ML17312B447
| ML17312B447 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 05/16/1997 |
| From: | Clifford J NRC (Affiliation Not Assigned) |
| To: | James M. Levine ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| References | |
| GL-95-03, GL-95-3, TAC-M92261, TAC-M92262, TAC-M92263, NUDOCS 9705230324 | |
| Download: ML17312B447 (8) | |
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t UNITED STATES t NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 16, 1997
$p 99t/P~< $94>
Hr. James H. Levine Executive Vice President, Nuclear Arizona Public Service Company Post Office Box 53999
- Phoenix, Arizona 85072-3999
SUBJECT:
COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 95-03, "CIRCUMFERENTIAL CRACKING OF STEAN GENERATOR TUBES,"
DATED APRIL 28,
- 1995, FOR THE PALO VARDE NUCLEAR GENERATING STATION (TAC NOS.
- H92261, H92262, AND H92263)
Dear Hr. Levine:
On April 28, 1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 95-03, "Circumferential Cracking of Steam Generator Tubes," to all holders of operating licenses or construction permits for pressurized-water reactors.
The NRC issued GL 95-03 for three principal reasons:
(1)
Notify addressees about the safety significance of the recent steam generator tube inspection findings at Maine Yankee Atomi,c Power Station.
(2)
Request that all addressees implement the actions described within the generic letter.
(3)
Require that all addressees submit to the NRC a written response regarding implementation of the requested actions.
In addition, GL 95-03 alerted addressees to the importance of performing comprehensive examinations of steam generator tubes using techniques and equipment capable of reliably detecting the types of degradation to which the steam generator tubes may be susceptible.
The staff also noted that the performance of steam generator tube examinations is controlled, in part, by Appendix B to Title 10, Part 50, of the Code of Federal Regulations (10 CFR Part 50).
In GL 95-03, the NRC staff also requested that licensees take the following actions:
(1)
Evaluate recent operating sizing of circumferential their plants.
experience with respect to the detection and indications to determine the applicability to (2)
On the basis of the evaluation in Item (1) above, as well as past inspection scope and results, susceptibility to circumferential cracking, threshold of detection, expected or inferred crack growth
- rates, and other relevant factors, develop a safety assessment justifying continued oper'ation until the next scheduled steam generator tube inspections.
9705230324 9705ib PDRI
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James H. Levine May 16, i997 (3)
Develop plans for the next steam generator tube inspections as they
,pertain to the detection of circumferential cracking.
The inspection plans should address, but not be limited to, scope (including sample expansion criteria, if applicable),
- methods, equipment, and criteria (including personnel training and qualification).
To document the outcome of these
- actions, the NRC staff requested that addressees prepare and submit the following:
(1)
A safety assessment justifying continued operation, predicated on the evaluation performed in accordance with requested actions 1 and 2
(above).
(2)
A summary of the inspection plans developed in accordance with requested action 3 (above) and a schedule for'he next planned inspection.
V In response to GL 95-03, you provided letters dated June 27,
- 1995, and February 8, 1996, for Palo Verde Units 1, 2,
and 3.
These submittals provided the information requested by GL 95-03.
We are therefore closing TAC Nos.
- H92261, M92262, and H92263.
For your information, the staff's findings regarding this issue are contained in NUREG-1604, "Circumferential Cracking, of Steam Generator Tubes."
If you have any questions regarding this matter, please contact me at (301) 415-1352.
cc:
See next page Sincerely, Original Signed By James W. Clifford, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos.
STN 50-528, STN 50-529 DISTRIBUTION:
and STN 50-530 Docket File ACRS PUBLIC PDIV-2 Reading J.
Roe
- OGC, 015B18 E.
Adensam K. Perkins, WCFO W. Bateman P.
- Gwynn, RIV J. Clifford Q. Kirsch, WCFO E.
Peyton S'.
Dembek K.'arwoski
'Strosnider DOCUMENT NAME: PV92261.LTR PDIV-2 LA OFC PDIV-2/PH E~ey o%"
5/lk,/97 NAME JCl'ord:ye DATE 5/IA/97 OFFICIAL RECORD COPY
I
Hr. James H. Levine Hay 16, 1997 (3)
Develop plans for the next steam generator tube inspections as they pertain to the detection of circumferential cracking.
The inspection plans should address, but not be limited to, scope (including sample expansion criteria, if applicable),
- methods, equipment, and criteria (including personnel training and qualification).
To document the outcome of these actions, the NRC staff requested that addressees prepare and submit the following:
(1)
A safety assessment justifying continued operati'on, predicated on the evaluation performed in accordance with requested actions 1 and 2, (above).
(2)
A summary of the inspection plans developed in accordance with requested action 3 (above) and a schedule for the next planned inspection.
In response to GL 95-03, you provided letters dated June 27,
- 1995, and February 8, 1996, for Palo Verde Units 1, 2, and 3.
These submittals provided the information requested by GL 95-03.
We are therefore closing TAC Nos.
- H92261, H92262, and H92263.
For your information, the staff's findings regarding this issue are contained in NUREG-1604, "Circumferential Cracking of Steam Generator Tubes."
If you have any questions regarding this matter, please contact me at (301) 415-1352.
Sincer ely, Docket Nos.
STN 50-528, STN 50-529 and STN 50-530 cc:
See next page J
mes W. Clif ord, Senior Project Hanager Project Directorate IV.-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
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Mr. James M. Levine May 16, i997 CC:
Hr. Steve Olea Arizona Corporation Commission 1200 W. Washington Street Phoenix, Arizona 85007 Do glas Kent Porter Senior Counsel Southern California Edison Company Law Department, Generation Resources P.O.
Box 800
- Rosemead, California 91770 Senior Resident Inspector USNRC P. 0.
Box 40 Buckeye, Arizona 85326 Regional Administrator, Region IV U. S. Nuclear Regulatory Commission Harris Tower
& Pavillion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064
- Chairman, Board of Supervisors ATTN:
Chairman 301=W. Jefferson, 10th Floor
- Phoenix, Arizona 85003 Hr. Aubrey V. Godwin, Director Arizona Radiation Regulatory Agency 4814 South 40 Street
- Phoenix, Arizona 85040 Hs. Angela K. Krainik, Manager Nuclear Licensing Arizona Public Service Company P.O.
Box 52034 Phoenix, Arizona 85072-2034 Hr. John C. Horne, Vice President Power Supply Palo Verde Services 2025 N. Third Street, Suite 220
- Phoenix, Arizona 85004 Hr. David Summers Public Service Company of New Mexico 414 Silver SW, 00604 Albuquerque, New Mexico 87102 Mr. Robert D. Bledsoe Southern California Edison Company 14300 Mesa
- Road, Drop D41-SONGS San Clemente, California 92672 Mr. Robert Henry Salt River Project 6504 East Thomas Road Scottsdale, Arizona 85251 Terry Bassham, Esq.
General Counsel El Paso Electric Company 123 W. Mills El Paso, Texas 79901 Mr. Robert Burt Los Angeles Department of Water
& Power Southern California Public Power Authority 111 North Hope Street, Room 1255-B Los Angeles, California 90051
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