ML20038A894
| ML20038A894 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/18/1981 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.44, TASK-TM NUDOCS 8111240403 | |
| Download: ML20038A894 (2) | |
Text
-
a 4
~ 3 in / q)
. h PHILADELPHIA ELECTRIC COMPANY s
2301 M ARKET STREET
[b P.O. BOX 8699 2
1881 -1981 PHILADELPHIA. PA.19101
.i
'$ lO8{h 6
SHIELDS L DALTROFF nactme mooucuo A
'lW *,.:
November 18, 1981 Re:
Docket Nos. 50-277 50-278 Mr. Darrell G.
Eisenhut, Director Division of Licensing U.S.
Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
Nureg 0737, Item II.K.3.44 -
Evaluation of Anticipated Transients Combined With Single Failure
Dear Mr. Eisenhut:
This letter responds to an NRC letter from D. G.
Eisenhut to All Licensees dated August 7, 1981 concerning a request for additional information on Nureg 0737, item II.K.3.44 for Peach Bottom Atomic Power Station, Units 2 and 3.
The letter requested a verification that the assumptions and initial conditions used in the BWR Owners' Group generic analysis for item II.K.3.44 are representative of Peach Bottom Atomic Power Station.
t The worst combination of a transient and single failure for the Peach Bottom Atomic Power Station as described in the BWR Owners' Group study (letter dated December 29, 1980, D.
B.
Waters, Chairman, BWR Owners' Group to D. G.
Eisenhut, NRC), is t
the loss of feedwater event plus a failure of the HPCI system.
For this event, the RCIC system will provide inventory makeup.
Analyses performed, as referenced in the Owners' Group study, show that the RCIC system will maintain the water level at least 6 ft. above the top of the active fuel.
8111240403 811118 d
PDR ADOCK 05000277 l
PDR 6I 0 P
i L
a O
Mr. Darrell G.
Eisenhut, Director Page 2 The analyses on which the Owners' Group's conclusions were based are presented in NEDO - 24708A, " Additional Information Required for NRC Staff Generic Report on Boiling Water Reactors", revision 1, December, 1980.
The initial conditions and assumptions of those analyses are summarized in Section 3.2.1.1.4 of that document.
We have reviewed the assumptions and initial conditions and concluded that they conservatively represent the Peach Bottom design.
Should you wish to discuss this item further or require additional information, please do not hesitate to contact us.
Very truly yours,
/
/
yt ;L AL, J