ML17326A261
| ML17326A261 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/24/1979 |
| From: | Dolan J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:00260, AEP:NRC:260, NUDOCS 7910010279 | |
| Download: ML17326A261 (14) | |
Text
REGULA!'UR INFORMATION DISTRIHU TIDE ST STEM (R IDS)
ACCESSION NOR:7910010279 VOC.DATE: 79/09/24 NOTARIZED:
NO FACIL:50-315 Donald C.
Cook Nuclear Power Planti Unit li Inaiana 50-316 Donald CD Cook Nuclear Power Planti Unit 2.i Inaiana 8,
AUTH ~ NAHE A0 TrlVR Al F ILI ATION COLA>!,J,E, Indiana K Nicniqan Electric Co ~
REC I P, NICHE RECIPIENT AF F ILI ATIUN DENTVNiHeRe Office of Nuclear Reactor Hegulat>on SvVJECT; Resoonas to NHC 7'IVUO 1 request. for addi info re r e c i r c u 1 a t i o n s ump. i'la d e 1 test t o be c orna 1 e t e a by N o v p 1 9 /9.
Sumo location arawings encl.
DOC~A.T
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05000315 05000316 DISTRI!!UTION CODE:
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TITLE: General Distrioution for Atter Issuance of Operating Lic CO!'IES LTTH ENCL COPIES LTTR ENCL 7
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RECIPIENT RECIPIENi IO CODE/NA;~E ID CDOE/NA~F ACTIO!i:
05 t3C Q R B +/
IN TERNAL e 12 15 1H 20 22 IKE CORE PERF SH REAC SFTY aA EE6
/PIN< jAN 1
1 2
2
'1 1
1 1
1 1
1 02 NRC PDR 1a TA/EOO 17 ENGR BR 19 Pl 4N'!
SYS UH 21 Ef LT TRT SYS GELD 1
1 1
1 1
1 1
1, 1
1 1
0 EXTEPNAL: 03 L~DR 23 ACHS 1lo 16 Oa NSIC 1
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INDIANA 5 MICHIGAN POWER COMPANY P ~ O. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 September 24, 1979 AEP:NRC:00260 Donald C.
Cook Nuclear Plant Uni'ts No.
1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 Request for Additional Information Regarding Recirculation Sump Mr. Harold R.
Denton Dffice of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington,D.C.
20555
Dear Mr. Denton:
This letter is in response to a Request for Additional Information en-closed in Mr. A. Schwencer's letter of August 1, 1979 concerning the per-formance of the D.C.Cook Plant recirculation sump under LOCA/jet impinge-ment conditions.
In response to Item 1 of the subject request, the following information is provided.
The original sump model testing program did not include pro-visions. for considering ice condenser drain flow or postulated pipe breaks.
The final report of the original study was submitted in our letter of December 20, 1978 (AEP:NRC:00112).
In our letter of December 29, 1978 (AEP:NRC:00110),
we stated that our testing program would be extended to in-clude jet impingement testing.
This model testing has been proceeding since February.
The current schedule calls for Alden Research Laboratory to com-plete model testing by November 1979.
Based on this schedule a final report would be submitted to the NRC no later than January 20, 1980.
Responses to the particular questions included in Item 1 will be provided at that time.
In response to Item 2 of the -subject request, Figures 1 and 2 of Attach-ment 1 are enclosed.
The figures are marked to indicate break locations being considered and containment water levels at various switchover points.
The piping segments shown in Figure 2 which is an enlargement of Section B-9 of FSAR Figure 5.2-5 represent the only high pressure piping in the vicinity of the recirculation sump.
JED:em Very truly yours, John E.
Dolan Vi,ce President qgzooxo ~7
Mr. Harold R. Denton, Di.rector
~2>
AEP:NRC:00260 cc; R, C, Callen G, Charnoff R.
M. Jurgensen R,
S.
Hunter D. V. Shaller-Bridgman
ATTACHMENT 1 TO AEP:NRC:00260
0 103o 27 IpfLFg MODEL
.BOUNDARY I
R.C.
PUMP NO. 2
//
c s ~icC l~~
~/
e+
STEAM GENERATOR r;O. 2 112o-4 MODEL BOUNDARY gO Q
cO
~Q.
gG 120 -44'
~
24 0
139 140 30' 23 151.04'23 0
21 1SOo 22 0
163 -27'-57" FIGURE 1
LOCATION OF SUMP WITHIN CONTAINMENT BUILDING
STEAN GENERATOR NO.
2
/
REACTOR COOLANT PUtlP NO. 2 I
HOT LEG CROSSOVER LEG ARROWS OESIGNATE AREAS CONSIDERED FOR POTENTIAL BREAK LOCATIONS
..I I
Evtttt a.aeltohover of ftrat I
RNR Train l
b.Switchover of second Rl!R Train c.Water level at time of second switchover con-sidering partial ice I
condenser melt-out LEVEL*
607a qae 610'."
612'"
a I
- MATER LEVFLS ARE BASED ON BREAK LOCATIONS SHOWN FIGURE 2
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
'P I fItBfR 1 8 1ST9 Docket Nos.
50-315 and 50-316 Mr. John Dolan, Vice President Indiana and Michigan Electric Company Indiana and Michigan Power Company Post Office Box 18 Bowling Green Station New York, New York 10004
Dear Mr. Dolan:
RE:
REACTOR CAVITY SEAL RING GENERIC ISSUE (PNIR)
He have completed our review of your response to our letter of February 2, 1978, in regard to the potential for the reactor cavity annulus seal ring to become a destructive missile in the event of a loss-of-coolant accident pipe break inside the reactor cavity.
Your response acceptably resolves this issue for Donald C.
Cook Nuclear Plant, Unit Nos.
1 and 2.
cc:
See next page Sincerely, pygmy/picc~
A. Schwencer, Chief Operating Reactors Branch gl Division of Operating Reactors
e
Hr. John Dolan Indiana and Michigan Electric Company Indiana and Michigan Power Company cc:
Mr. Robert W. Jurgensen Chief Nuclear Engineer American Electric Power Service Corporation 2 Broadway New York, New York 10004 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.
Washington, D.
C.
20036 Citizens for a Better Environment 59 East Van Buren Street Chicago, Illinois 60605 Maud'reston Palenske Memorial Library 500 Market Street St. Joseph, Michigan 49085 Hr'. D. Shaller, Plant Manager Donald C.
Cook Nuclear Plant.
P. 0.
Box 458 Bridgnan, Michigan 49106 Mr. Robert Masse Donald C.
Cook Nuclear Plant
, P. 0.
Box 458 Bridgman, Michigan 49106
,al
%P,.s 5 ms