ML20039H203
| ML20039H203 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 12/20/1976 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201190715 | |
| Download: ML20039H203 (3) | |
Text
_ _ _ _ _ _ _ _ _ _
i O p are
/
f UNITED ETATES p-
~'g NUCL5AR REGULATORY COf.'. MISSION
- u g
WASHINGTON, D. C. 20555
- g e
gh, DEC 2 01976 4-i
.p 7
Docket No. STN 50-561 RANDUM FOR:
Domenic B. Vassallo, Assistant Director for Light Water Reactors, DPM 4
I l
FROM:
Robert L. Tedesco, Assistant Director for Plant
~
Systems, DSS
SUBJECT:
SAFETY EVALUATION REPORT j
t j
. Plant Name:
Babcock and Wilcox Standard Nuclear j
Steam System (B-SAR-205) PSAR Licensing Stage:
PDA Milestone Number:
24-02 Docket Number:
STN 50-561 Responsible Branch LWR 3 and Project Manager:
T. Cox Requested Completion Date:
December 6, 1976 The enclosed Safety Evaluation Repcrt covers areas of the Babcock and Wilcox Standard Nuclear Steam System (B-SAR-205) up to and including Amendment 6 for which the Auxiliary and Power Conversion Systems Branch has primary responsibility, i
This report covers the following systems within the B-SAR-205 scope of I
design:
i 1.
New and Spent Fuel Racks 2.
Fuel llandling System 3.
Chemical and Volume Control System This report also evaluates interface requirements for the following balance-of-plant scope of review:
1.
Water Level (Flood) Design 2.
Protection Against Internally Generated Missiles (Outside Containment)
Contact:
A. Ungaro Ext. 27763 t
I kjlg15810403 NADDEN80-515 PDR
\\
1 i
j l
l i
DEC 2 0 B76 l
i
. D. B. Vassallo 2
Lp -, i p
L 3.
Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment 4.
Pressurizer Relief Tank 5.
Spent Fuel.Paol Cooling and Cleanup System 6.
Service Water System and Ultimate Heat Sink 7.
Component Cooling Water System 8.
Demineralized Water System 9.
Compressed Air System 10.
Ventilation System 11.
Fire Protection System 12.
Steam and Power Conversion Systems 13.
Auxiliary Feedwater System The following areas have not been resolved:
1.
Section 9.1.1 and _9.1.2.
_New and Spent Fuel Storage Racks 4
i BGW has not provided all' the necessary interface information for the i
new and spent fuel storage racks, i.e., rack dry and loaded weight, and rack wall tie and foot interface information.
BGW has committed
{
to provide this information in a later amendment.
1 2.
Section 9.2.1 and 9.2.5 - Service Water System and Ultimate Heat Sink'
~
l BGW has not provided all the necessary NSSS heat loads to enable utility / applicants referencing B-SAR-205 to design an acceptable service water system and ultimate heat sink.
BGW has committed to provide the additional information in a later amendment.
3.
Section_9.5.1_- Fire Protection System BGW is being requested to re-evaluate the fire protection system interface requirements and criteria and to identify B-SAR-205 equip-ment containing combustible materials in conformance with Branch Technical Position APCSB 9.5-1, " Guidelines for Fire Protection for Nuclear Power Plants."
DEC 2 0 875 D. B. Vassallo 3
The above open items will be resolved in a supplement to this report.
We have also addressed in the SER those ACRS generic concerns applicable to B-SAR-205 as contained in ACRS letter to Chairman Rowden dated April 16,1976.
Group I (Resolved) Generic Concerns 1.
Fuel Pool Design Bases: Section 9.1.1 and 9.1.2 2.
Ultimate Heat Sink: Section 9.2.1 and 9.2.5 Group II-(Res_olution Pending) Generic _ Concerns 1.
Fire Protection System: Section 9.5.1
^
2.
Water Hammer: Section 10.4.1
(<3 Cf]-., ;, << a.
G &g._.
<v i
Robert L. Tedesco, Assistant Director for Plant Systems i
Division of Systems Safety t
Enclosure:
As stated e
t l
cc:
S. Hanauer R. Heineman R. Boyd W. Mcdonald O. Parr T. Cox V. Benaroya P. bbtthews D. Fischer J. Glynn A. Ungaro
. _ - _ - -