ML19309F512
| ML19309F512 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/16/1980 |
| From: | Taylor J BABCOCK & WILCOX CO. |
| To: | Novak T Office of Nuclear Reactor Regulation |
| References | |
| 582-7108-T4.5, NUDOCS 8004290517 | |
| Download: ML19309F512 (2) | |
Text
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800429b b Babcock &Wilcox go.e,oene,aucno,oup P.O. Box 1260, Lynchburg. Va. 24505 Telephone: (804) 384-5111 File:
582-7108/T4.5
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Serial: ESC-104 April 16,1980 g
Mr. Tom Novak Assistant Director Operating Reactors Management Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.
10555
Dear Mr. Novak:
At the close of the B&W Owners' Group AT0G meeting with you and your staff on February 22, 1980, you requested that the Owners' Group begin providing specific AT0G program outputs for staff review.
In response to that request, B&W hereby submits the first of three elements of the program on behalf of the Owners' Group.
All items submitted are specific to Arkansas Power and Light AND-1 unit but are representative of the other owners' products. The submittal includes three (3) copies of each of the documents listed in Attachment 1.
This information is considered privilsged and it is hereby reauested that it not be subject to the Freedom of Information. Act in accordance with 10CFR50 Para-graph 2.790E.
A second submittal will be forwarded to you in early July and will include a copy of the draf t Guidelines (Parts I and II) for ANO-1.
If I can be of any further assistance, please advise.
Very truly yours, I
lA &
J. H. Taylor, Manager, Licensing D
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ATTACHMENT 1 1.
Arkansas Nuclea.'- One Unit i Safety Sequence Diagrams (SSD), Revision 0, for the following five initiating events considered in the ATOG Program:
EDS Drawing No.
a.
Loss of Feedwater EDS-0111-001-002 b.
Loss of Of fsite AC Power EDS-0111-011-003 c.
Steam Generator Tube Rupture EDS-0111-011-007 d.
Excessive Feedwater EDS-0111-011-011 e.
Small Steam Line Breaks EDS-0111-011-012 2.
Arkansas Nuclear One Unit 1 Event Trees developed from the SSD's:
B&W Drawing No.
a.
Loss of Offsite 1100949F, Rev. 1 b.
Excessive Feedwater 1100902J, Rev. I c.
Loss of Feedwater.
1100937F, Rev. 1 d.
Steam Generator Tube Rupture 1100960F, Rev. 1 e.
Small Steam Line Break 1100954F, Rev. 1 3.
Arkansas Nuclear One Unit 1 System Auxiliary Diagrams (SAD), Revision 0, for the following ten systems selected.
EDS Drawing No.
i s
a.
High Pressure Injection EDS-0111-011-103 b.
Containment Spray EDS-0111-011-104 c.
Auxiliary Feedwater EDS-0111-011-105 d.
Chemical Addition EDS-0111-011-106 e.
Low Pressure Injection EDS-0111-011-107 f.
Containment Coolers EDS-0111-011-111 g.
Containment Isolation EDS-0111-011-112 h.
Reactor Coolant Pressure Control (Pressurizer Heaters and Sprays)
EDS-0111-011-115 i.
Turbine Control EDS-0111-011-113 j.
Turbine Bypass and Atmospheric Dumps EDS-0111-011-114 4.
Safety Sequence Diagrams and System Auxiliary Diagrams Guideline, Revision 3, for Arkansas Nuclear One Unit 1, providing interpretation of content and direction for their intended use.
5.
Event Tree Guidelines including description, bounding assumptions, methodology, and application.
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