View source for 05000282/LER-1998-002, Forwards Proprietary Rept, Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at PINGP Unit 2, in Response to RAI Dtd 980218. Suppl Rept for LER 98-02 Will Also Be Delayed.Rept W

{{Adams
| number = ML20217Q600
| issue date = 04/06/1998
| title = Forwards Proprietary Rept, Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at PINGP Unit 2, in Response to RAI Dtd 980218. Suppl Rept for LER 98-02 Will Also Be Delayed.Rept Withheld
| author name = Sorensen J
| author affiliation = NORTHERN STATES POWER CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000282, 05000306
| license number = 
| contact person = 
| document report number = NUDOCS 9804130044
| package number = ML20036E313
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 2
}}
{{LER
| Title = Forwards Proprietary Rept, Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at PINGP Unit 2, in Response to RAI Dtd 980218. Suppl Rept for LER 98-02 Will Also Be Delayed.Rept Withheld
| Plant = 
| Reporting criterion = 
| Power level = 
| Mode = 
| Docket = 05000282
| LER year = 2098
| LER number = 2
| LER revision = 
| Event date = 
| Report date = 
| ENS = 
| abstract = 
}}

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* Northern States Power Company Prairie Island Nuclear Generating Plant
                                                                       ' 717 Wakonade Dr. East Welch, Minnesota 55089 April 6,1998                                                                                                 j l
U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos.50-282 License Nos. DPR-42 50-306                   DPR-60 Follow-Up to Response te Request for Additional Information Concerning PI Unit 2 CRDM Leak - Preliminary Summary Root Cause Analysis                                     j By letter dated February 18,1998, the NRC Staff requested additional information concerning the leak found on a Prairie Island Unit 2 part length control rod drive                           j mechanism (CRDM). The requested information was provided in response to that Request for Additional Information (RAI) by letter dated February 23,1998. In the February 23,1998 Response to Request for Additional Information, NSP committed that the formal root cause analysis report for the flaw in part length CRDM G-9 will be completed and submitted to the NRC by April 6,1998 (in a related submittal dated March 6,1998, NSP provided a CRDM housing design description and A-ferrite requirements for the weld and buttering metal used in fabrication.)
A preliminary summary root cause evaluation is provided as Attachment 1 of this letter.
However, the formal root cause has not been completed in accordance with the
,         schedule outlined in the February 23,1998, response to the RAl. The formal                                   :
Westirighouse WCAP has been delayed due to the volume of inquiries being directed at                         j the Wesdnghouse laboratory by parties outside of NSP. The formai root cause analysis                         !
will be provided upon its completion. The expected submittal date is currently May 15, 1998.
in addition, the related Unit 2 Licensee Event Report (LER) 98-02, submitted March 2, 1998, indicated that a supplemental report was expected to be issued April 13,1998. ,,
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USNRC                                             NORTHERN STATES POWER COMPANY April 6,1998 8
              ' Page 2 This expected issuance date was contingent on completion of the formal root cause analysis. Thus, the supplemental report for Unit 2 LER 98-02 will also be delayed. The supplemental report can be expected approximately one week after submittal of the formal root cause analysis.
In this letter we have made no new Nuclear Regulatory Commission commitments.
Please contact Richard Pearson (612-388-1121) if you have any questions related to this follow-up response.
Joel P Sorensen Plant Manager Prairie Island Nuclear Generating Plant c: Regional Administrator - Region lil, NRC Senior Resident inspector, NRC NRR Project Manager, NRC J E Silberg Attachments:
: 1. Westinghouse Report,"MetallurgicalInvestigation and Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at Prairie Island Nuclear Generating Plant Unit 2 - Preliminary Summary Report."
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      , Metallurgical Investigation and Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking      i at Prairie Island Nuclear Generating Plant Unit 2 Preliminary Summary Report 1
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