ML060730263
| ML060730263 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 03/13/2006 |
| From: | Harden P Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TAC MC8170 | |
| Download: ML060730263 (2) | |
Text
Palisades Nuclear Plant Committed to Nuclear E.u#lIence Operated by Nuclear Management Company, LLC March 13,2006 10 CFR 50.55a U. S. Nuclear Regulatory Commission AITN: Document Control Desk Washington, DC 20555 Palisades Nuclear Plant Docket 50-255 License No. DPR-20 Response to Request for Clarification on Request for Relief from ASME Section XI Code Requirements for Repair of Pressurizer Nozzle Penetrations flAC NO. MC8170)
By letter dated August 1 I, 2005, Nuclear Management Company, LLC (NMC) requested Nuclear Regulatory Commission (NRC) approval, pursuant to 10 CFR 50m55a(a)(3)(i),
for the use of an alternative to the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, related to the repair of pressurizer heater sleeve penetrations at the Palisades Nuclear Plant (PNP).
By letter dated December 28,2005, the NRC issued a request for additional information (RAI) on the subject relief request. NMC responded to the RAI by letter dated January 31,2006* By electronic mail, dated February 10,2006, the NRC sent a request for clarification of the RAI response. The clarification request was discussed in a teleconference between the NRC and NMC on February 15,2006. The NRC requested that NMC provide responses to questions 2b and 2c. On February 1 7,2008, NMC provided responses to questions 2b and 2c via electronic mail. On February 21, 2006, the NRC requested that the responses be docketed. Enclosure 1 provides the responses to questions 2b and 2c.
Summarv of Commitments commitments and no revisions to existing commitments.
Paul A. Harden Site Vice President, Palisades Nuclear Plant Nuclear Management Company, LLC Enctosure (I)
GC:
Administrator, Region Ill, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC 27780 Blue Star Memorial Highway Covert, Michigan 49043-9530 Telephone: 269.764.2000
ENCLOSURE I RESPONSE TO REQUEST FOR CLARIFICATION PALISADES NUCLEAR PLANT NRC Request Section 3.2.3 of the staffs safety evaluation indicates that the fatigue crack growth assessment for the Palisades' pressurirer heater sleeves is for 40 yeam ofplant operation. Atfachment 1 to the NMC's January 31, 2006, response does not indicate the time that the analysis is applicable. For what time is the fafjgue crack growth assessment applicable?
NMC Response The fatigue crack growth assessment is applicable for 40 years of plant operation.
NRC Request Tables 3 and 4 in Attachment 1 to NMC's January 3 1, 2006, letter identr'fies the allowable flaw size and the allowable stress intensifies at the final crack size.
The attachment does not describe the criteria used to establish the allowable flaw sire and the allowable stress intensities at the final crack size. What criteria was used to establish the allo wable flaw size and the allo wable stress intensities at the final crack size? Was this same cn'tefia used to establish the allowable
- a w size and the allowable stress intensities at the final crack size in the tables in sections 3.4 and 3.5 of WCAP-7 5973-P, Revision 7 ?
NMC Response The methodology and criteria from WCAP-15973-P, Revision 1 was used in the Palisades evaluation.
The criteria used to establish the allowable flaw size at the final crack size is based upon the Code criteria of paragraph IWB-3612 of Section XI of the ASME Code and the primary stress limits of NB-3000 of Section I11 of the ASME Code.
The criteria used to establish the allowable stress intensities at the final crack size in the tables in Sections 3.4 and 3.5 of WCAP-15973-P Revision I, is paragraph IWB-3612 of Section XI of the ASME Code.
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