ML20217R156
| ML20217R156 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 08/28/1997 |
| From: | Polich T NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| GL-96-04, GL-96-4, TAC-M95935, TAC-M95936, NUDOCS 9709040277 | |
| Download: ML20217R156 (2) | |
Text
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o August 28, 1997 NOTE 10:
PD IV-1 file
SUBJECT:
GENERIC LETTER 96-04 BORAFLEX DEGRADATION IN SPENT FUEL POOL STORAGE RACKS (TACS NOS. M95935 AND M95936)
Generic letter (GL) 96-04 did not require a response for licensee's that did not have "Boraflex in their spent fuel storage racks.
Texas Utilities Electric (TVE) curent as-built configuration for Spent Fuel Pool No. 1 (SFP1) is twenty racks that have no restrictions on the placement of spent fuel assemblies, do not contain Boraflex, and are thus referred to as " low density" racks.
I There were no racks initially installed in Spent fuel Pool No. 2 (SFP2).
The licensee originally purchased nine "high density" racks that included a i
i neutron absorber in the form of Boraflex, to be installed in SFP2, Because of industry experience with Boraflex, TUE elected to modify these racks to remove the Boraflex material prior to their installation in SFP2.
Licensee amendment numbers 46 and 32 were granted to TUE for Comanche Peak-Steam Electric Station (CPSES), Units 1 and 2 on February 9, 1996.
The amendment required the use of the "high density" racks in a 2 out of 4 (referred to as "high density (2/4)")
storage pattern as a limiting configuration.
Depending on plant specific needs (e.'g. refueling outages) some of the high density racks may also be used in a more conservative 1 out of 4 (referred to as "high density (1/4)")
storage pattern.
.Thus with no "Boraflex in the " low density" SFP1 racks originally and having been removed the "Boraflex" from the "high density" racks bofore installation into SFP2 CPSES does not need to respond to GL 96-04 and thus TAC Nos. M95935 and M95936 are considered closed.
ORIGINAL SIGNED BY:
Timothy J. Polich, Project Manager Project Directorate IV-1 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446 DISTRIBUTION:
Docket File PUBLIC (PDR)
JClifford TPolich Document Name: CPGL9604.N0T OFC PH/PD4-1 NAME-TPolich/vw DATE V/>t/97 Y COPY YES/NO OfflCIAL RECORD COPY ll 11,Il,11,lll ll! I.I
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August 28, 1997 NOTE 10:
PD IV-1 File
SUBJECT:
GENERIC LETTER 96-04 BORAFLEX DEGRADATION IN SPENT FUEL POOL STORAGE RACKS (TACSN05.M95935ANDM95936)
Generic Letter (GLg 96-04 did not require a response for licensee's that did not have "Boraflex in their spent fuel storage racks. Texas Utilities Electric (TUE) curent as-built configuration for Spent Fuel Pool No.1 (SFP1) is twenty racks that have no restrictions on the placement of spent fuel assemblies, do not contain Boraflex, and are thus referred to as " low density" racks.
There were no racks initially installed in Spent fuel Pool No. 2 (SFP2). The licensee originally purchasod nine "high density" racks that included a neutron absorber in the form of Boraflex to be installed in SFP2.
Because of industry experience with Boraflex, TUE elected to modify these racks to remove the Boraflex material prior to their installation in SFP2.
Licensee amendment numbers 46 and 32 were granted to TUE for Comanche Peak Steam Electric Station (CPSESD, Units 1 and 2 on February 9, 1996.
The amendment required the use of the "high density" racks in a 2 out of 4 (referred to as "high density (2/4)")
storage pattern as a limiting configuration. Depending on plant specifte needs (e.'g. refueling outages) some of the high density racks may also be used in a more consorvative 1 out of 4 (referred to as "high density (1/4)")
storage pattern.
Thus with no "Boraflex in the " low density" SFPI racks originally and having been removed the "Boraflex" from the "high density" racks before installation into SFP2 CPSES does not need to respond to GL 96-04 and thus TAC Nos. M95935 and M95936 are considered closed, t,.k Timothy J. Polich, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
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