft question will be sent in a formal RAI.
DRAFT RAI 3.1.2.2.12-1 LRA Table 3.1.2-1 identified the following GALL Report Table IV.B3 items under cracking due to stress corrosion cracking (SCC) and irradiation-assisted SCC (IASCC): IV.B3-2, IV.B3-11, IV.B3-15, IV.B3-21, and IV.B3-28. However, for this aging mechanism, the LRA table does not cover all RPV internals listed under the GALL Report Table IV.B3 items listed above. Clarify the disposition of the core support plate and core support column of the lower internal assembly (IV.B3-21) and the fuel alignment plate, the fuel alignment plate guide lugs, and guide lug inserts of the upper internals assembly (IV.B3-28).
Discussion: The applicant indicated that the question is clear. This draft question will be sent in a formal RAI.
ENCLOSURE 2
DRAFT RAI 3.1.2.2.15-1 LRA Table 3.1.2-1 identified the following GALL Report Table IV.B3 items under changes in dimension due to void swelling for stainless steel and nickel alloy RPV internals exposed to reactor coolant: IV.B3-4, IV.B3-13, IV.B3-14, IV.B3-19, and IV.B3-27. However, for this aging mechanism, the LRA table does not cover all RPV internals listed under the GALL Table IV.B3 items listed above. Clarify the disposition of the core support plate, fuel alignment pins, and core support column bolts of the lower internal assembly (IV.B3-19) and the fuel alignment plate, the fuel alignment plate guide lugs, and guide lug inserts of the upper internals assembly (IV.B3-27). Further, discuss the relationship between RVI ICI Support Structures (identified in LRA Table 3.1.2-1) and the core support plate, fuel alignment pins, and core support column bolts of the lower internal assembly (listed in the GALL Table IV.B3).
Discussion: The applicant indicated that the question is clear. This draft question will be sent in a formal RAI.
DRAFT RAI 4.7.5-1 LRA Section 4.7.5 references the WCAP-15973-P report, Low Alloy Steel Component Analysis Supporting Small Diameter Alloy 600/690 Nozzle Repair/Replacement Program, and concludes, [t]he bounding case for general corrosion in pressurizer heater sleeves in WCAP-15973-P gives an estimated repair life of 194 years; therefore the analysis is not a time limited aging analysis (TLAA), and is valid for the period of extended operation.
The staffs evaluation of the general corrosion analysis supporting half-nozzle repairs of small-diameter Alloy 600/690 nozzles was documented in the safety evaluation dated October 4, 2004, for the WCAP-15973-P report. The staffs evaluation of the plant-specific application of the WCAP-15973-P report, including its corrosion analysis, to pressurizer heater sleeves, was documented in an safety evaluation dated November 5, 2004, for Relief Request 29. The plant-specific application was approved for the second 10-year inservice inspection interval. Since the corrosion results were time dependent and the time period accepted and approved by the staff was only the second 10-year inservice inspection interval, the corrosion analysis is a TLAA.
Address the five conditions under 4.1 General Corrosion Assessment of the October 2004, safety evaluation for the WCAP-15973-P report to demonstrate the plant-specific applicability of the WCAP to PVNGS, for the period of extended operation. Also, provide the Updated Final Safety Analysis Report Supplement for this TLAA.
Discussion: Based on the discussion with the applicant, the staff revised the question as shown below. The revised question will be sent as a formal RAI.
LRA Section 4.7.5 references WCAP-15973-P, Low Alloy Steel Component Analysis Supporting Small Diameter Alloy 600/690 Nozzle Repair/Replacement Program, and concludes, [t]he bounding case for general corrosion in pressurizer heater sleeves in WCAP-15973-P gives an estimated repair life of
194 years; therefore the analysis is not a time-limited aging analysis (TLAA), and is valid for the period of extended operation.
The staffs evaluation of the general corrosion analysis supporting half-nozzle repairs of small-diameter Alloy 600/690 nozzles was documented in the safety evaluation (SE) dated January 12, 2005, for the WCAP-15973-P report. Please identify the plant-specific submittal addressing the general corrosion in support of the half-nozzle repairs installed in the pressurizer heater sleeves. Since the corrosion results are time dependent, unless they were evaluated and approved in an SE for a period of time covering the period of extended operation, they should be evaluated now as a TLAA. Please also provide the Updated Final Safety Analyses Report Supplement for this TLAA.
Palo Verde Nuclear Generating Station, Units 1, 2, and 3 cc:
Mr. Steve Olea Mr. John C. Taylor, Director, Nuclear Arizona Corporation Commission Generation 1200 W. Washington Street El Paso Electric Company Phoenix, AZ 85007 340 E. Palm Lane, Suite 310 Phoenix, AZ 85004 Mr. Douglas Kent Porter, Senior Counsel Southern California Edison Company Mr. James Ray Law Department, Generation Resources Public Service Company of New Mexico P.O. Box 800 2401 Aztec NE, MS Z110 Rosemead, CA 91770 Albuquerque, NM 87107-4224 Senior Resident Inspector Mr. Geoffrey M. Cook U.S. Nuclear Regulatory Commission Southern California Edison Company P.O. Box 40 5000 Pacific Coast Highway, Bldg. D21 Buckeye, AZ 85326 San Clemente, CA 92672 Regional Administrator, Region IV Mr. Robert Henry U.S. Nuclear Regulatory Commission Salt River Project 612 E. Lamar Blvd., Suite 400 6504 E. Thomas Road Arlington, TX 76011-4125 Scottsdale, AZ 85251 Chairman Mr. Jeffrey T. Weikert Maricopa County Board of Supervisors Assistant General Counsel 301 W. Jefferson, 10th Floor El Paso Electric Company Phoenix, AZ 85003 Mail Location 167 123 W. Mills Mr. Aubrey V. Godwin, Director El Paso, TX 79901 Arizona Radiation Regulatory Agency 4814 S. 40th Street Mr. Eric Tharp Phoenix, AZ 85040 Los Angeles Department of Water & Power Southern California Public Power Authority Mr. Ron Barnes, Director P.O. Box 51111, Room 1255-C Regulatory Affairs Los Angeles, CA 90051-0100 Palo Verde Nuclear Generating Station Mail Station 7636 Mr. Brian Almon P.O. Box 52034 Public Utility Commission Phoenix, AZ 85072-2034 William B. Travis Building P.O. Box 13326 Mr. Dwight C. Mims, Vice President 1701 N. Congress Avenue Regulatory Affairs and Plant Improvement Austin, TX 78701-3326 Palo Verde Nuclear Generating Station Mail Station 7605 Mr. Randall K. Edington P.O. Box 52034 Executive Vice President Phoenix, AZ 85072-2034 Nuclear/CNO Arizona Public Service Company P.O. Box 52034, Mail Station 7602 Phoenix, AZ 85072-2034