ML17249A878
| ML17249A878 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/30/1980 |
| From: | White L ROCHESTER GAS & ELECTRIC CORP. |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| TASK-03-12, TASK-3-12, TASK-RR NUDOCS 8005060176 | |
| Download: ML17249A878 (7) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8005060176 DOC,DATE; 80/04/30 NOTARIZED:
NO DOCKET FACIL:50"244 Robert Emmet Ginna Nuclear PlantE Unit 1E Rochester G
05000244 AUTH,NAME AUTHOR AFFII.I ATION NHITEPLBDS Rochester Gas 8 Electric Corp<
REC IP, NAME RECIPIENT AFFILIATION
. ZIEMANNED,L~
Procedures 8, Test Review Branch
SUBJECT:
Forwards supplemental response to NRC 800328 request for info re environ qualification of electrical equipmentE including post accident containment heat removal sys.Graphic representations of injection 8 recirculation phases encl'ISTRIBUTION CODE:
AOOIS COPIES RECEIVED:LTR g ENCL 9 SIEE:
TITLE: General Distribution for after Issuance of Operating Lic RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL ACTION:
05 BC dg8 WW 7
7 INTERNAL:
REG FI 17 ENGR BR 19 PLANT SYS BR 21 EFLT TRT SYS OELD 1
1 2
2 1
1 1
1 1
0 V
02 NRC PDR 15 CORE PERF BR 18 REAC SFTY BR 20 EEB EPB<<DOR STS GROUP LEADR 1
1 1
1 1
1 1
1 1
1 1
EXTERNAL0 03 LPDR 23 ACRS 1
1 04 NSIC 16 1
1 SAy po TOTAL NUMBER OF COPIES REQUIRED:
LTTR ~
ENCL
4 jl
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>>>>>>i>>>>ii ROCHESTER GAS AND ELECTRIC CORPORATION o
89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON O. WHITE, JR.
VICE PRESIDENT TELEPHONE ARE* CODE 7ld 546-2700 April 30, 1980 Director of Nuclear Reactor Regulation Attention:
Mr. Dennis L. Ziemann, Chief Operating Reactors Branch No.
2 U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Environmental Qualification of Electrical Equipement.
R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Ziemann:
Your March 28, 1980 letter (received on April 7, 1980),
requested that we submit information concerning the Ginna post-accident containment heat removal systems.
We promptly responded by letter dated April 10, 1980, noting that the requested infor-mation was virtually identical to that requested through SEP Topics VI-2.D and VI-3, and submitted to the NRC staff on August 10, 1979.
We did note that, in the March 28, 1980 letter, some of the requested information was to be in graphical form.
Since this format difference was considered inconsequential, we decided, to save time, to merely resubmit the previous SEP submittal, where the requested information had been provided in tabular form.
We have since been informed by the NRC staff that this approach was unacceptable.
We have therefore included the graphical represen-tation of the desired information in the attached Figures 1 and 2.
Very truly yours, L. D. Whi
, Jr.
IDW:rb Attachment QOOi 5
/r
I 1
N g ~
Spray 1200*
Hi-Head RWST 600*
GPM Low Head to UPI ozz es 230,000 Ga110nS 1560*
GPM 60 rF Temp a
FIGURE 1 - INJECTION PHASE
- 900" ""
S p j11 QPN, Spa.ll 0
GP Note z.ngectxon flow is directly into vessel (upper plenum injection),
so no spill
- single failure assumed is one diesel generator+minimum ECCS is thus two hi head and one low head pump(s).
(Design flow shown). minimum heat removal is one CS pump
.(1200 GPM min. flow) and two fan coolers (design capacity
= 2x'14,000 BTU/sec.)
Containment Spray Flow G
Residual Spray Flow To Core 1560*
GPM 0
GPM Not needed.
Fan cooler capacity sufficient even assuming a single failure (of the diesel generators)
Co lin ater low Reactor To Spill GPM Coo'ling 2780*
Mater Flow GPM Total Recirc. Flow 1560*
GPM N/A xlO6
'F x10 100 4F Containment Spray HX UA Cooling Water Temp RHR {Shutdown)
- design flow assumes single failure of one-diesel generator.
Flow given,is design flow from one pump RECIRCULATION PHASE FIGURE 2 - RECIRCULATION PHASE
C
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