ML20203F510
| ML20203F510 | |
| Person / Time | |
|---|---|
| Issue date: | 02/12/1999 |
| From: | Carpenter C NRC (Affiliation Not Assigned) |
| To: | Terry C AFFILIATION NOT ASSIGNED, NIAGARA MOHAWK POWER CORP. |
| Shared Package | |
| ML20136F620 | List: |
| References | |
| TAC-M99870, NUDOCS 9902180165 | |
| Download: ML20203F510 (3) | |
Text
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February 12, 1999 Carl Terry, BWRVIP Chairman Niagara Mohawk Power Company Post Office Box 63-Lycoming, NY 13093 i
SUBJECT:
PROPRIETARY REQUEST FOR ADDITIONAL INFORMATION - REVIEW OF "BWR VESSEL AND INTERNALS PROJECT, JET PUMP ASSEMBLY INSPECTION AND FLAW EVALUATION GUIDELINES (BWRVIP-41)"
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Dear Mr. Terry:
By your application dated October 15,1997, you submitted for NRC staff review the Electric Power Research Institute (EPRI) proprietary report, "BWR Vessel and Internals Project, Jet Pump Assembly inspection and Flaw Evaluation Guidelines (BWRVIP-41)," EPRI Report TR-108728, October 1997. The BWRVIP-41 report was submitted as a means of exchanging information with the staff for the purpose of supporting generic regulatory efforts related to the inspection and flaw evaluation of the subject reactor components.
1 The NRC staff has completed its preliminary review of the BWRVIP-41 report. As indicated in the enclosed request for additional information (RAl), the NRC staff has determined that additional information is needed. Enclosure 1 does not contain the questions 12 through 15, found on Page 2 of Enclosure 2, which addresses specific, proprietary, aspects of your submittal. We request that BWRVIP respond to the RAI as soon as possible in order for the NRC staff to complete its review in a timely manner. Since the attached concerns a report that the NRC staff has found to be proprietary in nature, the requested information will also be considered proprietary, as appropriate.
If you have any questions, please contact me at (301) 415-2169.
j Sincerely,
/
C E. Carpenter, Jr., Lead Project Manager Materials and Chemical Engineering Branch p
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9902180165 990212 Division of Engineering
[DR TOPRP EXIE R Office of Nuclear Reactor Regulation p
Enclosure:
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Carl Terry, BWRVIP Chiirm n Niagara Mohawk Power Company Post Office t3ox 63 Lycoming, NY 13093
SUBJECT:
PROPRIETARY REQUEST FOR ADDITIONAL INFORMATION - REVIEW OF "BWR VESSEL AND INTERNALS PROJECT, JET PUMP ASSEMBLY INSPECTION AND FLAW EVALUATION GUIDELINES (BWRVIP-41)"
Dear Mr. Terry:
By your application dated October 15,1997, you submitted for NRC staff review the Electric Power Research Institute (EPRI) proprietary report, "BWR Vessel and Internals Project, Jet Pump Assembly inspection and Flaw Evaluation Guidelines (BWRVIP-41)," EPRI Report TR-108728, October 1997. The BWRVIP-41 report was submitted as a means of exchanging
)
information with the staff for the purpose of supporting generic regulatory efforts related to the inspection and flaw evaluation of the subject reactor components.
The NRC staff has completed its preliminary review of the BWRVIP-41 report. As indicated in the enclosed request for additionalinformation (RA!), the NRC staff has determined that additionalinformation is needed. We request that BWRVIP respond to the RAI as soon as possible in order for the NRC staff to complete its review in a timely manner. Since the attached concerns a report that the NRC staff has found to be proprietary in nature, the requested information will also be considered proprietary.
If you have any questions, please contact me at (301) 415-2169.
Sincerely, i
C. E. Carpenter, Jr., Lead Project Manager Materials and Chemical Engineering Branch Division of Engineering j
Office of Nuclear Reactor Regulation
Enclosure:
As stated cc:
See next page Distribution: File Center MEMayfield EMCB Reading g
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REQUEST FOR ADDITIONAL INFORMATION SAFETY EVALUATION RELATED TO BWRVIP 41 "BWR JET PUMP ASSEMBLY INSPECTION AND FLAW EVALUATION GUIDELINES" Have all the examination procedures and personnel that are used for jet pump components 1.
been qualified? If so, to what criteria? How are uncertainties related in the criteria /
analyses? Verify that cleaning is required for visual examinations.
2.
For initial inspections and re-inspections, are the proposed inspection frequencies based solely on system performance and risk implications? Have crack growth and component integrity calculations been relied on to develop the proposed inspection frequencies?
3.
Provide a discussion of the cmck growth methodology in sufficient detail that allows the time to failure to be estimated after the failure of a riser brace.
4.
Why is there no difference for the proposed inspection frequencies between "L" grade and standard grade 304 parts? Were there controls on carbon for the filler meta' used? On the heat input for component welding?
5.
What is the recommended inspection frequency for BWR-3 hold-down beams? When is the first inspection required? What heat treat condition was used for the hold-down beams in service in BWR 3's?
6.
If analysis cannot be provided to alleviate the weld inspections, what type of recommended inspections are being considered for the thermal sleeve welds? Will the inspections be performed over two inspection cycles with at least 50% of the inspections being performed '
in the first cycle?
7.
What were the delta ferrite requirements imposed by the procurement specifications for these safety related castings? What were the requirements for delta ferrite and carbon content for the weld filler material used to weld these components? Were inspections i
performed of the finished welds to verify delta ferrite either in the castings or the finished welds?
8.
The degradation of the jet pump assembly can affect its natural frequency. The changes i
in the natural frequency are dependent on the extent of cracking or structural degradation of the components such as the piping, riser brace or restraints. The design basis flow-induced vibration and seismic loads can be greatly increased as a result of jet pump degradation. Discuss how these increased loads would be accounted for in flaw evaluations.
9.
For plants with 2 braces, is the methodology different for estimating when a jet pump would fail? Discuss the implication in terms of time to failure for both braces failing and for one brace failing and the other being degraded (cracked).
- 10. Provide a summary of the discussed evaluation that was used to determine the time to crack initiation, as presented in Table 2.3.2-2.
- 11. For the locations where no inspection technique is available, i.e., the thermal sleeve welds and the adapter / lower ring welds for Fermi and LaSalle 1, has the BWRVIP considered recommending plant specific risk assessments instead of plant specific analysos?
NOTE: PAGE 2 IS PROPRIETARY AND IS NOT INCLUDED IN THIS ENCLOSURE ENCLOSURE 1
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