ML14183A740
| ML14183A740 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 06/13/1996 |
| From: | Mozafari B NRC (Affiliation Not Assigned) |
| To: | Hinnant C CAROLINA POWER & LIGHT CO. |
| References | |
| GL-95-03, GL-95-3, TAC-M92268, NUDOCS 9606180366 | |
| Download: ML14183A740 (5) | |
Text
Mr. C. S. Hinnant, Vi resident June 13, 1996
.Car.oqlina Power & Lighampany H. B. Robinson Steam Electric Plant, Unit No. 2 3581 West Entrance Road Hartsville, South Carolina 29550
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - GENERIC LETTER 95-03, "CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR TUBES," H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 (TAC NOS. M92268)
Dear Mr. Hinnant:
On April 28, 1995, the NRC issued Generic Letter (GL) 95-03, "Circumferential Cracking of Steam Generator Tubes," to request that licensees complete the certain actions and submit information concerning experience and detection of circumferential cracking in steam generator tubes.
The NRC staff is reviewing and evaluating your response to GL 95-03. Additional information, as discussed in the enclosure, is requested in order for the staff to complete the review. We request that you respond within 30 days.
The information collections contained in this request are covered by the Office of Management and Budget clearance number 3150-0011, which expires July 31, 1997.
The public reporting burden for this collection of information is estimated to average 350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> per response, including the time for reviewing instructions, searching existing data sources, gathering and maintaining the data needs, and completing and reviewing the collection of information. Send comments regarding this burden estimate or any other aspect of this collection of information, including suggestions for reducing this burden, to the Information and Records Management Branch, (T-6 F33), U.S.
Nuclear Regulatory Commission, Washington, D.C., 20555-0001, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150 0011), Office of Management and Budget, Washington, D.C. 20503.
Sincerely, (Original Signed By)
Brenda Mozafari, Project Manager Project Directorate II-1 9606180366 960613 Division of Reactor Projects -
I/Il PDR ADOCK 05000261 Office of Nuclear Reactor Regulation P
PDR Docket No. 50-261
Enclosure:
Request for Additional Information cc w/enclosure:
See next page
_______170013 Distribution See next page FILENAME - G:\\ROBINSON\\ROB92268.RAI OFFICE LA:PDII-1 _ PMfDJI-1 D:PDII-1 qp I
NAME Dunnington ozafari Elmbro DATE
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/96 1//2/96
- /3/96 COPY ryNo Yes No Yes
Mr. C. S. Hinnant H. B. Robinson Steam Electric Carolina Power & Light Company Plant, Unit No. 2 cc:
Mr. William D. Johnson Mr. Dayne H. Brown, Director Vice President and Senior Counsel Department of Environmental, Carolina Power & Light Company Health and Natural Resources Post Office Box 1551 Division of Radiation Protection Raleigh, North Carolina 27602 Post Office Box 27687 Raleigh, North Carolina 27611-7687 Ms. Karen E. Long Assistant Attorney General Mr. Robert P. Gruber State of North Carolina Executive Director Post Office Box 629 Public Staff - NCUC Raleigh, North Carolina 27602 Post Office Box 29520 Raleigh, North Carolina 27626-0520 U.S. Nuclear Regulatory Commission Resident Inspector's Office Mr. Max Batavia, Chief H. B. Robinson Steam Electric Plant South Carolina Department of Health 2112 Old Camden Road Bureau of Radiological Health Hartsville, South Carolina 29550 and Environmental Control 2600 Bull Street Regional Administrator, Region II Columbia, South Carolina 29201 U.S. Nuclear Regulatory Commission 101 Marietta St., N.W., Ste. 2900 Mr. J. Cowan Atlanta, Georgia 30323 Manager Nuclear Services and Environmental Mr. Dale E. Young Support Department Plant General Manager Carolina Power & Light Company Carolina Power & Light Company Post Office Box 1551 - Mail OHS7 H. B. Robinson Steam Electric Plant Raleigh, North Carolina 27602 3581 West Entrance Road Hartsville, South Carolina 29550 Mr. Milton Shymlock U. S. Nuclear Regulatory Commission Public Service Commission 101 Marietta Street, N.W. Suite 2900 State of South Carolina Atlanta, Ga. 3023-0199 Post Office Drawer 11649 Columbia, South Carolina 29211 Mr. R. M. Krich Manager - Regulatory Affairs Carolina Power & Light Company H. B. Robinson Steam Electric Plant, Unit No. 2 3581 West Entrance Road Hartsville, South Carolina 29550
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION CONCERNING GENERIC LETTER 95-03, "CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR TUBES,"
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2
- 1.
The following areas have been identified as being susceptible to circumferential cracking:
- a. Expansion transition circumferential cracking
- b. Small radius U-bend circumferential cracking
- c. Dented location (including dented tube support plates) circumferential cracking
- d. Sleeve joint circumferential cracking In your response, areas b, c, and d were not specifically addressed.
Please submit the information requested in Generic Letter (GL) 95-03 per the guidance contained in the GL for this area (and any other area susceptible to circumferential cracking).
The staff realizes that some of the above areas may not have been addressed since they may not be applicable to your plant; however, the staff requests that you clarify this (e.g., no sleeves are installed; therefore, the plant is not susceptible to sleeve joint circumferential cracking).
If a voltage threshold is used for determining the severity of dented locations (if applicable), provide the calibration procedure used (e.g.,
2.75 volts peak-to-peak on 4-20% through-wall ASME holes at 550/130 mix).
- 2.
In your response, it was indicated that-the next steam generator tube inspections would primarily be performed with a bobbin coil with some rotating pancake coil probe examination of manufacturing burnishing mark (MBM) indications.
Please indicate whether the MBM indications are located at regions susceptible to circumferential cracking.
Furthermore, given that the bobbin coil is not qualified for the detection of circumferentially oriented indications per the Electric Power Research Institute Guidelines which were cited in your response, please discuss the basis for your statement that the planned inspections are effective in detecting precursors to circumferential steam generator tube cracking as well as actual circumferential cracks (i.e., does data exist that supports that the bobbin coil is capable of reliably detecting prototypic circumferential indications at the locations susceptible to circumferential cracking, thereby ensuring that these regions were, in fact, inspected).
- 3.
During the Maine Yankee outage in.July/August 1994, several weaknesses were identified in their eddy current program as detailed in NRC Information Notice 94-88, "Inservice Inspection Deficiencies Result in Severely Degraded Steam Generator Tubes."
In Information Notice 94-88, the staff observed that several circumferential indications could be
-2 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.,
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 or not 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 Maine 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).
June 13, 1996 Distribution KDE~ii Ee PUBLIC PDII-1 RF S. Varga J. Zwolinski OGC ACRS K. Karwoski M. Shymlock, RH