LR-N14-0175, CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-9233

CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-9233

ML14223A479
Person / Time
Site:	Hope Creek, 07109233
Issue date:	08/11/2014
From:	Davison P Public Service Enterprise Group
To:	Document Control Desk, NRC/NMSS/SFST
References
LR-N14-0175
Download: ML14223A479 (5)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 011Sf:Ci Nu.clear LLC AUG 1 1 2014 LR-N14-0175 10 CFR 71.95 ATTN: Document Control Desk Director, Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 NRC Docket No. 50-354

SUBJECT:

10 CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-9233 In accordance with 10 CFR 71.95(a)(3).and (b), PSEG Nuclear LLC (PSEG) submits this report for six shipments where a condition in the Areva Model TN-RAM transportation package Certificate of Compliance was not met.

This letter contains no regulatory commitments.

Should you have any questions or comments regarding the submittal, please contact Ms. Tammy Morin, Hope Creek Regulatory Assurance, at 856-339-2299.

Sincerely, c-Paul J. Davison Site Vice President - Hope Creek

Attachment:

PSEG 10 CFR 71.95 Report (Areva Model TN-RAM Cask)

Document Control Desk Page 2 LR-N14-0175 cc: Mr. W. Dean, Administrator - Region 1, NRC Mr. J. Lamb, Licensing Project Manager - Salem and Hope Creek Mr. J. Hawkins, USNRC Senior Resident Inspector, Hope Creek Mr. P. Mulligan, Manager IV, NJBNE Mr. P. Duca, Hope Creek Commitment Tracking Coordinator Mr. L. Marabella, PSEG Corporate Commitment Tracking Coordinator Mr. D. Shaw, Director, Regulatory Affairs, Areva

LR-N14-0175 Attachment Page 1 of 3 PSEG 10 CFR 71.95 Report (Areva Model TN-RAM Cask)

1) Abstract This report provides the information required by 10 CFR 71.95(a)(3) for instances in which the as-built Areva Model TN-RAM cask, used for shipments from Hope Creek Generating Station (HCGS), did not meet the specifications in the Certificate of Compliance (CoC) 71-9233.

On June 18, 2014, Areva submitted a report to the NRC (Reference), pursuant to 10 CFR 71.95(a)(3) and (b), detailing discrepancies between their as-built Model TN-RAM cask and the approved licensing drawings in CoC 71-9233. Areva has manufactured one Model TN-RAM shipping cask. As stated in their report to the NRC, there were twelve non-safety significant discrepancies between the licensing drawings, as listed in CoC 71-9233 Section 5(a)(3), and the as-built cask.

Based on a review of shipping records, PSEG has determined there were six shipments made from HCGS with the Model TN-RAM cask. There were no safety consequences as a result of these shipments.

Areva has since submitted a revision to the CoC for the Model TN-RAM-cask (71-9233). The revision has been approved by the NRC, thereby eliminating the discrepancies for future shipments.

2) Narrative On June 29, 2014, PSEG received a letter from Areva, which alerted users of the Model TN-RAM cask of discrepancies between the as-built Model TN-RAM cask and the approved licensing drawings. This letter also provided a copy of the Areva 10 CFR 71.95 report on the Model TN-RAM cask.

The Areva 10 CFR 71.95 report identifies twelve non-safety related discrepancies between the as-built Model TN-RAM cask and the approved licensing drawings referenced in CoC 71-9233 Section 5(a)(3).

PSEG reviewed cask shipment records and determined that the TN-RAM cask was used for six shipments originating from HCGS. The HCGS shipments were made in 2001 and 2011 and are reportable under 10 CFR 71.95.

a) Status of Components All Model TN-RAM cask components operated normally for the six shipments.

LR-N14-0175 Attachment Page 2 of 3 PSEG 10 CFR 71.95 Report (Areva Model TN-RAM Cask) b) Date(s) of Occurrence February 15, 2001 March 13, 2001 March 28, 2001 September 22, 2011 October 10, 2011 December 8, 2011 c) Method of Discovery These events were discovered as part of the review of all PSEG shipments made with the Model TN-RAM cask as a result of the Areva 10 CFR 71.95 report.

d) Cause There were twelve non-safety significant discrepancies between the as-built Model TN-RAM cask and the approved licensing drawings referenced in CoC 71-9233 Section 5(a)(3). It appears AREVA did not recognize that modifications made during fabrication of the shipping cask were inconsistent with the licensing drawings listed and approved in the CoC.

e) Package Contents The package contents contained irradiated hardware with a total activity as follows:

Shipment Date Activity (Ci)

February 15, 2001 23,100 March 13, 2001 25,000 March 28, 2001 23,900 September 22, 2011 14,400 October 10, 2011 13,400 December 8, 2011 13,200 (3) Assessment of Safety Consequences Based on evaluation from Areva (Reference 1), there are no safety consequences associated with these shipments. Areva states in the 10 CFR 71.95 report that the, "evaluation of these discrepancies concluded that there were no safety significant issues and that there was no reduction in the effectiveness of the TN-RAM cask," and the "evaluation concludes that these as-built discrepancies do not represent a public health and safety issue."

LR-N14-0175 Attachment Page 3 of 3 PSEG 10 CFR 71.95 Report (Areva Model TN-RAM Cask)

The recipient of the shipments (Barnwell Operations) acknowledged the arrival of the shipments without incident. There was no additional exposure to radiation as a result of these shipments.

4) Corrective Actions The proposed revision to the CoC 71-9233, made by Areva, has been approved by the NRC. No further corrective actions are required by PSEG.

5) Contact for Additional Information Ms. Tammy S. Morin, Hope Creek Regulatory Assurance, (856) 339-2299

6) Extent of Exposure of Individuals to Radiation or Radioactive Materials None

Reference:

Areva letter, "Report Pursuant to 10 CFR 71.95 (a)(3) and (b) of As Built Discrepancies in the TN-RAM Packaging Relative to Certificate of Compliance No. 9233," dated June 18, 2014