ML20206N641

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Refers to Discussions with Licensee on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions
ML20206N641
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 05/13/1999
From: Alexion T
NRC (Affiliation Not Assigned)
To:
NRC
References
GL-96-06, GL-96-6, NUDOCS 9905180021
Download: ML20206N641 (8)


Text

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May 13, 1999 MEMORANDUM TO: File i

FROM:

Thomas W. Alexion, Project Manager, Section 1 ORIG. SIGNED BY 4

Project Directorate IV & Decommissioning Division of Licensing Project Management

SUBJECT:

DISCUSSIONS WITH LICENSEE ON ITS RESPONSE TO GENERIC LETTER (GL) 96-06, " ASSURANCE OF EQUIPMENT OPERABILITY-

)

AND CONTAINMENT INTEGRITY DURING DESIGN-BASIS ACCIDENT CONDITIONS" The U. S. Nuclear Regulatory Commission staff has had discussions with the licensee on its response to GL 96-06. - In one of the discussions, the staff had asked for clarification of the phrase regarding the " condensing heat transfer coefficient calculated in the LOCA analysis of record," on page 4 of 12 of Attachment 1 of the licensee's November 11,1997, response.

in order to facilitate future discussions between the licensee and the staff, the licensee provided the information in the attached e-mail (the staff did not request an e-mail). The licensee has 1

informed me that this information is preliminary and it plans to follow-up this e-mail with a formal i

submittal. The purpose of this memorandum is to place the attachment in the Public Document i

Room.

Docket Nos. 50-498

)

and 50-499

Attachment:

As stated

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May 13, 1999 MEMORANDUM T File b

FROM:

Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management

SUBJECT:

DISCUSSIONS WITH LICENSEE ON ITS RESPONSE TO GENERIC LETTER (GL) 96-05, " ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN BASIS ACCIDENT CONDITIONS" The U. S. Nuclear Regulatory Commission staff has had discussions with the licensee on its response to GL 96-06. In one of the discussions, the staff had asked for clarification of the phrase regarding the " condensing heat transfer coefficient calculated in the LOCA antaysis of record," on page 4 of 12 of Attachment 1 of the licensee's November 11,1997, respense.

in order to facilitate future discussions between the licensee and the staff, the li;;enseo provided the information in the attached e-mail (the staff did not request an e-mail). The licensee has informed me that this information is preliminary and it plans to follow-up this a mail with a formal submittal. The purpose of this mernorandum is to place the attachment in the Public Document Room.

Docket Nos. 50 498 and 50-499

Attachment:

As stated

kThomas, Alexion - Re[4]:

~

Generic Letter 96-06

_ Pqge 1 i

i Prom:

" Philip L Walker" <plwalkere stpegs.com>

. To:

OWFN_DO.owf4 po(TWA)

Date:.

Mon, Jan 25,1999 2:57 FM

Subject:

Re[4): Generic Letter 96-06 i

For your review:

Forward Header

Subject:

Re[4): Generic Letter 96-06 Author: James M Wigginton at FSS-1 STP-HLP Date: 1/25/991:32 PM i

5

Phil, The following is a description of the condensing heat transfer coefficient

{

- option that was employed in the COPPATTA LOCA-1 analysis. The 1997 pipe

. pressurization analysis used a heat transfer coefficient that was 4 times i

this heat transfer coefficient in accordance with guideance provided for safety related component thermal analysis in NUREG 0588 Rev.1 Mike i

Forward Header

Subject:

Re[4]: Generic Letter 96-06

' Author: Safdar Hafeez at FSS 1 STP-HLP Date: 1/21/99 ~7:06 AM The information is correct and appreable to Model E SG analysis only.

The heat transfer coefficients used are:

.1) modified Tagami during the blowdown period of LOCA,

2) an er.ponentially decreasing function between the end of blowdown and the long-term post-blowdown phase, and

'/.

. 3) Uchida during the post-blowdown period.

+-

The above heat transfer coefficients are discussed in BN-TOP 3 mentioned below.

. Reply Separator

Subject:

Re[3]: Generic Lotter 96-06 Author: James M Wiggirdon at FSS-1 STP-HLP Date: 1/20/99 5:22 PM Charlie,'

Here are the answers to the NRC questions.

Heat transfer Coefficient = Modified Tagami as defined in the Bechtel

..(

ATTA09EllT 4

. x...

2.

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TThomas Alexion _- Re[4]: Generic Letter 96-00 Prge_E Topical Report - BN-TOP-3, "Pedormance and Sizing of Dry pressure j

containments" Revision 4, March 1983.

The LOCA 1 Run la contained in Calculation NC-7032.

The LOCA 1' analysis was performed by Bechtel.

Safdaris this information correct?

Reply Separator

Subject:

Re[2]: Generic Letter 96-06 Author: Philip L Walker at FS2-1-STP-HLP Date: 1/20/99 4:28 PM Over the phone for now.

Reply Separator -

Subject:

Re: Generic Letter 96-06

^ Author: Charies R Albury at FSS 1 STP HLP Date: 1/20/99 4:16 PM Do they want this in writing or over the phone at this time?

Reply Separator

Subject:

Generic Letter 96-06 Author: Philip L Walker at FS21 STP HLP Date: 1/20/99 4:07 PM The NRC containment systems reviewer has followup questions to the one regarding the condensing heat transfer coefficient used in our submittal of 11/11/97 (page 4 of 12):

1)ldentify the coefficient; i.e., is it still Tagami or Uchida? If it is

~ something else, please provide a reference.

. 2)What is the origin of LOCA-17 Vendor, WOG, home-grown?

^:

,.. u -.

May 13, 1999 1

MEMORANDUM TO: File FROM:

Thomas W. Alexion, Project Manager, Section 1 ORIG. SIGNED BY Project Directorate IV & Decommissioning Division of Licensing Project Management

SUBJECT:

DISCUSSIONS WITH LICENSEE ON ITS RESPONSE TO GENERIC LETTER (GL) 96-06, " ASSURANCE OF EQUlPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN-BASIS ACCIDENT CONDITIONS" The U. S. Nuclear Regulatory Commission staff has had discussions with the licensee on its response to GL 96-06, in one of the discussions, the staff had asked for clarification of the phrase regarding the " condensing heat transfer coefficient calculated in the LOCA analysis of record," on page 4 of 12 of Attachment 1 of the licensee's November 11,1997, response.

In order to facilitate future discussions between the licensee and the staff, the licensee provided the information in the attached e-mail (the staff did not request an e-mail). The licensee has informed me that this information is preliminary and it plans to follow up this e-mail with a formal submittal. The purpose of this memorandum is to place the attachment in the Public Document

- Room.

Docket Nos. 50-498 and 50-499 Attachment As stated i

DISTRIBUTION:

Docket Files (50-498 and 50-499)

I PUBLIC DOCUMENT NAME: 1:\\SOTEXAS\\MEM96868.WPD

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CJamerson 0,b NAME Tale 8 /13 /99/f lDATE

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UNffED STATES g

NUCLEAR REU.ULATORY COMMISSION WASHINGTON, D.c. 3000M1001 May 13, 1999 MEMORANDUMT File h

Thomas W. Alexion, Project Manager, Section 1 FROM:.

Project Directorate IV & Decommissioning Division of Licensing Project Management -

SUBJECT:

DISCUSS!ONS WITH LICENSEE ON ITS RESPONSE TO GENERIC LETTER (GL) 96-06, " ASSURANCE OF EQUlF' MENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN-BASIS ACCIDENT CONDITIONS" The U. S. Nuclear Regu!atory Commission staff has had discussions with the licensee si its response to GL 96-06. In one of the discussions, the staff had asked for clarification of the phrase regarding the " condensing heat transfer coefficient calculated in the LOCA analysis of record," on page 4 of 12 of Attachment 1 of the licensee's November 11,1997, response.

In order to facilitate future discussions between the licensee and the staff, the licensee provided the information in the attacned e-mail (the staff did not request an e-mail). The licensee has informed me that this information is preliminary and it plans to follow-up tNs e mail with a formal submittal. The purpose of this memorandum is to place the attachment in the Public Document Room.

Docket Nos. 50-498 and 50-499

Attachment:

As stated f

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F TThom WanV{< W daBM EFM'7

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Pagei

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From:

" Philip L Walkef' <plwalkerO stpegs.com>

To:

OWFN_DO.owf4_po(TWA)

Date:

Mon, Jan 25,1999 2:57 PM

Subject:

Re[4): Generic Letter 96-06 i

. For your review:

1 l

l

Subject:

Re[4]: Generic Letter 96-06 Author: James M Wigginton at FSS-1 STP-HLP Date: 1/25/991:32 PM

Phil, The following is a description of the condensing heat transfer coefficient option that was employed in the COPPATTA LOCA 1 analysis. The 1997 pipe pressurization analysis used a heat transfer coefficient that was 4 times

~ his heat transfer coefficient in accordance with guideance provided for t

safety releted component thermal analysis in NUREG 0588 Rev.1

{

- Mike i

I Forward Header j

Subject:

Re[4]: Generic Letter 96-06 t

Author: Safdar Hafeez at FSS 1 STP-HLP l

Date: 1/21/99 7:06 AM '

The information is correct and applicable to Model E SG analysis only.

The heat transfer coefficierrts used are:

1) modified Tagami during the blowdown period of LOCA,
2) an exponentiah decreasing function between the end of blowdown and the long-term post-blowdown phase, and.
3) Uchida during the post-blowdown period.

The above heat transfer coefficients are discussed in BN-TOP 3 mentioned below.

Reply Separator __

Subject:

Re[3): Generic Letter 96-06 Author: James M Wigginton at FSS 1 STP-HLP Date: : 1/20/99 5:22 PM

Charlie, Here are the answers to the NRC questions.
Heat transfer Coefficient = Modified Tagami as defined in the Bechtel ATTA090DfT

.i.._..n:nnn Z:r~~~~ ZrCC_L_

~

. IThomas Alexion - Re[4): Generic Let[t96-06 Pagei a

,1 Topical Report - BN-TOP 3, " Performance and Sizing of Dry pressure containments' Revision 4, March 1983.

The LOCA 1 Run is contained in Calculation NC 7032.

' The LOCA 1 analysis was performed by Bechtel.

- Safdar is this information correct?

Reply Separator

Subject:

Re[2): Generic Letter 96-06 Author: Philip L Walker at FS2-1 STP.HLP Date: 1/20/99 4:28 PM Over the phone for now.

I 1

ReplySeparator i

Subject:

Re: Generic Lettar 96-06 l

Author. Charles R Albury at FSS 1 STP HLP Date: 1/20/99 4:16 PM Do they want this in writing or over the phone at this time?

Reply Separator

Subject:

Generic Letter 96-06 Author. Philip L Walker at FS2 ' STP-HLP.

Date: 1/20/99 4:07 PM The NRC containment systems reviewer has followup questions to the one l

regarding the condensing heat transfer coefficient used in our submittal of 11/11/97 (page 4 of 12):

1)ldentify the coefficient; i.e., is it still Tagami or Uchida? If it is something else, please provide a reference.

_2)What is the origin of LOCA-17 Vendor, WOG, home grown?

i l

~.

_ _