ML13247A349: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 2: Line 2:
| number = ML13247A349
| number = ML13247A349
| issue date = 08/28/2013
| issue date = 08/28/2013
| title = Prairie Island - Revised ISFSI Bases, Includes Revised Record of Revision, Revised Current Page List, and Revision 9 to Page B 3.1.5-1
| title = Revised ISFSI Bases, Includes Revised Record of Revision, Revised Current Page List, and Revision 9 to Page B 3.1.5-1
| author name =  
| author name =  
| author affiliation = Nuclear Management Co, LLC
| author affiliation = Nuclear Management Co, LLC

Revision as of 02:56, 4 April 2019

Revised ISFSI Bases, Includes Revised Record of Revision, Revised Current Page List, and Revision 9 to Page B 3.1.5-1
ML13247A349
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 08/28/2013
From:
Nuclear Management Co
To:
Office of Nuclear Material Safety and Safeguards
References
000225895
Download: ML13247A349 (5)


Text

T-02 To Facility Address NRC DOC CONTROL DESK COPY #383 PI Department ONE WHITE FLINT NORTH 11555 ROCKVILLE PIKE ROCKVILLE, MD 20852-2738 PASSPORT DOCUMENT TRANSMITTAL Page: il~ Hg ~ I ~lnmiliI lll lll Nll l aill From C-DOC CNTRL-PI Attention:

Address : 1717 WAKONADE DR EAST City Country Email Contact Date/Time Trans No.Total Items: WELCH UNITED STATES 08/28/2013 0'000225895 00001 State: MN Postal Code: 55089 5:48 Transmittal Group Id: Title: 0000025413 Item Facility Type Sub Document Number Sheet Doc Status Revision Doc Date Copy # Media Cpys 0001 PI LIC BASE ISFSI BASES ISSUED 009 383 HC 01 If a document was not received or is no longer required check the response below and return to sender.Documents noted above not received (identify those not received).

I no longer require distribution of these documents (identify those no longer required).

Date: Signature:

ISFSI BASES UPDATING INSTRUCTIONS Revision 9 ISFSI BASES REMOVE Paqe Revision Document Type B RoR-1 12/10/12 Record of Revision A 12/10/12 Current Page List Page Revision Section/Chapter B 3.1.5-1 7 B 3.1_ _ _ _ I _ __ i __t *1-I +Prairie Island Units 1 and 2 ISFSI-B-1 8/27/13 PRAIRIE ISLAND NUCLEAR GENERATING PLANT INDEPENDENT SPENT FUEL STORAGE INSTALLATION RECORD OF REVISION BASES CHANGES AND LICENSE AMENDMENTS NSPM Date of License Revision Issue Amendment No. Remarks (REV) No.I thrnn h ý Or;o nnl Rt xunrp nrt nf AT hnoinl 5 7 8 9 8/20/2010 12/12/2012 7 Specifications Initial Issue of revised format and Inclusion of TN-40HT design.Clarify "helium environment" requirement in ISFSI SR 3.1.2.1.Revise B 3.1.5 paraphrase of regulatory requirements.

8/27/13 Prairie Island ISFSI B RoR- 8 8/27/13 BASES CURRENT PAGES PAGE DATE B RoR- 1 8/27/13 A 8/27/13 i 8/20/10 PAGE REVISION No.B 2.0-1 7 B 2.0-2 7 B 3.0-1 7 B 3.0-2 7 B 3.0-3 7 B 3.0-4 7 B 3.0-5 7 B 3.0-6 7 B 3.0-7 7 B 3.0-8 7 B 3.0-9 7 B 3.0-10 7 B 3.0-11 7 B 3.1.1-1 7 B 3.1.1-2 7 B 3.1.1-3 7 B 3.1.2-1 7 B 3.1.2-2 7 B 3.1.2-3 7 B 3.1.2-4 8 B 3.1.2-5 7 PAGE REVISION No.B 3.1.3-1 7 B 3.1.3-2 7 B 3.1.3-3 7 B 3.1.3-4 7 B 3.1.4-1 7 B 3.1.4-2 7 B 3.1.4-3 7 B 3.1.5-1 9 B 3.1.5-2 7 B 3.1.5-3 7 B 3.1.5-4 7 B 3.1.5-5 7 B 3.1.6-1 7 B 3.1.6-2 7 B 3.1.6-3 7 B 3.2.1-1 7 B 3.2.1-2 7 B 3.2.1-3 7 B 3.2.2-1 7 B 3.2.2-2 7 B 3.2.2-3 7 B 3.3.1-1 7 B 3.3.1-2 7 B 3.3.1-3 7 B 3.3.1-4 7 B 3.4.1-1 7 B 3.4.1-2 7 B 3.4.1-3 7 Prairie Island ISFSI A 8/27/13 Cask Interseal Pressure B 3.1.5 B 3.1 CASK INTEGRITY B 3.1.5 Cask Interseal Pressure BASES BACKGROUND A cask is loaded, dried, and sealed prior to being transported to the ISFSI and placed on a storage pad. The cask is designed with redundant seals to contain the radioactive material.

In addition, 10 CFR 72.122(h)(4) requires that confinement systems have the capability of being monitored.

The monitoring systems provide: a. the capability to monitor interseal pressure that will indicate if cask seal integrity is compromised; and b. local alarms to indicate that potential seal degradation has occurred.It is necessary to verify cask seal integrity at regular intervals to ensure the cask's interseal containment boundary is being maintained and to verify there is no seal leakage to the environment.

APPLICABLE SAFETY ANALYSIS The confinement of radioactive material during the storage of spent fuel in a cask is ensured by the use of multiple confinement barriers and systems. The barriers relied upon are the uranium dioxide fuel pellet matrix, the metallic fuel cladding tubes in which the fuel pellets are contained, and the cask in which the fuel assemblies are stored. Long-term integrity of the fuel cladding depends on storage in an inert atmosphere.

This is accomplished by removing water from the cask cavity and backfilling the cavity with an inert gas.The failure of storage cask confinement capability is considered in Prairie Island ISFSI B 3.1.5-1 Revision 9 1