ML18011B008
| ML18011B008 | |
| Person / Time | |
|---|---|
| Site: | Harris |
| Issue date: | 09/05/1995 |
| From: | Le N NRC (Affiliation Not Assigned) |
| To: | Robinson W CAROLINA POWER & LIGHT CO. |
| References | |
| GL-95-03, GL-95-3, NUDOCS 9509080275 | |
| Download: ML18011B008 (8) | |
Text
September 5,
1995 Mr.
W.
R. Robinson, Vice President Shearon Harris Nuclear Power Plant Carolina Power 8 Light Company Post Office Box 165 - Hail Code:
Zone 1
New Hill-', North Carolina 27562-0165
SUBJECT:
GENERIC LETTER 95-03, "CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR TUBES" SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 (TAC NO. H92246)
Dear Hr. Robinson:
'f On April 28, 1995, the U.S. Nuclear Regulatory Commission issued Generic Letter (GL) 95-03 "Circumferential Cracking of Steam Generator Tubes" which requested addressees to evaluate recent operating experience related to circumferential cracking, justify continued operation until the next scheduled steam generator tube inspections, and to develop plans for the next steam generator tube inspections; The staff has reviewed the response dated June 27, 1995, provided by the Carolina Power
& Light Company for the Shearon Harris Nuclear Power Plant, Unit l.
As a result of the review of your response, the staff has identified areas for which additional information arid/or clarification is needed.
The enclosure to this letter contains the information needed for the staff to complete its review of your response to GL 95-03.
Please provide the requested response 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.
Sincerely, (Original Signed By)
Ngoc B. Le, Project Manager Project Directorate II-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Docket No. 50-400
Enclosure:
As stated cc: w/enclosure:
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 5,
1995 Mr. W.
R. Robinson, Yice President Shearon Harris Nuclear Power Plant Carolina Power
& Light Company Post Office Box 165 Mail Code:
Zone 1
New Hill, North Carolina 27562-0165
SUBJECT:
GENERIC LETTER 95-03, "CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR TUBES" - SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 (TAC NO. M92246)
Dear Mr. Robinson:
On April 28, 1995, the U.S. Nuclear Regulatory Commission issued Generic Letter (GL) 95-03 "Circumferential Cracking of Steam Generator Tubes" which requested addressees to evaluate recent operating experience related to circumferential cracking, justify continued operation until the next scheduled steam generator tube inspections, and to develop plans for the next steam generator tube inspections.
The staff has reviewed the response dated June 27, 1995, provided by the Carolina Power & Light Company for the Shearon Harris Nuclear Power Plant, Unit l.
As a result of the review of your response, the staff has identified areas for which additional information and/or clarification is needed.
The enclosure to this letter contains the information needed for the staff to complete its review of your response to GL 95-03.
Please provide the requested response 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.
Sincerely, Docket No. 50-400
Enclosure:
As stated cc: w/enclosure:
See next page Ngoc B. Le, Project Manager Project Directorate II-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Mr.
W. R. Robinson Carolina Power 8 Light Company Shearon Harris Nuclear Power Plant Unit 1
CC:
Mr. R.
E. Jones General Counsel Legal Department Carolina Power 5 Light Company Post Office Box 1551
- Raleigh, North Carolina 27602 Resident Inspector/Harris NPS c/o U.S. Nuclear Regulatory Commission 5421'Shearon Harris Road New Hill, North Carolina 27562-9998 Kar en E.
Long Assistant Attorney General State of North Carolina Post Office Box 629
- Raleigh, North Carolina 27602 Public Service Commission State of South Carolina Post Office Drawer 11649
- Columbia, South Carolina 29211 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta St.,
N.W. Suite 2900 Atlanta, Georgia 30323 Mr. Dayne H. Brown, Director Division of Radiation Protection N.C. Department of Environmental Division of Radiation Protection Commerce K Natural Resources Post Office Box 27687
- Raleigh, North Carolina 27611-7687 Mr. H.
W. Habermeyer, Jr.
Vice President Nuclear Services Department Carolina Power 5 Light Company Post Office Box 1551
- Raleigh, North Carolina 27602 Mr. J.
W. Donahue Plant Manager - Harris Plant Carolina Power 8 Light Company Shearon Harris Nuclear Power Plant Post Office Box 165, MC: Zone 1
New Hill, North Carolina 27562-0165 Mr. Robert P. Gruber Executive Director Public Staff NCUC Post Office Box 29520
- Raleigh, North Carolina 27626 Chairman of the North Carolina Utilities Commission Post Office Box 29510 Raleigh, North Car olina 27626-0510 T. D. Walt
- Manager, Regulatory Affairs Carolina Power 5 Light Company Shearon Harris Nuclear Power Plant P. 0.
Box 165, Mail Zone 1
New Hill, North Carol ina 27562-0165 Mr. Vernon Malone, Chairman Board of County Commissioners of Wake County P. 0.
Box 550
- Raleigh, North Carolina 27602 Mr. Henry Dunlap, Chairman Board of County Commissioners of Chatham County P. 0.
Box ill Pittsboro, North Carolina 27312
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1 REQUEST FOR ADDITIONAL INFORMATION ENCL(ASSI=.
RE:
GENERIC LETTER 95-03, "CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR TUBES" SHEARON HARRIS NUCLEAR POWER PLANT, UNIT I (TAC NO. M92246) 2.
In your response, you indicated that sample expansion will be based on the Electric Power Research Institute PWR Steam Generator Examination Guidelines or
.the technical specifications, whichever is more conservative.
Please clarify the expansion criteria for all locations susceptible to circumferential cracking.
It was indicated that dents greater than 5.0 volts will be inspected with a probe qualified for circumferential crack detection.
Please provide the procedures used for sizing the dents. If a dent voltage threshold is used (e.g.,
5.0 volts) for determining the size of the dents, provide the calibration procedure used.
If the procedure is identical to the procedure for the voltage-based repair criteria, a detailed description is not necessary.
3.
Several plants with preheater model steam generators expanded tubes into the tube support plate in the preheater region to minimize the potential for vibration-induced wear.
Since these expansions contain similarities to other expanded regions which have experienced circumferential cracking, please discuss whether or not this area is susceptible to circumferential cracking. Ifthis area is susceptible to circumferential cracking, please submit the information requested in Generic Letter (GL) 95-03 per the guidance contained in the GL.
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