ML030770116
| ML030770116 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/20/2003 |
| From: | Donohew J NRC/NRR/DLPM/LPD4 |
| To: | |
| Shared Package | |
| ML030830280 | List: |
| References | |
| Download: ML030770116 (7) | |
Text
March 20, 2003 LICENSEE:
Arizona Public Service Company (APS)
FACILITIES:
Palo Verde Nuclear Generating Station
SUBJECT:
MEETING WITH REPRESENTATIVES OF ARIZONA PUBLIC SERVICE COMPANY FOR PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 A meeting was held on Wednesday, March 12, 2003, between the Nuclear Regulatory Commission (NRC) staff and the licensee for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Palo Verde). The meeting was held at the request of the licensee to inform the NRC about (1) the current status of fuel performance, control element assembly (CEA) replacement, and implementation of the NRC-approved CENTS computer code for the three units and (2) the current activities of the licensee for spent fuel dry cask storage at the site for the three units.
The spent fuel dry cask storage project is the construction of an Independent Spent Fuel and Storage Installation (ISFSI) on part of the Palo Verde plant site. The notice for the meeting was issued on February 25, 2003. is the list of attendees. Enclosure 2 is the slides handed out by the licensee. There was no handout from the NRC staff. Enclosure 3 is a list of acronyms used by the licensee in its handout.
The agenda for the meeting is the following, from the third slide of Enclosure 2 (there are two slides for each page of the first part, nuclear fuel update, of the enclosure):
Reactivity Management (Slides 4 through 7)
CENTS and Replacement Steam Generator (RSG)/Power Uprate (Slides 8 through 10)
Fuel Performance (Slides 11 through 17)
Core Protection Calculator (CPC) Replacement (Slides 18 through 20)
Control Element Assembly (CEA) Replacement (Slides 21 through 25)
Dry Cask Storage Update (Slides 26 through 28)
Before addressing the agenda, the licensee initially presented an overview of what had happened in 2002 (Slide 2 of Enclosure 2) with respect to fuel for the three units.
The licensee presented the information in its handout, and the NRC staff asked questions. The approval of the (1) CENTS computer code being added to the core operating limits report (COLR) and (2) ZIRLO fuel cladding technical specification were licensing amendments previously approved by NRC for the three units. The amendments were issued October 15, 2001, and March 12, 2002, respectively. The CENTS computer code is being used in the replacement steam generator and power uprate (RSG/PUR) amendment request that the licensee submitted to NRC on December 21, 2001. The amendment to upgrade the core protection calculator (CPC) was submitted November 7, 2002.
The licensee discussed fuel performance for the units in terms of (1) integrated fuel clad strategy including advanced clad alloys, (2) primary chemistry, (3) crud/oxide, (4) low duty core designs, (5) re-designed core lattice of fuel assemblies, and (6) long range fuel inspection. The reference to the Alloy A lead test assembly (LTA) is a reference to advanced clad alloys where the continued testing of the LTA in Unit 3 for a fourth operating cycle was approved in the exemption approved by NRC on October 16, 2001. Crud refers to material deposits adhering to the fuel cladding.
In the update on the CEA investigation (Slides 21 through 25), the licensee stated that all full length CEAs in the units have been replaced, the lifetime software which had been used to determine the CEA lifetime has been replaced by the determination of more conservative lifetime values, new full length CEAs are being designed, and that part length CEAs in the units will be replaced with full length CEAs after the technical specifications are amended to remove the words part length. The reference to YGN in Slide 23 stands for a plant in South Korea.
The last slides on the Palo Verde dry cask storage is the current status of the ISFSI that has been built on the Palo Verde Nuclear Generating Station site. The first canister was loaded with spent fuel assemblies on March 3, 2003. The licensee stated that it would develop the lessons learned from this first loading and apply them to the future loading of canisters. The plan is to load 10 casks per year. Each canister is loaded into a cask to transfer the spent fuel to the ISFSI.
The licensee completed its presentation and the meeting was closed.
/RA/
Jack Donohew, Senior Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No(s). 50-528, 50-529, and 50-530
Enclosures:
- 1. List of Meeting Attendees
- 2. Licensees Handout (ADAMS Accession No. ML030710565)
- 3. List of Acronyms cc w/encls: See next page
Palo Verde Generating Station, Units 1, 2, and 3 cc:
Mr. Steve Olea Arizona Corporation Commission 1200 W. Washington Street Phoenix, AZ 85007 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 Harris Tower & Pavillion 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 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. Craig K. Seaman, Director Regulatory Affairs/Nuclear Assurance Palo Verde Nuclear Generating Station P.O. Box 52034 Phoenix, AZ 85072-2034 Mr. Hector R. Puente Vice President, Power Generation El Paso Electric Company 2702 N. Third Street, Suite 3040 Phoenix, AZ 85004 Mr. John Taylor Public Service Company of New Mexico 2401 Aztec NE, MS Z110 Albuquerque, NM 87107-4224 Mr. Jarlath Curran Southern California Edison Company 5000 Pacific Coast Hwy Bldg DIN San Clemente, CA 92672 Mr. Robert Henry Salt River Project 6504 East Thomas Road Scottsdale, AZ 85251 Terry Bassham, Esq.
General Counsel El Paso Electric Company 123 W. Mills El Paso, TX 79901 Mr. John Schumann Los Angeles Department of Water & Power Southern California Public Power Authority P.O. Box 51111, Room 1255-C Los Angeles, CA 90051-0100 Brian Almon Public Utility Commission William B. Travis Building P. O. Box 13326 1701 North Congress Avenue Austin, TX 78701-3326 Mr. Gregg R. Overbeck Senior Vice President, Nuclear Arizona Public Service Company P. O. Box 52034 Phoenix, AZ 85072-2034
- 3. List of Acronyms cc w/encls: See next page DISTRIBUTION:
PUBLIC PDIV-2 Reading RidsNrrDlpm (JZwolinski/TMarsh)
MKotzalas (NRR/PMAS)
RidsNrrDlpmLpdiv (HBerkow)
RCaruso (NRR/DSSA/SRXB)
SDembek LSmith (RGN-IV/DRP/RPB-E)
RidsNrrPMJDonohew UShoop (NRR/DSSA/SRXB)
RidsNrrLAMMcAllister SLWu (NRR/DSSA/SRXB)
RidsOgcRp SOConnor (NMSS/SFPO)
RidsAcrsAcnwMailCenter SMorris (EDO)
RidsRgn4MailCenter (AHowell)
DDuvigneaud Handouts: ML030710565 PKG: ML030830280 ADAMS Accession No.: ML030770116 NRC-001 OFFICE PDIV-2/PM PDIV-2/LA PDIV-2/SC NAME JDonohew MMcAllister SDembek DATE 3/20/2003 3/20/03 3/20/03 DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML030770116.wpd
LIST OF ATTENDEES AT MEETING OF MARCH 12, 2003 STATUS OF FUEL PERFORMANCE AND CEA REPLACEMENT NAME AFFILIATION J. Donohew NRC/NRR/PDIV-2 R. Caruso NRC/NRR/SRXB U. Shoop NRC/NRR/SRXB S.L. Wu NRC/NRR/SRXB S. OConnor NRC/NMSS/SFPO D. Duvigneaud NRC/NRR/PDIV-2 T. Weber APS R. Bandere APS B. Hansen APS Where:
= Arizona Public Service Company NMSS
= Office of Nuclear Material Safety and Safeguards NRC
= Nuclear Regulatory Commission NRR
= Office of Nuclear Reactor Regulation PDIV-2
= Project Directorate IV-2 SFPO
= Spent Fuel Project Office SRXB
= Reactor Systems Branch ENCLOSURE 1
LICENSEES HANDOUT FOR MARCH 12, 2003, MEETING ADAMS ACCESSION NO. ML030710565 ENCLOSURE 2
LIST OF ACRONYMS AFI Areas for improvement APS Arizona Public Service Company AgInCd Silver indium cadmium CEA Control element assembly CPC Core protection calculator FDI Fuel duty index FWLB Feedwater line break IASCC Irradiation assisted stress corrosion cracking LOP Loss of offsite power LTA Lead test assembly NFM Nuclear Fuel management P1M316 Designation of a specific fuel assembly in the core PLCEA Part length CEA PSV Power operated safety valve R13 Refueling Outage No. 13 RSG Steam generator replacement SABD Safety analysis basis document SF Single failure U1 Unit 1 U2C11 Unit 2 Operating Cycle 11 YGN Name of a plant in Korea ENCLOSURE 3