ML17228B278
| ML17228B278 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 09/19/1995 |
| From: | Norris J NRC (Affiliation Not Assigned) |
| To: | Goldberg J FLORIDA POWER & LIGHT CO. |
| References | |
| GL-95-03, GL-95-3, NUDOCS 9509220179 | |
| Download: ML17228B278 (6) | |
Text
C" C
September 19, l.
Hr. J.
H. Goldberg President Nuclear Division Florida Power and Light Company Post Office Box 14000 Juno
- Beach, Florida 33408-0420
SUBJECT:
ST.
LUCIE 1
AND 2 GL 95-03 REQUEST FOR ADDITIONAL INFORMATION
Dear Hr. Goldberg:
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, to 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 provided by Florida Power
- 5. Light Company for St.
Lucie 1
and 2.
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 your responses within 90 days from the date of receipt of this request.
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)
Jan A. Norris, Sr. Project Manager Project Directorate II-I Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Docket Nos.
50-335 and 50-389
Enclosure:
As stated cc w/enclosure:
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Hr. J.
H. Goldberg Florida Power and Light Company St. Lucie Plant CC:
Jack Shreve, Public Counsel Office of the Public Counsel c/o The Florida Legislature 111 West Madison Avenue, Room 812 Tallahassee, Florida 32399-1400 Senior Resident Inspector St.
Lucie Plant U.S. Nuclear Regulatory Commission 7585 S.
Hwy A1A Jensen
- Beach, Florida 34957 Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Dr'ive Tallahassee, Florida 32399-2100 J.
R.
Newman
- Morgan, Lewis
& Bockius 1800 H Street, N.W.
Washington, DC 20036 John T. Butler, Esquire
- Steel, Hector and Davis 4000 Southeast Financial Center Miami, Florida 33131-2398 Hr. Thomas R.L. Kindred County Administrator St. Lucie County 2300 Virginia Avenue Fort Pierce, Florida 34982 Mr. Charles
- Brinkman, Manager Washington Nuclear Operations ABB Combustion Engineering, Nuclear Power.
12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Hr. Bill Passetti Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Blvd.
Tallahassee, Florida 32399-0700 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W. Suite 2900 Atlanta, Georgia 30323 H. N. Paduano, Manager Licensing
& Special Programs Florida Power and Light Company P.O.
Box 14000 Juno
- Beach, Florida 33408-0420 D. A. Sager, Vice President St. Lucie Nuclear Plant P. 0.
Box 128 Ft. Pierce, Florida 34954-0128 Miami, Florida 33102 J. Scarola Plant General Manager St.
Lucie Nuclear Plant P.O.
Box 128 Ft. Pierce, Florida 34954-0128
ENCLOSURE 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 TSP) circumferential cracking d.
Sleeve joint circumferential cracking In your response, areas b, c, and d, were not specifically addressed for both units although it was indicated that circumferential cracking has also been observed at tube support-plate intersections and in the U-bend of a retired Combustion Engineering steam generator.
In addition, recirculating steam generators designed by another vendor have experienced circumferential cracking in the U-bend portion of tubes with small radius U-bends and at dented locations.
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).
In your response, it was indicated that between 7% and 14% of the total hot leg dented tube support plate intersections were inspected at St.
Lucie Unit 1.
Discuss the criteria used for determining which dents were examined.
If a dent voltage threshold is used for such a
determination, provide the calibration procedure used (i.e., 4.0 volts on 4-20% through-wall ASNE,holes at 550/130 mix).
In your response you indicated that the circumferential cracks identified at St.
Lucie were identified early in their lifetimes and were not of sufficient size to threaten mid-cycle leakage.
Please indicate how tubes with circumferential indications were dispositioned during the previous inspection outage.
For the tubes identified to have circumferential cracks at St.
Lucie 1
and 2 during the prior inspection, provide your assessment of the structural integrity of these tubes (i.e.,
were they capable of withstanding the pressure loadings of Regulatory Guide 1.121).
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 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.,
c4
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 circ'umferential
- 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 fi'ndings 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).