ML18275A296

NRR E-mail Capture - (External_Sender) Brunswick Flooding MSA Review

ML18275A296
Person / Time
Site:	Brunswick
Issue date:	09/26/2018
From:	Guill P Duke Energy Carolinas
To:	Frankie Vega Division of Licensing Projects
References
Download: ML18275A296 (4)

Text

1 NRR-DMPSPEm Resource From:

Guill, Paul F <Paul.Guill@duke-energy.com>

Sent:

Wednesday, September 26, 2018 1:13 PM To:

Vega, Frankie

Subject:

[External_Sender] RE: Brunswick Flooding MSA review Frankie; The clarification information requested is provided below in red. Let me know if need any additional information to support your review. Again, thanks for your patience From: Vega, Frankie [1]

Sent: Monday, September 24, 2018 1:04 PM To: Guill, Paul F <Paul.Guill@duke-energy.com>

Subject:

RE: Brunswick Flooding MSA review

• • • Exercise caution. This is an EXTERNAL email. DO NOT open attachments or click links from unknown senders or unexpected email. ***

Hello Mr. Guill; Just a quick follow-up with my request below. I know that you guys are still dealing with the aftermath of the hurricane so I understand if the responses are not yet ready.

Thanks Frankie From: Vega, Frankie Sent: Wednesday, August 15, 2018 2:25 PM To: 'Guill, Paul F' <Paul.Guill@duke-energy.com>

Subject:

RE: Brunswick Flooding MSA review Hello Mr. Guill; In addition to the documents already provided I would need the following clarification information in order to complete my review:

Flooding MSA Section 3.5.1 states the following:

While most safety-related structures have finished floor elevations above 22 feet NGVD29, the Reactor Building has two access openings at 20 feet NGVD29: the equipment access airlock (i.e., railroad airlock) and the personnel airlock.

Leakage past these doors is intercepted by floor drains and routed to sump areas on the -17 feet level of the Reactor Building. The minimal water intrusion spread over the large area of the Reactor Building would not challenge any plant equipment relied upon for the FLEX strategy. In order to confirm that no key FLEX equipment is impacted by the LIP, can you please provide additional information regarding in-leakage water quantities and expected flood water depths at the -17 feet level.

2 DUKE RESPONSE:

In-leakage is conservatively determined to be 30 gpm for 6.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> from Reactor Building Doors D-2 and D-3 (closed). This leakage would migrate to the -17 ft elevation and be distributed over an area of about 140 ft by 40 ft and would result in approximately 3.25 in. (0.3 ft) of water on the -17 ft elevation floor.

The RCIC pump, located in the S. RHR Room, is relied upon for the FLEX strategy and is located on raised pedestal 2 ft-8 in above the floor. Instruments on the bottom row of instrument racks are located at least 12.9 in above the floor resulting an APM of 0.8 ft.

Also, water levels are expected to reach 26 feet NGVD29 or above at the reactor building due to the combined effects storm surge. These levels are well above the access openings for the reactor building airlock doors referenced above. It appears that the MSA doesnt address the potential water leakage through these doors due to storm surge water levels.

In order to confirm that no key FLEX equipment is impacted by the storm surge, please provide additional information regarding expected in-leakage water quantities and expected flood water depths at the -17 feet level.

DUKE RESPONSE:

In the Combined Effects Storm Surge event, temporary passive barriers are to be installed interior to the reactor airlock doors D-2 and D-3 with triggers for actions as per BSEP Administrative Instruction 0AI-68.

There is no in-leakage past these barriers and therefore in-leakage calculations are not performed for these locations. Modifications to these barriers are required to raise the top elevation from 26 ft to 27.5 ft NGVD29, which presents a minimum of 0.8 ft of margin at these barriers.

No formal responses are needed at this moment so replying to this email or placing the information in the electronic reading room (ERR) would work for me. If you have questions or need clarification on the questions above, please let me know.

I will be out of the office starting tomorrow until August 28 so no rush on this response. My replacement during my time-off would be Joe Sebrosky (Joseph.Sebrosky@nrc.gov). Joe is not familiar with Brunswicks flooding MSA so no need to forward him the response to the questions.

Thanks Frankie From: Vega, Frankie Sent: Wednesday, August 08, 2018 3:44 PM To: Guill, Paul F <Paul.Guill@duke-energy.com>

Subject:

Brunswick Flooding MSA review Mr. Guill; Hope youre doing well. Im currently reviewing the Brunswick MSA submittal and in order to complete the review I would need to have the following references from the MSA submittal available in the electronic reading room (ERR):

11. BSEP Procedure, Abnormal Operating Procedure 0AOP-13.0, Operation during Hurricane, Flood Conditions, Tornado, or Earthquake, Revision 67.

14. BSEP Calculation BNP-14-009, Combined Effects Flood Evaluation, Revision 1.

22. BSEP Engineering Change, EC 287907, Fukushima 2.3 Flooding Inspection Documentation - BNP, Attachment Z01, Flood Protection Walkdown Final Report for BNP Nuclear Plant Site, Revision 3.

30. BSEP Drawing F-02277, Diesel Generator Building Floor & Wall Sleeves, Revision 32.

3

33. BSEP Calculation BNP-17-001, Evaluation of Brunswick Plant Local Intense Precipitation along FLEX Deployment Path, Revision 0.

34. BSEP Drawing F-11018, Reactor Building - Unit 1 Equipment Foundations at El. (-)17-4, Revision 3.

35. BSEP Drawing F-01118, Reactor Building - Unit 2 Equipment Foundations at El. (-)17-4, Revision 5.

I have access to the CERTREC IMS ERR so if you are using that ERR we should be good. At this moment Im the only NRC staff member that needs access to the documents referenced above.

Thanks Frankie G. Vega, P.E.

Project Manager NRR/DLP/PBMB 301-415-1617 Location: O-12F02

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[External_Sender] RE: Brunswick Flooding MSA review Sent Date:

9/26/2018 1:12:45 PM Received Date:

9/26/2018 1:13:03 PM From:

Guill, Paul F Created By:

Paul.Guill@duke-energy.com Recipients:

"Vega, Frankie" <Frankie.Vega@nrc.gov>

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