ML11307A155

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Lr - FW: Sbk AMR-AMP RAI Trp 22 Closed Cycle Cooling Water Mintz Gavula - .Doc
ML11307A155
Person / Time
Site: Seabrook 
Issue date: 01/18/2011
From:
Office of Nuclear Reactor Regulation
To:
References
Download: ML11307A155 (3)


Text

1 SeabrookNPEm Resource From:

Plasse, Richard Sent:

Tuesday, January 18, 2011 3:36 PM To:

Cliche, Richard

Subject:

FW: SBK AMR-AMP RAI TRP 22 Closed Cycle Cooling Water Mintz Gavula -.doc Attachments:

SBK AMR-AMP RAI TRP 22 Closed Cycle Cooling Water Mintz Gavula -.doc Draft RAIs

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2242 Mail Envelope Properties (Richard.Plasse@nrc.gov20110118153600)

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FW: SBK AMR-AMP RAI TRP 22 Closed Cycle Cooling Water Mintz Gavula -

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1/18/2011 3:36:08 PM Received Date:

1/18/2011 3:36:00 PM From:

Plasse, Richard Created By:

Richard.Plasse@nrc.gov Recipients:

"Cliche, Richard" <Richard.Cliche@fpl.com>

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Files Size Date & Time MESSAGE 12 1/18/2011 3:36:00 PM SBK AMR-AMP RAI TRP 22 Closed Cycle Cooling Water Mintz Gavula -.doc 27762 Options Priority:

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DRAFT Seabrook Station Unit 1 - Technical Review Package 22: Closed Cycle Cooling Water RAI 3.3.1.46-1

Background

LRA Table 3.3.1, item 3.3.1-46 addresses stress corrosion cracking of stainless steel piping, piping components, piping elements, and heat exchangers exposed to closed-cycle cooling water at greater than 60 °C (140 °F). The LRA states that this line item is not used and LRA Table 3.3.2-29 does not show any other line item that addresses stress corrosion cracking for the stainless steel components in the primary component cooling water system. UFSAR Table 9.2-7 indicates that the stainless steel thermal barrier loop heat exchangers, which are included in the primary component cooling water system, have inlet temperatures of 80 °C (176.1 °F),

creating the potential for stress corrosion cracking.

Issue Current licensing basis information indicates that stainless steel components in the primary component cooling water system, specifically in the thermal barrier loop, may be subjected to closed cycle cooling water at temperatures greater than 60 °C (140 °F). However, the LRA neither addresses the potential for stress corrosion cracking of stainless steel components in the above system, nor provides sufficient information to justify the lack of potential.

Request Provide information to demonstrate that stainless steel components in the primary cooling water system, including the thermal barrier cooling water system, are not exposed to closed cycle cooling water greater than 60 °C (140 °F), or provide information to demonstrate that there is no need to manage stress corrosion cracking of these components.

RAI B.2.1.12-7

Background

The GALL AMP XI.M21 states that the Closed-Cycle Cooling Water System Program includes activities to minimize and monitor corrosion. In addition, SRP-LR item 3.3.1-49 addresses loss of material due to microbiologically influenced corrosion for stainless steel heat exchanger components exposed to closed cycle cooling water. LRA Section B.2.1.12 cites ERPI 1007820, which states, Microbiologically Influenced or Induced Corrosion is one of the main problems in closed cooling water systems. LRA Section B.2.1.12 also describes the Closed Cycle Cooling Water System Program as managing loss of material due to general, crevice, pitting and galvanic corrosion, but does not include microbiologically influenced corrosion.

Issue It was not clear if the Closed-Cycle Cooling Water System Program manages aging from microbiologically influenced corrosion.

Request Clarify whether the Closed-Cycle Cooling Water System Program manages microbiologically influenced corrosion in the closed cycle cooling water systems, and either provide the bases for not needing to include this or the technical background on the 1) preventive actions,

2) parameters monitored, and 3) inspection techniques being conducted.