ML092750237
| ML092750237 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/03/2009 |
| From: | Lisa Regner License Renewal Projects Branch 2 |
| To: | Edington R Arizona Public Service Co |
| Regner L M, NRR/DLR, 415-1906 | |
| References | |
| TAC ME0254, TAC ME0255, TAC ME0256 | |
| Download: ML092750237 (7) | |
Text
November 3, 2009 Mr. Randall K. Edington Executive Vice President, Nuclear Mail Station 7602 Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3, LICENSE RENEWAL APPLICATION (TAC NOs. ME0254, ME0255 AND ME0256)
Dear Mr. Edington:
By letter dated December 11, 2008 and supplemented by dated April 14, 2009 and October 14, 2009, Arizona Public Service Company (APS) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 to renew Operating License Nos. NPF-41, NPF-51, and NPF-74 for the Palo Verde Nuclear Generating Station, Units 1, 2, and 3. The staff is reviewing the information contained in the license renewal application and has identified in the enclosure areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future.
Items in the enclosure were discussed with APS staff on September 16, 2009, and a mutually agreeable date for your response was determined to be 45 calendar days from the date of this letter. If you have any questions, please contact me at 301-415-1906 or by e-mail at Lisa.Regner@nrc.gov.
Sincerely,
/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
Enclosure:
As stated cc w/encl: See next page
ML092750237 OFFICE LA:DLR PM:RPB2:DLR BC:RPB2:DLR PM:RPB2:DLR NAME SFigueroa LRegner DWrona LRegner (Signature)
DATE 10/02/09 10/15/09 11/3/09 11/3/09
Letter to Randall K. Edington from Lisa M. Regner dated November 3, 2009
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3, LICENSE RENEWAL APPLICATION (TAC NOs. ME0254, ME0255 AND ME0256)
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ENCLOSURE PALO VERDE NUCLEAR GENERATING STATION LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION Part I. License renewal application (LRA) Time-Limited Aging Analyses (TLAAs) 4.2, Reactor Vessel Neutron Embrittlement Analysis, and 4.7.7, Absence of a TLAA for a Reactor Coolant Pump Flywheel Fatigue Crack Growth Analysis.
RAI 4.2.1-1 LRA Tables 4.2-3 to 4.2-5 documented the 54 effective full power year (EFPY) upper-shelf energy (USE) values for Units 1, 2, and 3. LRA Tables 4.2-6 to 4.2-8 documented their corresponding 54 EFPY RTPTS values. The staff found mistakes in these tables and requests corrections:
- 1. In Table 4.2-3 for Unit 1, the 54 EFPY USE values for the intermediate shell plates M-6701-2 and M-6701-3 are incorrect.
- 2. In Table 4.2-4 for Unit 2, all unirradiated USE values are incorrect.
RAI 4.2.1-2 LRA Section 4.2.1, Neutron Fluence, Upper Shelf Energy and Adjusted Reference Temperature (Fluence, USE, and ART), Tables 4.2-3 to 4.2-5 listed 54 EPPY USE values for the beltline materials of PVNGS, Units 1, 2, and 3. They are all derived in accordance with Regulatory Guide (RG) 1.99, Revision (Rev.) 2, Radiation Embrittlement of Reactor Vessel Materials, without using surveillance data. The applicant also stated, [t]he most recent coupon examination results also show that the decline in USE and increase in RTNDT [reference temperature] in plate and weld materials are less than originally predicted by RG 1.99, Revision 2. One can conservatively estimate the ART and USE values for the beltline materials without using credible multiple surveillance data only when the estimates based on all measured surveillance data in accordance with RG 1.99, Rev. 2 are lower. Please provide your basis for not considering all surveillance data. Add references (i.e., surveillance reports) to support your clarification.
RAI 4.2.1-3 The staff found that the WCAP-15589 report (ML003764418), Analysis of Capsule 38° from the Arizona Public Service Company Palo Verde Unit 1 Reactor Vessel Radiation Surveillance Program, labeled two surveillance data from Capsule 38° as intermediate shell plate M-6701-2 and used them in the chemistry factor calculation for this limiting plate. However, the WCAP-16374 report (ML051020500), Analysis of Capsule 230° from the Arizona Public Service Company Palo Verde Unit 1 Reactor Vessel Radiation Surveillance Program, dropped the two Capsule 38° surveillance data from the chemistry factor calculation for intermediate shell plate M-6701-2. A statement on page D-3 of the WCAP-16374 report indicates a possible misidentification of specimens: [t]he lower shell plate M4311-1 also has surveillance data but only one set up to this point (from Capsule 38°), thus it will not be evaluated. Please confirm that you misidentified surveillance specimens for PVNGS, Unit 1 in the WCAP-15589 report and explain how it happened. Or, explain the basis of discarding surveillance data from Capsule 38° in the WCAP-16374 report in calculating the chemistry factor for intermediate shell plate M-6701-2. Please confirm that Units 2 and 3, did not experience similar misidentifications as Unit 1.
RAI 4.7.7-1 The title of LRA Section 4.7.7 is Absence of a TLAA for a Reactor Coolant Pump Flywheel Fatigue Crack Growth Analysis. To demonstrate that this is true, please confirm that the underlying stress and fracture mechanics analysis for the flywheels is not a part of the current licensing basis for PVNGS, Units 1, 2, and 3, or the underlying stress and fracture mechanics analysis does not contain fatigue and fatigue crack evaluations.
RAI 4.7.7-2 Discuss the evaluation of past examination results from in-place ultrasonic volumetric examination of the areas of higher stress concentration at the bore and keyway approximately every three years and from a surface examination of all exposed surfaces and complete ultrasonic volumetric examination approximately every 10 years. If a fracture mechanics analysis was performed on any indications from the examinations, provide your TLAA evaluation or explain why it is not a TLAA.
Part II. Aging Management Program (AMP) B2.1.15, Reactor Vessel Surveillance RAI B2.1.15-1 LRA Section B2.1.15 states under Program
Description:
PVNGS, Units 1, 2, and 3, determined neutron embrittlement effects, consistent with RG 1.99, Rev. 2, by option 1[b],
Neutron Embrittlement Using Surveillance Data. This is misleading. The staff found from its review of LRA Section 4.2 that, after having considered option 1b of Generic Aging Lessons Learned Report (GALL) Aging Management Program (AMP) XI.M31, you actually used the more conservative option 1a, Neutron Embrittlement Using Chemistry Tables to evaluate USE and pressure-temperature limits for 60 years. Both options are consistent with RG 1.99, Rev. 2. Please make the necessary clarification.
RAI B2.1.15-2 LRA Section B2.1.15 stated under Operating Experience what the recent examination results of the reactor vessel surveillance data revealed regarding neutron fluence, USE, and RTNDT.
Evaluation of operating experience of this PVNGS AMP should not be limited to the recent examination results. Please expand your discussion to include all tested reactor vessel surveillance data.
Palo Verde Nuclear Generating Station, Units 1, 2, and 3 cc:
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 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 40 Buckeye, AZ 85326 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 Chairman Maricopa County Board of Supervisors 301 W. Jefferson, 10th Floor Phoenix, AZ 85003 Mr. Aubrey V. Godwin, Director Arizona Radiation Regulatory Agency 4814 S. 40th 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. John C. Taylor, Director, Nuclear Generation El Paso Electric Company 340 E. Palm Lane, Suite 310 Phoenix, AZ 85004 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 Highway, Bldg. D21 San Clemente, CA 92672 Mr. Robert Henry Salt River Project 6504 E. Thomas Road Scottsdale, AZ 85251 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. Brian Almon Public Utility Commission William B. Travis Building P.O. Box 13326 1701 N. Congress Avenue Austin, TX 78701-3326