ML17311B334
| ML17311B334 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 01/02/1996 |
| From: | Thomas C NRC (Affiliation Not Assigned) |
| To: | Stewart W ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| References | |
| GL-95-03, GL-95-3, TAC-M92261, TAC-M92262, TAC-M92263, NUDOCS 9601160209 | |
| Download: ML17311B334 (10) | |
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January 2,
1996 Hr. William L. Stewards Executive Vice President, Nuclear Arizona Public Services Company Post Office Box 53999
- Phoenix, Arizona 85072-3999
SUBJECT:
RE(VEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 95-03 PALO VERDE NUCLEAR GENERATING STATION (TAC NOS.
- H92261, H92262, AND H92263)
Dear Hr. Stewart:
1 t
V The NRC staff has reviewed Arizona Public Service Company s June 27,
- 1995, response to Generic Letter 95-03, "Circumferential Cracking of Steam Generator Tubes,"
and'has found the response incomplete in certain areas.
These areas are discussed in'the enclosedrequest for additional'information.
To help us meet our review schedule, we request that you respond to this request for additional information in writing within 30 days of receiving this letter.
This request is "within the original reporting burden for information collection of 350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> covered by the Office of Management and Budget clearance number 3150-0011, which expires July 31, 1997.
If you have any questions, please contact me at 301-415-1325.
Sincerely, Docket Nos.
STN 50-528, STN 50-529 and STN 50-530
Enclosure:
Request for Additional Information cc w/encl:
See next page Original signed by:
Charles R. Thomas, Project Manager Project Directorate IV-2 Division of Reactor projects III/IV Office of Nuclear Reactor regulation DISTRIBUTION:
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January 2, 1996 Hr. WilIiam L. Stew~.
Executive Vice President, Nuclear Arizona Public Services Company Post Office Box 53999 Phoenix, Arizona 85072-3999
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 95-03 PALO VERDE NUCLEAR GENERATING STATION (TAC NOS. H92261,
- H92262, AND M92263)
Dear Hr. Stewart:
C The NRC staff has reviewed Arizona Public Service Company's June 27,
- 1995, response to Generic Letter 95-03, "Circumferential Cracking of Steam Generator Tubes," and has found the response incomplete in certain areas.
These areas are discussed in the enclosed request for additional information.
To help us meet our review schedule, we request that you respond to this request for additional information in writing within 30 days of receiving this letter.
This request is within the original reporting burden for information collection of 350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> covered by the Office of Management and Budget clearance number 3150-0011, which expires July 31, 1997.
If you have any questions, please contact me at 301-415-1325.
Sincerely, Docket Sos. SBl,50-528, STN 50-529 and 5TN 50-530 Enclosure Request for Additional Information cc w/encl.
.See next page Original signed by:
Charles R. Thomas, Project Manager Project Directorate IV-2 Division of Reactor projects III/IV Office of Nuclear Reactor regulation DISTR IBUNION:
Docket Fife JRoe WBateman EPeyton PDIV-2 Reading
- WJohnson, RIV TSullivan, EHCB KKarwoski PUBLIC EAdensam CThomas
- JDyer, RIV DHcDonald
- KPerkins, WCFO RIV DOCUHEMT NAME:
PV92261.BWI'FC NAME DATE PDIV.-2 LA PDIV-2 PH CThomas:
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 20555-0001 January 2,
1996 Hr. William L. Stewart Executive Vice President, Nuclear Arizona Public Services Company Post Office Box 53999
- Phoenix, Arizona 85072-3999
SUBJECT:
RE(VEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 95-03 PALO VERDE NUCLEAR GENERATING STATION (TAC NOS.
- M92261, H92262, AND H92263)
Dear Hr. Stewart:
The NRC staff has reviewed Arizona Public Service Company's June 27,
- 1995, response to Generic Letter 95-03, "Circumferential Cracking of Steam Generator Tubes,"
and has found the response incomplete in certain areas.
These areas are discussed in the enclosed request for additional information.
To help us meet our review schedule, we request that you respond to this request for additional information in writing within 30 days of receipt of this letter.
This request is within the original reporting burden for information collection of 350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> covered by the Office of Management and Budget clearance number 3150-0011, which expires July 31, 1997.
If you have any questions, please contact me at 301-415-1325.
Sincerely, Docket Nos.
STN 50-528, STN 50-529 and STN 50-530 Charles R. Thomas, Project Manager Project Directorate IV-2 Division of Reactor projects III/IV Office of Nuclear Reactor regulation
Enclosure:
Request for Additional Information cc w/encl:
See next page
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V Mr. William L. Stewart cc w/encl:
Mr. Steve Olea Arizona Corporation Commission 1200 W. Washington Street
- Phoenix, Arizona 85007 T.
E. Oubre, Esq.
Southern California Edison Company P. 0.
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 5 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 Mr. Aubrey V. Godwin, Director Arizona Radiation Regulatory Agency 4814 South 40 Street
- Phoenix, Arizona 85040 Mr. Curtis Hoskins
, Executive Vice President and Chief Operating Officer Palo Verde Services 2025 N. 3rd Street, Suite 200 Phoenix, Arizona 85004 Roy P.
Lessey, Jr.,
Esq.
Akin, Gump, Strauss, Hauer and Feld El Paso Electric Company 1333 New Hampshire Avenue, Suite 400 Washington, DC 20036 Ms. Angela K. Krainik, Manager Nuclear Licensing Arizona Public Service Company P.O.
Box 52034 Phoenix, Arizona 85072-2034
PALO VERDE NUCLEAR GENERATING STATION UNITS 1
2 AND 3 OCKET NOS.
STN 50-528 STN 50-529 AND STN 50-530 FOLLOMUP RE VEST FOR ADDITIONA INFORMATION REGARDING GENERIC ETTER 95-03 "CIRCU F ENTIAL CRACKING 0 M GENERATOR UBES" There appear to be some discrepancies in your Generic Letter 95-03 response regarding the examinations to be performed during the next outage at Units 1, 2, and 3 at the expansion transition region.
In Section IX, for example, you state that a 100 percent plus-point motorized rotating pancake coil (MRPC) exam will be performed in U3R5.
This is consistent with Table 3.
However, in Section X, you state that a 20 percent initial sample will be performed and the sample will be expanded to 100 percent if a circumferential indication is found and 12 months have passed since the last 100 percent inspection.
Furthermore, in Section X you state that 1000 tubes (approximately 10 percent) will be examined in the cold leg at the expansion transition during U3R5; however, this program may be discontinued for UlR6 and U2R6 pending the Unit 3 results.
Table 3, however, indicates that 10 percent of the cold-leg expansion transitions will be examined during U2R6.
As you noted in your Generic Letter 95-03 response, these discrepancies may be a result of the uncertainties associated with the allowable run times for Units 1, 2, and 3.
However, please clarify the inspections to be performed at the expansion transition during the next outage at Unit 1,2, and3.
In your response, you indicated that U-bend (Row 1 and 2) and square bend inspections were performed and that no indications of circumferential cracking were reported.
Please clarify the extent of these examinations (e.g.,
3 percent of the tubes in Row 1 and 2). If this region is susceptible to circumferential cracking, please provide the future inspection plans for this region.
In your response, you stated that there has been no evidence of "severe" denting of the Palo Verde steam generators.
Please clarify what is meant by severe denting.
If a voltage threshold is used for determining the severity of dented locations, provide the calibration procedure used (e.g.,
2.75 volts peak-to-peak on 4-20 percent through-wall ASME holes at 550/130 mix).
In addition, provide the past inspection scope and your future inspection plans for dented locations if these areas are susceptible to circumferential cracking.
During the Haine Yankee outage in July and August 1994, several weaknesses were identified in their eddy current program.
The staff discussed these deficiencies in NRC Information Notice 94-88, "Inservice Inspection Deficiencies Resulting in Severely Degraded Steam Generator
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Tubes,"
and observed that several circumferential indications could be traced back to earlier inspections when the data was reanalyzed using terrain plots.
These terrain plots had not been generated as part of the original field analysis for these tubes.
For the rotating pancake coil (RPC) examinations performed at your plant at locations susceptible to circumferential cracking during the previous inspection (i.e., the previous inspection per your Generic Letter 95-03 response),
discuss the extent to which terrain plots were used to analyze the eddy current data.
If terrain plots were not routinely used at locations susceptible to circumferential cracking, discuss whether the RPC eddy current data has been reanalyzed using terrain mapping of the data.
If terrain plots were not routinely used during the outage and your data has not been reanalyzed with terrain mapping of the data, discuss your basis for not reanalyzing your previous RPC data in light of the findings at Haine Yankee.
Discuss whether terrain plots will be used to analyze the RPC eddy current data at locations susceptible to circumferential cracking during your next steam generator tube inspection (i.e., the next inspection per your Generic Letter 95-03 response).
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