ML20151V024
| ML20151V024 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 08/12/1988 |
| From: | Allen C COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19297G777 | List: |
| References | |
| 5001K, NUDOCS 8808220053 | |
| Download: ML20151V024 (2) | |
Text
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N Commonwealth Edison f
'- ) One First NV.ional Plaza. Chicago, Wirns 7 Address Reply to. Post OKice Box 767
\\
w N.
/ Cnbago,IVinois 60690 0767 August 12, 1988 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Attn Document Control: Desk Washington, DC 20555
Subject:
LaSalle County Station Unit 2 Transmittal of Information Requested by US NRC NRC Docket No. 50-374 References (a):
Letter dated August 11, 1988 transmitting Information Requested by USNRC.
(b):
See Enclosure 1
Dear Sir:
At the request of the Nuclear Regulatory Commission, Commonwealth Edison Company (CECO) has been instructed to provide data to Brookhaven Natiopal Laboratory (BNL) to further analyze the March 9th event at LaSalle County Station. Nuclear Fuel Services Department of CECO is coordinating this data transmittal. A listing of the required data for the RAMONA-3B calculations is 11.ed in Attachment 1.
All non-proprietary data necessary to fulfill the Attaci_e.ent i roquirements is provided as Attachment 2.
All proprietary data (with GE's affidavits certifying the proprietary nature of the data) has been supplir' in Reference (a).
If you any questions regarding this rratter, please contact this office.
Ver truly yours, f
9808220053 880812 PDR ADOCK 05000374 PNU S
C. M. Allen Nuclear Licensing Administrator 1m Attachment C H ANGE LTA' BNcL 5001K j_ ppg
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.p; n-5 ATTACIMEtrL1 REQUIRED LASALLE UNIT 2 DATA FOR RAMONA-3B CALCULATIDES l
I.
Fuel Assembly Data A.
Geometry / Material Data - rod / cladding / bundle / control red dimensions, material compositions and enrichment by fuel rod.
B.
Burnable poison arrengement (radial / axial)', geometry and poison loading.
II.
Core Neutronic Data A.
Core radial / axial power diste*oution Core radial /exial exposure distribution Core radial / axial void-history distribution Core axial void distribution I
B.
Control rod pattern C.
Fuel' loading r.co D.
Vold, Doppler and moderator reactivity coefficients E.
3-D nodal exposure and void-history distributions III.
Thermal Hydraulic Data A.
Pl-3 thermal limits evaluation print-out D.
Fuel bundle-wise orificing/ flow distributlor V.
Bypass / core flow split D.
Downcomer liquid level E.
Feedwater flow and temperature F.
Carryunder fraction G.
Steam dorne pressure H.
Steam flow I.
Recirculation loop flow J.
Recirculation and jet pump characteristics K.
Vessel internals-riser / separator volumes, elevations, etc.
L.
Core pressure drop N.
Power / flow operating map IV.
Transient Data A.
Detailed sequence of e ;ents B.
Core flow and power vs. time C.
Fsadwater flow / temperature vs. time D.
Recirculation drive flow and pump speed vs. time i
E.
Steam dome pressure vs. time F.
Downcomer liquid level vs. time G.
LPRM locations and response vs. time i
500lK
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