ML040760860
| ML040760860 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/18/2004 |
| From: | Moroney B NRC/NRR/DLPM/LPD2 |
| To: | Stall J Florida Power & Light Co |
| Moroney B, NRR/DLPM, 415-3974 | |
| References | |
| TAC MC1177 | |
| Download: ML040760860 (5) | |
Text
March 18, 2004 Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
SAINT LUCIE PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST NO. 22 (TAC NO. MC1177)
Dear Mr. Stall:
By letter dated October 15, 2003, Florida Power and Light Company submitted Relief Request No. 22 for Saint Lucie Unit 1 to utilize an external weld between small bore nozzles and Reactor Coolant System piping as an alternative to the welding requirements contained in the American Society of Mechanical Engineers code.
The U.S. Nuclear Regulatory Commission staff has reviewed your submittal and finds that a response to the enclosed request for additional information (RAI) is needed before we can complete the review. This request was discussed with your staff on March 9 and March 16, 2004.
If you have any questions, please feel free to contact me at (301) 415-3974.
Sincerely,
/RA/
Brendan T. Moroney, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-335
Enclosure:
RAI cc w/encl: See next page
ML040760860 OFFICE PDII-2/PM PDII-2/LA EMCB/SC EMEB/SC PDII-2/SC (A)
NAME BMoroney BClayton GGeorgiev for TChan KManoly MMarshall for WBurton DATE 3/16/04 3/16/04 3/17/04 3/12/04 3/18/04
REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST NO. 22 SAINT LUCIE PLANT, UNIT 1 DOCKET NO. 50-335 1.
What nondestructive examinations (NDE) will be done prior to, during, and after the repair (including the base material of the pipe and nozzle)? How will the repair weld be inspected and determined to be acceptable?
2.
According to the proposed repair, the nozzle will be replaced during the next refueling outage. Discuss why the plant is not replacing the nozzle(s) at the time the leakage is identified (during the current refueling outage).
3.
Which nozzles are candidates for this repair? Use a diagram to show location of the subject nozzles.
4.
Relief Request 23 discusses the hardship associated with performing the Code replacement, yet part of the alternative for Relief Request 22 states that "Any nozzle repaired due to leakage will be replaced at the subsequent outage." What replacement activities will be performed during the subsequent outage for the subject nozzles?
5.
Discuss the effects on the nozzle, weld and piping associated with the proposed repair method leaving the nozzle fixed at both sides of the pipe. Discuss the effects on stresses, crack growth rates, and thermal expansion on the repair design verification and the flaw evaluation.
6.
Without performing NDE to evaluate the flaw, provide justification for the initial flaw size being confined to the weld. How will any degradation of the carbon steel pipe be assessed? How will any cracking in the nozzle be assessed? What is the justification that the flaws will not extend into the ferritic base metal of the pipe or into the nozzle material?
- 7., Pages 4 and 5 list the primary and secondary stress intensities and compares them to the value of 3Sm. The primary and secondary stress intensities are different than the values listed in the analysis, References 3 and 4. These values are also larger than 3Sm. An example of the values listed are as follows:
RTD Nozzle, Inside Nozzle 41,364ksi < 3 Sm (69.9 ksi)
The staff finds that 41,364 ksi is larger than 69.9 ksi. The value in the calculation documents show that the proper value is 41.364 ksi. It appears that the stress values contain a typographical error. The values need to be corrected and the significant figures need to be resolved.
8.
What mockups have been done to verify the welding procedure? What requirements are being followed for this repair? Is a preheat and/or postweld heat treatment required? Please explain. What is the proposed weld material for the repair? Is it Inconel 52, SFA-5.14, Class ENiCrFe-7?
9.
What effects does the leakage have on the proposed repair procedure? (Weld prep, cleanliness, weld impurities)
The following questions relate to Westinghouse calculation CN-CI-02-51.
10.
In Section 6.2 Input, provide the corresponding number of transients associated with each of transients 1 through 16.
11.
On the outside wall of a nozzle, the thermal expansion load causes an average shear stress between the weld and the nozzle surface. This shear stress was not included with the normal stress components. Per NB-3215 and NB-3216, stresses used in the fatigue calculations at a given location are the principal stresses determined from the normal and shear stresses at the location. Provide fatigue cumulative usage factors at the outside nozzle walls based on principal stresses calculated at the interface between the nozzle and the weld.
12.
Provide the basis for the equation used to calculate the allowable number of cycles, N.
13.
Provide the fatigue calculations for the hot leg at the location of the repair weld, and demonstrate that the cumulative usage factor will not exceed 1.0.
Mr. J. A. Stall ST. LUCIE PLANT Florida Power and Light Company cc:
Senior Resident Inspector St. Lucie Plant U.S. Nuclear Regulatory Commission P.O. Box 6090 Jensen Beach, Florida 34957 Craig Fugate, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 M. S. Ross, Attorney Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Douglas Anderson County Administrator St. Lucie County 2300 Virginia Avenue Fort Pierce, Florida 34982 Mr. William A. Passetti, Chief Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Tallahassee, Florida 32399-1741 Mr. William Jefferson, Jr.
Site Vice President St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957-2000 Mr. G. L. Johnston Plant General Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957 Mr. Terry Patterson Licensing Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957 Vice President, Nuclear Operations Support Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Rajiv S. Kundalkar Vice President - Nuclear Engineering Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. J. Kammel Radiological Emergency Planning Administrator Department of Public Safety 6000 SE. Tower Drive Stuart, Florida 34997