ML20136G155
| ML20136G155 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 11/08/1985 |
| From: | Massin H COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 0870K, 870K, NUDOCS 8511220268 | |
| Download: ML20136G155 (2) | |
Text
,.z m
. qr s Commonwo-Ith Edison
) one First National Plaza, Chicago, Illmoss kC Address Reply to: Post Office Box 767 N
Chicago, Ilknois 60690 November 8, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
LaSalle County Station Unit 2 Facility Operating License NPF-18 Condition No. 4 of Attachment 2 Procedure Generation Package NRC Docket No. 50-374 References (a): License NPF-13, Attachment 2 Condition No. 4.
(b): June 28,1985 letter from H. L. Massin to H. R. Denton transmitting revised LGA Procedure Generation Package.
(c): August 20, 1985 letter from H. L. Massin to H. R. Denton.
(d): October 18, 1985 letter from W. Butler to D. L. Farrar transmitting SER.
Dear Mr. Denton:
As requeste'd in the Safety Evaluation Report (Reference (d)), the following is our schedule for responding to the open items. They are identified by the numbers used in the draft SER.
A.4.a Venting of the Drywell during operation under the guidelines of the Emergency Operations Procedures is conducted in accordance with LOA-VR-01, Primary Containment Pressure Reduction or LOA-VP-03, Emergency Primary Containment Pressure Relief. Both procedures use the same sequential pathways which take advantage of the Suppression Pool scrubbing action to minimize off-site releases. The present order is:
Suppression Pool Vent Outlet Bypass (2 1/2")
Drywell Vent Outlet Bypass (21/2")
Suppression Pool Vent (26")
Drywell Vent (26")
We consider this item closed.
1220268 851108
/
ADOCK 05000374 8 0 E
3.x
. November 8, 1985 H. R. Denton The question of the depressurization rate during venting to A.4.b.
limit flashing and hydrodynamic loads in the suppression pool will be evaluated after completion of a simple depressurization rate test to be conducted during the ILRT on Unit 1.
Results of this evaluation are targeted for July 1, 1986. In the interim, venting in non-emergency cases (Orywell Pressure Limit not reached) is only allowed when Drywell Temperature is less than
' 212of ~.
The purge valve operability limit basis is being pursued and is
~
A.4.c.
also expected by July 1, 1986.
A review of the effects of containment venting on duct work A.4.d.
failure, and the consequences of subjecting equipment near failed ducts to steam / radiation atmosphere, will be completed Y
by July 1, 1986.
The Detailed Control Room Design Review has been completed and A.6.
was provided to A. Bournia on October 30, 1985. The review used the EPG's to identify control room operator tasks and information and control needs. (The staff's review of that process will be described in its evaluation report of the DCRDR program plan.) We consider this item closed.
We will provide a response to the open items by August 1,1986.
Please direct any questions you may have concerning this matter to this office.
One signed original and fifteen copies of this letter are provided for your use.
Very truly yours, YW H. L. Massin Nuclear Licensing Administrator 1m cc: Region III Inspector - LSCS A. Bournia - NRR 0870K