NSD-NRC-96-4805, Forwards Revised Background Info for AP600 Emergency Response Guidelines,Including Rev 1A to AE-1,Rev 1A to AES-1.1,Rev 1A to AES-1.2 & Rev 1A to AE-2: Difference between revisions

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Westinghouse                 Energy Systems                                   Box 355 Electric Corporation                                                         Pmsburgh Pennsylvania 15230-0355 NSD-NRC-96-4805 DCP/NRC0589 Docket No.: STN-52-003 August 30,1996 Document Control Desk U.S. Nuclear Regulatory Commission l     Washington, D.C. 20555 l     ATTENTION:               T.R. QUAY l
Westinghouse Energy Systems Box 355 Electric Corporation Pmsburgh Pennsylvania 15230-0355 NSD-NRC-96-4805 DCP/NRC0589 Docket No.: STN-52-003 August 30,1996 Document Control Desk U.S. Nuclear Regulatory Commission l
Washington, D.C. 20555 l
ATTENTION:
T.R. QUAY l


==SUBJECT:==
==SUBJECT:==
Line 25: Line 28:


==References:==
==References:==
: 1.     Letter DCP/NRC0376 from N. J. Liparulo to T. R. Quay, dated 8/9/95.
1.
l
Letter DCP/NRC0376 from N. J. Liparulo to T. R. Quay, dated 8/9/95.
: 2.       Letter DCP/NRC0574, from B. A. McIntyre To T. R. Quay, dated
l 2.
!                                      8/8/96.
Letter DCP/NRC0574, from B. A. McIntyre To T. R. Quay, dated 8/8/96.


==Dear Mr. Quay:==
==Dear Mr. Quay:==
 
Please find attached the following four " Background Information for AP600 Emergency Response Guidelines" documents, revised to include a Section 2.0
!    Please find attached the following four " Background Information for AP600 Emergency Response Guidelines" documents, revised to include a Section 2.0


== Description:==
== Description:==
 
AE-1, Rev. l A, 8/96 AP600 Loss of Reactor or Secondary Coolant AES-1.1, Rev. l A, 8/96 AP600 Passive Safety Systems Termination AES-1.2, Rev. l A, 8/96 AP600 Post LOCA Cooldown and Depressurization AE-2, Rev. l A, 8/96 AP600 Faulted Steam Generator Isolation To complete Westinghouse activities related to the AP600 ERGS and Background Documents, the at-power ERGS will be updated to reflect the AP600 as described in the SSAR, including design changes incorporated since issuance of Reference 1 as well as PRA insights. Upon completion of the at-power ERGS revision, the at-power ERGS and Background Information will be issued as Revision
AE-1, Rev. l A, 8/96             AP600 Loss of Reactor or Secondary Coolant AES-1.1, Rev. l A, 8/96           AP600 Passive Safety Systems Termination
,    AES-1.2, Rev. l A, 8/96           AP600 Post LOCA Cooldown and Depressurization                                     -
AE-2, Rev. l A, 8/96             AP600 Faulted Steam Generator Isolation To complete Westinghouse activities related to the AP600 ERGS and Background Documents, the at-power ERGS will be updated to reflect the AP600 as described in the SSAR, including design changes incorporated since issuance of Reference 1 as well as PRA insights. Upon completion of the at-power ERGS revision, the at-power ERGS and Background Information will be issued as Revision
: 2. You are requested to review the attached documents assuming minimal technical changes will result from revision of the at-power ERGS.
: 2. You are requested to review the attached documents assuming minimal technical changes will result from revision of the at-power ERGS.
                                                                                                                            \
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;-                  06005s                                                                             40W 9609100162 960830 PDR     ADOCK 05200003 l
06005s 40W 9609100162 960830 PDR ADOCK 05200003 l
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m NSD-NRC-96-4805                                                                                           l l_       DCP/NRC0589                                                             August 30,1996 While this submittal does not affect the status of any DSER/Open Item Tracking System open items, completion of the at-power ERGS revision will close the following DSER/OITS open items.                   i l
m NSD-NRC-96-4805 l_
l                DSER                   OITS l               13.3.5                 1222 18.9.3-3               1365 18.9.3-4               1366 18.9.3-6               1368 18.9.3-7               1369 18.9.3-8               1370 18.9.3-9               1371                                                                   ,
DCP/NRC0589 August 30,1996 While this submittal does not affect the status of any DSER/Open Item Tracking System open items, l
18,                   2043 13.5                 2304 l               13.5                   2305 l
completion of the at-power ERGS revision will close the following DSER/OITS open items.
Please contact Robin K. Nydes on (412) 374-4125 if you have any questions regarding this transmittal   ,
i l
or the AP600 Emergency Response Guidelines.
DSER OITS l
h .:v Brian A. McIntyre, Manager                                                                             L Advanced Plant Safety and Licensing
13.3.5 1222 18.9.3-3 1365 18.9.3-4 1366 18.9.3-6 1368 18.9.3-7 1369 18.9.3-8 1370 18.9.3-9 1371 18, 2043 13.5 2304 l
        /nja Enclosures l
13.5 2305 l
l cc:     D. Jackson, NRC (llE)
Please contact Robin K. Nydes on (412) 374-4125 if you have any questions regarding this transmittal or the AP600 Emergency Response Guidelines.
h.:v Brian A. McIntyre, Manager L
Advanced Plant Safety and Licensing
/nja Enclosures l
l cc:
D. Jackson, NRC (llE)
J. Bongarra, NRC (IE)
J. Bongarra, NRC (IE)
G. Galletti, NRC (IE)
G. Galletti, NRC (IE)
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W. Iluffman, NRC (IE)
W. Iluffman, NRC (IE)
: 11. Li, NRC (IE)
: 11. Li, NRC (IE)
N. Liparulo, Westinghouse (w/o Enclosures) i l       2WIA l                                                                                                                 I l
N. Liparulo, Westinghouse (w/o Enclosures) i l
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2WIA l
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Latest revision as of 21:42, 12 December 2024

Forwards Revised Background Info for AP600 Emergency Response Guidelines,Including Rev 1A to AE-1,Rev 1A to AES-1.1,Rev 1A to AES-1.2 & Rev 1A to AE-2
ML20117J098
Person / Time
Site: 05200003
Issue date: 08/30/1996
From: Mcintyre B
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To: Quay T
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20117J100 List:
References
NSD-NRC-96-4805, NUDOCS 9609100162
Download: ML20117J098 (2)


Text

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Westinghouse Energy Systems Box 355 Electric Corporation Pmsburgh Pennsylvania 15230-0355 NSD-NRC-96-4805 DCP/NRC0589 Docket No.: STN-52-003 August 30,1996 Document Control Desk U.S. Nuclear Regulatory Commission l

Washington, D.C. 20555 l

ATTENTION:

T.R. QUAY l

SUBJECT:

SUBMITTAL OF AP600 AT-POWER ERG BACKGROUND DOCUMENTS

References:

1.

Letter DCP/NRC0376 from N. J. Liparulo to T. R. Quay, dated 8/9/95.

l 2.

Letter DCP/NRC0574, from B. A. McIntyre To T. R. Quay, dated 8/8/96.

Dear Mr. Quay:

Please find attached the following four " Background Information for AP600 Emergency Response Guidelines" documents, revised to include a Section 2.0

Description:

AE-1, Rev. l A, 8/96 AP600 Loss of Reactor or Secondary Coolant AES-1.1, Rev. l A, 8/96 AP600 Passive Safety Systems Termination AES-1.2, Rev. l A, 8/96 AP600 Post LOCA Cooldown and Depressurization AE-2, Rev. l A, 8/96 AP600 Faulted Steam Generator Isolation To complete Westinghouse activities related to the AP600 ERGS and Background Documents, the at-power ERGS will be updated to reflect the AP600 as described in the SSAR, including design changes incorporated since issuance of Reference 1 as well as PRA insights. Upon completion of the at-power ERGS revision, the at-power ERGS and Background Information will be issued as Revision

2. You are requested to review the attached documents assuming minimal technical changes will result from revision of the at-power ERGS.

\\

l l

l t

06005s 40W 9609100162 960830 PDR ADOCK 05200003 l

F PDR l

l t

m NSD-NRC-96-4805 l_

DCP/NRC0589 August 30,1996 While this submittal does not affect the status of any DSER/Open Item Tracking System open items, l

completion of the at-power ERGS revision will close the following DSER/OITS open items.

i l

DSER OITS l

13.3.5 1222 18.9.3-3 1365 18.9.3-4 1366 18.9.3-6 1368 18.9.3-7 1369 18.9.3-8 1370 18.9.3-9 1371 18, 2043 13.5 2304 l

13.5 2305 l

Please contact Robin K. Nydes on (412) 374-4125 if you have any questions regarding this transmittal or the AP600 Emergency Response Guidelines.

h.:v Brian A. McIntyre, Manager L

Advanced Plant Safety and Licensing

/nja Enclosures l

l cc:

D. Jackson, NRC (llE)

J. Bongarra, NRC (IE)

G. Galletti, NRC (IE)

T. Collins, NRC (IE)

A. Levin, NRC (IE)

W. Iluffman, NRC (IE)

11. Li, NRC (IE)

N. Liparulo, Westinghouse (w/o Enclosures) i l

2WIA l

l l