ML20209H805
| ML20209H805 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 07/14/1999 |
| From: | Schuelke D NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 72-0010-99-201, 72-10-99-201, NUDOCS 9907210072 | |
| Download: ML20209H805 (3) | |
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Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East Welch, Minnesota 55089 July 14,1999 10 CFR 72.48 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 I
PRAIRIE ISLAND INDEPENDENT SPENT FUEL STORAGE INSTALLATION Docket No. 72-10 Materials L.icense No. SNM-2506 Submittal of Safety Evaluation Summary and Commitment To Submit License Amendment Reauest Related to Storage of Fuel inserts During NRC Inspection 72-010/99-201, it was identified that Northern States Power had not submitted to the NRC a summary of the safety evaluation related to the storage of fuel assembly inserts (burnable poison rod assemblies and thimble plugs) in TN-40 casks at Prairie Island per the requirements of 10 CFR 72.48. Subsequent to that inspection, we reviewed for completeness all of the Annual Reports of Changes, Tests and Experiments submitted for the Prairie Island ISFSI since the issuance of the facilities license. That review identified one additional safety evaluation performed under 10 CFR 72.48 for which a summary was not provided. The safety evaluation (72-515, " Wire Penetrameter Use for TN-40 Fabrication) was identified in the cover letter of the October 19,1998 Annual Report of Changes, Tests and Experiments. However, as noted in that letter, the change evaluated by the safety evaluation did not result in any change to the ISFSI Safety Analysis Report (SAR), so it was mistakenly assumed that e the submittal of a summary was not required. A copy of the summary of that safety evaluation is attached to this letter.
In response to the failure to submit all of the required safety evaluation summaries as required by 10 CFR 72.48, the licensing group procedure related to the updating of the ISFSI (SAR) is being revised to clarify the need to submit all safety evaluation summaries whether the change resulted in a change to the ISFSI SAR or not.
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9907210072 990714 PDR ADOCK 05000282 0
USNRC NORTHERN STATES POWER COMPANY July 14,1999 Page 2 in another matter related to NRC Inspection 72-010/99-201, a License Amendment Request is under preparation which will request NRC approval for the storage of fuel assembly inserts already in place in TN-40 casks in the Prairie Island ISFSI. The 1.icense Amendment Request will also request storage of fuel assembly inserts in future casks. We expect to submit that License Amendment Request prior to September 1, 1999.
With this letter we have made the following NRC commitments:
- 1. Revise licensing group procedurc related to updating the ISFSI SAR to clarify the need to submit safety evaluation summaries whether they result in changes to the SAR or not.
- 2. Submit License Amendment Request requesting NRC approval for storage of fuelinserts in the TN-40 casks at Prairie Island by September 1,1999.
Please contact Gene Eckholt (612-388-1121) if you have any questions related to this letter or the safety evaluation summary.
sta Y AN Donald A. Schuelke Plant Manager Prairie Island Nuclear Generating Plant c: Director, Spent Fuel Project Office, NRC NMSS Project Manager, NRC v Regional Administrator - Region Ill, NRC /
Senior Resident inspector, NRC 7 NRR Project Manager, NRC /
J E Silberg Attachments:
Summary of Safety Evaluation 72-515, " Wire Penetrameter Use for TN-40 Fabrication l
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Summary of Non-Modification Safety Evaluation No. 515 Description of Chanae The containment boundary of the TN-40 casks used at the Prairie Island ISFSI are designed, fabricated, and inspected and tested, to the maximum practicable extent, in accordance with the ASME Boiler and Pressure Vessel Code, Section Ill, Subsection NB (Ref: ISFSI SAR 4.5). The version of the code referenced in the ISFSI SAR is the 1989 Edition, with no Addenda. As part of the construction of the TN-40 inner shell all confinement boundary welds must be radiographed per the requirements of Article NB-5000, Examination. General requirements are contained in NB-5111, which includes the fellowing statement regarding penetrameters, "...the penetrameters of Table NB-5111-1 shall be used in lieu of those shown in Table T-27 3." Table NB-5111-1 only gives information as to acceptable plaque penetrameters, while Table T-276 gives information regarding the use of plaque and wire penetrameters. In addition to referencing wire penetrameters, Table T-276 has different requirements (essential hole size) regarding the.se of plaque penetrameters.
Later versions of the Code have incorporated the use of wire penetrameters into Table NB-5111-1.
Summary of Safety Evaluation This safety evaluation justified use of wire penetrameters, in accordance with Table NB5111-1 of the ASME Code, for TN-40 fabrication. It was determined that their use created no unreviewed safety question, Tech Spec change, increase in occupational exposure, or increased environmental impact.
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