IR 05000445/2012009

IR 05000445-12-009, 05000446-12-009, & 072-00074-12-002, on 6/4-7/2012, Comanche Peak Nuclear Power Plant, Units 1 and 2, NRC Reactive Inspection of Dry Cask Storage Activities

ML12172A311
Person / Time
Site:	Comanche Peak
Issue date:	06/20/2012
From:	Spitzberg D NRC/RGN-IV/DNMS/RSFSB
To:	Flores R Luminant Generation Co
References
IR-12-002, IR-12-009
Download: ML12172A311 (18)

Text

June 20, 2012

SUBJECT:

COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2

- NRC REACTIVE INSPECTION OF DRY CASK STORAGE ACTIVITIES

- INSPECTION REPORT 05000445/

2012009, 050 00446/2012009, AND 07200074/2012 002

Dear Mr. Flores

A reactive inspection was conducted of your dry cask storage activities associated with your Independent Spent Fuel Storage Installation (ISFSI)

on June 4 and June 7, 2012

. A telephonic exit was conducted with your staff to discuss the findings of the inspection on June 20, 2012 , after successfully completing the placement of Cask #9 on the ISFSI pad on June 19, 201 The purpose of the inspection was to review your corrective action s related to a stuck port cap on Cask #9 and to observe the final helium backfill operations to verify your corrective actions were effective in maintaining a seal on the loaded caniste In addition, information was collected related to the contamination of the annulus area of the transfer cask, recent evidence that neutron activation of the low profile transporter had occurred, and information related to the recent notification by Holtec, Int. that the pins used with your lift yoke were undergoing additional analysi The NRC has concluded that the actions taken to remove and replace the stuck port cap were successful and that the replacement port cap provided a seal that was adequate to maintain the pressure in the canister until the port cap cover plate was welded in place, providing the permanent seal over the damaged por The contamination of the annulus area was resolved by continuing to flush demineralized water through the annulus to remove the contaminatio Neutron activation of the low profile transporter was minor, but noteworthy in that you were the first to report this to the other Holtec cask users and the NR The re-analysis of the pins used in the lift yoke confirmed that the pins were adequately sized for the lifts that have occurred at Comanche Pea In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response if you choose to provide one, will be made available electronically for public inspection in the NRC Public Document Room or from the NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.htm To the extent possible, your response should not include any personal

, privacy or proprietary information so that it can be made available to the public without redactio U N I T E D S T A T E S N U C L E A R R E G U L A T O R Y C O M M I S S I O N R E G I O N I V 6 12 EAST LAMAR BLVD

, S U I T E 4 0 0 A R L I N G T O N , T E X A S 7 6 0 1 1-4125 Luminant Generation Company LLC

- 2 - Should you have any questions concerning this inspection, please contact the undersigned at (817) 20 0-1191 or Mr. Vincent Everett at (817) 20 0-1 19

Sincerely,

/RA/ D. Blair Spitzberg, Ph.D., Chief Repository & Spent Fuel Safety Branch

Docket s: 50-445, 50-446, 72-74 License s: NPF-87, NPF-89 Enclosure:

Inspection Report No s.: 05000445/2012 009 , 05000446/2012 009 07200074/2012002 Attachment: